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Sample records for cimarron plutonium production plant

  1. Decontamination and decommissioning of the Kerr-McGee Cimarron Plutonium Fuel Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-05-01

    This final report is a summary of the events that completes the decontamination and decommissioning of the Cimarron Corporation`s Mixed Oxides Fuel Plant (formally Sequoyah Fuels Corporation and formerly Kerr-McGee Nuclear Corporation - all three wholly owned subsidiaries of the Kerr-McGee Corporation). Included are details dealing with tooling and procedures for performing the unique tasks of disassembly decontamination and/or disposal. That material which could not be economically decontaminated was volume reduced by disassembly and/or compacted for disposal. The contaminated waste cleaning solutions were processed through filtration and ion exchange for release or solidified with cement for L.S.A. waste disposal. The L.S.A. waste was compacted, and stabilized as required in drums for burial in an approved burial facility. T.R.U. waste packaging and shipping was completed by the end of July 1987. This material was shipped to the Hanford, Washington site for disposal. The personnel protection and monitoring measures and procedures are discussed along with the results of exposure data of operating personnel. The shipping containers for both T.R.U. and L.S.A. waste are described. The results of the decommissioning operations are reported in six reports. The personnel protection and monitoring measures and procedures are contained and discussed along with the results of exposure data of operating personnel in this final report.

  2. Plutonium Finishing Plant

    Data.gov (United States)

    Federal Laboratory Consortium — The Plutonium Finishing Plant, also known as PFP, represented the end of the line (the final procedure) associated with plutonium production at Hanford.PFP was also...

  3. Plutonium Finishing Plant safety evaluation report

    International Nuclear Information System (INIS)

    The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) is DOE's independent review and evaluation of the PFP FSAR and the basis for approval of the PFP FSAR. The evaluation is presented in a format that parallels the format of the PFP FSAR. As an aid to the reactor, a list of acronyms has been included at the beginning of this report. The DOE review concluded that the risks associated with conducting plutonium handling, processing, and storage operations within PFP facilities, as described in the PFP FSAR, are acceptable, since the accident safety analyses associated with these activities meet the WHC risk acceptance guidelines and DOE safety goals in SEN-35-91

  4. Plutonium Finishing Plant safety evaluation report

    Energy Technology Data Exchange (ETDEWEB)

    1995-01-01

    The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) is DOE`s independent review and evaluation of the PFP FSAR and the basis for approval of the PFP FSAR. The evaluation is presented in a format that parallels the format of the PFP FSAR. As an aid to the reactor, a list of acronyms has been included at the beginning of this report. The DOE review concluded that the risks associated with conducting plutonium handling, processing, and storage operations within PFP facilities, as described in the PFP FSAR, are acceptable, since the accident safety analyses associated with these activities meet the WHC risk acceptance guidelines and DOE safety goals in SEN-35-91.

  5. Plutonium Finishing Plant. Interim plutonium stabilization engineering study

    International Nuclear Information System (INIS)

    This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage

  6. Plutonium Finishing Plant. Interim plutonium stabilization engineering study

    Energy Technology Data Exchange (ETDEWEB)

    Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J. [Pacific Northwest Lab., Richland, WA (United States); Nass, R. [Nuclear Fuel Services, Inc. (United States)

    1995-08-01

    This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage.

  7. Design-Only Conceptual Design Report: Plutonium Immobilization Plant

    Energy Technology Data Exchange (ETDEWEB)

    DiSabatino, A.; Loftus, D.

    1999-01-01

    This design-only conceptual design report was prepared to support a funding request by the Department of Energy Office of Fissile Materials Disposition for engineering and design of the Plutonium Immobilization Plant, which will be used to immobilize up to 50 tonnes of surplus plutonium. The siting for the Plutonium Immobilization Plant will be determined pursuant to the site-specific Surplus Plutonium Disposition Environmental Impact Statement in a Plutonium Deposition Record of Decision in early 1999. This document reflects a new facility using the preferred technology (ceramic immobilization using the can-in-canister approach) and the preferred site (at Savannah River). The Plutonium Immobilization Plant accepts plutonium from pit conversion and from non-pit sources and, through a ceramic immobilization process, converts the plutonium into mineral-like forms that are subsequently encapsulated within a large canister of high-level waste glass. The final immobilized product must make the plutonium as inherently unattractive and inaccessible for use in nuclear weapons as the plutonium in spent fuel from commercial reactors and must be suitable for geologic disposal. Plutonium immobilization at the Savannah River Site uses: (1) A new building, the Plutonium Immobilization Plant, which will convert non-pit surplus plutonium to an oxide form suitable for the immobilization process, immobilize plutonium in a titanate-based ceramic form, place cans of the plutonium-ceramic forms into magazines, and load the magazines into a canister; (2) The existing Defense Waste Processing Facility for the pouring of high-level waste glass into the canisters; and (3) The Actinide Packaging and Storage Facility to receive and store feed materials. The Plutonium Immobilization Plant uses existing Savannah River Site infra-structure for analytical laboratory services, waste handling, fire protection, training, and other support utilities and services. The Plutonium Immobilization Plant

  8. Plutonium finishing plant dangerous waste training plan

    International Nuclear Information System (INIS)

    This training plan describes general requirements, worker categories, and provides course descriptions for operation of the Plutonium Finish Plant (PFP) waste generation facilities, permitted treatment, storage and disposal (TSD) units, and the 90-Day Accumulation Areas

  9. Plutonium-238 processing at Savannah River Plant

    Energy Technology Data Exchange (ETDEWEB)

    Burney, G.A.

    1983-01-01

    Plutonium-238 is produced by irradiating NpO/sub 2/-Al cermet slugs or tubes with neutrons. The neptunium-237 is produced as a by-product when natural or enriched uranium is irradiated with neutrons. The neptunium is separated by solvent extraction and ion exchange and precipitated as neptunium oxalate. Neptunium oxalate is calcined to neptunium oxide and fabricated into targets for irradiation. The irradiation conditions are controlled to produce plutonium with 80 to 90 wt % /sup 238/Pu.

  10. Plutonium Finishing Plant (PFP) hazards assessment

    International Nuclear Information System (INIS)

    This report documents the hazards assessment for the Plutonium Finishing Plant (PFP) located on the US Department of Energy (DOE) Hanford Site. This hazards assessment was conducted to provide the emergency planning technical basis for the PFP. DOE Orders require an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification

  11. Accident Analysis for the Plutonium Finishing Plant Polycube Stabilization Process

    International Nuclear Information System (INIS)

    The Polycube Stabilization Project involves low temperature oxidation, without combustion, of polystyrene cubes using the production muffle furnaces in Glovebox HC-21C located in the Remote Mechanical ''C'' (RMC) Line in Room 230A in the 234-52 Facility. Polycubes are polystyrene cubes containing various concentrations of plutonium and uranium oxides. Hundreds of these cubes were manufactured for criticality experiments, and currently exist as unstabilized storage forms at the Plutonium Finishing Plant (PFP). This project is designed to stabilize and prepare the polycube material for stable storage using a process very similar to the earlier processing of sludges in these furnaces. The significant difference is the quantity of hydrogenous material present, and the need to place additional controls on the heating rate of the material. This calculation note documents the analyses of the Representative Accidents identified in Section 2.4.4 of Hazards Analysis for the Plutonium Finishing Plant Polycube Stabilization Process, HNF-7278 (HNF 2000). These two accidents, ''Deflagration in Glovebox HC-21C due to Loss of Power'' and ''Seismic Failure of Glovebox HC-21C'', will be further assessed in this accident analysis

  12. Use of plutonium for power production

    International Nuclear Information System (INIS)

    The panel reviewed available information on various aspects of plutonium utilization, such as physics of plutonium, technology of plutonium fuels in thermal and fast reactors, behaviour of plutonium fuel under reactor irradiation, technological and economic aspects of plutonium fuel cycle. Refs, figs and tabs

  13. History and stabilization of the Plutonium Finishing Plant (PFP) complex, Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, M.S., Fluor Daniel Hanford

    1997-02-18

    The 231-Z Isolation Building or Plutonium Metallurgy Building is located in the Hanford Site`s 200 West Area, approximately 300 yards north of the Plutonium Finishing Plant (PFP) (234-5 Building). When the Hanford Engineer Works (HEW) built it in 1944 to contain the final step for processing plutonium, it was called the Isolation Building. At that time, HEW used a bismuth phosphate radiochemical separations process to make `AT solution,` which was then dried and shipped to Los Alamos, New Mexico. (AT solution is a code name used during World War II for the final HEW product.) The process was carried out first in T Plant and the 224-T Bulk Reduction Building and B Plant and the 224-B Bulk Reduction Building. The 224-T and -B processes produced a concentrated plutonium nitrate stream, which then was sent in 8-gallon batches to the 231-Z Building for final purification. In the 231-Z Building, the plutonium nitrate solution underwent peroxide `strikes` (additions of hydrogen peroxide to further separate the plutonium from its carrier solutions), to form the AT solution. The AT solution was dried and shipped to the Los Alamos Site, where it was made into metallic plutonium and then into weapons hemispheres.` The 231-Z Building began `hot` operations (operations using radioactive materials) with regular runs of plutonium nitrate on January 16, 1945.

  14. Plutonium Finishing Plant (PFP) Final Safety Analysis Report (FSAR) [SEC 1 THRU 11

    Energy Technology Data Exchange (ETDEWEB)

    ULLAH, M K

    2001-02-26

    The Plutonium Finishing Plant (PFP) is located on the US Department of Energy (DOE) Hanford Site in south central Washington State. The DOE Richland Operations (DOE-RL) Project Hanford Management Contract (PHMC) is with Fluor Hanford Inc. (FH). Westinghouse Safety Management Systems (WSMS) provides management support to the PFP facility. Since 1991, the mission of the PFP has changed from plutonium material processing to preparation for decontamination and decommissioning (D and D). The PFP is in transition between its previous mission and the proposed D and D mission. The objective of the transition is to place the facility into a stable state for long-term storage of plutonium materials before final disposition of the facility. Accordingly, this update of the Final Safety Analysis Report (FSAR) reflects the current status of the buildings, equipment, and operations during this transition. The primary product of the PFP was plutonium metal in the form of 2.2-kg, cylindrical ingots called buttoms. Plutonium nitrate was one of several chemical compounds containing plutonium that were produced as an intermediate processing product. Plutonium recovery was performed at the Plutonium Reclamation Facility (PRF) and plutonium conversion (from a nitrate form to a metal form) was performed at the Remote Mechanical C (RMC) Line as the primary processes. Plutonium oxide was also produced at the Remote Mechanical A (RMA) Line. Plutonium processed at the PFP contained both weapons-grade and fuels-grade plutonium materials. The capability existed to process both weapons-grade and fuels-grade material through the PRF and only weapons-grade material through the RMC Line although fuels-grade material was processed through the line before 1984. Amounts of these materials exist in storage throughout the facility in various residual forms left from previous years of operations.

  15. One year of operation of the Belgonucleaire (Dessel) plutonium fuel fabrication plant

    International Nuclear Information System (INIS)

    Based on experience with plutonium since 1958, Belgonucleaire has successively launched a pilot plant and then a fuel fabrication plant for mixed uranium and plutonium oxides in 1968 and 1973 respectively. After describing briefly the plants and the most important stages in the planning, construction and operation of the Dessel plant, the present document describes the principal problems which were met during the course of operation of the plant and their direct incidence on the capacity and quality of the production of fuel elements

  16. Search for plutonium salt deposits in the plutonium extraction batteries of the Marcoule plant (1963)

    International Nuclear Information System (INIS)

    This report describes a method and a special apparatus making it possible to detach the insoluble plutonium salt deposits in the extraction chain of an irradiated fuel treatment plant. The process chosen allows the detection, in the extraction batteries or in the highly active chemical engineering equipment, of plutonium quantities of a few grains. After four years operation it has been impossible to detect measurable quantities of plutonium in any part of the extraction chain. The results have been confirmed by visual examinations carried out with a specially constructed endoscope. (authors)

  17. Plutonium

    Science.gov (United States)

    Clark, David L.; Hecker, Siegfried S.; Jarvinen, Gordon D.; Neu, Mary P.

    The element plutonium occupies a unique place in the history of chemistry, physics, technology, and international relations. After the initial discovery based on submicrogram amounts, it is now generated by transmutation of uranium in nuclear reactors on a large scale, and has been separated in ton quantities in large industrial facilities. The intense interest in plutonium resulted fromthe dual-use scenario of domestic power production and nuclear weapons - drawing energy from an atomic nucleus that can produce a factor of millions in energy output relative to chemical energy sources. Indeed, within 5 years of its original synthesis, the primary use of plutonium was for the release of nuclear energy in weapons of unprecedented power, and it seemed that the new element might lead the human race to the brink of self-annihilation. Instead, it has forced the human race to govern itself without resorting to nuclear war over the past 60 years. Plutonium evokes the entire gamut of human emotions, from good to evil, from hope to despair, from the salvation of humanity to its utter destruction. There is no other element in the periodic table that has had such a profound impact on the consciousness of mankind.

  18. Plutonium Finishing Plant (PFP) Dangerous Waste Training Plan

    International Nuclear Information System (INIS)

    This training plan describes general requirements, worker categories, and provides course descriptions for operation of the plutonium finishing plant (PFP) waste generation facilities, permitted treatment, storage and disposal (TSD) units, and the 90-Day Accumulation Areas

  19. Plutonium finishing plant dangerous waste training plan; TOPICAL

    International Nuclear Information System (INIS)

    This training plan describes general requirements, worker categories, and provides course descriptions for operation of the Plutonium Finish Plant (PFP) waste generation facilities, permitted treatment, storage and disposal (TSD) units, and the 90-Day Accumulation Areas

  20. Plutonium Finishing Plant (PFP) Dangerous Waste Training Plan

    Energy Technology Data Exchange (ETDEWEB)

    ENTROP, G.E.

    1999-12-03

    This training plan describes general requirements, worker categories, and provides course descriptions for operation of the plutonium finishing plant (PFP) waste generation facilities, permitted treatment, storage and disposal (TSD) units, and the 90-Day Accumulation Areas.

  1. Processing of Non-PFP Plutonium Oxide in Hanford Plants

    International Nuclear Information System (INIS)

    Processing of non-irradiated plutonium oxide, PuO2, at the Hanford Site has been done at the Plutonium Finishing Plant (PFP) and in recycle of PuO2-bearing fuels through Hanford reprocessing plants. Plutonium oxide is notoriously refractory and difficult to dissolve. As such, losses of PuO2 residues from the PFP or from Hanford reprocessing plants can report to Hanford Site underground tank waste storage. Those stored wastes are destined to become feed to the Waste Treatment Plant, WTP. Information on the processing of non-PFP plutonium oxide in Hanford plants is provided in this brief report. To help gain perspective, information on PFP processing and plutonium additions to the tank farm system from other Hanford processing is also presented. Processing of non-irradiated plutonium oxide, PuO2, scrap for recovery of plutonium values occurred routinely at Hanford's Plutonium Finishing Plant (PFP) in glovebox line operations. Plutonium oxide is difficult to dissolve, particularly if it has been high-fired; i.e., calcined to temperatures above about 400 C and much of it was. Dissolution of the PuO2 in the scrap typically was performed in PFP's Miscellaneous Treatment line using nitric acid (HNO3) containing some source of fluoride ion, F-, such as hydrofluoric acid (HF), sodium fluoride (NaF), or calcium fluoride (CaF2). The HNO3 concentration generally was 6 M or higher whereas the fluoride concentration was ∼0.5 M or lower. At higher fluoride concentrations, plutonium fluoride (PuF4) would precipitate, thus limiting the plutonium dissolution. Some plutonium-bearing scrap also contained PuF4 and thus required no added fluoride. Once the plutonium scrap was dissolved, the excess fluoride was complexed with aluminum ion, Al3+, added as aluminum nitrate, Al(NO3)3·9H2O, to limit collateral damage to the process equipment by the corrosive fluoride. Aluminum nitrate also was added in low quantities in processing PuF4. The PuO2 dissolution was not perfect, however, and

  2. Plutonium dissolution from Rocky Flats Plant incinerator ash

    International Nuclear Information System (INIS)

    Rockwell Hanford Operations (Rockwell) soon will commence recovery of plutonium from Rocky Flats Plant incinerator ash. In preparation for this processing, Rockwell undertook literature and laboratory studies to identify, select and optimize plutonium dissolution methods for treating the ash. Ash reburning, followed by dissolution in nitric acid containing calcium fluoride, was selected as the processing method for the ash. Recommended values of process parameters were identified. Using the selected process, 99.5% plutonium recovery was achieved, leaving about 12.7 wt % heel residue for an equal weight composite of the three ashes tested. 15 refs., 26 figs

  3. Plutonium: The first 50 years. United States plutonium production, acquisition, and utilization from 1944 through 1994

    Energy Technology Data Exchange (ETDEWEB)

    None

    1996-02-01

    The report contains important newly declassified information regarding the US production, acquisition, and removals of plutonium. This new information, when combined with previously declassified data, has allowed the DOE to issue, for the first time, a truly comprehensive report on the total DOE plutonium inventory. At the December 7, 1993, Openness Press Conference, the DOE declassified the plutonium inventories at eight locations totaling 33.5 metric tons (MT). This report declassifies the remainder of the DOE plutonium inventory. Newly declassified in this report is the quantity of plutonium at the Pantex Site, near Amarillo, Texas, and in the US nuclear weapons stockpile of 66.1 MT, which, when added to the previously released inventory of 33.5 MT, yields a total plutonium inventory of 99.5 MT. This report will document the sources which built up the plutonium inventory as well as the transactions which have removed plutonium from that inventory. This report identifies four sources that add plutonium to the DOE/DoD inventory, and seven types of transactions which remove plutonium from the DOE/DoD inventory. This report also discusses the nuclear material control and accountability system which records all nuclear material transactions, compares records with inventory and calculates material balances, and analyzes differences to verify that nuclear materials are in quantities as reported. The DOE believes that this report will aid in discussions in plutonium storage, safety, and security with stakeholders as well as encourage other nations to declassify and release similar data. These data will also be available for formulating policies with respect to disposition of excess nuclear materials. The information in this report is based on the evaluation of available records. The information contained in this report may be updated or revised in the future should additional or more detailed data become available.

  4. Determination of Trace Plutonium in Uranium Product by ID-ICP-MS

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    Plutonium is strictly limited in the uranium product of spent fuel reprocessing. The analysis of plutonium in uranium product is the key point of product quality control. Plutonium concentration is limited below

  5. Gamma ray NDA assay system for total plutonium and isotopics in plutonium product solutions

    International Nuclear Information System (INIS)

    A LASL-designed gamma-ray NDA instrument for assay of total plutonium and isotopics of product solutions at Tokai-Mura is currently installed and operating. The instrument is, optimally, a densitometer that uses radioisotopic sources for total plutonium measurements at the K absorption edge. The measured transmissions of additional gamma-ray lines from the same radioisotopic sources are used to correct for self-attenuation of passive gamma rays from plutonium. The corrected passive data give the plutonium isotopic content of freshly separated to moderately aged solutions. This off-line instrument is fully automated under computer control, with the exception of sample positioning, and operates routinely in a mode designed for measurement control. A one-half percent precision in total plutonium concentration is achieved with a 15-minute measurement

  6. Improving Efficiency with 3-D Imaging: Technology Essential in Removing Plutonium Processing Equipment from Plutonium Finishing Plant Gloveboxes

    International Nuclear Information System (INIS)

    The Plutonium Finishing Plant at Hanford, Washington began operations in 1949 to process plutonium and plutonium products. Its primary mission was to produce plutonium metal, fabricate weapons parts, and stabilize reactive materials. These operations, and subsequent activities, were performed in remote production lines, consisting primarily of hundreds of gloveboxes. Over the years these gloveboxes and processes have been continuously modified. The plant is currently inactive and Fluor Hanford has been tasked to clean out contaminated equipment and gloveboxes from the facility so it can be demolished in the near future. Approximately 100 gloveboxes at PFP have been cleaned out in the past four years and about 90 gloveboxes remain to be cleaned out. Because specific commitment dates for this work have been established with the State of Washington and other entities, it is important to adopt work practices that increase the safety and speed of this effort. The most recent work practice to be adopted by Fluor Hanford D and D workers is the use of 3-D models to improve the efficiency of cleaning out radioactive gloveboxes at the plant. The use of 3-D models has significantly improved the work planning process by providing workers with a clear image of glovebox construction and composition, which is then used to determine cleanout methods and work sequences. The 3-D visual products enhance safety by enabling workers to more easily identify hazards and implement controls. In addition, the ability to identify and target the removal of radiological materials early in the D and D process provides substantial dose reduction for the workers

  7. Plutonium-enriched thermal fuel production experience in Belgium

    International Nuclear Information System (INIS)

    Taking into account the strategic aspects of nuclear energy such as availability and sufficiency of resources and independence of energy supply, most countries planning to use plutonium look mainly to its use in fast reactors. However, by recycling the recovered uranium and plutonium in light water reactors, the saving of the uranium that would otherwise be required could already be higher than 35%. Therefore, until fast reactors are introduced, for macro- or microeconomic reasons, the plutonium recycle option seems to be quite valuable for countries having the plutonium technology. In Belgium, Belgonucleaire has been developing the plutonium technology for more than 20 yr and has operated a mixed oxide fuel fabrication plant since 1973. The past ten years of plant operation have provided for many improvements and relevant new documented experiences establishing a basis for new modifications that will be beneficial to the intrinsic quality, overall safety, and economy of the fuel

  8. Plutonium determination by spectrophotometry of plutonium (VI): control of the nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    The plutonium (VI) spectrophotometric determination, after AgO oxidation in 3 M nitric acid medium, is used for the running-control of the nuclear fuel reprocessing plant at La Hague. Analytical device used in glove-box or shielded-cell is briefly described. This method is fast, sensitive, unfailing and gives simple effluents. It is applied by day and night shifts, during Light Water Reactor fuel reprocessing campaign, for 0.5 mg/l up to 20 g/l plutonium solutions. Reference solution measurements have a 0.8 to 1.4 % relative standard deviation; duplicate plutonium determinations give a 0.3% relative standard deviation for sample analysis. There is a discrepancy (- 0.3% to - 0.9%) between the spectrophotometric method results and the isotopic dilution analysis

  9. USING 3-D MODELING TO IMPROVE THE EFFICIENCY FOR REMOVING PLUTONIUM PROCESSING EQUIMENT FROM GLOVEBOXES AT THE PLUTONIUM FINISHANG PLANT

    Energy Technology Data Exchange (ETDEWEB)

    CROW SH; KYLE RN; MINETTE MJ

    2008-07-15

    The Plutonium Finishing Plant at the Department of Energy's Hanford Site in southeastern Washington State began operations in 1949 to process plutonium and plutonium products. Its primary mission was to produce plutonium metal, fabricate weapons parts, and stabilize reactive materials. These operations, and subsequent activities, were performed in production lines, consisting primarily of hundreds of gloveboxes. Over the years, these gloveboxes and attendant processes have been continuously modified. The plant is currently inactive and Fluor Hanford has been tasked with cleaning out contaminated equipment and gloveboxes from the facility so it can be demolished in the near future. Approximately 100 gloveboxes at PFP have been cleaned out in the past four years and about 90 gloveboxes remain to be cleaned out. Because specific commitment dates for this work have been established with the State of Washington and other entities, it is important to adopt work practices that increase the safety and speed of this effort. The most recent work practice to be adopted by Fluor Hanford D and D workers is the use of 3-D models to make the process of cleaning out the radioactive gloveboxes more efficient. The use of 3-D models has significantly improved the work-planning process by giving workers a clear image of glovebox construction and composition, which in turn is used to determine cleanout methods and work sequences. The 3-D visual products also enhance safety by enabling workers to more easily identify hazards and implement controls. Further, the ability to identify and target the removal of radiological material early in the D and D process provides substantial dose reduction for the workers.

  10. USING 3-D MODELING TO IMPROVE THE EFFICIENCY FOR REMOVING PLUTONIUM PROCESSING EQUIMENT FROM GLOVEBOXES AT THE PLUTONIUM FINISHING PLANT

    International Nuclear Information System (INIS)

    The Plutonium Finishing Plant at the Department of Energy's Hanford Site in southeastern Washington State began operations in 1949 to process plutonium and plutonium products. Its primary mission was to produce plutonium metal, fabricate weapons parts, and stabilize reactive materials. These operations, and subsequent activities, were performed in production lines, consisting primarily of hundreds of gloveboxes. Over the years, these gloveboxes and attendant processes have been continuously modified. The plant is currently inactive and Fluor Hanford has been tasked with cleaning out contaminated equipment and gloveboxes from the facility so it can be demolished in the near future. Approximately 100 gloveboxes at PFP have been cleaned out in the past four years and about 90 gloveboxes remain to be cleaned out. Because specific commitment dates for this work have been established with the State of Washington and other entities, it is important to adopt work practices that increase the safety and speed of this effort. The most recent work practice to be adopted by Fluor Hanford D and D workers is the use of 3-D models to make the process of cleaning out the radioactive gloveboxes more efficient. The use of 3-D models has significantly improved the work-planning process by giving workers a clear image of glovebox construction and composition, which in turn is used to determine cleanout methods and work sequences. The 3-D visual products also enhance safety by enabling workers to more easily identify hazards and implement controls. Further, the ability to identify and target the removal of radiological material early in the D and D process provides substantial dose reduction for the workers

  11. 10 CFR Appendix J to Part 110 - Illustrative List of Uranium Conversion Plant Equipment and Plutonium Conversion Plant Equipment...

    Science.gov (United States)

    2010-01-01

    ... and Plutonium Conversion Plant Equipment Under NRC Export Licensing Authority J Appendix J to Part 110... Plutonium Conversion Plant Equipment Under NRC Export Licensing Authority Note—Uranium conversion plants and... feed for electromagnetic enrichment. Note: Plutonium conversion plants and systems may perform one...

  12. Thermal Stability Studies of Candidate Decontamination Agents for Hanford’s Plutonium Finishing Plant Plutonium-Contaminated Gloveboxes

    Energy Technology Data Exchange (ETDEWEB)

    Scheele, Randall D.; Cooper, Thurman D.; Jones, Susan A.; Ewalt, John R.; Compton, James A.; Trent, Donald S.; Edwards, Matthew K.; Kozelisky, Anne E.; Scott, Paul A.; Minette, Michael J.

    2005-09-29

    This report provides the results of PNNL's and Fluor's studies of the thermal stabilities of potential wastes arising from decontamination of Hanford's Plutonium Finishing Plant's plutonium contaminated gloveboxes. The candidate wastes arising from the decontamination technologies ceric nitrate/nitric acid, RadPro, Glygel, and Aspigel.

  13. Preliminary Materials Transport Plan for the Plutonium Immobilization Plant

    Energy Technology Data Exchange (ETDEWEB)

    Gilkison, J.M.; Dyches, G.M.; Randall, W.J.; Steed, J.H.

    2000-01-26

    This Materials Transport Plan defines the methodology for moving process and non-process materials within the Plutonium Immobilization Plant (PIP) operations. The scope of the plan includes the movement of materials between plant operational units (gloveboxes or operational areas/rooms within the plant). The movements of materials within the various plant operational units are described in the System Design Description prepared for the individual units. The plan provides a design concept for transporting each type of material including the containerization used during the movements. Further, the plan identifies the high-level functions and requirements for movements of the materials.

  14. Nuclear materials: Alternatives for relocating Rocky Flats Plant's plutonium operations

    International Nuclear Information System (INIS)

    Major operational problems in a plutonium-processing building at the Department of Energy's Rocky Flats Plant near Denver, Colorado, have existed since the building became operational in 1981. High estimated costs have been associated with repairing the building and potential risks have been associated with the plant's proximity to a major metropolitan center. Four alternatives have been identified for relocating plutonium processing that would cost between about $200 million and $600 million. These alternatives would require between 4 and 10 years to implement, including design, construction and/or alterations and startup. This is in comparison to an estimated cost of about $300 million to repair building 371 at the Rocky Flats Plant and an implementation period of 8 years. The alternative that addresses fabrication operations, the major contributor to safety and health risks at Rocky Flats is to relocate all Rocky Flats plutonium operations. This would cost over $4 billion and take as long as 24 years. On a cost basis alone, this alternative does not appear justified

  15. Plutonium in a grassland ecosystem. [Rocky Flats Plant

    Energy Technology Data Exchange (ETDEWEB)

    Little, C.A.

    1976-08-01

    A study was made of plutonium contamination of grassland at the Rocky Flats plant northwest of Denver, Colorado. Of interest were: the definition of major plutonium-containing ecosystem compartments; the relative amounts in those compartments; how those values related to studies done in other geographical areas; whether or not the predominant isotopes, /sup 238/Pu and /sup 239/Pu, behaved differently; and what mechanisms might have allowed for the observed patterns of contamination. Samples of soil, litter, vegetation, arthropods, and small mammals were collected for Pu analysis and mass determination from each of two macroplots. Small aliquots (5 g or less) were analyzed by a rapid liquid scintillation technique and by alpha spectrometry. Of the compartments sampled, greater than 99 percent of the total plutonium was contained in the soil and the concentrations were significantly inversely correlated with distance from the contamination source, depth of the sample, and particle size of the sieved soil samples. The soil data suggested that the distribution of contamination largely resulted from physical transport processes.

  16. THE DEACTIVATION DECONTAMINATION & DECOMMISSIONING OF THE PLUTONIUM FINISHING PLANT (PFP) A FORMER PLUTONIUM PROCESSING FACILITY AT DOE HANFORD SITE

    Energy Technology Data Exchange (ETDEWEB)

    CHARBONEAU, S.L.

    2006-02-01

    The Plutonium Finishing Plant (PFP) was constructed as part of the Manhattan Project during World War II. The Manhattan Project was developed to usher in the use of nuclear weapons to end the war. The primary mission of the PFP was to provide plutonium used as special nuclear material (SNM) for fabrication of nuclear devices for the war effort. Subsequent to the end of World War II, the PFP's mission expanded to support the Cold War effort through plutonium production during the nuclear arms race and later the processing of fuel grade mixed plutonium-uranium oxide to support DOE's breeder reactor program. In October 1990, at the close of the production mission for PFP, a shutdown order was prepared by the Department of Energy (DOE) in Washington, DC and issued to the Richland DOE field office. Subsequent to the shutdown order, a team from the Defense Nuclear Facilities Safety Board (DNFSB) analyzed the hazards at PFP associated with the continued storage of certain forms of plutonium solutions and solids. The assessment identified many discrete actions that were required to stabilize the different plutonium forms into stable form and repackage the material in high integrity containers. These actions were technically complicated and completed as part of the PFP nuclear material stabilization project between 1995 and early 2005. The completion of the stabilization project was a necessary first step in deactivating PFP. During stabilization, DOE entered into negotiations with the U.S. Environmental Protection Agency (EPA) and the State of Washington and established milestones for the Deactivation and Decommissioning (D&D) of the PFP. The DOE and its contractor, Fluor Hanford (Fluor), have made great progress in deactivating, decontaminating and decommissioning the PFP at the Hanford Site as detailed in this paper. Background information covering the PFP D&D effort includes descriptions of negotiations with the State of Washington concerning consent

  17. THE DEACTIVATION, DECONTAMINATION AND DECOMMISSIONING OF THE PLUTONIUM FINISHING PLANT, A FORMER PLUTONIUM PROCESSING FACILITY AT DOE'S HANFORD SITE

    International Nuclear Information System (INIS)

    The Plutonium Finishing Plant (PFP) was constructed as part of the Manhattan Project during World War II. The Manhattan Project was developed to usher in the use of nuclear weapons to end the war. The primary mission of the PFP was to provide plutonium used as special nuclear material (SNM) for fabrication of nuclear devices for the war effort. Subsequent to the end of World War II, the PFP's mission expanded to support the Cold War effort through plutonium production during the nuclear arms race and later the processing of fuel grade mixed plutonium-uranium oxide to support DOE's breeder reactor program. In October 1990, at the close of the production mission for PFP, a shutdown order was prepared by the Department of Energy (DOE) in Washington,; DC--and issued to the Richland DOE field office. Subsequent to the shutdown order, a team from the Defense Nuclear Facilities Safety Board (DNFSB) analyzed the hazards at PFP associated with the continued storage of certain forms of plutonium solutions and solids. The assessment identified many discrete actions that were required to stabilize the different plutonium forms into stable form and repackage the material in high integrity containers. These actions were technically complicated and completed as part of the PFP nuclear material stabilization project between 1995 and early 2005. The completion of the stabilization project was a necessary first step in deactivating PFP. During stabilization, DOE entered into negotiations with the U.S. Environmental Protection Agency (EPA) and the State of Washington and established milestones for the Deactivation and Decommissioning (DandD) of the PFP. The DOE and its contractor, Fluor Hanford (Fluor), have made great progress in deactivating, decontaminating and decommissioning the PFP at the Hanford Site as detailed in this paper. Background information covering the PFP DandD effort includes descriptions of negotiations with the State of Washington concerning consent

  18. Application of Prompt Gamma-Ray Analysis to Identify Electrorefining Salt-Bearing Plutonium Oxide at the Plutonium Finishing Plant

    International Nuclear Information System (INIS)

    Prompt gamma-ray analysis is being implemented at the Plutonium Finishing Plant (PFP) to screen impure plutonium oxide inventory items, received in the mid-1980s from the Rocky Flats Plant, for the presence of sodium chloride and potassium chloride salts from the electrorefining process. A large fraction of these items are suspected to contain electrorefining salts. Because the salts evaporate at the=950C stabilization temperature mandated for long-term storage under the U.S. Department of Energy plutonium oxide stabilization and storage criteria to plug and corrode process equipment, items found to have these salts qualify for thermal stabilization at 750C. The prompt gamma ray energies characteristic of sodium, potassium, chlorine, and other low atomic weight elements arise from the interaction the light elements with alpha radiation from plutonium and americium radioactive decay. High-resolution gamma ray spectrometers designed to detect energies up to ∼4.5 MeV are used to gather the high-energy prompt gamma spectra.Observation of the presence of the high-energy gamma peaks representing the natural chlorine-35, sodium-23, and potassium-39 isotopes and the sodium-to-chlorine peak area ratios in the range for plutonium oxide materials known to contain the electrorefining salts give the evidence needed to identify plutonium oxide materials at the PFP that qualify for the lower-temperature processing. Conversely, the absence of these telltale signals in the prompt gamma analysis provides evidence that the materials do not contain the electrorefining salts. Furthermore, based on calibrations using known assayed items, semiquantitative measurement of the quantity of chlorine present in materials containing electrorefining salt also can be performed by using the count rates observed for the chlorine peak, the plutonium quantity present in the measured item, and the plutonium- and chlorine-specific response of the gamma detection system. The origin and characteristics

  19. ORNL review of TRUEX flowsheet proposed for deployment at the Rockwell Hanford Plutonium Finishing Plant

    International Nuclear Information System (INIS)

    The Transuranium Extraction (TRUEX) process will be installed at the Rockwell Hanford Operations (RHO) Plutonium Finishing Plant (PFP). The purposes are to process the PFP waste to recover the plutonium, to isolate the americium, and to have the remaining waste converted to a non-TRU waste. Rockwell requested that ORNL provide an outside review of the process and its implementation. This review addresses the generation of the TRUEX feed, the chemical flowsheet, and the products and raffinates. It suggests that present PFP operations be modified to reduce the amount of transuranium elements that will be in the TRUEX process feed. This review also includes an assessment of the TRUEX solvent extraction flowsheet on the bases of material balance, adequate extraction and stripping stages, and solvent cleanup. The final part of the review includes results of three-party discussions [RHO, ORNL, and Argonne National Laboratory (ANL)] of some major issues

  20. Plutonium immobilization plant using ceramic in existing facilities at the Savannah River site

    Energy Technology Data Exchange (ETDEWEB)

    DiSabatino, A., LLNL

    1998-06-01

    The Plutonium Immobilization Plant (PIP) accepts plutonium (Pu) from pit conversion and from non-pit sources, and through a ceramic immobilization process converts the plutonium into an immobilized form that can be disposed of in a high level waste (HLW) repository. This immobilization process is shown conceptually in Figure 1-1. The objective is to make an immobilized form, suitable for geologic disposal, in which the plutonium is as inherently unattractive and inaccessible as the plutonium in spent fuel from commercial reactors. The ceramic immobilization alternative presented in this report consists of first converting the surplus material to an oxide, followed by incorporating the plutonium oxide into a titanate-based ceramic material that is placed in metal cans.

