Uranium chloride extraction of transuranium elements from LWR fuel

International Nuclear Information System (INIS)

Miller, W.E.; Ackerman, J.P.; Battles, J.E.; Johnson, T.R.; Pierce, R.D.

1992-01-01

A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800 C to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein. The U-Fe alloy having dissolved therein reduced metals from the spent nuclear fuel is contacted with a mixture of one or more alkali metal or alkaline earth metal halides selected from the class consisting of alkali metal or alkaline earth metal and Fe or U halide or a combination thereof to transfer transuranium actinide metals and rare earth metals to the halide salt leaving the uranium and some noble metal fission products in the U-Fe alloy and thereafter separating the halide salt and the transuranium metals dissolved therein from the U-Fe alloy and the metals dissolved therein. 1 figure

The Transuranium Elements - Present Status: Nobel Lecture

Science.gov (United States)

Seaborg, G. T.

1951-12-12

The discovery of the transuranium elements and the work done on them up to the present time are reviewed. The properties of these elements, their relationship to other elements, their place in the periodic table, and the possibility of production and identification of other transuranium elements are discussed briefly.

Experimental evaluation of admission and disposition of artificial radionuclides including transuranium elements in agricultural plants

Energy Technology Data Exchange (ETDEWEB)

Kozhakhanov, T.; Lukashenko, S. [Institute of radiation safety and ecology (Kazakhstan)

2014-07-01

Processes of radionuclides migration and transfer to agricultural plants are quite well developed worldwide, but the information on character of accumulation of {sup 241}Am and {sup 239+240}Pu transuranium radionuclides in agricultural plants is still fragmentary. Even in generalized materials of worldwide studies, IAEA guide, accumulation coefficient (AC) can have wide range of values (5-6 orders), no data exists on radionuclides' distribution in different organs of plants and they are given for joined groups of plants and types of soils. That is why the main aim of this work was to obtain basic quantitative parameters of radionuclides' migration in 'soil-plant' system, and firs of all- for transuranium elements.. In 2010 a series of experiments with agricultural plants was started at the territory of the former Semipalatinsk Test Site aimed to investigate entry of artificial radionuclides by crop products in natural climatic conditions. To conduct the experiment for study of coefficient of radionuclides' accumulation by agricultural corps, there was chosen a land spot at the STS territory, characterized by high concentration of radionuclides: {sup 241}Am - n*10{sup 4} Bq/kg, {sup 137}Cs - n*10{sup 3} Bq/kg, {sup 90}Sr - n*10{sup 3} Bq/kg and {sup 239+240}Pu- n*10{sup 5} Bq/kg. As objects of investigation, cultures, cultivated in Kazakhstan have been selected: wheat (Triticum vulgare), barley (Hordeum vulgare), oat (Avena sativa L.), water melon (Citrullus vulgaris), melon (Cucumis melo), potato (Solanum tuberosum), eggplant (Solanum melongena), pepper (Capsicum annuum), tomato (Solanum lycopersicum), sunflower (Helianthus cultus), onion (Allium cepa), carrot (Daucus carota), parsley(Petroselinum vulgare)and cabbage (Brassica oleracea). Investigated plants have been planted within the time limits, recommended for selected types of agricultural plants. Cropping system included simple agronomic and amelioration measures. Fertilizers were not

Magnesium transport extraction of transuranium elements from LWR fuel

International Nuclear Information System (INIS)

Ackerman, J.P.; Battles, J.E.; Johnson, T.R.; Miller, W.E.; Pierce, R.D.

1992-01-01

This patent describes a process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuel containing rare earth and noble metal fission products as well as fission products of alkali metals, alkaline earth metals and iodine. It comprises reducing the oxide fuel with Ca metal in the presence of Ca halide; separating the Ca halide with the CaO and the fission products contained therein from the U-Fe alloy and the metal values dissolved therein and electrolytically contacting the calcium salts with a carbon electrode; contacting the liquid U-Fe alloy having dissolved therein reduced metals from the spent nuclear fuel with liquid Mg metal, thereafter separating the liquid Mg and the metals dissolved therein from the U-Fe alloy and the metal dissolved therein, distilling the Mg from the transuranium actinide and rare earth metals, recontacting the U-Fe alloy with liquid Mg metal a sufficient number of times until not less than about 99% by weight of the transuranium actinide values have been removed from the U-Fe alloy

Transuranium Processing Plant semiannual report of production, status, and plans for period ending December 31, 1975

International Nuclear Information System (INIS)

King, L.J.; Bigelow, J.E.; Collins, E.D.

1976-10-01

Between July 1, 1975, and December 31, 1975, maintenance was conducted at TRU for a period of three months, 295 g of curium oxide (enough for approximately 26 HFIR targets) were prepared, 100 mg of high-purity 248 Cm, were separated from 252 Cf that had been purified during earlier periods, 11 HFIR targets were fabricated, and 28 product shipments were made. No changes were made in the chemical processing flowsheets normally used at TRU during this report period. However, three equipment racks were replaced (with two new racks) during this time. In Cubicle 6, the equipment replaced was that used to decontaminate the transplutonium elements from rare earth fission products and to separate curium from the heavier elements by means of the LiCl-based anion-exchange process. In Cubicle 5, the equipment used to separate the transcurium elements by high-pressure ion exchange and to purify berkelium by batch solvent extraction was replaced. Two neutron sources were fabricated, bringing the total fabricated to 79. One source that had been used in a completed project was returned to the TRU inventory and is available for reissue. Three sources, for which no further use was foreseen, were processed to isolate and recover the ingrown 248 Cm and the residual 252 Cf. Eight pellets, each containing 100 μg of high-purity 248 Cm were prepared for irradiation in HFIR to study the production of 250 Cm. The values currently being used for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated

Transuranium contamination in BWRs after fuel accidents and its impact on decommissioning exposures and costs

Energy Technology Data Exchange (ETDEWEB)

Lundgren, K.

1996-12-01

The theme of the present study is to quantify the amount of transuranium activity in different parts of the plant after various fuel accidents, and which impact such contamination has on radiation exposure and costs for decommissioning the plant. The consequences of four different accident degrees have been treated: Common fuel failures, e.g. in line with recent experiences from Swedish BWRs; Fuel channel obstruction resulting in partial melting of one fuel assembly; Total loss of electric power resulting in partial meltdown of the core, but with primary circuit intact preventing a massive contamination of the containment; A LOCA followed by a core meltdown and melting and penetration of the reactor pressure vessel. The amount of transuranium activity distributed, the form of this activity and the plant contamination are evaluated for these accidents. The costs and exposures have been split up on cleanup activities after the accident and decommissioning. 75 refs.

Transuranium contamination in BWRs after fuel accidents and its impact on decommissioning exposures and costs

International Nuclear Information System (INIS)

Lundgren, K.

1996-12-01

The theme of the present study is to quantify the amount of transuranium activity in different parts of the plant after various fuel accidents, and which impact such contamination has on radiation exposure and costs for decommissioning the plant. The consequences of four different accident degrees have been treated: Common fuel failures, e.g. in line with recent experiences from Swedish BWRs; Fuel channel obstruction resulting in partial melting of one fuel assembly; Total loss of electric power resulting in partial meltdown of the core, but with primary circuit intact preventing a massive contamination of the containment; A LOCA followed by a core meltdown and melting and penetration of the reactor pressure vessel. The amount of transuranium activity distributed, the form of this activity and the plant contamination are evaluated for these accidents. The costs and exposures have been split up on cleanup activities after the accident and decommissioning. 75 refs

Transuranium processing plant semiannual report of production, status, and plans for period ending June 30, 1976

Energy Technology Data Exchange (ETDEWEB)

King, L.J.; Bigelow, J.E.; Collins, E.D.

1977-02-01

During the period January 1, 1976, through June 30, 1976, the following amounts of transuranium elements were recovered from ten irradiated HFIR targets: 2 g /sup 243/Am, 50 g /sup 244/Cm, 29 mg /sup 249/Bk, 277 mg /sup 252/Cf, 1.7 mg /sup 253/Es, and 0.5 pg /sup 257/Fm. About 50 mg of high-purity /sup 248/Cm was purified chemically for shipment, and another 75 mg of /sup 248/Cm was separated from /sup 252/Cf. Nineteen HFIR targets, each containing approximately 9 g of curium, were fabricated. There have been no changes during this report period in the chemical processing flowsheets normally used at TRU. Five neutron sources were fabricated, bringing the total fabricated to 84. Six sources that were used previously in various projects have been returned to TRU and are available for reassignment. Special projects included (1) the continued study of /sup 250/Cm production by irradiation of /sup 248/Cm; (2) the production of 0.54 mg of /sup 250/Cf by irradiation of /sup 249/Bk; (3) the separation of approximately 200 pg of /sup 254/Cf from 39-hr /sup 254m/Es that was produced by irradiation of 5 ..mu..g of /sup 253/Es; and (4) the determination of process steps needed to obtain rare-earth fission products in an oxide form from LiCl-based anion exchange raffinate solution.

Transuranium element transport in agricultural systems (soil to food chain transfer of nuclear fuel cycle radionuclides). Annual progress report

International Nuclear Information System (INIS)

Wallace, A.

1977-10-01

Progress is reported on the following research projects: preparation of bibliography covering literature on plant uptake of transuranium elements; development of techniques for growth of agricultural crops in large containers that simulate field conditions; equipment for counting of alpha-emitting transuranium elements; studies on variability in concentration ratio of 241 Am under different environmental conditions; alpha radiation burn in bush beans exposed to 241 Am in solution; constancy of concentration ratio as a measure of plant uptake of 241 Am; growth of radishes in soil with and without DTPA, and radish peel as source of radionuclides; effects of varying levels of DTPA in loam soil on concentration ratio values; and a plant species (Atriplex hymenelytra--desert holly) with high C.R. values and search for other plants with high C.R. values

Transuranium elements in organic chemical forms

International Nuclear Information System (INIS)

Sakanoue, Masanobu; Yamamoto, Masayoshi

1987-01-01

It is very important to achive an understanding what role organic matter plays in the behavior of transuranium elements in the environment. This paper reports the studies on characteristics of fallout Pu and Am in soil closely related to soil organic matter, and interaction of humic acid and Am (III) in aqueous solution. From the results obtained, it was suggested that the humic acids had strong interaction with transuranium elements, but such soluble complexes were removed soon from the solution by coagulation and sorption on soil. (author)

The TRUEX [TRansUranium EXtraction] process and the management of liquid TRU [transuranic] waste

International Nuclear Information System (INIS)

Schulz, W.W.; Horwitz, E.P.

1987-01-01

The TRUEX process is a new generic liquid-liquid extraction process for removal of all actinides from acidic nitrate or chloride nuclear waste solutions. Because of its high efficiency and great flexibility, the TRUEX process appears destined to be widely used in the US and possibly in other countries for cost-effective management and disposal of transuranic (TRU) wastes. In the US, TRU wastes are those that contain ≥3.7 x 10 6 Bq/kg) of TRU elements with half-lives greater than 20 y. This paper gives a brief review of the relevant chemistry and summarizes the current status of development and deployment of the TRUEX (TRansUranium EXtraction) process flowsheets to treat specific acidic waste solutions at several US Department of Energy sites. 19 refs., 4 figs., 4 tabs

Preparation Technology and Study of Properties of New Detectors for Transuranium Elements

International Nuclear Information System (INIS)

Andrushchenko, G.Yu.; Blank, A.B.; Budakovsky, S.V.; Zelenska, O.V.; Shevtsov, M.I.

2006-01-01

A porous composite materials is described for determination of radionuclides in aquatic objects of the environment. Possibilities have been studied for the use of this material in monitoring of α-nuclides content in natural waters. The composite is a scintillator with through pores, the surface of which is impregnated by a sorbent that is selective with respect to transuranium elements. The structure of the material allows combination of two processes - concentrating the radionuclide and measuring its activity. as selective sorbent to transuranium elements an anion-exchange resin VP-1Ap was used. Studies of material functionality were carried out using the model systems based on reference radioactive solutions 239 Pu

Management of commercial high-level and transuranium-contaminated radioactive wastes. Environmental statement

International Nuclear Information System (INIS)

1974-09-01

This Draft Environmental Statement is issued to assess the environmental impact of the AEC's program to manage commercial high-level and transuranium-contaminated radioactive wastes. These are the types of commercial radioactive wastes for which AEC custody is required by present or anticipated regulations. The program consists of three basic parts: development of a Retrievable Surface Storage Facility (RSSF) for commercial high-level waste, using existing technology; evaluating geological formations and sites for the development of a Geological Disposal Pilot Plant (GDPP) which would lead to permanent disposal; and providing retrievable storage for the transuranium-contaminated waste pending availability of permanent disposal. Consideration has been given to all environmental aspects of the program, using waste generation projections through the year 2000. Radiological and other impacts of implementing the program are expected to be minimal, but will be discussed in further environmental statements which will support budget actions for specific repositories. The alternatives discussed in this Draft Environmental Statement are presented. (U.S.)

Ecological effects from transuranium elements in terrestrial environment

International Nuclear Information System (INIS)

Uiker, F.U.

1985-01-01

To understand ecological effects from transuranium elements in environment it is necessary to know how their chemical, physical and biological behaviour depends on duration of their being in natural environment. It is necesary to take into account that behaviour of transuranium elements in environment depends on physical and chemical forms of a nuclide as well as on characteristics of ecosystem. Radiation dose of certain tissues plays an essential role here but dose distribution is especially complicated for relatively non-soluble α-irradiators

Nuclear reactions and synthesis of new transuranium species

International Nuclear Information System (INIS)

Seaborg, G.T.

1983-01-01

In this short review, I shall describe the special aspects of heavy ion nuclear reaction mechanisms operative in the transuranium region, the role of new techniques, possible nuclear reactions for the production of additional transuranium elements and nuclear species and the importance of work in this region for the development of nuclear models and theoretical concepts. This discussion should make it clear that a continuing supply of leements and isotopes, some fo them relatively short-lived, produced by the HFIR-TRU facilities, will be a requirement for future synthesis of new elements and isotopes

Transuranium element behavior in the environment: What speciation studies can tell us

International Nuclear Information System (INIS)

Cleveland, J.M.

1989-01-01

Some of the transuranium elements - especially plutonium - can exist in the environment in several different oxidation states which differ chemically from one another as much as if they were different elements. Hence an understanding of the environmental chemistry of these elements requires knowledge of their oxidation-state distribution, or speciation, under a variety of realistic conditions. Such studies are in their infancy, but already several chemical speciation methods have yielded results indicating the uniqueness of transuranic environment chemistry; for example, dioxoplutonium(V), which is unstable in the acid solutions employed in laboratory and processing plant, is often the most prevalent plutonium oxidation state in natural waters. More sensitive and less invasive physical speciation methods under development will hopefully permit the extension of these studies to a wider variety of environmental conditions and to determinations of sorbed species necessary for an understanding of sorption processes

Transuranium nuclides in the environment

International Nuclear Information System (INIS)

Sakanoue, Masanobu

1987-01-01

Many countries are presently concerned with problems relating to the safe disposal of nuclear waste containing various levels of transuranium nuclides. In this context, a review on the distribution and behaviour of transuranium elements in the environment studied at Kanazawa University in Japan is presented. About 17 years ago, a high degree of accumulation of 239 Pu in the surface soil of Nagasaki was found in the Nishiyama area, where 'black rain' occured just after the nuclear bomb explosion. The introduction of newly developed radiochemical methods and instrumentation has enabled studies to be carried out on environmental plutonium isotopes, americium-241 and more recently neptunium-237 with respect to distribution depth profile, variation with time and relationship with organic materials. Valuable information has been obtained on the basis of samples collected from various locations in Japan, including surface soil, sea and lake sediments, atmospheric aerosol, water from the Japan Sea and the Pacific Ocean, and from material related with the 'Bikini Event' of 1954. (orig.)

Ion-ion interaction and energy transfer of 4+ transuranium ions in cerium tetrafluoride

International Nuclear Information System (INIS)

Liu, G.K.; Beitz, J.V.

1990-01-01

Dynamics of excited 5f electron states of the transuranium ions Cm 4+ and Bk 4+ in CeF 4 are compared. Based on time- and wavelength-resolved laser-induced fluorescence, excitation energy transfer processes have been probed. Depending on concentration and electronic energy level structure of the studied 4+ transuranium ion, the dominant energy transfer mechanisms were identified as cross relaxation, exciton-exciton annihilation, and trapping. Energy transfer rates derived from the fitting of the observed fluorescence decays to theoretical models, based on electric multipolar ion-ion interactions, are contrasted with prior studies of 4f states of 3+ lanthanide and 3d states of transition metal ions. 16 refs., 1 tab

Nuclear power: Health implications of transuranium elements

International Nuclear Information System (INIS)

1982-01-01

This report provides general guidelines for national public health and environmental authorities. It does not provide detailed technical data, but instead broadly surveys the whole field, indicating the present position as assessed by members of the Working Group. The Working Group considered three major facets: physiological, toxicological and dosimetric aspects of the transuranium elements; the application of occupational health control, including health physics; and environmental behaviour together with public health implications associated with the transuranium elements. The intention was to cover all aspects relevant to health, with respect both to those who are occupationally engaged in work with such elements and to the general public who might be affected as the result of such operations. Consideration was also given to routine and emergency situations

Treatment of incorporated transuranium elements

International Nuclear Information System (INIS)

Volf, V.

1978-01-01

The text of this report and its tables and figures provide basic information on the decorporation of transuranium elements as well as an insight into the more general principles, trends and interactions. The detailed tables and the exhaustive list of important references should enable the reader to make his own conclusions in a minimum of time

Transuranium element purification by liquid-liquid extraction

International Nuclear Information System (INIS)

Madic, C.; Koehly, G.

1976-01-01

In the transuranium element production, the liquid-liquid extraction purification is presented. The affinity of TBP and trilaurylammonium nitrate for these elements is given. Exemples of NP/Pu, Pu/Np, U/Pu, Am/Cm, Am and Cm/Ln separation are presented [fr

The transuranium elements: From neptunium and plutonium to element 112

International Nuclear Information System (INIS)

Hoffman, D.C.

1996-01-01

Beginning in the 1930's, both chemists and physicists became interested in synthesizing new artificial elements. The first transuranium element, Np, was synthesized in 1940. Over the past six decades, 20 transuranium elements have been produced. A review of the synthesis is given. The procedure of naming the heavy elements is also discussed. It appears feasible to produce elements 113 and 114. With the Berkeley Gas-filled Separator, it should be possible to reach the superheavy elements in the region of the spherical Z=114 shell, but with fewer neutrons than the N=184 spherical shell. 57 refs, 6 figs

Proceedings of transuranium elements

International Nuclear Information System (INIS)

Anon.

1992-01-01

The identification of the first synthetic elements was established by chemical evidence. Conclusive proof of the synthesis of the first artificial element, technetium, was published in 1937 by Perrier and Segre. An essential aspect of their achievement was the prediction of the chemical properties of element 43, which had been missing from the periodic table and which was expected to have properties similar to those of manganese and rhenium. The discovery of other artificial elements, astatine and francium, was facilitated in 1939-1940 by the prediction of their chemical properties. A little more than 50 years ago, in the spring of 1940, Edwin McMillan and Philip Abelson synthesized element 93, neptunium, and confirmed its uniqueness by chemical means. On August 30, 1940, Glenn Seaborg, Arthur Wahl, and the late Joseph Kennedy began their neutron irradiations of uranium nitrate hexahydrate. A few months later they synthesized element 94, later named plutonium, by observing the alpha particles emitted from uranium oxide targets that had been bombarded with deuterons. Shortly thereafter they proved that is was the second transuranium element by establishing its unique oxidation-reduction behavior. The symposium honored the scientists and engineers whose vision and dedication led to the discovery of the transuranium elements and to the understanding of the influence of 5f electrons on their electronic structure and bonding. This volume represents a record of papers presented at the symposium

Cleanex process: a versatile solvent extraction process for recovery and purification of lanthanides, americium, and curium

International Nuclear Information System (INIS)

Bigelow, J.E.; Collins, E.D.; King, L.J.

1979-01-01

At a concentration of 1 M in straight-chain hydrocarbon diluent, HDEHP will extract americium, curium, and other trivalent actinide and lanthanide elements from dilute acid or salt solutions. The solute is back-extracted with more concentrated acid, either nitric or hydrochloric. The process has been used in the continuous, countercurrent mode, but its greatest advantage arises in batch extractions where the excess acid can be titrated with NaOH to produce a final acidity of about 0.03 M. Under these conditions, 99% recovery can be achieved, usually in one stage. Cleanex was used on the 50-liter scale at the Transuranium Processing Plant at Oak Ridge for 12 years to provide a broad spectrum cleanup to transuranium elements before applying more sophisticated techniques for separating individual products. The process is also used routinely to recover excessive losses of curium and/or californium from plant waste streams. The solvent system is relatively resistant to radiation damage, being usable up to 200 W-h/liter

The TRansUranium EXtraction (TRUEX) process: A vital tool for disposal of US defense nuclear waste

International Nuclear Information System (INIS)

Horwitz, E.P.; Schulz, W.W.

1990-01-01

The TRUEX (TRansUranium EXtraction) process is a generic actinide extraction/recovery process for the removal of all actinides from acidic nitrate and chloride nuclear waste solutions. Because of its high efficiency and flexibility and its compatibility with existing process facilities, TRUEX has now become a vital tool for the disposal of certain US defense nuclear waste. The development of TRUEX is closely coupled to the development of bifunctional extractants belonging to the carbamoylphosphoryl class and CMPO in particular. A brief review of the development of CMPO and its relationship to other bifunctional and monofunctional extractants is presented. The effect of TBP on CMPO, the selectivity of CMPO for actinides extracted from acidic nitrate media, the influence of diluents on CMPO behavior and 3rd phase formation, and the radiolysis/hydrolysis of CMPO and subsequent solvent cleanup will be highlighted. Application of TRUEX in the chemical pretreatment of specific nuclear waste streams and a summary of the current status of development and deployment of TRUEX is presented. 15 refs., 10 figs., 3 tabs

Materials evaluation for a transuranic processing facility

International Nuclear Information System (INIS)

Barker, S.A.; Schwenk, E.B.; Divine, J.R.

1990-11-01

The Westinghouse Hanford Company, with the assistance of the Pacific Northwest Laboratory, is developing a transuranium extraction process for preheating double-shell tank wastes at the Hanford Site to reduce the volume of transuranic waste being sent to a repository. The bench- scale transuranium extraction process development is reaching a stage where a pilot plant design has begun for the construction of a facility in the existing B Plant. Because of the potential corrosivity of neutralized cladding removal waste process streams, existing embedded piping alloys in B Plant are being evaluated and ''new'' alloys are being selected for the full-scale plant screening corrosion tests. Once the waste is acidified with HNO 3 , some of the process streams that are high in F - and low in Al and zr can produce corrosion rates exceeding 30,000 mil/yr in austenitic alloys. Initial results results are reported concerning the applicability of existing plant materials to withstand expected process solutions and conditions to help determine the feasibility of locating the plant at the selected facility. In addition, process changes are presented that should make the process solutions less corrosive to the existing materials. Experimental work confirms that Hastelloy B is unsatisfactory for the expected process solutions; type 304L, 347 and 309S stainless steels are satisfactory for service at room temperature and 60 degrees C, if process stream complexing is performed. Inconel 625 was satisfactory for all solutions. 17 refs., 5 figs., 8 tabs

Radiological safety considerations in the design and operation of the ORNL Transuranium Research Laboratory (TRL)

International Nuclear Information System (INIS)

Haynes, C.E.

1976-01-01

The Transuranium Research Laboratory (TRL) is the central facility at Oak Ridge National Laboratory (ORNL) for chemical and physical research involving transuranium elements. Transuranium Research Laboratory investigations are about equally divided between studies of inorganic and structural chemistry of the heavy elements and nuclear structure and properties of their isotopes. Elements studied include neptunium, plutonium, americium, curium, berkelium, californium, and einsteinium, each in microgram-to-gram quantities depending upon availability and experimental requirements. This paper describes an eight-step safety procedure followed in planning and approving individual research projects. This procedure should provide an optimum margin of safety and should permit the accomplishment of successful research

Fundamental study on the extraction of transuranium elements from high-level liquid waste

International Nuclear Information System (INIS)

Kubota, Masumitsu; Morita, Yasuji; Tochiyama, Osamu; Inoue, Yasushi.

1988-01-01

A great many extractants have been studied for the separation of transuranium elements. The present study deals with the survey and classification of the extractants appearing in literature, bearing in mind the relationship between the molecular structure of extractants and their extractability for the transuranium elements from the standpoint of their selective separation from high-level liquid waste (HLW) generated from fuel reprocessing. The extractants surveyed were classified into six groups; unidentate neutral organophosphorus compounds, bidentate neutral organophosphorus compounds, acidic organophosphorus compounds, amines and ammonium salts, N,N-disubstituted amides and the other compounds. These extractants are not always applicable to the separation of transuranium elements from HLW because of their limitations in extractability and radiation durability. Only a limited number of extractants belonging to the bidentate neutral organophosphorus compounds and the acidic organophosphorus compounds are considered to be suitable for the present purpose. (author)

First-principles calculations of the thermodynamic properties of transuranium elements in a molten salt medium

International Nuclear Information System (INIS)

Noh, Seunghyo; Kwak, Dohyun; Lee, Juseung; Kang, Joonhee; Han, Byungchan

2014-01-01

We utilized first-principles density-functional-theory (DFT) calculations to evaluate the thermodynamic feasibility of a pyroprocessing methodology for reducing the volume of high-level radioactive materials and recycling spent nuclear fuels. The thermodynamic properties of transuranium elements (Pu, Np and Cm) were obtained in electrochemical equilibrium with a LiCl-KCl molten salt as ionic phases and as adsorbates on a W(110) surface. To accomplish the goal, we rigorously calculated the double layer interface structures on an atomic resolution, on the thermodynamically most stable configurations on W(110) surfaces and the chemical activities of the transuranium elements for various coverages of those elements. Our results indicated that the electrodeposition process was very sensitive to the atomic level structures of Cl ions at the double-layer interface. Our studies are easily expandable to general electrochemical applications involving strong redox reactions of transition metals in non-aqueous solutions.

Resuspension of the transuranium elements - a review of existing data

International Nuclear Information System (INIS)

Linsley, G.S.

1978-08-01

Resuspension is an important mechanism in the transfer to man of transuranium elements deposited on surfaces in the environment. In this report the data on resuspension are reviewed, including the limited number of relevant measurements which have been made in the United Kingdom. The various models developed to represent the resuspension process are reviewed and the most appropriate, when site specific data are absent, for application in UK conditions are identified. Recommendations are made on the main areas where further environmental studies are required to enable more reliable predictive models to be developed for application in these conditions. (author)

Recent progress of the United States transuranium and uranium registries

International Nuclear Information System (INIS)

Kathren, R.L.

1986-01-01

This paper provides a brief overview of the history and objectives of the US Transuranium and Uranium Registries along with a discussion of some recent activities and accomplishments of these two parallel programs. 17 refs

Transuranium analysis methodologies for biological and environmental samples

International Nuclear Information System (INIS)

Wessman, R.A.; Lee, K.D.; Curry, B.; Leventhal, L.

1978-01-01

Analytical procedures for the most abundant transuranium nuclides in the environment (i.e., plutonium and, to a lesser extent, americium) are available. There is a lack of procedures for doing sequential analysis for Np, Pu, Am, and Cm in environmental samples, primarily because of current emphasis on Pu and Am. Reprocessing requirements and waste disposal connected with the fuel cycle indicate that neptunium and curium must be considered in environmental radioactive assessments. Therefore it was necessary to develop procedures that determine all four of these radionuclides in the environment. The state of the art of transuranium analysis methodology as applied to environmental samples is discussed relative to different sample sources, such as soil, vegetation, air, water, and animals. Isotope-dilution analysis with 243 Am ( 239 Np) and 236 Pu or 242 Pu radionuclide tracers is used. Americium and curium are analyzed as a group, with 243 Am as the tracer. Sequential extraction procedures employing bis(2-ethyl-hexyl)orthophosphoric acid (HDEHP) were found to result in lower yields and higher Am--Cm fractionation than ion-exchange methods

Transuranium and other alpha-emitting nuclides in the marine environment

International Nuclear Information System (INIS)

Pentreath, R.J.

1980-01-01

Marine environment contains naturally occurring alpha-emitting transuranium nuclides which are discharged from nuclear fuel reprocessing plants into the marine environment. Calculation of their potential of both the inhalation pathway and ingestion pathway to man, their residence time in the oceans, their loss to sediments, the chemical state in which they exist in sea water, their oxidation states in sea water, and their biological availability to sea organisms are discussed. The areas where data are lacking are indicated. Studies on the Windscale Site (U.K.) are extensively referred to in the discussion of above-mentioned aspects. It is brought out that the study of the naturally occurring actinides can be useful in the understanding of behaviour of man-made radionuclides in the marine environment, because many of the former are good analogues of the latter. (M.G.B.)

Apparent distribution coefficients of transuranium elements in UK coastal waters

International Nuclear Information System (INIS)

Kershaw, P.J.; Pentreath, R.J.; Harvey, B.R.; Lovett, M.B.; Boggis, S.J.

1986-01-01

The authorized inputs of low-level radioactive waste into the Irish Sea from the British Nuclear Fuels plc reprocessing plant at Sellafield may be used to advantage to study the distribution and behaviour of artificial radionuclides in the marine environment. Apparent distribution coefficients (Ksub(d)) for the transuranium elements Np, Pu, Am and Cm have been determined by the analysis of environmental samples collected from UK coastal waters. The sampling methodology for obtaining suspended sediment-seawater Ksub(d)s by filtration is described and critically evaluated. Artefacts may be introduced in the sample collection stage. Ksub(d) values have also been determined for seabed sediment-interstitial waters and the precautions taken to preserve in-situ chemical conditions are described. Variations in Ksub(d) values are discussed in relation to distance from Sellafield, suspended load, redox conditions and oxidation state changes. (author)

United States Transuranium Registry annual report October 1, 1977-October 1, 1978 to DOE Office of Health and Environmental Research

International Nuclear Information System (INIS)

Breitenstein, B.D. Jr.; Norwood, W.D.; Newton, C.E. Jr.

1979-01-01

The US Transuranium Registry (USTR) serves as a center for the acquisition and recording of information of the transuranic elements in man and their effects on man. To data 15,045 US transuranium workers have been tabulated, authority for 1048 autopsies obtained, and 93 autopsies granted. Department of Energy contractor and National Regulatory Commission licensee activities at participating sites are discussed. A significant increase in participation from the Savannah River plant has been received during the past year. The low level transuranic measurement laboratory analyzing tissue specimens for the USTR (except Rocky Flats specimens) was transferred from Battelle Pacific Northwest Laboratory to Los Alamos Scientific Laboratory. Dr. Charles W. Mays was appointed Chairman of the USTR Advisory Committee upon the resignation of Dr. James H. Sterner. To improve the quality of autopsy tissue for analysis prosectors were appointed at the Hanford, Rocky Flats, and Los Alamos sites. USTR educational and informational activities were extensive and varied

Transuranium perrhenates: Np(IV), Pu(IV) and (III), Am (III)

International Nuclear Information System (INIS)

Silvestre, Jean-Paul; Freundlich, William; Pages, Monique

1977-01-01

Synthesis in aqueous solution and by solid state reactions, crystallographical characterization and study of the stability of some transuranium perrhenates: Asup(n+)(ReO 4 - )sub(n) (A=Np(IV), Pu(IV), Pu(III), Am(III) [fr

Biology of the transuranium elements: an indexed bibliography

International Nuclear Information System (INIS)

Thompson, R.C.

1976-07-01

This bibliography on the biology of the transuranium elements is a revision of one issued in 1973 (BNWL-1782). It includes essentially all of the citations from the earlier document, a few corrections and additions from the older literature, plus the new literature to mid-1975. It also includes a subject-matter index not present in the original document

Biology of the transuranium elements: an indexed bibliography

Energy Technology Data Exchange (ETDEWEB)

Thompson, R.C. (comp.)

1976-07-01

This bibliography on the biology of the transuranium elements is a revision of one issued in 1973 (BNWL-1782). It includes essentially all of the citations from the earlier document, a few corrections and additions from the older literature, plus the new literature to mid-1975. It also includes a subject-matter index not present in the original document.

The transuranium elements: Members of the 5f series

International Nuclear Information System (INIS)

Gruen, D.M.

1990-01-01

The Symposium to commemorate the fiftieth anniversary of the discovery of the transuranium elements is an appropriate occasion on which to review the history of the development of ideas concerning the electronic structure of the new elements which, by determining their chemistry, would fix their position in the Periodic Table. Seaborg's actinide hypothesis was based on the properties of Np and Pu, as well as those of transuranium elements discovered after 1940. The elaboration of this hypothesis, with its profound consequences for our current understanding of the Periodic Table, will be traced from its beginnings to its present status, making use of the wealth of spectroscopic and magnetic data accumulated over the years to draw conclusions about the electronic structure of the actinides. Np and Pu, in particular, offered the first possibility for detailed study of the binding energies of 5f versus 6d electrons. The rich chemistry of these two elements is still providing new insights into the subtleties of electronic structure

Synthesis and crystal chemistry of transuranium element chalcogenides. Contribution to the study of the 5f electron localization

International Nuclear Information System (INIS)

Damien, Daniel.

1976-09-01

The synthesis and crystal chemistry of Np, Pu, Am and Cm transuranium element chalcogenides are described. From plutonium, transuranium element chalcogenides exhibit the same crystal structure as their rare-earth homologues. The variations of the lattice constants of these compounds in terms of the atomic number are characterized by the lack of the 5f contraction and are interpreted by a localization of the 5f electrons depending upon the considered transuranium element, the nature of the ligand and the crystal structure. To compare the degree of magnitude of the 5f electron delocalization in various compounds, a delocalization scale is proposed based on a comparison between the molar volumes of actinide and isostructural lanthanide compounds. This scale provides a delocalization coefficient for each compound under study. Examination of these coefficients shows that the 5f electrons, in series of actinide compounds, become localized when going from neptunium to curium and that the delocalization process does not only depend upon overlaps between 5f-6d orbitals of neighbouring actinide atoms; the delocalization coefficients show the existence of a secondary delocalization effect due to overlaps between the p anion and f actinide orbitals which are more important for the Vb anion group (N, P, As, Sb) than for the Vib one (S,Se,Te) [fr

Development of an integrated facility for processing transuranium solid wastes at the Savannah River Plant

International Nuclear Information System (INIS)

Boersma, M.D.; Hootman, H.E.; Permar, P.H.

1978-01-01

An integrated facility is being designed for processing solid wastes contaminated with long-lived alpha emitting (TRU) nuclides; this waste has been stored retrievably at the Savannah River Plant since 1965. The stored waste, having a volume of 10 4 m 3 and containing 3x10 5 Ci of transuranics, consists of both mixed combustible trash and failed and obsolete equipment primarily from transuranic production and associated laboratory operations. The facility for processing solid transuranic waste will consist of five processing modules: 1) unpackaging, sorting, and assaying; 2) treatment of combustibles by controlled air incineration; 3) size reduction of noncombustibles by plasma-arc cutting followed by decontamination by electropolishing; 4) fixation of the processed waste in cement; and 5) packaging for shipment to a federal repository. The facility is projected for construction in the mid-1980's. Pilot facilities, sized to manage currently generated wastes, will also demonstrate the key process steps of incineration of combustibles and size reduction/decontamination of noncombustibles; these facilities are projected for 1980-81. Development programs leading to these extensive new facilities are described

Detection and speciation of transuranium elements in synthetic groundwater via pulsed-laser excitation

International Nuclear Information System (INIS)

Beitz, J.V.; Bowers, D.L.; Doxtader, M.M.; Maroni, V.A.; Reed, D.T.

1987-01-01

High sensitivity methods for detection and speciation of complexed transuranium ions in synthetic basalt groundwater, and simplified analogs, are being developed which exploit advances in pulsed laser technology. The first demonstration of high sensitivity detection of a transuranium ion at temperatures significantly above ambient is reported using laser photoacoustic spectroscopy (LPAS). The existence of enhanced LPAS signal amplitudes with increasing temperature in aqueous solution is confirmed in LPAS spectra recorded at 30 C, 60 C and 90 C using micromolar concentrations of /sup 241/Am/sup 3+/. A detection sensitivity of 8.5 parts per trillion (weight basis) of /sup 244/Cm/sup 3+/ in a simplified basalt groundwater at 22 C has been achieved using laser-induced fluorescence spectroscopy (LIF). This corresponds to 1 x 10/sup 8/ Cm/sup 3+/ ions in the laser beam. The detailed spectroscopic information obtained by this method points to the existence of previously unobserved Cm/sup 3+/ species. A brief assessment of the applicability and sensitivity of LPAS and LIF methods for speciating transuranium ions in near-neutral pH aqueous solution, such as the groundwater expected in a basalt nuclear waste repository, is presented. 27 refs., 3 figs

United States Transuranium Registry summary report to June 30, 1974 to USAEC Division of Biomedical and Environmental Research

International Nuclear Information System (INIS)

Norwood, W.D.; Newton, C.E. Jr.

1974-06-01

This report gives some of the highlights of the US Transuranium Registry since its inception in late 1968 together with more detailed information concerning the activities for the year ending April 30, 1974. Articles are referred to which describe autopsy studies to determine plutonium body content, performed since 1949 for the purpose of evaluating plant health safety programs. The purpose of the Registry is described and its administrative direction is discussed. The Registry is a data collecting agency whose success depends upon how well the data is collected by the cooperating companies is described

Process for separately recovering uranium, transuranium elements, and fission products of uranium from atomic reactor fuel

International Nuclear Information System (INIS)

Balal, A.L.; Metscher, K.; Muehlig, B.; Reichmuth, C.; Schwarz, B.; Zimen, K.E.

1976-01-01

Spent reactor fuel elements are dissolved in dilute nitric acid. After addition of acetic acid as a complexing agent, the nitric acid is partly decomposed and the mixture subjected to electrolysis while a carrier liquid, which may be dilute acetic acid or a dilute mixture of acetic acid and nitric acid is caused to flow in the electric field between the electrodes either against the direction of ion migration or transversely thereto. The ions of uranium, plutonium, and other transuranium elements, and of fission products accumulate in discrete portions of the electrolyte and are separately withdrawn as at least three fractions after one or more stages of electrolysis

Transition of transuranium radionuclides to the stock-raising production at the grazing land of the cattle on the territory of the radioactive contamination

International Nuclear Information System (INIS)

Kudryashov, V.P.; Korol', R.A.; Pershukevich, E.V.; Bykovskij, V.V.

2009-01-01

As a result of receipt of transuranium elements in an organism of cattle probably pollution of animal produces by significant amounts of transuranium elements and their receipt on a food chain in a human body. (authors)

Selective separation of actinides and long-lived fission products from 1 AW MTR liquid waste: pilot plant tests part II

International Nuclear Information System (INIS)

Grossi, G.; Marrocchelli, A.; Pietrelli, L.; Calle, C.; Gili, M.; Luce, A.; Troiani, F.

1992-01-01

In Italy there are some 120 m 3 of liquid High-level radioactive Wastes coming from MTR, Candu and EPK River fuel elements reprocessing. These High-level radioactive wastes contain a large amount of chemicals and inert salts together with cesium, strontium and transuranium elements. Transuranium elements and strontium are separated from the inert salts by means of a selective precipitation while Cesium is adsorbed on synthetic zeolithes (AZE Process) or precipitated with sodium Tetraphenyl borate (NaTPB) (ATE process). The benchscale experiments have confirmed the feasibility of selective separation processes and have showed that decontamination efficiency for strontium, plutonium and cesium were, respectively, 100, 5000 and 1000. This second part of the CEC final report describes Searse pilot plant tests with cold experiments. 37 Refs.; 17 Figs.; 16 Tabs

United States Transuranium and Uranium Registries

International Nuclear Information System (INIS)

Kathren, R.L.; Filipy, R.E.; Dietert, S.E.

1991-06-01

This report summarizes the primary scientific activities of the United States Transuranium and Uranium Registries for the period October 1, 1989 through September 30, 1990. The Registries are parallel human tissue research programs devoted to the study of the actinide elements in humans. To date there have been 261 autopsy or surgical specimen donations, which include 11 whole bodies. The emphasis of the Registry was directed towards quality improvement and the development of a fully computerized data base that would incorporate not only the results of postmortem radiochemical analysis, but also medical and monitoring information obtained during life. Human subjects reviews were also completed. A three compartment biokinetic model for plutonium distribution is proposed. 2 tabs

United States Transuranium and Uranium Registries. Annual report February 1, 2001 - January 31, 2002

International Nuclear Information System (INIS)

Ehrhart, Susan M.; Filipy, Ronald E.

2002-01-01

This report documents the activities of the United States Transuranium and Uranium Registries (USTUR) from February 2001 through January 2002. Progress in continuing collaborations and several new collaborations is reviewed

United States Transuranium and Uranium Registries. Annual report February 1, 2001--January 31, 2002

Energy Technology Data Exchange (ETDEWEB)

Ehrhart, Susan M. (ed.); Filipy, Ronald E. (ed)

2002-07-01

This report documents the activities of the United States Transuranium and Uranium Registries (USTUR) from February 2001 through January 2002. Progress in continuing collaborations and several new collaborations is reviewed.

An evaluation of the food chain pathway for transuranium elements dispersed in soils

International Nuclear Information System (INIS)

Linsley, G.S.; Simmonds, J.R.; Kelly, G.N.

1978-12-01

Man can be exposed to radiation from transuranium elements dispersed in soils by two main routes; through the inhalation of resuspended particles and by ingestion of food products derived from the contaminated soils. In this report relationships are derived between the concentration in soil of two radionuclides, plutonium-239 and americium-241, and the dose to man. The transfer of the transuranium radionuclides through the food chains to man is evaluated using compartment models which are dynamic in character. The two pathways to man are of the same order of importance, within the uncertainties of the available data, and both must be considered in dose assessments. The technique of sensitivity analysis is used to identify areas where further research and investigations are necessary to improve the reliability of the assessment of radiation dose to man. (author)

Efficiency Of Transuranium Nuclides Transmutation

International Nuclear Information System (INIS)

Kazansky, Yu.A.; Klinov, D.A.; Semenov, E.V.

2002-01-01

One of the ways to create a wasteless nuclear power is based on transmutation of spent fuel nuclides. In particular, it is considered that the radioactivity of the nuclear power wastes should be the same (or smaller), than radioactivity of the uranium and the thorium extracted from entrails of the Earth. The problem of fission fragments transmutation efficiency was considered in article, where, in particular, the concepts of transmutation factor and the ''generalised'' index of biological hazard of the radioactive nuclides were entered. The transmutation efficiency has appeared to be a function of time and, naturally, dependent on nuclear power activity scenario, from neutron flux, absorption cross-sections of the nuclides under transmutation and on the rate of their formation in reactors. In the present paper the efficiency of the transmutation of transuranium nuclides is considered

Transuranium elements in macroalgae at Monaco following the Chernobyl accident

International Nuclear Information System (INIS)

Holm, E.; Ballestra, S.; Lopez, J.J.; Barci-Funel, G.; Ardisson, G.

1991-01-01

The atmospheric deposition and transfer of transuranium elements (TU) to macroalgae at Monaco following the Chernobyl accident has been studied. The deposition of TU was small compared to most fission products: 239+240 Pu and 241 Am could not be detected in water or algae, 242 Cm was the dominant α emitter detected in Chernobyl fallout. Concentration factors of TU for the macroalgae are estimated

Pyrochemical extraction for selective removal of transuranium elements from molten LiCl-KCl

International Nuclear Information System (INIS)

Ackermann, J.P.; Johnson, T.R.

1993-01-01

Recent determinations of separation factors that describe partition of the actinide and rare earth elements between liquid cadmium and LiCl-KCl eutectic allowed identification of a process for selective removal of the transuranium (TRU) element chlorides from the electrolyte used for electrofining of metal fuel from the Integral Fast Reactor. It is periodically necessary to remove rare earth elements from the electrolyte to limit heat generation from radioactive decay. Countercurrent extraction of electrolyte with uranium in cadmium solution allows retention of valuable TRU elements in the reprocessed fuel, and results in a rare earth waste stream that is essentially free of TRU elements and their concomitant long-term hazards

Measurements of transuranium nuclides in the environment at the Institute for Radiation Protection of the Gessellschaft fuer Strehlen-und Umweltforschung mbH, Munich

International Nuclear Information System (INIS)

Rosner, G.; Hoetzl, H.; Winkler, R.

1978-01-01

Work on environmental transuranium nuclides at the Institute for Radiation Protection of the Gesellschaft fur Strahlen-und Umweltforschung mbH, Munich, is briefly described and standard needs are discussed. Fallout plutonium measurements in air dust and precipitation samples started in 1970/1971. The procedure is outlined and results are presented as annual mean and sum values, respectively. Since 1973, transuranium nuclides in primary coolant, stack effluent air and waste-water samples from nuclear power stations are measured. Nuclides detected are 239 240 Pu, 238 Pu and/or 241 Am, 242 Cm and 244 Cm. Examples of alpha particle spectra are given. Needs for standards in environmental transuranium analysis are discussed. (author)

Transuranium processing plant report of production, status, and plans for the period October 1, 1978-September 30, 1980

International Nuclear Information System (INIS)

King, L.J.; Bigelow, J.E.; Collins, E.D.

1981-08-01

During this period, transuranium elements were obtained from 26 irradiated HFIT targets. The products included 86 mg of 249 Bk, 686 mg of 252 Cf, 3.1 mg of 253 Es, and an estimated 1.4 pg of 257 Fm. In addition, about 326 mg of high-purity 248 Cm was separated from previously purified 252 Cf. One hundred seven product shipments were made from TRU; recipients and the amounts of nuclides shipped are listed in a table. Forty-two standard and two special HFIR targets were fabricated. During the next 18 months, production totals of 110 mg of 249 Bk, 1200 mg of 252 Cf, 5.5 mg of 253 Es, and 2 pg of 257 Fm are anticipated. Also, a total of 225 mg of 248 Cm is expected to be made available. During this report period, a charcoal adsorber system for radioiodine removal was installed, tested, and placed in service. This system serves as a backup to the Hopcalite-charcoal system for adsorption of 131 I from the VOG stream. Seven 252 Cf neutron sources were fabricated during this report period. A total of 100 neutron sources have been fabricated previously at TRU. The original and current contents ( 252 Cf and 248 Cm) of the existing sources and the individuals to whom the sources are currently loaned are listed in a table. In addition to neutron sources, nine fission sources were prepared by electroplating 252 Cf onto platinum disks or foils.Special projects during this report period included (1) purification of two batches of isotopically pure 240 Pu, (2) fabrication of two special HFIR targets, (3) repurification of the residues of the einsteinium product from Campaign 56, (4) production of approx. 235 μg of 250 Cf by irradiation of 249 Bk, (5) radiography of 28 irradiated, stainless steel alloy, fracture-strain specimens, and (6) preparations for the production of 40 μg of 245 Es by irradiation of 253 Es

Results of two years' operation of the waste processing cell PROLIXE

International Nuclear Information System (INIS)

Lecomte, M.; Madic, C.; Broudic, J.C.

1990-01-01

Solid wastes, contaminated by alpha, beta, gamma radioisotopes, are produced by spent fuel reprocessing and isotope production. The PROLIXE plant, prototype for leaching and encapsulation was put into operation in March 1988 for waste management with the following aims: development of decontamination by oxidative leaching of alpha wastes, to obtain less than 0.1 Ci/t for surface storage; recycling radioactive isotope recovered especially transuranium elements; define a versatile process for various solid radioactive waste for an industrial plant [fr

Environmental and biological behaviour of plutonium and some other transuranium elements

International Nuclear Information System (INIS)

Richmond, C.R.

1983-01-01

The objectives are to summarize our knowledge of the way in which plutonium and some other transuranium elements migrate through ecosystems; to consider how the physiochemical state of these elements and the biological systems through which they pass may influence this movement; and to put into perspective the risks of serious illness in man resulting from his exposure to these elements in the environment

Technical papers presented at a DOE meeting on criteria for cleanup of transuranium elements in soil

International Nuclear Information System (INIS)

1984-09-01

Transuranium element soil contamination cleanup experience gained from nuclear weapons accidents and cleanup at Eniwetok Atoll was reviewed. Presentations have been individually abstracted for inclusion in the data base

Critical masses for the even-neutron-numbered transuranium actinides

International Nuclear Information System (INIS)

Westfall, R.M.

1981-01-01

As part of a standards effort of the American Nuclear Society to establish subcritical mass limits for the transuranium actinides, critical masses were calculated for seven actinides, critical masses were calculated for seven actinide elements in bare, water-reflected, and steel-reflected metal systems. For the nuclides /sup 242/Pu and /sup 241/Am, values obtained with ENDF/B-V cross-section data were in much better agreement with values inferred from experimental measurement than were initial values calculated with ENDF/B-IV data. A brief description of the analytical methods employed is followed by a presentation of the results. 10 refs

Actinide-soil interactions in waste management at the Savannah River Plant

International Nuclear Information System (INIS)

Holcomb, H.P.; Horton, J.H.; Wilhite, E.L.