  1. Plutonium immobilization plant using ceramic in existing facilities at the Savannah River site

    International Nuclear Information System (INIS)

    The Plutonium Immobilization Plant (PIP) accepts plutonium (Pu) from pit conversion and from non-pit sources, and through a ceramic immobilization process converts the plutonium into an immobilized form that can be disposed of in a high level waste (HLW) repository. This immobilization process is shown conceptually in Figure 1-1. The objective is to make an immobilized form, suitable for geologic disposal, in which the plutonium is as inherently unattractive and inaccessible as the plutonium in spent fuel from commercial reactors. The ceramic immobilization alternative presented in this report consists of first converting the surplus material to an oxide, followed by incorporating the plutonium oxide into a titanate-based ceramic material that is placed in metal cans

  2. Experience gained with the Synroc demonstration plant at ANSTO and its relevance to plutonium immobilization

    Energy Technology Data Exchange (ETDEWEB)

    Jostsons, A.; Ridal, A.; Mercer, D.J.; Vance, E.R.L. [Australian Nuclear Science and Technology Organisation, Menai (Australia)

    1996-05-01

    The Synroc Demonstration Plant (SDP) was designed and constructed at Lucas Heights to demonstrate the feasibility of Synroc production on a commercial scale (10 kg/hr) with simulated Purex liquid HLW. Since commissioning of the SDP in 1987, over 6000 kg of Synroc has been fabricated with a range of feeds and waste loadings. The SDP utilises uniaxial hot-pressing to consolidate Synroc. Pressureless sintering and hot-isostatic pressing have also been studied at smaller scales. The results of this extensive process development have been incorporated in a conceptual design for a radioactive plant to condition HLW from a reprocessing plant with a capacity to treat 800 tpa of spent LWR fuel. Synroic containing TRU, including Pu, and fission products has been fabricated and characterised in a glove-box facility and hot cells, respectively. The extensive experience in processing of Synroc over the past 15 years is summarised and its relevance to immobilization of surplus plutonium is discussed.

  3. The dissolution vessel for plutonium pits at the U.S. DOE Pantex Plant.

    Science.gov (United States)

    Eifert, E J; Vickers, L D

    2000-02-01

    The U.S. DOE Pantex Plant has been given the mission to recertify and requalify plutonium pits for reuse in existing War Reserve nuclear weapons. The first process common to both recertification and requalification is cleaning the plutonium pit. The pit will be cleaned in a dissolution vessel using N-methyl pyrrolidone (NMP) solvent. The recertification and requalification programs are both in the design concept phase at Pantex Plant The U.S. DOE Pantex Plant secures the national security of the United States by using safe vessels for cleaning plutonium pits in a manner that protects the health and safety of employees, the public and the environment. PMID:10651401

  4. Chemical and Radiochemical Composition of Thermally Stabilized Plutonium Oxide from the Plutonium Finishing Plant Considered as Alternate Feedstock for the Mixed Oxide Fuel Fabrication Facility

    Energy Technology Data Exchange (ETDEWEB)

    Tingey, Joel M.; Jones, Susan A.

    2005-07-01

    Eighteen plutonium oxide samples originating from the Plutonium Finishing Plant (PFP) on the Hanford Site were analyzed to provide additional data on the suitability of PFP thermally stabilized plutonium oxides and Rocky Flats oxides as alternate feedstock to the Mixed Oxide Fuel Fabrication Facility (MFFF). Radiochemical and chemical analyses were performed on fusions, acid leaches, and water leaches of these 18 samples. The results from these destructive analyses were compared with nondestructive analyses (NDA) performed at PFP and the acceptance criteria for the alternate feedstock. The plutonium oxide materials considered as alternate feedstock at Hanford originated from several different sources including Rocky Flats oxide, scrap from the Remote Mechanical C-Line (RMC) and the Plutonium Reclamation Facility (PRF), and materials from other plutonium conversion processes at Hanford. These materials were received at PFP as metals, oxides, and solutions. All of the material considered as alternate feedstock was converted to PuO2 and thermally stabilized by heating the PuO2 powder at 950 C in an oxidizing environment. The two samples from solutions were converted to PuO2 by precipitation with Mg(OH)2. The 18 plutonium oxide samples were grouped into four categories based on their origin. The Rocky Flats oxide was divided into two categories, low- and high-chloride Rocky Flats oxides. The other two categories were PRF/RMC scrap oxides, which included scrap from both process lines and oxides produced from solutions. The two solution samples came from samples that were being tested at Pacific Northwest National Laboratory because all of the plutonium oxide from solutions at PFP had already been processed and placed in 3013 containers. These samples originated at the PFP and are from plutonium nitrate product and double-pass filtrate solutions after they had been thermally stabilized. The other 16 samples originated from thermal stabilization batches before canning at

  5. Maintenance implementation plan for the Plutonium Finishing Plant. Revision 3

    International Nuclear Information System (INIS)

    This document outlines the Maintenance Implementation Plan (MIP) for the Plutonium Finishing Plant (PFP) located at the Hanford site at Richland, Washington. This MIP describes the PFP maintenance program relative to DOE order 4330.4B. The MIP defines the key actions needed to meet the guidelines of the Order to produce a cost-effective and efficient maintenance program. A previous report identified the presence of significant quantities of Pu-bearing materials within PFP that pose risks to workers. PFP's current mission is to develop, install and operate processes which will mitigate these risks. The PFP Maintenance strategy is to equip the facility with systems and equipment able to sustain scheduled PFP operations. The current operating run is scheduled to last seven years. Activities following the stabilization operation will involve an Environmental Impact Statement (EIS) to determine future plant activities. This strategy includes long-term maintenance of the facility for safe occupancy and material storage. The PFP maintenance staff used the graded approach to dictate the priorities of the improvement and upgrade actions identified in Chapter 2 of this document. The MIP documents PFP compliance to the DOE 4330.4B Order. Chapter 2 of the MIP follows the format of the Order in addressing the eighteen elements. As this revision is a total rewrite, no sidebars are included to highlight changes

  6. Experience and activities in the field of plutonium recycling in civilian nuclear power plants in the European Union

    International Nuclear Information System (INIS)

    The European Union industry has established a world-wide leadership position in manufacturing and exploiting plutonium bearing fuel (MOX). About 15 to 20 tons of plutonium have been manufactured in the MOX fuel fabrication plants of E.U. companies. The current capacity of about 60 tons of MOX fuel per year is being upgraded to reach 400 tons/year by the year 2000. As a result, the excess amounts of separated plutonium, presently stored in the European Union, should no longer raise but should steadily decrease to converge to zero. Studies by the European Commission have indicated that the best use at present of weapons-grade and reactor-grade plutonium is to burn it in operating and future planned nuclear reactors. Disposing of plutonium by blending it with fission products or immobilising it into synthetic matrices appears to be far from being an industrially viable option. Following this path would mean to continue storing the excess plutonium of both military and civilian origin for an unknown, but very long period of time. For these and other reasons, the European Commission is striving to foster international cooperation between the European Union companies, having a long industrial experience accumulated in the field of recycling plutonium, and, so far, the Russian Federation and the Newly Independent States. This cooperation is aiming at supporting projects that could be mutually beneficial to all parties involved. To meet this objective, several programmes have been established either bilaterally or multilaterally, in particular within the framework of the International Science and Technology Centre (I.S.T.C.) in Moscow. Some examples of such collaborations will be described. (author)

  7. Sludge stabilization at the Plutonium Finishing Plant, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    This Environmental Assessment evaluates the proposed action to operate two laboratory-size muffle furnaces in glovebox HC-21C, located in the Plutonium Finishing Plant (PFP), Hanford Site, Richland, Washington. The muffle furnaces would be used to stabilize chemically reactive sludges that contain approximately 25 kilograms (55 pounds) of plutonium by heating to approximately 500 to 1000 degrees C (900 to 1800 degrees F). The resulting stable powder, mostly plutonium oxide with impurities, would be stored in the PFP vaults. The presence of chemically reactive plutonium-bearing sludges in the process gloveboxes poses a risk to workers from radiation exposure and limits the availability of storage space for future plant cleanup. Therefore, there is a need to stabilize the material into a form suitable for long-term storage. This proposed action would be an interim action, which would take place prior to completion of an Environmental Impact Statement for the PFP which would evaluate stabilization of all plutonium-bearing materials and cleanout of the facility. However, only 10 percent of the total quantity of plutonium in reactive materials is in the sludges, so this action will not limit the choice of reasonable alternatives or prejudice the Record of Decision of the Plutonium Finishing Plant Environmental Impact Statement

  8. Disposition of plutonium-239 via production of fission molybdenum-99.

    Science.gov (United States)

    Mushtaq, A

    2011-04-01

    A heritage of physical consequences of the U.S.-Soviet arms race has accumulated, the weapons-grade plutonium (WPu), which will become excess as a result of the dismantlement of the nuclear weapons under the arms reduction agreements. Disposition of Pu has been proposed by mixing WPu with high-level radioactive waste with subsequent vitrification into large, highly radioactive glass logs or fabrication into mixed oxide fuel with subsequent irradiation in existing light water reactors. A potential option may be the production of medical isotope molybdenum-99 by using Pu-239 targets.

  9. Fire hazard analysis for Plutonium Finishing Plant complex

    International Nuclear Information System (INIS)

    A fire hazards analysis (FHA) was performed for the Plutonium Finishing Plant (PFP) Complex at the Department of Energy (DOE) Hanford site. The scope of the FHA focuses on the nuclear facilities/structures in the Complex. The analysis was conducted in accordance with RLID 5480.7, [DOE Directive RLID 5480.7, 1/17/94] and DOE Order 5480.7A, ''Fire Protection'' [DOE Order 5480.7A, 2/17/93] and addresses each of the sixteen principle elements outlined in paragraph 9.a(3) of the Order. The elements are addressed in terms of the fire protection objectives stated in paragraph 4 of DOE 5480.7A. In addition, the FHA also complies with WHC-CM-4-41, Fire Protection Program Manual, Section 3.4 [1994] and WHC-SD-GN-FHA-30001, Rev. 0 [WHC, 1994]. Objectives of the FHA are to determine: (1) the fire hazards that expose the PFP facilities, or that are inherent in the building operations, (2) the adequacy of the fire safety features currently located in the PFP Complex, and (3) the degree of compliance of the facility with specific fire safety provisions in DOE orders, related engineering codes, and standards

  10. Fire hazard analysis for Plutonium Finishing Plant complex

    Energy Technology Data Exchange (ETDEWEB)

    MCKINNIS, D.L.

    1999-02-23

    A fire hazards analysis (FHA) was performed for the Plutonium Finishing Plant (PFP) Complex at the Department of Energy (DOE) Hanford site. The scope of the FHA focuses on the nuclear facilities/structures in the Complex. The analysis was conducted in accordance with RLID 5480.7, [DOE Directive RLID 5480.7, 1/17/94] and DOE Order 5480.7A, ''Fire Protection'' [DOE Order 5480.7A, 2/17/93] and addresses each of the sixteen principle elements outlined in paragraph 9.a(3) of the Order. The elements are addressed in terms of the fire protection objectives stated in paragraph 4 of DOE 5480.7A. In addition, the FHA also complies with WHC-CM-4-41, Fire Protection Program Manual, Section 3.4 [1994] and WHC-SD-GN-FHA-30001, Rev. 0 [WHC, 1994]. Objectives of the FHA are to determine: (1) the fire hazards that expose the PFP facilities, or that are inherent in the building operations, (2) the adequacy of the fire safety features currently located in the PFP Complex, and (3) the degree of compliance of the facility with specific fire safety provisions in DOE orders, related engineering codes, and standards.

  11. 10 CFR 140.13a - Amount of financial protection required for plutonium processing and fuel fabrication plants.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Amount of financial protection required for plutonium... of financial protection required for plutonium processing and fuel fabrication plants. (a) Each holder of a license issued pursuant to part 70 of this chapter to possess and use plutonium at...

  12. In situ remediation of plutonium from glovebox exhaust ducts at the Department of Energy's Rocky Flats Plant

    International Nuclear Information System (INIS)

    Plutonium and other miscellaneous hold-up materials have been accumulating in the glovebox exhaust ducts at the Rocky Flats Plant over the 40 years of weapons production at the site. The Duct Remediation Project was undertaken to assess the safety impacts of this material, and to remove it from the ductwork. The project necessitated the development of specialized tools, equipment and methods to remediate the material from continuously operating ventilation systems. Special engineered access locations were also required to provide access to the ductwork, and to ensure that safety and system operability were not degraded as a result of the remediation efforts. Operations personnel underwent significant training and development, and became an important asset to the success of the project. In total, the project succeeded in removing over 40 kilograms of plutonium-bearing material from one of the major weapons production buildings at the plant

  13. Plutonium Finishing Plant (PFP) Treatment and Storage Unit Waste Analysis Plan

    International Nuclear Information System (INIS)

    The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Plutonium Finishing Plant Treatment and Storage Unit (PFP Treatment and Storage Unit) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (4)(a) and (5). The PFP Treatment and Storage Unit is an interim status container management unit for plutonium bearing mixed waste radiologically managed as transuranic (TRU) waste. TRU mixed (TRUM) waste managed at the PFP Treatment and Storage Unit is destined for the Waste Isolation Pilot Plant (WIPP) and therefore is not subject to land disposal restrictions [WAC 173-303-140 and 40 CFR 268]. The PFP Treatment and Storage Unit is located in the 200 West Area of the Hanford Facility, Richland Washington (Figure 1). Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

  14. Reactor-grade plutonium inventory taking in the RT-1 storage production association Mayak site

    International Nuclear Information System (INIS)

    General characterization of plutonium physical inventory taking (PIT) system at the RT-1 plant is given in the paper. The proposed PIT procedure is based on measuring indirect parameters of inventory plutonium, the so called attributes of items - containers with plutonium. The method how to assess quality of item attribute measurements is proposed. If any defect is detected, the container is sent back to the place where it been filed and packed in order to perform direct measurements of plutonium mass. Taking into account the above-mentioned techniques and the availability of several access control means it is proposed the period between two PIT procedures be equal to 12 months

  15. A review of plutonium oxalate decomposition reactions and effects of decomposition temperature on the surface area of the plutonium dioxide product

    Science.gov (United States)

    Orr, R. M.; Sims, H. E.; Taylor, R. J.

    2015-10-01

    Plutonium (IV) and (III) ions in nitric acid solution readily form insoluble precipitates with oxalic acid. The plutonium oxalates are then easily thermally decomposed to form plutonium dioxide powder. This simple process forms the basis of current industrial conversion or 'finishing' processes that are used in commercial scale reprocessing plants. It is also widely used in analytical or laboratory scale operations and for waste residues treatment. However, the mechanisms of the thermal decompositions in both air and inert atmospheres have been the subject of various studies over several decades. The nature of intermediate phases is of fundamental interest whilst understanding the evolution of gases at different temperatures is relevant to process control. The thermal decomposition is also used to control a number of powder properties of the PuO2 product that are important to either long term storage or mixed oxide fuel manufacturing. These properties are the surface area, residual carbon impurities and adsorbed volatile species whereas the morphology and particle size distribution are functions of the precipitation process. Available data and experience regarding the thermal and radiation-induced decompositions of plutonium oxalate to oxide are reviewed. The mechanisms of the thermal decompositions are considered with a particular focus on the likely redox chemistry involved. Also, whilst it is well known that the surface area is dependent on calcination temperature, there is a wide variation in the published data and so new correlations have been derived. Better understanding of plutonium (III) and (IV) oxalate decompositions will assist the development of more proliferation resistant actinide co-conversion processes that are needed for advanced reprocessing in future closed nuclear fuel cycles.

  16. Uranium Fuel Plant. Applicants environmental report

    International Nuclear Information System (INIS)

    The Uranium Fuel Plant, located at the Cimarron Facility, was constructed in 1964 with operations commencing in 1965 in accordance with License No. SNM-928, Docket No. 70-925. The plant has been in continuous operation since the issuance of the initial license and currently possesses contracts extending through 1978, for the production of nuclear fuels. The Uranium Plant is operated in conjunction with the Plutonium Facility, each sharing common utilities and sanitary wastes disposal systems. The operation has had little or no detrimental ecological impact on the area. For the operation of the Uranium Fuel Fabrication Plant, initial equipment provided for the production of UO2, UF4, uranium metal and recovery of scrap materials. In 1968, the plant was expanded by increasing the UO2 and pellet facilities by the installation of another complete production line for the production of fuel pellets. In 1969, fabrication facilities were added for the production of fuel elements. Equipment initially installed for the recovery of fully enriched scrap has not been used since the last work was done in 1970. Economically, the plant has benefited the Logan County area, with approximately 104 new jobs with an annual payroll of approximately $1.3 million. In addition, $142,000 is annually paid in taxes to state, local and federal governments, and local purchases amount to approximately $1.3 million. This was all in land that was previously used for pasture land, with a maximum value of approximately 37,000 dollars. Environmental effects of plant operation have been minimal. A monitoring and measurement program is maintained in order to ensure that the ecology of the immediate area is not affected by plant operations

  17. VASCULAR FLORA OF ALABASTER CAVERNS STATE PARK, CIMARRON GYPSUM HILLS: WOODWARD COUNTY, OKLAHOMA

    Directory of Open Access Journals (Sweden)

    Kristi D. Rice

    2012-12-01

    Full Text Available Alabaster Caverns State Park is located in the Cimarron Gypsum Hills of northwestern Oklahoma, a semi-arid region of the state. The majority of the park is dominated by mixed-grass prairie and gypsum outcrops, with some riparian habitat and wooded north-facing slopes. A vascular plant inventory conducted from 2004 through 2007 yielded 274 species in 199 genera and 66 families. The largest families were the Poaceae (52 species, Asteraceae (47, and Fabaceae (23. There were 100 annuals, 6 biennials, and 163 perennials, as well as 5 species that have more than one life history form. Forty-two species (15.3% were not native to North America. Three taxa currently being tracked by the Oklahoma Natural Heritage Inventory (2012 were present: Echinocereus reichenbachii (S3G5, Haploesthes greggii (S1G4?, and Marsilea vestita (S1G5. Compared to floristic inventories of sites in the Cimarron Gypsum Hills that are less impacted by public visitation, but more intensively grazed, Alabaster Caverns State Park has a higher number of species as well as a higher proportion of introduced species.

  18. Intake and digestibility of range plants grown on plutonium contaminated soils as determined with grazing cattle

    International Nuclear Information System (INIS)

    Area 13 is one of several areas of the Nevada Test Site contaminated with transuranics. Cattle were grazed on the area to study the botanical and chemical composition of the forage, the digestibility of range plants as selected by range cattle, and the intake of plutonium and americium by grazing cattle. The botanical and chemical composition of the diet of cattle grazing on plutonium-contaminated range was determined. The major portion of the diet was browse plants which were high in fiber and ash but low in energy. Daily feed intake of the grazing animals was also determined so that the amount of nuclides ingested daily could be ascertained. Cattle generally consumed over 2 kilograms per 100 kilograms body weight of dry matter daily which resulted in a daily intake of 3600 to 6600 picocuries of plutonium-238, 85,000 to 400,000 picocuries of plutonium-239, and 11,000 to 31,000 picocuries of americium-241. The soil ingested by range cattle constituted the principal source of ingested plutonium and americium. This is not unexpected as plutonium oxide is one of the least soluble substances known and the range studied is one of very limited rainfall. As expected, the forage from an inner compound was contaminated to a greater extent than the range plants from an outer compound

  19. EIS Data Call Report: Plutonium immobilization plant using glass in new facilities at the Savannah River Site

    International Nuclear Information System (INIS)

    The Plutonium Immobilization Plant (PIP) accepts plutonium (Pu) from pit conversion and from non-pit sources and, through a glass immobilization process, converts the plutonium into an immobilized form that can be disposed of in a high level waste (HLW) repository. This immobilization process is shown conceptually in Figure 1-1. The objective is to make an immobilized form, suitable for geologic disposal, in which the plutonium is as inherently unattractive and inaccessible as the plutonium in spent fuel from commercial reactors

  20. Vitrification of plutonium at Rocky Flats the argument for a pilot plant

    Energy Technology Data Exchange (ETDEWEB)

    Moore, L. [Rocky Mountain Peace Center, Boulder, CO (United States)

    1996-05-01

    Current plans for stabilizing and storing the plutonium at Rocky Flats Plant fail to put the material in a form suitable for disposition and resistant to proliferation. Vitrification should be considered as an alternate technology. The vitrification should begin with a small-scale pilot plant.

  1. Enzymatic degradation of plutonium-contaminated cellulose products

    Energy Technology Data Exchange (ETDEWEB)

    Heintz, C.E.; Rainwater, K.A.; Swift, L.M. [Texas Tech Univ., Lubbock, TX (United States); Barnes, D.L. [Amarillo National Resource Center for Plutonium, TX (United States); Worl, L.; Avens, L. [Los Alamos National Lab., NM (United States)

    1999-03-01

    Enzyme solutions produced for commercial purposes unrelated to waste management have the potential for reducing the volume of wastes in streams containing cellulose, lipid and protein materials. For example, the authors have shown that cellulases used in denim production and in detergent formulations are able to digest cellulose-containing sorbents and other cellulose-based wastes contaminated either with crude oil or with radionuclides. This presentation describes the use of one such enzyme preparation (Rapidase{trademark}) for the degradation of cotton sorbents intentionally contaminated with low levels of plutonium. This is part of a feasibility study to determine if such treatments have a role in reducing the volume of low level and transuranic wastes to minimize the amount of radionuclide-contaminated waste that must be disposed of in secured storage areas.

  2. Enzymatic degradation of plutonium-contaminated cellulose products

    Energy Technology Data Exchange (ETDEWEB)

    Heintz, C.E.; Rainwater, K.A.; Swift, L.M. [Texas Tech Univ., Lubbock, TX (United States); Barnes, D.L. [Amarillo National Resource Center for Plutonium, TX (United States); Worl, L.A. [Los Alamos National Lab., NM (United States)

    1999-06-01

    Enzyme solutions produced for commercial purposes unrelated to waste management have the potential for reducing the volume of wastes in streams containing cellulose, lipid and protein materials. For example, the authors have shown previously that cellulases used in denim production and in detergent formulations are able to digest cellulose-containing sorbents and other cellulose-based wastes contaminated either with crude oil or with uranium. This presentation describes the use of one such enzyme preparation (Rapidase{trademark}, manufactured by Genencor, Rochester, NY) for the degradation of cotton sorbents intentionally contaminated with low levels of plutonium. This is part of a feasibility study to determine if such treatments have a role in reducing the volume of low level and transuranic wastes to minimize the amount of radionuclide-contaminated waste destined for costly disposal options.

  3. Enzymatic degradation of plutonium-contaminated cellulose products

    International Nuclear Information System (INIS)

    Enzyme solutions produced for commercial purposes unrelated to waste management have the potential for reducing the volume of wastes in streams containing cellulose, lipid and protein materials. For example, the authors have shown that cellulases used in denim production and in detergent formulations are able to digest cellulose-containing sorbents and other cellulose-based wastes contaminated either with crude oil or with radionuclides. This presentation describes the use of one such enzyme preparation (Rapidase trademark) for the degradation of cotton sorbents intentionally contaminated with low levels of plutonium. This is part of a feasibility study to determine if such treatments have a role in reducing the volume of low level and transuranic wastes to minimize the amount of radionuclide-contaminated waste that must be disposed of in secured storage areas

  4. Literature review: Phytoaccumulation of chromium, uranium, and plutonium in plant systems

    Energy Technology Data Exchange (ETDEWEB)

    Hossner, L.R.; Loeppert, R.H.; Newton, R.J. [Texas A& M Univ., College Station, TX (United States); Szaniszlo, P.J. [Univ. of Texas, Austin, TX (United States)

    1998-05-01

    Phytoremediation is an integrated multidisciplinary approach to the cleanup of contaminated soils, which combines the disciplines of plant physiology, soil chemistry, and soil microbiology. Metal hyperaccumulator plants are attracting increasing attention because of their potential application in decontamination of metal-polluted soils. Traditional engineering technologies may be too expensive for the remediation of most sites. Removal of metals from these soils using accumulator plants is the goal of phytoremediation. The emphasis of this review has been placed on chromium (Cr), plutonium (Pu), and uranium (U). With the exception of Cr, these metals and their decay products exhibit two problems, specifically, radiation dose hazards and their chemical toxicity. The radiation hazard introduces the need for special precautions in reclamation beyond that associated with non-radioactive metals. The uptake of beneficial metals by plants occurs predominantly by way of channels, pores, and transporters in the root plasma membrane. Plants characteristically exhibit a remarkable capacity to absorb what they need and exclude what they don`t need. But most vascular plants absorb toxic and heavy metals through their roots to some extent, though to varying degrees, from negligible to substantial. Sometimes absorption occurs because of the chemical similarity between beneficial and toxic metals. Some plants utilize exclusion mechanisms, where there is a reduced uptake by the roots or a restricted transport of the metal from root to shoot. At the other extreme, hyperaccumulator plants absorb and concentrate metals in both roots and shoots. Some plant species endemic to metalliferous soils accumulate metals in percent concentrations in the leaf dry matter.

  5. The quality evaluation program for plutonium pits at the U.S. DOE Pantex plant.

    Science.gov (United States)

    Vickers, L; Eifert, E

    2000-11-01

    The United States Department of Energy Pantex Plant quality evaluation program for plutonium pits is an extensive program that includes 1) weigh and leak check system; 2) radiography; and 3) dye penetrant testing. Successful completion of these diagnostics qualifies a pit to remain in the active status stockpile program. The use of lead aprons and a robot when handling the plutonium pits minimizes personnel exposures to ionizing radiation. All personnel exposures to ionizing radiation at Pantex Plant are As Low As Reasonably Achievable. PMID:11045519

  6. Plutonium production story at the Hanford site: processes and facilities history

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, M.S., Westinghouse Hanford

    1996-06-20

    This document tells the history of the actual plutonium production process at the Hanford Site. It contains five major sections: Fuel Fabrication Processes, Irradiation of Nuclear Fuel, Spent Fuel Handling, Radiochemical Reprocessing of Irradiated Fuel, and Plutonium Finishing Operations. Within each section the story of the earliest operations is told, along with changes over time until the end of operations. Chemical and physical processes are described, along with the facilities where these processes were carried out. This document is a processes and facilities history. It does not deal with the waste products of plutonium production.

  7. 75 FR 38809 - Southern Turner Cimarron I, LLC; Notice of Filing

    Science.gov (United States)

    2010-07-06

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Southern Turner Cimarron I, LLC; Notice of Filing June 25, 2010. Take notice that on June 24, 2010, Southern Turner Cimarron I, LLC filed a supplement confirming passive...

  8. Transport of plutonium, americium, and curium from soils into plants by roots

    International Nuclear Information System (INIS)

    For assessing the dose from radionuclides in agricultural products by ingestion it is necessary to know the soil to plant transfer factors. The literature was entirely investigated, in order to judge the size of the soil to plant transfer factors. In total, 92 publications - from 1948 to 1978 -have been evaluated. As result, transfer factors from 10-9 to 10-3 have been found for Plutonium, and from 10-6 to 1 for Americium. For Curium only few data are available in literature. The considerable variation of the measured transfer factors is based on the dependence of these transfer factors from the ion exchange capacity of soils, from the amount of organic materials, from the pH-value, and from the mode of contamination. There are, in any case, contradictory data, although there has been detected a dependence of the transfer factors from these parameters. Chelating agenst increase the transfer factors to approximately 1300. As well, fertilizers have an influence on the size of the transfer factors - however, the relationships have been scarcely investigated. The distribution of actinides within the individual parts of plants has been investigated. The highest concentrations are in the roots; in the plant parts above ground the concentration of actinides decreases considerably. The most inferior transfer factors were measured for the respective seed or fruits. The soil to plant transfer factors of actinides are more dependend on the age of the plants within one growing period. At the beginning of the period, the transfer factor is considerably higher than at the end of this period. With respect to plants with a growing period of several years, correlations are unknown. (orig.)

  9. The Chemical Hazards Assessment Prior to D&D of the Plutonium Finishing Plant, Hanford Nuclear Reservation

    Energy Technology Data Exchange (ETDEWEB)

    Hopkins, A. M.; Prevette, S. S.; Sherwood, A. R.; Fitch, L. R.; Ranade, D. G.; Oldham, R. W.

    2003-02-26

    This report describes the evaluation methods and results of a chemical safety status assessment of the process equipment at the U.S. Department of Energy Hanford Nuclear Reservation Plutonium Finishing Plant. This assessment, designated as the Plutonium Finishing Plant Residual Chemical Hazards Assessment, focused particular emphasis on the idle and inactive plant systems, though certain active areas also were examined to the extent that these were examined during a previous facility vulnerability assessment completed in 1999. The Plutonium Finishing Plant is located in the 200 West Area of the Hanford Nuclear Reservation that is situated in south central Washington State.

  10. Tritium and plutonium production as a step toward ICF commercialization

    International Nuclear Information System (INIS)

    The feasibility of a combined special nuclear materials (SNM) production plant/engineering test facility (ETF) with reduced pellet and driver performance requirements as a step toward commercialization of inertial confinement fusion (ICF) is examined. Blanket design and tritium production cost studies, the status of R and D programs, and the ETF role are emphasized

  11. Plutonium Story

    Science.gov (United States)

    Seaborg, G. T.

    1981-09-01

    The first nuclear synthesis and identification (i.e., the discovery) of the synthetic transuranium element plutonium (isotope /sup 238/Pu) and the demonstration of its fissionability with slow neutrons (isotope /sup 239/Pu) took place at the University of California, Berkeley, through the use of the 60-inch and 37-inch cyclotrons, in late 1940 and early 1941. This led to the development of industrial scale methods in secret work centered at the University of Chicago's Metallurgical Laboratory and the application of these methods to industrial scale production, at manufacturing plants in Tennessee and Washington, during the World War II years 1942 to 1945. The chemical properties of plutonium, needed to devise the procedures for its industrial scale production, were studied by tracer and ultramicrochemical methods during this period on an extraordinarily urgent basis. This work, and subsequent investigations on a worldwide basis, have made the properties of plutonium very well known. Its well studied electronic structure and chemical properties give it a very interesting position in the actinide series of inner transition elements.

  12. Plutonium story

    International Nuclear Information System (INIS)

    The first nuclear synthesis and identification (i.e., the discovery) of the synthetic transuranium element plutonium (isotope 238Pu) and the demonstration of its fissionability with slow neutrons (isotope 239Pu) took place at the University of California, Berkeley, through the use of the 60-inch and 37-inch cyclotrons, in late 1940 and early 1941. This led to the development of industrial scale methods in secret work centered at the University of Chicago's Metallurgical Laboratory and the application of these methods to industrial scale production, at manufacturing plants in Tennessee and Washington, during the World War II years 1942 to 1945. The chemical properties of plutonium, needed to devise the procedures for its industrial scale production, were studied by tracer and ultramicrochemical methods during this period on an extraordinarily urgent basis. This work, and subsequent investigations on a worldwide basis, have made the properties of plutonium very well known. Its well studied electronic structure and chemical properties give it a very interesting position in the actinide series of inner transition elements

  13. Determination of trace quantity of uranium in end product plutonium oxide samples by isotopic dilution mass spectrometry using an indigenous thermal ionization mass spectrometer

    International Nuclear Information System (INIS)

    Characterization of special nuclear materials is an important step for efficient nuclear material management (NMM) in a fuel reprocessing plant. Determination of trace quantity of impurities present in the end product plutonium oxide is very important in categorizing the product for end-user specifications. An accurate knowledge of uranium quantity helps in many ways to characterize the material. Objective of this present work is to optimize the indigenous thermal ionization mass spectrometer for this work and develop a better and effective separation procedure prior to mass spectrometric analysis for determination of trace quantity of uranium in plutonium product stream oxide samples

  14. Characterization of past and present solid waste streams from the Plutonium-Uranium Extraction Plant

    International Nuclear Information System (INIS)

    During the next two decades the transuranic wastes, now stored in the burial trenches and storage facilities at the Hanford Site, are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Over 7% of the transuranic waste to be retrieved for shipment to the Waste Isolation Pilot Plant has been generated at the Plutonium-Uranium Extraction (PUREX) Plant. The purpose of this report is to characterize the radioactive solid wastes generated by PUREX using process knowledge, existing records, and oral history interviews. The PUREX Plant is currently operated by the Westinghouse Hanford Company for the US Department of Energy and is now in standby status while being prepared for permanent shutdown. The PUREX Plant is a collection of facilities that has been used primarily to separate plutonium for nuclear weapons from spent fuel that had been irradiated in the Hanford Site's defense reactors. Originally designed to reprocess aluminum-clad uranium fuel, the plant was modified to reprocess zirconium alloy clad fuel elements from the Hanford Site's N Reactor. PUREX has provided plutonium for research reactor development, safety programs, and defense. In addition, the PUREX was used to recover slightly enriched uranium for recycling into fuel for use in reactors that generate electricity and plutonium. Section 2.0 provides further details of the PUREX's physical plant and its operations. The PUREX Plant functions that generate solid waste are as follows: processing operations, laboratory analyses and supporting activities. The types and estimated quantities of waste resulting from these activities are discussed in detail

  15. Characterization of past and present solid waste streams from the Plutonium-Uranium Extraction Plant

    Energy Technology Data Exchange (ETDEWEB)

    Pottmeyer, J.A.; Weyns, M.I.; Lorenzo, D.S.; Vejvoda, E.J. [Los Alamos Technical Associates, Inc., NM (US); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (US)

    1993-04-01

    During the next two decades the transuranic wastes, now stored in the burial trenches and storage facilities at the Hanford Site, are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Over 7% of the transuranic waste to be retrieved for shipment to the Waste Isolation Pilot Plant has been generated at the Plutonium-Uranium Extraction (PUREX) Plant. The purpose of this report is to characterize the radioactive solid wastes generated by PUREX using process knowledge, existing records, and oral history interviews. The PUREX Plant is currently operated by the Westinghouse Hanford Company for the US Department of Energy and is now in standby status while being prepared for permanent shutdown. The PUREX Plant is a collection of facilities that has been used primarily to separate plutonium for nuclear weapons from spent fuel that had been irradiated in the Hanford Site`s defense reactors. Originally designed to reprocess aluminum-clad uranium fuel, the plant was modified to reprocess zirconium alloy clad fuel elements from the Hanford Site`s N Reactor. PUREX has provided plutonium for research reactor development, safety programs, and defense. In addition, the PUREX was used to recover slightly enriched uranium for recycling into fuel for use in reactors that generate electricity and plutonium. Section 2.0 provides further details of the PUREX`s physical plant and its operations. The PUREX Plant functions that generate solid waste are as follows: processing operations, laboratory analyses and supporting activities. The types and estimated quantities of waste resulting from these activities are discussed in detail.

  16. Proposal to recirculate glove box and fabrication area air in a plutonium fuel fabrication plant

    International Nuclear Information System (INIS)

    Recirculating glove box and fabrication area ventilation systems are proposed for a 40 Te/yr mixed plutonium--uranium oxide fuel fabrication plant. The ventilation design criteria are outlined, features of the fabricating plant relating to the ventilation system are shown and the recirculating systems are described. A method of operating and recirculating systems during unusual situations, energy conservation and system advantages are discussed. (U.S.)

  17. EIS Data Call Report: Plutonium immobilization plant using ceramic in new facilities at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    DiSabatino, A.

    1998-06-01

    The Plutonium Immobilization Plant (PIP) accepts plutonium (Pu) from pit conversion and from non-pit sources and, through a ceramic immobilization process, converts the plutonium into an immobilized form that can be disposed of in a high level waste (HLW) repository. This immobilization process is shown conceptually in Figure 1-1. The objective is to make an immobilized form, suitable for geologic disposal, in which the plutonium is as inherently unattractive and inaccessible as the plutonium in spent fuel from commercial reactors. The ceramic immobilization alternative presented in this report consists of first converting the surplus material to an oxide, followed by incorporating the plutonium oxide into a titanate-based ceramic material that is placed in metal cans.

  18. EIS Data Call Report: Plutonium immobilization plant using ceramic in new facilities at the Savannah River Site

    International Nuclear Information System (INIS)

    The Plutonium Immobilization Plant (PIP) accepts plutonium (Pu) from pit conversion and from non-pit sources and, through a ceramic immobilization process, converts the plutonium into an immobilized form that can be disposed of in a high level waste (HLW) repository. This immobilization process is shown conceptually in Figure 1-1. The objective is to make an immobilized form, suitable for geologic disposal, in which the plutonium is as inherently unattractive and inaccessible as the plutonium in spent fuel from commercial reactors. The ceramic immobilization alternative presented in this report consists of first converting the surplus material to an oxide, followed by incorporating the plutonium oxide into a titanate-based ceramic material that is placed in metal cans

  19. Calculation note - Consequences of a fire in the sorting and repackaging glovebox in room 636 of bldg 2736-ZB - Plutonium Finishing Plant

    International Nuclear Information System (INIS)

    This Calculation Note provides a conservative estimate of the grams of plutonium released from Building 2736-ZB of the Plutonium Finishing Plant as a result of a fire within Glovebox 636, without consideration of mitigation

  20. METHOD OF SEPARATING URANIUM, PLUTONIUM AND FISSION PRODUCTS BY BROMINATION AND DISTILLATION

    Science.gov (United States)

    Jaffey, A.H.; Seaborg, G.T.

    1958-12-23

    The method for separation of plutonium from uranium and radioactive fission products obtained by neutron irradiation of uranlum consists of reacting the lrradiated material with either bromine, hydrogen bromide, alumlnum bromide, or sulfur and bromine at an elevated temperature to form the bromides of all the elements, then recovering substantlally pure plutonium bromide by dlstillatlon in combinatlon with selective condensatlon at prescribed temperature and pressure.

  1. Large scale production of Pu-238 to 'denature' weapons-grade plutonium. Rev. 0

    International Nuclear Information System (INIS)

    The concept of open-quote denaturing close-quote weapons-grade or reactor-grade plutonium through the addition of Pu-238 has been proposed recently by Dr. Mel Coops of Lawrence Livermore National Laboratory. He indicates that on the order of 2-3 wt.% plutonium-238 (Pu-238) may be sufficient to render the plutonium impractical for weapons use due to excessive heat generation. This would significantly reduce or eliminate proliferation concerns for use of plutonium in commercial nuclear fuels. This report presents a high-level assessment of the potential for producing large quantities of Pu-238 for the purpose of open-quote denaturing close-quote the weapons-grade or reactor-grade plutonium that may be used in commercial reactors as mixed-oxide (MOX) fuels. Pu-238 production can be done by two methods. The traditional method employed in the U.S. was to irradiate targets of neptunium-237 (Np-237), this isotope being produced from neutron capture in U-236. Recycling enriched uranium fuels in the defense production reactor fuel cycle increased the U-236 content, increasing the subsequent yield of Np-237. Production by this method thus involves significant reactor irradiation time, and reprocessing of fuel to recover uranium and Np-237 for fabrication into new fuel and targets, respectively. The second method would be to irradiate targets of Am-241, recovered as a decay product from aged plutonium. This method again would require processing of plutonium or spent fuel to recover Am-241. Either method would require processing of targets after irradiation, and a facility for fabricating targets and processing the plutonium to a final pure oxide form

  2. Characterization of past and present solid waste streams from the plutonium finishing plant

    Energy Technology Data Exchange (ETDEWEB)

    Duncan, D R; Mayancsik, B A [Westinghouse Hanford Co., Richland, WA (United States); Pottmeyer, J A; Vejvoda, E J; Reddick, J A; Sheldon, K M; Weyns, M I [Los Alamos Technical Associates, Kennewick, WA (United States)

    1993-02-01

    During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing (WRAP) Facility, and shipped to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico for final disposal. Over 50% of the TRU waste to be retrieved for shipment to the WIPP has been generated at the Plutonium Finishing Plant (PFP), also known as the Plutonium Processing and Storage Facility and Z Plant. The purpose of this report is to characterize the radioactive solid wastes generated by the PFP since its construction in 1947 using process knowledge, existing records, and history-obtained from interviews. The PFP is currently operated by Westinghouse Hanford Company (WHC) for the US Department of Energy (DOE).

  3. Simulation and analysis of experimental plutonium production rates in depleted uranium sphere bombarded by 14 MeV neutron

    International Nuclear Information System (INIS)

    According to the measurement of plutonium production rates resulting from 14 MeV neutrons in depleted uranium sphere, the experimental results and influencing factors were simulated and analyzed with MCNP5 code. It shows that simulant plutonium production rates from uresa and endf66c agree very well with experimental results, simulant effects on plutonium production rates by cavity, construction materials and water lays and background neutrons etc., are slight. (authors)

  4. A literature study of the behaviour of cesium, strontium and plutonium in the soil-plant ecosystem

    International Nuclear Information System (INIS)

    Literature on the occurrence of radiocesium (primarily 137CS) in the soil-plant system with emphasis on the influence of treatment on its root uptake, was reviewed. The aim was to study root uptake of radiocesium in order to estimate the applicability of suitable counter measures in cases of contamination of arable land with plutonium, radiostrontium and, in particular, radiocesium. To what extent 136CS is available to, and absorbed by, the plant and how it is distributed and absorbed in the soil is described. The physiological uptake of plutonium from soil through roots to plant parts lying above ground constitutes minor health hazards to population from the ingestion of vegetables. Extensive use of root fruits, might indicate that there is a risk present in areas of high plutonium soil concentration, because plutonium is adsorbed to root molecules, especially if soil and peel are not discarded. Another risk lies in the resuspension of plutonium deposited on the soil surface. As mentioned above, the impact of the leakage of plutonium from the Chernobyl accident was negligible in distant areas. The effects in the vicinity of the reactor, might have been important. In small areas with high levels of plutonium contamination removal of the top soil layer will be effective. Because of the high toxity and long half-life of plutonium, the risk involved merely in isolating such an area will be to high, because the plutonium may be further dispersed. In larger areas, deep ploughing to a depth of 30-40 cm or more, if feasible, is a possibility. Local factors have to be considered, e.g. position of bedrock, groundwater, soil parameters etc. Deep ploughing combined with previous dispersion of clay minerals, lime or humus or a combination, might be a solution, and should be followed by limiting crops to those with roots concentrated in the surface layer and with smallest attainable concentration ratios for plutonium. Cereals might fill this demand. 188 refs. (AB)

  5. Plutonium Finishing Plant (PFP) Standards/Requirements Identification Document (S/RID)

    International Nuclear Information System (INIS)

    This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ESH) standards/requirements for the Plutonium Finishing Plant (PFP). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment

  6. Plutonium Finishing Plant (PFP) Safety Class and Safety Significant Commercial Grade Items (CGI) Critical Characteristic

    International Nuclear Information System (INIS)

    This document specifies the critical characteristics for Commercial Grade Items (CGI) procured for use in the Plutonium Finishing Plant as required by HNF-PRO-268 and HNF-PRO-1819. These are the minimum specifications that the equipment must meet in order to properly perform its safety function. There may be several manufacturers or models that meet the critical characteristics of any one item

  7. Plutonium Finishing Plant (PFP) Standards/Requirements Identification Document (S/RID)

    Energy Technology Data Exchange (ETDEWEB)

    Maddox, B.S.

    1996-01-01

    This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ESH) standards/requirements for the Plutonium Finishing Plant (PFP). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

  8. SEPARATION OF PLUTONIUM

    Science.gov (United States)

    Maddock, A.G.; Smith, F.

    1959-08-25

    A method is described for separating plutonium from uranium and fission products by treating a nitrate solution of fission products, uranium, and hexavalent plutonium with a relatively water-insoluble fluoride to adsorb fission products on the fluoride, treating the residual solution with a reducing agent for plutonium to reduce its valence to four and less, treating the reduced plutonium solution with a relatively insoluble fluoride to adsorb the plutonium on the fluoride, removing the solution, and subsequently treating the fluoride with its adsorbed plutonium with a concentrated aqueous solution of at least one of a group consisting of aluminum nitrate, ferric nitrate, and manganous nitrate to remove the plutonium from the fluoride.

  9. Estimation and characterization of decontamination and decommissioning solid waste expected from the Plutonium Finishing Plant

    International Nuclear Information System (INIS)

    Purpose of the study was to estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the Hanford Plutonium Finishing Plant is decontaminated and decommissioned. (Building structure and soil are not covered.) Results indicate that ∼5,500 m3 of solid waste is expected to result from the decontamination and decommissioning of the Pu Finishing Plant. The breakdown of the volumes and percentages of waste by category is 1% dangerous solid waste, 71% low-level waste, 21% transuranic waste, 7% transuranic mixed waste

  10. Total Measurement Uncertainty for the Plutonium Finishing Plant (PFP) Segmented Gamma Scan Assay System

    CERN Document Server

    Fazzari, D M

    2001-01-01

    This report presents the results of an evaluation of the Total Measurement Uncertainty (TMU) for the Canberra manufactured Segmented Gamma Scanner Assay System (SGSAS) as employed at the Hanford Plutonium Finishing Plant (PFP). In this document, TMU embodies the combined uncertainties due to all of the individual random and systematic sources of measurement uncertainty. It includes uncertainties arising from corrections and factors applied to the analysis of transuranic waste to compensate for inhomogeneities and interferences from the waste matrix and radioactive components. These include uncertainty components for any assumptions contained in the calibration of the system or computation of the data. Uncertainties are propagated at 1 sigma. The final total measurement uncertainty value is reported at the 95% confidence level. The SGSAS is a gamma assay system that is used to assay plutonium and uranium waste. The SGSAS system can be used in a stand-alone mode to perform the NDA characterization of a containe...

  11. The chemistry of tributyl phosphate at elevated temperatures in the Plutonium Finishing Plant Process Vessels

    Energy Technology Data Exchange (ETDEWEB)

    Barney, G.S.; Cooper, T.D.

    1994-06-01

    Potentially violent chemical reactions of the tributyl phosphate solvent used by the Plutonium Finishing Plant at the Hanford Site were investigated. There is a small probability that a significant quantity of this solvent could be accidental transferred to heated process vessels and react there with nitric acid or plutonium nitrate also present in the solvent extraction process. The results of laboratory studies of the reactions show that exothermic oxidation of tributyl phosphate by either nitric acid or actinide nitrates is slow at temperatures expected in the heated vessels. Less than four percent of the tributyl phosphate will be oxidized in these vented vessels at temperatures between 125{degrees}C and 250{degrees}C because the oxidant will be lost from the vessels by vaporization or decomposition before the tributyl phosphate can be extensively oxidized. The net amounts of heat generated by oxidation with concentrated nitric acid and with thorium nitrate (a stand-in for plutonium nitrate) were determined to be about -150 and -220 joules per gram of tributyl phosphate initially present, respectively. This is not enough heat to cause violent reactions in the vessels. Pyrolysis of the tributyl phosphate occurred in these mixtures at temperatures of 110{degrees}C to 270{degrees}C and produced mainly 1-butene gas, water, and pyrophosphoric acid. Butene gas generation is slow at expected process vessel temperatures, but the rate is faster at higher temperatures. At 252{degrees}C the rate of butene gas generated was 0.33 g butene/min/g of tributyl phosphate present. The measured heat absorbed by the pyrolysis reaction was 228 J/g of tributyl phosphate initially present (or 14.5 kcal/mole of tributyl phosphate). Release of flammable butene gas into process areas where it could ignite appears to be the most serious safety consideration for the Plutonium Finishing Plant.

  12. Powder detergents production plant

    Directory of Open Access Journals (Sweden)

    Stanković Mirjana S.

    2003-01-01

    Full Text Available The IGPC Engineering Department designed basic projects for powder detergent production plant, using technology developed in the IGPC laboratories, in 1998. - 2000. Several projects were completed: technological, machine, electrical, automation. On the basis of these projects, a production plant with a capacity of 25,000 t/y was manufactured, at "Delta In", Zrenjanin, in 2000.This technology was an innovation, because new approach in mixing a powder materials was used, as well as introducing a new type of dryer in detergent production. The product meets all quality demands for detergents with high specific weight (1000 g/l, as well as environmental regulations. The detergent production process is fully automatized, and the product has uniform quality. There is no waste material in detergent zeolite production, because all products with unsatisfactory quality are returned to the process. The production process can be controlled manually, which is necessary during start-up, and repairs.

  13. ASSESSING CHEMICAL HAZARDS AT THE PLUTONIUM FINISHING PLANT (PFP) FOR PLANNING FUTURE D&D

    Energy Technology Data Exchange (ETDEWEB)

    HOPKINS, A.M.; KLOS, D.B.; MINETT, M.J.

    2007-01-25

    This paper documents the fiscal year (FY) 2006 assessment to evaluate potential chemical and radiological hazards associated with vessels and piping in the former plutonium process areas at Hanford's Plutonium Finishing Plant (PFP). Evaluations by PFP engineers as design authorities for specific systems and other subject-matter experts were conducted to identify the chemical hazards associated with transitioning the process areas for the long-term layup of PFP before its eventual final decontamination and decommissioning (D and D). D and D activities in the main process facilities were suspended in September 2005 for a period of between 5 and 10 years. A previous assessment conducted in FY 2003 found that certain activities to mitigate chemical hazards could be deferred safely until the D and D of PFP, which had been scheduled to result in a slab-on-grade condition by 2009. As a result of necessary planning changes, however, D and D activities at PFP will be delayed until after the 2009 time frame. Given the extended project and plant life, it was determined that a review of the plant chemical hazards should be conducted. This review to determine the extended life impact of chemicals is called the ''Plutonium Finishing Plant Chemical Hazards Assessment, FY 2006''. This FY 2006 assessment addresses potential chemical and radiological hazard areas identified by facility personnel and subject-matter experts who reevaluated all the chemical systems (items) from the FY 2003 assessment. This paper provides the results of the FY 2006 chemical hazards assessment and describes the methodology used to assign a hazard ranking to the items reviewed.

  14. Accelerator-based conversion (ABC) of weapons plutonium: Plant layout study and related design issues

    International Nuclear Information System (INIS)

    In preparation for and in support of a detailed R and D Plan for the Accelerator-Based Conversion (ABC) of weapons plutonium, an ABC Plant Layout Study was conducted at the level of a pre-conceptual engineering design. The plant layout is based on an adaptation of the Molten-Salt Breeder Reactor (MSBR) detailed conceptual design that was completed in the early 1070s. Although the ABC Plant Layout Study included the Accelerator Equipment as an essential element, the engineering assessment focused primarily on the Target; Primary System (blanket and all systems containing plutonium-bearing fuel salt); the Heat-Removal System (secondary-coolant-salt and supercritical-steam systems); Chemical Processing; Operation and Maintenance; Containment and Safety; and Instrumentation and Control systems. Although constrained primarily to a reflection of an accelerator-driven (subcritical) variant of MSBR system, unique features and added flexibilities of the ABC suggest improved or alternative approaches to each of the above-listed subsystems; these, along with the key technical issues in need of resolution through a detailed R ampersand D plan for ABC are described on the bases of the ''strawman'' or ''point-of-departure'' plant layout that resulted from this study

  15. Uptake and translocation of plutonium in two plant species using hydroponics.

    Science.gov (United States)

    Lee, J H; Hossner, L R; Attrep, M; Kung, K S

    2002-01-01

    This study presents determinations of the uptake and translocation of Pu in Indian mustard (Brassica juncea) and sunflower (Helianthus annuus) from Pu contaminated solution media. The initial activity levels of Pu were 18.50 and 37.00 Bq ml(-1), for Pu-nitrate [239Pu(NO3)4] and for Pu-citrate [239Pu(C6H5O7)+] in nutrient solution. Plutonium-diethylenetriaminepentaacetic acid (DTPA: [239Pu-C14H23O10N3] solution was prepared by adding 0, 5, 10, and 50 microg of DTPA ml(-1) with 239Pu(NO3)4 in nutrient solution. Concentration ratios (CR, Pu concentration in dry plant material/Pu concentration in nutrient solution) and transport indices (Tl, Pu content in the shoot/Pu content in the whole plant) were calculated to evaluate Pu uptake and translocation. All experiments were conducted in hydroponic solution in an environmental growth chamber. Plutonium concentration in the plant tissue was increased with increased Pu contamination. Plant tissue Pu concentration for Pu-nitrate and Pu-citrate application was not correlated and may be dependent on plant species. For plants receiving Pu-DTPA, the Pu concentration was increased in the shoots but decreased in the roots resulting in a negative correlation between the Pu concentrations in the plant shoots and roots. The Pu concentration in shoots of Indian mustard was increased for application rates up to 10 microg DTPA ml(-1) and up to 5 microg DTPA ml(-1) for sunflower. Similar trends were observed for the CR of plants compared to the Pu concentration in the shoots and roots, whereas the Tl was increased with increasing DTPA concentration. Plutonium in shoots of Indian mustard was up to 10 times higher than that in shoots of sunflower. The Pu concentration in the apparent free space (AFS) of plant root tissue of sunflower was more affected by concentration of DTPA than that of Indian mustard.

  16. Plant Productivity and ESM

    Science.gov (United States)

    Rygalov, V.; Drysdale, A.; Bartsev, S.; Wheeler, R.; Fowler, P.

    An approach for relating Plant Productivity (PP) and Equivalent System Mass (ESM) has been formulated. On this basis, possible reductions of ESM have been analyzed in relation to:-the general mission scenario;-the physiology and cultivation of mixed plant crops;-natural and modified environmental conditions for plant cultivation;-benefits of management approaches;-degree of closure of the artificial support system;-improved plant chamber design. This approach is applied to estimates of minimal ESM for Martian Deployable Greenhouse (MDG).

  17. Hanford Facility Dangerous Waste Closure Plan - Plutonium Finishing Plant Treatment Unit Glovebox HA-20MB

    International Nuclear Information System (INIS)

    This closure plan describes the planned activities and performance standards for closing the Plutonium Finishing Plant (PFP) glovebox HA-20MB that housed an interim status ''Resource Conservation and Recovery Act'' (RCRA) of 1976 treatment unit. This closure plan is certified and submitted to Ecology for incorporation into the Hanford Facility RCRA Permit (HF RCRA Permit) in accordance with Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement; TPA) Milestone M-83-30 requiring submittal of a certified closure plan for ''glovebox HA-20MB'' by July 31, 2003. Glovebox HA-20MB is located within the 231-5Z Building in the 200 West Area of the Hanford Facility. Currently glovebox HA-20MB is being used for non-RCRA analytical purposes. The schedule of closure activities under this plan supports completion of TPA Milestone M-83-44 to deactivate and prepare for dismantlement the above grade portions of the 234-5Z and ZA, 243-Z, and 291-Z and 291-Z-1 stack buildings by September 30, 2015. Under this closure plan, glovebox HA-20MB will undergo clean closure to the performance standards of Washington Administrative Code (WAC) 173-303-610 with respect to all dangerous waste contamination from glovebox HA-20MB RCRA operations. Because the intention is to clean close the PFP treatment unit, postclosure activities are not applicable to this closure plan. To clean close the unit, it will be demonstrated that dangerous waste has not been left at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or is environmentally impractical, the closure plan will be modified to address required postclosure activities. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. Any information on radionuclides is provided only for general knowledge. Clearance form only sent to

  18. The AL-R8 SI: the next generation staging container for plutonium pits at the USDOE Pantex Plant.

    Science.gov (United States)

    Eifert, E J; Vickers, L D

    1999-11-01

    The AL-R8 SI (sealed insert) is the next generation staging container for plutonium pits at the U.S. DOE Pantex Plant. The sealed insert is a stainless steel container that will be placed inside a modified AL-R8 container to stagepits. A pit is a hollow sphere of plutonium metal which is the primary fissionable material in nuclear weapons (warheads and bombs). It is hermetically sealed by a cladding material, which is usually stainless steel. Personnel exposures to ionizing radiation from the pits in storage are expected to decrease due to the attenuation provided by the new SI. All personnel exposures to ionizing radiation at Pantex Plant are As Low As Reasonably Achievable (ALARA). Pantex Plant secures the common defense and national security of the United States by safely staging plutonium pits in a manner that protects the health and safety of employees, the public, and the environment. PMID:10527158

  19. 77 FR 2718 - CPV Cimarron Renewable Energy Company, LLC; Supplemental Notice That Initial Market-Based Rate...

    Science.gov (United States)

    2012-01-19

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY Federal Energy Regulatory Commission CPV Cimarron Renewable Energy Company, LLC; Supplemental Notice That Initial... notice in the above-referenced proceeding of CPV Cimarron Renewable Energy Company, LLC's application...

  20. 77 FR 23476 - Cimarron Windpower II, LLC; Supplemental Notice That Initial Market-Based Rate Filing Includes...

    Science.gov (United States)

    2012-04-19

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Cimarron Windpower II, LLC; Supplemental Notice That Initial Market-Based... above-referenced proceeding of Cimarron Windpower II, LLC's application for market-based rate...

  1. 75 FR 16098 - Southern Turner Cimarron I, LLC; Supplemental Notice That Initial Market-Based Rate Filing...

    Science.gov (United States)

    2010-03-31

    ... From the Federal Register Online via the Government Publishing Office ] DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Southern Turner Cimarron I, LLC; Supplemental Notice That Initial... supplemental notice in the above-referenced proceeding of Southern Turner Cimarron I, LLC's application...

  2. Effects Influencing Plutonium-Absorber Interactions and Distributions in Routine and Upset Waste Treatment Plant Operations

    Energy Technology Data Exchange (ETDEWEB)

    Delegard, Calvin H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sinkov, Sergey I. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Fiskum, Sandra K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-05-01

    This report is the third in a series of analyses written in support of a plan to revise the Hanford Waste Treatment and Immobilization Plant (WTP) Preliminary Criticality Safety Evaluation Report (CSER) that is being implemented at the request of the U.S. Department of Energy (DOE) Criticality Safety Group. A report on the chemical disposition of plutonium in Hanford tank wastes was prepared as Phase 1 of this plan (Delegard and Jones 2015). Phase 2 is the provision of a chemistry report to describe the potential impacts on criticality safety of waste processing operations within the WTP (Freer 2014). In accordance with the request from the Environmental and Nuclear Safety Department of the WTP (Miles and Losey 2012), the Phase 2 report assessed the potential for WTP process conditions within and outside the range of normal control parameters to change the ratio of fissile material to neutron-absorbing material in the waste as it is processed with an eye towards potential implications for criticality safety. The Phase 2 study also considered the implications should WTP processes take place within the credible range of chemistry upset conditions. In the present Phase 3 report, the 28 phenomena described in the Phase 2 report were considered with respect to the disposition of plutonium and various absorber elements. The phenomena identified in the Phase 2 report are evaluated in light of the Phase 1 report and other resources to determine the impacts these phenomena might have to alter the plutonium/absorber dispositions and ratios. The outcomes of the Phase 3 evaluations then can be used to inform subsequent engineering decisions and provide reasonable paths forward to mitigate or overcome real or potential criticality concern in plant operations.

  3. Effects Influencing Plutonium-Absorber Interactions and Distributions in Routine and Upset Waste Treatment Plant Operations

    International Nuclear Information System (INIS)

    This report is the third in a series of analyses written in support of a plan to revise the Hanford Waste Treatment and Immobilization Plant (WTP) Preliminary Criticality Safety Evaluation Report (CSER) that is being implemented at the request of the U.S. Department of Energy (DOE) Criticality Safety Group. A report on the chemical disposition of plutonium in Hanford tank wastes was prepared as Phase 1 of this plan (Delegard and Jones 2015). Phase 2 is the provision of a chemistry report to describe the potential impacts on criticality safety of waste processing operations within the WTP (Freer 2014). In accordance with the request from the Environmental and Nuclear Safety Department of the WTP (Miles and Losey 2012), the Phase 2 report assessed the potential for WTP process conditions within and outside the range of normal control parameters to change the ratio of fissile material to neutron-absorbing material in the waste as it is processed with an eye towards potential implications for criticality safety. The Phase 2 study also considered the implications should WTP processes take place within the credible range of chemistry upset conditions. In the present Phase 3 report, the 28 phenomena described in the Phase 2 report were considered with respect to the disposition of plutonium and various absorber elements. The phenomena identified in the Phase 2 report are evaluated in light of the Phase 1 report and other resources to determine the impacts these phenomena might have to alter the plutonium/absorber dispositions and ratios. The outcomes of the Phase 3 evaluations then can be used to inform subsequent engineering decisions and provide reasonable paths forward to mitigate or overcome real or potential criticality concern in plant operations.

  4. Dry alcohol production plant

    Directory of Open Access Journals (Sweden)

    Stanković Mirjana S.

    2003-01-01

    Full Text Available The IGPC Engineering Department designed basic projects for dry alcohol production plant, using technology developed in the IGPC laboratories. Several projects were completed: technological, machine, electrical, automation. On the basis of these projects a production plant with a capacity of 40 m3/y was manufactured, at "Zorka Pharma", Šabac in 1995-1996. The product meets all quality demands, as well as environmental regulations. The dry alcohol production process is fully automatized. There is no waste in the process, neither gaseous, nor liquid. The chosen process provides safe operation according to temperature regime and resistance in the pipes, air purification columns and filters. Working at increased pressure is suitable for evaporation and condensation at increased temperatures. The production process can be controlled manually, which is necessary during start-up, and repairs.

  5. Introduction to Decommissioning of Plutonium Production Reactors%钚生产堆退役简介

    Institute of Scientific and Technical Information of China (English)

    王永仙; 安凯媛; 刘东

    2013-01-01

      简要阐述几个国家钚生产堆的退役情况,以期对我国今后生产堆的退役提供借鉴。%  The paper provides briefly the information on the decommissiong of plutonium production reactors in several countries across the world and some suggestions for possible future decommissioning of production reac -tors in our country .

  6. Update on the Department of Energy's 1994 plutonium vulnerability assessment for the plutonium finishing plant

    Energy Technology Data Exchange (ETDEWEB)

    HERZOG, K.R.

    1999-09-01

    A review of the environmental, safety, and health vulnerabilities associated with the continued storage of PFP's inventory of plutonium bearing materials and other SNM. This report re-evaluates the five vulnerabilities identified in 1994 at the PFP that are associated with SNM storage. This new evaluation took a more detailed look and applied a risk ranking process to help focus remediation efforts.

  7. Water bath and air bath calorimeter qualification for measuring 3013 containers of plutonium oxide at the Hanford Plutonium Finishing Plant (PFP)

    International Nuclear Information System (INIS)

    The purpose of this paper is to present qualification data generated from water and air-bath calorimeters measuring radioactive decay heat from plutonium oxide in DOE STD-3013-2000 (3013) containers at the Hanford Plutonium Finishing Plant (PFP). Published data concerning air and water bath calorimeters and especially 3013-qualified calorimeters is minimal at best. This paper will address the data from the measurement/qualification test plan, the heat standards used, and the calorimeter precision and accuracy results. The 3013 package is physically larger than earlier plutonium oxide storage containers, thereby necessitating a larger measurement chamber. To accommodate the measurements of the 3013 containers at PFP, Los Alamos National Laboratory (LANL) supplied a water bath dual-chambered unit and the Savannah River Technology Center (SRTC) provided two air-bath calorimeters. Both types of Calorimeters were installed in the analytical laboratory at PFP. The larger 3013 containers presented a new set of potential measurement problems: longer counting times, heat conductivity through a much larger container mass and wall thickness, and larger amounts of copper shot to assist sample thermal conductivity. These potential problems were addressed and included in the measurement/qualification test plan

  8. Furnace System Testing to Support Lower-Temperature Stabilization of High Chloride Plutonium Oxide Items at the Hanford Plutonium Finishing Plant

    International Nuclear Information System (INIS)

    High chloride content plutonium (HCP) oxides are impure plutonium oxide scrap which contains NaCl, KCl, MgCl2 and/or CaCl2 salts at potentially high concentrations and must be stabilized at 950 C per the DOE Standard, DOE-STD-3013-2000. The chlorides pose challenges to stabilization because volatile chloride salts and decomposition products can corrode furnace heating elements and downstream ventilation components. Thermal stabilization of HCP items at 750 C (without water washing) is being investigated as an alternative method for meeting the intent of DOE STD 3013-2000. This report presents the results from a series of furnace tests conducted to develop material balance and system operability data for supporting the evaluation of lower-temperature thermal stabilization

  9. Functional design criteria for the 242-A evaporator and PUREX [Plutonium-Uranium Extraction] Plant condensate interim retention basin

    International Nuclear Information System (INIS)

    This document contains the functional design criteria for a 26- million-gallon retention basin and 10 million gallons of temporary storage tanks. The basin and tanks will be used to store 242-A Evaporator process condensate, the Plutonium-Uranium Extraction (PUREX) Plant process distillate discharge stream, and the PUREX Plant ammonia scrubber distillate stream. Completion of the project will allow both the 242-A Evaporator and the PUREX Plant to restart. 4 refs

  10. Plutonium fuel program

    International Nuclear Information System (INIS)

    The project is concerned with developing an advanced method to produce nuclear reactor fuels. Since 1968 EIR has worked successfully on the production of uranium-plutonium mixed carbide using wet gelation chemistry. An important part of the development is irradiating the fuel in materials test reactors and evaluating its performance. During 1979 the programme continued with principal activities of fuel fabrication development, preparation for irradiation testing, performance evaluation, and modelling and plant engineering. (Auth.)

  11. Plutonium age dating (production date measurement) by inductively coupled plasma mass spectrometry

    OpenAIRE

    Varga, Zsolt; Nicholl, Adrian; Wallenius, Maria; Mayer, Klaus

    2015-01-01

    This paper describes rapid methods for the determination of the production date (age dating) of plutonium (Pu) materials by inductively coupled plasma mass spectrometry (ICP-MS) for nuclear forensic and safeguards purposes. One of the presented methods is a rapid, direct measurement without chemical separation using 235U/239Pu and 236U/240Pu chronometers. The other method comprises a straightforward extraction chromatographic separation, followed by ICP-MS measurement for the 234U/238Pu, 235U...

  12. Terrestrial plant methane production

    DEFF Research Database (Denmark)

    Mikkelsen, Teis Nørgaard; Bruhn, Dan; Møller, Ian M.;

    We evaluate all experimental work published on the phenomenon of aerobic methane (CH4) generation in terrestrial plants. We conclude that the phenomenon is true. Four stimulating factors have been observed to induce aerobic plant CH4 production, i.e. cutting injuries, increasing temperature...... into consideration other potential sources than pectin. Due to the large uncertainties related to effects of stimulating factors, genotypic responses and type of precursors, we conclude that current attempts for upscaling aerobic CH4 into a global budget is insufficient. Thus it is too early to draw the line under...