1976-01-01

Three aspects of the transuranium (TRU) nuclide-soil interaction were studied in connection with Savannah River Plant (SRP) burial ground operations. Results of the studies are reported as three separate parts of this report

Biological effects of transuranium elements in experimental animals

International Nuclear Information System (INIS)

Bair, W.J.

1975-01-01

Results are reported from life span studies of the biological effects of the transuranium elements ( 238 Pu, 239 Pu, 241 Am, and 242 Cm) on laboratory animals following inhalation, skin absorption, or injection in various chemical forms. The dose levels at which major biological effects have been observed in experimental animals are discussed relative to the maximum permissible lung burden of 0.016 μCi for occupational exposures. Lung cancer has been observed at dose levels equivalent to about 100 times the maximum permissible lung burden. Current experiments directed towards determining whether health effects will occur at lower levels and the mechanisms by which α emitters induce cancer are reviewed. (U.S.)

'Masurium' and the 'early transuranium elements' or how discovery of nuclear fission was not clearly seen

International Nuclear Information System (INIS)

Keller, C.

1988-01-01

Fifty years after the discovery of fission, the scientific community is aware that this type of nuclear reaction could have been discovered more than a decade earlier. Noddack, Tacke and Berg announced in 1925 the discovery of elements Z = 43 (masurium) and rhenium (Z = 75), the first one could be detected only in U-bearing minerals. A recent re-examination by P.H.M. von Assche of the published data clearly showed that the original claim for element Z = 43 of the authors in 1925 was correct and, therefore, they detected not only element Z = 43 but also the first fission product. Because this discovery of element Z = 43 could not be repeated by other authors as that time, the scientific credibility of Noddack-Tacke was very low in order to give credit to her proposal that the 'early' transuranium elements by Enrico Fermi might also be fragments of known (lighter) elements. Enrico Fermi in 1934 obtained these 'early' (and as we today know: wrong) transuranium isotopes by irradiation of uranium with neutrons. A 'wrong' periodic system in the thirties which placed Th, Pa and U as 6d-elements and not as 5f-actinides chemically helped to consider these fission products as transuranium elements Z = 93/94. In 1937/38 I. Curie and P. Savitch discovered an 'actinium-nuclide' with 3,5 h half-life which, however, had properties similar to lanthanium and not to actinium, as they stated. (orig.) [de

Institute for transuranium elements Karlsruhe Annual Report 1988

International Nuclear Information System (INIS)

1989-01-01

The present report summarizes the results of the work which has been performed in 1988 at the Institute for Transuranium Elements of the Joint Research Centre of the Commission of the European Communities. While, as in the past, major efforts were devoted to the Programme on Nuclear Fuels and Actinide Research, important contributions were made to other JRC Specific Programmes, i.e. Reactor Safety, Radioactive Waste Management, and Safeguards and Fissile Materials Control. In addition, The Institute has carried out analytical work for the EURATOM Safeguards Directorate and executed research tasks in the safeguards context, both, for the Commission of the European Communities and for the International Atomic Energy Agency in Vienna. Exploratory Research, finally, dealt with an investigation of possibilities of acoustic aerosol scavenging

The radiological significance of transuranium radioisotopes released to the environment during operation of the LMFBR fuel cycle

International Nuclear Information System (INIS)

Barr, N.F.

1976-01-01

Estimates based on current knowledge and conservative assumptions indicate that release of transuranium elements from the Liquid Metal Fast Breeder Reactor (LMFBR) fuel cycle are likely to proaduce population dose commitments small compared to those produced by naturally occurring alpha emitters and globally dispersed transuranium radioisotopes from tests of nuclear weapons in the atmosphere. Potential health consequences of these releases to current and future generations are estimated to be very small compared to risks associated with the production of energy by fossil fuels. The estimates are subject to a number of uncertainties imposed by lack of knowledge. Some of the uncertainties are not likely to be greatly reduced until LMFBR facilities are designed and operated. Others may be significantly reduced prior to facility design and operation. The paper discusses the sensitivity of the estimates to uncertainties and approches to reducing those uncertainties that strongly influence the estimates. (author)

United States Transuranium Registry. Annual report, October 1, 1983-September 30, 1984

International Nuclear Information System (INIS)

Swint, M.J.; Kathren, R.L.

1985-04-01

This report provides an overview of the objectives, program, facilities and FY-84 accomplishments of the United States Transuranium Registry. Specific activities summarized include postmortem radiochemical analysis of two whole bodies, one with a significant deposition of 241 Am and the other with a deposition of 239 Pu. Results of a followup of early Manhattan District workers as potential registrants, a possible relationship between actinide concentration in bone and ash content, and interlaboratory cooperative activities are briefly discussed along with the initiation of studies of actinides in bone marrow and hair

Prediction of the health effects of inhaled transuranium elements from experimental animal data

International Nuclear Information System (INIS)

Bair, W.J.; Thomas, J.M.

1976-01-01

Although animal experiments are conducted to obtain data that can be used to predict the consequences of exposure to alpha-emitting elements on human health, scientists have been hesitant to project the results of animal experiments to man. However, since a human data base does not exist for inhaled transuranics, the animal data cannot be overlooked. The paper describes the derivation of linear non-threshold response relationships for lung cancer in rats after inhalation of alpha-emitting transuranium elements. These relationships were used to calculate risk estimates, which were then compared with a value calculated from the incidence of lung cancer in humans who had been exposed to sources of radiation other than the transuranics. Both estimates were compared with the estimated cancer risk associated with the annual whole-body dose limit of 5 rems for occupational exposure. The rat data suggest that the risk from a working lifetime exposure of 15 rem/a to the lungs from transuranium elements may be 5 times the risk incurred with a whole-body exposure of 5 rem/a, while the human data suggest the risk may be less. Since the histological type of plutonium-induced lung cancer that occurs in experimental animals is rare in man, the use of animal data to estimate risks may be conservative. Risk estimates calculated directly from the results of experiments in which animals actually inhaled transuranic particles circumvent such controversial issues as 'hot particles'. (author)

Physical--chemical studies of transuranium elements. Progress report, April 1, 1976--March 31, 1977

International Nuclear Information System (INIS)

Peterson, J.R.

1977-01-01

Major advances in our continuing program to determine, interpret, and correlate the basic chemical and physical properties of the transuranium elements are summarized for the period April 1, 1976, through March 31, 1977. Implementation of data reduction programs and acquisition of a CRT time-sharing graphics terminal/stand-alone computer have advanced significantly the handling capabilities of single-beam spectral data obtained by our microscope spectrophotometer. EsCl 3 , EsBr 3 , and EsI 3 have been well characterized spectroscopically, and limited X-ray diffraction data have been obtained from EsBr 3 and EsI 3 . The reduction of mixed Es-lanthanide trihalides has produced what might be Es(II). Dimorphism in BkCl 3 , CfCl 3 , and BkBr 3 has been studied spectrophotometrically and the results confirmed by X-ray analysis. Our solution microcalorimeter was improved by reducing the system-generated electrical noise and developing a novel sample container. The operating sensitivity was determined to be within the desired 0.1 percent precision requirement. The necessary hardware was obtained and software development was initiated for the capability to acquire, store, and analyze the heat of solution data automatically. A very sensitive apparatus (SQUID) for the determination of magnetic susceptibility has been constructed and is being evaluated. Our device should greatly facilitate the study of microgram-sized samples of transuranium elements and compounds

Storing solid radioactive wastes at the Savannah River Plant

International Nuclear Information System (INIS)

Horton, J.H.; Corey, J.C.

1976-06-01

The facilities and the operation of solid radioactive waste storage at the Savannah River Plant (SRP) are discussed in the report. The procedures used to segregate and the methods used to store radioactive waste materials are described, and the monitoring results obtained from studies of the movement of radionuclides from buried wastes at SRP are summarized. The solid radioactive waste storage site, centrally located on the 192,000-acre SRP reservation, was established in 1952 to 1953, before any radioactivity was generated onsite. The site is used for storage and burial of solid radioactive waste, for storage of contaminated equipment, and for miscellaneous other operations. The solid radioactive waste storage site is divided into sections for burying waste materials of specified types and radioactivity levels, such as transuranium (TRU) alpha waste, low-level waste (primarily beta-gamma), and high-level waste (primarily beta-gamma). Detailed records are kept of the burial location of each shipment of waste. With the attention currently given to monitoring and controlling migration, the solid wastes can remain safely in their present location for as long as is necessary for a national policy to be established for their eventual disposal. Migration of transuranium, activation product, and fission product nuclides from the buried wastes has been negligible. However, monitoring data indicate that tritium is migrating from the solid waste emplacements. Because of the low movement rate of ground water, the dose-to-man projection is less than 0.02 man-rem for the inventory of tritium in the burial trenches. Limits are placed on the amounts of beta-gamma waste that can be stored so that the site will require minimum surveillance and control. The major portion (approximately 98 percent) of the transuranium alpha radioactivity in the waste is stored in durable containers, which are amenable to recovery for processing and restorage should national policy so dictate

United States Transuranium and Uranium Registries. Annual report October 1, 1994 - September 30, 1995

Energy Technology Data Exchange (ETDEWEB)

Kathren, R.L.; Harwick, L.A.; Markel, M.J.

1996-07-01

The United States Transuranium and Uranium Registries (USTUR) comprise a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This report covers USTUR activities during the year from October 1994 through September 1995.

United States Transuranium and Uranium Registries. Annual report February 1, 2000--January 31, 2001

Energy Technology Data Exchange (ETDEWEB)

Ehrhart, Susan M. (ed.); Filipy, Ronald E. (ed.)

2001-07-01

The United States Transuranium and Uranium Registries (USTUR) comprise a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This report covers USTUR activities during the year from February 2000 through January 2001.

United States Transuranium and Uranium Registries. Annual report February 1, 2000-January 31, 2001

International Nuclear Information System (INIS)

Ehrhart, Susan M.; Filipy, Ronald E.

2001-01-01

The United States Transuranium and Uranium Registries (USTUR) comprise a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This report covers USTUR activities during the year from February 2000 through January 2001

United States Transuranium and Uranium Registries. Annuary report, February 1, 2004 - June 30, 2005

Energy Technology Data Exchange (ETDEWEB)

Alldredge, J. Richard [Washington State Univ., Richland, WA (United States); Ehrhart, Susan M. [Washington State Univ., Richland, WA (United States); Eliston, James T. [Washington State Univ., Richland, WA (United States); Emmel, Robert R. [Washington State Univ., Richland, WA (United States); Filipy, Ronald E. [Washington State Univ., Richland, WA (United States); James, Anthony C. [Washington State Univ., Richland, WA (United States); Sasser, Lyle B. [Washington State Univ., Richland, WA (United States); Wood, Tanya G. [Washington State Univ., Richland, WA (United States)

2006-05-31

Three events of significance to the U. S. Transuranium and Uranium Registries (USTUR) occurred during this reporting period: 1. The search for a new Associate Director was successful in that Dr. Anthony C. (Tony) James was appointed to the position, 2. A five-year grant for the operation of the USTUR was approved by the U. S. Department of Energy; the previous grant cycles were for three years, 3. I retired from the USTUR Directorship on July 1, 2005 and Tony James became the new Director.

Transuranium elements intake during works connected with the Chernobyl' NPP accident effect elimination

International Nuclear Information System (INIS)

Popov, V.I.; Kukhta, B.A.; Kononykhina, N.N.

1992-01-01

The materials of studies realized in 1989, 1990, 1991 and dealing with internal irradiation control caused by intake of transuranium elements (TUE) for the Chernobyl' NPP personnel and persons engaged in the accident effect elimination are generalized. the leading part of TUE inhalation intake in formation of internal irradiation doses is revealed. Evaluation of TUE inhalation intake hazards is made according to the results of measuring TUE activity in urine samples for the personnel examined (271 persons). The results of surveillance shows the effect of organism internal irradiation connected with TUE intake through respiratory organs. 23 refs.; 1 tab

Development of treatment method for stillage residues of liquid radioactive wastes to remove organic substances and transuranium elements

International Nuclear Information System (INIS)

Rudenko, L.I.; Dzhuzha, O.V.; Khan, V.E.

2008-01-01

The paper presents the results of the study into the laws that govern the process of treating by oxidation the stillage residues of liquid radioactive wastes to remove organic compounds and transuranium elements with the use of hydrogen peroxide, potassium permanganate and subsequent ultra-filtration. The optimum oxidisation regime has been defined on the basis of this study to ensure that the initial dichromate oxidability of LRW's stillage residues decreases from 6,000-9,500 to 500-1,000 mg O/I, whereas the TUE activity associated with the key isotopes is reduced by 74-87 % for 238,239,240 Pu, by 94-95 % for 241 Am, and by 90-95 % for 244 Cm. The concentration of uranium decreases by 94-99 %. It is proposed to implement this method at the Chernobyl NPP site.

United States Transuranium Registry summary report, July 1, 1974 to October 1, 1975 to ERDA Division of Biomedical and Environmental Research

International Nuclear Information System (INIS)

Norwood, W.D.; Newton, C.E. Jr.

1975-11-01

The primary purpose of the Registry is to protect the interests of workers, employers and the public by serving as a national focal point for the acquisition and provision of the latest and most precise information about the effects of the transuranic elements on man. This is being done by establishing the population at risk. To date some 9063 transuranium workers have been so identified. On a continuing basis, the best current estimates of the amount and location of any internal deposition of any of the transuranium elements in employees are being accumulated. These determinations have been improved by reconciliation with actual burdens found in various organs at autopsy or by alternate methods. Such employees are followed clinically and by epidemiological methods to determine whether there may be any adverse effects on such desposits on health or longevity. Registry statistics are given for the following sites: Hanford, Rocky Flats, Los Alamos, Savannah River, Mount, and Oak Ridge. The seven appendces contain information related to the Registry activities

Use of triton-WR-1339 (TWR) for a quantitative determination of the lysosomal binding of transuranium elements in the rat liver

International Nuclear Information System (INIS)

Gruner, K.R.

1978-01-01

The subcellular localisation of 239 Pu and 241 Am in the rat liver was investigated. A biochemical separation method with modified lysosomes was applied for the first time; the method permitted unique statements on the mitochondrial or lysosomal association of transuranium elements. Lysosomal association of 239 Pu and 241 Am between days 4 and 6 after radionuclide injection was most easily detected by follow-up treatment with TWR, i.e. the nonionic detergent was applied 2 days after injection of the radionuclide and 4 days before the onset of the analytical procedure. Extracellular transuranium depots could not be proved to exist neither by comparing absolute retention figures in perfused and nonperfused livers nor by subcellular distribution studies. A quantitative relation between the DTPA mobilisation efficiency in the total liver and the subcellular distribution patterns obtained for americium could be estimated for the period between the first and 18th day after radionuclide injection. It suggests on intracellular effect of DTPA. (orig./MG) [de

Transuranium elements leaching from simulated HLW glasses in synthetic interstitial claywater

International Nuclear Information System (INIS)

Wang, L.

1992-08-01

The main objective of this Master Thesis is to measure the steady-state concentrations of Pu, Np, and Am upon the leaching of High-Level Waste Glass in two types of synthetic claywater: humic acid free and humic acid containing synthetic claywater. The synthetic claywater has a composition that is representative for the in-situ interstitial groundwater of the Boom clay formation, a potential geological repository of radioactive waste in Belgium. The steady-state concentrations of transuranium elements were measured by leaching experiments with a typical duration of 400 days. Five main conclusions are drawn from the experimental data. (1) The transuranium elements that are released from simulated High Level Waste Glass are dominantly present in the synthetic claywater solutions as colloids. These colloids are smaller than 2 nm in absence of humic acids. In the presence of humic acids however, the colloids interact with actinides (adsorb or coagulate) and form particles larger than 2 nm. Np and Am are associated with inorganic and organic colloids in the synthetic interstitial claywater solution whereas Pu forms only inorganic colloids. (2) The steady-state concentration of Pu is in good agreement with the solubility of the Pu compound PuO 2 .xH 2 O. It is therefore concluded that PuO 2 .xH 2 O is the solubility controlling phase. (3) The Pu(IV)-species are dominant in the leaching solutions. Carbonate and humic acid complexes are negligible. (4) The steady-state concentrations of Np and Am in leaching solutions were much lower than the values calculated on the basis of known thermodynamic data. This indicates that the solubility controlling phases for Np and Am were not correctly identified or that the measured Np and Am concentrations were not steady-state values. (5) Non-active glass leaching tests have indicated that no organic colloids were formed as a result of glass dissolution. (A.S.)

Annual report of the United States transuranium and uranium registries, October 1, 1988--September 30, 1989

International Nuclear Information System (INIS)

Kathren, R.L.; Swint, M.J.; Dietert, S.E.

1990-04-01

This report summarizes the primary scientific activities of the United States Transuranium and Uranium Registries for the period October 1, 1988 through September 30, 1989. The Registries are parallel human tissue research programs devoted to the study of the actinide elements in man. The emphasis of the Transuranium Registry was directed toward evaluation of six whole body donations. In the five cases whose exposure was through inhalation, approximately half of the total body content of Pu-239 + 240 and a third of the Am-241 was found in the respiratory tract, suggesting that these nuclides are more avidly retained than predicted by the current model of the International Commission on Radiological Protection. A significant fraction of these nuclides is found in soft tissues other than liver, and an uptake fraction of 0.2 is proposed for muscle, with a residence half-time of 10 years. Studies of these and routine autopsy cases indicate that more than 90% of the total respiratory tract plutonium or americium is in the lungs, with the remainder in the lymph nodes, and that a greater fraction is found in the lungs of smokers relative to the lymph nodes. Primary activities of the Uranium Registry centered around the acquisition of a whole body donation from a woman who had received an injection of colloidal thorium dioxide some 38 years prior to death

United States Transuranium Registry annual report October 1, 1975-October 1, 1976 to ERDA Division of Biomedical and Environmental Research

International Nuclear Information System (INIS)

Breitenstein, B.D. Jr.; Norwood, W.D.; Newton, C.E. Jr.

1976-12-01

The US Transuranium Registry is a center for collecting precise information about the occupational effects of transuranic elements on man. To date 13,943 past and present transuranium workers have been tabulated. Health, mortality, causes of death and transuranic organ depositions are being studied. Bryce D. Breitenstein, Jr., M.D. was named Director of the Registry in July 1976. The Los Alamos Scientific Laboratory is directing the epidemiological portion of a plutonium worker health study with George Voelz, M.D. and Louis Hempelmann, M.D. serving as principal investigators. The USTR is affiliated with this study. USTR statistical data shows progressive acquisition of information for 1975 and 1976. ERDA contractor and NRC licensee activities at participating sited are discussed. Preparation of the input format to record and store USTR data has been completed and is ready for trial operation. USTR educational and informational activities were extensive and varied. Many queries arose from the use of published Registry autopsy data by Ralph Nader's associate Dr. S. Wolfe. There was continued cooperation with representatives of the British Atomic Energy Authority in their efforts to develop a plutonium registry

United States transuranium and uranium registries - 25 years of growth, research, and service. Annual report, April 1992--September 1993

International Nuclear Information System (INIS)

Kathren, R.L.; Harwick, L.A.; Toohey, R.E.; Russell, J.J.; Filipy, R.E.; Dietert, S.E.; Hunacek, M.M.; Hall, C.A.

1994-01-01

The Registries originated in 1968 as the National Plutonium Registry with the name changed to the United States Transuranium Registry the following year to reflect a broader concern with the heavier actinides as well. Initially, the scientific effort of the USTR was directed towards study of the distribution and dose of plutonium and americium in occupationally exposed persons, and to assessment of the effects of exposure to the transuranium elements on health. This latter role was reassessed during the 1970's when it was recognized that the biased cohort of the USTR was inappropriate for epidemiologic analysis. In 1978, the administratively separate but parallel United States Uranium Registry was created to carry out similar work among persons exposed to uranium and its decay products. A seven member scientific advisory committee provided guidance and scientific oversight. In 1992, the two Registries were administratively combined and transferred from the purview of a Department of Energy contractor to Washington State University under the provisions of a grant. Scientific results for the first twenty-five years of the Registries are summarized, including the 1985 publication of the analysis of the first whole body donor. Current scientific work in progress is summarized along with administrative activities for the period

United States transuranium and uranium registries - 25 years of growth, research, and service. Annual report, April 1992--September 1993

Energy Technology Data Exchange (ETDEWEB)

Kathren, R.L.; Harwick, L.A.; Toohey, R.E.; Russell, J.J.; Filipy, R.E.; Dietert, S.E.; Hunacek, M.M.; Hall, C.A.

1994-10-01

The Registries originated in 1968 as the National Plutonium Registry with the name changed to the United States Transuranium Registry the following year to reflect a broader concern with the heavier actinides as well. Initially, the scientific effort of the USTR was directed towards study of the distribution and dose of plutonium and americium in occupationally exposed persons, and to assessment of the effects of exposure to the transuranium elements on health. This latter role was reassessed during the 1970`s when it was recognized that the biased cohort of the USTR was inappropriate for epidemiologic analysis. In 1978, the administratively separate but parallel United States Uranium Registry was created to carry out similar work among persons exposed to uranium and its decay products. A seven member scientific advisory committee provided guidance and scientific oversight. In 1992, the two Registries were administratively combined and transferred from the purview of a Department of Energy contractor to Washington State University under the provisions of a grant. Scientific results for the first twenty-five years of the Registries are summarized, including the 1985 publication of the analysis of the first whole body donor. Current scientific work in progress is summarized along with administrative activities for the period.

Physical--chemical studies of transuranium elements. Progress report, April 1, 1977--March 31, 1978

International Nuclear Information System (INIS)

Peterson, J.R.

1978-01-01

Major advances in our continuing program to determine, interpret, and correlate the basic chemical and physical properties of the transuranium elements are summarized for the period April 1, 1977, through March 31, 1978. CfCl 2 , EsCl 2 , EsBr 2 , and EsI 2 were synthesized and characterized spectrophotometrically, as were several mixed-valence lanthanide-actinide halides (e.g., GdCf 4 Cl 11 ) and CmF 4 , CfF 4 , and EsF 3 . All samples not containing einsteinium were also examined by X rays. Studies of the chemical consequences of the radioactive decay series 253 Es alpha decaying to 249 Bk beta decaying to 249 Cf have continued and expanded. Elemental Cm-248 has been prepared on the one-half milligram scale and used to synthesize CmP and CmSb. Single crystals of AmTe 2 and AmSe 2 have been grown from a Te melt and by iodine transport, respectively. Our SQUID magnetometer was tested successfully in a preliminary configuration, and the expected sensitivity of the device was confirmed. A new design for the flux sensing coils was incorporated prior to an apparatus calibration experiment with lead. A porous vitreous carbon material was found to make a useful optically transparent electrode for simultaneous electrochemical and absorption spectroscopic investigations. Cyclic voltammograms of UO 2 2+ were obtained prior to a spectroelectrochemical study of the radiation of UO 2 2+ . The major obstacle in our solution microcalorimetry program was overcome by the realization of a leak-free sample container. Calorimeter performance now warrants experiments with transuranium element samples. The electrochemical reductions of Cf(III) and Es(III) have been studied by polarography and/or cyclic voltammetry. The results suggest that both are reduced to the divalent state before being reduced to the amalgam

US Transuranium Registry report on the 241Am content of a whole body. Part I: Introduction and history of the case

International Nuclear Information System (INIS)

Breitenstein, B.D.; Newton, C.E.; Norris, H.T.

1985-01-01

The first whole-body analysis of the U.S. Transuranium Registry was initiated in 1979. The donor was a 49-yr-old male Caucasian radiochemist who died of metastatic malignant melanoma. The donor had a recognized, longstanding 241 Am internal deposition first identified in a routine urine sample in 1958. A summary of the clinical and postmortem findings is presented with the chronologic sequence of the procedures

Partitioning and transmutation of transuranium elements under nuclear phase-out conditions. Technically reliable?; Transmutation von Transuranen unter den Randbedingungen des Kernenergieausstiegs. Technisch machbar?

Energy Technology Data Exchange (ETDEWEB)

Merk, Bruno; Rohde, Ulrich [Helmholtz-Zentrum Dresden-Rossendorf, Dresden (Germany)

2016-04-15

The German government has decided for the nuclear phase out, but a decision on a strategy for the management of the highly radioactive waste is not defined yet. Partitioning and Transmutation (P and T) could be considered as a technological option in the process of management of highly radioactive waste management, therefore a wide study has been conducted. In this group objectives for P and T and the boundary conditions of the phase out have been discussed. The fulfillment of the given objectives is analyzed using simulations of molten salt reactors with fast neutron spectrum. It is shown that the efficient transmutation of all existing transuranium isotopes would be possible in 3 to 4 reactors in a time frame of 45 to 60 years. Further on a detailed balance of different isotopic inventories is given to allow a deeper understanding of the processes during transmutation.

Proceedings of public hearings: plutonium and the other transuranium elements, Washington, D.C., December 10--11, 1974. Volume 1

International Nuclear Information System (INIS)

1974-01-01

The Environmental Protection Agency embarked on a program to evaluate the environmental impact of the transuranium elements and to consider whether further guidelines or standards are needed to assure adequate protection of the general ambient environment and of the public health from potential contamination of the environment by radionuclides of these elements. Public hearings were held in Washington, D. C., and Denver, Colorado, to gather information regarding the public and social implications of plutonium utilization; the factors involved in the balancing of costs vs benefits; dosimetry, health, and environmental effects; environmental levels and pathways; applications using plutonium; and control and cleanup technology. The proceedings of the hearing in Washington, D. C., Dec. 10-11, 1974, are presented. Data are included on current and potential sources of transuranium elements in the environment; animal studies on the tissue distribution of 233 U, 237 Np, 238 Pu, 239 Pu, 241 Am, 244 Cm, 249 Bk, 252 Cf, and 253 Es and pathological effects of body burdens of these radionuclides; and data on the health status of personnel known to have body burdens of 238 Pu or 239 Pu acquired during acute or chronic exposure, many of them over 30 years previously. It is pointed out that the lack of demonstrable biological effects of Pu in man provides presumptive evidence that the radiation protection standards in effect are adequate. (U.S.)

Nuclear heat-load limits for above-grade storage of solid transuranium wastes

International Nuclear Information System (INIS)

Clontz, B.G.

1978-06-01

Nuclear safety and heat load limits were established for above-grade storage of transuranium (TRU) wastes. Nuclear safety limits were obtained from a study by J.L. Forstner and are summarized. Heat load limits are based on temperature calculations for TRU waste drums stored in concrete containers (hats), and results are summarized. Waste already in storage is within these limits. The limiting factors for individual drum heat load limits were (1) avoidance of temperatures in excess of 190 0 F (decomposition temperature of anion resin) when anion resin is present in a concrete hat, and (2) avoidance of temperatures in excess of 450 0 F (ignition temperature of paper) at any point inside a waste drum. The limiting factor for concrete had heat load limits was avoidance of temperatures in excess of 265 0 F (melt point of high density polyethylene) at the drum liners. A temperature profile for drums and hats filled to recommended limits is shown. Equations and assumptions used were conservative

About possibility of creation of ecologically pure, safe nuclear power plants on the basis of high-effective resonant neutron interaction with splitting substances

International Nuclear Information System (INIS)

Irdyncheyev, L.A.; Malofeyev, A.M.; Frid, E.S.; Abramov, E.P.

1993-01-01

Currently the most important problem in nuclear engineering is creation of ecologically pure, safe nuclear power plants in the context of real danger of global ecological pollution of the environment with long-lived fission products and the resultant transuranium nuclides. The problem can be solved by creating nuclear power plants on the basis of high-effective resonant interaction (HERI). Such power plants would provide the total cycle, including nuclear fuel production (Plutonium-239 from Uranium-238), combustion and waste products salvaging by way of transformation of radioactive nuclides into stable isotopes

ORNL process waste treatment plant modifications

International Nuclear Information System (INIS)

Bell, J.P.

1982-01-01

The ORNL Process Waste Treatment Plant removes low levels of radionuclides (primarily Cs-137 and Sr-90) from process waste water prior to discharge. The previous plant operation used a scavenging precipitaton - ion exchange process which produced a radioactive sludge. In order to eliminate the environmental problems associated with sludge disposal, the plant is being converted to a new ion exchange process without the precipitation process

United States Transuranium and Uranium Registries: Researching radiation protection. USTUR annual report for February 1, 1999 through January 31, 2000

International Nuclear Information System (INIS)

Ehrhart, Susan M.; Filipy, Ronald E.

2000-01-01

The United States Transuranium and Uranium Registries (USTUR) comprise a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This report covers USTUR activities during the year from February 1999 through January 2000

United States Transuranium and Uranium Registries: Researching radiation protection. USTUR annual report for February 1, 1999 through January 31, 2000

Energy Technology Data Exchange (ETDEWEB)

Ehrhart, Susan M. (ed.); Filipy, Ronald E. (ed.)

2000-07-01

The United States Transuranium and Uranium Registries (USTUR) comprise a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This report covers USTUR activities during the year from February 1999 through January 2000.

MRPP: multiregion processing plant code

International Nuclear Information System (INIS)

Kee, C.W.; McNeese, L.E.

1976-09-01

The report describes the machine solution of a large number (approximately 52,000) of simultaneous linear algebraic equations in which the unknowns are the concentrations of nuclides in the fuel salt of a fluid-fueled reactor (MSBR) having a continuous fuel processing plant. Most of the equations define concentrations at various points in the processing plant. The code allows as input a generalized description of a processing plant flowsheet; it also performs the iterative adjustment of flowsheet parameters for determination of concentrations throughout the flowsheet, and the associated effect of the specified processing mode on the overall reactor operation

Amster: a molten-salt reactor concept generating its own 233U and incinerating transuranium elements

International Nuclear Information System (INIS)

Lecarpentier, D.; Garzenne, C.; Vergnes, J.; Mouney, H.; Delpech, M.

2002-01-01

In the coming century, sustainable development of atomic energy will require the development of new types of reactors able to exceed the limits of the existing reactor types, be it in terms of optimum use of natural fuel resources, reduction in the production of long-lived radioactive waste, or economic competitiveness. Of the various candidates with the potential to meet these needs, molten-salt reactors are particularly attractive, in the light of the benefits they offer, arising from two fundamental features: - A liquid fuel does away with the constraints inherent in solid fuel, leading to a drastic simplification of the fuel cycle, in particular making in possible to carry out on-line pyrochemical reprocessing; - Thorium cycle and thermal spectrum breeding. The MSBR concept proposed by ORNL in the 1970's thus gave a breeding factor of 1.06, with a doubling time of about 25 years. However, given the tight neutron balance of the thorium cycle (the η of 233 U is about 2.3), MSBR performance is only possible if there are strict constraints set on the in-line reprocessing unit: all the 233 Pa must be removed from the core so that it can decay on the 233 U in no more than about ten days (or at least 15 tonnes of salt to be extracted from the core daily), and the absorbing fission products, in particular the rare earths, must be extracted in about fifty days. With the AMSTER MSR concept, which we initially developed for incinerating transuranium elements, we looked to reduce the mass of salt to be reprocessed in order to minimise the size and complexity of the reprocessing unit coupled to the reactor, and the quantity of transuranium elements sent for disposal, as this is directly proportional to the mass of salt reprocessed for extraction of the fission products. Given that breeding was not an absolute necessity, because the reactor can be started by incinerating the transuranium elements from the spent fuel assemblies of current reactors, or if necessary by loading

Transuranium Processing Plant report of production, status, and plans for October 1, 1980-March 31, 1983

International Nuclear Information System (INIS)

King, L.J.; Benker, D.E.; Bigelow, J.E.

1984-10-01

Operations during this report period are summarized, and the amounts of materials obtained and shipped are listed. Proposed processing schedules and anticipated yields of various products in the near future are outlined. The original and current contents ( 252 Cf and 248 Cm) of existing neutron sources made at TRU, as well as the individuals to whom these sources are currently loaned, are tabulated. Also, a variety of special projects that required use of the facilities available at TRU are described

Fate of cesium, strontium, iodine and some transuranium elements in farm animals

International Nuclear Information System (INIS)

Mueller-Brunecker, G.

1982-11-01

Domestic animals may take up Cs, I, Sr and the most important transuranium elements by contaminated food, inhalation and cutaneous resorption. The resorption takes place (with differing percentage distribution) via gastrointestinal tract, lungs, skin and with wounds via injured skin areas. With chronical exposure and after resorption of radionuclides a distribution balance develops in the blood; with a single incorporation the activity concentration in the blood one increases and decreases again. According to the affinity of the radionuclide its major part is transported to one particular organ or tissue system, where depending on the degree of specific activity the most different damages may be provoked. Considerable amounts of the radionuclide quantities are discharged with urine, feces or milk. The amount discharged into the milk is of particular radioecologic interest. The portion of the radionuclides, which is discharged into the muscles and the milk of animals for slaughter is indicated by transmission factors, which have to be subjected to revision. The transmission factors given in literature are classified according to the animal species and discussed in the corresponding chapters. (orig./MG) [de

Process Experimental Pilot Plant

International Nuclear Information System (INIS)

Henze, H.

1986-01-01

The Process Experimental Pilot Plant (PREPP) at the Idaho National Engineering Laboratory (INEL) was built to convert transuranic contaminated solid waste into a form acceptable for disposal at the Waste Isolation Pilot Plant (WIPP), located near Carlsbad, New Mexico. There are about 2.0 million cubic ft of transuranic waste stored at the Transuranic Storage Area of the INEL's Radioactive Waste Management Complex (RWMC). The Stored Waste Examination Pilot Plant (SWEPP) located at the RWMC will examine this stored transuranic waste to determine if the waste is acceptable for direct shipment to and storage at WIPP, or if it requires shipment to PREPP for processing before shipment to WIPP. The PREPP process shreds the waste, incinerates the shredded waste, and cements (grouts) the shredded incinerated waste in new 55-gal drums. Unshreddable items are repackaged and returned to SWEPP. The process off-gas is cleaned prior to its discharge to the atmosphere, and complies with the effluent standards of the State of Idaho, EPA, and DOE. Waste liquid generated is used in the grouting operation

Effect of γ-ray emission on transuranium element production cross sections in heavy ion reactions

International Nuclear Information System (INIS)

Il'inov, A.S.; Oganesyan, Yu.Ts.; Cherepanov, E.A.

1980-01-01

The effect of competition of the γ ray emission with neutron evaporation and of compound nuclei fission induced by heavy ion reactions on the production cross sections for transuranium elements is considered. It is shown that taking account of γ ray emission leads to the broadening of the excitation functions of the (HI, xny) reactions such as 18 O+ 238 U, 40 Ar+ 206 Pb, 40 Ar+ 207 Pb and 40 Ar+ 208 Pb reactions and to the displacement of their maximum toward the higher energies as well as to an increase of the absolute cross sections which is especially strong close to the fusion barrier. Cross sections for the radiative capture of heavy ions by a heavy target nucleus in 40 Ar+ 206 Pb, 40 Ar+ 208 Pb, 48 Ca+ 204 Pb and 48 Ca+ 208 Pb reactions are estimated

Enhancing Elementary Pre-service Teachers' Plant Processes Conceptions

Science.gov (United States)

Thompson, Stephen L.; Lotter, Christine; Fann, Xumei; Taylor, Laurie

2016-06-01

Researchers examined how an inquiry-based instructional treatment emphasizing interrelated plant processes influenced 210 elementary pre-service teachers' (PTs) conceptions of three plant processes, photosynthesis, cellular respiration, and transpiration, and the interrelated nature of these processes. The instructional treatment required PTs to predict the fate of a healthy plant in a sealed terrarium (Plant-in-a-Jar), justify their predictions, observe the plant over a 5-week period, and complete guided inquiry activities centered on one of the targeted plant processes each week. Data sources included PTs' pre- and post-predictions with accompanying justifications, course artifacts such as weekly terrarium observations and science journal entries, and group models of the interrelated plant processes occurring within the sealed terraria. A subset of 33 volunteer PTs also completed interviews the week the Plant-in-a-Jar scenario was introduced and approximately 4 months after the instructional intervention ended. Pre- and post-predictions from all PTs as well as interview responses from the subgroup of PTs, were coded into categories based on key plant processes emphasized in the Next Generation Science Standards. Study findings revealed that PTs developed more accurate conceptions of plant processes and their interrelated nature as a result of the instructional intervention. Primary patterns of change in PTs' plant process conceptions included development of more accurate conceptions of how water is used by plants, more accurate conceptions of photosynthesis features, and more accurate conceptions of photosynthesis and cellular respiration as transformative processes.

Power plant process computer

International Nuclear Information System (INIS)

Koch, R.

1982-01-01

The concept of instrumentation and control in nuclear power plants incorporates the use of process computers for tasks which are on-line in respect to real-time requirements but not closed-loop in respect to closed-loop control. The general scope of tasks is: - alarm annunciation on CRT's - data logging - data recording for post trip reviews and plant behaviour analysis - nuclear data computation - graphic displays. Process computers are used additionally for dedicated tasks such as the aeroball measuring system, the turbine stress evaluator. Further applications are personal dose supervision and access monitoring. (orig.)

Monitoring of releases from an irradiated fuel reprocessing plant

International Nuclear Information System (INIS)

Fitoussi, L.

1978-01-01

At its UP 2 plant, the La Hague facility reprocesses irradiated fuel by the PUREX process. The fuel stems from graphite/gas, natural-uranium reactors and pressurized or boiling water enriched-uranium reactors. The gaseous effluents are collected and purified by high-efficiency washing and filtration. After purification the gas stream is discharged into the atmosphere by a single stack, 100m high and 6m in diameter, located at a high point on the site (184m). The radionuclides released into the air are: krypton-85, iodine-129 and -131, and tritium. The liquid effluents are collected by drainage systems, which transfer them to the effluent treatment station in the case of active or suspect solutions. Active solutions undergo treatment by chemical and physical processes. After purification the waste water is released into the sea by an underwater drainage system 5km long, which brings the outlet point into the middle of a tidal current 2km offshore. The radionuclides contained in the purified waste water are fission products originating from irradiated fuels in only slightly variable proportions, in which ruthenium-rhodium-106 predominates. Traces of the transuranium elements are also found in these solutions

The United States Transuranium and Uranium Registries: overview and recent progress

International Nuclear Information System (INIS)

Kathren, R.L.

1989-01-01

This paper describes the organisation, activities and recent scientific accomplishments of the United States Transuranium and Uranium Registries. Through voluntary donations of tissue obtained at autopsies, the Registries carry out studies of the concentration, distribution and biokinetics of actinides in occupationally exposed persons. Findings from tissue analyses from more than 200 autopsies include the following: a greater proportion of the americium intake, as compared with plutonium, is found in the skeleton; the half-time of americium in liver is significantly shorter than that of plutonium; the concentration of actinide in the skeleton is inversely proportional to the calcium and ash content of the bone; only a small percentage of the total skeletal deposition of plutonium is found in the marrow, implying a smaller risk from irradiation of the marrow relative to the bone surfaces; estimates of plutonium body burden made from urinalysis typically exceed those made from autopsy data; pathologists are unable to discriminate between a group of uranium workers and persons without known occupational exposure on the basis of evaluation of microscopic kidney slides; the skeleton is an important long-term depot for uranium and its fractional uptake by both skeleton and kidney may be greater than indicated by current models. These and other findings and current studies are discussed in depth. (author)

Plant uptake and transport of 241Am

International Nuclear Information System (INIS)

Wallace, A.; Romney, E.M.; Mueller, R.T. Sr.; soufi, S.M.

1981-01-01

We conducted several experiments with 241 Am to obtain a more complete understanding of how this transuranium element is absorbed and transported in plants. In a plant species (Tamarix pentandra Pall.) that has salt glands in the leaves excreting NaCl and other ions, 241 Am was not pumped through these glands. Cyanide, which forms complexes with any metals, when applied to a calcareous soil, greatly increased the transport of 241 Am into stems and leaves of bush bean plants. Radioactive cyanide ( 14 C) was also transported to leaves and stems. When radish was grown in both calcareous and noncalcareous soils, 241 Am appeared to be fixed on the peel so firmly that it was resistant to removal by HNO 3 washing. The chelating agent DTPA induced increased transport of 241 Am to leaves and into the fleshy roots of the radish. Data for Golden Cross hybrid corn grown in solution culture showed at least seven times as much 241 Am transport to the xylem exudatields are corrected by recovery of added tracers

United States Transuranium Registry: Annual report, October 1, 1986 through September 30, 1987

International Nuclear Information System (INIS)

Swint, M.J.; Kathren, R.L.

1988-04-01

This report summarizes progress of the United States Transuranium Registry for the 1987 fiscal year, including as an appendix the observations and recommendations of the Scientific Advisory Committee. Completion of the first phase of the analytical laboratory intercomparison study has led to verification and reduction in the uncertainty of the values for two NBS Standard Reference Materials. The human arm phantom built as an in-vivo counting calibration standard for Am-241 has been completed and made available for use by other laboratories, along with the previously completed skull phantom. Preliminary evaluation of USTR Case 193, a whole body plutonium case, was completed and reported at a national scientific meeting. The autopsy results tend to verify improvements in recent biokinetic models. Tissue donation was received from a former Hanford worker who received an extensive internal deposition of Am-241 from an explosion in a glove box 10 years prior to death from heart disease. Because of the extraordinary nature of this case, plans are being developed for interlaboratory collaboration to ensure that the knowledge derived from evaluation of this case will be maximized

Control system for technological processes in tritium processing plants with process analysis

International Nuclear Information System (INIS)

Retevoi, Carmen Maria; Stefan, Iuliana; Balteanu, Ovidiu; Stefan, Liviu; Bucur, Ciprian

2005-01-01

Integration of a large variety of installations and equipment into a unitary system for controlling the technological process in tritium processing nuclear facilities appears to be a rather complex approach particularly when experimental or new technologies are developed. Ensuring a high degree of versatility allowing easy modifications in configurations and process parameters is a major requirement imposed on experimental installations. The large amount of data which must be processed, stored and easily accessed for subsequent analyses imposes development of a large information network based on a highly integrated system containing the acquisition, control and technological process analysis data as well as data base system. On such a basis integrated systems of computation and control able to conduct the technological process could be developed as well protection systems for cases of failures or break down. The integrated system responds to the control and security requirements in case of emergency and of the technological processes specific to the industry that processes radioactive or toxic substances with severe consequences in case of technological failure as in the case of tritium processing nuclear plant. In order to lower the risk technological failure of these processes an integrated software, data base and process analysis system are developed, which, based on identification algorithm of the important parameters for protection and security systems, will display the process evolution trend. The system was checked on a existing plant that includes a removal tritium unit, finally used in a nuclear power plant, by simulating the failure events as well as the process. The system will also include a complete data base monitoring all the parameters and a process analysis software for the main modules of the tritium processing plant, namely, isotope separation, catalytic purification and cryogenic distillation

Iodox process tests in a transuranium element production campaign

International Nuclear Information System (INIS)

Collins, E.D.; Benker, D.E.

1978-01-01

The Iodox process removes gaseous iodine from air by oxidation of organic iodides and by hydrolysis-oxidation of free iodine to the stable iodate form. An Iodox system for treatment of the 10 -4 m 3 /s dissolver off-gas (DOG) stream was installed and is used for initial removal of radioiodine, this allowing the Hopcalite-charcoal to serve as a backup system in TRU. During a recent TRU production campaign, three dissolver runs were made to test the Iodox process

Comparison of risk assessment methodologies for nuclear power and nuclear fuels processing plants

International Nuclear Information System (INIS)

Durant, W.S.; Walker, D.H.

1986-08-01

The utilization of nuclear fission for the generation of electric power or other purposes has as its by-product radioactive fission products. These radioactive fission products represent a potential hazard different in nature from that associated with other process operations or other methods of electrical power generation. As a result the electrical power stations and the facilities designed to process the irradiated fuel to recover the still useful fuel and the products of the irradiation are designed with multiple physical barriers to contain the radioactive fission products in the event that an accident were to occur. In recent years, a disciplined approach has evolved for developing detailed models of a facility and its processes. These models can be used to assess the response for the facility to upset or accident events. The approach is based on an ordered application of available data employing fault tree/event tree methodologies. Data and/or engineering judgment are applied in a probabilisitc framework so the approach has been called Probabilistic Risk Assessment (PRA). The approach has been applied to nuclear electric generating facilities and to nuclear fuel processing facilities to assess the potential for release of fission product and transuranium element radionuclides (the hazard) and the resulting risks. The application of the methodology to the electrical generating facilities and to the fuel processing facilities has evolved somewhat differently because of differences in the facilities, availability of failure rate data, and expected outputs. This paper summarizes the two approaches and the differences in them compares the risk results from the existing studies

Plant uptake of americium, curium, and the chemical analog neodymium

International Nuclear Information System (INIS)

Weimer, W.C.; Laul, J.C.; Kutt, J.C.; Bondietti, E.A.

1977-01-01

The plant uptake from several bulk soils has been determined for neodymium, a chemical analog to the transuranium elements americium and curium, and several other native rare earth elements as well. These investigations have demonstrated that neodymium, which has very similar chemical properties to amercium and curium and should have a similar environmental behavior, does behave indistinguishably under both laboratory and field conditions. The uptake of the weathered or mobile forms of these elements from soils is expected to be governed primarily by their identical oxidation states and nearly identical ionic radii. This hypothesis is strongly supported by the chondritic (primordial) normalized rare earth element patterns in several plants. In these samples, the entire series of rare earth elements behaves as a smooth function of the REE ionic radii, as is also seen in the contiguous soils. This behavior suggests that the plant uptake of other ions with similar chemical properties (i.e., americium and curium) would also be governed by ionic size and charge

Institute for transuranium elements Karlsruhe. Annual report 1989

International Nuclear Information System (INIS)

1990-01-01

Transient-tested high burn-up fuel samples were investigated by electron microscopy to study the effect of strain on fission product distribution, and the concentration of (U,Pu)O 2 agglomerates in irradiated MOX fuel was examined by electron microprobe analysis. Conclusions on maximum temperatures to which the core of the Three Mile Island reactor was exposed could be drawn from an examination of TMI fuel debris. Equipment to measure thermophysical fuel properties for reactor safety studies was further developed. An improved version (slice version) of the TRANSURANUS fuel pin code was tested and released for external use. Safety Aspects of Fuel Operation and Handling were dealt with by improving preparation methods of (U,Pu)N. Release and resuspension of radioactive dust particles in fires was studied. The principal objective of the Actinide Determination and Recycling activity was the reduction of long-term hazards of alpha-bearing nuclear waste. The long-term storage behaviour of UO 2 and MOX spent fuel samples as well as of vitrified waste forms was further investigated by studying the effect of leaching. The electronic structure of the transuranium elements is the central objective of basic Actinide Research. A large number of ternary alloys containing Np or Pu and Si or Ge, together with a transition metal was prepared for basic experimental studies. New high-pressure phases were discovered in PuSe, UPS, ThO 2 , and PuO 2 . Analytical techniques were evaluated and automated for safeguards. A multiwavelength pyrometer was adapted for industrial use. Major contracts with Third Parties were dealing with the development of minor actinide alloys, and the post-irradiation examination of high burn-up UO 2 and MOX fuel from LWR power stations

Processes for manufacture of products from plants

DEFF Research Database (Denmark)

2010-01-01

Disclosed herein is a process for inhibiting browning of plant material comprising adding a chelating agent to a disrupted plant material and adjusting the pH to a value of 2.0 to 4.5. Processes for manufacture of soluble and insoluble products from a plant material are also disclosed. Soluble...

Process control in biogas plants

DEFF Research Database (Denmark)

Holm-Nielsen, Jens Bo; Oleskowicz-Popiel, Piotr

2013-01-01

Efficient monitoring and control of anaerobic digestion (AD) processes are necessary in order to enhance biogas plant performance. The aim of monitoring and controlling the biological processes is to stabilise and optimise the production of biogas. The principles of process analytical technology...

Ferrous Metal Processing Plants

Data.gov (United States)

Department of Homeland Security — This map layer includes ferrous metal processing plants in the United States. The data represent commodities covered by the Minerals Information Team (MIT) of the...

Nonferrous Metal Processing Plants

Data.gov (United States)

Department of Homeland Security — This map layer includes nonferrous metal processing plants in the United States. The data represent commodities covered by the Minerals Information Team (MIT) of the...

United States Transuranium and Uranium Registries. Annual report, February 1, 2003 - January 31, 2004

Energy Technology Data Exchange (ETDEWEB)

Alldredge, J. R. [Washington State Univ., Pullman, WA (United States); Brumbaugh, T. L. [Washington State Univ., Pullman, WA (United States); Ehrhart, Susan M. [Washington State Univ., Pullman, WA (United States); Elliston, J. T. [Washington State Univ., Pullman, WA (United States); Filipy, R. E. [Washington State Univ., Pullman, WA (United States); James, A. C. [Washington State Univ., Pullman, WA (United States); Pham, M. V. [Washington State Univ., Pullman, WA (United States); Wood, T. G. [Washington State Univ., Pullman, WA (United States); Sasser, L. B. [Washington State Univ., Pullman, WA (United States)

2004-01-31

This year was my fourteenth year with the U. S. Transuranium and Uranium Registries (USTUR). How time flies! Since I became the director of the program five years ago, one of my primary goals was to increase the usefulness of the large USTUR database that consists of six tables containing personal information, medical histories, radiation exposure histories, causes of death, and the results of radiochemical analysis of organ samples collected at autopsy. It is essential that a query of one or more of these tables by USTUR researchers or by collaborating researchers provides complete and reliable information. Also, some of the tables (those without personal identifiers) are destined to appear on the USTUR website for the use of the scientific community. I am pleased to report that most of the data in the database have now been verified and formatted for easy query. It is important to note that no data were discarded; copies of the original tables were retained and the original paper documents are still available for further verification of values as needed.