  13. The Creative Application of Science, Technology and Work Force Innovations to the Decontamination and Decommissioning of the Plutonium Finishing Plant at the Hanford Nuclear Reservation

    International Nuclear Information System (INIS)

    The Plutonium Finishing Plant (PFP) consists of a number of process and support buildings for handling plutonium. Building construction began in the late 1940's to meet national priorities and became operational in 1950 producing refined plutonium salts and metal for the United States nuclear weapons program The primary mission of the PFP was to provide plutonium used as special nuclear material for fabrication into a nuclear device for the war effort. Subsequent to the end of World War II, the PFP's mission expanded to support the Cold War effort through plutonium production during the nuclear arms race. PFP has now completed its mission and is fully engaged in deactivation, decontamination and decommissioning (D and D). At this time the PFP buildings are planned to be reduced to ground level (slab-on-grade) and the site remediated to satisfy national, Department of Energy (DOE) and Washington state requirements. The D and D of a highly contaminated plutonium processing facility presents a plethora of challenges. PFP personnel approached the D and D mission with a can-do attitude. They went into D and D knowing they were facing a lot of challenges and unknowns. There were concerns about the configuration control associated with drawings of these old process facilities. There were unknowns regarding the location of electrical lines and the condition and contents of process piping containing chemical residues such as strong acids and caustics. The gloveboxes were highly contaminated with plutonium and chemical residues. Most of the glovebox windows were opaque with splashed process chemicals that coated the windows or etched them, reducing visibility to near zero. Visibility into the glovebox was a serious worker concern. Additionally, all the gloves in the gloveboxes were degraded and unusable. Replacing gloves in gloveboxes was necessary to even begin glovebox clean-out. The sheer volume of breathing air needed was also an issue. These and other challenges and PFP

  14. On-line monitoring of plutonium in mixed uranium-plutonium solutions

    International Nuclear Information System (INIS)

    The measurement of the total and isotopic plutonium concentrations in mixed uranium-plutonium solutions blended with highly radioactive fission product nuclides and other radionuclides (e.g., Cs-137 and Co-60) has been investigated at the Barnwell Nuclear Fuel Plant (BNFP). An on-line total and isotopic plutonium monitoring system is being tested for its ability to assay the plutonium abundances in solutions as might be found in the process streams of a light water reactor (LWR) spent fuel processing plant. The monitoring system is fully automated and designed to be maintained remotely. It is capable of near real-time inventory of plutonium in process streams and provides the basis for on-line computerized accounting of special nuclear materials

  15. The uptake of plutonium-239, 240, americium-241, strontium-90 into plants

    International Nuclear Information System (INIS)

    This report describes the results of measurements on the uptake of plutonium, americium, strontium-90 and caesium-137 into peas, beet, oats, sweet corn, tomatoes and vegetable marrow grown in tubs containing radioactively-contaminated silts. The silts had been taken from an area of West Cumbria commonly referred to as the Ravenglass estuary. The experiments are categorised as being carried out under non-standard conditions because of the manner in which the radioactivity came to be incorporated into the growth medium. The growth medium was representative of conditions which could arise when the estuarine silt moves inland under the influence of wind and tide and mixes with the adjacent farm land. The silt had been contaminated by radioactive effluents from the nuclear fuels reprocessing plant at Sellafield and this contamination had been brought about by natural means. (Auth.)

  16. Plutonium age dating (production date measurement) by inductively coupled plasma mass spectrometry

    International Nuclear Information System (INIS)

    This paper describes rapid methods for the determination of the production date (age dating) of plutonium (Pu) materials by inductively coupled plasma mass spectrometry (ICP-MS) for nuclear forensic and safeguards purposes. One of the presented methods is a rapid, direct measurement without chemical separation using 235U/239Pu and 236U/240Pu chronometers. The other method comprises a straightforward extraction chromatographic separation, followed by ICP-MS measurement for the 234U/238Pu, 235U/239Pu, 236U/240Pu and 238U/242Pu chronometers. Age dating results of two plutonium certified reference materials (SRM 946 and 947, currently distributed as NBL CRM 136 and 137) are in good agreement with the archive purification dates. (author)

  17. Nondestructive assay methods for solids containing plutonium

    International Nuclear Information System (INIS)

    Specific nondestructive assay (NDA) methods, e.g. calorimetry, coincidence neutron counting, singles neutron counting, and gamma ray spectrometry, were studied to provide the Savannah River Plant with an NDA method to measure the plutonium content of solid scrap (slag and crucible) generated in the JB-Line plutonium metal production process. Results indicate that calorimetry can be used to measure the plutonium content to within about 3% in 4 to 6 hours by using computerized equilibrium sample power predictive models. Calorimetry results confirm that a bias exists in the present indirect measurement method used to estimate the plutonium content of slag and crucible. Singles neutron counting of slag and crucible can measure plutonium to only +-30%, but coincidence neutron counting methods improve measurement precision to better than +-10% in less than ten minutes. Only four portions of a single slag and crucible sample were assayed, and further study is recommended

  18. Stop plutonium; Stop plutonium

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-02-01

    This press document aims to inform the public on the hazards bound to the plutonium exploitation in France and especially the plutonium transport. The first part is a technical presentation of the plutonium and the MOX (Mixed Oxide Fuel). The second part presents the installation of the plutonium industry in France. The third part is devoted to the plutonium convoys safety. The highlight is done on the problem of the leak of ''secret'' of such transports. (A.L.B.)

  19. Plan for the Startup of HA-21I Furnace Operations at the Plutonium Finishing Plant (PFP)

    International Nuclear Information System (INIS)

    Achievement of Thermal Stabilization mission elements require the installation and startup of three additional muffle furnaces for the thermal stabilization of plutonium and plutonium bearing materials at the Plutonium Finishing Plant (PFP). The release to operate these additional furnaces will require an Activity Based Startup Review. The conduct of the Activity Based Startup Review (ABSR) was approved by Fluor Daniel Hanford on October 15, 1999. This plan has been developed with the objective of identifying those activities needed to guide the controlled startup of five furnaces from authorization to unrestricted operations by adding the HA-211 furnaces in an orderly and safe manner after the approval to Startup has been given. The Startup Plan provides a phased approach that bridges the activities between the completion of the Activity Based Startup Review authorizing the use of the three additional furnaces and the unrestricted operation of the five thermal stabilization muffle furnaces. The four phases are: (1) the initiation of five furnace operations using three empty (simulated full) boat charges from HA-211 and two full charges from HC-21C; (2) three furnace operations (one full charge from HA-211 and two full charges from HC-21C); (3) four furnace operations (two full charges from HA-211 and two full charges from HC-21C); and (4) integrated five furnace operations and unrestricted operations. Phase 1 of the Plan will be considered as the cold runs. This Plan also provides management oversight and administrative controls that are to be implemented until unrestricted operations are authorized. It also provides a formal review process for ensuring that all preparations needed for full five furnace operations are completed and formally reviewed prior to proceeding to the increased activity levels associated with five furnace operations. Specific objectives include: (1) To ensure that activities are conducted in a safe manner. (2) To provide supplemental

  20. Summary of Plutonium-238 Production Alternatives Analysis Final Report

    Energy Technology Data Exchange (ETDEWEB)

    James Werner; Wade E. Bickford; David B. Lord; Chadwick D. Barklay

    2013-03-01

    The Team implemented a two-phase evaluation process. During the first phase, a wide variety of past and new candidate facilities and processing methods were assessed against the criteria established by DOE for this assessment. Any system or system element selected for consideration as an alternative within the project to reestablish domestic production of Pu-238 must meet the following minimum criteria: Any required source material must be readily available in the United States, without requiring the development of reprocessing technologies or investments in systems to separate material from identified sources. It must be cost, schedule, and risk competitive with existing baseline technology. Any identified facilities required to support the concept must be available to the program for the entire project life cycle (notionally 35 years, unless the concept is so novel as to require a shorter duration). It must present a solution that can generate at least 1.5 Kg of Pu-238 oxide per year, for at least 35 years. It must present a low-risk, near-term solution to the National Aeronautics and Space Administration’s urgent mission need. DOE has implemented this requirement by eliminating from project consideration any alternative with key technologies at less than Technology Readiness Level 5. The Team evaluated the options meeting these criteria using a more detailed assessment of the reasonable facility variations and compared them to the preferred option, which consists of target irradiation at the Advanced Test Reactor (ATR) and the High Flux Isotope Reactor (HFIR), target fabrication and chemical separations processing at the ORNL Radiochemical Engineering Development Center, and neptunium 237 storage at the Materials and Fuels Complex at INL. This preferred option is consistent with the Records of Decision from the earlier National Environmental Policy Act (NEPA) documentation

  1. Method of reprocessing of irradiated nuclear fission products of the uranium, plutonium and thorium group

    International Nuclear Information System (INIS)

    A solvent extraction is used to separate irradiated nuclear fission materials of the group uranium, plutonium, thorium from radioactive fission products which are present together in an aqueous solution. An improvement on the known mehod is proposed in which a carboxylic nitrile, carboxylic ester, carboxylic amide, or a mixture of these substances is added to the organic phase which is mixed with a non-polar diluting agent as a polar modificator, where the modificators are derived from mono- or polycarboxylic acids or also from substituted carboxylic acids. Amyl acetate, N-N dimethyl caprylic acid amide, and adiponitrile are particularly suitable. (UW/LH)

  2. Experience gained with nuclear material accounting and control in storage facility for plutonium dioxide of SChK radiochemical plant

    International Nuclear Information System (INIS)

    The task for the computerized accounting of containers at the storage with barcoding equipment for inventory taking has been performed at achieve the pre-commissioning phase. This gave the following upgrade: decrease of the time spent by the personnel in storage compartments with plutonium dioxide during inventory taking, this diminishing the dose for personnel; changeover from traditional record book to computerized accounting of nuclear materials at the storage, which will make it possible to include the local workstation of the storage into computer network for nuclear material (NM) accounting at the Radiochemical plant; test and improve technique for the use of barcoding equipment for further introduction at plants and storage facilities of the SChK. Works are underway for further improvement of the NM accounting at the storage for plutonium dioxide

  3. Plutonium use - Present status and prospects

    International Nuclear Information System (INIS)

    The use of plutonium in thermal and fast reactors is a demonstrated, if not proven, technology. Moreover, plutonium is being produced in increasing quantities. Evaluation of this production on a world scale shows that it would be theoretically possible to construct numerous breeders and thus to make the best use of plutonium, while considerably reducing uranium consumption. This source of plutonium is nevertheless dependent on the reprocessing of irradiated fuel. Long delays in installing and adequate world reprocessing capacity are weakening the prospects for introducing breeders. Furthermore, the critical situation regarding reprocessing may delay the development of complementary reprocessing methods for fuels with a high plutonium content and high burnup. The recycling of plutonium is now a well-known technique and any objections to it hardly bear analysis. Utilization of plutonium offers an appreciable saving in terms of uranium and separative work units; and it can also be shown that immediate reprocessing of the recycling fuel is not essential for the economics of the concept. Temporary storage of recycled fuel is a particularly safe form of concentrating plutonium, namely in irradiated plutonium-bearing fuel assemblies. Finally, recycling offers such flexibility that it represents no obstacle to fuel management at power plants with light-water reactors. These strategic considerations imply that the technology of using plutonium for fabricating thermal or fast reactor fuels is both technically reliable and economically viable. The methods used in industrial facilities are fully reassuring in this respect. Although various unsolved problems exist, none seems likely to impede current developments, while the industrial experience gained has enabled the economics and reliability of the methods to be improved appreciably. Apart from the techno-economic aspects, the plutonium industry must face extremely important problems in connection with the safety of personnel

  4. Estimate of airborne release of plutonium from Babcock and Wilcox plant as a result of severe wind hazard and earthquake

    Energy Technology Data Exchange (ETDEWEB)

    Mishima, J.; Schwendiman, L.C.; Ayer, J.E.

    1978-10-01

    As part of an interdisciplinary study to evaluate the potential radiological consequences of wind hazard and earthquake upon existing commercial mixed oxide fuel fabrication plants, the potential mass airborne releases of plutonium (source terms) from such events are estimated. The estimated souce terms are based upon the fraction of enclosures damaged to three levels of severity (crush, puncture penetrate, and loss of external filter, in order of decreasing severity), called damage ratio, and the airborne release if all enclosures suffered that level of damage. The discussion of damage scenarios and source terms is divided into wind hazard and earthquake scenarios in order of increasing severity. The largest airborne releases from the building were for cases involving the catastrophic collapse of the roof over the major production areas--wind hazard at 110 mph and earthquakes with peak ground accelerations of 0.20 to 0.29 g. Wind hazards at higher air velocities and earthquakes with higher ground acceleration do not result in significantly greater source terms. The source terms were calculated as additional mass of respirable particles released with time up to 4 days; and, under these assumptions, approximately 98% of the mass of material of concern is made airborne from 2 h to 4 days after the event. The overall building source terms from the damage scenarios evaluated are shown in a table. The contribution of individual areas to the overall building source term is presented in order of increasing severity for wind hazard and earthquake.

  5. Radioactive Air Emission Notice of Construction (NOC) for Plutonium Finishing Plant (PFP) Project W-460 Plutonium Stabilization and Handling

    Energy Technology Data Exchange (ETDEWEB)

    JANSKY, M.T.

    2000-05-01

    The following description and any attachments and references are provided to the Washington State Department of Health (WDOH), Division of Radiation Protection, Air Emissions & Defense Waste Section as a notice of construction (NOC) in accordance with Washington Administrative Code (WAC) 246-247, Radiation Protection-Air Emissions. The WAC 246-247-060, ''Applications, registration, and licensing'', states ''This section describes the information requirements for approval to construct, modify, and operate an emission unit. Any NOC requires the submittal of information listed in Appendix A.'' Additionally, the following description, attachments, and references are provided to the US Environmental Protection Agency (EPA) as an NOC, in accordance with Title 40 Code of Federal Regulations (CFR), Part 61, ''National Emission Standards for Hazardous Air Pollutants''. The information required for submittal to the EPA is specified in 40 CFR 61.07. The potential emissions from this activity are estimated to provide greater than 0.1 millirem year total effective dose equivalent (TEDE) to the hypothetical offsite maximally exposed individual (MEI) and commencement is needed within a short time. Therefore, this application also is intended to provide notification of the anticipated date of initial startup in accordance with the requirement listed in 40 CFR 61.09(a)(1), and it is requested that approval of this application also constitutes EPA acceptance of this initial startup notification. Written notification of the actual date of initial startup, in accordance with the requirement listed in 40 CFR 61.09(a)(2), will be provided later. This NOC covers the activities associated with the construction and operation activities involving stabilization and/or repackaging of plutonium in the 2736-ZB Building. A new exhaust stack will be built and operated at the 2736-ZB Building to handle the effluents associated with the

  6. Radioactive Air Emission Notice of Construction for (NOC) Plutonium Finishing Plant (PFP) Project W-460 Plutonium Stabilization and Handling

    International Nuclear Information System (INIS)

    The following description and any attachments and references are provided to the Washington State Department of Health (WDOH), Division of Radiation Protection, Air Emissions and Defense Waste Section as a notice of construction (NOC) in accordance with Washington Administrative Code (WAC) 246-247, Radiation Protection-Air Emissions. The WAC 246-247-060, ''Applications, registration, and licensing'', states ''This section describes the information requirements for approval to construct, modify, and operate an emission unit. Any NOC requires the submittal of information listed in Appendix A,'' Appendix A (WAC 246-247-1 IO) lists the requirements that must be addressed. Additionally, the following description, attachments, and references are provided to the U.S. Environmental Protection Agency (EPA) as an NOC, in accordance with Title 40 Code of Federal Regulations (CFR), Part 61, ''National Emission Standards for Hazardous Air Pollutants.'' The information required for submittal to the EPA is specified in 40 CFR 61.07. The potential emissions from this activity are estimated to provide greater than 0.1 millirem year total effective dose equivalent (TEDE) to the hypothetical offsite maximally exposed individual (MEI) and commencement is needed within a short time. Therefore, this application also is intended to provide notification of the anticipated date of initial startup in accordance with the requirement listed in 40 CFR 61.09(a)(1), and it is requested that approval of this application also constitutes EPA acceptance of this initial startup notification. Written notification of the actual date of initial startup, in accordance with the requirement listed in 40 CFR 61.09(a)(2), will be provided later. This NOC covers the activities associated with the construction and operation activities involving stabilization and/or repackaging of plutonium in the 2736-ZB Building. An operations support trailer will be installed in the proximity of the 2736-ZB Building. A new

  7. Study of the formation, prevention, and recovery of plutonium from plutonium esters in the Purex process

    International Nuclear Information System (INIS)

    The Savannah River Plant uses the basic Purex process to separate 239Pu from 238U and fission products. Dark-brown, dense solids containing up to 30% Pu have previously occurred in rotameters in the plutonium finishing operations. The kinetics of formation of this mixture of DBP- and MBP-Pu esters suggest two methods to prevent the formation of the solids. A selective dissolution method using NaOH metathesis has been developed to separate the phosphate ester from the plutonium before dissolution of the residual plutonium hydroxide in a HNO3-HF medium

  8. Solutions to criticality problems in a plutonium extraction plant; Solutions apportees aux problemes de criticite d'une usine d'extraction du plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Jouannaud, C.; Rodier, J.; Fruchard, Y.; Peyresblanques, H.; Papault, C.; Tabardel-Brian, R. [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule, service d' extraction du plutonium, service de protection contre les radiations et d' assainissement radioactif

    1968-08-01

    There are two aspects to nuclear criticality safety: prevention of criticality and protection against the consequences of a possible accident: this report considers these two aspects in the case of the Marcoule Plutonium Extraction Plant. After briefly recalling the various techniques used for avoiding criticality (mass, geometry, concentration, poisoning), the authors describe their application in the plant and show in particular that, a rational use of a favorable geometry is a factor both for security and from an economic point of view. The authors then describe the inside organisation which makes it possible to obtain the necessary intrinsic safety standard right from the advance project stage, and to control the workshop safety during the operation of the plant. The second part of the report deals with the system of protection against the consequences of a possible accident: definition of a typical accident, fixing of the boundaries of a critical zone, safety alarm device, individual and collective dosimetry, evacuation plan and safety instructions. (authors) [French] La securite vis-a-vis des risques de criticite revet deux aspects: la prevention de la criticite et la protection contre les consequences d'un accident eventuel: le present rapport developpe ces deux aspects dans le cas de l'Usine d'Extraction du Plutonium de Marcoule. Apres avoir rappele les differentes techniques de prevention de la criticite (masse, geometrie, concentration, empoisonnement), les auteurs decrivent leur application a l'Usine et montrent notamment que l'utilisation rationnelle de la geometrie favorable est un double facteur de securite et d'economie. Les auteurs decrivent ensuite l'organisation interieure qui permet de realiser la securite intrinseque des le stade d'un avant projet et de controler la securite des ateliers au cours de la vie de l'Usine. La deuxieme partie du rapport est consacree au systeme de protection contre les

  9. Plutonium, americium and radiocaesium in the marine environment close to the Vandellos I nuclear power plant before decommissioning

    International Nuclear Information System (INIS)

    The Vandellos nuclear power plant (NPP), releasing low-level radioactive liquid waste to the Mediterranean Sea, is the first to be decommissioned in Spain, after an incident which occurred in 1989. The presence, distribution and uptake of various artificial radionuclides (radiocaesium, plutonium and americium) in the environment close to the plant were studied in seawater, bottom sediments and biota, including Posidonia oceanica, fish, crustaceans and molluscs. Seawater, sediments and Posidonia oceanica showed enhanced levels in the close vicinity of the NPP, although the effect was restricted to its near environment. Maximum concentrations in seawater were 11.6±0.5 Bq m-3 and 16.9±1.2 mBq m-3 for 137Cs and 239,240Pu, respectively. When sediment concentrations were normalized to excess 210Pb, they showed both the short-distance transport of artificial radionuclides from the Vandellos plant and the long-distance transport of 137Cs from the Asco NPP. Posidonia oceanica showed the presence of various gamma-emitters attributed to the impact of the Chernobyl accident, on which the effect of the NPP was superimposed. Seawater, sediment and Posidonia oceanica collected near the plant also showed an enhancement of the plutonium isotopic ratio above the fallout value. The uptake of these radionuclides by marine organisms was detectable but limited. Pelagic fish showed relatively higher 137Cs concentrations and only in the case of demersal fish was the plutonium isotopic ratio increased. The reported levels constitute a set of baseline values against which the impact of the decommissioning operations of the Vandellos I NPP can be studied

  10. Systems work for Plutonium Fuel Production Facility (PFPF) near-real-time accounting

    International Nuclear Information System (INIS)

    A joint effort by the Los Alamos National Laboratory and the Power Reactor and Nuclear Fuel Development Corporation of Japan examines materials accounting for the Plutonium Fuel Production Facility. A unique feature of the systems work is a sophisticated data generator. This software follows individual items throughout the process, creating detailed data files for variance propagation. The data generator deals with user-specified process operations and handles related accounting problems, such as the tracking of individual measurements through numerous blending and splitting procedure, frequent decay correction (important for large inventories), scrap recovery, and automated determination of static inventory. There is no need to rely on simplified assumptions regarding process operation and material measurement. Also, the joint study applies recent theoretical work on stratified inspection of nonhomogeneous inventories and sequential analysis of MUF -- D. 4 refs

  11. Plutonium behavior during the early diagenesis of marine sediments: applications to two marine environments labelled by radionuclides released from reprocessing plants

    International Nuclear Information System (INIS)

    The plutonium released into the English Channel and the Irish Sea by nuclear fuel reprocessing plants is mainly associated to sediments. Nevertheless, this association is partially reversible. This work combines a field study, carried out on the Cumbrian mud patch and the Esk estuary (Eastern Irish Sea), and laboratory experiments performed on carbonaceous coarse-grained sediments collected in the Central Channel. It presents new data on the plutonium solid partition in sediments and suggests realistic scenarios for describing its release from sediments to the water column. The role of reactive sulphides acting as temporary sink phases is shown in anoxic sediments; those sulphides are liable to release dissolved plutonium upon their oxidation. The plutonium is also bound to carbonates within the carbonaceous matrix and as carbonate surface complexes. Conceptual schemes of the behaviour of the plutonium in marine sediments are proposed; they highlight the strong remobilization potential of plutonium from marine sediments to the interstitial water. Its plutonium content can be injected into the overlying water column. (author)

  12. Notice of Construction (NOC) Application for Criteria and Toxic Air Pollutant Emissions from Thermal Stabilization of Polycubes at the Plutonium Finishing Plant (PFP)

    International Nuclear Information System (INIS)

    This is a notice of construction (NOC) application for thermal stabilization of plutonium in a polystyrene matrix (polycubes) in the muffle furnaces at the Plutonium Finishing Plant (PFP). This NOC application is required by Washington Administrative Code (WAC) 173-460-040. During the 1960's and 1970's, polycubes were thermally stabilized using a pyrolysis process at PFP. The proposed process of thermal stabilization of polycubes in muffle furnaces results in emissions of air contaminants not emitted since implementation of WAC 173-460 (effective 9/18/91). The new process and related air contaminants are the basis for this NOC application. The proposed activity would use the muffle furnaces in the 234-52 Building to stabilize polycubes. The resulting plutonium oxides would be packaged to meet storage requirements specified in Stabilization, Packaging, and Storage of Plutonium Bearing Materials (DOE-STD-3013). The PFP is located in the 200 West Area of the Hanford Site. The PFP consists of several large and small buildings that are grouped to form the processing complex. The PFP activities are focused on the stabilization of plutonium-bearing materials to a form suitable for long-term storage; immobilization of residual plutonium-bearing materials; and removal of readily retrievable, plutonium-bearing materials left behind in process equipment and process areas

  13. Plutonium release from Fukushima Daiichi fosters the need for more detailed investigations

    OpenAIRE

    Stephanie Schneider; Clemens Walther; Stefan Bister; Viktoria Schauer; Marcus Christl; Hans-Arno Synal; Katsumi Shozugawa; Georg Steinhauser

    2013-01-01

    The contamination of Japan after the Fukushima accident has been investigated mainly for volatile fission products, but only sparsely for actinides such as plutonium. Only small releases of actinides were estimated in Fukushima. Plutonium is still omnipresent in the environment from previous atmospheric nuclear weapons tests. We investigated soil and plants sampled at different hot spots in Japan, searching for reactor-borne plutonium using its isotopic ratio 240Pu/239Pu. By using accelerator...

  14. Properties of plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Jin Su; Yoon, Hwan Ki; Min, Kyung Sik; Kim, Hyun Tae; Ahn, Jong Sung; Kwag, Eon Ho; Ryu, Keon Joong [Korea Atomic Energy Research Institute, Daeduk (Korea, Republic of)

    1996-03-01

    Plutonium has unique chemical and physical properties. Its uniqueness in use has led to rare publications, in Korea. This report covers physical aspects of phase change of metal plutonium, mechanical properties, thermal conductivity, etc, chemical aspects of corrosion, oxidation, how to produce plutonium from spent fuels by describing various chemical treatment methods, which are currently used and were used in the past. It also contains characteristics of the purex reprocessing process which is the most widely used nowadays. And show processes to purify and metalize from recovered plutonium solution. Detection and analysis methods are introduced with key pints for handling, critical safety, toxicity, and effects on peoples. This report gives not only a general idea on what plutonium is, rather than deep technical description, but also basic knowledge on plutonium production and safeguards diversion from the view point of nonproliferation. 18 refs. (Author) .new.

  15. PLUTONIUM FINISHING PLANT (PFP) 241-Z LIQUID WASTE TREATMENT FACILITY DEACTIVATION AND DEMOLITION

    International Nuclear Information System (INIS)

    Fluor Hanford, Inc. (FH) is proud to submit the Plutonium Finishing Plant (PFP) 241-Z liquid Waste Treatment Facility Deactivation and Demolition (D and D) Project for consideration by the Project Management Institute as Project of the Year for 2008. The decommissioning of the 241-Z Facility presented numerous challenges, many of which were unique with in the Department of Energy (DOE) Complex. The majority of the project budget and schedule was allocated for cleaning out five below-grade tank vaults. These highly contaminated, confined spaces also presented significant industrial safety hazards that presented some of the most hazardous work environments on the Hanford Site. The 241-Z D and D Project encompassed diverse tasks: cleaning out and stabilizing five below-grade tank vaults (also called cells), manually size-reducing and removing over three tons of process piping from the vaults, permanently isolating service utilities, removing a large contaminated chemical supply tank, stabilizing and removing plutonium-contaminated ventilation ducts, demolishing three structures to grade, and installing an environmental barrier on the demolition site . All of this work was performed safely, on schedule, and under budget. During the deactivation phase of the project between November 2005 and February 2007, workers entered the highly contaminated confined-space tank vaults 428 times. Each entry (or 'dive') involved an average of three workers, thus equaling approximately 1,300 individual confined -space entries. Over the course of the entire deactivation and demolition period, there were no recordable injuries and only one minor reportable skin contamination. The 241-Z D and D Project was decommissioned under the provisions of the 'Hanford Federal Facility Agreement and Consent Order' (the Tri-Party Agreement or TPA), the 'Resource Conservation and Recovery Act of 1976' (RCRA), and the 'Comprehensive Environmental Response, Compensation, and Liability Act of 1980

  16. PLUTONIUM FINISHING PLANT (PFP) 241-Z LIQUID WASTE TREATMENT FACILITY DEACTIVATION AND DEMOLITION

    Energy Technology Data Exchange (ETDEWEB)

    JOHNSTON GA

    2008-01-15

    Fluor Hanford, Inc. (FH) is proud to submit the Plutonium Finishing Plant (PFP) 241-Z liquid Waste Treatment Facility Deactivation and Demolition (D&D) Project for consideration by the Project Management Institute as Project of the Year for 2008. The decommissioning of the 241-Z Facility presented numerous challenges, many of which were unique with in the Department of Energy (DOE) Complex. The majority of the project budget and schedule was allocated for cleaning out five below-grade tank vaults. These highly contaminated, confined spaces also presented significant industrial safety hazards that presented some of the most hazardous work environments on the Hanford Site. The 241-Z D&D Project encompassed diverse tasks: cleaning out and stabilizing five below-grade tank vaults (also called cells), manually size-reducing and removing over three tons of process piping from the vaults, permanently isolating service utilities, removing a large contaminated chemical supply tank, stabilizing and removing plutonium-contaminated ventilation ducts, demolishing three structures to grade, and installing an environmental barrier on the demolition site . All of this work was performed safely, on schedule, and under budget. During the deactivation phase of the project between November 2005 and February 2007, workers entered the highly contaminated confined-space tank vaults 428 times. Each entry (or 'dive') involved an average of three workers, thus equaling approximately 1,300 individual confined -space entries. Over the course of the entire deactivation and demolition period, there were no recordable injuries and only one minor reportable skin contamination. The 241-Z D&D Project was decommissioned under the provisions of the 'Hanford Federal Facility Agreement and Consent Order' (the Tri-Party Agreement or TPA), the 'Resource Conservation and Recovery Act of 1976' (RCRA), and the 'Comprehensive Environmental Response, Compensation, and

  17. Analysis of mdr1-1Δ mutation of MDR1 gene in the “Cimarron Uruguayo” dog

    Directory of Open Access Journals (Sweden)

    Rosa Gagliardi B.

    2013-08-01

    Full Text Available Objective. The aim of this paper is to analyze the frequency of the mdr1-1D mutation of the MDR1 gene in a dog sample of the Uruguayan Cimarron breed with the objective of increasing the knowledge of this breed’s genome. Materials and methods. Thirty-six animals of this breed were analyzed. The MDR1 gene region, which includes the location where the mutation would be present, was amplified by PCR. Results. The mutation was not detected in any of the analyzed Uruguayan Cimarron. Conclusions. The lack of described ivermectin intoxication cases in veterinary clinic in this breed is explained by the lack of the mutation object of this study. The sequence studied in Cimarron dogs is kept compared to other breeds, except Collies and related breeds (Border Collie, Bearded Collie, Old English sheepdog.

  18. Stop plutonium

    International Nuclear Information System (INIS)

    This press document aims to inform the public on the hazards bound to the plutonium exploitation in France and especially the plutonium transport. The first part is a technical presentation of the plutonium and the MOX (Mixed Oxide Fuel). The second part presents the installation of the plutonium industry in France. The third part is devoted to the plutonium convoys safety. The highlight is done on the problem of the leak of ''secret'' of such transports. (A.L.B.)

  19. CARBONATE METHOD OF SEPARATION OF TETRAVALENT PLUTONIUM FROM FISSION PRODUCT VALUES

    Science.gov (United States)

    Duffield, R.B.; Stoughton, R.W.

    1959-02-01

    It has been found that plutonium forms an insoluble precipitate with carbonate ion when the carbonate ion is present in stoichiometric proportions, while an excess of the carbonate ion complexes plutonium and renders it soluble. A method for separating tetravalent plutonium from lanthanum-group rare earths has been based on this discovery, since these rare earths form insoluble carbonates in approximately neutral solutions. According to the process the pH is adjusted to between 5 and 7, and approximately stoichiometric amounts of carbonate ion are added to the solution causing the formation of a precipitate of plutonium carbonate and the lanthanum-group rare earth carbonates. The precipitate is then separated from the solution and contacted with a carbonate solution of a concentration between 1 M and 3 M to complex and redissolve the plutonium precipitate, and thus separate it from the insoluble rare earth precipitate.

  20. Comparison of actinides and fission products recycling scheme with the normal plutonium recycling scheme in fast reactors

    OpenAIRE

    Salahuddin Asif; Iqbal Masood

    2013-01-01

    Multiple recycling of actinides and non-volatile fission products in fast reactors through the dry re-fabrication/reprocessing atomics international reduction oxidation process has been studied as a possible way to reduce the long-term potential hazard of nuclear waste compared to that resulting from reprocessing in a wet PUREX process. Calculations have been made to compare the actinides and fission products recycling scheme with the normal plutonium recycling scheme in a fast reactor....

  1. Production and characterization of monodisperse plutonium, uranium, and mixed uranium-plutonium particles for nuclear safeguard applications.

    Science.gov (United States)

    Ranebo, Y; Niagolova, N; Erdmann, N; Eriksson, M; Tamborini, G; Betti, M

    2010-05-15

    In order to prevent nuclear proliferation, the isotopic analysis of uranium and plutonium microparticles has strengthened the means in international safeguards for detecting undeclared nuclear activities. In order to ensure accuracy and precision in the analytical methodologies used, the instrumental techniques need to be calibrated. The objective of this study was to produce and characterize particles consisting of U, Pu, and mixed U-Pu, suitable for such reliability verifications. A TSI vibrating orifice aerosol generator in connection with a furnace system was used to produce micrometer sized, monodispersed particles from reference U and Pu materials in solution. The particle masses (in the range of 3-6 pg) and sizes (approximately 1.5 microm) were controlled by the experimental conditions and the parameters for the aerosol generator. Size distributions were obtained from scanning electron microscopy, and energy-dispersive X-ray analysis confirmed that the particle composition agreed with the starting material used. A secondary ion mass spectrometer (SIMS) was used to characterize the isotopic composition of the particles. Isobaric and polyatomic interference in the SIMS spectra was identified. In order to obtain accurate estimates of the interference, a batch of Pu particles were produced of mainly (242)Pu. These were used for SIMS analysis to characterize the relative ionization of Pu and U hydride ions and to determine the SIMS useful yields of U and Pu. It was found that U had a higher propensity to form the hydride than Pu. Useful yields were determined at a mass resolution of 450 for U-Pu particles: (1.71 +/- 0.15) % for Pu and (0.72 +/- 0.06) % for U. For Pu particles: (1.65 +/- 0.14) % for Pu. This gave a relative sensitivity factor between U and Pu (RSF(U:Pu)) of 2.4 +/- 0.2. However, the RSF(U:Pu) showed large fluctuations during the sputtering time for each analyses of the mixed U-Pu particles, in the range of 1.9-3.4. PMID:20415437

  2. The Integrated Safety Management System Verification Enhancement Review of the Plutonium Finishing Plant (PFP)

    International Nuclear Information System (INIS)

    The primary purpose of the verification enhancement review was for the DOE Richland Operations Office (RL) to verify contractor readiness for the independent DOE Integrated Safety Management System Verification (ISMSV) on the Plutonium Finishing Plant (PFP). Secondary objectives included: (1) to reinforce the engagement of management and to gauge management commitment and accountability; (2) to evaluate the ''value added'' benefit of direct public involvement; (3) to evaluate the ''value added'' benefit of direct worker involvement; (4) to evaluate the ''value added'' benefit of the panel-to-panel review approach; and, (5) to evaluate the utility of the review's methodology/adaptability to periodic assessments of ISM status. The review was conducted on December 6-8, 1999, and involved the conduct of two-hour interviews with five separate panels of individuals with various management and operations responsibilities related to PFP. A semi-structured interview process was employed by a team of five ''reviewers'' who directed open-ended questions to the panels which focused on: (1) evidence of management commitment, accountability, and involvement; and, (2) consideration and demonstration of stakeholder (including worker) information and involvement opportunities. The purpose of a panel-to-panel dialogue approach was to better spotlight: (1) areas of mutual reinforcement and alignment that could serve as good examples of the management commitment and accountability aspects of ISMS implementation, and, (2) areas of potential discrepancy that could provide opportunities for improvement. In summary, the Review Team found major strengths to include: (1) the use of multi-disciplinary project work teams to plan and do work; (2) the availability and broad usage of multiple tools to help with planning and integrating work; (3) senior management presence and accessibility; (4) the institutionalization of worker involvement; (5) encouragement of self-reporting and self

  3. The Integrated Safety Management System Verification Enhancement Review of the Plutonium Finishing Plant (PFP)

    Energy Technology Data Exchange (ETDEWEB)

    BRIGGS, C.R.

    2000-02-09

    The primary purpose of the verification enhancement review was for the DOE Richland Operations Office (RL) to verify contractor readiness for the independent DOE Integrated Safety Management System Verification (ISMSV) on the Plutonium Finishing Plant (PFP). Secondary objectives included: (1) to reinforce the engagement of management and to gauge management commitment and accountability; (2) to evaluate the ''value added'' benefit of direct public involvement; (3) to evaluate the ''value added'' benefit of direct worker involvement; (4) to evaluate the ''value added'' benefit of the panel-to-panel review approach; and, (5) to evaluate the utility of the review's methodology/adaptability to periodic assessments of ISM status. The review was conducted on December 6-8, 1999, and involved the conduct of two-hour interviews with five separate panels of individuals with various management and operations responsibilities related to PFP. A semi-structured interview process was employed by a team of five ''reviewers'' who directed open-ended questions to the panels which focused on: (1) evidence of management commitment, accountability, and involvement; and, (2) consideration and demonstration of stakeholder (including worker) information and involvement opportunities. The purpose of a panel-to-panel dialogue approach was to better spotlight: (1) areas of mutual reinforcement and alignment that could serve as good examples of the management commitment and accountability aspects of ISMS implementation, and, (2) areas of potential discrepancy that could provide opportunities for improvement. In summary, the Review Team found major strengths to include: (1) the use of multi-disciplinary project work teams to plan and do work; (2) the availability and broad usage of multiple tools to help with planning and integrating work; (3) senior management presence and accessibility; (4) the

  4. Modular Engineering of Production Plants

    DEFF Research Database (Denmark)

    Miller, Thomas Dedenroth

    1998-01-01

    Based on a case-study on design of pharmaceutical production plants, this paper suggests that modularity may support business efficiency for companies with one-of-a-kind production and without in-house manufacturing. Modularity may support efficient management of design knowledge and may facilitate...

  5. The United States Plutonium Balance, 1944 - 2009

    Energy Technology Data Exchange (ETDEWEB)

    None

    2012-06-01

    This report updates the report -Plutonium: The first 50 years- which was released by the U.S.Department of Energy (DOE) in 1996. The topic of both reports is plutonium, sometimes referred to as Pu-239, which is capable of sustaining a nuclear chain reaction and is used in nuclear weapons and for nuclear power production. This report updates 1994 data through 2009. The four most significant changes since 1994 include: (a) the completion of cleanup activities at the Rocky Flats Plant in 2005; (b) material consolidation and disposition activities, especially shipments from Hanford to the Savannah River Site; (c) the 2007 declaration of an additional 9.0 MT of weapons grade plutonium to be surplus to defense needs in the coming decades; and (d) the opening of the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico in 1999.

  6. Nondestructive assay measurements applied to reprocessing plants

    International Nuclear Information System (INIS)

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

  7. Radiolysis of hexavalent plutonium in solutions of uranyl nitrate containing fission product simulants

    International Nuclear Information System (INIS)

    The effect of the inherent radioactivity on the chemical state of plutonium ions in solution was recognized very shortly after the first macroscopic amounts of plutonium became available and early studies were conducted as part of the Manhattan Project. However, the behavior of plutonium ions, in nitric acid especially, has been found to be somewhat complex, so much so that a relatively modern summary paper included the comment that, ''The vast amount of work carried out in nitric acid solutions can not be adequately summarized. Suffice it to say results in these solutions are plagued with irreproducibility and induction periods...'' Needless to say, the presence of other ions in solution, as occurs when irradiated nuclear fuel is dissolved, further complicates matters. The purpose of the work described below was to add to the rather small amount of qualitative data available relating to the radiolytic behavior of plutonium in solutions of irradiated nuclear fuel

  8. Calibration of X-ray densitometers for the determination of uranium and plutonium concentrations in reprocessing input and product solutions

    International Nuclear Information System (INIS)

    In June 1985 a calibration exercise has been carried out, which included the calibration of the KfK K-Edge Densitometer for uranium assay in the uranium product solutions from reprocessing, and the calibration of the Hybrid K-Edge/K-XRF Instrument for the determination of total uranium and plutonium in reprocessing input solutions. The calibration measuremnts performed with the two X-ray densitometers are described and analyzed, and calibration constants are evaluated from the obtained results. (orig.)

  9. Alert Systems for production Plants

    DEFF Research Database (Denmark)

    Nielsen, Thomas Dyhre; Jensen, Finn Verner

    2005-01-01

    We present a new methodology for detecting faults and abnormal behavior in production plants. The methodology stems from a joint project with a Danish energy consortium. During the course of the project we encountered several problems that we believe are common for projects of this type. Most...... system operation, i.e., it does not rely on information about the possible faults. We illustrate the proposed method using real-world data from a coal driven power plant as well as simulated data from an oil production facility....

  10. Plutonium controversy

    Energy Technology Data Exchange (ETDEWEB)

    Richmond, C.R.

    1980-01-01

    The toxicity of plutonium is discussed, particularly in relation to controversies surrounding the setting of radiation protection standards. The sources, amounts of, and exposure pathways of plutonium are given and the public risk estimated. (ACR)

  11. PLUTONIUM SEPARATION METHOD

    Science.gov (United States)

    Beaufait, L.J. Jr.; Stevenson, F.R.; Rollefson, G.K.

    1958-11-18

    The recovery of plutonium ions from neutron irradiated uranium can be accomplished by bufferlng an aqueous solutlon of the irradiated materials containing tetravalent plutonium to a pH of 4 to 7, adding sufficient acetate to the solution to complex the uranyl present, adding ferric nitrate to form a colloid of ferric hydroxide, plutonlum, and associated fission products, removing and dissolving the colloid in aqueous nitric acid, oxldizlng the plutonium to the hexavalent state by adding permanganate or dichromate, treating the resultant solution with ferric nitrate to form a colloid of ferric hydroxide and associated fission products, and separating the colloid from the plutonlum left in solution.

  12. Cimarrones y palenques en las provincias al norte del Nuevo Reino de Granada siglo XVII

    Directory of Open Access Journals (Sweden)

    María Cristina Navarrete P.

    2001-01-01

    Full Text Available A finales del siglo XVII, ya existían comunidades de cimarrones en varias provincias de la jurisdicción de la Audiencia del Nuevo Reino de Granada. Hacia 1598, en Zaragoza, y en 1607, en Remedios, provincia de Antioquia, esclavos negros de las rancherías mineras se levantaron violentamente y fortificaron en palenques, causando perjuicios en el comercio, la vida de las ciudades y la labor de las minas. Otro de los más importantes alzamientos de esclavos fue el dirigido por Domingo Biohó quien se refugió con sus seguidores en la Ciénaga de la Matuna. Asimismo, las Sierras de María y la Serranía de San Lucas fueron espacios de establecimiento de palenques. Los cimarrones intentaron reconstruir organizaciones sociales con base en la herencia cultural africana, en la permanencia en las haciendas y minas al contacto con amos, capataces y compañeros de circunstancias y, en las nuevas condiciones que les ofrecía la vida de los palenques.

  13. 77 FR 14010 - Rocky Ridge Wind Project, LLC, Blackwell Wind, LLC, CPV Cimarron Renewable Energy Company, LLC...

    Science.gov (United States)

    2012-03-08

    ... Cimarron Renewable Energy Company, LLC, Minco Wind Interconnection Services, LLC, Shiloh III Lessee, LLC, California Ridge Wind Energy LLC, Perrin Ranch Wind, LLC, Erie Wind, LLC: Notice of Effectiveness of Exempt... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY...

  14. Wet water glass production plant

    Directory of Open Access Journals (Sweden)

    Stanković Mirjana S.

    2003-01-01

    Full Text Available The IGPC Engineering Department designed basic projects for a wet hydrate dissolution plant, using technology developed in the IGPC laboratories. Several projects were completed: technological, machine, electrical, automation. On the basis of these projects, a production plant of a capacity of 75,000 t/y was manufactured, at "Zeolite Mira", Mira (VE, Italy, in 1997. and 1998, increasing detergent zeolite production, from 50,000 to 100,000 t/y. Several goals were realized by designing a wet hydrate dissolution plant. The main goal was increasing the detergent zeolite production. The technological cycle of NaOH was closed, and no effluents emitted, and there is no pollution (except for the filter cake. The wet water glass production process is fully automatized, and the product has uniform quality. The production process can be controlled manually, which is necessary during start - up, and repairs. By installing additional process equipment (centrifugal pumps and heat exchangers technological bottlenecks were overcome, and by adjusting the operation of autoclaves, and water glass filters and also by optimizing the capacities of process equipment.

  15. Plant senescence and crop productivity

    DEFF Research Database (Denmark)

    Gregersen, Per L.; Culetic, Andrea; Boschian, Luca;

    2013-01-01

    Senescence is a developmental process which in annual crop plants overlaps with the reproductive phase. Senescence might reduce crop yield when it is induced prematurely under adverse environmental conditions. This review covers the role of senescence for the productivity of crop plants...... plants, the expression of the IPT gene under control of senescence-associated promoters has been the most successful. The promoters employed for senescence-regulated expression contain cis-elements for binding of WRKY transcription factors and factors controlled by abscisic acid. In most crops...... transformed with such constructs the stay-green character has led to increased biomass, but only in few cases to increased seed yield. A coincidence of drought stress resistance and stay-green trait is observed in many transgenic plants....

  16. Investigation Of In-Line Monitoring Options At H Canyon/HB Line For Plutonium Oxide Production

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-10-14

    H Canyon and HB Line have a production goal of 1 MT per year of plutonium oxide feedstock for the MOX facility by FY17 (AFS-2 mission). In order to meet this goal, steps will need to be taken to improve processing efficiency. One concept for achieving this goal is to implement in-line process monitoring at key measurement points within the facilities. In-line monitoring during operations has the potential to increase throughput and efficiency while reducing costs associated with laboratory sample analysis. In the work reported here, we mapped the plutonium oxide process, identified key measurement points, investigated alternate technologies that could be used for in-line analysis, and initiated a throughput benefit analysis.

  17. Application of neutron well coincidence counting for plutonium determination in mixed oxide fuel fabrication plant

    International Nuclear Information System (INIS)

    Mixed oxide (MOX) fuel is an alternative to conventional enriched uranium oxide fuel in thermal reactors. Indian interest in plutonium recycle in thermal reactors is primarily due to the need to develop alternative indigenous fuel for two boiling water reactors (BWR) at Tarapur, which are designed to use imported light enriched uranium fuel. A few MOX assemblies have been fabricated and loaded into the reactors. Neutron well coincidence counting (NWCC) system has been successfully employed to check the enrichments of PuO2 in MOX blends. NWCC has also been successfully applied in developing dry recycling process of clean rejected oxide (CRO) and dirty rejected oxide (DRO). (author)

  18. Plutonium Immobilization Project Baseline Formulation

    Energy Technology Data Exchange (ETDEWEB)

    Ebbinghaus, B.

    1999-02-01

    A key milestone for the Immobilization Project (AOP Milestone 3.2a) in Fiscal Year 1998 (FY98) is the definition of the baseline composition or formulation for the plutonium ceramic form. The baseline formulation for the plutonium ceramic product must be finalized before the repository- and plant-related process specifications can be determined. The baseline formulation that is currently specified is given in Table 1.1. In addition to the baseline formulation specification, this report provides specifications for two alternative formulations, related compositional specifications (e.g., precursor compositions and mixing recipes), and other preliminary form and process specifications that are linked to the baseline formulation. The preliminary specifications, when finalized, are not expected to vary tremendously from the preliminary values given.

  19. Evaluation of the Magnesium Hydroxide Treatment Process for Stabilizing PFP Plutonium/Nitric Acid Solutions

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, Mark A.; Schmidt, Andrew J.; Delegard, Calvin H.; Silvers, Kurt L.; Baker, Aaron B.; Gano, Susan R.; Thornton, Brenda M.

    2000-09-28

    This document summarizes an evaluation of the magnesium hydroxide [Mg(OH)2] process to be used at the Hanford Plutonium Finishing Plant (PFP) for stabilizing plutonium/nitric acid solutions to meet the goal of stabilizing the plutonium in an oxide form suitable for storage under DOE-STD-3013-99. During the treatment process, nitric acid solutions bearing plutonium nitrate are neutralized with Mg(OH)2 in an air sparge reactor. The resulting slurry, containing plutonium hydroxide, is filtered and calcined. The process evaluation included a literature review and extensive laboratory- and bench-scale testing. The testing was conducted using cerium as a surrogate for plutonium to identify and quantify the effects of key processing variables on processing time (primarily neutralization and filtration time) and calcined product properties.

  20. Dairy Product Manufacturing Costs at Cooperative Plants

    OpenAIRE

    Ling, K. Charles

    1983-01-01

    Cost data are summarized for 14 plants manufacturing cheese, butter, and powder and average costs are presented for each product. Average cost curves are estimated for each plant. The scale of plant for least-cost operations is identified for plants of each product type. Plant capacity utilization and seasonal volume variation and their impacts on manufacturing cost are delineated.

  1. Storage for the Fast Flux Test Facility unirradiated fuel in the Plutonium Finishing Plant Complex, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    This Environmental Assessment evaluates the proposed action to relocate and store unirradiated Fast Flux Test Facility fuel in the Plutonium Finishing Plant Complex on the Hanford Site, Richland, Washington. The US Department of Energy has decided to cease fuel fabrication activities in the 308 Building in the 300 Area. This decision was based on a safety concern over the ability of the fuel fabrication portion of the 308 Building to withstand a seismic event. The proposed action to relocate and store the fuel is based on the savings that could be realized by consolidating security costs associated with storage of the fuel. While the 308 Building belowgrade fuel storage areas are not at jeopardy by a seismic event, the US Department of Energy is proposing to cease storage operations along with the related fabrication operations. The US Department of Energy proposes to remove the unirradiated fuel pins and fuel assemblies from the 308 Building and store them in Room 192A, within the 234-5Z Building, a part of the Plutonium Finishing Plant Complex, located in the 200 West Area. Minor modifications to Room 192A would be required to accommodate placement of the fuel. The US Department of Energy estimates that removing all of the fuel from the 308 Building would save $6.5 million annually in security expenditures for the Fast Flux Test Facility. Environmental impacts of construction, relocation, and operation of the proposed action and alternatives were evaluated. This evaluation concluded that the proposed action would have no significant impacts on the human environment

  2. Digital data sets that describe aquifer characteristics of the alluvial and terrace deposits along the Cimarron River from Freedom to Guthrie in northwestern Oklahoma

    Data.gov (United States)

    U.S. Geological Survey, Department of the Interior — This data set consists of digital polygons of a constant recharge rate for the alluvial and terrace deposits along the Cimarron River from Freedom to Guthrie in...

  3. Digital data sets that describe aquifer characteristics of the alluvial and terrace deposits along the Cimarron River from Freedom to Guthrie in northwestern Oklahoma

    Data.gov (United States)

    U.S. Geological Survey, Department of the Interior — This data set consists of digital polygons of constant hydraulic conductivity values for the alluvial and terrace deposits along the Cimarron River from Freedom to...

  4. Digital data sets that describe aquifer characteristics of the alluvial and terrace deposits along the Cimarron River from Freedom to Guthrie in northwestern Oklahoma

    Data.gov (United States)

    U.S. Geological Survey, Department of the Interior — This data set consists of digital aquifer boundaries for the alluvial and terrace deposits along the Cimarron River from Freedom to Guthrie in northwestern...

  5. Digital data sets that describe aquifer characteristics of the alluvial and terrace deposits along the Cimarron River from Freedom to Guthrie in northwestern Oklahoma

    Data.gov (United States)

    U.S. Geological Survey, Department of the Interior — This data set consists of digital water-level elevation contours for the alluvial and terrace deposits along the Cimarron River in northwestern Oklahoma during...

  6. 10 CFR 140.107 - Appendix G-Form of indemnity agreement with licensees processing plutonium for use in plutonium...

    Science.gov (United States)

    2010-01-01

    ... processing plutonium for use in plutonium processing and fuel fabrication plants and furnishing insurance... § 140.107 Appendix G—Form of indemnity agreement with licensees processing plutonium for use in plutonium processing and fuel fabrication plants and furnishing insurance policies as proof of...

  7. 10 CFR 140.108 - Appendix H-Form of indemnity agreement with licensees possessing plutonium for use in plutonium...

    Science.gov (United States)

    2010-01-01

    ... possessing plutonium for use in plutonium processing and fuel fabrication plants and furnishing proof of... Appendixes to Part 140 § 140.108 Appendix H—Form of indemnity agreement with licensees possessing plutonium for use in plutonium processing and fuel fabrication plants and furnishing proof of...

  8. Plutonium Vulnerability Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-01

    This Plutonium Vulnerability Management Plan describes the Department of Energy`s response to the vulnerabilities identified in the Plutonium Working Group Report which are a result of the cessation of nuclear weapons production. The responses contained in this document are only part of an overall, coordinated approach designed to enable the Department to accelerate conversion of all nuclear materials, including plutonium, to forms suitable for safe, interim storage. The overall actions being taken are discussed in detail in the Department`s Implementation Plan in response to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1. This is included as Attachment B.

  9. Plutonium Vulnerability Management Plan

    International Nuclear Information System (INIS)

    This Plutonium Vulnerability Management Plan describes the Department of Energy's response to the vulnerabilities identified in the Plutonium Working Group Report which are a result of the cessation of nuclear weapons production. The responses contained in this document are only part of an overall, coordinated approach designed to enable the Department to accelerate conversion of all nuclear materials, including plutonium, to forms suitable for safe, interim storage. The overall actions being taken are discussed in detail in the Department's Implementation Plan in response to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1. This is included as Attachment B

  10. Concentration of Plutonium in Desert Plants From Contaminated Area%钚在放射性污染区沙漠植物中的含量

    Institute of Scientific and Technical Information of China (English)

    徐辉; 金玉仁; 田梅; 李伟平; 王耀芹; 王煜; 曾可

    2012-01-01

    研究沙漠植物中钚的含量,对于评估沙漠植物受钚污染状况,寻找钚指示和超积累植物有重要意义.本文采集某放射性污染区内的植物并分析其中239 Pu的含量,获得7种沙漠植物受239Pu污染的数据,据此分析影响植物体内核素含量的因素.所研究沙漠植物体内239 Pu含量平均值为(1.8士4.9)Bq/kg(干重),明显受到钚的污染.再悬浮是造成植物表面污染严重的重要因素之一.植物体内钚的含量与植物种类、生长期、地表污染程度等密切相关.所研究沙漠植物中钚含量的大小顺序为:河西苣>芦苇>盐穗木>盐生草>黑果枸杞>刚毛柽柳>沙拐枣,其中草本植物中钚的含量均大于木本植物.%The investigation of plutonium in desert plants from contaminated sites contributes to the evaluation of its pollution situation and to the survey of plutonium hyperaccumulator. The concentration of 239Pu in desert plants collected from a contaminated site was determined, and the influence factors were studied. The concentration of 239Pu in plants was (1. 8 + 4. 9) Bq/kg in dry weight, and it means that the plants were contaminated, moreover, the resuspension results in dramatic plutonium pollution of plant surface. The concentration of plutonium in plants depends on species, live stages and the content of plutonium in the rhizosphere soil. The concentration of plutonium in herbage is higher than that in woody plant, and for the seven species of desert plants investigated, it decreases in the order of Hexinia polydichotoma, Phragmites austra-lis, Halostashys caspica, Halogeton arachnoideus, Lycium ruthenicum ,Tamarix hispida and Calligonum aphyllum.

  11. Plutonium contamination in soils and sediments at Mayak PA, Russia.

    Science.gov (United States)

    Skipperud, Lindis; Salbu, Brit; Oughton, Deborah H; Drozcho, Eugeny; Mokrov, Yuri; Strand, Per

    2005-09-01

    The Mayak Production Association (Mayak PA) was established in the late 1940's to produce plutonium for the Soviet Nuclear Weapons Programme. In total, seven reactors and two reprocessing plants have been in operation. Today, the area comprises both military and civilian reactors as well as reprocessing and metallurgical plants. Authorized and accidental releases of radioactive waste have caused severe contamination to the surrounding areas. In the present study, [alpha]-spectrometry and inductively coupled plasma-mass spectrometry (ICP-MS) have been used to determine plutonium activities and isotope ratios in soil and sediment samples collected from reservoirs of the Techa River at the Mayak area and downstream Techa River. The objective of the study was to determine the total inventory of plutonium in the reservoirs and to identify the different sources contributing to the plutonium contamination. Results based on [alpha]-spectrometry and ICP-MS measurements show the presence of different sources and confirmed recent reports of civilian reprocessing at Mayak. Determination of activity levels and isotope ratios in soil and sediment samples from the Techa River support the hypothesis that most of the plutonium, like other radionuclides in the Techa River, originated from the very early waste discharges to the Techa River between 1949 and 1951. Analysis of reservoir sediment samples suggest that about 75% of the plutonium isotopes could have been released to Reservoir 10 during the early weapons production operation of the plant, and that the majority of plutonium in Reservoir 10 originates from discharges from power production or reprocessing. Enhanced 240Pu/239Pu atom ratios in river sediment upper layers (0-2 cm) between 50 and 250 km downstream from the plant indicate a contribution from other, non-fallout sources. PMID:16096501

  12. Radioactive Air Emissions Notice of Construction for the Magnesium Hydroxide Precipitation Process at the Plutonium Finishing Plant (PFP)

    International Nuclear Information System (INIS)

    The following description and any attachments and references are provided to the Washington State Department of Health (WDOH), Division of Radiation Protection, Air Emissions and Defense Waste (WAC) 246-247, Radiation Protection-Air Emissions. The WAC 246-247-060, ''Applications, registration, and licensing'', states ''This section describes the information requirements for approval to construct, modify, and operate an emission unit. Any NOC requires the submittal of information listed in Appendix A.'' Appendix A (WAC 246-247-1 10) lists the requirements that must be addressed. Additionally, the following description, attachments and references are provided to the US Environmental Protection Agency (EPA) as an NOC, in accordance with Title 40, Code of Federal Regulations (CFR), Part 61, ''National Emission Standards for Hazardous Air Pollutants.'' The information required for submittal to the EPA is specified in 40 CFR 61.07. The potential emissions from this activity are estimated to provide greater than 0.1 millirem per year total effective dose equivalent (TEDE) to the hypothetical offsite maximally exposed individual (MEI), and commencement is needed within a short time. Therefore, this application also is intended to provide notification of the anticipated date of initial startup in accordance with the requirement listed in 40 CFR 61.09(a)(1), and it is requested that approval of this application also will constitute EPA acceptance of this initial startup notification. Written notification of the actual date of initial startup, in accordance with the requirement listed in 40 CFR 61.09(a)(2) will be provided at a later date. This NOC covers the activities associated with the Construction and operation activities involving the magnesium hydroxide precipitation process of plutonium solutions within the Plutonium Finishing Plant (PFP)

  13. Preliminary studies of the genetic structure of “Cimarron uruguayo” dog using microsatellite markers

    Directory of Open Access Journals (Sweden)

    Rosa Gagliardi B.

    2010-12-01

    Full Text Available Objetive. To analyze the population structure, using microsatellite markers in a sample of “Cimarron Uruguayo” dogs. Materials and methods. Thirty dogs were analyzed in different areas of Uruguay with a set of nine molecular microsatellite markers using PCR. The population structure was analyzed using the free distribution software “Structure’’. Results. According to our data, the preliminary results show that it is not possible to establish a subdivision among the animals in the sample. Conclusions. The study supports the hypothesis that the currently existing canines derive from a founding nucleus that took refuge in the Northeastern region of the country. The distribution of the breed among the different areas of Uruguay continues nowadays, so there is no isolation among the different groups of animals, and the exchange is constant

  14. Uranium hexafluoride production plant decommissioning

    International Nuclear Information System (INIS)

    The Institute of Energetic and Nuclear Research - IPEN is a research and development institution, located in a densely populated area, in the city of Sao Paulo. The nuclear fuel cycle was developed from the Yellow Cake to the enrichment and reconversion at IPEN. After this phase, all the technology was transferred to private enterprises and to the Brazilian Navy (CTM/SP). Some plants of the fuel cycle were at semi-industrial level, with a production over 20 kg/h. As a research institute, IPEN accomplished its function of the fuel cycle, developing and transferring technology. With the necessity of space for the implementation of new projects, the uranium hexafluoride (UF6) production plant was chosen, since it had been idle for many years and presented potential leaking risks, which could cause environmental aggression and serious accidents. This plant decommission required accurate planning, as this work had not been carried out in Brazil before, for this type of facility, and there were major risks involving gaseous hydrogen fluoride aqueous solution of hydrofluoric acid (HF) both highly corrosive. Evaluations were performed and special equipment was developed, aiming to prevent leaking and avoid accidents. During the decommissioning work, the CNEN safety standards were obeyed for the whole operation. The environmental impact was calculated, showing to be not relevant.The radiation doses, after the work, were within the limits for the public and the area was released for new projects. (author)

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

    International Nuclear Information System (INIS)

    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

  16. DISPOSAL OF TRU WASTE FROM THE PLUTONIUM FINISHING PLANT IN PIPE OVERPACK CONTAINERS TO WIPP INCLUDING NEW SECURITY REQUIREMENTS

    Energy Technology Data Exchange (ETDEWEB)

    Hopkins, A.M.; Sutter, C.; Hulse, G.; Teal, J.

    2003-02-27

    The Department of Energy is responsible for the safe management and cleanup of the DOE complex. As part of the cleanup and closure of the Plutonium Finishing Plant (PFP) located on the Hanford site, the nuclear material inventory was reviewed to determine the appropriate disposition path. Based on the nuclear material characteristics, the material was designated for stabilization and packaging for long term storage and transfer to the Savannah River Site or, a decision for discard was made. The discarded material was designated as waste material and slated for disposal to the Waste Isolation Pilot Plant (WIPP). Prior to preparing any residue wastes for disposal at the WIPP, several major activities need to be completed. As detailed a processing history as possible of the material including origin of the waste must be researched and documented. A technical basis for termination of safeguards on the material must be prepared and approved. Utilizing process knowledge and processing history, the material must be characterized, sampling requirements determined, acceptable knowledge package and waste designation completed prior to disposal. All of these activities involve several organizations including the contractor, DOE, state representatives and other regulators such as EPA. At PFP, a process has been developed for meeting the many, varied requirements and successfully used to prepare several residue waste streams including Rocky Flats incinerator ash, Hanford incinerator ash and Sand, Slag and Crucible (SS&C) material for disposal. These waste residues are packed into Pipe Overpack Containers for shipment to the WIPP.

  17. Multi-Product Plants and Product Switching in Japan

    OpenAIRE

    Andrew B. Bernard; Okubo, Toshihiro

    2013-01-01

    This paper explores the role of multi-product plants and product switching in the Japanese manufacturing sector. While a substantial body of work has explored the importance of the extensive margins of plant entry and exit in employment and output flows, only recently has research begun to examine the adjustment across products within establishments and its importance for plant and aggregate output and employment flows. Using a novel, annual plant-product dataset covering all Japanese manufac...

  18. High temperature X-ray diffraction study of the oxidation products and kinetics of uranium-plutonium mixed oxides.

    Science.gov (United States)

    Strach, Michal; Belin, Renaud C; Richaud, Jean-Christophe; Rogez, Jacques

    2014-12-15

    The oxidation products and kinetics of two sets of mixed uranium-plutonium dioxides containing 14%, 24%, 35%, 46%, 54%, and 62% plutonium treated in air were studied by means of in situ X-ray diffraction (XRD) from 300 to 1773 K every 100 K. The first set consisted of samples annealed 2 weeks before performing the experiments. The second one consisted of powdered samples that sustained self-irradiation damage. Results were compared with chosen literature data and kinetic models established for UO2. The obtained diffraction patterns were used to determine the temperature of the hexagonal M3O8 (M for metal) phase formation, which was found to increase with Pu content. The maximum observed amount of the hexagonal phase in wt % was found to decrease with Pu addition. We conclude that plutonium stabilizes the cubic phases during oxidation, but the hexagonal phase was observed even for the compositions with 62 mol % Pu. The results indicate that self-irradiation defects have a slight impact on the kinetics of oxidation and the lattice parameter even after the phase transformation. It was concluded that the lattice constant of the high oxygen phase was unaffected by the changes in the overall O/M when it was in equilibrium with small quantities of M3O8. We propose that the observed changes in the high oxygen cubic phase lattice parameter are a result of either cation migration or an increase in the miscibility of oxygen in this phase. The solubility of Pu in the hexagonal phase was estimated to be below 14 mol % even at elevated temperatures. PMID:25412433

  19. Productivity growth patterns in US dairy products manufacturing plants

    NARCIS (Netherlands)

    Geylani, P.C.; Stefanou, S.E.

    2011-01-01

    We analyse the productivity growth patterns in the US dairy products industry using the Census Bureau's plant-level data set. We decompose Total Factor Productivity (TFP) growth into the scale and technical change components and analyse variability of plants' productivity by constructing transition

  20. Comparison of actinides and fission products recycling scheme with the normal plutonium recycling scheme in fast reactors

    Directory of Open Access Journals (Sweden)

    Salahuddin Asif

    2013-01-01

    Full Text Available Multiple recycling of actinides and non-volatile fission products in fast reactors through the dry re-fabrication/reprocessing atomics international reduction oxidation process has been studied as a possible way to reduce the long-term potential hazard of nuclear waste compared to that resulting from reprocessing in a wet PUREX process. Calculations have been made to compare the actinides and fission products recycling scheme with the normal plutonium recycling scheme in a fast reactor. For this purpose, the Karlsruhe version of isotope generation and depletion code, KORIGEN, has been modified accordingly. An entirely novel fission product yields library for fast reactors has been created which has replaced the old KORIGEN fission products library. For the purposes of this study, the standard 26 groups data set, KFKINR, developed at Forschungszentrum Karlsruhe, Germany, has been extended by the addition of the cross-sections of 13 important actinides and 68 most important fission products. It has been confirmed that these 68 fission products constitute about 95% of the total fission products yield and about 99.5% of the total absorption due to fission products in fast reactors. The amount of fissile material required to guarantee the criticality of the reactor during recycling schemes has also been investigated. Cumulative high active waste per ton of initial heavy metal is also calculated. Results show that the recycling of actinides and fission products in fast reactors through the atomics international reduction oxidation process results in a reduction of the potential hazard of radioactive waste.

  1. Simulation of a complex chemical plant taking the example of uranium-plutonium extraction

    International Nuclear Information System (INIS)

    The first extraction cycle of a reprocessing plant is simulated by means of the ABAS program system. A program-orientated modular arranged simulation system is presented and described with ABAS which is suitable for the simulation of stationary as well as instationary operation states of engineering plants. The program system can be flexibly applied and independently of computers by using the FORTRAN program language. The functioning ABAS is demonstrated by the example of the reprocessing plant of Eurochemic in Mol, Belgium which works according to the Purex process. The stationary concentration profile in the pulsed sieve diaphragm extraction column of this plant are calculated using the Backflow model. The agreement of the results with the operational data is good if one takes the deficiencies into account when determining the model parameters and equilibrium relationships applied. In the simulation of the transient behaviour of the plant, in the start-up procedure and in accidents, concentration maxima can arise as a result of competing extraction of the components taking part, which are not observed in systems only having one extractable component. (orig.)

  2. Particle Generation by Laser Ablation in Support of Chemical Analysis of High Level Mixed Waste from Plutonium Production Operations

    International Nuclear Information System (INIS)

    Investigate particles produced by laser irradiation and their analysis by Laser Ablation Inductively Coupled Plasma Mass Spectroscopy (LA/ICP-MS), with a view towards optimizing particle production for analysis of high level waste materials and waste glass. LA/ICP-MS has considerable potential to increase the safety and speed of analysis required for the remediation of high level wastes from cold war plutonium production operations. In some sample types, notably the sodium nitrate-based wastes at Hanford and elsewhere, chemical analysis using typical laser conditions depends strongly on the details of sample history composition in a complex fashion, rendering the results of analysis uncertain. Conversely, waste glass materials appear to be better behaved and require different strategies to optimize analysis

  3. Plutonium Oxide Process Capability Work Plan

    Energy Technology Data Exchange (ETDEWEB)

    Meier, David E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Tingey, Joel M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2014-02-28

    Pacific Northwest National Laboratory (PNNL) has been tasked to develop a Pilot-scale Plutonium-oxide Processing Unit (P3U) providing a flexible capability to produce 200g (Pu basis) samples of plutonium oxide using different chemical processes for use in identifying and validating nuclear forensics signatures associated with plutonium production. Materials produced can also be used as exercise and reference materials.

  4. Plutonium Oxide Process Capability Work Plan

    International Nuclear Information System (INIS)

    Pacific Northwest National Laboratory (PNNL) has been tasked to develop a Pilot-scale Plutonium-oxide Processing Unit (P3U) providing a flexible capability to produce 200g (Pu basis) samples of plutonium oxide using different chemical processes for use in identifying and validating nuclear forensics signatures associated with plutonium production. Materials produced can also be used as exercise and reference materials.

  5. Plutonium behavior during the early diagenesis of marine sediments: applications to two marine environments labelled by radionuclides released from reprocessing plants; Etude du comportement du plutonium au cours de la diagenese precoce des sediments marins: applications a deux environnements marins marques par les rejets issus d'usines de retraitement de combustibles uses

    Energy Technology Data Exchange (ETDEWEB)

    Gouzy, A

    2004-12-15

    The plutonium released into the English Channel and the Irish Sea by nuclear fuel reprocessing plants is mainly associated to sediments. Nevertheless, this association is partially reversible. This work combines a field study, carried out on the Cumbrian mud patch and the Esk estuary (Eastern Irish Sea), and laboratory experiments performed on carbonaceous coarse-grained sediments collected in the Central Channel. It presents new data on the plutonium solid partition in sediments and suggests realistic scenarios for describing its release from sediments to the water column. The role of reactive sulphides acting as temporary sink phases is shown in anoxic sediments; those sulphides are liable to release dissolved plutonium upon their oxidation. The plutonium is also bound to carbonates within the carbonaceous matrix and as carbonate surface complexes. Conceptual schemes of the behaviour of the plutonium in marine sediments are proposed; they highlight the strong remobilization potential of plutonium from marine sediments to the interstitial water. Its plutonium content can be injected into the overlying water column. (author)

  6. HPLC analysis of plant sterol oxidation products

    OpenAIRE

    Kemmo, Suvi

    2008-01-01

    Increased interest in the cholesterol-lowering effect of plant sterols has led to development of plant sterol-enriched foods. When products are enriched, the safety of the added components must be evaluated. In the case of plant sterols, oxidation is the reaction of main concern. In vitro studies have indicated that cholesterol oxides may have harmful effects. Due their structural similarity, plant sterol oxidation products may have similar health implications. This study concentrated on...