Carbide process picked for Chinese polyethylene plant

International Nuclear Information System (INIS)

Alperowicz, N.

1993-01-01

Union Carbide (Danbury, CT) is set to sign up its eighth polyethylene (PE) license in China. The company has been selected to supply its Unipol technology to Jilin Chemical Industrial Corp. (JCIC) for a 100,000-m.t./year linear low-density PE (LLDPE) plant at Jilin. The plant will form part of a $2-billion petrochemical complex, based on a 300,000-m.t./year ethylene unit awarded to a consortium made up of Samsung Engineering (Seoul) and Linde. A 10,000-m.t./year butene-1 unit will also be built. Toyo Engineering, Snamprogetti, Mitsubishi Heavy Industries, and Linde are competing for the contract to supply the LLDPE plant. The signing is expected this spring. Two contenders are vying to supply an 80,000-m.t./year phenol plant for JCIC. They are Mitsui Engineering, offering the Mitsui Petrochemical process, and Chisso, with UOP technology. Four Unipol process PE plants are under construction in China and three are in operation. At Guangzhou, Toyo Engineering is building a 100,000-m.t./year plant, due onstream in 1995, while Snamprogetti is to finish construction of two plants in the same year at Zhonguyan (120,000 m.t./year) and at Maoming (140,000 m.t./year). The Daquing Design Institute is responsible for the engineering of a 60,000-m.t./year Unipol process PE plant, expected onstream early in 1995. Existing Unipol process PE plants are located in Qilu (60,000 m.t./year LLDPE and 120,000 m.t./year HDPE) and at Taching (60,000 m.t./year HDPE)

United States Transuranium and Uranium Registries: A human tissue research program. USTUR annual report for October 1, 1997 through January 31, 1999

Energy Technology Data Exchange (ETDEWEB)

Ehrhart, Susan M. (ed.); Filipy, Ronald E. (ed.)

1999-10-01

The United States Transuranium and Uranium Registries (USTUR) are a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This annual report covers October 1, 1997, through January 31, 1999; the reporting period has been extended so that future annual reports will coincide with the period covered by the grant itself.

Office of Basic Energy Sciences: 1984 summary report

International Nuclear Information System (INIS)

1984-11-01

Subprograms of the OBES discussed in this document include: materials sciences, chemical sciences, nuclear sciences, engineering and geosciences, advanced energy projects, biological energy research, carbon dioxide research, HFBR, HFIR, NSLS, SSRL, IPNS, Combustion Research Facility, high-voltage and atomic resolution electron microscopic facilities, Oak Ridge Electron Linear Accelerator, Dynamitron Accelerator, calutrons, and Transuranium Processing Plant. Nickel aluminide and glassy metals are discussed

Water processing in power plants

International Nuclear Information System (INIS)

Marquardt, K.

1984-01-01

Surface water can be treated to a high degree of efficiency by means of new compact processes. The quantity of chemicals to be dosed can easily be adjusted to the raw water composition by intentional energy supply via agitators. In-line coagulations is a new filtration process for reducing organic substances as well as colloids present in surface water. The content of organic substances can be monitored by measuring the plugging index. Advanced ion-exchanger processes (fluidised-bed, compound fluidised-bed and continuously operating ion exchanger plants) allow the required quantity of chemicals as well as the plant's own water consumption to be reduced, thus minimising the adverse effect on the environment. The reverse-osmosis process is becoming more and more significant due to the low adverse effect on the environment and the given possibilities of automation. As not only ionogenic substances but also organic matter are removed by reverse osmosis, this process is particularly suited for treating surface water to be used as boiler feed water. The process of vacuum degassing has become significant for the cold removal of oxygen. (orig.) [de

Enhancing Elementary Pre-Service Teachers' Plant Processes Conceptions

Science.gov (United States)

Thompson, Stephen L.; Lotter, Christine; Fann, Xumei; Taylor, Laurie

2016-01-01

Researchers examined how an inquiry-based instructional treatment emphasizing interrelated plant processes influenced 210 elementary pre-service teachers' (PTs) conceptions of three plant processes, photosynthesis, cellular respiration, and transpiration, and the interrelated nature of these processes. The instructional treatment required PTs to…

Nuclear pre-mRNA processing in plants

Energy Technology Data Exchange (ETDEWEB)

Reddy, A.S.N. [Colorado State Univ., Fort Collins, CO (United States). Dept. of Biology and Program in Molecular Plant Biology; Golovkin, M. (eds.) [Thomas Jefferson Univ., Philadelphia, PA (United States). Dept. of Microbiology

2008-07-01

This volume of CTMI, entitled Nuclear premRNA Processing in Plants, with 16 chapters from leading scientists in this area, summarizes recent advances in nuclear pre-mRNA processing and its role in plant growth and development. It provides researchers in the field, as well as those in related areas, with an up-to-date and comprehensive, yet concise, overview of the current status and future potential of this research in understanding plant biology. The first four chapters focus on spliceosome composition, genome-wide alternative splicing, and splice site requirements for U1 and U12 introns using computational and empirical approaches. Analysis of sequenced plant genomes has revealed that 80% of all protein-coding nuclear genes contain one or more introns. The lack of an in vitro plant splicing system has made it difficult to identify general and plant-specific components of splicing machinery in plants. The next three chapters focus on serine/arginine-rich (SR) proteins, a family of highly conserved proteins, which are known to play key roles in constitutive and regulated splicing of pre-mRNA and other aspects of RNA metabolism in metazoans. These proteins engage both in RNA binding and protein.protein interactions and function as splicing regulators at multiple stages of spliceosome assembly. This family of proteins has expanded considerably in plants with several plant-specific SR proteins. Several serendipitous discoveries made using forward genetics are indicating that RNA metabolism (alternative splicing, alternative polyadenylation, mRNA transport) plays an important role in many aspects of plant growth and development and in plant responses to biotic and abiotic stresses. The next seven chapters focus on these aspects of RNA metabolism. The plant hormone abscisic acid (ABA) regulates a number of physiological processes during plant growth and development. The next chapter or A.B. Rose discusses the ways introns affect gene expression both positively and

Nuclear pre-mRNA processing in plants

International Nuclear Information System (INIS)

Reddy, A.S.N.; Golovkin, M.

2008-01-01

This volume of CTMI, entitled Nuclear premRNA Processing in Plants, with 16 chapters from leading scientists in this area, summarizes recent advances in nuclear pre-mRNA processing and its role in plant growth and development. It provides researchers in the field, as well as those in related areas, with an up-to-date and comprehensive, yet concise, overview of the current status and future potential of this research in understanding plant biology. The first four chapters focus on spliceosome composition, genome-wide alternative splicing, and splice site requirements for U1 and U12 introns using computational and empirical approaches. Analysis of sequenced plant genomes has revealed that 80% of all protein-coding nuclear genes contain one or more introns. The lack of an in vitro plant splicing system has made it difficult to identify general and plant-specific components of splicing machinery in plants. The next three chapters focus on serine/arginine-rich (SR) proteins, a family of highly conserved proteins, which are known to play key roles in constitutive and regulated splicing of pre-mRNA and other aspects of RNA metabolism in metazoans. These proteins engage both in RNA binding and protein.protein interactions and function as splicing regulators at multiple stages of spliceosome assembly. This family of proteins has expanded considerably in plants with several plant-specific SR proteins. Several serendipitous discoveries made using forward genetics are indicating that RNA metabolism (alternative splicing, alternative polyadenylation, mRNA transport) plays an important role in many aspects of plant growth and development and in plant responses to biotic and abiotic stresses. The next seven chapters focus on these aspects of RNA metabolism. The plant hormone abscisic acid (ABA) regulates a number of physiological processes during plant growth and development. The next chapter or A.B. Rose discusses the ways introns affect gene expression both positively and

Transmutation of All German Transuranium under Nuclear Phase Out Conditions - Is This Feasible from Neutronic Point of View?

Science.gov (United States)

Merk, Bruno; Litskevich, Dzianis

2015-01-01

The German government has decided for the nuclear phase out, but a decision on a strategy for the management of the highly radioactive waste is not defined yet. Partitioning and Transmutation (P&T) could be considered as a technological option for the management of highly radioactive waste, therefore a wide study has been conducted. In the study group objectives for P&T and the boundary conditions of the phase out have been discussed. The fulfillment of the given objectives is analyzed from neutronics point of view using simulations of a molten salt reactor with fast neutron spectrum. It is shown that the efficient transmutation of all existing transuranium isotopes would be possible from neutronic point of view in a time frame of about 60 years. For this task three reactors of a mostly new technology would have to be developed and a twofold life cycle consisting of a transmuter operation and a deep burn phase would be required. A basic insight for the optimization of the time duration of the deep burn phase is given. Further on, a detailed balance of different isotopic inventories is given to allow a deeper understanding of the processes during transmutation in the molten salt fast reactor. The effect of modeling and simulation is investigated based on three different modeling strategies and two different code versions.

Transmutation of All German Transuranium under Nuclear Phase Out Conditions - Is This Feasible from Neutronic Point of View?

Directory of Open Access Journals (Sweden)

Bruno Merk

Full Text Available The German government has decided for the nuclear phase out, but a decision on a strategy for the management of the highly radioactive waste is not defined yet. Partitioning and Transmutation (P&T could be considered as a technological option for the management of highly radioactive waste, therefore a wide study has been conducted. In the study group objectives for P&T and the boundary conditions of the phase out have been discussed. The fulfillment of the given objectives is analyzed from neutronics point of view using simulations of a molten salt reactor with fast neutron spectrum. It is shown that the efficient transmutation of all existing transuranium isotopes would be possible from neutronic point of view in a time frame of about 60 years. For this task three reactors of a mostly new technology would have to be developed and a twofold life cycle consisting of a transmuter operation and a deep burn phase would be required. A basic insight for the optimization of the time duration of the deep burn phase is given. Further on, a detailed balance of different isotopic inventories is given to allow a deeper understanding of the processes during transmutation in the molten salt fast reactor. The effect of modeling and simulation is investigated based on three different modeling strategies and two different code versions.

Mass Customization of process plants

DEFF Research Database (Denmark)

Hvam, Lars

2006-01-01

This case study describes how F.L.Smidth A/S, a manufacturer of large processing plants for cement production, has applied the principles of mass customisation in the area of highly complex, custom engineered products. The company has based its sales process on a configuration system to achieve...

Issues evaluation process at Rocky Flats Plant

International Nuclear Information System (INIS)

Smith, L.C.

1992-01-01

This report describes the issues evaluation process for Rocky Flats Plant as established in July 1990. The issues evaluation process was initiated February 27, 1990 with a Charter and Process Overview for short-term implementation. The purpose of the process was to determine the projects required for completion before the Phased Resumption of Plutonium Operations. To determine which projects were required, the issues evaluation process and emphasized risk mitigation, based on a ranking system. The purpose of this report is to document the early design of the issues evaluation process to record the methodologies used that continue as the basis for the ongoing Issues Management Program at Rocky Flats Plant

Process plant equipment operation, control, and reliability

CERN Document Server

Holloway, Michael D; Onyewuenyi, Oliver A

2012-01-01

"Process Plant Equipment Book is another great publication from Wiley as a reference book for final year students as well as those who will work or are working in chemical production plants and refinery…" -Associate Prof. Dr. Ramli Mat, Deputy Dean (Academic), Faculty of Chemical Engineering, Universiti Teknologi Malaysia "…give[s] readers access to both fundamental information on process plant equipment and to practical ideas, best practices and experiences of highly successful engineers from around the world… The book is illustrated throughout with numerous black & white p

A contractor's approach to engineering process plant for radioactive liquor processing

International Nuclear Information System (INIS)

Braide, W.M.; Fletcher, P.D.

1982-01-01

Protection of personnel from damaging sources of radiation is the overriding consideration which influences the fundamental design of plant for processing active liquors in the Nuclear Industry. The conventional design procedures of the Chemical Plant Contractor have therefore to be modified to meet the specific technology and additional safety requirements. Ways in which the added factor of radiation influences the design philosophy for Nuclear Plant compared to conventional Chemical Plant are described. Design philosophy is demonstrated by design studies for active liquor storage and evaporation plant. (author)

A contractors's approach to engineering process plant for radioactive liquor processing

International Nuclear Information System (INIS)

Braide, W.M.; Fletcher, P.D.

1982-01-01

Protection of personnel from damaging sources of radiation is the overriding consideration which influences the fundamental design of plant for processing active liquors in the Nuclear Industry. The conventional design procedures of the Chemical Plant Contractor have therefore to be modified to meet the specific technology and additional safety requirements. This paper describes ways in which the added factor of radiation influences the design philosophy for Nuclear Plant compared to conventional Chemical Plant. The design philosophy is demonstrated by design studies for active liquor storage and evaporation plant. (author)

Empirical evaluation of the Process Overview Measure for assessing situation awareness in process plants.

Science.gov (United States)

Lau, Nathan; Jamieson, Greg A; Skraaning, Gyrd

2016-03-01

The Process Overview Measure is a query-based measure developed to assess operator situation awareness (SA) from monitoring process plants. A companion paper describes how the measure has been developed according to process plant properties and operator cognitive work. The Process Overview Measure demonstrated practicality, sensitivity, validity and reliability in two full-scope simulator experiments investigating dramatically different operational concepts. Practicality was assessed based on qualitative feedback of participants and researchers. The Process Overview Measure demonstrated sensitivity and validity by revealing significant effects of experimental manipulations that corroborated with other empirical results. The measure also demonstrated adequate inter-rater reliability and practicality for measuring SA in full-scope simulator settings based on data collected on process experts. Thus, full-scope simulator studies can employ the Process Overview Measure to reveal the impact of new control room technology and operational concepts on monitoring process plants. Practitioner Summary: The Process Overview Measure is a query-based measure that demonstrated practicality, sensitivity, validity and reliability for assessing operator situation awareness (SA) from monitoring process plants in representative settings.

Transmutation of All German Transuranium under Nuclear Phase Out Conditions – Is This Feasible from Neutronic Point of View?

Science.gov (United States)

Merk, Bruno; Litskevich, Dzianis

2015-01-01

The German government has decided for the nuclear phase out, but a decision on a strategy for the management of the highly radioactive waste is not defined yet. Partitioning and Transmutation (P&T) could be considered as a technological option for the management of highly radioactive waste, therefore a wide study has been conducted. In the study group objectives for P&T and the boundary conditions of the phase out have been discussed. The fulfillment of the given objectives is analyzed from neutronics point of view using simulations of a molten salt reactor with fast neutron spectrum. It is shown that the efficient transmutation of all existing transuranium isotopes would be possible from neutronic point of view in a time frame of about 60 years. For this task three reactors of a mostly new technology would have to be developed and a twofold life cycle consisting of a transmuter operation and a deep burn phase would be required. A basic insight for the optimization of the time duration of the deep burn phase is given. Further on, a detailed balance of different isotopic inventories is given to allow a deeper understanding of the processes during transmutation in the molten salt fast reactor. The effect of modeling and simulation is investigated based on three different modeling strategies and two different code versions. PMID:26717509

Trans-Uranium Doping Utilization for Increasing Protected Plutonium Proliferation of Small Long Life Reactor

Energy Technology Data Exchange (ETDEWEB)

Permana, Sidik [Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology 2-12-1-N1-17, O-okayama, Meguro-ku, Tokyo 152-8550 (Japan); Nuclear and Biophysics Research Group, Department of Physics, Bandung Institute of Technology, Gedung Fisika, Jl. Ganesha 10, Bandung 40132 (Indonesia); Suud, Zaki [Nuclear and Biophysics Research Group, Department of Physics, Bandung Institute of Technology, Gedung Fisika, Jl. Ganesha 10, Bandung 40132 (Indonesia); Suzuki, Mitsutoshi [Japan Atomic Energy Agency, Nuclear Non-proliferation Science and Technology Center, 2-4 Shirane Shirakata, Tokai-mura, Ibaraki, 319-1195 (Japan)

2009-06-15

Scientific approaches are performed by adopting some methodologies in order to increase a material 'barrier' in plutonium isotope composition by increasing the even mass number of plutonium isotope such as Pu-238, Pu-240 and Pu-242. Higher difficulties (barrier) or more complex requirement for peaceful use of nuclear materials, material fabrication and handling and isotopic enrichment can be achieved by a higher isotopic barrier. Higher barrier which related to intrinsic properties of plutonium isotopes with even mass number (Pu-238, Pu-240 and Pu-242), in regard to their intense decay heat (DH) and high spontaneous fission neutron (SFN) rates were used as a parameter for improving the proliferation resistance of plutonium itself. Pu-238 has relatively high intrinsic characteristics of DH (567 W/kg) and SFN rate of 2660 n/g/s can be used for making a plutonium characteristics analysis. Similar characteristics with Pu-238, other even mass number of plutonium isotopes such as Pu-240 and Pu-242 have been shown in regard to SFN values. Those even number mass of plutonium isotope contribute to some criteria of plutonium characterization which will be adopted for present study such as IAEA, Pellaud and Kessler criteria (IAEA, 1972; Pellaud, 2002; and Kessler, 2004). The study intends to evaluate the trans-uranium doping effect for increasing protected plutonium proliferation in long-life small reactors. The development of small and medium reactor (SMR) is one of the options which have been adopted by IAEA as future utilization of nuclear energy especially for less developed countries (Kuznetsov, 2008). The preferable feature for small reactors (SMR) is long life operation time without on-site refueling and in the same time, it includes high proliferation resistance feature. The reactor uses MOX fuel as driver fuel for two different core types (inner and outer core) with blanket fuel arrangement. Several trans-uranium doping and some doping rates are evaluated

Proceedings: Distributed digital systems, plant process computers, and networks

International Nuclear Information System (INIS)

1995-03-01

These are the proceedings of a workshop on Distributed Digital Systems, Plant Process Computers, and Networks held in Charlotte, North Carolina on August 16--18, 1994. The purpose of the workshop was to provide a forum for technology transfer, technical information exchange, and education. The workshop was attended by more than 100 representatives of electric utilities, equipment manufacturers, engineering service organizations, and government agencies. The workshop consisted of three days of presentations, exhibitions, a panel discussion and attendee interactions. Original plant process computers at the nuclear power plants are becoming obsolete resulting in increasing difficulties in their effectiveness to support plant operations and maintenance. Some utilities have already replaced their plant process computers by more powerful modern computers while many other utilities intend to replace their aging plant process computers in the future. Information on recent and planned implementations are presented. Choosing an appropriate communications and computing network architecture facilitates integrating new systems and provides functional modularity for both hardware and software. Control room improvements such as CRT-based distributed monitoring and control, as well as digital decision and diagnostic aids, can improve plant operations. Commercially available digital products connected to the plant communications system are now readily available to provide distributed processing where needed. Plant operations, maintenance activities, and engineering analyses can be supported in a cost-effective manner. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

AIRBORNE MICROORGANISMS IN BROILER PROCESSING PLANTS.

Science.gov (United States)

KOTULA, A W; KINNER, J A

1964-05-01

Concentrations of total aerobic bacteria, molds, yeasts, coliforms, enterococci, and psychrophiles were determined in the air of two poultry processing plants with Andersen samplers and a mobile power supply. Total aerobic bacterial counts were highest in the dressing room, with diminishing numbers in the shackling, eviscerating, and holding rooms, when sampling was carried out during plant operation. The average counts per ft(3) of air in these four rooms were 2,200; 560; 230; and 62, respectively. (Each value is the average of 36 observations.) The number of organisms increased in the shackling and dressing rooms once processing was begun. Average total aerobic bacterial counts increased from 70 to 870 to 3,000 in the shackling room and from 310 to 4,900 to 7,000 in the dressing room when sampling was carried out at 5:00 am (before plant operations), 9:00 am, and 2:00 pm, respectively. (Each value is the mean of 12 observations.) Airborne molds might originate from a source other than the poultry being processed.

Conceptual design study and evaluation of an advanced treatment process applying a submerged combustion technique for spent solvents

International Nuclear Information System (INIS)

Uchiyama, Gunzo; Maeda, Mitsuru; Fijine, Sachio; Chida, Mitsuhisa; Kirishima, Kenji.

1993-10-01

An advanced treatment process based on a submerged combustion technique was proposed for spent solvents and the distillation residues containing transuranium (TRU) nuclides. A conceptual design study and the preliminary cost estimation of the treatment facility applying the process were conducted. Based on the results of the study, the process evaluation on the technical features, such as safety, volume reduction of TRU waste and economics was carried out. The key requirements for practical use were also summarized. It was shown that the process had the features as follows: the simplified treatment and solidification steps will not generate secondary aqueous wastes, the volume of TRU solid waste will be reduced less than one tenth of that of a reference technique (pyrolysis process), and the facility construction cost is less than 1 % of the total construction cost of a future large scale reprocessing plant. As for the low level wastes of calcium phosphate, it was shown that the further removal of β · γ nuclides with TRU nuclides from the wastes would be required for the safety in interim storage and transportation and for the load of shielding. (author)

Laser-based analytical monitoring in nuclear-fuel processing plants

International Nuclear Information System (INIS)

Hohimer, J.P.

1978-09-01

The use of laser-based analytical methods in nuclear-fuel processing plants is considered. The species and locations for accountability, process control, and effluent control measurements in the Coprocessing, Thorex, and reference Purex fuel processing operations are identified and the conventional analytical methods used for these measurements are summarized. The laser analytical methods based upon Raman, absorption, fluorescence, and nonlinear spectroscopy are reviewed and evaluated for their use in fuel processing plants. After a comparison of the capabilities of the laser-based and conventional analytical methods, the promising areas of application of the laser-based methods in fuel processing plants are identified

Improvements to a uranium solidification process by in-plant testing

International Nuclear Information System (INIS)

Rindfleisch, J.A.

1984-01-01

When a process is having operational or equipment problems, often there is not enough time or money available for an extensive pilot plant program. This is when in-plant testing becomes imperative. One such process at the Idaho Chemical Processing Plant (ICPP) to undergo such an in-plant testing program was the uranium product solidification (denitrator) system. The testing program took approximately six months of in-plant testing that would have required at least two years of pilot plant preparation and operation to obtain the same information. This paper describes the results of the testing program, and the equipment and procedural changes

Alarm-Processing in Nuclear Power Plants

International Nuclear Information System (INIS)

Otazo, J; Fernandez, R

2000-01-01

Information overload due to the activation of a great number of alarms in a short time is a common problem for the operator in the control room of a industrial plant, mainly in complex process like the nuclear power plants.The problem is the conventional conception of the alarm system, that defines each alarm like a separated and independent entity of the global situation of the plant.A direct consequence is the generation of multiple alarms during a significative disturbance in the process, being most of them redundant and irrelevant to the actual process state wich involves an extra load to the operator, who wastes time in acting selecting the important alarms of the group that appears or lead to a an erroneous action.The present work first describes the techniques developed in the last years to attack the avalanche of alarms problem.Later we present our approach to alarm-processing: an expert system as alarm-filter.Our objective is collect in the system the state of the art in the development of advanced alarm systems, offering an improvement of the information flow to the operators through the suppression of nonsignificant alarms and a structured visualization of the process state.Such support is important during a disturbance for the identification of plant state, diagnosis, consequence prediction and corrective actions.The system is arranged in three stages: alarm-generation, alarm-filter and alarm-presentation.The alarm-generation uses conventional techniques or receives them from an external system.The alarm-filter uses suppression techniques based on: irrelevance analysis with the operation mode and the state of components, causal reasoning and static importance analysis.The alarm presentation is made through a structured way using a priority scheme with three level.The knowledge representation of each alarm is based on frames and a graph of alarms for global knowledge, where the connections between nodes represent causal and irrelevance relations

New plant improves radwaste processing at the Tokai-2 BWR

International Nuclear Information System (INIS)

Anon.

1988-01-01

New plant for radiowaste processing at the Tokaj-2 NPP, put in operation in September, 1986, is described. The plant includes five systems providing processing of drianage water, solid waste combustion, decrease of volume and solidification of concentrated wastes, waste storage and flushing water processing. Pressed tablets represent the final product of the waste processing. New plant enables to reduce sufficiently the volume of radioactive wastes

New Process Controls for the Hera Cryogenic Plant

Science.gov (United States)

Böckmann, T.; Clausen, M.; Gerke, Chr.; Prüß, K.; Schoeneburg, B.; Urbschat, P.

2010-04-01

The cryogenic plant built for the HERA accelerator at DESY in Hamburg (Germany) is now in operation for more than two decades. The commercial process control system for the cryogenic plant is in operation for the same time period. Ever since the operator stations, the control network and the CPU boards in the process controllers went through several upgrade stages. Only the centralized Input/Output system was kept unchanged. Many components have been running beyond the expected lifetime. The control system for one at the three parts of the cryogenic plant has been replaced recently by a distributed I/O system. The I/O nodes are connected to several Profibus-DP field busses. Profibus provides the infrastructure to attach intelligent sensors and actuators directly to the process controllers which run the open source process control software EPICS. This paper describes the modification process on all levels from cabling through I/O configuration, the process control software up to the operator displays.

Dose Assurance in Radiation Processing Plants

DEFF Research Database (Denmark)

Miller, Arne; Chadwick, K.H.; Nam, J.W.

1983-01-01

Radiation processing relies to a large extent on dosimetry as control of proper operation. This applies in particular to radiation sterilization of medical products and food treatment, but also during development of any other process. The assurance that proper dosimetry is performed...... at the radiation processing plant can be obtained through the mediation of an international organization, and the IAEA is now implementing a dose assurance service for industrial radiation processing....

Transuranium element toxicity: dose-response relationships at low exposure levels. Summary and speculative interpretation relative to exposure limits

International Nuclear Information System (INIS)

Thompson, R.C.

1975-01-01

A summary is given of information on transuranium element toxicity and the correlation of this information with current established exposure limits. It is difficult to calculate a biologically relevant radiation dose from deposited plutonium; it is exposure that must be controlled in order to prevent biological effect, and if the relationship between exposure and effect is known, then radiation dose is of no concern. There are extensive data on the effects of plutonium in bone. Results of studies at the University of Utah indicate that plutonium in beagles may be as much as ten times more toxic than radium. It has been suggested that this toxicity ratio may be even higher in man than in the beagle dog because of differences in surface-to-volume ratios and differences in the rate of burial of surface-deposited plutonium. The present capabilities for extrapolating dose-effect relationships seem to be limited to the setting of upper limits, based on assumptions of linearity and considerations related to natural background

Design and installation of high-temperature ultrasonic measuring system and grinder for nuclear fuel containing trans-uranium elements

International Nuclear Information System (INIS)

Serizawa, Hiroyuki; Kikuchi, Hironobu; Iwai, Takashi; Arai, Yasuo; Kurosawa, Makoto; Mimura, Hideaki; Abe, Jiro

2005-07-01

A high-temperature ultrasonic measuring system had been designed and installed in a glovebox (711-DGB) to study a mechanical property of nuclear fuel containing trans-uranium (TRU) elements. A figuration apparatus for the cylinder-type sample preparation had also been modified and installed in an established glovebox (142-D). The system consists of an ultrasonic probe, a heating furnace, cooling water-circulating system, a cooling air compressor, vacuum system, gas supplying system and control system. An A/D converter board and an pulsar/receiver board for the measurement of wave velocity were installed in a personal computer. The apparatus was modified to install into the glovebox. Some safety functions were supplied to the control system. The shape and size of the sample was revised to minimize the amount of TRU elements for the use of the measurement. The maximum sample temperature is 1500degC. The performance of the installed apparatuses and the glovebox were confirmed through a series of tests. (author)

Modification of the processes of resorption of alpha-emitting nuclides from gastrointestinal tract depending of the properties of the compounds administered and the physiological status of rats

International Nuclear Information System (INIS)

Zalikin, G.A.; Moskalev, Yu.I.; Nisimov, P.G.; Romanova, I.B.

1986-01-01

In experiments on rats a study was made of resorption from the gastrointestinal tract of simple salts, complex compounds and ''biologically incorporated'' forms of transuranium nuclides, the influence of age, pregnancy and chemically active substances (for instance, trivalent iron and ethyl alcohol) on this process

Screen-based process control in nuclear plants

International Nuclear Information System (INIS)

Hinz, W.; Arnoldt, C.; Hessler, C.

1993-01-01

Requirements, development and conceptual design of a screen-based control room for nuclear power plants are outlined. The control room consists of three or four equally equipped operator workstations comprising screens for process information and manual process control. A plant overview will assist the coordination among the operators. A safety classified backup system (safety control area) is provided to cover postulated failures of the control means. Some aspects of ergonomical validation and of future development trends are discussed. (orig.) [de

A study on the criticality search of transuranium recycling BWR core by adjusting supplied fuel composition in equilibrium state

International Nuclear Information System (INIS)

Seino, Takeshi; Sekimoto, Hiroshi

1998-01-01

There have been some difficulties in carrying out an extensive evaluation of the equilibrium state of Light Water Reactor (LWR) recycling operations keeping their fixed criticality condition using conventional design codes because of the complexity of their calculation model for practical fuel and core design and because of a large amount of calculation time. This study presents an efficient approach to secure the criticality in an equilibrium cycle by adjusting a supplied fuel composition. The criticality search is performed by the use of fuel importance obtained from the equation adjoint to a continuously fuel supplied core burnup equation. Using this method, some numerical analyses were carried out in order to evaluate the mixed oxide (MOX) fuel composition of equilibrium Boiling Water Reactor (BWR) cores satisfying the criticality requirement. The results showed the comprehensive and quantitative characteristics on the equilibrium cores confining transuraniums for different MOX fuel loading fractions and irradiating conditions

Process monitoring for reprocessing plant safeguards: a summary review

International Nuclear Information System (INIS)

Kerr, H.T.; Ehinger, M.H.; Wachter, J.W.; Hebble, T.L.

1986-10-01

Process monitoring is a term typically associated with a detailed look at plant operating data to determine plant status. Process monitoring has been generally associated with operational control of plant processes. Recently, process monitoring has been given new attention for a possible role in international safeguards. International Safeguards Project Office (ISPO) Task C.59 has the goal to identify specific roles for process monitoring in international safeguards. As the preliminary effort associated with this task, a review of previous efforts in process monitoring for safeguards was conducted. Previous efforts mentioned concepts and a few specific applications. None were comprehensive in addressing all aspects of a process monitoring application for safeguards. This report summarizes the basic elements that must be developed in a comprehensive process monitoring application for safeguards. It then summarizes the significant efforts that have been documented in the literature with respect to the basic elements that were addressed

Future of robots in nuclear plants and processes

International Nuclear Information System (INIS)

Fisher, J.J.; Byrd, J.S.

1985-01-01

The role of robotics at the Savannah River Plant and Laboratory is reviewed. The site's remote process areas are described briefly, and existing remote handling equipment and robots are discussed. Three technology areas under development and relating to process automation are reviewed. These are: inspection systems to detect and evaluate process problems or to determine equipment integrity, process monitoring systems to analyze plant operations and to supply information in the event of an unusual occurrence, and remote manipulator systems and controls to handle instruments and tools. A technique is presented for employing future intelligent robots through process networks. These networks will represent the integration of robotic technology with dedicated process knowledge bases

Fissile material holdup monitoring in the PREPP [Process Experimental Pilot Plant] process

International Nuclear Information System (INIS)

Becker, G.K.; Pawelko, R.J.

1989-01-01

The Process Experimental Pilot Plant (PREPP) is an incineration system designed to thermally process mixed transuranic (TRU) waste and TRU contaminated low-level waste. The TRU isotopic composition is that of weapons grade plutonium (Pu) which necessitates that criticality prevention measures by incorporated into the plant design and operation. Criticality safety in the PREPP process is assured through the utilization of mass and moderation control in conjunction with favorable vessel geometries. The subject of this paper concerns the Pu mass holdup instrumentation system which is an integral part of the inprocess mass control strategy. Plant vessels and components requiring real-time mass holdup measurements were selected based on their evaluated potential for achieving physically credible Pu mass loadings and associated parameters which could lead to a criticality event. If the parameters requisite to a criticality occurrence could not physically be achieved under credible plant conditions, the particular location only required periodic portable holdup monitoring. Based on these analyses five real-time holdup monitoring locations were identified for criticality assurance purposes. An additional real-time instrument is part of the system but serves primarily in the capacity of providing operational support data. 1 fig

Crosstalk between endophytes and a plant host within information-processing networks

Directory of Open Access Journals (Sweden)

Kozyrovska N. O.

2013-05-01

Full Text Available Plants are heavily populated by pro- and eukaryotic microorganisms and represent therefore the tremendous complexity as a biological system. This system exists as an information-processing entity with rather complex processes of communication, occurring throughout the individual plant. The plant cellular information-proces- sing network constitutes the foundation for processes like growth, defense, and adaptation to the environment. Up to date, the molecular mechanisms, underlying perception, transfer, analysis, and storage of the endogenous and environmental information within the plant, remain to be fully understood. The associated microorganisms and their investment in the information conditioning are often ignored. Endophytes as plant partners are indispen- sable integrative part of the plant system. Diverse endophytic microorganisms comprise «normal» microbiota that plays a role in plant immunity and helps the plant system to survive in the environment (providing assistance in defense, nutrition, detoxification etc.. The role of endophytic microbiota in the processing of information may be presumed, taking into account a plant-microbial co-evolution and empirical data. Since the literature are be- ginning to emerge on this topic, in this article, I review key works in the field of plant-endophytes interactions in the context of information processing and represent the opinion on their putative role in plant information web under defense and the adaptation to changed conditions.

Data processing software for purex plant process control laboratory

International Nuclear Information System (INIS)

Kansara, V.P.; Achuthan, P.V.; Sridhar, S.; Ramanujam, A.; Dhumwad, R.K.

1990-01-01

A software has been developed at the Fuel Reprocessing Division, Trombay to meet the data processing needs of the Control Laboratory of a reprocessing plant. During the normal plant operations contents of over one hundred process tanks have to be sampled and analysed for regular monitoring. In order to speed up the computation and the reporting of results as well as to obtain the process performance data over a period of time a software has been developed. The package has been sucessfully demonstrated and implemented at the Plutonium Plant, Trombay. This has been in continuous use since May 1987 with highly satisfactory performance. The software is a totally menu-driven package which can be used by the laboratory analysts with a few hours of training. The features include data validation involving source tank identification, the nature of the sample, the range of expected results, any duplication in sample numbering etc. Audio indication of deviations from the expected input or output values are given with an option to override in case of abnormal samples. The progress of analysis can be obtained for a given sample at any given time. Incorporated in the software is the help menu for quick reference of analytical protocol to be followed for a given tank/method. The computations for the determinations are carried out after obtaining input values on a screen-form. Th e results can be displayed on the monitor or obtained in the form of a hard copy i n any desired format. (author). 17 figs., 2 refs

A study on the criticality search of transuranium recycling BWR core by adjusting supplied fuel composition in equilibrium state

International Nuclear Information System (INIS)

Seino, Takeshi; Sekimoto, Hiroshi

1997-01-01

There have been some difficulties in carrying out an extensive evaluation of the equilibrium state of Light Water Reactor (LWR) recycling operations keeping their fixed criticality condition using conventional design codes, because of the complexity of their calculational model for practical fuel and core design and because of a large amount of calculation time. This study presents an efficient approach to secure the criticality in an equilibrium cycle by adjusting a supplied fuel composition. The criticality search is performed by the use of fuel importance obtained from the equilibrium adjoint to a continuously fuel supplied core burnup equation. Using this method, some numerical analyses were carried out in order to evaluate the mixed oxide (MOX) fuel composition of equilibrium Boiling Water Reactor (BWR) cores satisfying the criticality requirement. The results showed the comprehensive and quantitative characteristics on the equilibrium cores confining transuranium for different MOX fuel loading fractions and irradiating conditions. (author)

A survey of process control computers at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Dahl, C.A.

1989-01-01

The Idaho Chemical Processing Plant (ICPP) at the Idaho National Engineering Laboratory is charged with the safe processing of spent nuclear fuel elements for the United States Department of Energy. The ICPP was originally constructed in the late 1950s and used state-of-the-art technology for process control at that time. The state of process control instrumentation at the ICPP has steadily improved to keep pace with emerging technology. Today, the ICPP is a college of emerging computer technology in process control with some systems as simple as standalone measurement computers while others are state-of-the-art distributed control systems controlling the operations in an entire facility within the plant. The ICPP has made maximal use of process computer technology aimed at increasing surety, safety, and efficiency of the process operations. Many benefits have been derived from the use of the computers for minimal costs, including decreased misoperations in the facility, and more benefits are expected in the future

Electronic data processing codes for California wildland plants

Science.gov (United States)

Merton J. Reed; W. Robert Powell; Bur S. Bal

1963-01-01

Systematized codes for plant names are helpful to a wide variety of workers who must record the identity of plants in the field. We have developed such codes for a majority of the vascular plants encountered on California wildlands and have published the codes in pocket size, using photo-reductions of the output from data processing machines. A limited number of the...

AI-based alarm processing for a nuclear power plant

International Nuclear Information System (INIS)

Na, N.J.; Kim, I.S.; Hwang, I.K.; Lee, D.Y.; Ham, C.S.

1996-01-01

A real-time expert system is implemented using artificial intelligence and object-oriented technology for alarm processing and presentation in a nuclear power plant. The knowledge base is constructed based on some schemes to process and display alarms to the plant operators. The activated alarms are dynamically prioritized by the reasoning rules, and then, presented on the process mimic overview and by some other means. To demonstrate the proposed system, the alarm processing and presentation is carried out in a simulated environment of the TMI-2 accident

Idaho Chemical Processing Plant Process Efficiency improvements

International Nuclear Information System (INIS)

Griebenow, B.

1996-03-01

In response to decreasing funding levels available to support activities at the Idaho Chemical Processing Plant (ICPP) and a desire to be cost competitive, the Department of Energy Idaho Operations Office (DOE-ID) and Lockheed Idaho Technologies Company have increased their emphasis on cost-saving measures. The ICPP Effectiveness Improvement Initiative involves many activities to improve cost effectiveness and competitiveness. This report documents the methodology and results of one of those cost cutting measures, the Process Efficiency Improvement Activity. The Process Efficiency Improvement Activity performed a systematic review of major work processes at the ICPP to increase productivity and to identify nonvalue-added requirements. A two-phase approach was selected for the activity to allow for near-term implementation of relatively easy process modifications in the first phase while obtaining long-term continuous improvement in the second phase and beyond. Phase I of the initiative included a concentrated review of processes that had a high potential for cost savings with the intent of realizing savings in Fiscal Year 1996 (FY-96.) Phase II consists of implementing long-term strategies too complex for Phase I implementation and evaluation of processes not targeted for Phase I review. The Phase II effort is targeted for realizing cost savings in FY-97 and beyond

The Assessment of Radioactive Liquid Waste Treatment Generated From The Fuel Reprocessing Plant Using Chemical Coagulation Method

International Nuclear Information System (INIS)

Kuncoro Arief, H; M Birmano, Dj

1998-01-01

Reprocessing of nuclear spent fuel produced 8 lot of radioactive liquid waste still bearing uranium and transuranium. The assessment of the radioactive liquid waste treatment with FeCI 3 as coagulant has been done. Decontamination factor and separation efficiency can be calculated from known activities of initial and post-treatment wastes. It can be concluded that some factors i.e. pH of treatment process, quantity of coagulant, mixing rate, and mixing time have influenced the treatment product

Vacuolar processing enzyme: an executor of plant cell death.

Science.gov (United States)

Hara-Nishimura, Ikuko; Hatsugai, Noriyuki; Nakaune, Satoru; Kuroyanagi, Miwa; Nishimura, Mikio

2005-08-01

Apoptotic cell death in animals is regulated by cysteine proteinases called caspases. Recently, vacuolar processing enzyme (VPE) was identified as a plant caspase. VPE deficiency prevents cell death during hypersensitive response and cell death of limited cell layers at the early stage of embryogenesis. Because plants do not have macrophages, dying cells must degrade their materials by themselves. VPE plays an essential role in the regulation of the lytic system of plants during the processes of defense and development. VPE is localized in the vacuoles, unlike animal caspases, which are localized in the cytosol. Thus, plants might have evolved a regulated cellular suicide strategy that, unlike animal apoptosis, is mediated by VPE and the vacuoles.

Plant extraction process

DEFF Research Database (Denmark)

2006-01-01

A method for producing a plant extract comprises incubating a plant material with an enzyme composition comprising a lipolytic enzyme.......A method for producing a plant extract comprises incubating a plant material with an enzyme composition comprising a lipolytic enzyme....

Extraction of deuterium from D-rich process condensate of ammonia plants

Energy Technology Data Exchange (ETDEWEB)

Haldar, T K; Kumar, Manoj; Ramamurty, C B [Heavy Water Board, Department of Atomic Energy, Mumbai (India)

1994-06-01

Heavy water plants based on ammonia-hydrogen exchange process receives feed synthesis gas from the adjacent fertilizer plants. The production capacity of such heavy water plants is directly proportional to the deuterium-content in feed synthesis gas. The chemical process involved in gas generation section of the fertilizer plant includes catalytic steam-reforming of natural gas/naphtha/fuel oil followed by shift conversion, alternatively coal classification followed by shift conversion. Effective extraction of deuterium from the deuterium-rich process condensate can boost the production capacity of heavy water plants considerably. This paper discusses various possible methods to achieve this objective. (author). 5 refs., 1 fig., 1 tab.

Plant process computer replacements - techniques to limit installation schedules and costs

International Nuclear Information System (INIS)

Baker, M.D.; Olson, J.L.

1992-01-01

Plant process computer systems, a standard fixture in all nuclear power plants, are used to monitor and display important plant process parameters. Scanning thousands of field sensors and alarming out-of-limit values, these computer systems are heavily relied on by control room operators. The original nuclear steam supply system (NSSS) vendor for the power plant often supplied the plant process computer. Designed using sixties and seventies technology, a plant's original process computer has been obsolete for some time. Driven by increased maintenance costs and new US Nuclear Regulatory Commission regulations such as NUREG-0737, Suppl. 1, many utilities have replaced their process computers with more modern computer systems. Given that computer systems are by their nature prone to rapid obsolescence, this replacement cycle will likely repeat. A process computer replacement project can be a significant capital expenditure and must be performed during a scheduled refueling outage. The object of the installation process is to install a working system on schedule. Experience gained by supervising several computer replacement installations has taught lessons that, if applied, will shorten the schedule and limit the risk of costly delays. Examples illustrating this technique are given. This paper and these examples deal only with the installation process and assume that the replacement computer system has been adequately designed, and development and factory tested

Study of CO2 capture processes in power plants

International Nuclear Information System (INIS)

Amann, J.M.

2007-12-01

The aim of the present study is to assess and compare various processes aiming at recover CO 2 from power plants fed with natural gas (NGCC) and pulverized coal (PC). These processes are post-combustion CO 2 capture using chemical solvents, natural gas reforming for pre-combustion capture by methanol and oxy-fuel combustion with cryogenic recovery of CO 2 . These processes were evaluated using the process software Aspen PlusTM to give some clues for choosing the best option for each type of power plant. With regard to post-combustion, an aqueous solution based on a mixture of amines (N-methyldiethanolamine (MDEA) and triethylene tetramine (TETA)) was developed. Measurements of absorption were carried out between 298 and 333 K in a Lewis cell. CO 2 partial pressure at equilibrium, characteristic of the CO 2 solubility in the solvent, was determined up to 393 K. The solvent performances were compared with respect to more conventional solvents such as MDEA and monoethanolamine (MEA). For oxy-fuel combustion, a recovery process, based on a cryogenic separation of the components of the flue gas, was developed and applied to power plants. The study showed that O 2 purity acts on the CO 2 concentration in the flue gas and thus on the performances of the recovery process. The last option is natural gas reforming with CO 2 pre-combustion capture. Several configurations were assessed: air reforming and oxygen reforming, reforming pressure and dilution of the synthesis gas. The comparison of these various concepts suggests that, in the short and medium term, chemical absorption is the most interesting process for NGCC power plants. For CP power plants, oxy-combustion can be a very interesting option, as well as post-combustion capture by chemical solvents. (author)

Integration of distributed plant process computer systems to nuclear power generation facilities

International Nuclear Information System (INIS)

Bogard, T.; Finlay, K.

1996-01-01

Many operating nuclear power generation facilities are replacing their plant process computer. Such replacement projects are driven by equipment obsolescence issues and associated objectives to improve plant operability, increase plant information access, improve man machine interface characteristics, and reduce operation and maintenance costs. This paper describes a few recently completed and on-going replacement projects with emphasis upon the application integrated distributed plant process computer systems. By presenting a few recent projects, the variations of distributed systems design show how various configurations can address needs for flexibility, open architecture, and integration of technological advancements in instrumentation and control technology. Architectural considerations for optimal integration of the plant process computer and plant process instrumentation ampersand control are evident from variations of design features

Basic TRUEX process for Rocky Flats Plant

International Nuclear Information System (INIS)

Leonard, R.A.; Chamberlain, D.B.; Dow, J.A.; Farley, S.E.; Nunez, L.; Regalbuto, M.C.; Vandegrift, G.F.

1994-08-01

The Generic TRUEX Model was used to develop a TRUEX process flowsheet for recovering the transuranics (Pu, Am) from a nitrate waste stream at Rocky Flats Plant. The process was designed so that it is relatively insensitive to changes in process feed concentrations and flow rates. Related issues are considered, including solvent losses, feed analysis requirements, safety, and interaction with an evaporator system for nitric acid recycle

Maturation processes and structures of small secreted peptides in plants

Directory of Open Access Journals (Sweden)

Ryo eTabata

2014-07-01

Full Text Available In the past decade, small secreted peptides have proven to be essential for various aspects of plant growth and development, including the maintenance of certain stem cell populations. Most small secreted peptides identified in plants to date are recognised by membrane-localized receptor kinases, the largest family of receptor proteins in the plant genome. This peptide-receptor interaction is essential for initiating intracellular signalling cascades. Small secreted peptides often undergo post-translational modifications and proteolytic processing to generate the mature peptides. Recent studies suggest that, in contrast to the situation in mammals, the proteolytic processing of plant peptides involves a number of complex steps. Furthermore, NMR-based structural analysis demonstrated that post-translational modifications induce the conformational changes needed for full activity. In this mini review, we summarise recent advances in our understanding of how small secreted peptides are modified and processed into biologically active peptides and describe the mature structures of small secreted peptides in plants.

Plants in constructed wetlands help to treat agricultural processing wastewater

Directory of Open Access Journals (Sweden)

Mark Grismer

2008-05-01

Full Text Available Over the past three decades, wineries in the western United States and sugarcane processing for ethanol in Central and South America have experienced problems related to the treatment and disposal of process wastewater. Both winery and sugarcane (molasses wastewaters are characterized by large organic loadings that change seasonally and are detrimental to aquatic life. We examined the role of plants for treating these wastewaters in constructed wetlands. In the greenhouse, subsurface-flow flumes with volcanic rock substrates and plants steadily removed approximately 80% of organic-loading oxygen demand from sugarcane process wastewater after about 3 weeks of plant growth; unplanted flumes removed about 30% less. In field studies at two operational wineries, we evaluated the performance of similar-sized, paired, subsurface constructed wetlands with and without plants; while both removed most of the oxygen demand, removal rates in the planted system were slightly greater and significantly different from those of the unplanted system under field conditions.

Springfield Processing Plant (SPP) Facility Information

Energy Technology Data Exchange (ETDEWEB)

Leach, Janice; Torres, Teresa M.

2012-10-01

The Springfield Processing Plant is a hypothetical facility. It has been constructed for use in training workshops. Information is provided about the facility and its surroundings, particularly security-related aspects such as target identification, threat data, entry control, and response force data.

Pre-engineering assessment of Enersolve Demonstration Project. Dairy processing plant. Final report

Energy Technology Data Exchange (ETDEWEB)

1985-07-15

This study involved evaluation of a dairy processing plant to demonstrate energy conservation potential and developing a strategy to realize energy savings through retrofitting and revamping. The cheese and whey making plant of Agropur Cooperative Agro-Alimentaire located in Quebec was selected as a representative Canadian dairy processing plant. The pre-engineering assessment included a review of existing facility at the plant and plant operation, identification of plant equipment or process steps where substantial economic benefits would result from retrofitting and revamping, and estimation of budgetary cost for the subsequent engineering, procurement, construction management and monitoring of the retrofitted equipment. 3 figs., 2 tabs.