  7. PLUTONIUM UPTAKE AND BEHAVIOR IN PLANTS OF THE DESERT SOUTHWEST: A PRELIMINARY ASSESSMENT

    Energy Technology Data Exchange (ETDEWEB)

    Caldwell, E.; Duff, M.; Ferguson, C.

    2011-03-01

    Eight species of desert vegetation and associated soils were collected from the Nevada National Security Site (N2S2) and analyzed for 238Pu and 239+240Pu concentrations. Amongst the plant species sampled were: atmospheric elemental accumulators (moss and lichen), the very slow growing, long-lived creosote bush and the rapidly growing, short-lived cheatgrass brome. The diversity of growth strategies provided insight into the geochemical behavior and bio-availability of Pu at the N2S2. The highest concentrations of Pu were measured in the onion moss (24.27 Bq kg-1 238Pu and 52.78 Bq kg-1 239+240Pu) followed by the rimmed navel lichen (8.18 Bq kg-1 and 18.4 Bq kg-1 respectively), pointing to the importance of eolian transport of Pu. Brome and desert globemallow accumulated between 3 and 9 times higher concentrations of Pu than creosote and sage brush species. These results support the importance of species specific elemental accumulation strategies rather than exposure duration as the dominant variable influencing Pu concentrations in these plants. Total vegetation elemental concentrations of Ce, Fe, Al, Sm and others were also analyzed. Strong correlations were observed between Fe and Pu. This supports the conclusion that Pu was accumulated as a consequence of the active accumulation of Fe and other plant required nutrients. Cerium and Pu are considered to be chemical analogs. Strong correlations observed in plants support the conclusion that these elements displayed similar geochemical behavior in the environment as it related to the biochemical uptake process of vegetation. Soils were also sampled in association with vegetation samples. This allowed for the calculation of a concentration ratio (CR). The CR values for Pu in plants were highly influenced by the heterogeneity of Pu distribution among sites. Results from the naturally occurring elements of concern were more evenly distributed between sample sites. This allowed for the development of a pattern of plant

  8. Plutonium solubilities

    International Nuclear Information System (INIS)

    Thermochemical data has been selected for plutonium oxide, hydroxide, carbonate and phosphate equilibria. Equilibrium constants have been evaluated in the temperature range 0 to 300 degrees C at a pressure of 1 bar to T≤100 degrees C and at the steam saturated pressure at higher temperatures. Measured solubilities of plutonium that are reported in the literature for laboratory experiments have been collected. Solubility data on oxides, hydroxides, carbonates and phosphates have been selected. No solubility data were found at temperatures higher than 60 degrees C. The literature solubility data have been compared with plutonium solubilities calculated with the EQ3/6 geochemical modelling programs, using the selected thermodynamic data for plutonium. (authors)

  9. Estimated airborne release of plutonium from the Exxon Nuclear Mixed Oxide Fuel Plant at Richland, Washington as a result of postulated damage from severe wind and earthquake hazard

    International Nuclear Information System (INIS)

    The potential airborne releases of plutonium from postulated damage sustained by the Exxon Nuclear Company's Mixed Oxide Fabrication Plant at Richland, Washington, as a result of various levels of wind and earthquake hazard, are estimated. The releases are based on damage scenarios that range up to 250 mph for wind hazard and in excess of 1.0 g ground acceleration for seismic hazard, which were developed by other specialists. The approaches and factors used to estimate the releases (inventories of dispersible materials at risk, damage levels and ratios, fractional airborne releases of dispersible materials under stress, atmosphere exchange rates, and source term ranges) are discussed. Release estimates range from less than 10-7 g to greater than 14 g of plutonium over a four-day period

  10. Estimated airborne release of plutonium from the Exxon Nuclear Mixed Oxide Fuel Plant at Richland, Washington as a result of postulated damage from severe wind and earthquake hazard

    Energy Technology Data Exchange (ETDEWEB)

    Mishima, J.; Schwendiman, L.C.; Ayer, J.E.; Owzarski, E.L.

    1980-02-01

    The potential airborne releases of plutonium from postulated damage sustained by the Exxon Nuclear Company's Mixed Oxide Fabrication Plant at Richland, Washington, as a result of various levels of wind and earthquake hazard, are estimated. The releases are based on damage scenarios that range up to 250 mph for wind hazard and in excess of 1.0 g ground acceleration for seismic hazard, which were developed by other specialists. The approaches and factors used to estimate the releases (inventories of dispersible materials at risk, damage levels and ratios, fractional airborne releases of dispersible materials under stress, atmosphere exchange rates, and source term ranges) are discussed. Release estimates range from less than 10/sup -7/ g to greater than 14 g of plutonium over a four-day period.

  11. Performance of prototype authentication equipment for A C/S system at the Plutonium Fuel Production Facility

    International Nuclear Information System (INIS)

    The Power Reactor and Nuclear Fuel Development Corporation (PNC) designed an Advanced Containment and Surveillance System (A C/S) for its Plutonium Fuel Production facility at Tokai-Mura, Japan. PNC entered into an agreement with the US Department of Energy (DOE) to have Sandia National Laboratories (SNL) develop options for authenticating the information provided by the A C/S System, as well as to develop PNC-selected hardware for demonstration purposes. The equipment was installed in the early summer of 1989, and has undergone performance evaluation since that time. The key technologies being evaluated include authentication item monitoring, video and digital signal authentication, and event data logging, plus the system integration of these components. A review of the performance of this equipment will be highlighted. 3 refs., 4 figs

  12. IODATE METHOD FOR PURIFYING PLUTONIUM

    Science.gov (United States)

    Stoughton, R.W.; Duffield, R.B.

    1958-10-14

    A method is presented for removing radioactive fission products from aqueous solutions containing such fission products together with plutonium. This is accomplished by incorporating into such solutions a metal iodate precipitate to remove fission products which form insoluble iodates. Suitable metal iodates are those of thorium and cerium. The plutonium must be in the hexavalent state and the pH of the solution must be manintained at less than 2.

  13. Assessment of plutonium in the Savannah River Site environment

    International Nuclear Information System (INIS)

    Plutonium in the Savannah River Site Environment is published as a part of the Radiological Assessment Program (RAP). It is the fifth in a series of eight documents on individual radioisotopes released to the environment as a result of Savannah River Site (SRS) operations. These are living documents, each to be revised and updated on a two-year schedule. This document describes the sources of plutonium in the environment, its release from SRS, environmental transport and ecological concentration of plutonium, and the radiological impact of SRS releases to the environment. Plutonium exists in the environment as a result of above-ground nuclear weapons tests, the Chernobyl accident, the destruction of satellite SNAP 9-A, plane crashes involving nuclear weapons, and small releases from reactors and reprocessing plants. Plutonium has been produced at SRS during the operation of five production reactors and released in small quantities during the processing of fuel and targets in chemical separations facilities. Approximately 0.6 Ci of plutonium was released into streams and about 12 Ci was released to seepage basins, where it was tightly bound by clay in the soil. A smaller quantity, about 3.8 Ci, was released to the atmosphere. Virtually all releases have occurred in F- and H-Area separation facilities. Plutonium concentration and transport mechanisms for the atmosphere, surface water, and ground water releases have been extensively studied by Savannah River Technology Center (SRTC) and ecological mechanisms have been studied by Savannah River Ecology Laboratory (SREL). The overall radiological impact of SRS releases to the offsite maximum individual can be characterized by a total dose of 15 mrem (atmospheric) and 0.18 mrem (liquid), compared with the dose of 12,960 mrem from non-SRS sources during the same period of time (1954--1989). Plutonium releases from SRS facilities have resulted in a negligible impact to the environment and the population it supports

  14. Recent development of technology in MOX fuel production system. Technological development for reduction of plutonium hold-up in the process

    International Nuclear Information System (INIS)

    Tokai Works, Power Reactor and Nuclear Fuel Development Corporation (PNC) has been engaged in the technical development of remote-controlled production of uranium-plutonium mixed-oxide (MOX) and trying to solve various problems concerning the equipments for remote and automatic operation, the production of MOX fuel and security measures etc. Recent technological developments were reviewed here focusing on the development of the techniques for reducing the plutonium hold-up. Pu-recovering from the hold-up is very difficult because of the distribution in the glove box. Thus, the following three attempts were made. The hold-up amount was reduced as possible by dismantling the instruments in the glove box in order to wash-out and recover the plutonium. Second, the assay accuracy of Glove Box Assay System (GBAS) was improved by removing the influence from the adjacent glove box and raising the position-dependency. And improvement of the system for the production of MOX fuel was performed by constructing in a compact size, speeding up the data processing and raising the efficiency in the maintenance and manipulation. The amount of plutonium hold up was successfully reduced as well as the generation. (M.N.)

  15. Photovoltaic power plants: production calculation

    Energy Technology Data Exchange (ETDEWEB)

    Cirillo, E.; Lazzarin, R.

    Rational sizing of a photovoltaic plant requires a good evaluation of the obtainable electric energy as a function of the many meteorological and plant parameters. A computing procedure is described in detail together with a fully developed numerical example. The procedure is based on monthly usability. It is reliable and it allows designers to take into account the influence of the main plant parameters within rather wide ranges.

  16. SULFIDE METHOD PLUTONIUM SEPARATION

    Science.gov (United States)

    Duffield, R.B.

    1958-08-12

    A process is described for the recovery of plutonium from neutron irradiated uranium solutions. Such a solution is first treated with a soluble sullide, causing precipitation of the plutoniunn and uraniunn values present, along with those impurities which form insoluble sulfides. The precipitate is then treated with a solution of carbonate ions, which will dissolve the uranium and plutonium present while the fission product sulfides remain unaffected. After separation from the residue, this solution may then be treated by any of the usual methods, such as formation of a lanthanum fluoride precipitate, to effect separation of plutoniunn from uranium.

  17. International plutonium policy

    International Nuclear Information System (INIS)

    As any other fissile material, the plutonium raises several utilization problems, particularly as far as diversion by sub-national groups or proliferation are concerned. The purpose of this paper is to show that these problems can be given reasonable solutions avoiding over penalties on energy production

  18. Plutonium: An introduction

    International Nuclear Information System (INIS)

    This report is a summary of the history and properties of plutonium. It presents information on the atoms, comparing chemical and nuclear properties. It looks at the history of the atom, including its discovery and production methods. It summarizes the metallurgy and chemistry of the element. It also describes means of detecting and measuring the presence and quantity of the element

  19. Medicinal plants: production and biochemical characterization

    International Nuclear Information System (INIS)

    Recent advances in the area of biotechnology offer some possibility for the development of new technologies for the conservation, characterization and mass production of medicinal plant species, (i.e. in vitro cell culture techniques for the mass production of sterile, consistent, standardized medicinal plant materials). This paper discussed the following subjects - plant tissue culture, de novo shoot organogenesis, de novo root organogenesis, somatic embryogenesis, large scale propagation in bioreactors and discovery of unique biomolecules

  20. Towards a Plutonium Market

    International Nuclear Information System (INIS)

    Taking as their starting point the various power reactor construction programmes, the authors estimate in the first part of the paper the production of plutonium in the non-socialist world for the period up to 1980. They also estimate the plutonium requirements of the various fast reactor programmes. For the period up to 1970-71, it is found that United States requirements will be satisfied only by drawing on the United States Atomic Energy Commission's stocks and through the exchange agreement with the United Kingdom. For the rest of the world, resources and requirements will be more or less in equilibrium. From 1971 onwards production will greatly exceed the requirements of fast reactors, which will still only be at the prototype stage. If it is assumed that the large-scale construction of fast reactors will not begin until ten years later, the only outlet for plutonium, for which there will no longer be a guarantee of repurchase by the USAEC in the case of enriched uranium reactors, will consist of recycling in thermal reactors. Storage with a view to re-use in breeders at a more remote and indeterminate date would impose an intolerable financial burden on power reactor operators. The question thus arises whether a collapse in the price of plutonium will occur after 1970. In the second part of the paper the authors attempt to predict the course of such a price collapse, followed by a rise as breeders enter service on a commercial basis. They discuss the effects that the absence of plutonium stocks and die competition of recycling in thermal reactors might have on the commercial introduction of breeders. Finally, an attempt is made to determine by what mechanisms a harmonious market for plutonium could be assured during the next fifteen years. (author)

  1. Miniaturization of uranium/plutonium/fission products separation: design of a 'lab-on-CD' micro-system and application

    International Nuclear Information System (INIS)

    The chemical analysis of spent nuclear fuels is essential to design future nuclear fuels cycle and reprocessing methods but also for waste management. The analysis cycle consists of several chemical separation steps which are time consuming and difficult to implement due to confinement in glove boxes. It is required that the separation steps be automated and that the volume of radioactive waste generated be reduced. The design of automated, miniaturized and disposable analytical platforms should fulfill these requirements. This project aims to provide an alternative to the first analytical step of the spent fuels analysis: the chromatographic separation of Uranium and Plutonium from the minor actinides and fission products. The goal is to design a miniaturized platform showing analytical performances equivalent to the current process, and to reduce both the exposure of workers through automation, and the volume of waste produced at the end of the analysis cycle. Thus, the separation has been implemented on a disposable plastic micro-system (COC), specifically designed for automation: a lab on a Compact Disk or lab-on-CD. The developed prototype incorporates an anion-exchange monolithic micro-column whose in-situ synthesis as well as surface functionalization have been optimized specifically for the desired separation. The development of an adapted separation protocol was carried out using a simulation tool modeling the elution of the various elements of interest. This tool is able to predict the column geometry (length and cross section) suited to obtain pure fractions of Uranium and Plutonium as a function of the sample composition. Finally, the prototype is able to automatically carry out four separations simultaneously reducing the number of manipulations, the analysis time and reducing the volume of liquid waste by a factor of 1000. (author)

  2. The elimination as radioactive waste of a fluorination furnace from the plutonium extraction plant (1962)

    International Nuclear Information System (INIS)

    The furnace, 1.60 x 0. 75 x 0.80 m in dimensions, was placed inside a 2. 50 x 1.25 x 2 m glove box. The operations were as follows: - removal of the furnace from the glove box; - storage of the furnace in a special container ; - reduction to a minimum volume and elimination of the glove box. A very high α activity, oxidation of the various channeling, and waste products trapped in the box necessitated special safety measures such as fixing of the contamination, crushing, the use of appropriate vinyl envelopes. This long and tedious work was carried out with no resulting bodily or atmospheric contamination. (authors)

  3. Design concepts for an analytical chemistry laboratory to support plutonium processing

    International Nuclear Information System (INIS)

    The Idaho National Engineering Laboratory was chosen as the preferred site for the location of the special isotope separation (SIS) production plant. The SIS plant will use the atomic vapor laser isotope separation process to ionize the undesirable isotopes of plutonium (238Pu, 240Pu, and 241Pu) in the metal vapor and separate them electrostatically from the desirable isotope 239Pu. Feed to the plant will be reactor-grade plutonium oxide, and the product will be weapons-grade plutonium metal. The SIS plant uses both pyrochemical and aqueous processes. An analytical laboratory, the Material and Process Control Laboratory (MPCL), was designed for making chemical measurements for process control, material control and accountability, and criticality safety

  4. Design concepts for an analytical chemistry laboratory to support plutonium processing

    Energy Technology Data Exchange (ETDEWEB)

    Wade, M.A.; Treibs, H.A.; Hartenstein, S.D.

    1990-01-01

    The Idaho National Engineering Laboratory was chosen as the preferred site for the location of the special isotope separation (SIS) production plant. The SIS plant will use the atomic vapor laser isotope separation process to ionize the undesirable isotopes of plutonium ([sup 238]Pu, [sup 240]Pu, and [sup 241]Pu) in the metal vapor and separate them electrostatically from the desirable isotope [sup 239]Pu. Feed to the plant will be reactor-grade plutonium oxide, and the product will be weapons-grade plutonium metal. The SIS plant uses both pyrochemical and aqueous processes. An analytical laboratory, the Material and Process Control Laboratory (MPCL), was designed for making chemical measurements for process control, material control and accountability, and criticality safety.

  5. Plutonium Proliferation: The Achilles Heel of Disarmament

    Energy Technology Data Exchange (ETDEWEB)

    Leventhal, Paul (President, Nuclear Control Institute, Washington D.C.)

    2001-02-07

    Plutonium is a byproduct of nuclear fission, and it is produced at the rate of about 70 metric tons a year in the world's nuclear power reactors. Concerns about civilian plutonium ran high in the 1970s and prompted enactment of the Nuclear Non-Proliferation Act of 1978 to give the United States a veto over separating plutonium from U.S.-supplied uranium fuel. Over the years, however, so-called reactor-grade plutonium has become the orphan issue of nuclear non-proliferation, largely as a consequence of pressures from plutonium-separating countries. The demise of the fast breeder reactor and the reluctance of utilities to introduce plutonium fuel in light-water reactors have resulted in large surpluses of civilian, weapons-usable plutonium, which now approach in size the 250 tons of military plutonium in the world. Yet reprocessing of spent fuel for recovery and use of plutonium proceeds apace outside the United States and threatens to overwhelm safeguards and security measures for keeping this material out of the hands of nations and terrorists for weapons. A number of historical and current developments are reviewed to demonstrate that plutonium commerce is undercutting efforts both to stop the spread of nuclear weapons and to work toward eliminating existing nuclear arsenals. These developments include the breakdown of U.S. anti-plutonium policy, the production of nuclear weapons by India with Atoms-for-Peace plutonium, the U.S.-Russian plan to introduce excess military plutonium as fuel in civilian power reactors, the failure to include civilian plutonium and bomb-grade uranium in the proposed Fissile Material Cutoff Treaty, and the perception of emerging proliferation threats as the rationale for development of a ballistic missile defense system. Finally, immobilization of separated plutonium in high-level waste is explored as a proliferation-resistant and disarmament-friendly solution for eliminating excess stocks of civilian and military plutonium.

  6. AVLIS Production Plant Project Management Plan

    International Nuclear Information System (INIS)

    The AVLIS Production Plant is designated as a Major System Acquisition (in accordance with DOE Order 4240.IC) to deploy Atomic Vapor Laser Isotope Separation (AVLIS) technology at the Oak Ridge, Tennessee site, in support of the US Uranium Enrichment Program. The AVLIS Production Plant Project will deploy AVLIS technology by performing the design, construction, and startup of a production plant that will meet capacity production requirements of the Uranium Enrichment Program. The AVLIS Production Plant Project Management Plan has been developed to outline plans, baselines, and control systems to be employed in managing the AVLIS Production Plant Project and to define the roles and responsibilities of project participants. Participants will develop and maintain detailed procedures for implementing the management and control systems in agreement with this plan. This baseline document defines the system that measures work performed and costs incurred. This plan was developed by the AVLIS Production Plant Project staff of Martin Marietta Energy Systems, Inc. and Lawrence Livermore National Laboratory in accordance with applicable DOE directives, orders and notices. 38 figures, 19 tables

  7. AVLIS Production Plant Project Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    1984-11-15

    The AVLIS Production Plant is designated as a Major System Acquisition (in accordance with DOE Order 4240.IC) to deploy Atomic Vapor Laser Isotope Separation (AVLIS) technology at the Oak Ridge, Tennessee site, in support of the US Uranium Enrichment Program. The AVLIS Production Plant Project will deploy AVLIS technology by performing the design, construction, and startup of a production plant that will meet capacity production requirements of the Uranium Enrichment Program. The AVLIS Production Plant Project Management Plan has been developed to outline plans, baselines, and control systems to be employed in managing the AVLIS Production Plant Project and to define the roles and responsibilities of project participants. Participants will develop and maintain detailed procedures for implementing the management and control systems in agreement with this plan. This baseline document defines the system that measures work performed and costs incurred. This plan was developed by the AVLIS Production Plant Project staff of Martin Marietta Energy Systems, Inc. and Lawrence Livermore National Laboratory in accordance with applicable DOE directives, orders and notices. 38 figures, 19 tables.

  8. Natural products – learning chemistry from plants

    NARCIS (Netherlands)

    Staniek, A.; Bouwmeester, H.J.; Fraser, P.D.; Kayser, O.; Martens, S.; Tissier, A.; Krol, van der A.R.; Wessjohann, L.; Warzecha, H.

    2014-01-01

    Plant natural products (PNPs) are unique in that they represent a vast array of different structural features, ranging from relatively simple molecules to very complex ones. Given the fact that many plant secondary metabolites exhibit profound biological activity, they are frequently used as fragran

  9. Operational management in pot plant production.

    NARCIS (Netherlands)

    Leutscher, K.J.

    1995-01-01

    Operational management in pot plant production was investigated by means of system analysis and simulation. A theoretical framework for operational decision-making consisted of elaboration decisions, progress decisions, and adoption decisions. This framework was incorporated in a pot plant nursery m

  10. AVLIS production plant waste management plan

    International Nuclear Information System (INIS)

    Following the executive summary, this document contains the following: (1) waste management facilities design objectives; (2) AVLIS production plant wastes; (3) waste management design criteria; (4) waste management plan description; and (5) waste management plan implementation. 17 figures, 18 tables

  11. AVLIS production plant waste management plan

    Energy Technology Data Exchange (ETDEWEB)

    1984-11-15

    Following the executive summary, this document contains the following: (1) waste management facilities design objectives; (2) AVLIS production plant wastes; (3) waste management design criteria; (4) waste management plan description; and (5) waste management plan implementation. 17 figures, 18 tables.

  12. Plutonium generated by commercial reactors presents danger

    International Nuclear Information System (INIS)

    This article summarizes a 1995 keynote address by Dr. Paul Cunningham, Program Director for Nuclear Materials at Los Alamos National Laboratory which highlights the growing plutonium problem. Plutonium production for weapons use has ceased in the US and the former Soviet Union, but the production in commercial reactors, where it is considered a waste product, continues. The amount of plutonium already existing in spent reactor fuel is 5 times as large as the amount both countries have for their weapons. One solution is to use plutonium to generate power

  13. Plutonium disposition study phase 1b final report

    International Nuclear Information System (INIS)

    This report provides the results of the Westinghouse activities performed as part of the Plutonium Disposition Study Phase 1b. These activities, which took place from May 16, 1993 to September 15, 1993, build upon the work completed in Phase 1a, which concluded on May 15, 1993. In Phase 1a, three Plutonium Disposal Reactor (PDR) options were developed for the disposal of excess weapons grade plutonium from returned and dismantled nuclear weapons. This report documents the results of several tasks that were performed to further knowledge in specific areas leading up to Phase 2 of the PDR Study. The Westinghouse activities for Phase 1b are summarized as follows: (1) resolved technical issues concerning reactor physics including equilibrium cycle calculations, use of gadolinium, moderator temperature coefficient, and others as documented in Section 2.0; (2) analyzed large Westinghouse commercial plants for plutonium disposal; (3) reactor safety issues including the steam line break were resolved, and are included in Section 2.0; (4) several tasks related to the PDR Fuel Cycle were examined; (5) cost and deployment options were examined to determine optimal configuration for both plutonium disposal and tritium production; (6) response to questions from DOE and National Academy of Scientists (NAS) reviewers concerning the PDR Phase 1a report are included in Appendix A

  14. Freshwater aquatic plant biomass production in Florida

    Energy Technology Data Exchange (ETDEWEB)

    Reddy, K.R.; Sutton, D.L.; Bowes, G.

    1983-01-01

    About 8% (1.2 million ha) of the total surface area of Florida is occupied by freshwater. Many of these water bodies are eutrophic. Nutrients present in these water bodies can be potentially used to culture aquatic plants as a possible feedstock for methane production. This paper summarizes the results of known research findings on biomass production potential of freshwater aquatic plants in Florida and identifies key research needs to improve the quality and quantity of biomass yields. Among floating aquatic plants, biomass yield potential was in the order of water-hyacinth > water lettuce > pennywort > salvinia > duckweed > azolla. Pennywort, duckweed, and azolla appear to perform well during the cooler months compared to other aquatic plants. Among emergent plants, biomass yield potential was in the order of southern wild rice > cattails > soft rush > bulrush. Cultural techniques, nutrient management, and environmental factors influencing the biomass yields were discussed. 68 references.

  15. Plutonium, {sup 137}Cs and {sup 90}Sr in selected invertebrates from some areas around Chernobyl nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Mietelski, Jerzy W., E-mail: jerzy.mietelski@ifj.edu.p [Henryk Niewodniczanski Institute of Nuclear Physics, Polish Academy of Sciences, Radzikowskiego 152, 31-342 Krakow (Poland); Maksimova, Svetlana, E-mail: soilzool@biobel.bas-net.b [Institute of Zoology, National Academy of Sciences, Akademicheskaya 27, 220072 Minsk (Belarus); Szwalko, Przemyslaw [Institute of Systematics and Evolution of Animals, Polish Academy of Sciences, Slawkowska 17, 31-016 Krakow (Poland); Wnuk, Katarzyna [Holycross Cancer Center, Department on Nuclear Medicine, Artwinskiego 3, 25-734 Kielce (Poland); Zagrodzki, Pawel [Henryk Niewodniczanski Institute of Nuclear Physics, Polish Academy of Sciences, Radzikowskiego 152, 31-342 Krakow (Poland); Department of Food Chemistry and Nutrition, Medical College, Jagiellonian University, Medyczna 9, 30-688 Krakow (Poland); Blazej, Sylwia; Gaca, Pawel; Tomankiewicz, Ewa [The Henryk Niewodniczanski Institute of Nuclear Physics, Polish Academy of Sciences, Radzikowskiego 152, 31-342 Krakow (Poland); Orlov, Olexandr, E-mail: station@zt.ukrpack.ne [Poleskiy Branch of Ukrainian Scientific Research Institute of Forestry and Agro-Forest-Amelioration, Prospect Mira 38, Zhytomyr 10004 (Ukraine)

    2010-06-15

    Results are presented for {sup 137}Cs, {sup 90}Sr and plutonium activity concentrations in more than 20 samples of terrestrial invertebrates, including species of beetles, ants, spiders and millipedes, collected in the highly contaminated area of the Chernobyl exclusion zone. The majority of samples were collected in Belarus, with some also collected in the Ukraine. Three other samples were collected in an area of lower contamination. Results show that seven samples exceed an activity concentration of 100 kBq/kg (ash weight - a.w.) for {sup 137}Cs. The maximum activity concentration for this isotope was 1.52 +- 0.08 MBq/kg (a.w.) determined in ants (Formica cynerea). Seven results for {sup 90}Sr exceeded 100 kBq/kg (a.w.), mostly for millipedes. Relatively high plutonium activity concentrations were found in some ants and earth-boring dung beetles. Analyses of activity ratios showed differences in transfer of radionuclides between species. To reveal the correlation structure of the multivariate data set, the Partial Least-Squares method (PLS) was used. Results of the PLS model suggest that high radiocesium activity concentrations in animal bodies can be expected mainly for relatively small creatures living on the litter surface. In contrast, high strontium activity concentrations can be expected for creatures which conduct their lives within litter, having mixed trophic habits and a moderate lifespan. No clear conclusions could be made for plutonium.

  16. International plutonium policy

    International Nuclear Information System (INIS)

    The need to distinguish between diversion by sub-national groups and by governments is clearly stated. The paper identifies the international safeguards measures which already exist for the handling of plutonium. It proposes that the implementation of Article XII A5 of the IAEA statute concerning the international storage of plutonium could be an important additional measure. The paper also mentions the concept of using confinement as a complimentary safeguards measure and identifies the PIPEX concept. In addition, greater use is proposed of containment and surveillance procedures. The multiplication of small reprocessing plants spread over many countries is perceived as a proliferation risk. Other means such as co-location of reprocessing and fuel fabrication facilities are relevant to diversion by sub-national groups

  17. Oxidation of plutonium dioxide.

    Science.gov (United States)

    Korzhavyi, Pavel A; Vitos, Levente; Andersson, David A; Johansson, Börje

    2004-04-01

    The physics and chemistry of the actinide elements form the scientific basis for rational handling of nuclear materials. In recent experiments, most unexpectedly, plutonium dioxide has been found to react with water to form higher oxides up to PuO(2.27), whereas PuO(2) had always been thought to be the highest stable oxide of plutonium. We perform a theoretical analysis of this complicated situation on the basis of total energies calculated within density functional theory combined with well-established thermodynamic data. The reactions of PuO(2) with either O(2) or H(2)O to form PuO(2+delta) are calculated to be endothermic: that is, in order to occur they require a supply of energy. However, our calculations show that PuO(2+delta) can be formed, as an intermediate product, by reactions with the products of radiolysis of water, such as H(2)O(2). PMID:15034561

  18. Managing plutonium in Britain. Current options

    International Nuclear Information System (INIS)

    This is the report of a two day meeting to discuss issues arising from the reprocessing of plutonium and production of mixed oxide nuclear fuels in Britain. It was held at Charney Manor, near Oxford, on June 25 and 26, 1998, and was attended by 35 participants, including government officials, scientists, policy analysts, representatives of interested NGO's, journalists, a Member of Parliament, and visiting representatives from the US and Irish governments. The topic of managing plutonium has been a consistent thread within ORG's work, and was the subject of one of our previous reports, CDR 12. This particular seminar arose out of discussions earlier in the year between Dr. Frank Barnaby and the Rt. Hon. Michael Meacher MP, Minister for the Environment. With important decisions about the management of plutonium in Britain pending, ORG undertook to hold a seminar at which all aspects of the subject could be aired. A number of on-going events formed the background to this initiative. The first was British Nuclear Fuels' [BNFL] application to the Environment Agency to commission a mixed oxide fuel [MOX] plant at Sellafield. The second was BNFL's application to vary radioactive discharge limits at Sellafield. Thirdly, a House of Lords Select Committee was in process of taking evidence, on the disposal of radioactive waste. Fourthly, the Royal Society, in a recent report entitled Management of Separated Plutonium, recommended that 'the Government should commission a comprehensive review... of the options for the management of plutonium'. Four formal presentations were made to the meeting, on the subjects of Britain's plutonium policy, commercial prospects for plutonium use, problems of plutonium accountancy, and the danger of nuclear terrorism, by experts from outside the nuclear industry. It was hoped that the industry's viewpoint would also be heard, and BNFL were invited to present a paper, but declined on the grounds that they were 'currently involved in a formal

  19. 238Pu: accumulation, tissue distribution, and excretion in Mayak workers after exposure to plutonium aerosols.

    Science.gov (United States)

    Suslova, Klara G; Sokolova, Alexandra B; Khokhryakov, Viktor V; Miller, Scott C

    2012-03-01

    The alpha spectrometry measurements of specific activity of 238Pu and 239Pu in urine from bioassay examinations of 1,013 workers employed at the radiochemical and plutonium production facilities of the Mayak Production Association and in autopsy specimens of lung, liver, and skeleton from 85 former nuclear workers who died between 1974-2009, are summarized.The accumulation fraction of 238Pu in the body and excreta has not changed with time in workers involved in production of weapons-grade plutonium production (e.g., the plutonium production facility and the former radiochemical facility). The accumulation fraction of 238Pu in individuals exposed to plutonium isotopes at the newer Spent Nuclear Fuel Reprocessing Plant ranged from 0.13% up to 27.5% based on the autopsy data. No statistically significant differences between 238Pu and 239Pu in distribution by the main organs of plutonium deposition were found in the Mayak workers. Based on the bioassay data,the fraction of 238Pu activity in urine is on average 38-69% of the total activity of 238Pu and 239Pu, which correlates with the isotopic composition in workplace air sampled at the Spent Nuclear Fuel Reprocessing Plant. In view of the higher specific activity of 238Pu, the contribution of 238Pu to the total internal dose, particularly in the skeleton and liver, might be expected to continue to increase, and continued surveillance is recommended.

  20. Medical Radioisotope Production in a Power-Flattened ADS Fuelled with Uranium and Plutonium Dioxides

    OpenAIRE

    Gizem Bakır; Saltuk Buğra Selçuklu; Hüseyin Yapıcı

    2016-01-01

    This study presents the medical radioisotope production performance of a conceptual accelerator driven system (ADS). Lead-bismuth eutectic (LBE) is selected as target material. The subcritical fuel core is conceptually divided into ten equidistant subzones. The ceramic (natural U, Pu)O2 fuel mixture and the materials used for radioisotope production (copper, gold, cobalt, holmium, rhenium, thulium, mercury, palladium, thallium, molybdenum, and yttrium) are separately prepared as cylindrical r...

  1. Plant protection products in organic grapevine growing

    Directory of Open Access Journals (Sweden)

    Sivčev Branislava V.

    2010-01-01

    Full Text Available Pests and grapevine diseases in organic production are suppressed by preventive measures with a view to reducing the impact of the attack. Allowed substances acting on patogenous fungi, insects, mites and other harmful organisms are used, if appropriate. Insecticides of plant origin are used in the organic production of grapevine, as well as vegetable oils, powders and insecticidal soaps that are selective, with a narrow range of effects and of lower toxicity, as well as biological products. As a rule, such plant protection products require a more frequent application. Copper-based and sulphur-based fungicides are still leading products in suppressing grapevine diseases. Researches are directed to decrease the quantity of application and to find their replacement by also efficient fungicides. A special emphasis is put on researching the efficient fungicides for suppressing Botrytis bunch rot and factors causing grapevine wood diseases (Esca and Eutypa in organic production. Along with copper and sulphur, different substances such as bicarbonates, plant extracts and oils, biological products being parasites, patogenous or diseases agent antagonists, and natural products such as milk and whey are applied in the organic production of grapevine.