Establishing error management process for power plants. A study on entire picture of the process and introduction stages

International Nuclear Information System (INIS)

Hirotsu, Yuko; Fujimoto, Junzo; Sugihara, Yoshikuni; Takeda, Daisuke

2009-01-01

The purpose of this study is to establish a management process for a power plant to positively find out actual and/or potential problems that may possibility cause a serious human factor event, and to take effective measures. Firstly, detail steps for error management process utilizing human factor event data has been examined through an application at a plant. Secondly, basic steps for evaluating the degree of execution, enhancement and usefulness of each human performance activity and for identifying unsafe acts and uneasy human performance states were established based on literature searching and our experiences on plant evaluation. Finally, an entire picture of error management process was proposed by unifying the steps studied above. In addition, as stages for introducing and establishing the above proposed error management process into a power plant, a basic idea of supplementing an insufficient part of the process with a phased approach after comparing the above proposed management process and the existing human performance activities at the plant was introduced. (author)

Thermodynamic analysis applied to a food-processing plant

Energy Technology Data Exchange (ETDEWEB)

Ho, J C; Chandratilleke, T T

1987-01-01

Two production lines of a multi-product, food-processing plant are selected for energy auditing and analysis. Thermodynamic analysis showed that the first-law and second-law efficiencies are 81.5% and 26.1% for the instant-noodles line and 23.6% and 7.9% for the malt-beverage line. These efficiency values are dictated primarily by the major energy-consuming sub-processes of each production line. Improvements in both first-law and second-law efficiencies are possible for the plants if the use of steam for heating is replaced by gaseous or liquid fuels, the steam ejectors for creating vacuum are replaced by a mechanical pump, and employing the cooler surroundings to assist in the cooling process.

Industrial applications for remote operation in a processing plant

International Nuclear Information System (INIS)

Hermier, J.; Le Guennec, R.

1984-01-01

In the first part of this article, J. Hermier covers the use of remote handling equipment in the UP2-400 plant at La Hague near Cherbourg, in which for the most part master/slave mechanism remote handling units are used with a number of these employed in daily processing operations. As regards this subject, it is useful to remember that, at the time of the designing of this plant (UP2-400), this was the only equipment available on the market with remote-controlled remote handling equipment. In the second part, before speaking about the development of remote operation equipment in the plants now under construction and attempting to project what might be the remote operation role in future plants, R. Le Guennec reviews the problems faced by engineering in designing industrial-sized processing plants and, consequently, the motivations of engineering when faced with a choice between several possible solutions [fr

Ranstad - A new uranium-processing plant

Energy Technology Data Exchange (ETDEWEB)

Peterson, A [AB Atomenergi, Stockholm (Sweden)

1967-06-15

A short outline is given of the decisions concerning the erection and operation of the Ranstad mill which was recently taken into operation. It is followed by a brief description of the geological conditions and the planning of the mining system, plant location, and the factory. The main part of the paper describes processes and equipment of the plant which has a capacity to treat approx. 850 000 tons of low-grade ore (alum shale) per year. The operational experience so far is also reviewed. The economy of uranium production at Ranstad is discussed and some development possibilities are indicated. (author)

Proposals for setting possible limits on intake of transuranium radionuclides absorbed from the gastrointestinal tract

International Nuclear Information System (INIS)

Zalikin, G.A.; Nisimov, P.G.

1987-01-01

The absorption of transuranium elements ( 238 Pu, 241 Am, 252 Cf) from the gastrointestinal (GI) tract as influenced by physiological factors (e.g. age) and physical and chemical properties of compounds incorporated has been studied in 600 white mongrel rats. Average values of absorption have been determined for simple salts and a complex citrate. A number of factors increasing absorption have been found. Thus, originally bound compounds contained in the meat of animals incorporated with 238 Pu and 241 Am when alive, 241 Am-containing potato juice and green oat stalks enhanced absorption by a factor of 5 to 30 as compared with an adequate control. Ethanol administered orally as a 20% solution increased the absorption of americium nitrate by 60% and that of citrate by 23%. Oral administratio of 241 Am nitrate solution together with ferric chloride changes the metabolic kinetics of the nuclide completely. The total absorption of americium from DI tract is 7.1 times that of the control, but a considerable fraction absorbed into blood is excreted with urine (4.2% over 8 days). Among physiological factors age effects the absorption of transuranics from the GI tract to acertain degree. The absorption of 252 Cf in 7 day-old young rats proves to be 8.1 times that of adults. Gestation brought about a 2.7 fold increase of 241 Am absorption

IMPROVING TACONITE PROCESSING PLANT EFFICIENCY BY COMPUTER SIMULATION, Final Report

Energy Technology Data Exchange (ETDEWEB)

William M. Bond; Salih Ersayin

2007-03-30

This project involved industrial scale testing of a mineral processing simulator to improve the efficiency of a taconite processing plant, namely the Minorca mine. The Concentrator Modeling Center at the Coleraine Minerals Research Laboratory, University of Minnesota Duluth, enhanced the capabilities of available software, Usim Pac, by developing mathematical models needed for accurate simulation of taconite plants. This project provided funding for this technology to prove itself in the industrial environment. As the first step, data representing existing plant conditions were collected by sampling and sample analysis. Data were then balanced and provided a basis for assessing the efficiency of individual devices and the plant, and also for performing simulations aimed at improving plant efficiency. Performance evaluation served as a guide in developing alternative process strategies for more efficient production. A large number of computer simulations were then performed to quantify the benefits and effects of implementing these alternative schemes. Modification of makeup ball size was selected as the most feasible option for the target performance improvement. This was combined with replacement of existing hydrocyclones with more efficient ones. After plant implementation of these modifications, plant sampling surveys were carried out to validate findings of the simulation-based study. Plant data showed very good agreement with the simulated data, confirming results of simulation. After the implementation of modifications in the plant, several upstream bottlenecks became visible. Despite these bottlenecks limiting full capacity, concentrator energy improvement of 7% was obtained. Further improvements in energy efficiency are expected in the near future. The success of this project demonstrated the feasibility of a simulation-based approach. Currently, the Center provides simulation-based service to all the iron ore mining companies operating in northern

Process plant alarm diagnosis using synthesised fault tree knowledge

International Nuclear Information System (INIS)

Trenchard, A.J.

1990-01-01

The development of computer based tools, to assist process plant operators in their task of fault/alarm diagnosis, has received much attention over the last twenty five years. More recently, with the emergence of Artificial Intelligence (AI) technology, the research activity in this subject area has heightened. As a result, there are a great variety of fault diagnosis methodologies, using many different approaches to represent the fault propagation behaviour of process plant. These range in complexity from steady state quantitative models to more abstract definitions of the relationships between process alarms. Unfortunately, very few of the techniques have been tried and tested on process plant and even fewer have been judged to be commercial successes. One of the outstanding problems still remains the time and effort required to understand and model the fault propagation behaviour of each considered process. This thesis describes the development of an experimental knowledge based system (KBS) to diagnose process plant faults, as indicated by process variable alarms. In an attempt to minimise the modelling effort, the KBS has been designed to infer diagnoses using a fault tree representation of the process behaviour, generated using an existing fault tree synthesis package (FAULTFINDER). The process is described to FAULTFINDER as a configuration of unit models, derived from a standard model library or by tailoring existing models. The resultant alarm diagnosis methodology appears to work well for hard (non-rectifying) faults, but is likely to be less robust when attempting to diagnose intermittent faults and transient behaviour. The synthesised fault trees were found to contain the bulk of the information required for the diagnostic task, however, this needed to be augmented with extra information in certain circumstances. (author)

The pilot plant for electron beam food processing

Science.gov (United States)

Migdal, W.; Walis, L.; Chmielewski, A. G.

1993-07-01

In the frames of the national programme on the application of irradiation for food preservation and hygienization an experimental plant for electron beam processing has been established in INCT. The pilot plant has been constructed inside an old fort what decreases significantly the cost of the investment. The pilot plant is equipped with a small research accelerator Pilot (10 MeV, 1 kW) and an industrial unit Elektronika (10 MeV, 10 kW). This allows both laboratory and full technological scale testing of the elaborated process to be conducted. The industrial unit is being equipped with e-/X conversion target, for high density products irradiation. On the basis of the research there were performed at different scientific institutions in Poland, health authorities have issued permissions for permanent treatment of spices, garlic, onions and temporary permissions for mushrooms, and potatoes. Dosimetric methods have been elaborated for the routine use at the plant. In the INCT laboratory methods for the control of e-/X treated food have been established.

The pilot plant for electron beam food processing

International Nuclear Information System (INIS)

Migdal, W.; Kosmal, W.; Malec-Czechowska, K.; Maciszewski, W.

1992-01-01

In the frames of the national programme on the application of irradiation for food preservation and hygienization an experimental plant for electron beam processing has been established in INCT. The pilot plant has been constructed inside an old fort what decreases significantly the cost of the investment. The pilot plants is equipped with a small research accelerator Pilot (10 MeV, 1 kW) and an industrial unit Elektronika (10 MeV, 10 kW). This allows both laboratory and full technological scale testing of the elaborated process to be conducted. The industrial unit is being equipped with e-/X conversion target, for high density products irradiation. On the basis of the research there were performed at different scientific institutions in Poland, health authorities have issued permissions for permanent treatment of spices, garlic, onions and temporary permissions for mushrooms, and potatoes. Dosimetric methods have been elaborated for the routine use at the plant. In the INCT laboratory methods for the control of e-/X treated food have been established. (author). 9 refs, 5 figs, 1 tab

Plant operator performance evaluation based on cognitive process analysis experiment

International Nuclear Information System (INIS)

Ujita, H.; Fukuda, M.

1990-01-01

This paper reports on an experiment to clarify plant operators' cognitive processes that has been performed, to improve the man-machine interface which supports their diagnoses and decisions. The cognitive processes under abnormal conditions were evaluated by protocol analyses interviews, etc. in the experiment using a plant training simulator. A cognitive process model is represented by a stochastic network, based on Rasmussen's decision making model. Each node of the network corresponds to an element of the cognitive process, such as observation, interpretation, execution, etc. Some observations were obtained as follows, by comparison of Monte Carlo simulation results with the experiment results: A process to reconfirm the plant parameters after execution of a task and feedback paths from this process to the observation and the task definition of next task were observed. The feedback probability average and standard deviation should be determined for each incident type to explain correctly the individual differences in the cognitive processes. The tendency for the operator's cognitive level to change from skill-based to knowledge-based via rule-based behavior was observed during the feedback process

Transuranium element incorporation into the β-U3O8 uranyl sheet

International Nuclear Information System (INIS)

Miller, M.L.; Burns, P.C.; Ewing, R.C.; Finch, R.J.

1997-01-01

Spent nuclear fuel (SNF) is unstable under oxidizing conditions. Although recent studies have determined the paragenetic sequence for uranium phases that result from the corrosion of SNF, there are only limited data on the potential of alteration phases for the incorporation of transuranium elements. The crystal chemical characteristics of transuranic elements (TUE) are to a certain extent similar to uranium; thus TUE incorporation into the sheets of uranyl oxide hydrate structures can be assessed by examination of the structural details of the β-U 3 O 8 sheet type. The sheets of uranyl polyhedra observed in the crystal structure of β-U 3 O 8 also occur in the mineral billietite, where they alternate with α-U 3 O 8 type sheets. Preliminary crystal structure determinations for the minerals ianthinite, and wyartite, indicate that these phases also contain β-U 3 O 8 type sheets. The β-U 3 O 8 sheet anion topology contains triangular, rhombic, and pentagonal sites in the proportions 2:1:2. In all structures containing β-U 3 O 8 type sheets, the triangular sites are vacant. The pentagonal sites are filled with U 6+ O 2 forming pentagonal bipyramids. The rhombic dipyramids filling the rhombic sites contain U 6+ O 2 in billietite, U 4+ O 2 in β-U 3 O 8 , U 4+ (H 2 O) 2 in ianthinite, and U 4+ O 3 in wyartite-II. Interlayer species include: H 2 O (billietite, wyartite II, and ianthinite), Ba 2+ (billietite) Ca 2+ wyartite II, and Co 3 2- wyartite II; there is no interlayer in β-U 3 O 8 . The similarity of known TUE coordination polyhedra with those of U suggests that the β-U 3 O 8 sheet will accommodate TUE substitution coupled with variations in apical anion configuration and interlayer population providing the required charge balance

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)

Solid municipal waste processing plants: Cost benefit analysis

International Nuclear Information System (INIS)

Gerardi, V.

1992-01-01

This paper performs cost benefit analyses on three solid municipal waste processing alternatives with plants of diverse daily outputs. The different processing schemes include: selected wastes incineration with the production of refuse derived fuels; selected wastes incineration with the production of refuse derived fuels and compost; pyrolysis with energy recovery in the form of electric power. The plant daily outputs range from 100 to 300 tonnes for the refuse derived fuel alternatives, and from 200 to 800 tonnes for the pyrolysis/power generation scheme. The cost analyses consider investment periods of fifteen years in duration and interest rates of 5%

Idaho Chemical Processing Plant and Plutonium-Uranium Extraction Plant phaseout/deactivation study

International Nuclear Information System (INIS)

Patterson, M.W.; Thompson, R.J.

1994-01-01

The decision to cease all US Department of Energy (DOE) reprocessing of nuclear fuels was made on April 28, 1992. This study provides insight into and a comparison of the management, technical, compliance, and safety strategies for deactivating the Idaho Chemical Processing Plant (ICPP) at Westinghouse Idaho Nuclear Company (WINCO) and the Westinghouse Hanford Company (WHC) Plutonium-Uranium Extraction (PUREX) Plant. The purpose of this study is to ensure that lessons-learned and future plans are coordinated between the two facilities

Determination of Properties of Selected Fresh and Processed Medicinal Plants

Directory of Open Access Journals (Sweden)

Shirley G. Cabrera

2015-11-01

Full Text Available The study aimed to determine the chemical properties, bioactive compounds, antioxidant activity and toxicity level of fresh and processed medicinal plants such as corn (Zea mays silk, pancitpancitan (Peperomiapellucida leaves, pandan (Pandanus amaryllifolius leaves, and commercially available tea. The toxicity level of the samples was measured using the Brine Shrimp Lethality Assay (BSLA. Statistical analysis was done using Statistical Package for Social Sciences (SPSS. Results showed that in terms of chemical properties there is significant difference between fresh and processed corn silk except in crude fiber content was noted. Based on proximate analyses of fresh and processed medicinal plants specifically in terms of % moisture, %crude protein and % total carbohydrates were also observed. In addition, there is also significant difference on bioactive compound contents such as total flavonoids and total phenolics between fresh and processed corn silk except in total vitamin E (TVE content. Pandan and pancit-pancitan showed significant difference in all bioactive compounds except in total antioxidant content (TAC. Fresh pancit-pancitan has the highest total phenolics content (TPC and TAC, while the fresh and processed corn silk has the lowest TAC and TVE content, respectively. Furthermore, results of BSLA for the three medicinal plants and commercially available tea extract showed after 24 hours exposure significant difference in toxicity level was observed. The percentage mortality increased with an increase in exposure time of the three medicinal plants and tea extract. The results of the study can served as baseline data for further processing and commercialization of these medicinal plants.

United States Transuranium Registry annual report October 1, 1979-October 1, 1980 to Human Health and Assessments Division, US Department of Energy

International Nuclear Information System (INIS)

Breitenstein, B.D. Jr.; Heid, K.R.; Swint, M.J.

1981-01-01

One of the primary objectives of the United States Transuranium Registry is to improve health physics models used to evaluate occupational exposure from internally deposited transuranic elements. During FY 1980 emphasis continued to be placed on improving methods for collecting data. The use of a prosector for all cases assures that autopsy tissue samples are properly identified and reasonably well cleaned. A procedure has been developed at the University of California Los Alamos Scientific Laboratory to ash tissue specimens collected as part of this program. This same method is also being utilized at the Rocky Flats Analytical laboratory. A comparison of data collected from thirteen USTR autopsy cases using wet and ashed weights was made. The results suggest that the use of ashed weights improves the agreement of the systemic burden at autopsy to that estimated using ante mortem health physics data by a factor of nearly two

Vulnerability analysis of process plants subject to domino effects

International Nuclear Information System (INIS)

Khakzad, Nima; Reniers, Genserik; Abbassi, Rouzbeh; Khan, Faisal

2016-01-01

In the context of domino effects, vulnerability analysis of chemical and process plants aims to identify and protect installations which are relatively more susceptible to damage and thus contribute more to the initiation or propagation of domino effects. In the present study, we have developed a methodology based on graph theory for domino vulnerability analysis of hazardous installations within process plants, where owning to the large number of installations or complex interdependencies, the application of sophisticated reasoning approaches such as Bayesian network is limited. We have taken advantage of a hypothetical chemical storage plant to develop the methodology and validated the results using a dynamic Bayesian network approach. The efficacy and out-performance of the developed methodology have been demonstrated via a real-life complex case study. - Highlights: • Graph theory is a reliable tool for vulnerability analysis of chemical plants as to domino effects. • All-closeness centrality score can be used to identify most vulnerable installations. • As for complex chemical plants, the methodology outperforms Bayesian network.

The Relation of Design Parameters, Plant Capacity and Processing Costs in Cobalt-60 Sterilization Plants

International Nuclear Information System (INIS)

Brown, M.G.

1967-01-01

The paper describes the main features of three basic types of cobalt-60 sterilization plants which have been designed to provide a complete range of capacities for radiosterilization of medical products. The smallest plant has a capacity of up to 50 000 cubic feet of medical products a year, the intermediate size plant has a capacity of up to 500 000 cubic feet a year, and the largest plant has a capacity in excess of 1000 000 cubic feet a year. The relations between capital costs, rate of production, efficiency and unit processing costs for each type of plant are discussed. The method of selecting the best type of plant for a particular need will also be outlined. (author)

Pinellas Plant facts. [Products, processes, laboratory facilities

Energy Technology Data Exchange (ETDEWEB)

1986-09-01

This plant was built in 1956 in response to a need for the manufacture of neutron generators, a principal component in nuclear weapons. The neutron generators consist of a miniaturized linear ion accelerator assembled with the pulsed electrical power supplies required for its operation. The ion accelerator, or neutron tube, requires ultra clean, high vacuum technology: hermetic seals between glass, ceramic, glass-ceramic, and metal materials: plus high voltage generation and measurement technology. The existence of these capabilities at the Pinellas Plant has led directly to the assignment of the lightning arrester connector, specialty capacitor, vacuum switch, and crystal resonator. Active and reserve batteries and the radioisotopically-powered thermoelectric generator draw on the materials measurement and controls technologies which are required to ensure neutron generator life. A product development and production capability in alumina ceramics, cermet (electrical) feedthroughs, and glass ceramics has become a specialty of the plant; the laboratories monitor the materials and processes used by the plant's commercial suppliers of ferroelectric ceramics. In addition to the manufacturing facility, a production development capability is maintained at the Pinellas Plant.

Financial Benefits of Process Data Reconciliation in Power Generating Plants

International Nuclear Information System (INIS)

Jansky, Andy

2006-01-01

Process Data Reconciliation (PDR) is a certified method that calculates the most likely values considering process measurement uncertainties and closing all energy- and material balances where all inter-dependencies within the entire plant process are fulfilled in a covariance matrix. There are three main factors that generate the financial benefits for the user of reconciled data, depending on the type of plant and base/peak load behaviour: Increased efficiency / maximized output, Time advantage in retrieving 'lost' megawatts, Reduction of maintenance costs. (author)

Application of Tecnomatix Plant Simulation for Modeling Production and Logistics Processes

Directory of Open Access Journals (Sweden)

Julia Siderska

2016-06-01

Full Text Available The main objective of the article was to present the possibilities and examples of using Tecnomatix Plant Simulation (by Siemens to simulate the production and logistics processes. This tool allows to simulate discrete events and create digital models of logistic systems (e.g. production, optimize the operation of production plants, production lines, as well as individual logistics processes. The review of implementations of Tecnomatix Plant Simulation for modeling processes in production engineering and logistics was conducted and a few selected examples of simulations were presented. The author’s future studies are going to focus on simulation of production and logistic processes and their optimization with the use of genetic algorithms and artificial neural networks.

Alarm processing system using AI techniques for nuclear power plant

International Nuclear Information System (INIS)

Yang, Joon On; Chang, Soon Heung

1990-01-01

An alarm processing system (APS) has been developed using artificial intelligence (AI) techniques. The alarms of nuclear power plants (NPP's) are classified into the generalized and special alarms. The generalized alarms are also classified into the global and local alarms. For each type of alarms, the specific processing rules are applied to filter and suppress unnecessary and potentially misleading alarms. The local processing are based on 'model-based reasoning.' The global and special alarms are processed by using the general cause-consequence check rules. The priorities of alarms are determined according to the plant state and the consistencies between them

Integration of drinking water treatment plant process models and emulated process automation software

NARCIS (Netherlands)

Worm, G.I.M.

2012-01-01

The objective of this research is to limit the risks of fully automated operation of drinking water treatment plants and to improve their operation by using an integrated system of process models and emulated process automation software. This thesis contains the design of such an integrated system.

Recent Progress on Data-Based Optimization for Mineral Processing Plants

Directory of Open Access Journals (Sweden)

Jinliang Ding

2017-04-01

Full Text Available In the globalized market environment, increasingly significant economic and environmental factors within complex industrial plants impose importance on the optimization of global production indices; such optimization includes improvements in production efficiency, product quality, and yield, along with reductions of energy and resource usage. This paper briefly overviews recent progress in data-driven hybrid intelligence optimization methods and technologies in improving the performance of global production indices in mineral processing. First, we provide the problem description. Next, we summarize recent progress in data-based optimization for mineral processing plants. This optimization consists of four layers: optimization of the target values for monthly global production indices, optimization of the target values for daily global production indices, optimization of the target values for operational indices, and automation systems for unit processes. We briefly overview recent progress in each of the different layers. Finally, we point out opportunities for future works in data-based optimization for mineral processing plants.

Plant uprooting by flow as a fatigue mechanical process

Science.gov (United States)

Perona, Paolo; Edmaier, Katharina; Crouzy, Benoît

2015-04-01

In river corridors, plant uprooting by flow mostly occurs as a delayed process where flow erosion first causes root exposure until residual anchoring balances hydrodynamic forces on the part of the plant that is exposed to the stream. Because a given plant exposure time to the action of the stream is needed before uprooting occurs (time-to-uprooting), this uprooting mechanism has been denominated Type II, in contrast to Type I, which mostly affect early stage seedlings and is rather instantaneous. In this work, we propose a stochastic framework that describes a (deterministic) mechanical fatigue process perturbed by a (stochastic) process noise, where collapse occurs after a given exposure time. We test the model using the experimental data of Edmaier (2014) and Edmaier et al. (submitted), who investigated vegetation uprooting by flow in the limit of low plant stem-to-sediment size ratio by inducing parallel riverbed erosion within an experimental flume. We first identify the proper timescale and lengthscale for rescaling the model. Then, we show that it describes well all the empirical cumulative distribution functions (cdf) of time-to-uprooting obtained under constant riverbed erosion rate and assuming additive gaussian process noise. By this mean, we explore the level of determinism and stochasticity affecting the time-to-uprooting for Avena sativa in relation to root anchoring and flow drag forces. We eventually ascribe the overall dynamics of the Type II uprooting mechanism to the memory of the plant-soil system that is stored by root anchoring, and discuss related implications thereof. References Edmaier, K., Uprooting mechansims of juvenile vegetation by flow erosion, Ph.D. thesis, EPFL, 2014. Edmaier, K., Crouzy, B. and P. Perona. Experimental characterization of vegetation uprooting by flow. J. of Geophys. Res. - Biogeosci., submitted

Processing and solidification of Savannah River Plant high-level waste

International Nuclear Information System (INIS)

Kelley, J.A.

1981-01-01

The entire flowsheet for processing and solidification of Savannah River Plant (SRP) high-level wastes has been demonstrated. A new small-scale integrated pilot plant is operating with actual radioactive wastes, and large-scale equipment is being demonstrated with nonradioactive simulated wastes. Design of a full-scale waste solidification plant is in progress. Plant construction is expected to begin in 1983, and startup is anticipated in 1988. The plant will poduce about 500 cans of glass per year with each can containing about 1.5 tons of glass

Water-integrated scheduling of batch process plants

NARCIS (Netherlands)

Pulluru, Sai Jishna; Akkerman, Renzo

2018-01-01

Efficient water management is becoming increasingly important in production systems, but companies often do not have any concrete strategies to implement. While there are numerous technological options for improving water efficiency in process plants, there is a lack of effective decision support to

Water-integrated scheduling of batch process plants

NARCIS (Netherlands)

Pulluru, Sai Jishna; Akkerman, Renzo

2017-01-01

Efficient water management is becoming increasingly important in production systems, but companies often do not have any concrete strategies to implement. While there are numerous technological options for improving water efficiency in process plants, there is a lack of effective decision support to

Chemical process and plant design bibliography 1959-1989

International Nuclear Information System (INIS)

Ray, M.S.

1991-01-01

This book is concerned specifically with chemical process in formation and plant equipment design data. It is a source for chemical engineers, students and academics involved in process and design evaluation. Over 500 chemical categories are included, from Acetaldehyde to zirconium Dioxide, with cross-referencing within the book to appropriate associated chemicals

Defense Waste Processing Facility, Savannah River Plant

International Nuclear Information System (INIS)

After 10 years of research, development, and testing, the US Department of Energy is building a new facility which will prepare high-level radioactive waste for permanent disposal. The Defense Waste Processing Facility, known as the DWPF, will be the first production-scale facility of its kind in the United States. In the DWPF, high-level waste produced by defense activities at the Savannah River Plant will be processed into a solid form, borosilicate glass, suitable for permanent off-site geologic disposal. With construction beginning in the fall of 1983, the DWPT is scheduled to be operational in 1989. By 2005, the DWPF will have immobilized the backlog of high-level waste which has been accumulating in storage tanks at the Savannah River Plant since 1954. Canisters of the immobilized waste will then be ready for permanent disposal deep under the ground, safely isolated from the environment

Nuclear power plant personnel training process management system

International Nuclear Information System (INIS)

Arjona Vazquez, Orison; Venegas Bernal, Maria del Carmen; Armeteros Lopez, Ana L.

1996-01-01

The system in charge the management of the training process personnel from a nuclear power plant was designed taking into account all the requirements stated in the training guide for nuclear power plant personnel and their evaluation, which were prepared by the IAEA in 1995 in order to implement the SAT in the training programs for nuclear plant personnel. In the preparations of formats and elements that shape the system, account has been taken of the views expressed in such a guide, in some other bibliography that was consulted, and in the authors own opinion mainly with regard to those issues which the guide does not go deeper into

When do plants modify fluvial processes? Plant-hydraulic interactions under variable flow and sediment supply rates

Science.gov (United States)

Manners, Rebecca B.; Wilcox, Andrew C.; Kui, Li; Lightbody, Anne F.; Stella, John C.; Sklar, Leonard S.

2015-02-01

Flow and sediment regimes shape alluvial river channels; yet the influence of these abiotic drivers can be strongly mediated by biotic factors such as the size and density of riparian vegetation. We present results from an experiment designed to identify when plants control fluvial processes and to investigate the sensitivity of fluvial processes to changes in plant characteristics versus changes in flow rate or sediment supply. Live seedlings of two species with distinct morphologies, tamarisk (Tamarix spp.) and cottonwood (Populus fremontii), were placed in different configurations in a mobile sand-bed flume. We measured the hydraulic and sediment flux responses of the channel at different flow rates and sediment supply conditions representing equilibrium (sediment supply = transport rate) and deficit (sediment supply plant species and configuration. Species-specific traits controlled the hydraulic response: compared to cottonwood, which has a more tree-like morphology, the shrubby morphology of tamarisk resulted in less pronation and greater reductions in near-bed velocities, Reynolds stress, and sediment flux rates. Under sediment-deficit conditions, on the other hand, abiotic factors dampened the effect of variations in plant characteristics on the hydraulic response. We identified scenarios for which the highest stem-density patch, independent of abiotic factors, dominated the fluvial response. These results provide insight into how and when plants influence fluvial processes in natural systems.

Formosa Plastics Corporation: Plant-Wide Assessment of Texas Plant Identifies Opportunities for Improving Process Efficiency and Reducing Energy Costs

Energy Technology Data Exchange (ETDEWEB)

None

2005-01-01

At Formosa Plastics Corporation's plant in Point Comfort, Texas, a plant-wide assessment team analyzed process energy requirements, reviewed new technologies for applicability, and found ways to improve the plant's energy efficiency. The assessment team identified the energy requirements of each process and compared actual energy consumption with theoretical process requirements. The team estimated that total annual energy savings would be about 115,000 MBtu for natural gas and nearly 14 million kWh for electricity if the plant makes several improvements, which include upgrading the gas compressor impeller, improving the vent blower system, and recovering steam condensate for reuse. Total annual cost savings could be $1.5 million. The U.S. Department of Energy's Industrial Technologies Program cosponsored this assessment.

Process data validation according VDI 2048 in conventional and nuclear power plants

International Nuclear Information System (INIS)

Langenstein, M.; Laipple, B.; Schmid, F.

2004-01-01

Process data validation according VDI 2048 in conventional and nuclear power plants is required for acceptance testing, process and component monitoring, and status-oriented maintenance. Once a validation system like VALI III has been certified according to VDI 2048, power plant owners can use the data obtained for efficiency increase. Further, all control variables can be adjusted so as to ensure maximum plant efficiency. (orig.)

Chemical process measurements in PWR-type nuclear power plants

International Nuclear Information System (INIS)

Glaeser, E.

1978-01-01

In order to achieve high levels of availability of nuclear power plants equipped with pressurized water reactors, strict standards have to be applied to the purity of coolant and of other media. Chemical process measurements can meet these requirements only if programmes are established giving maximum information with minimum expenditure and if these programmes are realized with effective analytical methods. Analysis programmes known from literature are proved for their usefulness, and hints are given for establishing rational programmes. Analytical techniques are compared with each other taking into consideration both methods which have already been introduced into nuclear power plant practice and methods not yet generally used in practice, such as atomic absorption spectrophotometry, gas chromatography, etc. Finally, based on the state of the art of chemical process measurements in nuclear power plants, the trends of future development are pointed out. (author)

St. Louis demonstration final report: refuse processing plant equipment, facilities, and environmental evaluations

Energy Technology Data Exchange (ETDEWEB)

Fiscus, D.E.; Gorman, P.G.; Schrag, M.P.; Shannon, L.J.

1977-09-01

The results are presented of processing plant evaluations of the St. Louis-Union Electric Refuse Fuel Project, including equipment and facilities as well as assessment of environmental emissions at both the processing and the power plants. Data on plant material flows and operating parameters, plant operating costs, characteristics of plant material flows, and emissions from various processing operations were obtained during a testing program encompassing 53 calendar weeks. Refuse derived fuel (RDF) is the major product (80.6% by weight) of the refuse processing plant, the other being ferrous metal scrap, a marketable by-product. Average operating costs for the entire evaluation period were $8.26/Mg ($7.49/ton). The average overall processing rate for the period was 168 Mg/8-h day (185.5 tons/8-h day) at 31.0 Mg/h (34.2 tons/h). Future plants using an air classification system of the type used at the St. Louis demonstration plant will need an emissions control device for particulates from the large de-entrainment cyclone. Also in the air exhaust from the cyclone were total counts of bacteria and viruses several times higher than those of suburban ambient air. No water effluent or noise exposure problems were encountered, although landfill leachate mixed with ground water could result in contamination, given low dilution rates.

CO₂ Capture Membrane Process for Power Plant Flue Gas

Energy Technology Data Exchange (ETDEWEB)

Toy, Lora [Research Triangle Inst. International, Research Triangle Park, NC (United States); Kataria, Atish [Research Triangle Inst. International, Research Triangle Park, NC (United States); Gupta, Raghubir [Research Triangle Inst. International, Research Triangle Park, NC (United States)

2012-04-01

Because the fleet of coal-fired power plants is of such importance to the nation's energy production while also being the single largest emitter of CO₂, the development of retrofit, post-combustion CO₂ capture technologies for existing and new, upcoming coal power plants will allow coal to remain a major component of the U.S. energy mix while mitigating global warming. Post-combustion carbon capture technologies are an attractive option for coal-fired power plants as they do not require modification of major power-plant infrastructures, such as fuel processing, boiler, and steam-turbine subsystems. In this project, the overall objective was to develop an advanced, hollow-fiber, polymeric membrane process that could be cost-effectively retrofitted into current pulverized coal-fired power plants to capture at least 90% of the CO₂ from plant flue gas with 95% captured CO₂ purity. The approach for this project tackled the technology development on three different fronts in parallel: membrane materials R&D, hollow-fiber membrane module development, and process development and engineering. The project team consisted of RTI (prime) and two industrial partners, Arkema, Inc. and Generon IGS, Inc. Two CO₂-selective membrane polymer platforms were targeted for development in this project. For the near term, a next-generation, high-flux polycarbonate membrane platform was spun into hollow-fiber membranes that were fabricated into both lab-scale and larger prototype (~2,200 ft²) membrane modules. For the long term, a new fluoropolymer membrane platform based on poly(vinylidene fluoride) [PVDF] chemistry was developed using a copolymer approach as improved capture membrane materials with superior chemical resistance to flue-gas contaminants (moisture, SO₂, NO_x, etc.). Specific objectives were: - Development of new, highly chemically resistant, fluorinated polymers as membrane materials with minimum selectivity of 30 for CO₂ over N₂ and CO�

Digital Process Management Technology for Nuclear Power Plants

International Nuclear Information System (INIS)

You, Young M.; Suh, Kune Y.

2009-01-01

PHILOSOPHIA, Inc. and Seoul National University have utilized the cutting edge Digital Process Management (DPM) technology for the good of Nuclear Power Plant in recent days. This work represent the overall benefits and the use of this new flow of technology which come into the spotlight. Before realizing the three dimensional (3D) technologies and applying it to real mechanical manufactures and constructions, majority of planning and designing works need huge time and cost even if the process is before the real work. Especially, for a massive construction such as power plant and harbor, without computer-aided technology currently we cannot imagine the whole process can be established easily. Computer-aided Design (CAD) is now main and common technology for manufacturing or construction. This technology lead the other virtual reality 3D technologies into the job site. As a member of these new technologies, DPM is utilized in high-tech and huge scale manufacturing and construction for the benefits of time and cost

Do the Czech Production Plants Measure the Performance of Energy Processes?

Directory of Open Access Journals (Sweden)

Zuzana Tučková

2016-04-01

Full Text Available The research was focused to the actual situation in Performance Measurement of the energy processes in Czech production plants. The results are back – upped by the previous researches which were aimed to performance measurement methods usage in the whole organizational structure of the plants. Although the most of big industrial companies declared using of modern Performance Measurements methods, the previous researches shown that it is not purely true. The bigger differences were found in the energy area – energy processes. The authors compared the Energy concepts of European Union (EU and Czech Republic (CZ which are very different and do not create any possibilities for manager’s clear decision in the process management strategy of energy processes in their companies. Next step included the Energy department’s analysis. The significant part of energy processes in the production plants is still not mapped, described and summarized to one methodical manual for managing and performance measurement.

Exposure to airborne microorganisms and endotoxin in herb processing plants.

Science.gov (United States)

Dutkiewicz, J; Krysińska-Traczyk, E; Skórska, C; Sitkowska, J; Prazmo, Z; Golec, M

2001-01-01

Microbiological air sampling was performed in two herb processing plants located in eastern Poland. Air samples for determination of the levels of bacteria, fungi, dust and endotoxin were collected at 14 sites during cleaning, cutting, grinding, sieving, sorting and packing of 11 kinds of herbs (nettle, caraway, birch, celandine, marjoram, mint, peppermint, sage, St. John's wort, calamus, yarrow), used for production of medications, cosmetics and spices. It was found that processing of herbs was associated with a very high pollution of the air with bacteria, fungi, dust and endotoxin. The numbers of microorganisms (bacteria and fungi) in the air of herb processing plants ranged within 40.6-627.4 x 10(3) cfu/m3 (mean +/- S.D = 231.4 +/- 181.0 x 10(3) cfu/m3). The greatest concentrations were noted at the initial stages of production cycle, during cleaning, cutting and grinding of herbs. The numbers of airborne microorganisms were also significantly (pnettle, yarrow and mint. The values of the respirable fraction of airborne microflora in the examined facilities varied within a fairly wide range and were between 14.7-67.7%. The dominant microorganisms in the air of herb processing plants were mesophilic bacteria, among which endospore-forming bacilli (Bacillus spp.) and actinomycetes of the species Streptomyces albus were most numerous. Among Gram-negative bacteria, the most common was endotoxin-producing species Alcaligenes faecalis. Altogether, 37 species or genera of bacteria and 23 species or genera of fungi were identified in the air of herb processing plants, of these, 11 and 10 species or genera respectively were reported as having allergenic and/or immunotoxic properties. The concentrations of dust and bacterial endotoxin in the air of herb processing plants were large with extremely high levels at some sampling sites. The concentrations of airborne dust ranged within 3.2-946.0 mg/m3 (median 18.1 mg/m3), exceeding at 13 out of 14 sampling sites the Polish OEL

Automated systems for control of technological processes at nuclear power plants and their use in putting the plant into operation

International Nuclear Information System (INIS)

Majtan, L.

1987-01-01

The systems of testing and control of technological processes in WWER-440 units in nuclear power plants which have so far been constructed in Czechoslovakia have been based on the conceptual principles and hardware used in the USSR. For the Mochovce nuclear power plant an automated process control system is to be introduced which proceeds from experiences gained with new Czechoslovak conventional power plants with 200 MW units. The control system consists of two levels: unit control and the control of the whole power plant the unit control consists of the DERIS-900 decentralized control system and the SM 1804 microcomputer and SM 1420 minicomputer based information and control system. A data processing system based on the SM 52/11.M1 minicomputer system will be used for power plant start-up and commissioning. (Z.M.). 2 figs., 4 refs

Increasing operational efficiency in a radioactive waste processing plant - 16100

International Nuclear Information System (INIS)

Turner, T.W.; Watson, S.N.

2009-01-01

The solid waste plant at Harwell in Oxfordshire, contains a purpose built facility to input, assay, visually inspect and sort remote handled intermediate level radioactive waste (RHILW). The facility includes a suite of remote handling cells, known as the head-end cells (HEC), which waste must pass through in order to be repackaged. Some newly created waste from decommissioning works on site passes through the cells, but the vast majority of waste for processing is historical waste, stored in below ground tube stores. Existing containers are not suitable for long term storage, many are already badly corroded, so the waste must be efficiently processed and repackaged in order to achieve passive safety. The Harwell site is currently being decommissioned and the land is being restored. The site is being progressively de-licensed, and redeveloped as a business park, which can only be completed when all the nuclear liabilities have been removed. The recovery and processing of old waste in the solid waste plant is a key project linked to de-licensing of a section of the site. Increasing the operational efficiency of the waste processing plant could shorten the time needed to clear the site and has the potential to save money for the Nuclear Decommissioning Authority (NDA). The waste processing facility was constructed in the mid 1990's, and commissioned in 1999. Since operations began, the yearly throughput of the cells has increased significantly every year. To achieve targets set out in the lifetime plan (LTP) for the site, throughput must continue to increase. The operations department has measured the overall equipment effectiveness (OEE) of the process for the last few years, and has used continuous improvement techniques to decrease the average cycle time. Philosophies from operational management practices such as 'lean' and 'kaizen' have been employed successfully to drive out losses and increase plant efficiency. This paper will describe how the solid waste plant

Waste processing system for nuclear power plant

International Nuclear Information System (INIS)

Higashinakagawa, Emiko; Tezuka, Fuminobu; Maesawa, Yukishige; Irie, Hiromitsu; Daibu, Etsuji.

1996-01-01

The present invention concerns a waste processing system of a nuclear power plant, which can reduce the volume of a large amount of plastics without burying them. Among burnable wastes and plastic wastes to be discarded in the power plant located on the sea side, the plastic wastes are heated and converted into oils, and the burnable wastes are burnt using the oils as a fuel. The system is based on the finding that the presence of Na 2 O, K 2 O contained in the wastes catalytically improves the efficiency of thermal decomposition in a heating atmosphere, in the method of heating plastics and converting them into oils. (T.M.)

Analysis of Unit Process Cost for an Engineering-Scale Pyroprocess Facility Using a Process Costing Method in Korea

Directory of Open Access Journals (Sweden)

Sungki Kim

2015-08-01

Full Text Available Pyroprocessing, which is a dry recycling method, converts spent nuclear fuel into U (Uranium/TRU (TRansUranium metal ingots in a high-temperature molten salt phase. This paper provides the unit process cost of a pyroprocess facility that can process up to 10 tons of pyroprocessing product per year by utilizing the process costing method. Toward this end, the pyroprocess was classified into four kinds of unit processes: pretreatment, electrochemical reduction, electrorefining and electrowinning. The unit process cost was calculated by classifying the cost consumed at each process into raw material and conversion costs. The unit process costs of the pretreatment, electrochemical reduction, electrorefining and electrowinning were calculated as 195 US$/kgU-TRU, 310 US$/kgU-TRU, 215 US$/kgU-TRU and 231 US$/kgU-TRU, respectively. Finally the total pyroprocess cost was calculated as 951 US$/kgU-TRU. In addition, the cost driver for the raw material cost was identified as the cost for Li3PO4, needed for the LiCl-KCl purification process, and platinum as an anode electrode in the electrochemical reduction process.

Head-end process technology for the new reprocessing plants in France and Japan

International Nuclear Information System (INIS)

Saudray, D.; Hugelmann, D.; Cho, A.

1991-01-01

Major technological innovations brought to the new UP3 and UP2-800 reprocessing plants of COGEMA LA HAGUE and also to the JNFS ROKKASHO plant concern the head-end process. The continuous process designed allows for high throughputs whilst meeting stringent safety requirements. The head-end of each plant includes two lines for each operation in order to guarantee availability. This paper presents the T1 head-end facility of the UP3 plant as well as the few adaptations implemented in the ROKKASHO Reprocessing Plant to fulfill the particular design requirements in Japan

Investigation of small scale sphere-pac fuel fabrication plant with external gelation process

International Nuclear Information System (INIS)

Maekawa, Kazuhiko; Yoshimura, Tadahiro; Kikuchi, Toshiaki; Hoshino, Yasushi; Munekata, Hideki; Shimizu, Makoto

2005-02-01

In feasibility studies on commercialized FBR cycle system, comprehensive system investigation and properties evaluation for candidate FBR cycle systems have been implemented through view point of safety, economics, environmental burden reduction, non-proliferation resistivity, etc. As part of these studies, an investigation of small scale sphere-pac fuel fabrication plant with external gelation process was conducted. Until last fiscal year, equipment layout in cells and overall layout design of the 200t-HM/y scale fuel fabrication plant were conducted as well as schematical design studies on main equipments in gelation and reagent recovery processes of the plant. System property data concerning economics and environmental burden reduction of fuel fabrication plant was also acquired. In this fiscal year, the processes from vibropacking to fuel assemblies storage were added to the investigation range, and a conceptual design of whole fuel fabrication plant was studied as well as deepening the design study on main equipments. The conceptual design study was mainly conducted for small 50t-HM/y scale plant and a revising investigation was done for 200t-HM/y scale plant. Taking the planed comparative evaluation with pellet fuel fabrication system into account, design of equipments which should be equivalent with pellet system, especially in post-vibropacking processes, were standardized in each system. Based on these design studies, system properties data concerning economics and environmental burden reduction of the plant was also acquired. In comparison with existing design, the cell height was lowered on condition that plug type pneumatic system was adopted and fuel fabrication building was downsized by applying rationalized layout design of pellet system to post-vibropacking processes. Reduction of reagent usage at gelation process and rationalization of sintering and O/M controlling processes etc., are foremost tasks. (author)

TBP production plant effluent treatment process

International Nuclear Information System (INIS)

Sriniwas, C.; Sugilal, G.; Wattal, P.K.

2004-06-01

TBP production facility at Heavy Water Plant, Talcher generates about 2000 litres of effluent per 200 kg batch. The effluent is basically an aqueous solution containing dissolved and dispersed organics such as dibutyl phosphate, butanol etc. The effluent has high salinity, chemical oxygen demand (30-80 g/L) and pungent odour. It requires treatment before discharge. A chemical precipitation process using ferric chloride was developed for quantitative separation of organics from the aqueous part of the effluent. This process facilitates the discharge of the aqueous effluent. Results of the laboratory and bench scale experiments on actual effluent samples are presented in this report. (author)

Hydroponic potato production on nutrients derived from anaerobically-processed potato plant residues

Science.gov (United States)

Mackowiak, C. L.; Stutte, G. W.; Garland, J. L.; Finger, B. W.; Ruffe, L. M.

1997-01-01

Bioregenerative methods are being developed for recycling plant minerals from harvested inedible biomass as part of NASA's Advanced Life Support (ALS) research. Anaerobic processing produces secondary metabolites, a food source for yeast production, while providing a source of water soluble nutrients for plant growth. Since NH_4-N is the nitrogen product, processing the effluent through a nitrification reactor was used to convert this to NO_3-N, a more acceptable form for plants. Potato (Solanum tuberosum L.) cv. Norland plants were used to test the effects of anaerobically-produced effluent after processing through a yeast reactor or nitrification reactor. These treatments were compared to a mixed-N treatment (75:25, NO_3:NH_4) or a NO_3-N control, both containing only reagent-grade salts. Plant growth and tuber yields were greatest in the NO_3-N control and yeast reactor effluent treatments, which is noteworthy, considering the yeast reactor treatment had high organic loading in the nutrient solution and concomitant microbial activity.

STUDY OF PLANT-WIDE CONTROL IMPLEMENTATION IN PRODUCTION PROCESS OF GEOTHERMAL POWER PLANT

Directory of Open Access Journals (Sweden)

KATHERIN INDRIAWATI

2017-02-01

Full Text Available The design of plant-wide control system to optimize electricity production in geothermal power plant is proposed in this research. The objective is to overcome the deficiency due to changes in the characteristics of production well and fluctuation in electricity demand load. The proposed plant-wide control system has two main tasks; to maintain production process at optimum value and to increase efficiency. The pressure in separator and condenser is maintained at the respective set points under electrical load fluctuations in order to ensure optimum efficiency. The control system also reduce the usage of auxialiary electrical power and increase efficiency. The task was performed by controlling inlet cooling water temperatures to the condenser. It was concluded that the proposed control structure was able to increase efficiency and maintain production.

Growth of Radiation Processing Plant, Vashi - an overview

International Nuclear Information System (INIS)

Singh, Ranjeet

2014-01-01

Radiation Processing Plant, Vashi (RPP) is the first commercial scale Gamma Irradiator for food processing in India. The facility was commissioned on 1 st January 2000 with the mandate of showcasing commercial viability of food processing using gamma radiation. Some of the food products that are processed at RPP, Vashi include dehydrated onion powder, coriander, turmeric, black pepper, cumin, pet food and dried seafood items. RPP, Vashi is the largest radiation processor of food products in the country. More than 95% of the quantity processed is exported to various countries generating millions of foreign exchange annually

Remote sampling of process fluids in radiochemical plants

International Nuclear Information System (INIS)

Sengar, P.B.; Bhattacharya, R.; Ozarde, P. D.; Rana, D.S.

1990-01-01

Sampling of process fluids, continuous or periodic, is an essential requirement in any chemical process plant, so as to keep a control on process variables. In a radiochemical plant the task of taking and conveying the samples is a very tricky affair. This is due to the fact that neither the vessels/equipment containing radioactive effluents can be approached for manual sampling nor sampled fluids can be handled directly. The problems become more accute with higher levels of radioactivity. As such, inovative systems have to be devised to obtain and handle the raioactive samples employing remote operations. The remote sampling system developed in this Division has some of the unique features such as taking only requisite amount of samples in microlitre range, practically maintenance free design, avoidence of excess radioactive fluids coming out of process systems, etc. The paper describes in detail the design of remote sampling system and compares the same with existing systems. The design efforts are towards simplicity in operation, obtaining homogenised representative samples and highly economical on man-rem expenditure. The performance of a prototype system has also been evaluated. (author). 3 refs

New nuclear plant design and licensing process

International Nuclear Information System (INIS)

Luangdilok, W.

1996-01-01

This paper describes latest developments in the nuclear power reactor technology with emphasis on three areas: (1) the US technology of advanced passive light water reactors (AP600 and S BWR), (2) regulatory processes that certify their safety, and (3) current engineering concerns. The goal is to provide and insight of how the government's regulatory agency guarantees public safety by looking into how new passive safety features were designed and tested by vendors and how they were re-evaluated and retested by the US NRC. The paper then discusses the US 1989 nuclear licensing reform (10 CFR Part 52) whose objectives are to promote the standardization of nuclear power plants and provide for the early and definitive resolution of site and design issues before plants are built. The new licensing process avoids the unpredictability nd escalated construction cost under the old licensing process. Finally, the paper summarizes engineering concerns found in current light water reactors that may not go away in the new design. The concerns are related the material and water chemistry technology in dealing with corrosion problems in water-cooled nuclear reactor systems (PWRs and BWRs). These engineering concerns include core shroud cracking (BWRs), jet pump hold-down beam cracking (BWRs), steam generator tube stress corrosion cracking (PWR)

Technical Characteristics of the Process Information System - Nuclear Power Plant Krsko

International Nuclear Information System (INIS)

Mandic, D.; Smolej, M.

1998-01-01

process Information System (PIS) of Nuclear Power Plant Krsko (NEK) is newly installed distributed and redundant process computer system which was built in NEK (Phase I: 1991-1995) to integrate the following main functions: - Signal Data Acquisition from the technological processes and environment - Implementation of the basic SCADA functions on the real time process signals data base - Execution of complex plant specific application programs - Advanced MMI (Man Machine Interface) features for users in MCR - Process data transfer to other than Main Control Room (MCR) locations - Process data archiving and capability to retrieve same data for future analysis PIS NEK architecture consists of three hierarchically interconnected hardware platforms: - PIS Level 1, DAS (Data Acquisition System) Level - PIS Level2, Level for MMI, application programs and process data archiving - PIS Level 3, Level for distribution of process data to remote users of PIS data. (author)

Process analysis in a THTR trial reprocessing plant

International Nuclear Information System (INIS)

Brodda, B.G.; Filss, P.; Kirchner, H.; Kroth, K.; Lammertz, H.; Schaedlich, W.; Brocke, W.; Buerger, K.; Halling, H.; Watzlawik, K.H.

1979-01-01

The demands on an analytical control system for a THTR trial reprocessing plant are specified. In a rather detailed example, a typical sampling, sample monitoring and measuring process is described. Analytical control is partly automated. Data acquisition and evaluation by computer are described for some important, largely automated processes. Sample management and recording of in-line and off-line data are carried out by a data processing system. Some important experiments on sample taking, sample transport and on special analysis are described. (RB) [de

Biorefinery plant design, engineering and process optimisation

DEFF Research Database (Denmark)

Holm-Nielsen, Jens Bo; Ehimen, Ehiazesebhor Augustine

2014-01-01

Before new biorefinery systems can be implemented, or the modification of existing single product biomass processing units into biorefineries can be carried out, proper planning of the intended biorefinery scheme must be performed initially. This chapter outlines design and synthesis approaches...... applicable for the planning and upgrading of intended biorefinery systems, and includes discussions on the operation of an existing lignocellulosic-based biorefinery platform. Furthermore, technical considerations and tools (i.e., process analytical tools) which could be applied to optimise the operations...... of existing and potential biorefinery plants are elucidated....

All part of the process[3D plant modelling

Energy Technology Data Exchange (ETDEWEB)

Snieckus, D.

2002-12-01

The second coming of EPIC contracts, a renewed emphasis on life-of-field costs for offshore developments, and the deepwater FPSO market's fast approaching construction boom are together demanding fresh thinking - and software systems - from 3D plant modelling and information specialists. Based on its own calculations, Intergraph's Process, Power and Offshore (PPO) division states that it holds down some 35-40% of the market for 3D plant modelling and information management in the offshore oil and gas industry. This article reviews their success, how they have to preserve their hard won share of the market, due to the changeable nature of that market, marked recently by the fundamental shifts in EPIC contract structure, life-of-field costs focuses, and, not least, the rise of FPSO-driven production concepts. Intergraph PPO's integrated product portfolio, which brings together plant design modelling systems and plant information management systems, was founded on its SmartPlant Foundation data warehouse hub. It has maintained its project data integrity o some of the largest and most complex offshore developments, including Phillips Petroleum's Bayu-Undan and Statoil Asgard fields. Some 70% of Intergraph PPO's clients have been contractors, and while the company aims to continue to build on the strength of these relationships, it also recognises that growing its client base of owner-operators will create some 'real synergies' in the process.

The modernization of the process computer of the Trillo Nuclear Power Plant

International Nuclear Information System (INIS)

Martin Aparicio, J.; Atanasio, J.

2011-01-01

The paper describes the modernization of the Process computer of the Trillo Nuclear Power Plant. The process computer functions, have been incorporated in the non Safety I and C platform selected in Trillo NPP: the Siemens SPPA-T2000 OM690 (formerly known as Teleperm XP). The upgrade of the Human Machine Interface of the control room has been included in the project. The modernization project has followed the same development process used in the upgrade of the process computer of PWR German nuclear power plants. (Author)

Development of an experimental approach to study coupled soil-plant-atmosphere processes using plant analogs

Science.gov (United States)

Trautz, Andrew C.; Illangasekare, Tissa H.; Rodriguez-Iturbe, Ignacio; Heck, Katharina; Helmig, Rainer

2017-04-01

The atmosphere, soils, and vegetation near the land-atmosphere interface are in a state of continuous dynamic interaction via a myriad of complex interrelated feedback processes which collectively, remain poorly understood. Studying the fundamental nature and dynamics of such processes in atmospheric, ecological, and/or hydrological contexts in the field setting presents many challenges; current experimental approaches are an important factor given a general lack of control and high measurement uncertainty. In an effort to address these issues and reduce overall complexity, new experimental design considerations (two-dimensional intermediate-scale coupled wind tunnel-synthetic aquifer testing using synthetic plants) for studying soil-plant-atmosphere continuum soil moisture dynamics are introduced and tested in this study. Validation of these experimental considerations, particularly the adoption of synthetic plants, is required prior to their application in future research. A comparison of three experiments with bare soil surfaces or transplanted with a Stargazer lily/limestone block was used to evaluate the feasibility of the proposed approaches. Results demonstrate that coupled wind tunnel-porous media experimentation, used to simulate field conditions, reduces complexity, and enhances control while allowing fine spatial-temporal resolution measurements to be made using state-of-the-art technologies. Synthetic plants further help reduce system complexity (e.g., airflow) while preserving the basic hydrodynamic functions of plants (e.g., water uptake and transpiration). The trends and distributions of key measured atmospheric and subsurface spatial and temporal variables (e.g., soil moisture, relative humidity, temperature, air velocity) were comparable, showing that synthetic plants can be used as simple, idealized, nonbiological analogs for living vegetation in fundamental hydrodynamic studies.

United States Transuranium Registry annual report, October 1, 1980-October 1, 1981 to Human Health and Assessments Division, US Department of Energy

International Nuclear Information System (INIS)

Breitenstein, B.D. Jr.; Heid, K.R.; Swint, M.J.

1982-01-01

The Registry initiates and supports programs at the various sites, where significant numbers of transuranic workers are employed, to conduct interviews and secure medical, health physics and autopsy releases. Terminated employees, not previously contacted, are encouraged to participate in the Registry program. This effort requires cooperation from the company administration as well as the medical and health physics staff. For those persons who are not reached through this network, we attempt to reach them through information about the Registry in professional newsletters and publications. Table 1 is a summary of the status of the US Transuranium Registry autopsy program as of September 1981. The need to prove or improve the accuracy of the present in vivo models is of paramount interest to health physicists. The correlation of in vivo measurements with the radiochemical analysis brings the possibilities of increased predictability of whole body deposition closer to reality. The correlation of in vivo with autopsy tissue will aid epidemiological studies to define those observable health effects in the exposed population that should be looked for

Energy optimization of integrated process plants

Energy Technology Data Exchange (ETDEWEB)

Sandvig Nielsen, J

1996-10-01

A general approach for viewing the process synthesis as an evolutionary process is proposed. Each step is taken according to the present level of information and knowledge. This is formulated in a Process Synthesis Cycle. Initially the synthesis is conducted at a high abstraction level maximizing use of heuristics (prior experience, rules of thumbs etc). When further knowledge and information are available, heuristics will gradually be replaced by exact problem formulations. The principles in the Process Synthesis Cycle, is used to develop a general procedure for energy synthesis, based on available tools. The procedure is based on efficient use of process simulators with integrated Pinch capabilities (energy targeting). The proposed general procedure is tailored to three specific problems (Humid Air Turbine power plant synthesis, Nitric Acid process synthesis and Sulphuric Acid synthesis). Using the procedure reduces the problem dimension considerable and thus allows for faster evaluation of more alternatives. At more detailed level a new framework for the Heat Exchanger Network synthesis problem is proposed. The new framework is object oriented based on a general functional description of all elements potentially present in the heat exchanger network (streams, exchangers, pumps, furnaces etc.). (LN) 116 refs.

Development of process simulation code for reprocessing plant and process analysis for solvent degradation and solvent washing waste

International Nuclear Information System (INIS)

Tsukada, Tsuyoshi; Takahashi, Keiki

1999-01-01

We developed a process simulation code for an entire nuclear fuel reprocessing plant. The code can be used on a PC. Almost all of the equipment in the reprocessing plant is included in the code and the mass balance model of each item of equipment is based on the distribution factors of flow-out streams. All models are connected between the outlet flow and the inlet flow according to the process flow sheet. We estimated the amount of DBP from TBP degradation in the entire process by using the developed code. Most of the DBP is generated in the Pu refining process by the effect of α radiation from Pu, which is extracted in a solvent. On the other hand, very little of DBP is generated in the U refining process. We therefore propose simplification of the solvent washing process and volume reduction of the alkali washing waste in the U refining process. The first Japanese commercial reprocessing plant is currently under construction at Rokkasho Mura, Recently, for the sake of process simplification, the original process design has been changed. Using our code, we analyzed the original process and the simplified process. According our results, the volume of alkali waste solution in the low-level liquid treatment process will be reduced by half in the simplified process. (author)

Short-term acclimation to warmer temperatures accelerates leaf carbon exchange processes across plant types.

Science.gov (United States)

Smith, Nicholas G; Dukes, Jeffrey S

2017-11-01

While temperature responses of photosynthesis and plant respiration are known to acclimate over time in many species, few studies have been designed to directly compare process-level differences in acclimation capacity among plant types. We assessed short-term (7 day) temperature acclimation of the maximum rate of Rubisco carboxylation (V cmax ), the maximum rate of electron transport (J max ), the maximum rate of phosphoenolpyruvate carboxylase carboxylation (V pmax ), and foliar dark respiration (R d ) in 22 plant species that varied in lifespan (annual and perennial), photosynthetic pathway (C 3 and C 4 ), and climate of origin (tropical and nontropical) grown under fertilized, well-watered conditions. In general, acclimation to warmer temperatures increased the rate of each process. The relative increase in different photosynthetic processes varied by plant type, with C 3 species tending to preferentially accelerate CO 2 -limited photosynthetic processes and respiration and C 4 species tending to preferentially accelerate light-limited photosynthetic processes under warmer conditions. R d acclimation to warmer temperatures caused a reduction in temperature sensitivity that resulted in slower rates at high leaf temperatures. R d acclimation was similar across plant types. These results suggest that temperature acclimation of the biochemical processes that underlie plant carbon exchange is common across different plant types, but that acclimation to warmer temperatures tends to have a relatively greater positive effect on the processes most limiting to carbon assimilation, which differ by plant type. The acclimation responses observed here suggest that warmer conditions should lead to increased rates of carbon assimilation when water and nutrients are not limiting. © 2017 John Wiley & Sons Ltd.

United States Transuranium and Uranium Registries. Annual Report, October 1, 1993--September 30, 1994

Energy Technology Data Exchange (ETDEWEB)

Kathren, R.L.; Harwick, L.A. [comps.] [eds.

1995-08-01

This report summarizes the salient activities and progress of the United States Transuranium. and Uranium Registries for the period October 1, 1993 through September 30, 1994, along with details of specific programs areas including the National Human Radiobiology Tissue Repository (NHRTR) and tissue radiochemistry analysis project. Responsibility for tissue radioanalysis was transferred from Los Alamos National Laboratory to Washington State University in February 1994. The University of Washington was selected as the Quality Assurance/Quality Control laboratory and a three way intercomparison with them and LANL has been initiated. The results of the initial alpha spectrometry intercomparison showed excellent agreement among the laboratories and are documented in full in the Appendices to the report. The NHRTR serves as the initial point of receipt for samples received from participants in the USTUR program. Samples are weighed, divided, and reweighed, and a portion retained by the NHRTR as backup or for use in other studies. Tissue specimens retained in the NHRTR are maintained frozen at -70 C and include not only those from USTUR registrants but also those from the radium dial painter and thorium worker studies formerly conducted by Argonne National Laboratory. In addition, there are fixed tissues and a large collection of histopathology slides from all the studies, plus about 20,000 individual solutions derived from donated tissues. These tissues and tissue related materials are made available to other investigators for legitimate research purposes. Ratios of the concentration of actinides in various tissues have been used to evaluate the biokinetics, and retention half times of plutonium and americium. Retention half times for plutonium in various soft tissues range from 10-20 y except for the testes for which a retention half time of 58 y was observed. For americium, the retention half time in various soft tissues studied was 2.2-3.5 y.

United States Transuranium and Uranium Registries. Annual Report, October 1, 1993--September 30, 1994

International Nuclear Information System (INIS)

Kathren, R.L.; Harwick, L.A.

1995-01-01

This report summarizes the salient activities and progress of the United States Transuranium. and Uranium Registries for the period October 1, 1993 through September 30, 1994, along with details of specific programs areas including the National Human Radiobiology Tissue Repository (NHRTR) and tissue radiochemistry analysis project. Responsibility for tissue radioanalysis was transferred from Los Alamos National Laboratory to Washington State University in February 1994. The University of Washington was selected as the Quality Assurance/Quality Control laboratory and a three way intercomparison with them and LANL has been initiated. The results of the initial alpha spectrometry intercomparison showed excellent agreement among the laboratories and are documented in full in the Appendices to the report. The NHRTR serves as the initial point of receipt for samples received from participants in the USTUR program. Samples are weighed, divided, and reweighed, and a portion retained by the NHRTR as backup or for use in other studies. Tissue specimens retained in the NHRTR are maintained frozen at -70 C and include not only those from USTUR registrants but also those from the radium dial painter and thorium worker studies formerly conducted by Argonne National Laboratory. In addition, there are fixed tissues and a large collection of histopathology slides from all the studies, plus about 20,000 individual solutions derived from donated tissues. These tissues and tissue related materials are made available to other investigators for legitimate research purposes. Ratios of the concentration of actinides in various tissues have been used to evaluate the biokinetics, and retention half times of plutonium and americium. Retention half times for plutonium in various soft tissues range from 10-20 y except for the testes for which a retention half time of 58 y was observed. For americium, the retention half time in various soft tissues studied was 2.2-3.5 y

Process specifications and standards for the 1970 thorium campaign in the Purex Plant

International Nuclear Information System (INIS)

Van der Cook, R.E.; Ritter, G.L.

1970-01-01

The process specifications and standards for thorium processing operations in the Purex Plant are presented. These specifications represent currently known limits within which plant processing conditions must be maintained to meet defined product requirements safely and with minimum effect on equipment service life. These specifications cover the general areas of feed, essential materials, and chemical hazards

Radiosterilization process control in plants using electron accelerators

International Nuclear Information System (INIS)

Stuglik, Z.

1997-01-01

Electron beam parameters deciding the irradiation dose in radiosterilization plants should be continuously controlled during the process. Dosimetric procedure suitable to irradiated material and dose range should be chosen. The practical advice and directions in this subject have been done. 7 refs

Secondary cleanup of Idaho Chemical Processing Plant solvent

International Nuclear Information System (INIS)

Mailen, J.C.

1985-01-01

Solvent from the Idaho Chemical Processing Plant (ICPP) (operated by Westinghouse Idaho Nuclear Company, Inc.) has been tested to determine the ability of activated alumina to remove secondary degradation products - those degradation products which are not removed by scrubbing with sodium carbonate

Absorption process for removing krypton from the off-gas of an LMFBR fuel reprocessing plant

International Nuclear Information System (INIS)

Stephenson, M.J.; Dunthorn, D.I.; Reed, W.D.; Pashley, J.H.

1975-01-01

The Oak Ridge Gaseous Diffusion Plant selective absorption process for the collection and recovery of krypton and xenon is being further developed to demonstrate, on a pilot scale, a fluorocarbon-based process for removing krypton from the off-gas of an LMFBR fuel reprocessing plant. The new ORGDP selective absorption pilot plant consists of a primary absorption-stripping operation and all peripheral equipment required for feed gas preparation, process solvent recovery, process solvent purification, and krypton product purification. The new plant is designed to achieve krypton decontamination factors in excess of 10 3 with product concentration factors greater than 10 4 while processing a feed gas containing typical quantities of common reprocessing plant off-gas impurities, including oxygen, carbon dioxide, nitrogen oxides, water, xenon, iodine, and methyl iodide. Installation and shakedown of the facility were completed and some short-term tests were conducted early this year. The first operating campaign using a simulated reprocessing plant off-gas feed is now underway. The current program objective is to demonstrate continuous process operability and performance for extended periods of time while processing the simulated ''dirty'' feed. This year's activity will be devoted to routine off-gas processing with little or no deliberate system perturbations. Future work will involve the study of the system behavior under feed perturbations and various plant disturbances. (U.S.)

Floating natural gas processing plants. Technical ideal or feasible technology

Energy Technology Data Exchange (ETDEWEB)

Backhaus, H

1977-04-01

Realizability of floating natural gas processing plants is decisively influenced by the economy of the system. Illustrated by the example of the natural gas product LPG (liquefied petroleum gas), a model cost calculation is carried out. It is demonstrated that the increase in the price level during the 1973/1974 energy crisis is an important factor for the realiability in terms of economy of such complicated technical systems. Another aspect which the model calculation revealed is that the economy of floating natural gas processing plants and storage systems can only be estimated in connection with other system components.

Job training planning and design for process plant operators

International Nuclear Information System (INIS)

Wirstad, J.

1983-01-01

A method is presented by which process plant operators for nuclear power plants are trained in Sweden. It works by a top-down method of systems analysis which can be integrated into the analysis, specification, and design of the process automation system. The training methods can also be adapted to existing automation systems and operating schedules. The author's method is based on the principle that training programs should be based on job requirements, e.g. operator tasks in common, less frequent, and rare operating conditions. Procedures have been tested for the following steps: Job analysis, analysis of knowledge and experience required, analysis of operator training requirements, set-up and organisation of the training programme, achievement control, evaluation of the training programme. (orig./HP) [de

Job training planning and design for process plant operators

Energy Technology Data Exchange (ETDEWEB)

Wirstad, J.

1983-01-01

A method is presented by which process plant operators for nuclear power plants are trained in Sweden. It works by a top-down method of systems analysis which can be integrated into the analysis, specification, and design of the process automation system. The training methods can also be adapted to existing automation systems and operating schedules. The author's method is based on the principle that training programs should be based on job requirements, e.g. operator tasks in common, less frequent, and rare operating conditions. Procedures have been tested for the following steps: Job analysis, analysis of knowledge and experience required, analysis of operator training requirements, set-up and organisation of the training programme, achievement control, evaluation of the training programme.

Prototype plant for nuclear process heat (PNP) - operation of the pilot plant for hydrogasification of coal

International Nuclear Information System (INIS)

Bruengel, N.; Dehms, G.; Fiedler, P.; Gerigk, H.P.; Ruddeck, W.; Schrader, L.; Schumacher, H.J.

1988-04-01

The Rheinische Braunkohlenwerke AG developed the process of hydrogasification of coal in a fluidized bed for generation of SNG. On basis of test results obtained in a semi-technical pilot plant of a through-put of 250 kg/h dried coal a large pilot plant was erected processing 10 t/h dried brown coal. This plant was on stream for about 14700 h, of which about 7800 h were with gasifier operation; during this time about 38000 t of dried brown coal of the Rhenish district were processed containing 4 to 25% of ash. At pressures of 60 to 120 bar and temperatures of 800 to 935 0 C carbon conversion rates up to 81 percent and methane amounts of 5000 m 3 (STP)/h were reached. The decisive parameter for methane generation was the hydrogen/coal-ratio. Even at high moisture contents, usually diminishing the methane yield from the coal essentially, by high hydrogen/coal-ratios high methane yields could be obtained. The gasifier itself caused no troubles during the total time operation. Difficulties with the original design of the residual char cooler could be overcome by change-over from water injection to liquid carbon dioxide. The design of the heat recovery system proved well. Alltogether so the size increasement of the gasifier from the semi-technical to the large pilot plant as well as the harmonization of gas generation and gas refining was proved. (orig.) With 20 refs., 20 tabs., 81 figs [de

Effects of different drying processes on the concentrations of metals and metalloids in plant materials

International Nuclear Information System (INIS)

Anawar, H.M.; Canha, N.; Freitas, M.C; Santa Regina, I.; Garcia-Sanchez, A.

2011-01-01

The drying process of fresh plant materials may affect the porous structure, dehydration and a number of quality characteristics of these materials. Therefore, this study has investigated the effect of different drying processes on the variation of metal and metalloid concentrations in the dried plant materials. Seven varieties of native plant species collected from Sao Domingos mine were analyzed by instrumental neutron activation analysis (INAA) to investigate the effects of freeze-drying (FD), ambient air-drying (AAD) and oven-drying (OD) process on the concentrations of metals and metalloids in the plant biomass. Comparison of ambient air-dried, oven-dried and freeze-dried preparations allows a phenomenological description of the dehydration artefacts. In the quantitative analysis of metals and metalloids, FD and OD plant samples show the higher concentrations of metals and metalloids when compared to those in the AAD plant biomass. The freeze-drying process is comparatively reliable for determination of metals and metalloids concentrations in plant materials. (author)

Radiological hazards assessment at mineral processing plants in Malaysia

International Nuclear Information System (INIS)

Mohd Tadza Abdul Rahman; Shamsul Bahrin Ludin; Mohd Yusof Harun; Amran Kamaruddin; Abdul Hamid Latip; Mohd Azwar Hashim

1994-01-01

The estimated total dose due to radiation received by workers at the minerals processing plants in Malaysia based on area monitoring data. The dose was evaluated using three main parameters, namely exposures from external radiation, inhalation of airborne radioactive dusts and radon/thoron progenies. The study shows that workers at different location in the plants are potentially exposed to in excess of one tenth (1/10) and three tenth (3/10) of the annual dose limit. (author)

Large-scale methanol plants. [Based on Japanese-developed process

Energy Technology Data Exchange (ETDEWEB)

Tado, Y

1978-02-01

A study was made on how to produce methanol economically which is expected as a growth item for use as a material for pollution-free energy or for chemical use, centering on the following subjects: (1) Improvement of thermal economy, (2) Improvement of process, and (3) Problems of hardware attending the expansion of scale. The results of this study were already adopted in actual plants, obtaining good results, and large-scale methanol plants are going to be realized.

Nuclear fuel re-processing plant

International Nuclear Information System (INIS)

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

1989-01-01

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

Advance purex process for the new reprocessing plants in France and in Japan

International Nuclear Information System (INIS)

Viala, M.

1991-01-01

In the early Eighties, Japanese utilities formed the Japan Nuclear Fuel Service Co (JNFS), which is in charge of the construction and the operation of the first commercial reprocessing plant in Japan to be erected in Rokkasho Village, Aomori Prefecture. Following a thorough worldwide examination of available processes and technologies, JNFS selected the French technology developed for UP3 and UP2 800 for the plants' main facilities. For these three new plants, the 40-year old PUREX process which is used worldwide for spent fuel reprocessing, has been significantly improved. This paper describes some of the innovative features of the selected processes

SignalPlant: an open signal processing software platform.

Science.gov (United States)

Plesinger, F; Jurco, J; Halamek, J; Jurak, P

2016-07-01

The growing technical standard of acquisition systems allows the acquisition of large records, often reaching gigabytes or more in size as is the case with whole-day electroencephalograph (EEG) recordings, for example. Although current 64-bit software for signal processing is able to process (e.g. filter, analyze, etc) such data, visual inspection and labeling will probably suffer from rather long latency during the rendering of large portions of recorded signals. For this reason, we have developed SignalPlant-a stand-alone application for signal inspection, labeling and processing. The main motivation was to supply investigators with a tool allowing fast and interactive work with large multichannel records produced by EEG, electrocardiograph and similar devices. The rendering latency was compared with EEGLAB and proves significantly faster when displaying an image from a large number of samples (e.g. 163-times faster for 75  ×  10(6) samples). The presented SignalPlant software is available free and does not depend on any other computation software. Furthermore, it can be extended with plugins by third parties ensuring its adaptability to future research tasks and new data formats.

Nuclear heat source design for an advanced HTGR process heat plant

International Nuclear Information System (INIS)

McDonald, C.F.; O'Hanlon, T.W.

1983-01-01

A high-temperature gas-cooled reactor (HTGR) coupled with a chemical process facility could produce synthetic fuels (i.e., oil, gasoline, aviation fuel, methanol, hydrogen, etc.) in the long term using low-grade carbon sources (e.g., coal, oil shale, etc.). The ultimate high-temperature capability of an advanced HTGR variant is being studied for nuclear process heat. This paper discusses a process heat plant with a 2240-MW(t) nuclear heat source, a reactor outlet temperature of 950 0 C, and a direct reforming process. The nuclear heat source outputs principally hydrogen-rich synthesis gas that can be used as a feedstock for synthetic fuel production. This paper emphasizes the design of the nuclear heat source and discusses the major components and a deployment strategy to realize an advanced HTGR process heat plant concept

Transuranium radionuclide pollution in the waters of the La Maddalena National Marine Park

International Nuclear Information System (INIS)

Aumento, F.; Le Donne, K.; Eroe, K.

2005-01-01

Following the grounding and subsequent explosion, in October 2003, of a nuclear submarine in the waters of the La Maddalena National Marine Park, fears arose of possible radioactive leakages. However, isotopic analyses on algae showed that the gamma-ray emitting artificial radionuclides that one might expect to leak from a damaged nuclear reactor (such as U-235, I-131, Cs-137) were absent, and that U-238/U-234 activities were in equilibrium with values typical of sea water; this excluded any direct anthropogenic contamination as a result of the accident. We used alpha autoradiographic techniques to detect possible traces of transuranium radionuclides; 160 samples of algae, granites, sea urchins, gastropods, limpets, cuttlefish and jellyfish were collected from the area, as well as from other Mediterranean coastlines and the Baltic Sea. All samples were autoradiographed, and selected samples further analysed by alpha spectrometry. There were no alpha track concentrations above background levels in our control Mediterranean specimens. In the samples from the La Maddalena and Baltic areas two different track distributions were observed:-those homogeneously distributed over the surfaces examined; -groups (10 to over 500) of radially distributed alpha tracks (forming 'star' bursts, or 'hot spots') emanating from point sources. By comparing radionuclide activities measured by alpha spectroscopy with alpha track densities, we extrapolated Pu activities for all samples. About 74% of algae had Pu activities of less than 1Bq/kg and 0.25Bq/kg, 16% had accumulated Pu to levels between 1 and 2Bq/kg, and a very few specimens had concentrations between 2 and 6Bq/kg. Plots showed that alpha tracks and stars concentrate around the northern and eastern margins of the Rada (Basin) di Santo Stefano, sites facing the nuclear submarine base on the eastern shore of the island of Santo Stefano. What is the source of these nuclides: last century's atmospheric nuclear testing, Chernobyl or

Using graph theory to analyze the vulnerability of process plants in the context of cascading effects

International Nuclear Information System (INIS)

Khakzad, Nima; Reniers, Genserik

2015-01-01

Dealing with large quantities of flammable and explosive materials, usually at high-pressure high-temperature conditions, makes process plants very vulnerable to cascading effects compared with other infrastructures. The combination of the extremely low frequency of cascading effects and the high complexity and interdependencies of process plants makes risk assessment and vulnerability analysis of process plants very challenging in the context of such events. In the present study, cascading effects were represented as a directed graph; accordingly, the efficacy of a set of graph metrics and measurements was examined in both unit and plant-wide vulnerability analysis of process plants. We demonstrated that vertex-level closeness and betweenness can be used in the unit vulnerability analysis of process plants for the identification of critical units within a process plant. Furthermore, the graph-level closeness metric can be used in the plant-wide vulnerability analysis for the identification of the most vulnerable plant layout with respect to the escalation of cascading effects. Furthermore, the results from the application of the graph metrics have been verified using a Bayesian network methodology. - Highlights: • Graph metrics can effectively be employed to identify vulnerable units and layouts in process plants. • Units with larger vertex-level closeness result in more probable and severe cascading effects. • Units with larger vertex-level betweenness contribute more to the escalation of cascading effects. • Layouts with larger graph-level closeness are more vulnerable to the escalation of cascading effects

Impacts of oil sands process water on fen plants: Implications for plant selection in required reclamation projects

International Nuclear Information System (INIS)

Pouliot, Rémy; Rochefort, Line; Graf, Martha D.

2012-01-01

Fen plant growth in peat contaminated with groundwater discharges of oil sands process water (OSPW) was assessed in a greenhouse over two growing seasons. Three treatments (non-diluted OSPW, diluted OSPW and rainwater) were tested on five vascular plants and four mosses. All vascular plants tested can grow in salinity and naphthenic acids levels currently produced by oil sands activity in northwestern Canada. No stress sign was observed after both seasons. Because of plant characteristics, Carex species (C. atherodes and C. utriculata) and Triglochin maritima would be more useful for rapidly restoring vegetation and creating a new peat-accumulating system. Groundwater discharge of OSPW proved detrimental to mosses under dry conditions and ensuring adequate water levels would be crucial in fen creation following oil sands exploitation. Campylium stellatum would be the best choice to grow in contaminated areas and Bryum pseudotriquetrum might be interesting as it has spontaneously regenerated in all treatments. - Highlights: ► Fen plant growth was assessed under groundwater discharges of oil sands process water. ► Sedge and grass species were not stressed after two growing seasons in greenhouse. ► Carex species and Triglochin maritima would be helpful in created contaminated fens. ► In dry conditions, contaminated groundwater discharge was detrimental for mosses. ► Campylium stellatum would be the best choice in created fens with contaminated water. - Sedges and grasses tolerated the contact with oil sands process water and could probably grow well in contaminated created fens, but mosses were particularly affected under dry conditions.

Improving sustainability of maize to ethanol processing by plant breeding and process optimization

NARCIS (Netherlands)

Slegers, P.M.; Torres Salvador, A.F.; Boxtel, van A.J.B.; Trindade, L.M.

2017-01-01

Efficient management of plant resources is essential for a sustainable biobased economy. The biomass conversion efficiency and sustainability performance depend greatly on the choice of feedstock and the applied processing technology. The aim of this research was to enhance the biomass use of maize

Maintenance of process instrumentation in nuclear power plants

CERN Document Server

Hashemian, H M

2006-01-01

Compiles 30 years of practical knowledge gained by the author and his staff in testing the I and C systems of nuclear power plants around the world. This book focuses on process temperature and pressure sensors and the verification of these sensors' calibration and response time.

Prevalence and Persistence of Listeria monocytogenes in Ready-to-Eat Tilapia Sashimi Processing Plants.

Science.gov (United States)

Chen, Bang-Yuan; Wang, Chung-Yi; Wang, Chia-Lan; Fan, Yang-Chi; Weng, I-Ting; Chou, Chung-Hsi

2016-11-01

A 2-year study was performed at two ready-to-eat tilapia sashimi processing plants (A and B) to identify possible routes of contamination with Listeria monocytogenes during processing. Samples were collected from the aquaculture environments, transportation tanks, processing plants, and final products. Seventy-nine L. monocytogenes isolates were found in the processing environments and final products; 3.96% (50 of 1,264 samples) and 3.86% (29 of 752 samples) of the samples from plants A and B, respectively, were positive for L. monocytogenes . No L. monocytogenes was detected in the aquaculture environments or transportation tanks. The predominant L. monocytogenes serotypes were 1/2b (55.70%) and 4b (37.97%); serotypes 3b and 4e were detected at much lower percentages. At both plants, most processing sections were contaminated with L. monocytogenes before the start of processing, which indicated that the cleaning and sanitizing methods did not achieve adequate pathogen removal. Eleven seropulsotypes were revealed by pulsed-field gel electrophoresis and serotyping. Analysis of seropulsotype distribution revealed that the contamination was disseminated by the processing work; the same seropulsotypes were repeatedly found along the work flow line and in the final products. Specific seropulsotypes were persistently found during different sampling periods, which suggests that the sanitation procedures or equipment used at these plants were inadequate. Plant staff should improve the sanitation procedures and equipment to reduce the risk of L. monocytogenes cross-contamination and ensure the safety of ready-to-eat tilapia products.

Maintenance of process instrumentation in nuclear power plants

International Nuclear Information System (INIS)

Hashemian, H.M.

2006-01-01

The resurgence of the nuclear power industry at a time when the nuclear plant I and C workforce is diminishing due to aging and retirements has been the motivation for writing this book. This book compiles 30 years of practical knowledge gained by the author and his staff in testing the I and C systems of nuclear power plants around the world. It focuses on process temperature and pressure sensors and the verification of these sensors' calibration and response time. In spite of great advances in electronics, computers, and measurement technologies, important process parameters such as temperature and pressure are still measured with conventional sensing techniques found in RTDs, thermocouples, and conventional pressure and differential pressure sensors. Furthermore, no improved technology providing comparable performance is currently on the horizon. Therefore, it is important to understand how these sensors function and the testing techniques for verifying their performance. This book is intended to help provide this understanding. (orig.)

A new advanced software platform for nuclear power plant process information systems

International Nuclear Information System (INIS)

Sorsa, A.

1993-01-01

In the late 80s, ABB Stromberg Power Ltd. started the development of a new generation software platform for the power plant Process Information System (PIS). This development resulted in a software platform called Procontrol PMS. Procontrol PMS is a platform for fully distributed systems which provides the following features: distributed data processing, non-stop architecture, low-cost incremental expansion path, open network architecture, high functionality, effective application development environment, and advanced user interface services. A description of the structure of the Procontrol PMS software is given. ABB has received by May 1992 six orders for nuclear power plant PISs based on Procontrol PMS (4 for PWR plants, 2 for BWRs). The first Procontrol PMS based nuclear power plant PIS was commissioned in 1989 at the Loviisa nuclear power plant and has been running with 100% availability since the commissioning. (Z.S.) 2 figs

Long term developments in irradiated natural uranium processing costs. Optimal size and siting of plants

International Nuclear Information System (INIS)

Thiriet, L.

1964-01-01

The aim of this paper is to help solve the problem of the selection of optimal sizes and sites for spent nuclear fuel processing plants associated with power capacity programmes already installed. Firstly, the structure of capital and running costs of irradiated natural uranium processing plants is studied, as well as the influence of plant sizes on these costs and structures. Shipping costs from the production site to the plant must also be added to processing costs. An attempt to reach a minimum cost for the production of a country or a group of countries must therefore take into account both the size and the location of the plants. The foreseeable shipping costs and their structure (freight, insurance, container cost and depreciation), for spent natural uranium are indicated. Secondly, for various annual spent fuel reprocessing programmes, the optimal sizes and locations of the plants are determined. The sensitivity of the results to the basic assumptions relative to processing costs, shipping costs, the starting up year of the plant programme and the length of period considered, is also tested. - this rather complex problem, of a combinative nature, is solved through dynamic programming methods. - It is shown that these methods can also be applied to the problem of selecting the optimal sizes and locations of processing plants for MTR type fuel elements, related to research reactor programmes, as well as to future plutonium element processing plants related to breeder reactors. Thirdly, the case where yearly extraction of the plutonium contained in the irradiated natural uranium is not compulsory is examined; some stockpiling of the fuel is then allowed some years, entailing delayed processing. The load factor of such plants is thus greatly improved with respect to that of plants where the annual plutonium demand is strictly satisfied. By including spent natural uranium stockpiling costs an optimal rhythm of introduction and optimal sizes for spent fuel

The KALPUREX-process – A new vacuum pumping process for exhaust gases in fusion power plants

Energy Technology Data Exchange (ETDEWEB)

Giegerich, Thomas, E-mail: thomas.giegerich@kit.edu; Day, Christian

2014-10-15

Highlights: • A new vacuum pumping process for fusion power plants has been developed and is presented in this paper. • This process works continuously and non-cryogenic what leads to a strong reduction of the tritium inventory in the fuel cycle. • This pumping process is based on the use of a liquid metal (mercury) as working fluid and is called KALPUREX process. • The KALPUREX process is the technical realization of the DIR concept using a set of three vacuum pumps (metal foil pump/diffusion pump/liquid ring pump). • This paper discusses the arrangement of the pumps and also the required infrastructure for operation. - Abstract: The Karlsruhe Institute of Technology (KIT) is developing a continuously working and non-cryogenic pumping solution for torus exhaust pumping of a demonstration power plant (DEMO) including Direct Internal Recycling (DIR). This full pumping system consists of three pumps, namely a metal foil pump for gas separation, a linear diffusion pump as primary pump and a liquid ring pump as backing pump. The latter two pumps apply mercury as working fluid due to its perfect tritium compatibility. This asks for a baffle system on both sides of the pumping train to control working fluid vapour and to avoid any mercury propagation in the machine. In this paper, the arrangement of all torus pumps required for a power plant reactor as well as the corresponding infrastructure and its effect on the DEMO machine design is presented and discussed. The full pumping process is called ‘Karlsruhe liquid metal based pumping process for fusion reactor exhaust gases’ (KALPUREX process, patent pending)

The KALPUREX-process – A new vacuum pumping process for exhaust gases in fusion power plants

International Nuclear Information System (INIS)

Giegerich, Thomas; Day, Christian

2014-01-01

Highlights: • A new vacuum pumping process for fusion power plants has been developed and is presented in this paper. • This process works continuously and non-cryogenic what leads to a strong reduction of the tritium inventory in the fuel cycle. • This pumping process is based on the use of a liquid metal (mercury) as working fluid and is called KALPUREX process. • The KALPUREX process is the technical realization of the DIR concept using a set of three vacuum pumps (metal foil pump/diffusion pump/liquid ring pump). • This paper discusses the arrangement of the pumps and also the required infrastructure for operation. - Abstract: The Karlsruhe Institute of Technology (KIT) is developing a continuously working and non-cryogenic pumping solution for torus exhaust pumping of a demonstration power plant (DEMO) including Direct Internal Recycling (DIR). This full pumping system consists of three pumps, namely a metal foil pump for gas separation, a linear diffusion pump as primary pump and a liquid ring pump as backing pump. The latter two pumps apply mercury as working fluid due to its perfect tritium compatibility. This asks for a baffle system on both sides of the pumping train to control working fluid vapour and to avoid any mercury propagation in the machine. In this paper, the arrangement of all torus pumps required for a power plant reactor as well as the corresponding infrastructure and its effect on the DEMO machine design is presented and discussed. The full pumping process is called ‘Karlsruhe liquid metal based pumping process for fusion reactor exhaust gases’ (KALPUREX process, patent pending)

Development of partitioning process: purification of DIDPA

Energy Technology Data Exchange (ETDEWEB)

Watanabe, Masayuki; Morita, Yasuji; Kubota, Masumitsu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-04-01

The partitioning process has developed and demonstrated that the solvent extraction with diisodecylphosphoric acid (DIDPA) can successfully separate transuranium elements from a high-level liquid waste. In the solvent extraction, DIDPA is decomposed by radiolysis and hydrolysis. The main degradation product is monoisodecyl phosphoric acid (MIDPA). Ethylene glycol has been used for removing the product by a solvent extraction method. However this method has two drawbacks that two phases separate slowly and the used ethylene glycol is not regeneratable. First it was found that the addition of acetone or methanol with 20 volume % improved the phase separation. Then a new purification method was developed by using an aqueous solution of methanol or acetone. The new purification method is as excellent as the ethylene glycol method for the removal of MIDPA. (author)

Safety implications of computerized process control in nuclear power plants

International Nuclear Information System (INIS)

1991-02-01

Modern nuclear power plants are making increasing use of computerized process control because of the number of potential benefits that accrue. This practice not only applies to new plants but also to those in operation. Here, the replacement of both conventional process control systems and outdated computerized systems is seen to be of benefit. Whilst this contribution is obviously of great importance to the viability of nuclear electricity generation, it must be recognized that there are major safety concerns in taking this route. However, there is the potential for enhancing the safety of nuclear power plants if the full power of microcomputers and the associated electronics is applied correctly through well designed, engineered, installed and maintained systems. It is essential that areas where safety can be improved be identified and that the pitfalls are clearly marked so that they can be avoided. The deliberations of this Technical Committee Meeting are a step on the road to this goal of improved safety through computerized process control. This report also contains the papers presented at the technical committee meeting by participants. A separate abstract was prepared for each of these 15 presentations. Refs, figs and tabs

Multilevel flow modelling of process plant for diagnosis and control

International Nuclear Information System (INIS)

Lind, M.

1982-08-01

The paper describes the multilevel flow modelling methodology which can be used to construct functional models of energy and material processing systems. The models describe mass and energy flow topology on different levels of abstraction and represent the hierarchical functional structure of complex systems. A model of a nuclear power plant (PWR) is presented in the paper for illustration. Due to the consistency of the method, multilevel flow models provide specifications of plant goals and functions and may be used as a basis for design of computer-based support systems for the plant operator. Plant control requirements can be derived from the models and due to independence of the actual controller implementation the method may be used as basic for design of control strategies and for the allocation of control tasks to the computer and the plant operator. (author)

Multilevel Flow Modelling of Process Plant for Diagnosis and Control

DEFF Research Database (Denmark)

Lind, Morten

1982-01-01

The paper describes the multilevel flow modelling methodology which can be used to construct functional models of energy and material processing systems. The models describe mass and energy flow topology on different levels of abstraction and represent the hierarchical functional structure...... of complex systems. A model of a nuclear power plant (PWR) is presented in the paper for illustration. Due to the consistency of the method, multilevel flow models provide specifications of plant goals and functions and may be used as a basis for design of computer-based support systems for the plant...... operator. Plant control requirements can be derived from the models and due to independence of the actual controller implementation the method may be used as a basis for design of control strategies and for the allocation of control tasks to the computer and the plant operator....

Lithium actinide recycle process demonstration

Energy Technology Data Exchange (ETDEWEB)

Johnson, G.K.; Pierce, R.D.; McPheeters, C.C. [Argonne National Laboratory, IL (United States)

1995-10-01

Several pyrochemical processes have been developed in the Chemical Technology Division of Argonne Laboratory for recovery of actinide elements from LWR spent fuel. The lithium process was selected as the reference process from among the options. In this process the LWR oxide spent fuel is reduced by lithium at 650{degrees}C in the presence of molten LiCl. The Li{sub 2}O formed during the reduction process is soluble in the salt. The spent salt and lithium are recycled after the Li{sub 2}O is electrochemically reduced. The oxygen is liberated as CO{sub 2} at a carbon anode or oxygen at an inert anode. The reduced metal components of the LWR spent fuel are separated from the LiCL salt phase and introduced into an electrorefiner. The electrorefining step separates the uranium and transuranium (TRU) elements into two product streams. The uranium product, which comprises about 96% of the LWR spent fuel mass, may be enriched for recycle into the LWR fuel cycle, stored for future use in breeder reactors, or converted to a suitable form for disposal as waste. The TRU product can be recycled as fast reactor fuel or can be alloyed with constituents of the LWR cladding material to produce a stable waste form.

Characterization of process air emissions in automotive production plants.

Science.gov (United States)

D'Arcy, J B; Dasch, J M; Gundrum, A B; Rivera, J L; Johnson, J H; Carlson, D H; Sutherland, J W

2016-01-01

During manufacturing, particles produced from industrial processes become airborne. These airborne emissions represent a challenge from an industrial hygiene and environmental standpoint. A study was undertaken to characterize the particles associated with a variety of manufacturing processes found in the auto industry. Air particulates were collected in five automotive plants covering ten manufacturing processes in the areas of casting, machining, heat treatment and assembly. Collection procedures provided information on air concentration, size distribution, and chemical composition of the airborne particulate matter for each process and insight into the physical and chemical processes that created those particles.

Example of an in-plant near-real-time accountancy/process control system

International Nuclear Information System (INIS)

Anon.

1981-01-01

This session describes an existing computerized in-plant near-real-time accounting and process monitoring system at the Allied-General Nuclear Services (AGNS) Barnwell Nuclear Fuel Plant (BNFP). Details of the system performance, objectives, hardware, plant instrumentation, and system functions are presented. Examples of actual programs for accounting and monitoring are described and system benefits will be discussed. The purpose of this session is to enable participants to: (1) identify the major computer hardware components of functional near-real-time accounting systems; (2) identify the types of process instrumentation necessary to perform near-real-time accounting; (3) describe the major nuclear material control and accounting functions of the AGNS computer system; and (4) assess the benefits to safeguards and plant operations of a computerized near-real-time accounting system

Advanced Purex process for the new French reprocessing plants

International Nuclear Information System (INIS)

Viala, M.; Ledermann, P.; Pradel, P.

1993-01-01

The paper describes the main process innovations of the new Cogema reprocessing plants of La Hague (UP3 and UP2 800). Major improvements of process like the use of rotary dissolvers and annular columns, and also entirely new processes like solvent distillation and plutonium oxidizing dissolution, yield an advanced Purex process. The results of these innovations are significant improvements for throughput, end-products purification performances and waste minimization. They contribute also to limit personnel exposure. The main results of the first three years of operation are described. (author). 3 refs., 5 figs

Modeling of plant in vitro cultures: overview and estimation of biotechnological processes.

Science.gov (United States)

Maschke, Rüdiger W; Geipel, Katja; Bley, Thomas

2015-01-01

Plant cell and tissue cultivations are of growing interest for the production of structurally complex and expensive plant-derived products, especially in pharmaceutical production. Problems with up-scaling, low yields, and high-priced process conditions result in an increased demand for models to provide comprehension, simulation, and optimization of production processes. In the last 25 years, many models have evolved in plant biotechnology; the majority of them are specialized models for a few selected products or nutritional conditions. In this article we review, delineate, and discuss the concepts and characteristics of the most commonly used models. Therefore, the authors focus on models for plant suspension and submerged hairy root cultures. The article includes a short overview of modeling and mathematics and integrated parameters, as well as the application scope for each model. The review is meant to help researchers better understand and utilize the numerous models published for plant cultures, and to select the most suitable model for their purposes. © 2014 Wiley Periodicals, Inc.

Standard format and content of license applications for plutonium processing and fuel fabrication plants

International Nuclear Information System (INIS)

1976-01-01

The standard format suggested for use in applications for licenses to possess and use special nuclear materials in Pu processing and fuel fabrication plants is presented. It covers general description of the plant, summary safety assessment, site characteristics, principal design criteria, plant design, process systems, waste confinement and management, radiation protection, accident safety analysis, conduct of operations, operating controls and limits, and quality assurance

Frequency of hepatitis E virus, rotavirus and porcine enteric calicivirus at various stages of pork carcass processing in two pork processing plants.

Science.gov (United States)

Jones, Tineke H; Muehlhauser, Victoria

2017-10-16

Hepatitis E virus (HEV), rotavirus (RV), and porcine enteric calicivirus (PEC) infections are common in swine and raises concerns about the potential for zoonotic transmission through undercooked meat products. Enteric viruses can potentially contaminate carcasses during meat processing operations. There is a lack of information on the prevalence and control of enteric viruses in the pork processing chain. This study compared the incidence and levels of contamination of hog carcasses with HEV, RV and PEC at different stages of the dressing process. A total of 1000 swabs were collected from 2 pork processing plants on 10 separate occasions over the span of a year. The samples were obtained from random sites on hog carcasses at 4 dressing stages (plant A: bleeding, dehairing, pasteurization, and evisceration; plant B: bleeding, skinning, evisceration, and washing) and from meat cuts. Numbers of genome copies (gc) of HEV, RV and PEC were determined by RT-qPCR. RV and PEC were detected in 100%, and 18% of samples, respectively, after bleeding for plant A and in 98%, and 36% of samples, respectively, after bleeding for plant B. After evisceration, RV and PEC were detected in 21% and 3% of samples, respectively, for plant A and in 1%, and 0% of samples, respectively for plant B. RV and PEC were detected on 1%, and 5% of pork cuts, respectively, for plant A and on 0%, and 0% of pork cuts, respectively, for plant B. HEV was not detected in any pork carcass or retail pork samples from plants A or B. The frequency of PEC and RV on pork is progressively reduced along the pork processing chain but the viruses were not completely eliminated. The findings suggest that consumers could be at risk when consuming undercooked meat contaminated with pathogenic enteric viruses. Crown Copyright © 2017. Published by Elsevier B.V. All rights reserved.

Potential use of advanced process control for safety purposes during attack of a process plant

International Nuclear Information System (INIS)

Whiteley, James R.

2006-01-01

Many refineries and commodity chemical plants employ advanced process control (APC) systems to improve throughputs and yields. These APC systems utilize empirical process models for control purposes and enable operation closer to constraints than can be achieved with traditional PID regulatory feedback control. Substantial economic benefits are typically realized from the addition of APC systems. This paper considers leveraging the control capabilities of existing APC systems to minimize the potential impact of a terrorist attack on a process plant (e.g., petroleum refinery). Two potential uses of APC are described. The first is a conventional application of APC and involves automatically moving the process to a reduced operating rate when an attack first begins. The second is a non-conventional application and involves reconfiguring the APC system to optimize safety rather than economics. The underlying intent in both cases is to reduce the demands on the operator to allow focus on situation assessment and optimal response planning. An overview of APC is provided along with a brief description of the modifications required for the proposed new applications of the technology

Data processing project management in the construction of plants and power stations

International Nuclear Information System (INIS)

Huelsen, H.; Hayen, W.