  2. Preparation of plutonium hexafluoride. Recovery of plutonium from waste dross (1962)

    International Nuclear Information System (INIS)

    The object of this work is to study the influence of various physical factors on the rate of fluorination of solid plutonium tetrafluoride by fluorine. In a horizontal oven with a circulation for pure fluorine at atmospheric pressure and 520 deg. C, at a fluorine rate of 9 litres/hour, it is possible to transform 3 g of tetrafluoride to hexafluoride with about 100 per cent transformation and a recovery yield of over 90 per cent, in 4 to 5 hours. The fluorination rate is a function of the temperature, of the fluorine flow-rate, of the crucible surface, of the depth of the tetrafluoride layer and of the reaction time. It does not depend on the diffusion of the fluorine into the solid but is determined by the reaction at the gas-solid interface and obeys the kinetic law (1 - TT)1/3 = kt + 1. The existence of intermediate fluorides, in particular Pu4 F17, is confirmed by a break in the Arrhenius plot at about 370 deg. C, by differences in the fluorination rates inside the tetrafluoride layer, and by reversible colour changes. The transformation to hexafluoride occurs with a purification with respect of the foreign elements present in the initial plutonium. Recovery of plutonium from waste dross: The study is based on the transformation of occluded plutonium particles to gaseous hexafluoride which is then decomposed thermally to the tetrafluoride which can be reintroduced directly in the production circuit. Under the conditions considered this process is not applicable industrially. After milling, it is possible to separate the dross into enriched (75 per cent Pu in 2.6 per cent by weight of dross) and depleted portions. By prolonged fluorination (16 hours) of the various fractions it is possible to recover about 80 per cent of the plutonium. A treatment plant using fluidization, as described at the end of this study, should make it possible to substantially improve the yield. (author)

  3. Aqueous Chloride Operations Overview: Plutonium and Americium Purification/Recovery

    Energy Technology Data Exchange (ETDEWEB)

    Kimball, David Bryan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Skidmore, Bradley Evan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-06-22

    Acqueous Chloride mission is to recover plutonium and americium from pyrochemical residues (undesirable form for utilization and storage) and generate plutonium oxide and americium oxide. Plutonium oxide is recycled into Pu metal production flowsheet. It is suitable for storage. Americium oxide is a valuable product, sold through the DOE-OS isotope sales program.

  4. Where to dispose Plutonium? Options and decision criteria

    International Nuclear Information System (INIS)

    The main topics of this information report on Plutonium are: base information on Plutonium like production, detection, toxicity, possibilities for weapon production, inventory and quantity; utilization in reactors; concepts on removal of Plutonium e.g. vitrification, underground explosions and shooting in space; evaluation of different options: environmental and safety risks, proliferation resistance; safeguards and verification; international laws: agreements and regulation demand on the removal of Plutonium. (GL)

  5. Mo99 Production Plant Layout

    Energy Technology Data Exchange (ETDEWEB)

    Woloshun, Keith Albert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dale, Gregory E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Naranjo, Angela Carol [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-06-25

    The NorthStar Medical Technologies 99Mo production facility configuration is envisioned to be 8 accelerator pairs irradiating 7 100Mo targets (one spare accelerator pair undergoing maintenance while the other 7 pairs are irradiating targets). The required shielding in every direction for the accelerators is initially estimated to be 10 feet of concrete. With the accelerator pairs on one (ground) level and spaced with the required shielding between adjacent pairs, the only practical path for target insertion and removal while minimizing floor space is vertical. The current scheme then requires a target vertical lift of nominally 10 feet through a shield stack. It is envisioned that the lift will be directly into a hot cell where an activated target can be removed from its holder and a new target attached and lowered. The hot cell is on a rail system so that a single hot cell can service all active target locations, as well as deliver the ready targets to the separations lab. On this rail system, coupled to the hot cell, will be a helium recovery and clean-up system. All helium coolant equipment is located on the upper level near to the target removal point.

  6. 78 FR 1848 - Plutonium-238 Production for Radioisotope Power Systems for National Aeronautics and Space...

    Science.gov (United States)

    2013-01-09

    ... foreseeable future in the NI PEIS (DOE/EIS-0310), which was issued on December 15, 2000 (65 FR 78484). The NI... production capabilities. The NI PEIS ROD was published on January 26, 2001 (66 FR 7877). In the ROD, DOE had... determined that no additional NEPA documentation was necessary and amended its ROD (69 FR 50180, August...

  7. Seaborg's Plutonium ?

    CERN Document Server

    Norman, Eric B; Telhami, Kristina E

    2014-01-01

    Passive x-ray and gamma-ray analysis was performed on UC Berkeley's EH&S Sample S338. The object was found to contain Pu-239 and no other radioactive isotopes. The mass of Pu-239 contained in this object was determined to be 2.0 +- 0.3 micrograms. These observations are consistent with the identification of this object being the 2.77-microgram plutonium oxide sample described by Glenn Seaborg and his collaborators as the first sample of Pu-239 that was large enough to be weighed.

  8. Development of an Efficient Approach to Perform Neutronics Simulations for Plutonium-238 Production

    Energy Technology Data Exchange (ETDEWEB)

    Chandler, David [ORNL; Ellis, Ronald James [ORNL

    2016-01-01

    Conversion of 238Pu decay heat into usable electricity is imperative to power National Aeronautics and Space Administration (NASA) deep space exploration missions; however, the current stockpile of 238Pu is diminishing and the quality is less than ideal. In response, the US Department of Energy and NASA have undertaken a program to reestablish a domestic 238Pu production program and a technology demonstration sub-project has been initiated. Neutronics simulations for 238Pu production play a vital role in this project because the results guide reactor safety-basis, target design and optimization, and post-irradiation examination activities. A new, efficient neutronics simulation tool written in Python was developed to evaluate, with the highest fidelity possible with approved tools, the time-dependent nuclide evolution and heat deposition rates in 238Pu production targets irradiated in the High Flux Isotope Reactor (HFIR). The Python Activation and Heat Deposition Script (PAHDS) was developed specifically for experiment analysis in HFIR and couples the MCNP5 and SCALE 6.1.3 software quality assured tools to take advantage of an existing high-fidelity MCNP HFIR model, the most up-to-date ORIGEN code, and the most up-to-date nuclear data. Three cycle simulations were performed with PAHDS implementing ENDF/B-VII.0, ENDF/B-VII.1, and the Hybrid Library GPD-Rev0 cross-section libraries. The 238Pu production results were benchmarked against VESTA-obtained results and the impact of various cross-section libraries on the calculated metrics were assessed.

  9. Medical Radioisotope Production in a Power-Flattened ADS Fuelled with Uranium and Plutonium Dioxides

    Directory of Open Access Journals (Sweden)

    Gizem Bakır

    2016-01-01

    Full Text Available This study presents the medical radioisotope production performance of a conceptual accelerator driven system (ADS. Lead-bismuth eutectic (LBE is selected as target material. The subcritical fuel core is conceptually divided into ten equidistant subzones. The ceramic (natural U, PuO2 fuel mixture and the materials used for radioisotope production (copper, gold, cobalt, holmium, rhenium, thulium, mercury, palladium, thallium, molybdenum, and yttrium are separately prepared as cylindrical rods cladded with carbon/carbon composite (C/C and these rods are located in the subzones. In order to obtain the flattened power density, percentages of PuO2 in the mixture of UO2 and PuO2 in the subzones are adjusted in radial direction of the fuel zone. Time-dependent calculations are performed at 1000 MW thermal fission power (Pth for one hour using the BURN card. The neutronic results show that the investigated ADS has a high neutronic capability, in terms of medical radioisotope productions, spent fuel transmutation and energy multiplication. Moreover, a good quasiuniform power density is achieved in each material case. The peak-to-average fission power density ratio is in the range of 1.02–1.28.

  10. Power plant productivity improvement in New York

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-03-01

    The New York Public Service Commission (PSC), under contract with the US Department of Energy (DOE), began a joint program in September 1978 to improve the productivity of coal and nuclear electric generating units in New York State. The project had dual objectives: to ensure that the utilities in New York State have or develop a systematic permanent, cost-effective productivity improvement program based on sound engineering and economic considerations, and to develop a model program for Power Plant Productivity Improvement, which, through DOE, can also be utilized by other regulatory commissions in the country. To accomplish these objectives, the program was organized into the following sequence of activities: compilation and analysis of power plant performance data; evaluation and comparison of utility responses to outage/derating events; power plant productivity improvement project cost-benefit analysis; and evaluation of regulatory procedures and policies for improving productivity. The program that developed for improving the productivity of coal units is substantially different than for nuclear units. Each program is presented, and recommendations are made for activities of both the utilities and regulatory agencies which will promote improved productivity.

  11. Experiences in Decontamination and Decommissioning (D and D) of former plutonium production reactors at the Hanford reservation

    International Nuclear Information System (INIS)

    Nine nuclear reactors were built at the Hanford reservation for plutonium production from 1943 to 1964. Eight of the reactors were shutdown by 1971, and the last in early 1987. Since then, disposition of the reactors has been incorporated into the Hanford cleanup program. The objective is to transition the reactors from their existing state of minimal maintenance and upkeep into a safe condition that can be maintained for several decades. This paper describes the decontamination and decommissioning (DandD) work performed on five of the nine reactors Reactor systems and structures, including subgrade systems such as piping were removed. An enclosure was built over the defueled reactor block. The resulting structure is called the Safe Storage Enclosure and is intended to safely house the core for at least 75 years. A permanent disposition for the facility will be determined at that time. Numerous hazards have been encountered and safely handled during this work, including the discovery of over a dozen irradiated fuel pins in one storage basin. This paper discusses how this work was integrated into the cleanup program and then moved through the DandD process. The goal is to facilitate site cleanup by quickly removing imminent hazards while not compromising safety standards during a time of reduced budgets and intense emphasis on efficiency. This paper demonstrates excellence in coordination of safety analysis and DandD field work that will soon place the reactors in a safe storage condition for several decades. Safety analysis and field programs, practices, and lessons-learned will be discussed. Efforts to convert B Reactor into a permanent museum will be briefly discussed

  12. Chemistry of plutonium revealed

    International Nuclear Information System (INIS)

    In 1941 one goal of the Manhattan Project was to unravel the chemistry of the synthetic element plutonium as rapidly as possible. In this paper the work carried out at Berkeley from the spring of 1942 to the summer of 1945 is described briefly. The aqueous chemistry of plutonium is quite remarkable. Important insights were obtained from tracer experiments, but the full complexity was not revealed until macroscopic amounts (milligrams) became available. Because processes for separation from fission products were based on aqueous solutions, such solution chemistry was emphasized, particularly precipitation and oxidation-reduction behavior. The latter turned out to be unusually intricate when it was discovered that two more oxidation states existed in aqueous solution than had previously been suspected. Further, an equilibrium was rapidly established among the four aqueous oxidation states, while at the same time any three were not in equilibrium. These and other observations made while doing a crash study of a previously unknown element are reported

  13. The plutonium cycle under high surveillance

    International Nuclear Information System (INIS)

    The plutonium is a source of strong public anxiety because of the risk of uncontrolled nuclear weapons proliferation. Several countries have decided to adopt a politics of transparency by drawing up the inventory of plutonium stocks. Most of the plutonium available comes from the operation of nuclear power plants and from the dismantlement of US and Soviet nuclear weapons. A part of plutonium reserves can be burn in fast breeder reactors while the rest can be recycled to produce the Mox (mixed oxides) fuel made of 5 to 7 % of plutonium and 93 to 95 % of uranium 238. The Mox fuel is presently tested in 20 European reactor from which seven are French. The use of Mox requires some modifications of the reactor conception such as the addition of supplementary control rods. The expectations from now to the year 2000 are to use Mox in 28 French reactors, which represents half of the EdF (Electricite de France) units. The paper describes the Melox facility sited in Marcoule (Gard, France) and devoted to the fabrication of Mox fuel from uranium and plutonium oxides. The paper also focusses on the safety and security aspects of plutonium transportation and storage. In a second part, the plutonium isotopes properties are briefly described together with the possible use of plutonium for the fabrication of radiological weapons in the case of nuclear materials diversion. (J.S.). 1 fig., 5 photos

  14. 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.

  15. Plant-Based Vaccines: Production and Challenges

    Directory of Open Access Journals (Sweden)

    Erna Laere

    2016-01-01

    Full Text Available Plant-based vaccine technologies involve the integration of the desired genes encoding the antigen protein for specific disease into the genome of plant tissues by various methods. Agrobacterium-mediated gene transfer and transformation via genetically modified plant virus are the common methods that have been used to produce effective vaccines. Nevertheless, with the advancement of science and technology, new approaches have been developed to increase the efficiency of former methods such as biolistic, electroporation, agroinfiltration, sonication, and polyethylene glycol treatment. Even though plant-based vaccines provide many benefits to the vaccine industry, there are still challenges that limit the rate of successful production of these third-generation vaccines. Even with all the limitations, continuous efforts are still ongoing in order to produce efficient vaccine for many human and animals related diseases owing to its great potentials. This paper reviews the existing conventional methods as well as the development efforts by researchers in order to improve the production of plant-based vaccines. Several challenges encountered during and after the production process were also discussed.

  16. Plant protection products in organic grapevine growing

    OpenAIRE

    Sivčev Branislava V.; Sivčev Ivan L.; Ranković-Vasić Zorica Z.

    2010-01-01

    Pests and grapevine diseases in organic production are suppressed by preventive measures with a view to reducing the impact of the attack. Allowed substances acting on patogenous fungi, insects, mites and other harmful organisms are used, if appropriate. Insecticides of plant origin are used in the organic production of grapevine, as well as vegetable oils, powders and insecticidal soaps that are selective, with a narrow range of effects and of lower toxici...

  17. Solubility product of plutonium hydrous oxide and its ionic strength dependence

    International Nuclear Information System (INIS)

    The solubility of PuO2.xH2O was measured at 25 C in a NaClO4 solution containing Na2S2O4 as a reductant. The experiment was carried out by an oversaturation method at I=1.0 and by an undersaturation method at I=0.5, 1.0 and 2.0. The concentration of Pu3+ was measured by a-spectrometry and UV/Visible spectrophotometry, and the equilibrium constant of the reaction, PuO2.xH2O + e- = Pu3+ + 4 OH- + (x-2) H2O, was obtained. From the obtained results, the solubility product (Ksp) of PuO2. x H2O, for PuO2. x H2O = Pu4+ + 4 OH- + (x-2) H2O at I=0.5, 1.0 and 2.0 was determined. By using the specific interaction theory (SIT), the solubility product of PuO2.xH2O at the standard state (I=0) was determined to be log Ksp0= -57.97±0.24, and the ion interaction coefficient e(Pu4+, ClO4-) was also evaluated to be 0.99±0.20

  18. How not to reduce plutonium stocks. The danger of MOX-fuelled nuclear reactors

    International Nuclear Information System (INIS)

    Plutonium is a radioactive by-product of nuclear reactor operation and one of the most toxic substances known. The world would be a safer place if the governments of countries with stocks of it, including Britain, would adopt effective policies for reducing and managing them. Two recent authoritative reports recommend that the British government take urgent action to reduce its 'civil' plutonium stock - currently one quarter of the world's total and set to rise to about two-thirds by the year 2010. The March 1999 House of Lords report, Management of Nuclear Waste, concludes that British government policy on plutonium 'should be the maintenance of the minimum strategic stock, and the declaration of the remainder as waste'. A report from the Royal Society, Britain's main learned society, meanwhile states that: 'In addition to disposing of some of the plutonium already in the stockpile, steps should be taken to reduce the amount added to it each year, primarily by reducing the amount of reprocessing carried out'. The government's reply to the House of Lords is expected to be followed by a public consultation before changes in legislation are proposed. But, at the same time, the government is considering an application from British Nuclear Fuels Limited (BNFL), the government-owned company which separates plutonium from spent nuclear fuel rods, for a licence to operate a new plant at Sellafield in Cumbria to produce mixed-oxide (MOX) nuclear fuel from its plutonium stockpile. The nuclear industry justifies the Sellafield MOX plant as one way of reducing plutonium stocks. But critics point out that this is not a rational way to manage plutonium. This briefing aims to contribute to an informed debate during the current flurry of British government nuclear policy making by explaining why

  19. How not to reduce plutonium stocks. The danger of MOX-fuelled nuclear reactors

    International Nuclear Information System (INIS)

    Plutonium is a radioactive by-product of nuclear reactor operation and one of the most toxic substances known. The world would be a safer place if the governments of countries with stocks of it, including Britain, would adopt effective policies for reducing and managing them. Two recent authoritative reports recommend that the British government take urgent action to reduce its 'civil' plutonium stock - currently one quarter of the world's total and set to rise to about two-thirds by the year 2010. The March 1999 House of Lords report, Management of Nuclear Waste, concludes that British government policy on plutonium 'should be the maintenance of the minimum strategic stock, and the declaration of the remainder as waste'. A report from the Royal Society, Britain's main learned society, meanwhile states that: 'In addition to disposing of some of the plutonium already in the stockpile, steps should be taken to reduce the amount added to it each year, primarily by reducing the amount of reprocessing carried out'. The government's reply to the House of Lords is expected to be followed by a public consultation before changes in legislation are proposed. But, at the same time, the government is considering an application from British Nuclear Fuels Limited (BNFL), the government-owned company which separates plutonium from spent nuclear fuel rods, for a licence to operate a new plant at Sellafield in Cumbria to produce mixed-oxide (MOX) nuclear fuel from its plutonium stockpile. The nuclear industry justifies the Sellafield MOX plant as one way of reducing plutonium stocks. But critics point out that this is not a rational way to manage plutonium. This briefing aims to contribute to an informed debate during the current flurry of British government nuclear policymaking by explaining why. (author)

  20. Design concepts for an analytical chemistry laboratory to support plutonium processing

    Energy Technology Data Exchange (ETDEWEB)

    Wade, M.A.; Treibs, H.A.; Hartenstein, S.D.

    1990-08-31

    Design concepts were developed for an analytical chemistry laboratory to support the plutonium processing functions of the Special Isotope Separation (SIS) Production Plant. These concepts include pneumatic sample delivery, total containment of samples during analyses, robotic-based dry sample storage, continuous flow air locks for introducing supplies into the gloveboxes, and a within-laboratory sample transport system capable of multiple, simultaneous transfers.

  1. Design concepts for an analytical chemistry laboratory to support plutonium processing

    International Nuclear Information System (INIS)

    Design concepts were developed for an analytical chemistry laboratory to support the plutonium processing functions of the Special Isotope Separation (SIS) Production Plant. These concepts include pneumatic sample delivery, total containment of samples during analyses, robotic-based dry sample storage, continuous flow air locks for introducing supplies into the gloveboxes, and a within-laboratory sample transport system capable of multiple, simultaneous transfers

  2. Selecting a plutonium vitrification process

    Energy Technology Data Exchange (ETDEWEB)

    Jouan, A. [Centre d`Etudes de la Vallee du Rhone, Bagnols sur Ceze (France)

    1996-05-01

    Vitrification of plutonium is one means of mitigating its potential danger. This option is technically feasible, even if it is not the solution advocated in France. Two situations are possible, depending on whether or not the glass matrix also contains fission products; concentrations of up to 15% should be achievable for plutonium alone, whereas the upper limit is 3% in the presence of fission products. The French continuous vitrification process appears to be particularly suitable for plutonium vitrification: its capacity is compatible with the required throughout, and the compact dimensions of the process equipment prevent a criticality hazard. Preprocessing of plutonium metal, to convert it to PuO{sub 2} or to a nitric acid solution, may prove advantageous or even necessary depending on whether a dry or wet process is adopted. The process may involve a single step (vitrification of Pu or PuO{sub 2} mixed with glass frit) or may include a prior calcination step - notably if the plutonium is to be incorporated into a fission product glass. It is important to weigh the advantages and drawbacks of all the possible options in terms of feasibility, safety and cost-effectiveness.

  3. 9 CFR 355.21 - Products entering inspected plants.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Products entering inspected plants... Products entering inspected plants. All products of a kind certified under this part or materials to be used in the preparation of such products when brought into an inspected plant shall be identified...

  4. AVLIS production plant project schedule and milestones

    International Nuclear Information System (INIS)

    An AVLIS Production Plant Deployment Schedule for the engineering, procurement, and construction for both the Initial Increment of Production and the fully Activated Plant, has been developed by the project team consisting of Lawrence Livermore National Laboratory, Martin Marietta Energy Systems, Inc. with architect-engineer support from Bechtel National, Inc., Stone and Webster Engineering Corporation, and Westinghouse Corporation. The initial deployment phase consists of six separators modules and the three laser power amplifier modules consistent with the FY84 reference design with a name plate capacity of 5 million separative work units/yr followed by a full plant activation to approximately 13 million separative work units/yr. The AVLIS Production Plant project team's strategy for deployment schedule analysis focused on three schedule options: engineering limited schedule; authorization limited schedule; and funding limited project schedule. The three deployment schedule options developed by AVLIS project team have been classified in ranges such as an optimistic, rapid/moderate, or moderate/pessimistic based on the probability of meeting the individual schedule option's major milestones or program objectives of enriching uranium by the AVLIS process in an effective cost and schedule manner. 47 figures, 7 tables

  5. Terrestrial plant methane production and emission.

    Science.gov (United States)

    Bruhn, Dan; Møller, Ian M; Mikkelsen, Teis N; Ambus, Per

    2012-03-01

    In this minireview, we evaluate all experimental work published on the phenomenon of aerobic methane (CH(4) ) generation in terrestrial plants and plant. Clearly, despite much uncertainty and skepticism, we conclude that the phenomenon is true. Four stimulating factors have been observed to induce aerobic plant CH(4) production, i.e. cutting injuries, increasing temperature, ultraviolet radiation and reactive oxygen species. Further, we analyze rates of measured emission of aerobically produced CH(4) in pectin and in plant tissues from different studies and argue that pectin is very far from the sole contributing precursor. In consequence, scaling up of aerobic CH(4) emission needs to take into consideration other potential sources than pectin. Due to the large uncertainties related to effects of stimulating factors, genotypic responses and type of precursors, we conclude that current attempts for upscaling aerobic CH(4) into a global budget is inadequate. Thus it is too early to draw the line under the aerobic methane emission in plants. Future work is needed for establishing the relative contribution of several proven potential CH(4) precursors in plant material.

  6. Pilot plant for biohidrometallurgical production of copper

    Directory of Open Access Journals (Sweden)

    Conić Vesna T.

    2009-01-01

    Full Text Available In this work, technical and technological characteristics of pilot plant for biohydrometallurgical production of copper financed by Ministry of Science and Environment Protection of Serbia, in the frame of capital providing for scientific research for the period 2006-2008 is presented. Presented within this project is the contribution and capability of the Institute for Mining and Metallurgy Bor to carry out the Fp6 IP project: 'Biotechnology for Metal Bearing Materials in Europe (BioMinE'. In the pilot plant, processes such as: microbiological leaching, pressures oxidation, chemical purification of solutions, solvent extraction and electrowining of copper were carried out. Bioleaching can treat complex copper concentrates which are either unacceptable to smelting or attract high penalties. Some of the elements penalized in smelting (for example zinc are dissolved in the bioleach process and can be recovered for sale. This may often allow an increased recovery of a few percent in the production of the copper concentrate. Bioleaching can be used in either small or large cathodic copper production from copper concentrate. Bioleaching uses conventional upstream and downstream process technology and the unit operation itself has been proven in the gold industry. For these reasons, this work describes the pilot plant for biotechnological production of copper from RTB Bor resources.

  7. 7 CFR 613.4 - Special production of plant materials.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 6 2010-01-01 2010-01-01 false Special production of plant materials. 613.4 Section... production of plant materials. NRCS can produce plant materials in the quantity required to do a specific conservation job if this production will serve the public welfare and only if the plant materials are...

  8. Plutonium release from Fukushima Daiichi fosters the need for more detailed investigations

    Science.gov (United States)

    Schneider, Stephanie; Walther, Clemens; Bister, Stefan; Schauer, Viktoria; Christl, Marcus; Synal, Hans-Arno; Shozugawa, Katsumi; Steinhauser, Georg

    2013-10-01

    The contamination of Japan after the Fukushima accident has been investigated mainly for volatile fission products, but only sparsely for actinides such as plutonium. Only small releases of actinides were estimated in Fukushima. Plutonium is still omnipresent in the environment from previous atmospheric nuclear weapons tests. We investigated soil and plants sampled at different hot spots in Japan, searching for reactor-borne plutonium using its isotopic ratio 240Pu/239Pu. By using accelerator mass spectrometry, we clearly demonstrated the release of Pu from the Fukushima Daiichi power plant: While most samples contained only the radionuclide signature of fallout plutonium, there is at least one vegetation sample whose isotope ratio (0.381 +/- 0.046) evidences that the Pu originates from a nuclear reactor (239+240Pu activity concentration 0.49 Bq/kg). Plutonium content and isotope ratios differ considerably even for very close sampling locations, e.g. the soil and the plants growing on it. This strong localization indicates a particulate Pu release, which is of high radiological risk if incorporated.

  9. Plutonium release from Fukushima Daiichi fosters the need for more detailed investigations.

    Science.gov (United States)

    Schneider, Stephanie; Walther, Clemens; Bister, Stefan; Schauer, Viktoria; Christl, Marcus; Synal, Hans-Arno; Shozugawa, Katsumi; Steinhauser, Georg

    2013-10-18

    The contamination of Japan after the Fukushima accident has been investigated mainly for volatile fission products, but only sparsely for actinides such as plutonium. Only small releases of actinides were estimated in Fukushima. Plutonium is still omnipresent in the environment from previous atmospheric nuclear weapons tests. We investigated soil and plants sampled at different hot spots in Japan, searching for reactor-borne plutonium using its isotopic ratio ²⁴⁰Pu/²³⁹Pu. By using accelerator mass spectrometry, we clearly demonstrated the release of Pu from the Fukushima Daiichi power plant: While most samples contained only the radionuclide signature of fallout plutonium, there is at least one vegetation sample whose isotope ratio (0.381 ± 0.046) evidences that the Pu originates from a nuclear reactor (²³⁹⁺²⁴⁰Pu activity concentration 0.49 Bq/kg). Plutonium content and isotope ratios differ considerably even for very close sampling locations, e.g. the soil and the plants growing on it. This strong localization indicates a particulate Pu release, which is of high radiological risk if incorporated.

  10. Plutonium contamination in the environment. January 1970-July 1989 (A Bibliography from Pollution Abstracts). Report for January 1970-July 1989

    International Nuclear Information System (INIS)

    This bibliography contains citations concerning the ecological impact of plutonium contamination in the environment. Topics include plutonium contamination in freshwater and marine sediments, plutonium bioaccumulation, plutonium transport in the food chain, plutonium accumulation in the soil, methods of analysis, plutonium removal from contaminated soils, and plutonium contamination from nuclear fallout and nuclear waste. Government regulations on containment and disposal of plutonium contaminated wastes are described. Government regulations regarding plutonium levels in consumer products and drinking water are discussed. (Contains 202 citations fully indexed and including a title list.)

  11. A World made of Plutonium?

    International Nuclear Information System (INIS)

    This lecture by Engelbert Broda was written for the 26th Pugwash Conference in Mühlhausen, Germany, 26 – 31 August 1976: Public doubts about nuclear energy are generally directed at the problems of routine emissions of radionuclides, of catastrophic accidents, and of terminal waste disposal. Curiously, the most important problem is not being given sufficient attention: The use of plutonium from civilian reactors fpr weapons production. According to current ideas about a nuclear future, 5000 tons (order of magnitude) of plutonium are to be made annually by year 2000, and about 10 000 tons will all the time be in circulation (transport, reprocessing, reproduction of fuel elements, etc.). It is a misconception that plutonium from power reactors is unsuitable as a nuclear explosive. 5000 tons are enough for several hundred thousand (!) of bombs, Nagasaki type. By the year 2000 maybe 40 – 50 countries will have home-made plutonium. Plutonium production and proliferation are the most serious problems in a nuclear world. (author)

  12. Pilot plant for biohidrometallurgical production of copper

    OpenAIRE

    Conić Vesna T.; Cvetkovski Vladimir B.; Vuković Milovan D.; Cvetkovska Milena V.

    2009-01-01

    In this work, technical and technological characteristics of pilot plant for biohydrometallurgical production of copper financed by Ministry of Science and Environment Protection of Serbia, in the frame of capital providing for scientific research for the period 2006-2008 is presented. Presented within this project is the contribution and capability of the Institute for Mining and Metallurgy Bor to carry out the Fp6 IP project: 'Biotechnology for Metal Bearing Materials in Europe (BioMinE)'. ...

  13. Terrestrial plant production and climate change.

    Science.gov (United States)

    Friend, Andrew D

    2010-03-01

    The likely future increase in atmospheric CO(2) and associated changes in climate will affect global patterns of plant production. Models integrate understanding of the influence of the environment on plant physiological processes and so enable estimates of future changes to be made. Moreover, they allow us to assess the consequences of different assumptions for predictions and so stimulate further research. This paper is a review of the sensitivities of one such model, Hybrid6.5, a detailed mechanistic model of terrestrial primary production. This model is typical of its type, and the sensitivities of the global distribution of predicted production to model assumptions and possible future CO(2) levels and climate are assessed. Sensitivity tests show that leaf phenology has large effects on mean C(3) crop and needleleaved cold deciduous tree production, reducing potential net primary production (NPP) from that obtained using constant maximum annual leaf area index by 32.9% and 41.6%, respectively. Generalized Plant Type (GPT) specific parameterizations, particularly photosynthetic capacity per unit leaf N, affect mean predicted NPP of higher C(3) plants by -22.3% to 27.9%, depending on the GPT, compared to NPP predictions obtained using mean parameter values. An increase in atmospheric CO(2) concentrations from current values to 720 ppm by the end of this century, with associated effects on climate from a typical climate model, is predicted to increase global NPP by 37.3%. Mean increases range from 43.9-52.9% across different C(3) GPTs, whereas the mean NPP of C(4) grass and crop increases by 5.9%. Significant uncertainties concern the extent to which acclimative processes may reduce any potential future increase in primary production and the degree to which any gains are transferred to durable, and especially edible, biomass. Experimentalists and modellers need to work closely together to reduce these uncertainties. A number of research priorities are suggested

  14. Design of a lunar oxygen production plant

    Science.gov (United States)

    Radhakrishnan, Ramalingam

    1990-01-01

    To achieve permanent human presence and activity on the moon, oxygen is required for both life support and propulsion. Lunar oxygen production using resources existing on the moon will reduce or eliminate the need to transport liquid oxygen from earth. In addition, the co-products of oxygen production will provide metals, structural ceramics, and other volatile compounds. This will enable development of even greater self-sufficiency as the lunar outpost evolves. Ilmenite is the most abundant metal-oxide mineral in the lunar regolith. A process involving the reaction of ilmenite with hydrogen at 1000 C to produce water, followed by the electrolysis of this water to provide oxygen and recycle the hydrogen has been explored. The objective of this 1990 Summer Faculty Project was to design a lunar oxygen-production plant to provide 5 metric tons of liquid oxygen per year from lunar soil. The results of this study describe the size and mass of the equipment, the power needs, feedstock quantity and the engineering details of the plant.

  15. Antibody Production in Plants and Green Algae.

    Science.gov (United States)

    Yusibov, Vidadi; Kushnir, Natasha; Streatfield, Stephen J

    2016-04-29

    Monoclonal antibodies (mAbs) have a wide range of modern applications, including research, diagnostic, therapeutic, and industrial uses. Market demand for mAbs is high and continues to grow. Although mammalian systems, which currently dominate the biomanufacturing industry, produce effective and safe recombinant mAbs, they have a limited manufacturing capacity and high costs. Bacteria, yeast, and insect cell systems are highly scalable and cost effective but vary in their ability to produce appropriate posttranslationally modified mAbs. Plants and green algae are emerging as promising production platforms because of their time and cost efficiencies, scalability, lack of mammalian pathogens, and eukaryotic posttranslational protein modification machinery. So far, plant- and algae-derived mAbs have been produced predominantly as candidate therapeutics for infectious diseases and cancer. These candidates have been extensively evaluated in animal models, and some have shown efficacy in clinical trials. Here, we review ongoing efforts to advance the production of mAbs in plants and algae. PMID:26905655

  16. Biofuel production from plant biomass derived sugars

    Energy Technology Data Exchange (ETDEWEB)

    Cripps, R.

    2007-03-15

    This report details the results of a project that aimed to develop a recombinant thermophilic microorganism able to produce ethanol in a commercial yield from mixed C5 (xylose and arabinose) and C6 (mainly glucose) sugar substrates typically found in biomass hydrolysates. The main focus of the project was on producing a stable recombinant which formed ethanol as its major product and did not produce significant quantities of by-products. The costs of bioethanol could be substantially reduced if cheap plant-based feedstocks could be utilised. This study focussed on a strain of Geobacillus thermoglucosidasius known to be a thermophilic ethanol producer and developed the genetic manipulation techniques necessary to engineer its metabolism such that unwanted products (mainly organic acids) were no longer formed and ethanol became the overwhelming product. An appropriate genetic took kit to allow the required metabolic engineering was acquired and used to inactivate the genes of the metabolic pathways involved in the formation of the organic acids (e.g. lactic acid) and to up-regulate genes concerned with the formation of ethanol. This allowed the flow of metabolites derived from the sugar substrates to be redirected to the desired product. Stable mutants lacking the ability to form lactic acid were created and shown to give enhanced levels of ethanol, with yields from glucose approaching those achieved in yeast fermentations and low by-product formation.

  17. Application of PGNAA to plutonium surveillance

    International Nuclear Information System (INIS)

    Prompt gamma-ray neutron activation analysis (PGNAA) is a well-established tool for nondestructive elemental analysis of bulk samples. At Los Alamos National Laboratory we are investigating the use of PGNAA as a diagnostic tool for a number of applications, particularly matrix characterization for nondestructive assay and plutonium surveillance. Surveillance is an essential feature of most plutonium facility operations, including routine material processing and research, short-term storage, and processing operations prior to disposal or long-term storage. The ability to identify and assay specific elements from gamma-ray-produced active neutron interrogation (e.g., by neutron capture, nonelastic scattering, and the decay of activation products) makes PGNAA an ideal tool for surveillance. For example, PGNAA can help confirm item descriptions (for example, plutonium chloride versus plutonium oxide). This feature is particularly important in operations involving poorly characterized legacy materials where the material form could adversely impact plutonium-processing operations

  18. Application of PGNAA to plutonium surveillance

    Energy Technology Data Exchange (ETDEWEB)

    Prettyman, T.H.; Foster, L.A.; Staples, P. [Los Alamos National Lab., NM (United States)

    1997-12-01

    Prompt gamma-ray neutron activation analysis (PGNAA) is a well-established tool for nondestructive elemental analysis of bulk samples. At Los Alamos National Laboratory we are investigating the use of PGNAA as a diagnostic tool for a number of applications, particularly matrix characterization for nondestructive assay and plutonium surveillance. Surveillance is an essential feature of most plutonium facility operations, including routine material processing and research, short-term storage, and processing operations prior to disposal or long-term storage. The ability to identify and assay specific elements from gamma-ray-produced active neutron interrogation (e.g., by neutron capture, nonelastic scattering, and the decay of activation products) makes PGNAA an ideal tool for surveillance. For example, PGNAA can help confirm item descriptions (for example, plutonium chloride versus plutonium oxide). This feature is particularly important in operations involving poorly characterized legacy materials where the material form could adversely impact plutonium-processing operations.

  19. Role of Osmotic Adjustment in Plant Productivity

    Energy Technology Data Exchange (ETDEWEB)

    Gebre, G.M.