1987-01-01

The requirements of project management in plant construction i.e. basic data, supervision and control became more and more detailed. These requirements can only satisfactorily be met with the help of data processing. Piping design requires up to 50% of the whole amount of engineering in design and management of plant construction. We present data processing project management system which explains the connections of single aspects. Its connections consists of: collection of basic data, plant design and installation, supervision of planning and installation, planning and calculation, collection, use, administration and approval of plan data, procurement material, construction of the model (1:25), and installation. (orig.) [de

Preliminary design needs for pilot plant of Monazite processing into Thorium Oxide (ThO_2)

International Nuclear Information System (INIS)

Hafni Lissa Nuri; Prayitno; Abdul Jami; M-Pancoko

2014-01-01

Data and information collection aimed in order to meet the needs of the initial design for pilot plant of monazite processing into thorium oxide (ThO_2). The content of thorium in monazite is high in Indonesia between 2.9 to 4.1% and relatively abundant in Bangka Belitung Islands. Thorium can be used as fuel because of its potential is more abundant instead of uranium. Plant of thorium oxide commercially from monazite established starting from pilot uranium. Plant of thorium oxide commercially from monazite established starting from pilot plant in order to test laboratory data. Pilot plant design started from initial design, basic design, detailed design, procurement and construction. Preliminary design needs includes data feed and products, a block diagram of the process, a description of the process, the determination of process conditions and type of major appliance has been conducted. (author)

Model experiments on depressurisation accidents in nuclear process heat plants (HTGR)

Energy Technology Data Exchange (ETDEWEB)

Fritsching, G.; Wolf, G. [Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.)

1981-01-15

The analysis of depressurisation accidents requires the use of digital computer programs to find out the dynamic loads acting on the plant structures. Because of the importance of such accidents in safety and licensing procedures of nuclear process heat plants, it is necessary to compare these computer results with suitable experiments to show the accuracy and the limits of the programs in question. For this purpose a series of depressurisation experiments has been started at INTERATOM on a small scale model of a primary loop of a nuclear process heat plant. Using the results of these experiments three different computer programs were tested with good success. The development of the experimental program and the estimation of the results was carried out in co-operation with KFA-Juelich and the Technische Hochschule Aachen.

Model experiments on depressurisation accidents in nuclear process heat plants (HTGR)

International Nuclear Information System (INIS)

Fritsching, G.; Wolf, G.

1981-01-01

The analysis of depressurisation accidents requires the use of digital computer programs to find out the dynamic loads acting on the plant structures. Because of the importance of such accidents in safety and licensing procedures of nuclear process heat plants, it is necessary to compare these computer results with suitable experiments to show the accuracy and the limits of the programs in question. For this purpose a series of depressurisation experiments has been started at INTERATOM on a small scale model of a primary loop of a nuclear process heat plant. Using the results of these experiments three different computer programs were tested with good success. The development of the experimental program and the estimation of the results was carried out in co-operation with KFA-Juelich and the Technische Hochschule Aachen

Continuous precipitation of uranium peroxide in process pilot plant

International Nuclear Information System (INIS)

Quinelato, A.L.

1990-01-01

An experimental study on uranium peroxide precipitation has been carried out with the objective to evaluate the influence of the main process parameters with a technological approach. The uraniferous solution used was obtained from the hydrometallurgical processing of an ore from Itataia - CE. Studies were developed in two distinct experimental stages. In the first stage, the precipitation was investigated by means of laboratory batch tests and, in the second stage, by means of continuous operation in a process pilot plant. (author)

Process simulation of heavy water plants - a powerful analytical tool

International Nuclear Information System (INIS)

Miller, A.I.

1978-10-01

The commercially conscious designs of Canadian GS (Girdler-Sulphide) have proved sensitive to process conditions. That, combined with the large scale of our units, has meant that computer simulation of their behaviour has been a natural and profitable development. Atomic Energy of Canada Limited has developed a family of steady state simulations to describe all of the Canadian plants. Modelling of plant conditions has demonstrated that the simulation description is very precise and it has become an integral part of the industry's assessments of both plant operation and decisions on capital expenditures. The simulation technique has also found extensive use in detailed designing of both the rehabilitated Glace Bay and the new La Prade plants. It has opened new insights into plant design and uncovered a radical and significant flowsheet change for future designs as well as many less dramatic but valuable lesser changes. (author)

Efficiency of Sanitary Treatment in Poultry Breeding and Poultry Meat Processing Plant

Directory of Open Access Journals (Sweden)

A. Kašková

2006-01-01

Full Text Available The aim of this study was to observe the effectiveness of disinfection on a broiler farm and in a plant processing the poultry from this farm. The broiler farm was disinfected with a preparation based on peracetic acid while a preparation based on quarternary ammonium salt was used in the processing plant. We evaluated swabs taken from surfaces, which come into contact with broilers and broiler meat. Results of the swabs taken by standard microbiological swabbing method were evaluated with results of the swabs taken by the ATP-bioluminescence method. The microbiological examination included total counts of microorganisms, coliform count and moulds. When using the standard plate counts method on the broiler farm we found that the plate counts in 0% of swabs were 100 CFU. In the processing plant, out of 22% of swabs 100. The bioluminescence method was applied only in the processing plant where 300 RLU were measured in 80, 10 and 10% of swabs, resp. Our observations and results allowed us to conclude that the disinfectants tested appeared suitable for the respective premises and the ATP bioluminescence method could be use as a as a suitable complement for detection of cleanliness of individual surfaces.

Plant-based remediation processes

Energy Technology Data Exchange (ETDEWEB)

Gupta, Dharmendra Kumar (ed.) [Belgian Nuclear Research Centre (SCK.CEN), Mol (Belgium). Radiological Impact and Performance Assessment Division

2013-11-01

A valuable source of information for scientists in the field of environmental pollution and remediation. Describes the latest biotechnological methods for the treatment of contaminated soils. Includes case studies and protocols. Phytoremediation is an emerging technology that employs higher plants for the clean-up of contaminated environments. Basic and applied research have unequivocally demonstrated that selected plant species possess the genetic potential to accumulate, degrade, metabolize and immobilize a wide range of contaminants. The main focus of this volume is on the recent advances of technologies using green plants for remediation of various metals and metalloids. Topics include biomonitoring of heavy metal pollution, amendments of higher uptake of toxic metals, transport of heavy metals in plants, and toxicity mechanisms. Further chapters discuss agro-technological methods for minimizing pollution while improving soil quality, transgenic approaches to heavy metal remediation and present protocols for metal remediation via in vitro root cultures.

Simulation of Plant Physiological Process Using Fuzzy Variables

Science.gov (United States)

Daniel L. Schmoldt

1991-01-01

Qualitative modelling can help us understand and project effects of multiple stresses on trees. It is not practical to collect and correlate empirical data for all combinations of plant/environments and human/climate stresses, especially for mature trees in natural settings. Therefore, a mechanistic model was developed to describe ecophysiological processes. This model...

Process and apparatus for detecting presence of plant substances

International Nuclear Information System (INIS)

Kirby, J.A.

1991-01-01

This patent describes an apparatus and process for detecting the presence of plant substances in a particular environment. It comprises: measuring the background K40 gamma ray radiation level in a particular environment with a 1.46 MeV gamma ray counter system; measuring the amount of K40 gamma ray radiation emanating from a package containing a plant substance being passed through an environment with a counter; and generating an alarm signal when the total K40 gamma ray radiation reaches a predetermined level over and above the background level

Processing of transuranic waste at the Savannah River Plant

International Nuclear Information System (INIS)

Daugherty, B.A.; Gruber, L.M.; Mentrup, S.J.

1986-01-01

Transuranic wastes at the Savannah River Plant (SRP) have been retrievably stored on concrete pads since early 1972. This waste is stored primarily in 55-gallon drums and large carbon steel boxes. Higher activity drums are placed in concrete culverts. In support of a National Program to consolidate and permanently dispose of this waste, a major project is planned at SRP to retrieve and process this waste. This project, the TRU Waste Facility (TWF), will provide equipment and processes to retrieve TRU waste from 20-year retrievable storage and prepare it for permanent disposal at the Waste Isolation Pilot Plant (WIPP) geological repository in New Mexico. This project is an integral part of the SRP Long Range TRU Waste Management Program to reduce the amount of TRU waste stored at SRP. The TWF is designed to process 15,000 cubic feet of retrieved waste and 6200 cubic feet of newly generated waste each year of operation. This facility is designed to minimize direct personnel contact with the waste using state-of-the-art remotely operated equipment

[Design of a HACCP Plan for the Gouda-type cheesemaking process in a milk processing plant].

Science.gov (United States)

Dávila, Jacqueline; Reyes, Genara; Corzo, Otoniel

2006-03-01

The Hazard Analysis and Critical Control Point (HACCP) is a preventive and systematic method used to identify, assess and control of the hazards related with raw material, ingredients, processing, marketing and intended consumer in order to assure the safety of the food. The aim of this study was to design a HACCP plan for implementing in a Gouda-type cheese-making process in a dairy processing plant. The used methodology was based in the application of the seven principles of the HACCP, the information from the plant about the compliment of the pre-requisite programs (70-80%), the experience of the HACCP team and the sequence of stages settles down by the COVENIN standard 3802 for implementing the HACCP system. A HACCP plan was proposed with the scope, the selection of HACCP team, the description of the product and the intended use, the flow diagram of the process, the hazard analysis and the control table of the plan with the critical control points (CCP). The following CCP were identified in the process: pasteurization, coagulation and ripening.

Flow modelling of plant processes for fault diagnosis

International Nuclear Information System (INIS)

Praetorius, N.; Duncan, K.D.

1989-01-01

Flow and its interruption or degradation is seen by many people in industry to be the essential problem in fault diagnonsis. It is this observation which has motivated the representation of a complex simulation of a process plant presented here. The display system we have developed represents the mass and energy flow functions of the plant and the relationship between such flow functions. In this report we shall mainly discuss how such representation seems to provide opportunities to design alarm systems as an integral part of the flow function representation itself and to solve two of the most intricate problems in diagnosis, namely the problem of symptom referral and the problem of confuseable faults. (author)

Waste processing plant eco-auditing system for minimization of environmental risk: European Communities regulatory proposal

International Nuclear Information System (INIS)

Brunetti, N.

1993-01-01

This paper delineates a system of process control and monitoring checks to be applied to municipal-industrial waste processing and disposal plants to ensure their energy efficient, environmentally safe and reliable operation. In line with European Communities environmental protection strategies, this eco-auditing system requires the preparation of environmental impacts statements on a regular basis during plant operation, as well as, prior to plant start-up. Continuous plant environmental compatibility evaluations are to ascertain: material and energy inputs and outputs; the composition and amounts of exhaust gases released into the atmosphere and the integrity of treatment liquids; control and monitoring instrumentation reliability. The implementation of the auditing system is to be carried out under the supervision of authorized auditing personnel. Waste processing and disposal plants are to make maximum use of energy and materials recovery processes so as to minimize energy consumption and risk to the environment

Effects of feed process variables on Hanford Vitrification Plant performance

International Nuclear Information System (INIS)

Farnsworth, R.K.; Peterson, M.E.; Wagner, R.N.

1987-01-01

As a result of nuclear defense activities, high-level liquid radioactive wastes have been generated at the Hanford Site for over 40 yr. The Hanford Waste Vitrification Plant (HWVP) is being proposed to immobilize these wastes in a waste form suitable for disposal in a geologic repository. Prior to vitrification, the waste will undergo several conditioning steps before being fed to the melter. The effect of certain process variables on the resultant waste slurry properties must be known to assure processability of the waste slurry during feed preparation. Of particular interest are the rheological properties, which include the yield stress and apparent viscosity. Identification of the rheological properties of the slurry is required to adequately design the process equipment used for feed preparation (agitators, mixing tanks, concentrators, etc.). Knowledge of the slurry rheological properties is also necessary to establish processing conditions and operational limits for maximum plant efficiency and reliability. A multivariable study was performed on simulated HWVP feed to identify the feed process variables that have a significant impact on rheology during processing. Two process variables were evaluated in this study: (a) the amount of formic acid added to the feed and (b) the degree of shear encountered by the feed during processing. The feed was physically and rheologically characterized at various stages during feed processing

Seawater desalination plant using nuclear heating reactor coupled with MED process

Institute of Scientific and Technical Information of China (English)

无

2000-01-01

A small size plant for seawater desalination using nuclear heating reactor coupled with MED process was developed by the Institute of Nuclear Energy Technology, Tsinghua University, China. This seawater desalination plant was designed to supply potable water demand to some coastal location or island where both fresh water and energy source are severely lacking. It is also recommended as a demonstration and training facility for seawater desalination using nuclear energy. The design of small size of seawater desalination plant couples two proven technologies: Nuclear Heating Reactor (NHR) and Multi-Effect Destination (MED) process. The NHR design possesses intrinsic and passive safety features, which was demonstrated by the experiences of the project NHR-5. The intermediate circuit and steam circuit were designed as the safety barriers between the NHR reactor and MED desalination system. Within 10～200 MWt of the power range of the heating reactor, the desalination plant could provide 8000 to 150,000 m3/d of high quality potable water. The design concept and parameters, safety features and coupling scheme are presented.

Seawater desalination plant using nuclear heating reactor coupled with MED process

International Nuclear Information System (INIS)

Wu Shaorong; Dong Duo; Zhang Dafang; Wang Xiuzhen

2000-01-01

A small size plant for seawater desalination using nuclear heating reactor coupled with MED process was developed by the Institute of Nuclear Energy Technology, Tsinghua University, China. this seawater desalination plant was designed to supply potable water demand to some coastal location or island where both fresh water and energy source are severely lacking. It is also recommended as a demonstration and training facility for seawater desalination using nuclear energy. The design of small size of seawater desalination plant couples two proven technologies: Nuclear Heating Reactor (NHR) and Multi-Effect Destination (MED) process. The NHR design possesses intrinsic and passive safety features, which was demonstrated by the experiences of the project NHR-5. the intermediate circuit and steam circuit were designed as the safety barriers between the NHR reactor and MED desalination system. Within 10-200 MWt of the power range of the heating reactor, the desalination plant could provide 8000 to 150,000 m 3 /d of high quality potable water. The design concept and parameters, safety features and coupling scheme are presented

Lanthanides, thorium, iodine in terrestrail invertebrates

International Nuclear Information System (INIS)

Zhulidov, A.V.; Pokarzhevskij, A.D.; Katargin, N.V.; AN SSSR, Moscow

1991-01-01

It is shown that among examined terrestrial invertebrates the highest levels on lanthanide and thorium concentration are typical for animals, feeding on plant tissues - earthworms, molluscs, diploid. It is shown that there are no reasons to hope, that regularities of migration of transuranium elements and lanthanides in tropic chains are identical

Concept of a HTR modular plant for generation of process heat in a chemical plant

International Nuclear Information System (INIS)

1991-07-01

This final report summarizes the results of a preliminary study on behalf of Buna AG and Leunawerke AG. With regard to the individual situations the study investigated the conditions for modular HTR-2 reactors to cover on-site process heat and electric power demands. HTR-2 reactor erection and operation were analyzed for their economic efficiency compared with fossil-fuel power plants. Considering the prospective product lines, the technical and economic conditions were developed in close cooperation with Buna AG and Leunawerke AG. The study focused on the technical integration of modular HTR reactors into plants with regard to safety concepts, on planning, acceptance and erection concepts which largely exclude uncalculable scheduling and financial risks, and on comparative economic analyses with regard to fossil-fuel power plants. (orig.) [de

Three essential management processes of nuclear power plant operators

International Nuclear Information System (INIS)

Qi Tunfeng

2010-01-01

The paper takes the operation and management of Qinshan NPP Phase II as an example, focusing on the implementation of the essential process from the following three aspects the NPP production organization, training, examination and authorization for safety-related personnel, and financing budge management. A better understanding and implementation of the essential process will enable nuclear power plants to effectively control the nuclear safety from the most fundamental managerial level. (author)

Basic design of alpha aqueous waste treatment process in NUCEF

Energy Technology Data Exchange (ETDEWEB)

Mineo, Hideaki; Matsumura, Tatsuro; Nishizawa, Ichio; Mitsui, Takeshi; Ueki, Hiroyuki; Wada, Atsushi; Sakai, Ichita; Takeshita, Isao [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Nishimura, Kenji

1996-11-01

This paper described the basic design of Alpha Aqueous Waste Treatment Process in NUCEF. Since various experiments using the TRU (transuranium) elements are carried out in NUCEF, wastes containing TRU elements arise. The liquid wastes in NUCEF are categorized into three types. Decontamination and volume reduction of the liquid waste mainly of recovery water from acid recovery process which has lowest radioactive concentration is the most important task, because the arising rate of the waste is large. The major function of the Alpha Aqueous Waste Treatment Process is to decontaminate the radioactive concentration below the level which is allowed to discharge into sea. Prior the process design of this facility, the followings are evaluated:property and arising rate of the liquid waste, room space to install and licensing condition. Considering varieties of liquid wastes and their large volume, the very high decontamination factor was proposed by a process of multiple evaporation supported with filtration and adsorption in the head end part and reverse osmosis in the distillate part. (author)

Facility for processing the condensates from nuclear power plants (BWR and PWR)

International Nuclear Information System (INIS)

Lucker, Georges.

1975-01-01

A plant for the processing of the condensates from boiling water or pressurized water nuclear power plants is presented. A series of couples of units for the processing of the condensates through mixed beds of ion exchange resins simultaneously ensures the filtration and demineralization of the condensates. When the resins are saturated, each mixed bed is transferred into a unit of regeneration of said resins. Each processing unit is a sphere made of a stainless material, and provided with a plurality of air and water pipes allowing the admission and evacuation of the various elements to be successively controlled [fr

Modeling the high-temperature gas-cooled reactor process heat plant: a nuclear to chemical conversion process

International Nuclear Information System (INIS)

Pfremmer, R.D.; Openshaw, F.L.

1982-05-01

The high-temperature heat available from the High-Temperature Gas-Cooled Reactor (HTGR) makes it suitable for many process applications. One of these applications is a large-scale energy production plant where nuclear energy is converted into chemical energy and stored for industrial or utility applications. This concept combines presently available nuclear HTGR technology and energy conversion chemical technology. The design of this complex plant involves questions of interacting plant dynamics and overall plant control. This paper discusses how these questions were answered with the aid of a hybrid computer model that was developed within the time-frame of the conceptual design studies. A brief discussion is given of the generally good operability shown for the plant and of the specific potential problems and their anticipated solution. The paper stresses the advantages of providing this information in the earliest conceptual phases of the design

People detection in nuclear plants by video processing for safety purpose

Energy Technology Data Exchange (ETDEWEB)

Jorge, Carlos Alexandre F.; Mol, Antonio Carlos A., E-mail: calexandre@ien.gov.b, E-mail: mol@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN), Rio de Janeiro, RJ (Brazil); Seixas, Jose M.; Silva, Eduardo Antonio B., E-mail: seixas@lps.ufrj.b, E-mail: eduardo@lps.ufrj.b [Coordenacao dos Programas de Pos-Graduacao de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Eletrica; Cota, Raphael E.; Ramos, Bruno L., E-mail: brunolange@poli.ufrj.b [Universidade Federal do Rio de Janeiro (EP/UFRJ), RJ (Brazil). Dept. de Engenharia Eletronica e de Computacao

2011-07-01

This work describes the development of a surveillance system for safety purposes in nuclear plants. The final objective is to track people online in videos, in order to estimate the dose received by personnel, during the execution of working tasks in nuclear plants. The estimation will be based on their tracked positions and on dose rate mapping in a real nuclear plant at Instituto de Engenharia Nuclear, Argonauta nuclear research reactor. Cameras have been installed within Argonauta's room, supplying the data needed. Both video processing and statistical signal processing techniques may be used for detection, segmentation and tracking people in video. This first paper reports people segmentation in video using background subtraction, by two different approaches, namely frame differences, and blind signal separation based on the independent component analysis method. Results are commented, along with perspectives for further work. (author)

People detection in nuclear plants by video processing for safety purpose

International Nuclear Information System (INIS)

Jorge, Carlos Alexandre F.; Mol, Antonio Carlos A.; Seixas, Jose M.; Silva, Eduardo Antonio B.; Cota, Raphael E.; Ramos, Bruno L.

2011-01-01

This work describes the development of a surveillance system for safety purposes in nuclear plants. The final objective is to track people online in videos, in order to estimate the dose received by personnel, during the execution of working tasks in nuclear plants. The estimation will be based on their tracked positions and on dose rate mapping in a real nuclear plant at Instituto de Engenharia Nuclear, Argonauta nuclear research reactor. Cameras have been installed within Argonauta's room, supplying the data needed. Both video processing and statistical signal processing techniques may be used for detection, segmentation and tracking people in video. This first paper reports people segmentation in video using background subtraction, by two different approaches, namely frame differences, and blind signal separation based on the independent component analysis method. Results are commented, along with perspectives for further work. (author)

Future trends in power plant process computer techniques

International Nuclear Information System (INIS)

Dettloff, K.

1975-01-01

The development of new concepts of the process computer technique has advanced in great steps. The steps are in the three sections: hardware, software, application concept. New computers with a new periphery such as, e.g., colour layer equipment, have been developed in hardware. In software, a decisive step in the sector 'automation software' has been made. Through these components, a step forwards has also been made in the question of incorporating the process computer in the structure of the whole power plant control technique. (orig./LH) [de

Plant growth regulator interactions in physiological processes for controlling plant regeneration and in vitro development of Tulbaghia simmleri

Czech Academy of Sciences Publication Activity Database

Kumari, A.; Baskaran, P.; Plačková, Lenka; Omámiková, Hana; Nisler, Jaroslav; Doležal, Karel; Van Staden, J.

2018-01-01

Roč. 223, APR (2018), s. 65-71 ISSN 0176-1617 R&D Projects: GA MŠk(CZ) LO1204 Institutional support: RVO:61389030 Keywords : Endogenous hormone * Exogenous hormone application * In vitro regeneration * Ornamental and medicinal plant * Physiological process * Tulbaghia simmleri Subject RIV: EB - Genetics ; Molecular Biology OBOR OECD: Plant sciences, botany Impact factor: 3.121, year: 2016

Hierarchical spatial point process analysis for a plant community with high biodiversity

DEFF Research Database (Denmark)

Illian, Janine B.; Møller, Jesper; Waagepetersen, Rasmus

2009-01-01

A complex multivariate spatial point pattern of a plant community with high biodiversity is modelled using a hierarchical multivariate point process model. In the model, interactions between plants with different post-fire regeneration strategies are of key interest. We consider initially a maxim...

Spatial point process analysis for a plant community with high biodiversity

DEFF Research Database (Denmark)

Illian, Janine; Møller, Jesper; Waagepetersen, Rasmus Plenge

A complex multivariate spatial point pattern for a plant community with high biodiversity is modelled using a hierarchical multivariate point process model. In the model, interactions between plants with different post-fire regeneration strategies are of key interest. We consider initially...... a maximum likelihood approach to inference where problems arise due to unknown interaction radii for the plants. We next demonstrate that a Bayesian approach provides a flexible framework for incorporating prior information concerning the interaction radii. From an ecological perspective, we are able both...

Investigation of the solution properties of the transuranium elements. Final report, July 1, 1979-September 30, 1984

International Nuclear Information System (INIS)

Ensor, D.D.

1984-01-01

This final report summarizes the significant results obtained during our investigation of the fundamental solution properties of the transuranium elements for the period July 1, 1979 to September 30, 1984. Primary interest of the project was the development of improved separation methods for the trivalent actinide elements from each other and from the chemically similar trivalent lanthanide elements using solvent extraction techniques. Two different synergistic systems were investigated. The combination of dialkynaphthalenesulfonic acids with a crown ether or an oxime was an attempt to combine the excellent ion exchange properties of the sulfonic extractant with a synergistic agent which would improve the selectivity of the extraction system. The results showed that the presence of the crown ether improved the extraction of the light lanthanides by approximately 50% while the heavy lanthanides were unaffected. The use of the oxime in combination with the sulfonic acid extractant showed significant enhancement for all metal ions studied but little, if any, selectivity. The use of novel oxygen donors as synergistic agents in combination with thenoyltrifluoroacetone provided significant enhancement for the extraction of trivalent lanthanides and actinides. The data showed the best selectivity was obtained using a linear polyether as the synergistic agent. The crown ether and the cryptand showed significant synergistic capabilities but lacked selectivity due to their rigid cavities. The results of this study indicate that the linear polyether is more promising as a synergistic agent because of its flexibility and ease of chemical modification of the end groups. 10 figures, 5 tables

Saltstone processing startup at the Savannah River Plant

International Nuclear Information System (INIS)

Wilhite, E.L.; Langton, C.A.; Sturm, H.F.; Hooker, R.L.; Occhipinti, E.S.

1988-01-01

High-level nuclear wastes are stored in large underground tanks at the Savannah River Plant. Processing of this waste in preparation for ultimate disposal will begin in 1988. The waste will be processed to separate the high-level radioactive fraction from the low-level radioactive fraction. The separation will be made in existing waste tanks by a process combining precipitation, adsorption, and filtration. The high-level fraction will be vitrified into borosilicate glass in the Defense Waste Processing Facility (DWPF) for permanent disposal in a federal repository. The low-level fraction (decontaminated salt solution) will be mixed with a cementitious slag-flyash blend. The resulting wasteform, saltstone, will be disposed of onsite by emplacement in an engineered facility. Waste properties, disposal facility details, and wasteform characteristics are discussed. In particular, details of saltstone processing, focusing on experience obtained from facility startup, are presented

Prevalence and serotypes of Listeria monocytogenes contamination in Chinese beef processing plants.

Science.gov (United States)

Zhu, Lixian; Feng, Xiaohui; Zhang, Lihua; Zhu, Ruiliang; Luo, Xin

2012-06-01

The aim of this work was to study the epidemiology of Listeria spp., particularly Listeria monocytogenes, and to identify the serotypes present in contaminated samples from beef processing plants in China. A total of 439 samples were obtained from bovine feces, hides, and carcasses at three commercial processing plants. A standard protocol (ISO 11290-1) was followed to detect Listeria spp. and L. monocytogenes, and multiplex polymerase chain reaction was used to identify the various L. monocytogenes serotypes. The overall prevalences of Listeria spp. and L. monocytogenes were 65.6% and 26.4%, respectively, and the contamination was highest in the hide samples. The identified L. monocytogenes serotypes were 1/2c and 1/2a. The results of the current study indicate that Listeria spp. contamination is common in Chinese beef processing plants; specific measures should be taken to prevent and/or treat L. monocytogenes contamination of feces and hides in beef slaughter plants. Furthermore, because Listeria spp. contamination was found to be prevalent, it should, therefore, be studied further. The prevention of cases of sporadic listeriosis in China should also be addressed.

Laser effects on the growth and photosynthesis process in mustard plants (Sinapis Alba)

Science.gov (United States)

Anghel, Sorin; Stanescu, Constantin S.; Giosanu, Dana; Flenacu, Monica; Iorga-Siman, Ion

2001-06-01

In this paper we present the results of our experiments concerning the influence of the low energy laser (LEL) radiation on the germination, growth and photosyntheses processes in mustard plants (sinapis alba). We used a He-Ne laser ((lambda) equals 632.8 nm, P equals 6 mW) to irradiate the mustard seeds with different exposure times. The seeds were sowed and some determinations (the germination and growth intensity, chlorophyll quantity, and respiration intensity) were made on the plant culture. We ascertained that the germination and growth of the plants are influenced by the irradiation. Also, the chlorophyll quantity is the same for both plants from irradiated and non-irradiated seeds but the respiration and photosynthesis processes are influenced by the irradiation.

Sustained qualification process for full scope nuclear power plant simulators

International Nuclear Information System (INIS)

Pirson, J.; Stubbe, E.; Vanhoenacker, L.

1994-01-01

In the past decade, simulator training for all nuclear power plant operators has evolved into a vital requirement. To assure a correct training, the simulator qualification process is an important issue not only for the initial validation but also following major simulator updates, which are necessary during the lifetime of the simulator. In order to avoid degradation of the simulator validated software, the modifications have to be introduced according to a rigorous methodology and a practical requalification process has to be applied. Such methodology has to be enforced at every phase of the simulator construction or updating process from plant data package constitution, over simulator software development to simulator response qualification. The initial qualification and requalification process is based on the 3 levels identified by the ANSI/ANS 3-5 standard for steady-state, operational transients and accident conditions. For the initial certification of the full scope simulators in Belgium, a practical qualification methodology has been applied, which has been adapted into a set of non regression tests for the requalification after major simulator updates. (orig.) (4 refs., 3 figs.)

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

Study on designing a complete pilot plant for processing sandstone ores in Palua-Parong area

International Nuclear Information System (INIS)

Le Quang Thai; Tran Van Son; Tran The Dinh; Trinh Nguyen Quynh; Vu Khac Tuan

2015-01-01

Design work is the first step of the construction and operation of pilot plant. Thus, the project Study on designing a complete pilot plant for processing sandstone ores in Palua - Parong area was conducted to design a pilot plant for testing entire technological process to obtain yellowcake. Based on a literature review of uranium ore processing technology in the world, information of ore and previous research results of uranium ore in PaLua - PaRong area at the Institute for Technology of Radioactive and Rare Elements, a suitable technological flowsheet for processing this ore has been selected. The size, location of the pilot plant and planed experiments has been selected during the implementation of this project, in which basic parameters, designed system of equipment, buildings, ect. were also calculated. (author)

Chemical mode control in nuclear power plant decommissioning during operation of technologies in individual radioactive waste processing plants

International Nuclear Information System (INIS)

Horvath, J.; Dugovic, L.

1999-01-01

Sewage treatment of nuclear power plant decommissioning is performed by system of sewage concentration in evaporator with formation of condensed rest, it means radioactive waste concentrate and breeding steam. During sewage treatment plant operation department of chemical mode performs chemical and radiochemical analysis of sewage set for treatment, chemical and radiochemical analysis of breeding steam condensate which is after final cleaning on ionization filter and fulfilling the limiting conditions released to environment; chemical and radiochemical analysis of heating steam condensate which is also after fulfilling the limiting conditions released to environment. Condensed radioactive concentrate is stored in stainless tanks and later converted into easy transportable and chemically stable matrix from the long term storage point of view in republic storage Mochovce. The article also refer to bituminous plant, vitrification plant, swimming pool decontamination plant of long term storage and operation of waste processing plant Bohunice

The use of mass and energy balances for observation in process plant diagnosis

International Nuclear Information System (INIS)

Lind, M.; Talmon, H.

1981-12-01

A method is described that uses the invariant mass and energy conservation laws in order to extract a detailed pattern of mass and energy flows from the instrumentation of a process plant. The basic feature of the method is that it is applicable to a large range of plant operational situations, such as those initiated by unforeseen failures during sequential operations. The authors' intensions with this interim progress report are to describe the basic ideas behind the method, as well as to discuss some of its implications for man-computer cooperation in process plant diagnosis. (author)

Thermodynamic analysis of CO2 capture processes for power plants

OpenAIRE

Biyouki, Zeinab Amrollahi

2014-01-01

This thesis work presents an evaluation of various processes for reducing CO2 emissions from natural-gas-fired combined cycle (NGCC) power plants. The scope of the thesis is to focus mainly on post-combustion chemical absorption for NGCC. For the post-combustion capture plant, an important interface is the steam extraction from the steam turbine in order to supply the heat for solvent regeneration. The steam extraction imposes a power production penalty. The thesis includes analysis and compa...

Prototype plant for nuclear process heat (PNP), reference phase

International Nuclear Information System (INIS)

Fladerer, R.; Schrader, L.

1982-07-01

The coal gasification processes using nuclear process heat being developed within the framwork of the PNP project, have the advantages of saving feed coal, improving efficiency, reducing emissions, and stabilizing energy costs. One major gasification process is the hydrogasification of coal for producing SNG or gas mixture of carbon monoxide and hydrogen; this process can also be applied in a conventional route. The first steps to develop this process were planning, construction and operation of a semi-technical pilot plant for hydrogasification of coal in a fluidized bed having an input of 100 kg C/h. Before the completion of the development phase (reference phase) describing here, several components were tested on part of which no operational experience had so far been gained; these were the newly developed devices, e.g. the inclined tube for feeding coal into the fluidized bed, and the raw gas/hydrogenation gas heat exchanger for utilizing the waste heat of the raw gas leaving the gasifier. Concept optimizing of the thoroughly tested equipment parts led to an improved operational behaviour. Between 1976 and 1980, the semi-technical pilot plant was operated for about 19,400 hours under test conditions, more than 7,400 hours of which it has worked under gasification conditions. During this time approx. 1,100 metric tons of dry brown coal and more than 13 metric tons of hard coal were gasified. The longest coherent operational phase under gasification conditions was 748 hours in which 85.4 metric tons of dry brown coal were gasified. Carbon gasification rates up to 82% and methane contents in the dry raw gas (free of N 2 ) up to 48 vol.% were obtained. A detailed evaluation of the test results provided information of the results obtained previously. For the completion of the test - primarily of long-term tests - the operation of the semi-technical pilot plant for hydrogasification of coal is to be continued up to September 1982. (orig.) [de

Tetrafluoride uranium pilot plant in operation at IEA, using the moving bed process

International Nuclear Information System (INIS)

Franca Junior, J.M.

1975-01-01

A UF 4 pilot plant, in operation at IEA, using the moving bed process is reported. UO 3 obtained from the thermal decomposition of ADU is used as a starting material in this pilot plant. The type of equipment and the process are both described. Ammonia gas (NH 3 ) was used in the reduction operation and anhydrous hydrofluoric acid (HF) in the hydrofluorination step

Exergetic analysis of cogeneration plants through integration of internal combustion engine and process simulators

Energy Technology Data Exchange (ETDEWEB)

Carvalho, Leonardo de Oliveira [Petroleo Brasileiro S.A. (PETROBRAS), Rio de Janeiro, RJ (Brazil)], E-mail: leonardo.carvalho@petrobras.com.br; Leiroz, Albino Kalab; Cruz, Manuel Ernani [Coordenacao dos Programas de Pos-Graduacao de Engenharia (COPPE/UFRJ), RJ (Brazil). Programa de Engenharia Mecanica], Emails: leiroz@mecanica.ufrj.br, manuel@mecanica.ufrj.br

2010-07-01

Internal combustion engines (ICEs) have been used in industry and power generation much before they were massively employed for transportation. Their high reliability, excellent power-to-weight ratio, and thermal efficiency have made them a competitive choice as main energy converters in small to medium sized power plants. Process simulators can model ICE powered energy plants with limited depth, due to the highly simplified ICE models used. Usually a better understanding of the global effects of different engine parameters is desirable, since the combustion process within the ICE is typically the main cause of exergy destruction in systems which utilize them. Dedicated commercial ICE simulators have reached such a degree of maturity, that they can adequately model a wide spectrum of phenomena that occur in ICEs. However, ICE simulators are unable to incorporate the remaining of power plant equipment and processes in their models. This paper presents and exploits the integration of an internal combustion engine simulator with a process simulator, so as to evaluate the construction of a fully coupled simulation platform to analyze the performance of ICE-based power plants. A simulation model of an actual cogeneration plant is used as a vehicle for application of the proposed computational methodology. The results show that by manipulating the engine mapping parameters, the overall efficiency of the plant can be improved. (author)

Identification and Control of Nutrient Removing Processes in Wastewater Treatment Plants

DEFF Research Database (Denmark)

Nielsen, Marinus K.; Madsen, Henrik; Carstensen, Niels Jacob

1994-01-01

the possibility of using statistical methods for identifying dynamical models for the biological processes. These models can then be used for simulating various control strategies and the parameters of the controllers can be found by off-line optimization. Simulation studies have shown that considerable savings......Today the use of on-line control for wastewater treatment plants is very low. A main reason is the lack of quality of the data, and the fact that more sophisticated control strategies must be based on a model of the dynamics of the biological processes. This paper discusses the historical reasons...... for the limited use of modern control strategies for wastewater treatment plants. Today, however, on-line nutrient sensors are more reliable. In the present context the use of on-line monitored values of ammonia, nitrate and phosphate from a full scale plant are used as the background for discussing...

Research on plant of metal fuel fabrication using casting process

International Nuclear Information System (INIS)

Senda, Yasuhide; Mori, Yukihide

2003-12-01

This document presents the plant concept of metal fuel fabrication system (38tHM/y) using casting process in electrolytic recycle, which based on recent studies of its equipment design and quality control system. And we estimate the cost of its construction and operation, including costs of maintenance, consumed hardware and management of waste. The content of this work is as follows. (1) Designing of fuel fabrication equipment: We make material flow diagrams of the fuel fabrication plant and rough designs of the injection casting furnace, demolder and inspection equipment. (2) Designing of resolution system of liquid waste, which comes from analytical process facility. Increased analytical items, we rearrange analytical process facility, estimate its chemicals and amount of waste. (3) Arrangement of equipments: We made a arrangement diagram of the metal fuel fabrication equipments in cells. (4) Estimation of cost data: We estimated cost to construct the facility and to operate it. (author)

Actin based processes that could determine the cytoplasmic architecture of plant cells

NARCIS (Netherlands)

Honing, van der H.S.; Emons, A.M.C.; Ketelaar, M.J.

2007-01-01

Actin polymerisation can generate forces that are necessary for cell movement, such as the propulsion of a class of bacteria, including Listeria, and the protrusion of migrating animal cells. Force generation by the actin cytoskeleton in plant cells has not been studied. One process in plant cells

Coal Preparation and Processing Plants New Source Performance Standards (NSPS)

Science.gov (United States)

Learn about the NSPS regulation for coal preparation and processing plants by reading the rule summary, the rule history, the code of federal regulation text, the federal register, and additional docket documents

A proposed strategy for upgrade of the ORNL Process Wastewater Treatment Plant

International Nuclear Information System (INIS)

Kent, T.E.; Robinson, S.M.; Scott, C.B.

1990-01-01

An approach to the upgrade of the radiological Process Wastewater Treatment Plant (PWTP) at Oak Ridge National Laboratory (ORNL) has been developed that, if adopted, will result in significant cost reductions and improved water quality. The strategy described in this report satisfies the short-term upgrade needs of the PWTP and ultimately results in replacement of existing PWTP softening/ion- exchange technology with a zeolite molecular sieve treatment system for removal of radioactive contaminants from process wastewater. Use of zeolites will improve wastewater quality while reducing operating and disposal costs. The zeolite system would be constructed adjacent to the site now occupied by the Non-Radiological Process Wastewater Treatment Plant (NRWTP), thereby consolidating all process wastewater treatment systems at one location. 4 refs., 4 figs

A proposed strategy for upgrade of the ORNL process wastewater treatment plant

International Nuclear Information System (INIS)

Kent, T.E.; Robinson, S.M.; Scott, C.B.

1990-01-01

This paper reports on an approach to the upgrade of the radiological Process Wastewater Treatment Plant (PWTP) at Oak Ridge National Laboratory (ORNL), which has been developed and that, if adopted, will result in significant cost reductions and improved water quality. The strategy described in this report satisfies the short-term upgrade needs of the PWTP and ultimately results in replacement of existing PWTP softening/ion-exchange technology with a zeolite molecular sieve treatment system for removal of radioactive contaminants from process wastewater. Use of zeolites will improve wastewater quality while reducing operating and disposal costs. The zeolite system would be constructed adjacent to the site now occupied by the Non-Radiological Process Wastewater Treatment Plant (NRWTP), thereby consolidating all process wastewater treatment systems at one location

Habitat Fragmentation Drives Plant Community Assembly Processes across Life Stages

Science.gov (United States)

Hu, Guang; Feeley, Kenneth J.; Yu, Mingjian

2016-01-01

Habitat fragmentation is one of the principal causes of biodiversity loss and hence understanding its impacts on community assembly and disassembly is an important topic in ecology. We studied the relationships between fragmentation and community assembly processes in the land-bridge island system of Thousand Island Lake in East China. We focused on the changes in species diversity and phylogenetic diversity that occurred between life stages of woody plants growing on these islands. The observed diversities were compared with the expected diversities from random null models to characterize assembly processes. Regression tree analysis was used to illustrate the relationships between island attributes and community assembly processes. We found that different assembly processes predominate in the seedlings-to-saplings life-stage transition (SS) vs. the saplings-to-trees transition (ST). Island area was the main attribute driving the assembly process in SS. In ST, island isolation was more important. Within a fragmented landscape, the factors driving community assembly processes were found to differ between life stage transitions. Environmental filtering had a strong effect on the seedlings-to-saplings life-stage transition. Habitat isolation and dispersal limitation influenced all plant life stages, but had a weaker effect on communities than area. These findings add to our understanding of the processes driving community assembly and species coexistence in the context of pervasive and widespread habitat loss and fragmentation. PMID:27427960

Application of process simulation for evaluation of ecologically benefical developments in thermal power plant technology

International Nuclear Information System (INIS)

Schuster, G.

2000-04-01

Responsibility for the environment and a sustainable utilization of resources gain also in the production of electric power more and more importance. For this reason existing power generation processes have to be improved and alternatives to existing processes have to be developed. As a first step in this procedure process simulation is a powerful tool to evaluate the potentials of new developments. In this work it is shown, how new thermal power processes are modeled and simulated based on well-known thermodynamic and chemical correlations. Processes for thermal power plants using lignite with high water content and biomass as fuel are studied. In each case simulations are carried out for complete plants including all important unit operations. Based on a conventional thermal power plant for lignite different variants for efficiency improvement by fuel drying are examined. Additionally the potential of a process with gasification and gas turbine is discussed. Compared to a lignite power plant the preconditions for a biomass power plant are different. A promising option for the future seems to be small, decentralized combined heat and power plants. Therefore a process with simple and compact design including gasifier and gas turbine is regarded and sensitivity analyses are carried out. As well as for the lignite processes possible improvements by fuel drying are studied. The basis lignite power plant (drying in an impact rotor mill with hot flue gas) has an overall electric efficiency of 36 %. Alternative fuel drying processes (reducing water content from 54 w % to 10 w %) can increase efficiency to nearly 43 %. Using integrated air-blown gasification combined with gas turbine and steam turbine and additional fuel drying raises the efficiency up to 49 % in the case of cold gas cleanup and up to 50 percent in the case of hot gas cleanup. Efficiencies of the regarded biomass power plants are in the range of about 20 % (with a biomass water content of 25 w %). By

Image Harvest: an open-source platform for high-throughput plant image processing and analysis

Science.gov (United States)

Knecht, Avi C.; Campbell, Malachy T.; Caprez, Adam; Swanson, David R.; Walia, Harkamal

2016-01-01

High-throughput plant phenotyping is an effective approach to bridge the genotype-to-phenotype gap in crops. Phenomics experiments typically result in large-scale image datasets, which are not amenable for processing on desktop computers, thus creating a bottleneck in the image-analysis pipeline. Here, we present an open-source, flexible image-analysis framework, called Image Harvest (IH), for processing images originating from high-throughput plant phenotyping platforms. Image Harvest is developed to perform parallel processing on computing grids and provides an integrated feature for metadata extraction from large-scale file organization. Moreover, the integration of IH with the Open Science Grid provides academic researchers with the computational resources required for processing large image datasets at no cost. Image Harvest also offers functionalities to extract digital traits from images to interpret plant architecture-related characteristics. To demonstrate the applications of these digital traits, a rice (Oryza sativa) diversity panel was phenotyped and genome-wide association mapping was performed using digital traits that are used to describe different plant ideotypes. Three major quantitative trait loci were identified on rice chromosomes 4 and 6, which co-localize with quantitative trait loci known to regulate agronomically important traits in rice. Image Harvest is an open-source software for high-throughput image processing that requires a minimal learning curve for plant biologists to analyzephenomics datasets. PMID:27141917

Plant senescence and proteolysis: two processes with one destiny.

Science.gov (United States)

Diaz-Mendoza, Mercedes; Velasco-Arroyo, Blanca; Santamaria, M Estrella; González-Melendi, Pablo; Martinez, Manuel; Diaz, Isabel

2016-01-01

Senescence-associated proteolysis in plants is a complex and controlled process, essential for mobilization of nutrients from old or stressed tissues, mainly leaves, to growing or sink organs. Protein breakdown in senescing leaves involves many plastidial and nuclear proteases, regulators, different subcellular locations and dynamic protein traffic to ensure the complete transformation of proteins of high molecular weight into transportable and useful hydrolysed products. Protease activities are strictly regulated by specific inhibitors and through the activation of zymogens to develop their proteolytic activity at the right place and at the proper time. All these events associated with senescence have deep effects on the relocation of nutrients and as a consequence, on grain quality and crop yield. Thus, it can be considered that nutrient recycling is the common destiny of two processes, plant senescence and, proteolysis. This review article covers the most recent findings about leaf senescence features mediated by abiotic and biotic stresses as well as the participants and steps required in this physiological process, paying special attention to C1A cysteine proteases, their specific inhibitors, known as cystatins, and their potential targets, particularly the chloroplastic proteins as source for nitrogen recycling.

Intensifying drying process with creation of functional plant compositions

Directory of Open Access Journals (Sweden)

Zh. Petrova

2015-05-01

Full Text Available Introduction. The process of drying agricultural raw products is associated with loss of bioactive substances by the products exposed to heat, light, oxygen, or рН medium. It is reasonable to enhance the table beet processing technology in order to achieve maximum betanin conservation at lower energy consumption. Materials and methods. Table beets, rhubarbs, lemons, and tomatoes were dried at temperature of 50 to 100 ºС, air speed of 1.5 to 3.5 m/s, heat carrier water content of 7 to 15 g/kg, and layer thickness of 2 to 20 mm. The betanіn content was determined via absorption spectra, using the optical density value at 540 nm wavelength. A differential microcalorimeter was used for measuring evaporation heat consumption. Results and discussion.The effect of raw product pre-drying preparation was studied. With no preliminary preparation, the loss of betanin after drying reaches 66 %. The preliminary preparation technology we have developed includes boiling whole root crops with optimal selection of acid medium and allows us to reduce the betanin loss down to 6 %. Regretfully, the process requires large energy consumption. Low energy consumption pre-drying preparation method was developed for antioxidant raw products with thermal processing replaced by blending. The betanin loss, in this case, does not exceed 5 %. Optimal drying temperature of betanin-containing raw stock, after its preliminary processing, is 60 °С. It allows to keep up to 95 % of betanіn. Specific heat consumption for water evaporation out of the developed table beet based antioxidant plant compositions, with addition of rhubarb and lemon, is less by 4 to 5 % as compared to the initial components. Conclusions. Dependence of betanin loss in plant raw stock on the material temperature and composition components, in the course of their pre-drying preparation, was found. It was also found that water evaporation heat, for some antioxidant plant compositions developed, is less

Safety Philosophy in Process Heat Plants Coupled to High Temperature Reactors

International Nuclear Information System (INIS)

Brown, Nicholas R.; Revankar, Shripad T.

2011-01-01

With the future availability of fossil fuel resources in doubt, high temperature nuclear reactors have the potential to be an important technology in the near term. Due to a high coolant outlet temperature, high temperature reactors (HTR) can be used to drive chemical plants that directly utilize process heat. Additionally, the high temperature improves the thermodynamic efficiency of the energy utilization. Many applications of high temperature reactors exist as a thermal driving vector for endothermic chemical process plants. Hydrogen generation using the General Atomics (GA) sulfur iodine (SI) cycle is one promising application of high temperature nuclear heat. The main chemical reactions in the SI cycle are: 1. I 2 +SO 2 + 2H 2 O → 2HI + H 2 SO 4 (Bunsen reaction) 2. H 2 SO 4 → H 2 O + SO 2 + 1/2O 2 (Sulfuric acid decomposition) 3. 2HI → H 2 + I 2 (Hydrogen Iodide decomposition). With the exception of hydrogen and oxygen, all relevant reactants are recycled within the process. However, there are many unresolved safety and operational issues related to implementation of such a coupled plant

Heat Integration and Renewable Energy in Meat Processing Plants

OpenAIRE

Colley, Tracey Anne

2016-01-01

This thesis aims to optimise energy efficiency at meat processing plants and minimise their carbon footprint, as a way of reducing operating costs and minimising the potential negative impacts of a carbon price on the red meat industry. In the context of the export meat industry, there is continual competition with the live export trade. Therefore, there is a risk that a carbon price could increase the live export trade over domestic processing of meat, thereby exporti...

Performance and Model Calibration of R-D-N Processes in Pilot Plant

DEFF Research Database (Denmark)

de la Sota, A.; Larrea, L.; Novak, L.

1994-01-01

This paper deals with the first part of an experimental programme in a pilot plant configured for advanced biological nutrient removal processes treating domestic wastewater of Bilbao. The IAWPRC Model No.1 was calibrated in order to optimize the design of the full-scale plant. In this first phas...

Study of transport processes in soils and plants by microautoradiographic and radioabsorption methods

International Nuclear Information System (INIS)

Varro, T.; Gelencser, Judit; Somogyi, G.

1987-01-01

The concentration profiles of lead and boron in carrot root and potato tuber were determined at various diffusion times by microradiographic method. The transport process of nutrients, leaf-manures and plant-protecting agents in plants was investigated by radioabsorption method. The influence of the pH of soils and complex-forming agents on the effective diffusion coefficients of nutritives was studied by radioabsorption technique. In soils, the effective diffusion coefficient of the nutrients was found to change in the region of 10 -16 -10 -10 m 2 s -1 . The data of the measurements give valuable information about the transport processes in plants and soils. (author) 9 refs., 4 figs

Materials control and accountability at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Denning, G.E.; Britschgi, J.J.; Spraktes, F.W.

1985-01-01

The ICPP high enriched uranium recovery process has historically been operated as a single Material Balance Area (MBA), with input and output measurement capabilities. Safeguards initiated changes in the last five years have resulted in significant materials control and accountability improvements. Those changes include semi-automation of process accountability measurement, data collection and recording; definition of Sub-MBAs; standard plant cleanouts; and, bimonthly inventory estimates. Process monitoring capabilities are also being installed to provide independent operational procedural compliance verification, process anomaly detection, and enhanced materials traceability. Development of a sensitivity analysis approach to defining process measurement requirements is in progress

Coal conversion process by the United Power Plants of Westphalia

Energy Technology Data Exchange (ETDEWEB)

1974-08-01

The coal conversion process used by the United Power Plants of Westphalia and its possible applications are described. In this process, the crushed and predried coal is degassed and partly gasified in a gas generator, during which time the sulfur present in the coal is converted into hydrogen sulfide, which together with the carbon dioxide is subsequently washed out and possibly utilized or marketed. The residual coke together with the ashes and tar is then sent to the melting chamber of the steam generator where the ashes are removed. After desulfurization, the purified gas is fed into an external circuit and/or to a gas turbine for electricity generation. The raw gas from the gas generator can be directly used as fuel in a conventional power plant. The calorific value of the purified gas varies from 3200 to 3500 kcal/cu m. The purified gas can be used as reducing agent, heating gas, as raw material for various chemical processes, or be conveyed via pipelines to remote areas for electricity generation. The conversion process has the advantages of increased economy of electricity generation with desulfurization, of additional gas generation, and, in long-term prospects, of the use of the waste heat from high-temperature nuclear reactors for this process.

On-line calibration of process instrumentation channels in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hashemian, H.M.; Farmer, J.P. [Analysis and Measurement Services Corp., Knoxville, TN (United States)

1995-04-01

An on-line instrumentation monitoring system was developed and validated for use in nuclear power plants. This system continuously monitors the calibration status of instrument channels and determines whether or not they require manual calibrations. This is accomplished by comparing the output of each instrument channel to an estimate of the process it is monitoring. If the deviation of the instrument channel from the process estimate is greater than an allowable limit, then the instrument is said to be {open_quotes}out of calibration{close_quotes} and manual adjustments are made to correct the calibration. The success of the on-line monitoring system depends on the accuracy of the process estimation. The system described in this paper incorporates both simple intercomparison techniques as well as analytical approaches in the form of data-driven empirical modeling to estimate the process. On-line testing of the calibration of process instrumentation channels will reduce the number of manual calibrations currently performed, thereby reducing both costs to utilities and radiation exposure to plant personnel.

Radioactive waste processing method for a nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Sugimoto, Y; Kuriyama, O

1976-06-04

Object is to subject radioactive liquid waste in a nuclear power plant to reverse permeation process after which it is vaporized and concentrated thereby decreasing the quantity of foam to be used to achieve effective concentration of the liquid waste. Liquid waste containing a radioactive material produced from a nuclear power plant is first applied with pressure in excess of osmotic pressure by a reverse permeation device and is separated into clean water and concentrated liquid by semi-permeable membrane. Next, the thus reverse-permeated and concentrated waste is fed to an evaporator which control foaming by the foam and then further reconcentrated for purification of the liquid waste.

Recent developments in the extraction separation method for treatment of high-level liquid waste

International Nuclear Information System (INIS)

Jiao Rongzhou; Song Chongli; Zhu Yongjun

2000-01-01

A description and review of the recent developments in the extraction separation method for partitioning transuranium elements from high-level liquid waste (HLLW) is presented. The extraction separation processes such as TRUEX process, DIAMEX process, DIDPA process, CTH process, TRPO process are briefly discussed

Design consideration on hydrogen production demonstration plant of thermochemical IS process

International Nuclear Information System (INIS)

Iwatsuki, Jin; Noguchi, Hiroki; Terada, Atsuhiko; Kubo, Shinji; Sakaba, Nariaki; Onuki, Kaoru; Hino, Ryutaro

2009-03-01

Preliminary design study was carried out on the hydrogen production demonstration plant of thermochemical IS process. In the pilot test, hydrogen production will be examined under prototypical condition using an apparatus made of industrial materials, which is driven by the sensible heat of helium gas heated by an electric heater that simulates the High Temperature Engineering Test Reactor (HTTR). Tentative system condition was defined considering the HTTR specification and the experience on the construction and the operation of the mock-up test facility using methane reforming for hydrogen production. The process condition and the system flow diagram were discussed to meet the system condition. Based on the defined process condition, types of the main components were discussed taking the corrosion resistance of the structural materials into consideration. Applicable rules and regulations were also surveyed regarding the plant construction and operation. (author)

Image Harvest: an open-source platform for high-throughput plant image processing and analysis.

Science.gov (United States)

Knecht, Avi C; Campbell, Malachy T; Caprez, Adam; Swanson, David R; Walia, Harkamal

2016-05-01

High-throughput plant phenotyping is an effective approach to bridge the genotype-to-phenotype gap in crops. Phenomics experiments typically result in large-scale image datasets, which are not amenable for processing on desktop computers, thus creating a bottleneck in the image-analysis pipeline. Here, we present an open-source, flexible image-analysis framework, called Image Harvest (IH), for processing images originating from high-throughput plant phenotyping platforms. Image Harvest is developed to perform parallel processing on computing grids and provides an integrated feature for metadata extraction from large-scale file organization. Moreover, the integration of IH with the Open Science Grid provides academic researchers with the computational resources required for processing large image datasets at no cost. Image Harvest also offers functionalities to extract digital traits from images to interpret plant architecture-related characteristics. To demonstrate the applications of these digital traits, a rice (Oryza sativa) diversity panel was phenotyped and genome-wide association mapping was performed using digital traits that are used to describe different plant ideotypes. Three major quantitative trait loci were identified on rice chromosomes 4 and 6, which co-localize with quantitative trait loci known to regulate agronomically important traits in rice. Image Harvest is an open-source software for high-throughput image processing that requires a minimal learning curve for plant biologists to analyzephenomics datasets. © The Author 2016. Published by Oxford University Press on behalf of the Society for Experimental Biology.

Calibration of whole-body counters for transuranic radionuclides by using total-body donations to the United States Transuranium Registry

International Nuclear Information System (INIS)

Palmer, H.E.; Heid, K.R.; Breitenstein, B.D.; Durbin, P.W.; McInroy, J.F.

1985-01-01

One of the many benefits of the whole-body donation programme of the United States Transuranium Registry is the calibration of whole-body counters by measuring a donated body containing radioactivity before radiochemical analysis of the body occurs. These measurements have provided the best existing calibration factors for measuring 241 Am and 239 Pu in the skeleton of living people. In one case where the body contained an easily measurable quantity of 241 Am, the 241 Am content was found to be the same for identical bones on the right and left sides of the body. The bones from the right side of the body and every other vertebrae were radiochemically analysed and the bones from the left side were reserved. These latter have a known quantity of naturally distributed 241 Am based on the analysis of bones from the right side. These reserved bones are being incorporated into tissue equivalent body parts for future calibrations and interlaboratory comparisons. The measurements on the total body and the reserved bones have already been very useful in determining the contribution of skeletal activity to that of lung measurements and determining a calibration factor for measuring 239 Pu deposited in the skeleton. In the future it is planned to periodically make in vivo measurements on those people participating in the total-body donation programme so that calibration factors can be obtained for lung and liver content after subsequent analysis of these tissues. (author)

'Virtual' monitoring in LabVIEW 8 and process simulation of the cryogenic pilot plant

International Nuclear Information System (INIS)

Moraru, Carmen Maria; Stefan, Iuliana; Balteanu, Ovidiu; Bucur, Ciprian; Stefan, Liviu; Bornea, Anisia; Stefanescu, Ioan

2007-01-01

Full text: The implementation of the new software and hardware's technologies for tritium processing nuclear plants, and especially those with an experimental character or of new technology developments shows a coefficient of complexity due to issues raised by the use of the performing instrumentation and equipment into a unitary monitoring system of the nuclear technological process of tritium removal. Keeping the system's flexibility is a demand of the nuclear experimental plants for which the change of configuration, process and parameters is something usual. The big amount of data that needs to be processed, stored and accessed for real time simulation and optimization demands the achievement of the virtual technologic platform where the data acquiring, control and analysis systems of the technological process can be integrated with a developed technological monitoring system. Thus, integrated computing and monitoring systems needed for the supervising of the technological process will be carried out, and continued with the optimization of the system, by choosing new and performing methods corresponding to the technological processes within the tritium removal processing nuclear plants. The developing software applications is carried out by means of the program packages dedicated to industrial processes and they will include acquisition and monitoring sub-modules, named 'virtual' as well as the storage sub-module of the process data later required for the software of optimization and simulation of the technological process for tritium removal. The system plays an important role in the environment protection and sustainable development through new technologies, that is - the reduction of and fight against industrial accidents in the case of tritium processing nuclear plants. Research for monitoring optimization of nuclear processes is also a major driving force for economic and social development. (authors)

Self-assessment on nuclear power plants operational experience feedback process

International Nuclear Information System (INIS)

Li Hongtao; Ding Ying

2005-01-01

This paper introduces the purpose and function of self-assessment conducted by the responsible organizations of nuclear power plants, and describes the methods and requirements of self-assessment on operational experience feedback process to give a example. (authors)

Codigestion of manure and industrial organic waste at centralized biogas plants: process imbalances and limitations

DEFF Research Database (Denmark)

Bangsø Nielsen, Henrik; Angelidaki, Irini

2008-01-01

The present study focuses on process imbalances in Danish centralized biogas plants treating manure in combination with industrial waste. Collection of process data from various full-scale plants along with a number of interviews showed that imbalances occur frequently. High concentrations...... of ammonia or long chain fatty acids is in most cases expected to be the cause of microbial inhibitions/imbalances while foaming in the prestorage tanks and digesters is the most important practical process problem at the plants. A correlation between increased residual biogas production (suboptimal process...... conditions) and high fractions of industrial waste in the feedstock was also observed. The process imbalances and suboptimal conditions are mainly allowed to occur due to 1) inadequate knowledge about the waste composition, 2) inadequate knowledge about the waste degradation characteristics, 3) inadequate...

Energy efficiency improvements in sewage sludge processing plants; Energetische Optimierung der Klaerschlammaufbereitung

Energy Technology Data Exchange (ETDEWEB)

Vetter, H.; Burger, S.

2006-07-01

From October 1st, 2006, sewage sludge may no longer be used as a fertilizer by farmers in Switzerland. Mechanical dewatering and drying of the sludge are the pre-stages of incineration. Based on a monitoring campaign and the results thereof, recommendations aiming at improving the energy efficiency have been worked out for use by waste water treatment plant operators and engineers for the design of drying plants. From the energetic point of view, solar drying of sludge is the best process. However, due to the large area required and the limited drying capacity, solar drying cannot be implemented everywhere. Therefore, three further drying processes have been monitored for eleven months: the fluidized bed drying process at the waste water treatment plant (WWTP) of the Region Berne, the low temperature/air recirculation dryer at WWTP Schwyz and the middle-temperature belt dryer at WWTP Wohlen. The electric energy consumption of the three investigated sludge drying processes was between 22 and 94 kWh per ton of evaporated water. The low temperature dryer showed the lowest energy consumption. The thermal energy consumption (expressed in useful energy) was between 648 and 1'033 kWh per ton of evaporated water, with the middle temperature dryer having the lowest consumption. On the other hand, the most advantageous process is the low temperature dryer if the comparison is based on the final energy consumption. This process has the advantage of making possible the integration of low-temperature waste heat. For whole Switzerland, the energy savings potential is estimated to be 133 GWh/year for fuel and 32 GWh/year for electricity, provided the drying process with the lowest energy consumption is implemented. It is recommended to conduct another measuring campaign at the first just commissioned sludge drying plant comprising a heat pump using waste water as a heat source, to check the effective energy savings. (author)

Effect of post-Chernobyl chronic irradiation on some important plant processes

International Nuclear Information System (INIS)

Goncharova, N.

1994-01-01

The efficiency of photosynthetic plant apparatus characterized by photochemical activity of chloroplasts (the Hill reaction), cyclic photophosphorylation and activity of ribulosebiphosphate carboxylase (RuBC) is investigated. These characteristics are used to show the state of plant growing under increased background radiation. There is a trend towards increase of chlorophyll content per unit wet weight of a leaf and reduction in the concentration of soluble protein in irradiated plants. However, the photochemical reactions, as indicated by RuBC activity, are similar. The low hydrolytic activity of chlorophyllase, an enzyme of chlorophyll degradation, indicates a high activity of the photosynthetic apparatus of plants growing under increased background radiation conditions. Thus, the observed resistance of photosynthetic apparatus to ionizing radiation and stimulation of pigment metabolism and activity of photochemical and enzyme reactions reveals a high adaptive ability of plants. Under conditions of elevated radiation background, the processes of photosynthesis in plants may become more active. This in turn may favour the accumulation of green mass and the crop raising. The prolonged chronic action of radionuclides on plants in contaminated zones will be determined by their specific accumulation in individual plant species, their radiosensitivity and factors connected with their growth - type of soil, kind of radionuclide fallout, chemical and physical effects. (author)

Concept of a cognitive-numeric plant and process modelizer

International Nuclear Information System (INIS)

Vetterkind, D.

1990-01-01

To achieve automatic modeling of plant distrubances and failure limitation procedures, first the system's hardware and the present media (water, steam, coolant fluid) are formalized into fully computable matrices, called topographies. Secondly a microscopic cellular automation model, using lattice gases and state transition rules, is combined with a semi - microscopic cellular process model and with a macroscopic model, too. In doing this, at semi-microscopic level there are acting a cellular data compressor, a feature detection device and the Intelligent Physical Element's process dynamics. At macroscopic level the Walking Process Elements, a process evolving module, a test-and-manage device and abstracting process net are involved. Additionally, a diagnosis-coordinating and a counter measurements coordinating device are used. In order to automatically get process insights, object transformations, elementary process functions and associative methods are used. Developments of optoelectronic hardware language components are under consideration

Tube failures due to cooling process problem and foreign materials in power plants

Energy Technology Data Exchange (ETDEWEB)

Ahmad, J. [Kapar Energy Ventures Sdn Bhd, Jalan Tok Muda, Kapar 42200 (Malaysia); Purbolaksono, J., E-mail: judha@uniten.edu.m [Department of Mechanical Engineering, Universiti Tenaga Nasional, Km 7 Jalan Kajang-Puchong, Kajang 43009, Selangor (Malaysia); Beng, L.C. [Kapar Energy Ventures Sdn Bhd, Jalan Tok Muda, Kapar 42200 (Malaysia)

2010-07-15

Cooling process which uses water for heat transfer is an essential factor in coal-fired and nuclear plants. Loss of cooling upset can force the plants to shut down. In particular, this paper reports visual inspections and metallurgical examinations on the failed SA210-A1 right-hand side (RHS) water wall tube of a coal-fired plant. The water wall tube showed the abnormal outer surface colour and has failed with wide-open ductile rupture and thin edges indicating typical signs of short-term overheating. Metallurgical examinations confirmed the failed tube experiencing higher temperature operation. Water flow starvation due to restriction inside the upstream tube is identified as the main root cause of failure. The findings are important to take failure mitigation actions in the future operation. Discussion on the typical problems related to the cooling process in nuclear power plants is also presented.

Tube failures due to cooling process problem and foreign materials in power plants

International Nuclear Information System (INIS)

Ahmad, J.; Purbolaksono, J.; Beng, L.C.

2010-01-01

Cooling process which uses water for heat transfer is an essential factor in coal-fired and nuclear plants. Loss of cooling upset can force the plants to shut down. In particular, this paper reports visual inspections and metallurgical examinations on the failed SA210-A1 right-hand side (RHS) water wall tube of a coal-fired plant. The water wall tube showed the abnormal outer surface colour and has failed with wide-open ductile rupture and thin edges indicating typical signs of short-term overheating. Metallurgical examinations confirmed the failed tube experiencing higher temperature operation. Water flow starvation due to restriction inside the upstream tube is identified as the main root cause of failure. The findings are important to take failure mitigation actions in the future operation. Discussion on the typical problems related to the cooling process in nuclear power plants is also presented.

Derived heuristics-based consistent optimization of material flow in a gold processing plant

Science.gov (United States)

Myburgh, Christie; Deb, Kalyanmoy

2018-01-01

Material flow in a chemical processing plant often follows complicated control laws and involves plant capacity constraints. Importantly, the process involves discrete scenarios which when modelled in a programming format involves if-then-else statements. Therefore, a formulation of an optimization problem of such processes becomes complicated with nonlinear and non-differentiable objective and constraint functions. In handling such problems using classical point-based approaches, users often have to resort to modifications and indirect ways of representing the problem to suit the restrictions associated with classical methods. In a particular gold processing plant optimization problem, these facts are demonstrated by showing results from MATLAB®'s well-known fmincon routine. Thereafter, a customized evolutionary optimization procedure which is capable of handling all complexities offered by the problem is developed. Although the evolutionary approach produced results with comparatively less variance over multiple runs, the performance has been enhanced by introducing derived heuristics associated with the problem. In this article, the development and usage of derived heuristics in a practical problem are presented and their importance in a quick convergence of the overall algorithm is demonstrated.

Relationships at the aboveground-belowground interface: plants, soil biota and soil processes

NARCIS (Netherlands)

Porazinska, D.L.; Bardgett, R.D.; Postma-Blaauw, M.B.; Hunt, H.W.; Parsons, A.N.; Seastedt, T.R.; Wall, D.M.

2003-01-01

Interactions at the aboveground-below ground interface provide important feedbacks that regulate ecosystem processes. Organisms within soil food webs are involved in processes of decomposition and nutrient mineralization, and their abundance and activity have been linked to plant ecophysiological

The use of process simulation models in virtual commissioning of process automation software in drinking water treatment plants

NARCIS (Netherlands)

Worm, G.I.M.; Kelderman, J.P.; Lapikas, T.; Van der Helm, A.W.C.; Van Schagen, K.M.; Rietveld, L.C.

2012-01-01

This research deals with the contribution of process simulation models to the factory acceptance test (FAT) of process automation (PA) software of drinking water treatment plants. Two test teams tested the same piece of modified PA-software. One team used an advanced virtual commissioning (AVC)

Lenin nuclear reactor research institute in the tenth five-year plan

International Nuclear Information System (INIS)

Tsykanov, V.A.; Kulov, E.V.

1980-01-01

Main tasks and research results of Lenin Nuclear Reactor Reseach Institute in the 10-th Five-Year Plan are considered. Main research achievements are noted in nuclear power, radiation material testing, accumulation of transuranium elements and investigation of their physicochemical properties at VK-50, BOR-60, SM-2, RBT-6 and MIR reactor plants and in material testing laboratories

Backfitting possibilities of process instrumentation during planning, construction or operation of nuclear power plants

International Nuclear Information System (INIS)

Kaiser, G.E.; Schemmel, R.R.; Warren, H.D.

1985-01-01

The necessity for backfitting existing C and I equipment in nuclear power plants arises as a result of new licensing requirements being imposed or through a need for improved performance as experience with operating plants becomes available. These changes arise either because additional process variables need to be monitored; improved sensors need to be installed (to increase safety or operating margin); more directly sense the processes; or to address concerns in signal conditioning, control algorithms, control system strategy, or safety system design. This paper discusses examples of backfitting experiences on existing plants and some being developed for future improvements

NEURO-FUZZY MODELLING OF BLENDING PROCESS IN CEMENT PLANT

Directory of Open Access Journals (Sweden)

Dauda Olarotimi Araromi

2015-11-01

Full Text Available The profitability of a cement plant depends largely on the efficient operation of the blending stage, therefore, there is a need to control the process at the blending stage in order to maintain the chemical composition of the raw mix near or at the desired value with minimum variance despite variation in the raw material composition. In this work, neuro-fuzzy model is developed for a dynamic behaviour of the system to predict the total carbonate content in the raw mix at different clay feed rates. The data used for parameter estimation and model validation was obtained from one of the cement plants in Nigeria. The data was pre-processed to remove outliers and filtered using smoothening technique in order to reveal its dynamic nature. Autoregressive exogenous (ARX model was developed for comparison purpose. ARX model gave high root mean square error (RMSE of 5.408 and 4.0199 for training and validation respectively. Poor fit resulting from ARX model is an indication of nonlinear nature of the process. However, both visual and statistical analyses on neuro-fuzzy (ANFIS model gave a far better result. RMSE of training and validation are 0.28167 and 0.7436 respectively, and the sum of square error (SSE and R-square are 39.6692 and 0.9969 respectively. All these are an indication of good performance of ANFIS model. This model can be used for control design of the process.

Some Aspects of Process Computers Configuration Control in Nuclear Power Plant Krsko - Process Computer Signal Configuration Database (PCSCDB)

International Nuclear Information System (INIS)

Mandic, D.; Kocnar, R.; Sucic, B.

2002-01-01

During the operation of NEK and other nuclear power plants it has been recognized that certain issues related to the usage of digital equipment and associated software in NPP technological process protection, control and monitoring, is not adequately addressed in the existing programs and procedures. The term and the process of Process Computers Configuration Control joins three 10CFR50 Appendix B quality requirements of Process Computers application in NPP: Design Control, Document Control and Identification and Control of Materials, Parts and Components. This paper describes Process Computer Signal Configuration Database (PCSCDB), that was developed and implemented in order to resolve some aspects of Process Computer Configuration Control related to the signals or database points that exist in the life cycle of different Process Computer Systems (PCS) in Nuclear Power Plant Krsko. PCSCDB is controlled, master database, related to the definition and description of the configurable database points associated with all Process Computer Systems in NEK. PCSCDB holds attributes related to the configuration of addressable and configurable real time database points and attributes related to the signal life cycle references and history data such as: Input/Output signals, Manually Input database points, Program constants, Setpoints, Calculated (by application program or SCADA calculation tools) database points, Control Flags (example: enable / disable certain program feature) Signal acquisition design references to the DCM (Document Control Module Application software for document control within Management Information System - MIS) and MECL (Master Equipment and Component List MIS Application software for identification and configuration control of plant equipment and components) Usage of particular database point in particular application software packages, and in the man-machine interface features (display mimics, printout reports, ...) Signals history (EEAR Engineering

Processes for producing polyhydroxybutyrate and related polyhydroxyalkanoates in the plastids of higher plants

Science.gov (United States)

Somerville, C.R.; Nawrath, C.; Poirier, Y.

1997-03-11

The present invention relates to a process for producing poly-D-(-)-3-hydroxybutyric acid (PHB) and related polyhydroxyalkanoates (PHA) in the plastids of plants. The production of PHB is accomplished by genetically transforming plants with modified genes from microorganisms. The genes encode the enzymes required to synthesize PHB from acetyl-CoA or related metabolites and are fused with additional plant sequences for targeting the enzymes to the plastid. 37 figs.

Darlington tritium removal facility and station upgrading plant dynamic process simulation

International Nuclear Information System (INIS)

Busigin, A.; Williams, G. I. D.; Wong, T. C. W.; Kulczynski, D.; Reid, A.

2008-01-01

Ontario Power Generation Nuclear (OPGN) has a 4 x 880 MWe CANDU nuclear station at its Darlington Nuclear Div. located in Bowmanville. The station has been operating a Tritium Removal Facility (TRF) and a D 2 O station Upgrading Plant (SUP) since 1989. Both facilities were designed with a Distributed Control System (DCS) and programmable logic controllers (PLC) for process control. This control system was replaced with a DCS only, in 1998. A dynamic plant simulator was developed for the Darlington TRF (DTRF) and the SUP, as part of the computer control system replacement. The simulator was used to test the new software, required to eliminate the PLCs. The simulator is now used for operator training and testing of process control software changes prior to field installation. Dynamic simulation will be essential for the ITER isotope separation system, where the process is more dynamic than the relatively steady-state DTRF process. This paper describes the development and application of the DTRF and SUP dynamic simulator, its benefits, architecture, and the operational experience with the simulator. (authors)

Control of the technological processes at ''Azovstal'' plant using radioisotope devices

Energy Technology Data Exchange (ETDEWEB)

Nosochenko, O V; Overchenko, Z V; Karpov, O I; Deryabina, G N

1980-05-01

Considered is the state of radioisotope control of the technological process at 'Azovstal' plant which has permitted to increase the quality of metal and of metal production. With the help of radioisotope densimeter PR-1024 carried out is the control of the density of the lime solution used for hearth spraying at pig iron casting. A system of automatic correction of skip coke supply according to indications of moisture gauges ''Neutron 3-1'' is implemented at blast furnaces. A radioisotope thickness gauge of hot rolling is positioned on the section of finishing stand of thick-sheet plant, its operation is based on the ..gamma.. radiation weakening in dependence on sheet thickness. The introduction of thickness gauges in the automatized system of rolling control is planned. A radioisotope device ''Paza 2'' for measuring of continuous ingot skin thickness is tested successively at the plant. Gamma-relay devices are used to control the level of loose materials in bunkers. Noted is the prospects of using radioisotopic means of control and automatization of technological processes in ferrous matallurgy.

Process description and plant design for preparing ceramic high-level waste forms

International Nuclear Information System (INIS)

Grantham, L.F.; McKisson, R.L.; Guon, J.; Flintoff, J.F.; McKenzie, D.E.

1983-01-01

The ceramics process flow diagram has been simplified and upgraded to utilize only two major processing steps - fluid-bed calcination and hot isostatic press consolidating. Full-scale fluid-bed calcination has been used at INEL to calcine high-level waste for 18 y; and a second-generation calciner, a fully remotely operated and maintained calciner that meets ALARA guidelines, started calcining high-level waste in 1982. Full-scale hot isostatic consolidation has been used by DOE and commercial enterprises to consolidate radioactive components and to encapsulate spent fuel elements for several years. With further development aimed at process integration and parametric optimization, the operating knowledge of full-scale demonstration of the key process steps should be rapidly adaptable to scale-up of the ceramic process to full plant size. Process flowsheets used to prepare ceramic and glass waste forms from defense and commercial high-level liquid waste are described. Preliminary layouts of process flow diagrams in a high-level processing canyon were prepared and used to estimate the preliminary cost of the plant to fabricate both waste forms. The estimated costs for using both options were compared for total waste management costs of SRP high-level liquid waste. Using our design, for both the ceramic and glass plant, capital and operating costs are essentially the same for both defense and commercial wastes, but total waste management costs are calculated to be significantly less for defense wastes using the ceramic option. It is concluded from this and other studies that the ceramic form may offer important advantages over glass in leach resistance, waste loading, density, and process flexibility. Preliminary economic calculations indicate that ceramics must be considered a leading candidate for the form to immobilize high-level wastes

Prioritizing of effective factors on development of medicinal plants cultivation using analytic network process

Directory of Open Access Journals (Sweden)

Ghorbanali Rassam

2014-07-01

Full Text Available For the overall development of medicinal plants cultivation in Iran, there is a need to identify various effective factors on medicinal plant cultivation. A proper method for identifying the most effective factor on the development of the medicinal plants cultivation is essential. This research conducted in order to prioritizing of the effective criteria for the development of medicinal plant cultivation in North Khorasan province in Iran using Analytical Network Process (ANP method. The multi-criteria decision making (MCDM is suggested to be a viable method for factor selection and the analytic network process (ANP has been used as a tool for MCDM. For this purpose a list of effective factors offered to expert group. Then pair wise comparison questionnaires were distributed between relevant researchers and local producer experts of province to get their opinions about the priority of criteria and sub- criteria. The questionnaires were analyzed using Super Decision software. We illustrated the use of the ANP by ranking main effective factors such as economic, educational-extension services, cultural-social and supportive policies on development of medicinal plants. The main objective of the present study was to develop ANP as a decision making tool for prioritizing factors affecting the development of medicinal plants cultivation. Results showed that the ANP methodology was perfectly suited to tackling the complex interrelations involved in selection factor in this case. Also the results of the process revealed that among the factors, supporting the cultivation of medicinal plants, build the infrastructure for marketing support, having educated farmer and easy access to production input have most impact on the development of medicinal plant cultivation.

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

Idaho Chemical Processing Plant Site Development Plan

International Nuclear Information System (INIS)

Ferguson, F.G.

1994-02-01

The Idaho Chemical Processing Plant (ICPP) mission is to receive and store spent nuclear fuels and radioactive wastes for disposition for Department of Energy (DOE) in a cost-effective manner that protects the safety of Idaho National Engineering Laboratory (INEL) employees, the public, and the environment by: Developing advanced technologies to process spent nuclear fuel for permanent offsite disposition and to achieve waste minimization. Receiving and storing Navy and other DOE assigned spent nuclear fuels. Managing all wastes in compliance with applicable laws and regulations. Identifying and conducting site remediation consistent with facility transition activities. Seeking out and implementing private sector technology transfer and cooperative development agreements. Prior to April 1992, the ICPP mission included fuel reprocessing. With the recent phaseout of fuel reprocessing, some parts of the ICPP mission have changed. Others have remained the same or increased in scope

Technological, economic and sustainability evaluation of power plants using the analytic hierarchy process

International Nuclear Information System (INIS)

Chatzimouratidis, Athanasios I.; Pilavachi, Petros A.

2009-01-01

Complexity of power plant evaluation is steadily rising, as more criteria are involved in the overall assessment while evaluation data change rapidly. Apart from evaluating several aspects of power plants separately, a multicriteria analysis based on hierarchically structured criteria is necessary, so as to address the overall assessment of power plants according to the technological, economic and sustainability aspects. For this reason, in this paper, ten types of power plant are evaluated using nine end node criteria properly structured under the Analytical Hierarchy Process. Moreover, pairwise comparisons allow for accurate subjective criteria weighting. According to the scenario based on the subjective criteria weighting, emphasis is laid on sustainability driving renewable energy power plants at the top of the overall ranking, while nuclear and fossil fuel power plants rank in the last five positions. End node criteria contribution to each power plant and power plant performance per end node criterion is presented for all types of power plant and end node criteria. (author)

A REVIEW ON DIAGNOSIS OF NUTRIENT DEFICIENCY SYMPTOMS IN PLANT LEAF IMAGE USING DIGITAL IMAGE PROCESSING

Directory of Open Access Journals (Sweden)

S Jeyalakshmi

2017-05-01

Full Text Available Plants, for their growth and survival, need 13 mineral nutrients. Toxicity or deficiency in any one or more of these nutrients affects the growth of plant and may even cause the destruction of the plant. Hence, a constant monitoring system for tracking the nutrient status in plants becomes essential for increase in production as well as quality of yield. A diagnostic system using digital image processing would diagnose the deficiency symptoms much earlier than human eyes could recognize. This will enable the farmers to adopt appropriate remedial action in time. This paper focuses on the review of work using image processing techniques for diagnosing nutrient deficiency in plants.

Effect of processing on iodine content of some selected plants food ...

African Journals Online (AJOL)

Effect of processing on iodine content of some selected plants food was investigated. Results show significant reduction (p < 0.05) in the iodine content of the processed food compared with the raw forms. The iodine value of 658.60 ± 17.2 ìg/100g observed in raw edible portion of Discorea rotundata was significantly higher ...

Evaluation of regulatory processes affecting nuclear power plant early site approval and standardization

International Nuclear Information System (INIS)

1983-12-01

This report presents the results of a survey and evaluation of existing federal, state and local regulatory considerations affecting siting approval of power plants in the United States. Those factors that may impede early site approval of nuclear power plants are identified, and findings related to the removal of these impediments and the general improvement of the approval process are presented. A brief evaluation of standardization of nuclear plant design is also presented

Reliability and maintenance in European nuclear power plants: A structural analysis of a controlled stochastic process

International Nuclear Information System (INIS)

Sturm, R.

1991-01-01

Two aspects of performance are of main concern: plant availability and plant reliability (defined as the conditional probability of an unplanned shutdown). The goal of the research is a unified framework that combines behavioral models of optimizing agents with models of complex technical systems that take into account the dynamic and stochastic features of the system. In order to achieve this synthesis, two liens of work are necessary. One line requires a deeper understanding of complex production systems and the type of data they give rise to; the other line involves the specification and estimation of a rigorously specified behavioral model. Plant operations are modeled as a controlled stochastic process, and the sequence of up and downtime spells is analyzed during failure time and point process models. Similar to work on rational expectations and structural econometric models, the behavior model of how the plant process is controlled is formulated at the level of basic processes, i.e., the objective function of the plant manager, technical constraints, and stochastic disturbances

Ammonia-water exchange front end process for ammonia-hydrogen heavy water plants (Preprint No. PD-1)

International Nuclear Information System (INIS)

Sadhukhan, H.K.; Varadarajan, T.G.; Nair, N.K.; Das, S.K.; Nath, G.K.

1989-04-01

The ammonia-hydrogen exchange process, which utilizes the deutrium exchange between liquid ammonia and gaseous hydrogen is a parasitic process and the heavy water plants (HWP) based on this process has to be linked with the fertilizer plant (FP) for its enormous requirements of hydrogen (synthesis gas, N 2 +3H 2 ). This dependence of HWP on FP gives rise to certain constraints which are listed. These deficiencies of the ammonia-hydrogen process can be overcome to a great extent by delinking the HWP from FP by incorporating NH 3 -H 2 O exchange as the front end step. In addition to the elimination of the above limitations, by employing water as the ultimate feed for the HWP, the plant capacity can be increased substantially and this would go a long way in achieving economies of the large capacity plants. A schematic diagram of this integrated plant is given. Some of the results of developmental efforts and feasibility studies of this NH 3 -H 2 O exchange are briefly reviewed. (author). 4 figs

Advanced safeguards systems development for chemical processing plants. Final report for Fiscal Year 1979

International Nuclear Information System (INIS)

Johnson, C.E.

1980-01-01

A computer system is being installed by INEL to test and evaluate safeguards monitoring concepts in an operating nuclear fuel processing plant. Safeguards development sensors and instruments installed in the ICPP provide plant information to a computer data acquisition and analysis system. Objective of the system is to collect data from process and safeguards sensors and show how this data can be analyzed to detect diversion operations or improper plant operation, and to test the performance of the monitoring devices. Approximately one-third of the installation designs and one-eighth of the installations were completed in FY 1979. The ICPP processing schedule for FY 1980 permits installation of the remaining monitoring devices before process startup in the fourth quarter of FY 1980. All computer hardware was delivered and checked out in FY 1979. Computer software system designs were completed with the majority of the programming scheduled for FY 1980. Sensor and instrument development in FY 1979 emphasized device testing for ICPP monitoring applications

Modified ADS molten salt processes for back-end fuel cycle of PWR spent fuel

International Nuclear Information System (INIS)

Choi, In-Kyu; Yeon, Jei-Won; Kim, Won-Ho

2002-01-01

The back-end fuel cycle concept for PWR spent fuel is explained. This concept is adequate for Korea, which has operated both PWR and CANDU reactors. Molten salt processes for accelerator driven system (ADS) were modified both for the transmutation of long-lived radioisotopes and for the utilisation of the remained fissile uranium in PWR spent fuels. Prior to applying molten salt processes to PWR fuel, hydrofluorination and fluorination processes are applied to obtain uranium hexafluoride from the spent fuel pellet. It is converted to uranium dioxide and fabricated into CANDU fuel. From the remained fluoride compounds, transuranium elements can be separated by the molten salt technology such as electrowinning and reductive extraction processes for transmutation purpose without weakening the proliferation resistance of molten salt technology. The proposed fuel cycle concept using fluorination processes is thought to be adequate for our nuclear program and can replace DUPIC (Direct Use of spent PWR fuel in CANDU reactor) fuel cycle. Each process for the proposed fuel cycle concept was evaluated in detail

Utilizing clad piping to improve process plant piping integrity, reliability, and operations

International Nuclear Information System (INIS)

Chakravarti, B.

1996-01-01

During the past four years carbon steel piping clad with type 304L (UNS S30403) stainless steel has been used to solve the flow accelerated corrosion (FAC) problem in nuclear power plants with exceptional success. The product is designed to allow ''like for like'' replacement of damaged carbon steel components where the carbon steel remains the pressure boundary and type 304L (UNS S30403) stainless steel the corrosion allowance. More than 3000 feet of piping and 500 fittings in sizes from 6 to 36-in. NPS have been installed in the extraction steam and other lines of these power plants to improve reliability, eliminate inspection program, reduce O and M costs and provide operational benefits. This concept of utilizing clad piping in solving various corrosion problems in industrial and process plants by conservatively selecting a high alloy material as cladding can provide similar, significant benefits in controlling corrosion problems, minimizing maintenance cost, improving operation and reliability to control performance and risks in a highly cost effective manner. This paper will present various material combinations and applications that appear ideally suited for use of the clad piping components in process plants

Plant process computer system upgrades at the KSG simulator centre

International Nuclear Information System (INIS)

2006-01-01

The human-machine interface (HMI) of a modern plant process computer system (PPC) differs significantly from that of older systems. Along with HMI changes, there are often improvements to system functionality such as alarm display and printing functions and transient data analysis capabilities. Therefore, the upgrade or replacement of a PPC in the reference plant will typically require an upgrade of the simulator (see Section 6.5.1 for additional information). Several options are available for this type of project including stimulation of a replica system,or emulation, or simulation of PPC functionality within the simulation environment. To simulate or emulate a PCC, detailed knowledge of hardware and software functionality is required. This is typically vendor proprietary information, which leads to licensing and other complications. One of the added benefits of stimulating the PPC system is that the simulator can be used as a test bed for functional testing (i.e. verification and validation) of the system prior to installation in the reference plant. Some of this testing may include validation of the process curve and system diagram displays. Over the past few years several German NPPs decided to modernize their plant process computer (PPC) systems. After the NPPs had selected the desired system to meet their requirements the question arose how to modernize the PPC systems on the corresponding simulators. Six German NPPs selected the same PPC system from the same vendor and it was desired to perform integral tests of the HMI on the simulators. In this case the vendor offered a stimulated variant of their system and it therefore made sense to choose that implementation method for upgrade of the corresponding simulators. The first simulator PPC modernization project can be considered as a prototype project for the follow-on projects. In general, from the simulator project execution perspective the implementation of several stimulated PPC systems of the same type

Process synthesis for natural products from plants based on PAT methodology

DEFF Research Database (Denmark)

Malwade, Chandrakant Ramkrishna; Qu, Haiyan; Rong, Ben-Guang

2017-01-01

(QbD) approach, has been included at various steps to obtain molecular level information of process streams and thereby, support the rational decision making. The formulated methodology has been used to isolate and purify artemisinin, an antimalarial drug, from dried leaves of the plant Artemisia...... generates different process flowsheet alternatives consisting of multiple separation techniques. Decision making is supported by heuristics as well as basic process information already available from previous studies. In addition, process analytical technology (PAT) framework, a part of Quality by Design...

Vacuolar processing enzyme in plant programmed cell death

Directory of Open Access Journals (Sweden)

Noriyuki eHatsugai

2015-04-01

Full Text Available Vacuolar processing enzyme (VPE is a cysteine proteinase originally identified as the proteinase responsible for the maturation and activation of vacuolar proteins in plants, and it is known to be an orthologue of animal asparaginyl endopeptidase (AEP/VPE/legumain. VPE has been shown to exhibit enzymatic properties similar to that of caspase 1, which is a cysteine protease that mediates the programmed cell death (PCD pathway in animals. Although there is limited sequence identity between VPE and caspase 1, their predicted three-dimensional structures revealed that the essential amino-acid residues for these enzymes form similar pockets for the substrate peptide YVAD. In contrast to the cytosolic localization of caspases, VPE is localized in vacuoles. VPE provokes vacuolar rupture, initiating the proteolytic cascade leading to PCD in the plant immune response. It has become apparent that the VPE-dependent PCD pathway is involved not only in the immune response, but also in the responses to a variety of stress inducers and in the development of various tissues. This review summarizes the current knowledge on the contribution of VPE to plant PCD and its role in vacuole-mediated cell death, and it also compares VPE with the animal cell death executor caspase 1.

Process integration of chemical looping combustion with oxygen uncoupling in a coal-fired power plant

International Nuclear Information System (INIS)

Spinelli, Maurizio; Peltola, Petteri; Bischi, Aldo; Ritvanen, Jouni; Hyppänen, Timo; Romano, Matteo C.

2016-01-01

High-temperature solid looping processes for CCS (carbon capture and storage) represent a class of promising technologies that enables CO2 capture with relatively low net efficiency penalties. The novel concept of the CLOU (Chemical Looping with Oxygen Uncoupling) process is based on a system of two interconnected fluidized bed reactors that operate at atmospheric pressure. In the fuel reactor, the capability of certain metal oxides to spontaneously release molecular oxygen at high temperatures is exploited to promote the direct conversion of coal in an oxygen-rich atmosphere. As a novel CO_2 capture concept, the CLOU process requires the optimization of design and operation parameters, which may substantially influence the total power plant performance. This study approaches this issue by performing joint simulations of CLOU reactors using a 1.5D model and a steam cycle power plant. A sensitivity analysis has been performed to investigate the performance and main technical issues that are related to the integration of a CLOU island in a state-of-the-art USC (ultra-supercritical) power plant. In particular, the effect of the key process parameters has been evaluated. Superior performance has been estimated for the power plant, with electrical efficiencies of approximately 42% and more than 95% CO2 avoided. - Highlights: • Process modeling and simulation of CLOU integrated in USC coal power plant carried out. • Comprehensive sensitivity analysis on Cu-based CLOU process performed. • Electrical efficiencies of 42% and more than 95% CO_2 avoided obtained. • Reactor size and operating conditions suitable for industrial applications.

Process and device for remote inspection of parts of a nuclear plant

International Nuclear Information System (INIS)

Schmalfuss, H.

1987-01-01

The process is suitable for remote position inspection of the parts of the plant in a large hot cell, for example of a reprocessing plant. A device with a TV camera was selected as the inspection system, where pictures obtained by photography are compared (photogrammetry). The possible resolution is considerably increased by using two spatially movable separate picture systems with the associated drawing media. (DG) [de

Revisit of analytical methods for the process and plant control analyses during reprocessing of fast reactor fuels

International Nuclear Information System (INIS)

Subba Rao, R.V.

2016-01-01

CORAL (COmpact facility for Reprocessing of Advanced fuels in Lead cell) is an experimental facility for demonstrating the reprocessing of irradiated fast reactor fuels discharged from the Fast Breeder Test Reactor (FBTR). The objective of the reprocessing plant is to achieve nuclear grade plutonium and uranium oxides with minimum process waste volumes. The process flow sheet for the reprocessing of spent Fast Reactor Fuel consists of Transport of spent fuel, Chopping, Dissolution, Feed conditioning, Solvent Extraction cycle, Partitioning Cycle and Re-conversion of Plutonium nitrate and uranium nitrate to respective oxides. The efficiency and performance of the plant to achieve desired objective depends on the analyses of various species in the different steps adopted during reprocessing of fuels. The analytical requirements in the plant can be broadly classified as 1. Process control Analyses (Analyses which effect the performance of the plant- PCA); 2. Plant control Analyses (Analyses which indicates efficiency of the plant-PLCA); 3. Nuclear Material Accounting samples (Analyses which has bearing on nuclear material accounting in the plant - NUMAC) and Quality control Analyses (Quality of the input bulk chemicals as well as products - QCA). The analytical methods selected are based on the duration of analyses, precision and accuracies required for each type analytical requirement classified earlier. The process and plant control analyses requires lower precision and accuracies as compared to NUMAC analyses, which requires very high precision accuracy. The time taken for analyses should be as lower as possible for process and plant control analyses as compared to NUMAC analyses. The analytical methods required for determining U and Pu in process and plant samples from FRFR will be different as compared to samples from TRFR (Thermal Reactor Fuel Reprocessing) due to higher Pu to U ratio in FRFR as compared TRFR and they should be such that they can be easily

Development of RBWR (Resource-renewable BWR) for environmental burden reduction of radioactive wastes

International Nuclear Information System (INIS)

Hino, Tetsushi; Ohtsuka, Masaya; Moriya, Kumiaki; Matsuura, Masayoshi

2014-01-01

Accumulation of long-life transuranium elements produced as by-products with uranium fuel burning became an issue of nuclear power. Hitachi had been developing the reactor with transuranium elements burning as fuels based on BWR type reactors successfully used as commercial reactors: RBWR (Resource-renewable BWR). Efficient transmutation and fissioning of transuranium elements needed adjustment of in-core neutron energy spectra distribution better for nuclear reaction of transuranium elements. Taking advantage of characteristics of BWR type reactors with neutron spectra hardening more easily adjustable than other type of reactors, multiple recycling and fissioning transuranium elements as fuels could make environmental burden reduction of radioactive wastes and efficient use of resources compatible. This article described the concept and history of RBWR and showed its specifications and reactor core characteristics. (T. Tanaka)

Liquid radioactive waste processing improvement of PWR nuclear power plants

International Nuclear Information System (INIS)

Nery, Renata Wolter dos Reis; Martinez, Aquilino Senra; Monteiro, Jose Luiz Fontes

2005-01-01

The study evaluate an inorganic ion exchange to process the low level liquid radwaste of PWR nuclear plants, so that the level of the radioactivity in the effluents and the solid waste produced during the treatment of these liquid radwaste can be reduced. The work compares two types of ion exchange materials, a strong acid cation exchange resin, that is the material typically used to remove radionuclides from PWR nuclear plants wastes, and a mordenite zeolite. These exchange material were used to remove cesium from a synthetic effluent containing only this ion and another effluent containing cesium and cobalt. The breakthrough curves of the zeolite and resin using a fix bed reactor were compared. The results demonstrated that the zeolite is more efficient than the resin in removing cesium from a solution containing cesium and cobalt. The results also showed that a bed combining zeolite and resin can process more volume of an effluent containing cesium and cobalt than a bed resin alone. (author)

Defense waste processing facility at Savannah River Plant. Instrument and power jumpers

International Nuclear Information System (INIS)

Heckendorm, F.M. II.

1983-06-01

The Defense Waste Processing Facility (DWPF) for waste vitrification at the Savannah River Plant is in the final design stage. Development of equipment interconnecting devices or jumpers for use within the remotely operated processing canyon is now complete. These devices provide for the specialized instrument and electrical requirements of the DWPF process for low-voltage, high-frequency, and high-power interconnections

Operating experiences of Heavy Water Plant at Talcher using bithermal ammonia-hydrogen exchange process (Paper No. 1.9)

International Nuclear Information System (INIS)

Haldar, T.K.; Manoj Kumar; Ramamurty, C.B.

1992-01-01

A heavy water plant employing bithermal ammonia-hydrogen exchange process was set up at Talcher (India). The energy consumption in the process is lower as compared to monothermal process. The plant performance was affected by various problems and has resulted in low heavy water production. The problems are: (i)formation of solid deposits, (ii)inability of exchange towers to process design gas flow rates, (iii)inadequate exchange efficiency of the sieve trays provided as exchange trays, and (iv)differential amide concentration in different plant sections. These problems and their effect on the overall plant performance are discussed in detail and modifications to improve the performance are suggested. (author). 4 figs

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.)

EDRP public local inquiry, UKAEA/BNFL precognition on: EDRP process and plant

International Nuclear Information System (INIS)

Walker, B.J.

1986-01-01

A description is given of the process to be operated in the proposed EDRP, and of the plant and equipment in which the process will be carried out. The design and construction of new facilities to be provided on the EDRP site at Dounreay are detailed. (U.K.)

Evidence for the remobilisation of transuranic elements in the terrestrial environment.

Science.gov (United States)

Hursthouse, A S; Livens, F R

1993-09-01

The transuranium elements, Np, Pu and Am discharged from the BNFL fuel reprocessing plant at Sellafield have accumulated in the local environment. The processes responsible for their dispersal rely both on physical transportation and their chemical reactivity. The transuranics have a complex chemistry, with multiple oxidation states and a strongly polarising character. In the environment, the particle active III/IV and more mobile VNI oxidation state groups are important and govern their geochemical behaviour and subsequent dispersal.Studies of the behaviour of the transuranics, particularly Pu, in the Irish Sea, have shown that the majority of the radionuclides in the liquid effluent discharged from Sellafield, quickly becomes associated with the marine sediments. Their dispersal and distribution in the environment is then governed primarily by the movement of particulate material and for some sites it has been suggested that sediment profiles preserve the historical record of discharges from the plant.In tidally inundated soils, radionuclide levels are greatly enhanced. These soils are water-logged for long periods of the year, are strongly anoxic and accretion rate are very low. The distribution of Np, Pu and Am in the soil suggests that simple sedimentary accumulation mechanism cannot provide an adequate explanation for the profiles observed. From preliminary studies of soil pore water composition and detailed analysis of the variation of isotopic ratios in the soil cores, it is apparent that a small but significant component of the radionuclide inventory is mobile. In addition, it is clear that the mechanisms responsible for this mobility allows differentiation between the transuranium nuclides.

Manufacturing plant location selection in logistics network using Analytic Hierarchy Process

Directory of Open Access Journals (Sweden)

Ping-Yu Chang

2015-11-01

Full Text Available Purpose: In recent years, numerous companies have moved their manufacturing plants to China to capitalize on lower cost and tax. Plant location has such an impact on cost, stocks, and logistics network but location selection in the company is usually based on subjective preference of high ranking managers. Such a decision-making process might result in selecting a location with a lower fixed cost but a higher operational cost. Therefore, this research adapts real data from an electronics company to develop a framework that incorporates both quantitative and qualitative factors for selecting new plant locations. Design/methodology/approach: In-depth interviews were conducted with 12 high rank managers (7 of them are department manager, 2 of them are vice-president, 1 of them is senior engineer, and 2 of them are plant manager in the departments of construction, finance, planning, production, and warehouse to determine the important factors. A questionnaire survey is then conducted for comparing factors which are analyzed using the Analytic Hierarchy Process (AHP. Findings: Results show that the best location chosen by the developed framework coincides well with the company’s primal production base. The results have been presented to the company’s high ranking managers for realizing the accuracy of the framework. Positive responses of the managers indicate usefulness of implementing the proposed model into reality, which adds to the value of this research. Practical implications: The proposed framework can save numerous time-consuming meetings called to compromise opinions and conflictions from different departments in location selection. Originality/value: This paper adapts the Analytic Hierarchy Process (AHP to incorporate quantitative and qualitative factors which are obtained through in-depth interviews with high rank managers in a company into the location decision.

Technical study for the automation and control of processes of the chemical processing plant for liquid radioactive waste at Racso Nuclear Center

International Nuclear Information System (INIS)

Quevedo D, M.; Ayala S, A.

1997-01-01

The purpose of this study is to introduce the development of an automation and control system in a chemical processing plant for liquid radioactive waste of low and medium activity. The control system established for the chemical processing plant at RACSO Nuclear Center is described. It is an on-off sequential type system with feedback. This type of control has been chosen according to the volumes to be treated at the plant as processing is carried out by batches. The system will be governed by a programmable controller (PLC), modular, with a minimum of 24 digital inputs, 01 analog input, 16 digital outputs and 01 analog input. Digital inputs and outputs are specifically found at the level sensors of the tanks and at the solenoid-type electro valve control. Analog inputs and outputs have been considered at the pH control. The comprehensive system has been divided into three control bonds, The bonds considered for the operation of the plant are described, the plant has storing, fitting, processing and clarifying tanks. National Instruments' Lookout software has been used for simulation, constituting an important tool not only for a design phase but also for a practical one since this software will be used as SCADA system. Finally, the advantages and benefits of this automation system are analyzed, radiation doses received by occupationally exposed workers are reduced and reliability on the operation on the system is increased. (authors)

Uptake and distribution of Pu, Am, Cm and Np in four plant species

Energy Technology Data Exchange (ETDEWEB)

Schreckhise, R G; Cline, J F [Battelle, Pacific Northwest Laboratories, Richland, WA (United States)

1978-12-01

The relative uptake of the nitrate forms of {sup 238}Pu, {sup 239}Pu, {sup 241}Sm, {sup 244}Cm and {sup 237}Np from soil into selectee parts of four different plant species grown under field conditions were observed. Cheatgrass (Bromus tectorum L.), peas (Pisum sativum, var. Blue Bonnet), barley (Hordeum vulgare, var. U. Cal. Briggs), and alfalfa (Medicago sativa, var. Ranger) were grown outdoors in contaminated soil contained in small weighing lysimeters constructed from 13.2 cm diameter by 1-meter-long polyvinyl chloride pipe. The amended soil, containing 0.1 to 1.0 mCi of each isotope individually per 3.4 kg soil, was situated in a 20 cm band and covered by 10 cm of uncontaminated soil to eliminate chances of windblown contamination to the surrounding environs. The plants were harvested at maturity, divided into selected components and radiochemically analyzed by alpha-energy analysis. There did not appear to be any effect of soil concentration on the plant uptake of {sup 238}Pu, {sup 239}Pu, {sup 241}Am or {sup 244}Cm for the two levels utilized (approximately 0.03 and 0.3 {mu}Ci/g soil). The relative uptake of {sup 238}Pu and {sup 239}Pu were not significantly different. Likewise, {sup 241} Am uptake values were not significantly different from the {sup 244}Cm values. The relative plant uptake of the four different transuranium element was: Np > Cm {approx} Am > Pu. The relative uptake values of Np were 2,200 to 45,000 times greater than for Pu, while Am and Cm values were 10 to 20 times greater. The seeds were significantly lower than the rest of the above ground plant parts for all four transuranics. The legumes accumulated approximately ten times more than the grasses. A hypothetical comparison of the radionuclide content of plants grown in soil contaminated with LMFBR fuels indicate that Am, Cm and Np concentrations would exceed Pu values. (author)

Low-level radioactive waste processing at nuclear power plants

International Nuclear Information System (INIS)

1992-12-01

The Solid Radwaste Processing Source Book is presented as a supplement to the Liquid Radwaste Source Book released in 1990 and updated in 1991. The publication is the result of an industry-wide survey, and is intended as a resource for technical and managerial decisions involving of the processing of solid radioactive waste including ''wet'' and ''dry'' active waste as found at both Pressurized and Boiling Water Reactor sites. In addition to information on processes, vendors, volumes, and in-plant management activities, technology under consideration for future use and computer applications are listed. Together with key personnel and contact information contained in the Liquid Source Books, the collected data will be of great use when seeking specific, unbiased experience on which to base decisions related to so processing, disposal policy, or potential economic and regulatory impact

A new method of knowledge processing for equipment diagnosis of nuclear power plants

International Nuclear Information System (INIS)

Fujii, M.; Fukumoto, A.; Tai, I.; Morioka, T.

1987-01-01

In this work, the authors complete the development of a new knowledge processing method and representation for equipment diagnosis of nuclear power plants and evaluate its functions by applying to the maintenance and diagnosis support system of the reactor instrumentation. This knowledge processing method system is based on the Cause Generation and Checking concept and has sufficient performance not only in the diagnosis function but also in the man-machine interfacing function. The maintenance and diagnosis support system based on this method leads to the possibility for users to diagnose various phenomena occurred in an objective equipment to the considerable extent by consulting with the system, even if they don't have enough knowledge. With this system, it becomes easy for operators or plant engineers to take immediate actions to counteract against the abnormality. The maintainability of the equipments is improved and MTTR (Mean Time To Repair) is expected to be shorter. This new knowledge processing method is proved to be suited for fault diagnosis of the equipments of nuclear power plants

Multistep food plant processing at Grotta Paglicci (Southern Italy) around 32,600 cal B.P.

Science.gov (United States)

Mariotti Lippi, Marta; Foggi, Bruno; Aranguren, Biancamaria; Ronchitelli, Annamaria; Revedin, Anna

2015-09-29

Residue analyses on a grinding tool recovered at Grotta Paglicci sublayer 23A [32,614 ± 429 calibrated (cal) B.P.], Southern Italy, have demonstrated that early modern humans collected and processed various plants. The recording of starch grains attributable to Avena (oat) caryopses expands our information about the food plants used for producing flour in Europe during the Paleolithic and about the origins of a food tradition persisting up to the present in the Mediterranean basin. The quantitative distribution of the starch grains on the surface of the grinding stone furnished information about the tool handling, confirming its use as a pestle-grinder, as suggested by the wear-trace analysis. The particular state of preservation of the starch grains suggests the use of a thermal treatment before grinding, possibly to accelerate drying of the plants, making the following process easier and faster. The study clearly indicates that the exploitation of plant resources was very important for hunter-gatherer populations, to the point that the Early Gravettian inhabitants of Paglicci were able to process food plants and already possessed a wealth of knowledge that was to become widespread after the dawn of agriculture.

The comparison of greenhouse gas emissions in sewage treatment plants with different treatment processes.

Science.gov (United States)

Masuda, Shuhei; Sano, Itsumi; Hojo, Toshimasa; Li, Yu-You; Nishimura, Osamu

2018-02-01

Greenhouse gas emissions from different sewage treatment plants: oxidation ditch process, double-circulated anoxic-oxic process and anoxic-oxic process were evaluated based on the survey. The methane and nitrous oxide characteristics were discussed based on the gaseous and dissolved gas profiles. As a result, it was found that methane was produced in the sewer pipes and the primary sedimentation tank. Additionally, a ventilation system would promote the gasification of dissolved methane in the first treatment units. Nitrous oxide was produced and emitted in oxic tanks with nitrite accumulation inside the sewage treatment plant. A certain amount of nitrous oxide was also discharged as dissolved gas through the effluent water. If the amount of dissolved nitrous oxide discharge is not included, 7-14% of total nitrous oxide emission would be overlooked. Based on the greenhouse gas calculation, electrical consumption and the N 2 O emission from incineration process were major sources in all the plants. For greenhouse gas reduction, oxidation ditch process has an advantage over the other advanced systems due to lower energy consumption, sludge production, and nitrogen removal without gas stripping. Copyright © 2017 Elsevier Ltd. All rights reserved.

Thoughts on environmental actinide research-future and present situation

International Nuclear Information System (INIS)

Yamamoto, Masayoshi

2002-01-01

Thoughts on environmental actinides, especially transuranium elements, are presented with emphasis on present situation and future researches. It is since 1945 that man has been in direct relationship to the significant quantities of such transuranium elements, although Pu was discovered in 1942 to exist in very small quantities in nature. Substantial amounts of these elements (Np, Pu, Am) have been distributed in the environment mainly as the result of nuclear weapon testing, followed by accident of satellite and release of radioactive substances from nuclear facilities. Chernobyl nuclear power plant accident might serve as a most recent example of such release. Considerable efforts have been devoted to the investigation of the processes involved in the transfer of radionuclides in the environment and how these can be influenced. And, many data (levels and distribution) and knowledge to understand these processes have been obtained and accumulated. The final purpose in all the research was the protection of the human being. The present trends for environmental radioactivity research (or radioecology) involves a further development of models, speciation of radionuclides, tracer studies and countermeasures of other species than man in radiological protection. Joint researches between radioecologists and specialists such as meteorology, oceanography, geology, botany, statistics and so on are more and more needed to make one of the most fascinating environmental sciences. Finally, an effort should be made to develop radioecology into a more hypothesis-oriented science, as mentioned by Platt. (author)

Thorium base fuels reprocessing at the L.P.R. (Radiochemical Processes Laboratory) experimental plant

International Nuclear Information System (INIS)

Almagro, J.C.; Dupetit, G.A.; Deandreis, R.A.

1987-01-01

The availability of the LPR (Radiochemical Processes Laboratory) plant offers the possibility to demonstrate and create the necessary technological basis for thorium fuels reprocessing. To this purpose, the solvents extraction technique is used, employing TBP (at 30%) as solvent. The process is named THOREX, a one-cycle acid, which permits an adequate separation of Th 232 and U 233 components and fission products. For thorium oxide elements dissolution, the 'chopp-leach' process (installed at LPR) is used, employing a NO 3 H 13N, 0.05M FH and 0.1M Al (NO 3 ) 3 , as solvent. To adapt the pilot plant to the flow-sheet requirements proposed, minor modifications must be carried out in the interconnection of the existing decanting mixers. The input of the plant has been calculated by Origin Code modified for irradiations in reactors of the HWR type. (Author)

Design criteria for the new waste calcining facility at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Anderson, F.H.; Bingham, G.E.; Buckham, J.A.; Dickey, B.R.; Slansky, C.M.; Wheeler, B.R.

1976-01-01

The New Waste Calcining Facility (NWCF) at the Idaho Chemical Processing Plant (ICPP) is being built to replace the existing fluidized-bed, high-level waste calcining facility (WCF). Performance of the WCF is reviewed, equipment failures in WCF operation are examined, and pilot-plant studies on calciner improvements are given in relation to NWCF design. Design features of the NWCF are given with emphasis on process and equipment improvements. A major feature of the NWCF is the use of remote maintenance facilities for equipment with high maintenance requirements, thereby reducing personnel exposures during maintenance and reducing downtime resulting from plant decontamination. The NWCF will have a design net processing rate of 11.36 m 3 of high-level waste per day, and will incorporate in-bed combustion of kerosene for heating the fluidized bed calciner. The off-gas cleaning system will be similar to that for the WCF

Intermediate size LWR plant study for process heat plus power. Volume 1. Executive summary

International Nuclear Information System (INIS)

Head, M.A.

1977-01-01

The appropriateness of intermediate sized LWRs is evaluated for application to the process industry and for cogeneration of electric power and process steam. This brief study is directed toward determination of whether such plants show enough promise to warrant more detailed investigation. In light of higher fossil fuel costs, the study shows that intermediate sized, standardized power plants potentially are economically competitive for such industrial applications. A representative intermediate sized operating plant of the BWR/4 design class, the Swiss Muhleberg unit (1000 MWt) has been examined with respect to design, licensability, capacity factor and cost. It has operated at high capacity factor (approximately 75 percent) since turnover 11/72. Its cost when escalated from 1969 to 1976 ($620/kWe) appears competitive. Cost adjustments ($100-$250/kWe) included at this stage for compliance with current licensing and mandatory design requirements are only a preliminary estimate. Further study is recommended to confirm necessary regulatory upgrades for this BWR/4 nuclear plant and to explore specific cost economies through replication leading to a program for construction of a demonstration plant

Initiating events study of the first extraction cycle process in a model reprocessing plant

Energy Technology Data Exchange (ETDEWEB)

Wang, Renze; Zhang, Jian Gang; Zhuang, Dajie; Feng, Zong Yang [China Institute for Radiation Protection, Taiyuan (China)

2016-06-15

Definition and grouping of initiating events (IEs) are important basics for probabilistic safety assessment (PSA). An IE in a spent fuel reprocessing plant (SFRP) is an event that probably leads to the release of dangerous material to jeopardize workers, public and environment. The main difference between SFRPs and nuclear power plants (NPPs) is that hazard materials spread diffusely in a SFRP and radioactive material is just one kind of hazard material. Since the research on IEs for NPPs is in-depth around the world, there are several general methods to identify IEs: reference of lists in existence, review of experience feedback, qualitative analysis method, and deductive analysis method. While failure mode and effect analysis (FMEA) is an important qualitative analysis method, master logic diagram (MLD) method is the deductive analysis method. IE identification in SFRPs should be consulted with the experience of NPPs, however the differences between SFRPs and NPPs should be considered seriously. The plutonium uranium reduction extraction (Purex) process is adopted by the technics in a model reprocessing plant. The first extraction cycle (FEC) is the pivotal process in the Purex process. Whether the FEC can function safely and steadily would directly influence the production process of the whole plant-production quality. Important facilities of the FEC are installed in the equipment cells (ECs). In this work, IEs in the FEC process were identified and categorized by FMEA and MLD two methods, based on the fact that ECs are containments in the plant. The results show that only two ECs in the FEC do not need to be concerned particularly with safety problems, and criticality, fire and red oil explosion are IEs which should be emphatically analyzed. The results are accordant with the references.

29 CFR 788.11 - “Transporting [such] products to the mill, processing plant, railroad, or other transportation...

Science.gov (United States)

2010-07-01

... 29 Labor 3 2010-07-01 2010-07-01 false âTransporting [such] products to the mill, processing plant... EMPLOYED § 788.11 “Transporting [such] products to the mill, processing plant, railroad, or other transportation terminal.” The transportation or movement of logs or other forestry products to a “mill processing...

Nuclear heat source component design considerations for HTGR process heat reactor plant concept

International Nuclear Information System (INIS)

McDonald, C.F.; Kapich, D.; King, J.H.; Venkatesh, M.C.

1982-05-01

The coupling of a high-temperature gas-cooled reactor (HTGR) and a chemical process facility has the potential for long-term synthetic fuel production (i.e., oil, gasoline, aviation fuel, hydrogen, etc) using coal as the carbon source. Studies are in progress to exploit the high-temperature capability of an advanced HTGR variant for nuclear process heat. The process heat plant discussed in this paper has a 1170-MW(t) reactor as the heat source and the concept is based on indirect reforming, i.e., the high-temperature nuclear thermal energy is transported [via an intermediate heat exchanger (IHX)] to the externally located process plant by a secondary helium transport loop. Emphasis is placed on design considerations for the major nuclear heat source (NHS) components, and discussions are presented for the reactor core, prestressed concrete reactor vessel (PCRV), rotating machinery, and heat exchangers

Investigation of Natural Radioactivity in a Monazite Processing Plant in Japan.

Science.gov (United States)

Iwaoka, Kazuki; Yajima, Kazuaki; Suzuki, Toshikazu; Yonehara, Hidenori; Hosoda, Masahiro; Tokonami, Shinji; Kanda, Reiko

2017-09-01

Monazite is a naturally occurring radioactive material that is processed for use in a variety of domestic applications. At present, there is little information available on potential radiation doses experienced by people working with monazite. The ambient dose rate and activity concentration of natural radionuclides in raw materials, products, and dust in work sites as well as the Rn and Rn concentrations in work sites were measured in a monazite processing plant in Japan. Dose estimations for plant workers were also conducted. The activity concentration of the U series in raw materials and products for the monazite processing plant was found to be higher than the relevant values described in the International Atomic Energy Agency Safety Standards. The ambient dose rates in the raw material yard were higher than those in other work sites. Moreover, the activity concentrations of dust in the milling site were higher than those in other work sites. The Rn concentrations in all work sites were almost the same as those in regular indoor environments in Japan. The Rn concentrations in all work sites were much higher than those in regular indoor environments in Japan. The maximum value of the effective dose for workers was 0.62 mSv y, which is lower than the reference level range (1-20 mSv y) for abnormally high levels of natural background radiation published in the International Commission of Radiological Protection Publication 103.

Processed vs. non-processed biowastes for agriculture: effects of post-harvest tomato plants and biochar on radish growth, chlorophyll content and protein production.

Science.gov (United States)

Mozzetti Monterumici, Chiara; Rosso, Daniele; Montoneri, Enzo; Ginepro, Marco; Baglieri, Andrea; Novotny, Etelvino Henrique; Kwapinski, Witold; Negre, Michèle

2015-04-21

The aim of this work was to address the issue of processed vs. non-processed biowastes for agriculture, by comparing materials widely differing for the amount of process energy consumption. Thus, residual post harvest tomato plants (TP), the TP hydrolysates obtained at pH 13 and 60 °C, and two known biochar products obtained by 650 °C pyrolysis were prepared. All products were characterized and used in a cultivation of radish plants. The chemical composition and molecular nature of the materials was investigated by solid state 13C NMR spectrometry, elemental analysis and potentiometric titration. The plants were analysed for growth and content of chlorophyll, carotenoids and soluble proteins. The results show that the TP and the alkaline hydrolysates contain lignin, hemicellulose, protein, peptide and/or amino acids moieties, and several mineral elements. The biochar samples contain also similar mineral elements, but the organic fraction is characterized mainly by fused aromatic rings. All materials had a positive effect on radish growth, mainly on the diameter of roots. The best performances in terms of plant growth were given by miscanthus originated biochar and TP. The most significant effect was the enhancement of soluble protein content in the plants treated with the lowest energy consumption non processed TP. The significance of these findings for agriculture and the environment is discussed.

Extraction of uranium from seawater: chemical process and plant design feasibility study

International Nuclear Information System (INIS)

Campbell, M.H.; Frame, J.M.; Dudey, N.D.; Kiel, G.R.; Mesec, V.; Woodfield, F.W.; Binney, S.E.; Jante, M.R.; Anderson, R.C.; Clark, G.T.

1979-02-01

A major assessment was made of the uranium resources in seawater. Several concepts for moving seawater to recover the uranium were investigated, including pumping the seawater and using natural ocean currents or tides directly. The optimal site chosen was on the southeastern Puerto Rico coast, with the south U.S. Atlantic coast as an alternate. The various processes for extracting uranium from seawater were reviewed, with the adsorption process being the most promising at the present time. Of the possible adsorbents, hydrous titanium oxide was found to have the best properties. A uranium extraction plant was conceptually designed. Of the possible methods for contacting the seawater with the adsorbent, a continuous fluidized bed concept was chosen as most practical for a pumped system. A plant recovering 500 tonnes of U 3 O 8 per year requires 5900 cubic meters per second of seawater to be pumped through the adsorbent beds for a 70% overall recovery efficiency. Total cost of the plant was estimated to be about $6.2 billion. A computer model for the process was used for parametric sensitivity studies and economic projections. Several design case variations were developed. Other topics addressed were the impact of co-product recovery, environmental considerations, etc

Extraction of uranium from seawater: chemical process and plant design feasibility study

Energy Technology Data Exchange (ETDEWEB)

Campbell, M.H.; Frame, J.M.; Dudey, N.D.; Kiel, G.R.; Mesec, V.; Woodfield, F.W.; Binney, S.E.; Jante, M.R.; Anderson, R.C.; Clark, G.T.

1979-02-01

A major assessment was made of the uranium resources in seawater. Several concepts for moving seawater to recover the uranium were investigated, including pumping the seawater and using natural ocean currents or tides directly. The optimal site chosen was on the southeastern Puerto Rico coast, with the south U.S. Atlantic coast as an alternate. The various processes for extracting uranium from seawater were reviewed, with the adsorption process being the most promising at the present time. Of the possible adsorbents, hydrous titanium oxide was found to have the best properties. A uranium extraction plant was conceptually designed. Of the possible methods for contacting the seawater with the adsorbent, a continuous fluidized bed concept was chosen as most practical for a pumped system. A plant recovering 500 tonnes of U/sub 3/O/sub 8/ per year requires 5900 cubic meters per second of seawater to be pumped through the adsorbent beds for a 70% overall recovery efficiency. Total cost of the plant was estimated to be about $6.2 billion. A computer model for the process was used for parametric sensitivity studies and economic projections. Several design case variations were developed. Other topics addressed were the impact of co-product recovery, environmental considerations, etc.

Steam generators and waste heat boilers for process and plant engineers

CERN Document Server

Ganapathy, V

2014-01-01

Incorporates Worked-Out Real-World ProblemsSteam Generators and Waste Heat Boilers: For Process and Plant Engineers focuses on the thermal design and performance aspects of steam generators, HRSGs and fire tube, water tube waste heat boilers including air heaters, and condensing economizers. Over 120 real-life problems are fully worked out which will help plant engineers in evaluating new boilers or making modifications to existing boiler components without assistance from boiler suppliers. The book examines recent trends and developments in boiler design and technology and presents novel idea

Decontamination process applied to radioactive solid wastes from nuclear power plants

International Nuclear Information System (INIS)

Franco, Milton B.; Kastner, Geraldo F.; Monteiro, Roberto Pellacani G.

2009-01-01

The process of decontamination is an important step in the economic operation of nuclear facilities. A large number of protective clothing, metallic parts and equipment get contaminated during the handling of radioactive materials in laboratory, plants and reactors. Safe and economic operation of these nuclear facilities will have a bearing on the extent to which these materials are reclaimed by the process of decontamination. The most common radioactive contaminants are fission products, corrosion products, uranium and thorium. The principles involved in decontamination are the same as those for an industrial cleaning process. However, the main difference is in the degree of cleaning required and at times special techniques have to be employed for removing even trace quantities of radioactive materials. This paper relate decontaminations experiences using acids and acids mixtures (HCl, HF, HNO 3 , KMnO 4 , C 2 H 2 O 4 , HBF 4 ) in several kinds of radioactive solid wastes from nuclear power plants. The result solutions were monitored by nuclear analytical techniques, in order to contribute for radiochemical characterization of these wastes. (author)

Process integration in bioprocess indystry: waste heat recovery in yeast and ethyl alcohol plant

International Nuclear Information System (INIS)

Raskovic, P.; Anastasovski, A.; Markovska, Lj.; Mesko, V.

2010-01-01

The process integration of the bioprocess plant for production of yeast and alcohol was studied. Preliminary energy audit of the plant identified the huge amount of thermal losses, caused by waste heat in exhausted process streams, and reviled the great potential for energy efficiency improvement by heat recovery system. Research roadmap, based on process integration approach, is divided on six phases, and the primary tool used for the design of heat recovery network was Pinch Analysis. Performance of preliminary design are obtained by targeting procedure, for three process stream sets, and evaluated by the economic criteria. The results of process integration study are presented in the form of heat exchanger networks which fulfilled the utilization of waste heat and enable considerable savings of energy in short payback period.

Constructing wetlands: measuring and modeling feedbacks of oxidation processes between plants and clay-rich material

Science.gov (United States)

Saaltink, Rémon; Dekker, Stefan C.; Griffioen, Jasper; Wassen, Martin J.

2016-04-01

Interest is growing in using soft sediment as a building material in eco-engineering projects. Wetland construction in the Dutch lake Markermeer is an example: here the option of dredging some of the clay-rich lake-bed sediment and using it to construct 10.000 ha of wetland will soon go under construction. Natural processes will be utilized during and after construction to accelerate ecosystem development. Knowing that plants can eco-engineer their environment via positive or negative biogeochemical plant-soil feedbacks, we conducted a six-month greenhouse experiment to identify the key biogeochemical processes in the mud when Phragmites australis is used as an eco-engineering species. We applied inverse biogeochemical modeling to link observed changes in pore water composition to biogeochemical processes. Two months after transplantation we observed reduced plant growth and shriveling as well as yellowing of foliage. The N:P ratios of plant tissue were low and were affected not by hampered uptake of N but by enhanced uptake of P. Plant analyses revealed high Fe concentrations in the leaves and roots. Sulfate concentrations rose drastically in our experiment due to pyrite oxidation; as reduction of sulfate will decouple Fe-P in reducing conditions, we argue that plant-induced iron toxicity hampered plant growth, forming a negative feedback loop, while simultaneously there was a positive feedback loop, as iron toxicity promotes P mobilization as a result of reduced conditions through root death, thereby stimulating plant growth and regeneration. Given these two feedback mechanisms, we propose that when building wetlands from these mud deposits Fe-tolerant species are used rather than species that thrive in N-limited conditions. The results presented in this study demonstrate the importance of studying the biogeochemical properties of the building material and the feedback mechanisms between plant and soil prior to finalizing the design of the eco-engineering project.

Are the metabolomic responses to folivory of closely related plant species linked to macroevolutionary and plant-folivore coevolutionary processes?

Energy Technology Data Exchange (ETDEWEB)

Rivas-Ubach, Albert [Environmental Molecular Sciences Laboratory, Pacific Northwest National Laboratory, Richland Washington 99354 USA; CREAF, Cerdanyola del Vallès 08913 Catalonia Spain; Hódar, José A. [Grupo de Ecología Terrestre, Departamento de Biología Animal y Ecología, Facultad de Ciencias, Universidad de Granada, 18071 Granada Spain; Sardans, Jordi [CREAF, Cerdanyola del Vallès 08913 Catalonia Spain; CSIC, Global Ecology Unit CREAF-CEAB-CSIC-UAB, Cerdanyola del Vallès 08913 Catalonia Spain; Kyle, Jennifer E. [Biological Sciences Division, Pacific Northwest National Laboratory, Richland Washington 99354 USA; Kim, Young-Mo [Biological Sciences Division, Pacific Northwest National Laboratory, Richland Washington 99354 USA; Oravec, Michal [Global Change Research Centre, Academy of Sciences of the Czech Republic, Bĕlidla 4a CZ-603 00 Brno Czech Republic; Urban, Otmar [Global Change Research Centre, Academy of Sciences of the Czech Republic, Bĕlidla 4a CZ-603 00 Brno Czech Republic; Guenther, Alex [Department of Earth System Science, University of California, Irvine California 92697 USA; Peñuelas, Josep [CREAF, Cerdanyola del Vallès 08913 Catalonia Spain; CSIC, Global Ecology Unit CREAF-CEAB-CSIC-UAB, Cerdanyola del Vallès 08913 Catalonia Spain

2016-06-02

The debate whether the coevolution of plants and insects or macroevolutionary processes (phylogeny) is the main driver determining the arsenal of molecular defensive compounds of plants remains unresolved. Attacks by herbivorous insects affect not only the composition of defensive compounds in plants but the entire metabolome (the set of molecular metabolites), including defensive compounds. Metabolomes are the final products of genotypes and are directly affected by macroevolutionary processes, so closely related species should have similar metabolomic compositions and may respond in similar ways to attacks by folivores. We analyzed the elemental compositions and metabolomes of needles from Pinus pinaster, P. nigra and P. sylvestris to determine if these closely related Pinus species with different coevolutionary histories with the caterpillars of the processionary moth respond similarly to attacks by this lepidopteran. All pines had different metabolomes and metabolic responses to herbivorous attack. The metabolomic variation among the pine species and the responses to folivory reflected their macroevolutionary relationships, with P. pinaster having the most divergent metabolome. The concentrations of phenolic metabolites were generally not higher in the attacked trees, which had lower concentrations of terpenes, suggesting that herbivores avoid individuals with high concentrations of terpenes. Our results suggest that macroevolutionary history plays important roles in the metabolomic responses of these pine species to folivory, but plant-insect coevolution probably constrains those responses. Combinations of different evolutionary factors and trade-offs are likely responsible for the different responses of each species to folivory, which is not necessarily exclusively linked to plant-insect coevolution.

Silicophosphate Sorbents, Based on Ore-Processing Plants' Waste in Kazakhstan

Science.gov (United States)

Kubekova, Sholpan N.; Kapralova, Viktoria I.; Telkov, Shamil A.

2016-01-01

The problem of ore-processing plants' waste and man-made mineral formations (MMF) disposal is very important for the Republic of Kazakhstan. The research of various ore types (gold, polymetallic, iron-bearing) MMF from a number of Kazakhstan's deposits using a complex physical and chemical methods showed, that the waste's main components are…

Yield analysis at a poultry processing plant in Harare, Zimbabwe ...

African Journals Online (AJOL)

This investigation was conducted to establish the yield of parts or organs of chickens brought for slaughter at a poultry processing plant in Harare. Results of the study will furnish management and other poultry farmers with information that will enable them to identify yield losses and sustainable ways of minimizing resultant ...

The pilot plant experiment of electron beam irradiation process for removal of NOx and SOx from sinter plant exhaust gas in the iron and steel industry

International Nuclear Information System (INIS)

Kawamura, K.; Katayama, T.; Kawamura, Ke.

1981-01-01

Air pollution problem has become more important in the progress of industry. Nitrogen oxides (NOx, mostly NO) and sulfur oxides (SOx, mostly SO 2 ) which are contained in a sinter plant exhaust gas, are known as serious air pollutants. In such circumstances, an attempt has been made to simultaneously remove NOx and SOx from the sinter plant exhaust gas by means of a new electron beam irradiation process. The process consists of adding a small amount of NH 3 to the exhaust gas, irradiating the gas by electron beam, forming ammonium salts by reactions of NOx and SOx with the NH 3 and collecting ammonium salts by dry electrostatic precipitator (E.P.). Basic research on the present process had been performed using heavy oil combustion gas. Based on the results research was launched to study the applicability of the process to the treatment of sinter plant exhaust gas. A pilot plant, capable of treating a gas flow of 3000 Nm 3 /H was set up, and experiments were performed from July 1977 to June 1978. The plant is described and the results are presented. (author)

Effects of Planting and Processing Modes on the Degradation of Dithianon and Pyraclostrobin in Chinese Yam (Dioscorea spp.).

Science.gov (United States)

Shi, Kaiwei; Wu, Xujin; Ma, Jingwei; Zhang, Junfeng; Zhou, Ling; Wang, Hong; Li, Li

2017-12-06

The yam (Dioscorea spp.) is widely cultivated in China. The degradation of dithianon and pyraclostrobin in yams with different planting and processing treatments was investigated in this article. An analytical method for two pesticides in yam and yam plant was developed, and recoveries were between 77% and 93%, with relative standard deviations from 0.8% to 7.4%, respectively. On the basis of this method, half-lives for plants grown on stakes versus plants grown without stakes were compared. The results indicated that the half-life for pesticide residues for plants grown on stakes versus plants grown without stakes differed as 6.7 versus 3.1 days for dithianon and 5.4 versus 5.2 days for pyraclostrobin. Dithianon was significantly influenced by planting mode because of its low stability under sunlight. The processing factors of various processing treatments (hot air-drying, vacuum freeze-drying, microwave vacuum-drying, infrared-drying, steaming, and boiling) were all <1, indicating that those processes can reduce residues of two pesticides at different levels. Significant amounts of residues were removed during the boiling treatment, whereas the others showed less effect.

Operational experinece with large scale biogas production at the promest manure processing plant in Helmond, the Netherlands

International Nuclear Information System (INIS)

Schomaker, A.H.H.M.

1992-01-01

In The Netherlands a surplus of 15 million tons of liquid pig manure is produced yearly on intensive pig breeding farms. The dutch government has set a three-way policy to reduce this excess of manure: 1. conversion of animal fodder into a product with less and better ingestible nutrients; 2. distribution of the surplus to regions with a shortage of animal manure; 3. processing of the remainder of the surplus in large scale processing plants. The first large scale plant for the processing of liquid pig manure was put in operation in 1988 as a demonstration plant at Promest in Helmond. The design capacity of this plant is 100,000 tons of pig manure per year. The plant was initiated by the Manure Steering Committee of the province Noord-Brabant in order to prove at short notice whether large scale manure processing might contribute to the solution of the problem of the manure surplus in The Netherlands. This steering committee is a corporation of the national and provincial government and the agricultural industrial life. (au)

Inhibiting Cadmium Transport Process in Root Cells of Plants: A Review

Directory of Open Access Journals (Sweden)

ZHAO Yan-ling

2016-05-01

Full Text Available Cadmium(Cd is the most common element found in the heavy-metal contaminated soils in China. Roots of rice and vegetables can concentrate Cd from acid soils, and then transport Cd to above-ground parts. Cd in edible part of plants directly influences the food safety. Cellwall, plasma membrane and organells of root cells in plant can discriminate Cd from other elements. A lot of Cd can be fixed in root cells by precipitation, complexation, compartmentation, and so on, to inhibit its transport from roots to shoot and guarantee the physiological activities in above-ground parts carrying out normally. This paper summarized recent advance on inhibiting Cd transport process in subcellular fractions of root cells of plants, which is in advantage of exploring excellent germplasms and gene resources in the future.

Information interfaces for process plant diagnosis

International Nuclear Information System (INIS)

Lind, M.

1984-02-01

The paper describes a systematic approach to the design of information interfaces for operator support in diagnosing complex systems faults. The need of interpreting primary measured plant variables within the framework of different system representations organized into an abstraction hierarchy is identified from an analysis of the problem of diagnosing complex systems. A formalized approach to the modelling of production systems, called Multilevel Flow Modelling, is described. A MFM model specifies plant control requirements and the associated need for plant information and provide a consistent context for the interpretation of real time plant signals in diagnosis of malfunctions. The use of MFM models as a basis for functional design of the plant instrumentation system is outlined, and the use of knowledge Based (Expert) Systems for the design of man-machine interfaces is mentioned. Such systems would allow an active user participation in diagnosis and thus provide the basis for cooperative problem solving. 14 refs. (author)

Designing new nuclear chemical processing plants for safeguards accountability

International Nuclear Information System (INIS)

Sprouse, K.M.

1987-01-01

New nuclear chemical processing plants will be required to develop material accountability control limits from measurement error propagation analysis rather than historical inventory difference data as performed in the past. In order for measurement error propagation methods to be viable alternatives, process designers must ensure that two nondimensional accountability parameters are maintained below 0.1. These parameters are ratios between the material holdup increase and the variance in inventory difference measurement uncertainty. Measurement uncertainty data for use in error propagation analysis is generally available in the open literature or readily derived from instrument calibration data. However, nuclear material holdup data has not been adequately developed for use in the material accountability design process. Long duration development testing on isolated unit operations is required to generate this necessary information

Evaluation of power plants in Turkey using Analytic Network Process (ANP)

International Nuclear Information System (INIS)

Atmaca, Ediz; Basar, Hasan Burak

2012-01-01

Energy is one of the most important parameters of the development of societies. Low cost, clean and secure energy supply is a common issue for all countries. Every country spends commercial and political effort to avoid not having sufficient energy and to ensure an uninterrupted energy supply. This study attempts to determine the suitability of existing power plants in Turkey and the plants that are being considered for establishment in the near future. The alternatives which are being considered are natural gas, wind, geothermal, hydroelectric, and coal/lignite energy plants as well as nuclear energy plants. By using the multi-criteria decision making technique of Analytic Network Process (ANP), a multi-criteria evaluations of six different energy plants were performed with respect to the major criteria such as technology and sustainability, economical suitability, life quality and socio-economic impacts. -- Highlights: ► The study attempted to lay out the criteria based on which power plant investments are evaluated. ► In the energy industry in Turkey and in the world, it is considerably difficult to access data on energy. ► This study will provide significant support for people working in the energy area and related decision makers in Turkey. ► The study is also thought to provide benefit decision makers in the world energy industry. ► It can provide great benefit in ensuring the security of the energy to be produced from power plant investments.

Packaging of radioactive sludges at the Saclay effluent processing plant

International Nuclear Information System (INIS)

Cerre, Pierre; Mestre, Emile; Bourdrez, Jean; Leconnetable, Jean

1964-10-01

The authors describe technical and technological aspects of the packaging workshop for radioactive sludges produced by processes of co-precipitation of Saclay effluents. This facility is an achievement of studies which aimed at improving working conditions for the plant staff. This workshop implements a process of solidification of filtered sludge by mixing with a hydraulic binding agent. After some generalities on the decontamination process applied to effluents produced by the Saclay research centre, the authors present and describe the adopted process, propose a physical description of the facility: building, chemical engineering equipment (filtration, packaging, and handling). They describe facility operation: introduction of a block into the cell, block filling, output of a packaged container. They briefly discuss the first results of facility exploitation [fr

Iodine-129 in aquatic organisms near nuclear fuels processing plants

International Nuclear Information System (INIS)

Watson, D.G.

1975-04-01

Concentrations of 129 I in two aquatic habitats near nuclear fuel processing plants were highest in algae and crustaceans. These two forms may be useful in future monitoring of 129 I. There is some indication of an increase in atom ratios and specific activity in aquatic organisms over that in water and sediments. Additional measurements should be made to verify this conclusion. Efforts should continue to measure the possible long term build-up of 129 I in aquatic environments receiving effluents from fuels reprocessing plants. Even at very low rates of release to the environment, the long physical half-life of 129 I creates the potential for build-up of this nuclide to significant levels. (U.S.)

Distribution and prevalence of airborne microorganisms in three commercial poultry processing plants.

Science.gov (United States)

Whyte, P; Collins, J D; McGill, K; Monahan, C; O'Mahony, H

2001-03-01

Airborne microbial contaminants and indicator organisms were monitored within three poultry processing plants (plants A, B, and C). In total, 15 cubic feet (c.f.) of air was sampled per location during 15 visits to each plant and quantitatively analyzed for total mesophilic and psychrophilic aerobic counts, thermophilic campylobacters, Escherichia coli, and Enterobacteriaceae. The prevalence of Salmonella spp. in air samples was also evaluated. Significant reductions in total aerobic counts were observed between defeathering and evisceration areas of the three plants (P defeathering areas of all plants compared to equivalent psychrophilic plate counts. Enterobacteriaceae counts were highest in the defeathering areas of all three plants with counts of log10 1.63, 1.53, and 1.18 CFU/15 c.f. recovered in plants A, B, and C, respectively. E. coli enumerated from air samples in the defeathering areas exhibited a similar trend to those obtained for Enterobacteriaceae with log10 1.67, 1.58, and 1.18 CFU for plants A, B, and C, respectively. Thermophilic campylobacters were most frequently isolated from samples in the defeathering areas followed by the evisceration areas. The highest mean counts of the organism were observed in plant A at 21 CFU/15 c.f. sample with plants B and C at 9 and 8 CFU/sample, respectively. With the exception of low levels of Enterobacteriaceae recovered from samples in the on-line air chill in plant A, E. coli, Enterobacteriaceae, or Campylobacter spp. were not isolated from samples in postevisceration sites in any of the plants examined. Salmonella spp. were not recovered from any samples during the course of the investigation.

Hanford Waste Vitrification Plant - the project and process systems

International Nuclear Information System (INIS)

Swenson, L.D.; Miller, W.C.; Smith, R.A.

1990-01-01

The Hanford Waste Vitrification Plant (HWVP) project is scheduled to start construction on the Hanford reservation in southeastern Washington State in 1991. The project will immobilize the liquid high-level defense waste stored there. The HWVP represents the third phase of the U.S. Department of Energy (DOE) activities that are focused on the permanent disposal of high-level radioactive waste, building on the experience of Defense Waste Processing Facility (DWPF) at the Savannah River site, South Carolina, and of the West Valley Demonstration Plant (WVDP), New York. This sequential approach to disposal of the country's commercial and defense high-level radioactive waste allows HWVP to make extensive use of lessons learned from the experience of its predecessors, using mature designs from the earlier facilities to achieve economies in design and construction costs while enhancing operational effectiveness

Techno-economic study of CO2 capture process for cement plants. Paper no. IGEC-1-107

International Nuclear Information System (INIS)

Nazmul Hassan, S.M.; Douglas, P.L.; Croiset, E.

2005-01-01

Carbon dioxide is considered to be the major source of GHG responsible for global warming; man-made CO 2 contributes approximately 63.5% to all greenhouse gases. The cement industry is responsible for approximately 5% of global anthropogenic carbon dioxide emissions emitting nearly 900 kg of CO 2 for every 1000 kg of cement produced. Amine absorption processes, in particular the monoethanolamine (MEA) based process, is considered to be a viable technology for capturing CO 2 from low-pressure flue gas streams because of its fast reaction rate with CO 2 and low cost of raw materials compared to other amines. However, the MEA absorption process is associated with high capital and operating costs because a significant amount of energy is required for solvent regeneration and because of severe operating problems such as corrosion, solvent loss and solvent degradation. This research was motivated by the need to design, size and cost a CO 2 capture process from the cement industry. The MEA based absorption process was used as a potential technique to model CO 2 capture from cement plants. In this research four cases were considered all to reach a CO 2 purity of 98%: i) the plant operates at the highest capacity; ii) the plant operates at average load; iii) the plant operates at minimum operating capacity; and iv) switching to a lower carbon content fuel at average plant load. A comparison among the four cases were performed to determine the best operating conditions for capturing CO 2 from cement plants. A sensitivity analysis of the economics to the lean loading and percent recovery were carried out as well as the different absorber and striper tray combinations. (author)

Guidebook on design, construction and operation of pilot plants for uranium ore processing

International Nuclear Information System (INIS)

1990-01-01

The design, construction and operation of a pilot plant are often important stages in the development of a project for the production of uranium concentrates. Since building and operating a pilot plant is very costly and may not always be required, it is important that such a plant be built only after several prerequisites have been met. The main purpose of this guidebook is to discuss the objectives of a pilot plant and its proper role in the overall project. Given the wide range of conditions under which a pilot plant may be designed and operated, it is not possible to provide specific details. Instead, this book discusses the rationale for a pilot plant and provides guidelines with suggested solutions for a variety of problems that may be encountered. This guidebook is part of a series of Technical Reports on uranium ore processing being prepared by the IAEA's Division of Nuclear Fuel Cycle and Waste Management. 42 refs, 7 figs, 3 tabs

ADVANCED MULTI-PRODUCT COAL UTILIZATION BY-PRODUCT PROCESSING PLANT

Energy Technology Data Exchange (ETDEWEB)

Robert Jewell; Thomas Robl; John Groppo

2005-03-01

The objective of the project is to build a multi-product ash beneficiation plant at Kentucky Utilities 2,200-MW Ghent Generating Station, located in Carroll County, Kentucky. This part of the study includes the examination of the feedstocks for the beneficiation plant. The ash, as produced by the plant, and that stored in the lower pond were examined. The ash produced by the plant was found to be highly variable as the plant consumes high and low sulfur bituminous coal, in Units 1 and 2 and a mixture of subbituminous and bituminous coal in Units 3 and 4. The ash produced reflected this consisting of an iron-rich ({approx}24%, Fe{sub 2}O{sub 3}), aluminum rich ({approx}29% Al{sub 2}O{sub 3}) and high calcium (6%-7%, CaO) ash, respectively. The LOI of the ash typically was in the range of 5.5% to 6.5%, but individual samples ranged from 1% to almost 9%. The lower pond at Ghent is a substantial body, covering more than 100 acres, with a volume that exceeds 200 million cubic feet. The sedimentation, stratigraphy and resource assessment of the in place ash was investigated with vibracoring and three-dimensional, computer-modeling techniques. Thirteen cores to depths reaching nearly 40 feet, were retrieved, logged in the field and transported to the lab for a series of analyses for particle size, loss on ignition, petrography, x-ray diffraction, and x-ray fluorescence. Collected data were processed using ArcViewGIS, Rockware, and Microsoft Excel to create three-dimensional, layered iso-grade maps, as well as stratigraphic columns and profiles, and reserve estimations. The ash in the pond was projected to exceed 7 million tons and contain over 1.5 million tons of coarse carbon, and 1.8 million tons of fine (<10 {micro}m) glassy pozzolanic material. The size, quality and consistency of the ponded material suggests that it is the better feedstock for the beneficiation plant.

Water and Nitrogen Limitations of Ecosystem Processes Across Three Dryland Plant Communities

Science.gov (United States)

Beltz, C.; Lauenroth, W. K.; Burke, I. C.

2017-12-01

The availability of water and nitrogen (N) play a major role in controlling the distribution of ecosystem types and the rates of ecosystem processes across the globe. Both these resources are being altered by human activity. Anthropogenic fixation of N has increased inputs into the biosphere from 0.5 kg N ha-1 yr-1 to upwards of 10 kg N ha-1 yr-1, while the amount and seasonality of precipitation are expected to continue to change. Within dryland environments, the relationships between increasingly available N and ecosystem processes are especially complex due to dryland's characteristic strong limitation by low and highly variable precipitation. Other experiments have shown that this interplay between N and water can cause temporally complex co-limitation and spatially complex responses with variable effects on ecosystems, such as those to net primary productivity, soil respiration, and plant community composition. Research spanning multiple dryland plant communities is critical for generalizing findings to the 40% of the Earth's terrestrial surface covered in dryland ecosystems. Given IPCC projections in which both N availability and precipitation are altered, examining their interactive effect across multiple plant communities is critical to increasing our understanding of the limitations to ecosystem process in drylands. We are studying a gradient of three plant communities representing a C4 grassland (shortgrass steppe), a C3/C4 grassland (mixed grass prairie), and a shrub-dominated ecosystem with C3 and C4 grasses (sagebrush steppe). We added two levels of N (10 kg N ha-1 and 100 kg N ha-1) and increased summer monthly precipitation by 20%. Sites responded differently to treatments, with the scale of effect varying by treatment. The high-level nitrogen increased soil N availability and soil respiration, while decreasing soil carbon in the labile pool in the upper soil layers. These results will allow for better understanding of increased N in combination with

Demonstration of the potential for energy conservation in two Midwestern pork processing plants. Final report, December 15, 1977-December 31, 1980

Energy Technology Data Exchange (ETDEWEB)

Wilson, P.; Okos, M.

1981-01-19

Two Midwestern pork processing plants were studied to quantify present energy consumption and to determine potential energy savings with modification of existing processing equipment or adoption of alternative equipment. Process energy consumption was measured in each plant at each processing step or at each unit operation and pertinent costs obtained. Energy utilized was categorized by type such as gas, electricity, steam, etc. Process conditions such as temperature, pressure, flow rates, etc., were also measured so that they could be related to energy consumption. Through measurement of operating parameters and the calculation of material and energy balances, patterns of energy loss in the major unit operations were determined. The total yearly steam and gas energy consumed by the processes studied in Plant A amounted to 133.6 billion Btu's and 207.8 billion Btu's in Plant B. Of that total, Plant A uses approximately 15.5% and Plant B uses 7.5% for sanitation and cleaning. The remaining energy is used to operate the various unit operations. The energy used in the major unit operations can be broken down into lost energy and recoverable energy. Lost energy is that energy that will not effect production if eliminated. For the processes studied in Plant A, non-productive energy amounts to 48% of the energy supplied. The nonproductive energy in Plant B amounted to 60.6% of the total process energy. On the other hand, recoverable energy is that energy that was used for some productive purpose but still has value upon completion of the process. For the processes studied in Plant A, a recoverable energy amounts to 40% of the energy supplied. The potentially recoverable energy for Plant B is 35.8% of the process energy supplied.

Management of radioactive liquid waste at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Bendixsen, C.L.

1992-01-01

Highly radioactive liquid wastes (HLLW) are routinely produced during spent nuclear fuel processing at the Idaho Chemical Processing Plant (ICPP), located at the Idaho National Engineering Laboratory (INEL). This paper discusses the processes and safe practices for management of the radioactive process waste streams, which processes include collection, concentration, interim storage, calcination to granular solids, and long-term intermediate storage. Over four million gallons of HLLW have been converted to a recoverable granular solid form through waste liquid injection into a high-temperature, fluidized bed wherein the wastes are converted to their respective solid oxides. The development of a glass ceramic solid for the long-term permanent disposal of the high level waste (HLW) solids is also described

Radionuclide-migration model for buried waste at the Savannah River Plant