    2001-01-11

    Successful implementation of short rotation woody crops requires that the selected species and clones be productive, drought tolerant, and pest resistant. Since water is one of the major limiting factors in poplar (Populus sp.) growth, there is little debate for the need of drought tolerant clones, except on the wettest of sites (e.g., lower Columbia River delta). Whether drought tolerance is compatible with productivity remains a debatable issue. Among the many mechanisms of drought tolerance, dehydration postponement involves the maintenance of high leaf water potential due to, for example, an adequate root system. This trait is compatible with productivity, but requires available soil moisture. When the plant leaf water potential and soil water content decline, the plant must be able to survive drought through dehydration tolerance mechanisms, such as low osmotic potential or osmotic adjustment. Osmotic adjustment and low osmotic potential are considered compatible with growth and yield because they aid in the maintenance of leaf turgor. However, it has been shown that turgor alone does not regulate cell expansion or stomatal conductance and, therefore, the role of osmotic adjustment is debated. Despite this finding, osmotic adjustment has been correlated with grain yield in agronomic crop species, and gene markers responsible for osmotic adjustment are being investigated to improve drought tolerance in productive progenies. Although osmotic adjustment and low osmotic potentials have been investigated in several forest tree species, few studies have investigated the relationship between osmotic adjustment and growth. Most of these studies have been limited to greenhouse or container-grown plants. Osmotic adjustment and rapid growth have been specifically associated in Populus and black spruce (Picea mariuna (Mill.) B.S.P.) progenies. We tested whether these relationships held under field conditions using several poplar clones. In a study of two hybrid poplar

  20. Development and active demonstration of acid digestion of burnable plutonium bearing solid wastes

    International Nuclear Information System (INIS)

    The investigations were focused on the active demonstration of the process in a technical scale plant by treatment of 790 kg of waste which contained about 7 kg of plutonium. Complete oxidation of the waste material is achieved within 15 min in sulfuric acid (kept under oxidizing condition by nitric acid) at 250 deg C. At 250 deg C with permanent stirring a rate of plutonium oxide to plutonium sulfate conversion of up to 99.9% is obtained within 8 hours. The waste oxidation product, besides offgas, is a residue of 320 g per kg waste digested. Precipitation of plutonium is achieved with an efficiency of 88% using cetylpyridinium nitrate. Active process demonstration was performed in a plant of 10 kg capacity per daily run from March 1983 until June 1985. The average waste throughput achieved was 4.1 kg waste per run (maximum 10.4 kg). The plutonium decontamination factors were 1010 for the cleaned offgas and 106 for the liquid secondary waste. Tantalum as a potential construction material for the digester does not exhibit specific corrosion; its surface corrosion is 0.1 mm per annum at the maximum

  1. PLUTONIUM-THORIUM ALLOYS

    Science.gov (United States)

    Schonfeld, F.W.

    1959-09-15

    New plutonium-base binary alloys useful as liquid reactor fuel are described. The alloys consist of 50 to 98 at.% thorium with the remainder plutonium. The stated advantages of these alloys over unalloyed plutonium for reactor fuel use are easy fabrication, phase stability, and the accompanying advantuge of providing a means for converting Th/sup 232/ into U/sup 233/.

  2. PLUTONIUM CLEANING PROCESS

    Science.gov (United States)

    Kolodney, M.

    1959-12-01

    A method is described for rapidly removing iron, nickel, and zinc coatings from plutonium objects while simultaneously rendering the plutonium object passive. The method consists of immersing the coated plutonium object in an aqueous acid solution containing a substantial concentration of nitrate ions, such as fuming nitric acid.

  3. Determination of Uranium and Plutonium Concentration in 1AF by Isotopic Dilution Mass Spectrometry Methods

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>It is important data to measure uranium and plutonium concentration for the reprocessing plant control analysis. The determination of uranium and plutonium concentration in 1AF by isotopic dilution mass

  4. Qualitative chemical analysis of plutonium by Alpha spectroscopy

    International Nuclear Information System (INIS)

    In this work the separation and purification of plutonium from irradiated uranium was done. The plutonium, produced by the irradiation of uranium in a nuclear reactor and the β decay of 239 Np, was stabilized to Pu +4 with sodium nitrite. Plutonium was separated from the fission products and uranium by ion exchange using the resin Ag 1 X 8. It was electrodeposited on stainless steel discs and the alpha radioactivity of plutonium was measured in a surface barrier detector. The results showed that plutonium was separated with a radiochemical purity higher than 99 %. (Author)

  5. Research project of P3 (Protected Plutonium Production) and global academy for 3S (Safety, Security, Safeguard) for peace and sustainable prosperity

    International Nuclear Information System (INIS)

    Full text:Nuclear engineering education has been initiated in 1957 at the graduate school of Tokyo Institute of Technology. Higher Educational activities have been conducted for more than half century. More than 1000 Master students and 200 Doctoral students graduated from the Department of Nuclear Engineering in Tokyo Institute of Technology. Many of them are working in nuclear industries and institutes. International course of nuclear engineering was initiated in 1994, and 130 students from 20 overseas countries have graduated from Master and Doctoral Programs. In the national research program, Protected Plutonium Production (P3) has been proposed to enhance the proliferation resistance of plutonium by the transmutation of Minor Actinides (MAs). In 2011, Academy for Global Nuclear Safety and Security Agent was initiated with the unique features of a full boarding system and a curriculum that combines education in liberal arts and science/ engineering. Both educational and research programs have been supported by the Ministry of Education, Culture, Sports, Science and Technology in Japan. In the conference, the current nuclear educational and research activities in Tokyo Institute of Technology will be presented. (author)

  6. A PILOT PLANT FOR THE BIOGAS PRODUCTION

    Directory of Open Access Journals (Sweden)

    A. Omrani

    1988-08-01

    Full Text Available Manure and Putreseible garbage are some of the main sources of pathogenic germs in countryside’s. On the other hand, demand for fertilizer and energy increases in rural areas every day. To study Potential of cow manure for these requirements a 16,5m3 pilot plant was designed and constructed as fermentation tank near animal husbandry of karaj Agriculture Faculty. Some 260kg cow manure and water with the ratio of 4 and 7 was fed to fermentation tank every day. Average daily biogas production was 3.4m3, which was burned successfully in a gas range. Gas production was reduced by 86% during coldest winter days. Design for control of gas pressure and reservation of excessive gas was successful. Concentration of nitrate in sludge increased by 1.6 folds compared to row material. Some bacteria and Parasites were reduced drastically.

  7. In-place testing of multiple stage filter systems without disruption of plant operations in the plutonium facility at Los Alamos

    International Nuclear Information System (INIS)

    The Los Alamos National Laboratory Plutonium Facility has a number of multiple-stage air-cleaning systems. These systems operate on a continuous basis and economic considerations require that shutting down of the ventilation systems due to in-place testing be kept to a minimum. Earlier methods of testing multiple-stage filter systems required scheduled shut down of the filter system. Methods such as injecting the test aerosol between the stages have proven costly because of the need to install temporary injection ducts and completely close off the ventilation from the process area. Also, additional personnel were needed to install and move injection and bypass ducts from one system to another. After considering these costly methods, current methods of testing were improved to prevent interruption of plant operations. The modified procedure uses a laser particle size spectrometer that has the capability of counting single particles downstream of two filter stages where decontamination factors of the first stage and overall system effectiveness is established. This procedure is similar to that of Nuclear Standard NEF 3-4IT, ''In-Place Testing of HEPA filter systems by the Single-Particle, Particle-Size Spectrometer Method.'' Decontamination factors of 109 are measured downstream of two stages. Particle size analyses of the challenge and the aerosol penetrating the first and second stages have been established. A cost estimation comparing two test methods show considerable savings in operational costs

  8. The differential radiological impact of plutonium recycle in the fuel cycle of LWR type reactors: accidental conditions

    International Nuclear Information System (INIS)

    The radiological impact of the fuel cycle of LWR type reactors using enriched uranium may be changed by plutonium recycle. The differences, which result from accidents which may occur in the different stages of the fuel cycle, are estimated in this study. The differential radiological impact on the population of the European Community is estimated for the recycle of 10t of plutonium metal, taking into consideration some characteristic accidents of each stage of the fuel cycle: fuel fabrication, reactor operation, fuel reprocessing and conversion, and, transport between the different units of the fuel cycle. Each unit is supposed built on an European ''average'' site (mean distributions of the populations and of the agricultural productions, reference meteorological situations). The recycle of plutonium in the fuel cycle involves a few per cent decrease of the radiological impact of the accident choosed for the nuclear power plants. The accidents of transport of plutonium, of new fuels and of plutonium wastes, as also thoses choosed for the fuel fabrication plant involve an increase of the impact for these types of transport and this plant. Finally, the differential radiological impact of the fuel reprocessing plant is positive but low

  9. Interaction of Plutonium with Bacteria in the Repository Environment

    Energy Technology Data Exchange (ETDEWEB)

    Gillow, J. B.; Francis, A. J.; Lucero, D. A.; Papenguth, H. W.

    2000-07-01

    Microorganisms in the nuclear waste repository environment may interact with plutonium through (1) sorption, (2) intracellular accumulation, and (3) transformation speciation. These interactions may retard or enhance the mobility of Pu by precipitation reactions, biocolloid formation, or production of more soluble species. Current and planned radioactive waste repository environments, such as deep subsurface halite and granite formations, are considered extreme relative to life processes in the near-surface terrestrial environment. There is a paucity of information on the biotransformation of radionuclides by microorganisms present in such extreme environments. In order to gain a better understanding of the interaction of plutonium with microorganisms present in the waste repository sites we investigated a pure culture (Halomonas sp.) and a mixed culture of bacteria (Haloarcula sinaiiensis, Marinobacter hydrocarbonoclasticus, Altermonas sp., and a {gamma}-proteobacterium) isolated from the Waste Isolation Pilot Plant (WIPP) site and an Acetobacterium sp. from alkaline groundwater at the Grimsel Test Site in Switzerland.

  10. The interaction of plutonium with bacteria in the repository environment

    Science.gov (United States)

    Gillow, J. B.; Francis, A. J.; Lucero, D. A.; Papenguth, H. W.

    2000-07-01

    Microorganisms in the nuclear waste repository environment may interact with plutonium through (i) sorption, (ii) intracellular accumulation, and (iii) transformation of chemical speciation. These interactions may retard or enhance the mobility of Pu by precipitation reactions, biocolloid formation, or production of more soluble species. Current and planned radioactive waste repository environments, such as deep subsurface halite and granite formations, are considered extreme relative to life processes in the near-surface terrestrial environment. There is a paucity of information on the biotransformation of radionuclides by microorganisms present in such extreme environments. In order to gain a better understanding of the interaction of plutonium with microorganisms present in the waste repository sites we investigated a pure culture (Halomonas sp.) and a mixed culture of bacteria (Haloarcula sinaiiensis, Marinobacter hydrocarbonoclasticus, Altermonas sp., and a g-proteobacterium) isolated from the Waste Isolation Pilot Plant (WIPP) site and an Acetobacterium sp. from alkaline groundwater at the Grimsel Test Site in Switzerland.

  11. Distribution of plutonium, americium, and several rare earth fission product elements between liquid cadmium and LiCl-KCl eutectic

    International Nuclear Information System (INIS)

    Separation factors were measured that describe the partition between molten cadmium and molten LiCl-KCl eutectic of plutonium, americium, praseodymium, neodymium, cerium, lanthanum, gadolinium, dysprosium, and yttrium. The temperature range was 753-788 K, and the range of concentrations was that allowed by the sensitivity of the chemical analysis methods. Mean separation factors were derived for Am-Pu, Nd-Am, Nd-Pu, Nd-Pr, Gd-La, Dy-La, La-Ce, La-Nd, Y-La, and Y-Nd. Where previously published data were available, agreement was good. For convenience, the following series of separation factors relative to plutonium was derived by combining the measured separation factors: Pu, 1.00 (basis); Am, 1.54; Pr, 22.0; Nd, 23.4; Ce, 26; La, 70; Gd, 77; Dy, 270; Y, 3000. These data are used in calculating the distribution of the actinide and rare earth elements in the prochemical reprocessing of spent fuel from the Integral Fast Reactor. (orig.)

  12. Historical plant cost and annual production expenses for selected electric plants, 1982

    International Nuclear Information System (INIS)

    This publication is a composite of the two prior publications, Hydroelectric Plant Construction Cost and Annual Production Expenses and Thermal-Electric Plant Construction Cost and Annual Production Expenses. Beginning in 1979, Thermal-Electric Plant Construction Cost and Annual Production Expenses contained information on both steam-electric and gas-turbine electric plant construction cost and annual production expenses. The summarized historical plant cost described under Historical Plant Cost in this report is the net cumulative-to-date actual outlays or expenditures for land, structures, and equipment to the utility. Historical plant cost is the initial investment in plant (cumulative to the date of initial commercial operation) plus the costs of all additions to the plant, less the value of retirements. Thus, historical plant cost includes expenditures made over several years, as modifications are made to the plant. Power Production Expenses is the reporting year's plant operation and maintenance expenses, including fuel expenses. These expenses do not include annual fixed charges on plant cost (capital costs) such as interest on debt, depreciation or amortization expenses, and taxes. Consequently, total production expenses and the derived unit costs are not the total cost of producing electric power at the various plants. This publication contains data on installed generating capacity, net generation, net capability, historical plant cost, production expenses, fuel consumption, physical and operating plant characteristics, and other relevant statistical information for selected plants

  13. NDA systems to support nuclear material control and accounting in spent fuel reprocessing plants

    International Nuclear Information System (INIS)

    Detailed descriptions of a number of instrument systems relating to accountancy and safeguarding of plutonium operations and storage on Thermal Oxide Plant (Thorp) are provided. The systems described include the Plutonium Inventory Measurement System (PIMS), used to provide Near Real Time Materials Accountancy (NRTMA) information within the Thorp plutonium finishing area; the Product Can Contents Monitor (PCCM), used to verify can weight measurements and isotopic composition and; the In-Store Plutonium Verification Monitor, used to provide in-situ measurements of plutonium in cans whilst they are in their storage channels. These nondestructive systems are necessarily combined with other physical security, surveillance and identification arrangements for the handling and storage of plutonium product cans

  14. Russian plutonium policy

    Energy Technology Data Exchange (ETDEWEB)

    Ponomarev-Stepnoi, N.; Tsourikov, D. [Rossijskij Nauchnyj Tsentr ``Kurchatovskij Inst.``, Moscow (Russian Federation)

    1997-10-01

    This paper is intended to provide more detail on the main features of Russian strategy of utilization of both the civilian and weapons-grade plutonium. At present, the Russian Federation has a large stock of plutonium and at the same time some scientific, technological and industrial experience in the utilization of plutonium, in particular in fast reactors. The key elements of Russian plutonium policy are the interim secure storage and plutonium disposition in nuclear reactors. The disposition options being discussed are the following: BN-type reactors, VVERs, and HTGR. It is shown that the utilization of weapons-grade plutonium, for a number of reasons, should begin using the reactors currently in operation. The importance of broad international cooperation for a safe and effective management of weapons plutonium designated as no longer required for defense purposes has been stressed. (orig.)

  15. Uranium plutonium oxide fuels

    International Nuclear Information System (INIS)

    Uranium plutonium oxide is the principal fuel material for liquid metal fast breeder reactors (LMFBR's) throughout the world. Development of this material has been a reasonably straightforward evolution from the UO2 used routinely in the light water reactor (LWR's); but, because of the lower neutron capture cross sections and much lower coolant pressures in the sodium cooled LMFBR's, the fuel is operated to much higher discharge exposures than that of a LWR. A typical LMFBR fuel assembly is shown. Depending on the required power output and the configuration of the reactor, some 70 to 400 such fuel assemblies are clustered to form the core. There is a wide variation in cross section and length of the assemblies where the increasing size reflects a chronological increase in plant size and power output as well as considerations of decreasing the net fuel cycle cost. Design and performance characteristics are described

  16. Proliferation resistance of plutonium based on decay heat

    International Nuclear Information System (INIS)

    Proliferation resistance of plutonium can be enhanced by increasing the decay heat of plutonium. For example, it can be enhanced by increasing the isotopic fraction of 238Pu, which has the largest decay heat among plutonium isotopes, produced by transmutation of Minor Actinides (Protected Plutonium Production: P3). In the present paper, proliferation resistance of plutonium was evaluated based on decay heat with physical assessment model. As a summary of the evaluation, new criteria to evaluate proliferation resistance of plutonium based on its isotopic composition from the view point of decay heat were suggested. The present methodology and the criteria were applied to evaluate the impact of P3 by the transmutation of Minor Actinides in fast breeder reactor blanket on proliferation resistance of plutonium. (author)

  17. Salvage of plutonium-and americium-contaminated metals

    International Nuclear Information System (INIS)

    Melt-slagging techniques were evaluated as a decontamination and consolidation step for metals contaminated with oxides of plutonium and americium. Experiments were performed in which mild steel, stainless steel, and nickel metals contaminated with oxides of plutonium and americium were melted in the presence of silicate slags of various compositions. The metal products were low in contamination, with the plutonium and americium strongly fractionated to the slags. Partition coefficients (plutonium in slag/plutonium in steel) of 7*10/sup 6/ with borosilicate slag and 3*10/sup 6/ for calcium, magnesium silicate slag were measured. Decontamination of metals containing as much as 14,000 p.p.m. plutonium appears to be as efficient as that of metals with plutonium levels of 400 p.p.m. Staged extraction, that is, a remelting of processed metal with clean slag, results in further decontamination of the metal. 10 refs

  18. APPLICATION OF COLUMN EXTRACTION METHOD FOR IMPURITIES ANALYSIS ON HB-LINE PLUTONIUM OXIDE IN SUPPORT OF MOX FEED PRODUCT SPECIFICATIONS

    Energy Technology Data Exchange (ETDEWEB)

    Jones, M.; Diprete, D.; Wiedenman, B.

    2012-03-20

    The current mission at H-Canyon involves the dissolution of an Alternate Feedstocks 2 (AFS-2) inventory that contains plutonium metal. Once dissolved, HB-Line is tasked with purifying the plutonium solution via anion exchange, precipitating the Pu as oxalate, and calcining to form plutonium oxide (PuO{sub 2}). The PuO{sub 2} will provide feed product for the Mixed Oxide (MOX) Fuel Fabrication Facility, and the anion exchange raffinate will be transferred to H-Canyon. The results presented in this report document the potential success of the RE resin column extraction application on highly concentrated Pu samples to meet MOX feed product specifications. The original 'Hearts Cut' sample required a 10000x dilution to limit instrument drift on the ICP-MS method. The instrument dilution factors improved to 125x and 250x for the sample raffinate and sample eluent, respectively. As noted in the introduction, the significantly lower dilutions help to drop the total MRL for the analyte. Although the spike recoveries were half of expected in the eluent for several key elements, they were between 94-98% after Nd tracer correction. It is seen that the lower ICD limit requirements for the rare earths are attainable because of less dilution. Especially important is the extremely low Ga limit at 0.12 {mu}g/g Pu; an ICP-MS method is now available to accomplish this task on the sample raffinate. While B and V meet the column A limits, further development is needed to meet the column B limits. Even though V remained on the RE resin column, an analysis method is ready for investigation on the ICP-MS, but it does not mean that V cannot be measured on the ICP-ES at a low dilution to meet the column B limits. Furthermore, this column method can be applicable for ICP-ES as shown in Table 3-2, in that it trims the sample of Pu, decreasing and sometimes eliminating Pu spectral interferences.

  19. Plant Level Evidence on Product Mix Changes in Chilean Manufacturing

    OpenAIRE

    Lucas Navarro

    2008-01-01

    This paper analyzes changes in the product mix by Chilean manufacturing plants in the period 1996-2003. Three-quarters of the surviving plants changed the set of products produced and more than three-quarters of the exporting plants changed the mix of products they exported during the sample period. Plants that changed their product mix contributed 85% of the aggregate growth in real sales of surviving plants between 1996 and 2003. Finally and in contrast to the US evidence, there is a negati...

  20. Risk assessment of plant protection products

    Directory of Open Access Journals (Sweden)

    Hardy T

    2012-10-01

    Full Text Available

    EFSA’s Panel on Plant Protection Products and their Residues (PPR Panel provides independent scientific advice in the field of risk assessment of plant protection products (PPPs, pesticides. Since its establishment in 2003 under Regulation (EC No 178/2002, it has delivered a series of scientific outputs in support of evaluation of pesticide active substances, establishing scientific principles and guidance documents in the field of pesticide risk assessment and in support of decision making of European Union (EU law makers. Next to a series of scientific opinions evaluating specific adverse effects of PPPs for human health (like for instance carcinogenicity the Panel also delivered scientific opinions on general principles in the field of human health risk assessment (like reference value setting and is, in particular over the last years, very much engaged in development of methodologies to meet new challenges in regulatory risk assessments such as assessment of toxicity of pesticide metabolites and potential cumulative effects of pesticides to human health. Fate, behaviour and transformation of pesticides after their application and consequent release to the environment are a major aspect of pesticide risk assessment. The PPR Panel has achieved major accomplishments by delivering guidance and scientific opinions on degradation in soil, exposure of soil organisms and assessment of environmental risks by use of pesticides in greenhouses or grown under cover. A series of scientific opinions have been delivered also in the field of environmental risk assessment of pesticides. Scientific output covered specific issues arising in the peer review of specific active substances, revision of data requirements, development of risk assessment methodologies and the development of guidance documents. A major milestone of the PPR Panel was the development of the methodological framework for deriving specific protection goals for environmental risk

  1. Incineration of simulated plutonium-contaminated waste

    International Nuclear Information System (INIS)

    Pyrolysis rate data are presented which will enable larger pyrolyser furnaces to be made for processing solid plutonium-contaminated materials at throughputs of up to 20 kg/h using either 1 or 2.5 kg packages as feed. The influence of liquids, such as water, kerosene or oil, on the pyrolysis process has also been assessed. The products of pyrolysis for a range of individual materials and their mixtures have been defined. The oxidation rates for both static and stirred beds of char have been obtained. The implications of both the pyrolysis and char-oxidation processes for plant design are discussed. This work has been commissioned by the Department of the Environment as part of its radioactive waste management programme. The results will be used in the formulation of government policy, but as this stage they do not necessarily represent that policy

  2. Plutonium speciation affected by environmental bacteria

    International Nuclear Information System (INIS)

    Plutonium has no known biological utility, yet it has the potential to interact with bacterial cellular and extracellular structures that contain metal-binding groups, to interfere with the uptake and utilization of essential elements, and to alter cell metabolism. These interactions can transform plutonium from its most common forms, solid, mineral-adsorbed, or colloidal Pu(IV), to a variety of biogeochemical species that have much different physico-chemical properties. Organic acids that are extruded products of cell metabolism can solubilize plutonium and then enhance its environmental mobility, or in some cases facilitate plutonium transfer into cells. Phosphate- and carboxylate-rich polymers associated with cell walls can bind plutonium to form mobile biocolloids or Pu-laden biofilm/mineral solids. Bacterial membranes, proteins or redox agents can produce strongly reducing electrochemical zones and generate molecular Pu(III/IV) species or oxide particles. Alternatively, they can oxidize plutonium to form soluble Pu(V) or Pu(VI) complexes. This paper reviews research on plutonium-bacteria interactions and closely related studies on the biotransformation of uranium and other metals. (orig.)

  3. Radio-ecological researches in the Sea of Japan and northwestern part of the Pacific Ocean after accident on the Japanese nuclear power plant 'Fukushima-1': the content of plutonium isotopes and strontium-90 in sea water

    Energy Technology Data Exchange (ETDEWEB)

    Fedorova, A. [Research and Production Association - RPA Typhoon (Russian Federation)

    2014-07-01

    In April-May 2011 and in August-September 2012 'Roshydromet' has conducted radio ecological researches in the Sea of Japan and on the water area of northwestern part of the Pacific Ocean (Kuril-Kamchatka area and the area of the Kuroshio current), which had purpose to make assessment of contamination hazard that can be caused to the coast of Russian Far East because of emergency releases of radioactive materials on the nuclear power plant 'Fukushima-1'. During the research works was done the sampling and processing of sea water samples not only for detection of Cs{sup 134}, Cs{sup 137}, but also for such radio-ecological significant long-living radionuclides, as {sup 90}Sr, plutonium isotopes ({sup 239,240}Pu) and tritium. Information about radionuclides was required for correct assessment of nuclear power plant 'Fukushima-1' aftermath on the Far Eastern sea water areas, but was not available in the beginning of research. In the present report the radiochemical measuring results on content of plutonium isotopes and {sup 90}Sr in the sea water from researched areas are presented. Sampling was done from the various horizons. Surface and deep water samples were filtered via the compound filter which made it possible to filter particles bigger than 1 micron. Radiochemical testing of the {sup 90}Sr and plutonium isotopes content was done separately on a suspension and in a filtrate of sea water samples. The content of {sup 90}Sr in the filtrate of the sea water that had been selected in 2011, ranges 0,7-2,4 Bq/m{sup 3}, in suspensions the interval makes 0,0013-0,021 Bq/m3. The results received in researches in 2012 are in range of 0,5-2,6 Bq/m{sup 3} of the sea water filtrate. According to results of IAEA in 2000, the average content of {sup 90}Sr in surface water of the Sea of Japan made 1,6 Bq/m{sup 3}. Hereby, the data obtained in researches in 2011-2012 agrees with results which had been presented by IAEA before the accident. The

  4. Characterization of plutonium-bearing wastes by chemical analysis and analytical electron microscopy

    Energy Technology Data Exchange (ETDEWEB)

    Behrens, R.G. [Los Alamos National Lab., NM (United States); Buck, E.C.; Dietz, N.L.; Bates, J.K.; Van Deventer, E.; Chaiko, D.J. [Argonne National Lab., IL (United States)

    1995-09-01

    This report summarizes the results of characterization studies of plutonium-bearing wastes produced at the US Department of Energy weapons production facilities. Several different solid wastes were characterized, including incinerator ash and ash heels from Rocky Flats Plant and Los Alamos National Laboratory; sand, stag, and crucible waste from Hanford; and LECO crucibles from the Savannah River Site. These materials were characterized by chemical analysis and analytical electron microscopy. The results showed the presence of discrete PuO{sub 2}PuO{sub 2{minus}x}, and Pu{sub 4}O{sub 7} phases, of about 1{mu}m or less in size, in all of the samples examined. In addition, a number of amorphous phases were present that contained plutonium. In all the ash and ash heel samples examined, plutonium phases were found that were completely surrounded by silicate matrices. Consequently, to achieve optimum plutonium recovery in any chemical extraction process, extraction would have to be coupled with ultrafine grinding to average particle sizes of less than 1 {mu}m to liberate the plutonium from the surrounding inert matrix.

  5. Production of Monoclonal Antibodies in Plants for Cancer Immunotherapy

    OpenAIRE

    Ghislain Moussavou; Kisung Ko; Jeong-Hwan Lee; Young-Kug Choo

    2015-01-01

    Plants are considered as an alternative platform for recombinant monoclonal antibody (mAb) production due to the improvement and diversification of transgenic techniques. The diversity of plant species offers a multitude of possibilities for the valorization of genetic resources. Moreover, plants can be propagated indefinitely, providing cheap biomass production on a large scale in controlled conditions. Thus, recent studies have shown the successful development of plant systems for the produ...

  6. PREPARATION OF PLUTONIUM HALIDES

    Science.gov (United States)

    Davidson, N.R.; Katz, J.J.

    1958-11-01

    A process ls presented for the preparation of plutonium trihalides. Plutonium oxide or a compound which may be readily converted to plutonlum oxide, for example, a plutonium hydroxide or plutonlum oxalate is contacted with a suitable halogenating agent. Speciflc agents mentioned are carbon tetrachloride, carbon tetrabromide, sulfur dioxide, and phosphorus pentachloride. The reaction is carried out under superatmospberic pressure at about 300 icient laborato C.

  7. PLUTONIUM-ZIRCONIUM ALLOYS

    Science.gov (United States)

    Schonfeld, F.W.; Waber, J.T.

    1960-08-30

    A series of nuclear reactor fuel alloys consisting of from about 5 to about 50 at.% zirconium (or higher zirconium alloys such as Zircaloy), balance plutonium, and having the structural composition of a plutonium are described. Zirconium is a satisfactory diluent because it alloys readily with plutonium and has desirable nuclear properties. Additional advantages are corrosion resistance, excellent fabrication propenties, an isotropie structure, and initial softness.

  8. Demolition of Building 12, an old plutonium filter facility

    International Nuclear Information System (INIS)

    This report discusses the decommissioning and disposal of a plutonium-contaminated air filter facility that provided ventilation for the main plutonium processing plant at Los Alamos from 1945 until 1973. The health physics, waste management, and environmental aspects of the demolition are also discussed

  9. Biomass Production System (BPS) Plant Growth Unit

    Science.gov (United States)

    Morrow, R. C.; Crabb, T. M.

    The Biomass Production System (BPS) was developed under the Small Business Innovative Research (SBIR) program to meet science, biotechnology and commercial plant growth needs in the Space Station era. The BPS is equivalent in size to a double middeck locker, but uses it's own custom enclosure with a slide out structure to which internal components mount. The BPS contains four internal growth chambers, each with a growing volume of more than 4 liters. Each of the growth chambers has active nutrient delivery, and independent control of temperature, humidity, lighting, and CO2 set-points. Temperature control is achieved using a thermoelectric heat exchanger system. Humidity control is achieved using a heat exchanger with a porous interface which can both humidify and dehumidify. The control software utilizes fuzzy logic for nonlinear, coupled temperature and humidity control. The fluorescent lighting system can be dimmed to provide a range of light levels. CO2 levels are controlled by injecting pure CO2 to the system based on input from an infrared gas analyzer. The unit currently does not scrub CO2, but has been designed to accept scrubber cartridges. In addition to providing environmental control, a number of features are included to facilitate science. The BPS chambers are sealed to allow CO2 and water vapor exchange measurements. The plant chambers can be removed to allow manipulation or sampling of specimens, and each chamber has gas/fluid sample ports. A video camera is provided for each chamber, and frame-grabs and complete environmental data for all science and hardware system sensors are stored on an internal hard drive. Data files can also be transferred to 3.5-inch disks using the front panel disk drive

  10. Product Mix Changes and Performance in Chilean Plants

    OpenAIRE

    Roberto Alvarez; Claudio Bravo-Ortega; Lucas Navarro

    2012-01-01

    A recent theoretical literature has given relevance to the study of the relationship between product mix changes and firm productivity. In this paper, taking advantage of a rich dataset for manufacturing plants in Chile during the period 1996-2000, we use matching techniques and a difference in difference approach to estimate the causal impact of product mix changes on productivity and other plant-specific outcomes. Our results suggest a positive and increasing impact of product mix changes o...

  11. Perspective on plutonium

    International Nuclear Information System (INIS)

    This paper is intended as a brief overview on the element plutonium. Plutonium is the first primarily man-made element to play a significant role not only in technological development, but also in the economic growth of many countries. The importance of plutonium centers around its enormous energy making it ideal for wide-scale use in reactors, while the nuclear industry continues to work toward improving safety and efficiency of plutonium as a reactor fuel politicians and the public still debate over the safety and benefits of nuclear power. (30 refs.)

  12. Technical progress report on the metabolic studies of plutonium for month of August 1945

    Energy Technology Data Exchange (ETDEWEB)

    Hamilton, J.G.

    1945-12-31

    This monthly report briefly describes ongoing studies including urinary and fecal excretion of Plutonium 238 by human subjects and by rats, exploring way to facilitate the removal of Plutonium 238 from rat bone, the absorption of Plutonium 238 by barley plants, and use of inert iodine to block absorption of Iodine-131 in the rat.

  13. Aromatic plant production on metal contaminated soils

    Energy Technology Data Exchange (ETDEWEB)

    Zheljazkov, Valtcho D. [Mississippi State, Department of Plant and Soil Sciences and North Mississippi Research and Extension Center, 5421 Highway 145 South, Verona, MS 38879 (United States)], E-mail: vj40@pss.msstate.edu; Craker, Lyle E.; Xing Baoshan [Department of Plant and Soil Sciences, 12 Stockbridge Hall, University of Massachusetts, Amherst, MA 01003 (United States); Nielsen, Niels E. [Plant Nutrition and Soil Fertility Lab, Department of Agricultural Sciences, Royal Veterinary and Agricultural University, Thorvaldsensvej 40, DK1871, Copenhagen (Denmark); Wilcox, Andrew [Harper Adams University College, Newport, Shropshire, TF10 8NB (United Kingdom)

    2008-06-01

    Field and container experiments were conducted to assess the feasibility of growing aromatic crops in metal contaminated areas and the effect of metals on herbage and oil productivity. The field experiments were conducted in the vicinities of the Non-Ferrous Metals Combine (Zn-Cu smelter) near Plovdiv, Bulgaria using coriander, sage, dill, basil, hyssop, lemon balm, and chamomile grown at various distances from the smelter. Herbage essential oil yields of basil, chamomile, dill, and sage were reduced when they were grown closer to the smelter. Metal removal from the site with the harvestable plant parts was as high as 180 g ha{sup -1} for Cd, 660 g ha{sup -1} for Pb, 180 g ha{sup -1} for Cu, 350 g ha{sup -1} for Mn, and 205 g ha{sup -1} for Zn. Sequential extraction of soil demonstrated that metal fractionation was affected by the distance to the smelter. With decreasing distance to the smelter, the transfer factor (TF) for Cu and Zn decreased but increased for Cd, while the bioavailability factor (BF) for Cd, Pb, Cu, Mn, and Zn decreased. Scanning electron microscopy and X-ray microanalyses of contaminated soil verified that most of the Pb, Cd, Mn, Cu, and Zn were in the form of small (< 1 {mu}m) particles, although there were larger particles (1-5 {mu}m) with high concentrations of individual metals. This study demonstrated that high concentrations of heavy metals in soil or growth medium did not result in metal transfer into the essential oil. Of the tested metals, only Cu at high concentrations may reduce oil content. Our results demonstrated that aromatic crops may not have significant phytoremediation potential, but growth of these crops in metal contaminated agricultural soils is a feasible alternative. Aromatic crops can provide economic return and metal-free final product, the essential oil.

  14. Recovery and purification of uranium-234 from aged plutonium-238

    International Nuclear Information System (INIS)

    The current production methods used to recover and purify uranium-234 from aged plutonium-238 at Mound Laboratory are presented. The three chemical separation steps are described in detail. In the initial separation step, the bulk of the plutonium is precipitated as the oxalate. Successively lower levels of plutonium are achieved by anion exchange in nitrate media and by anion exchange in chloride media. The procedures used to characterize and analyze the final U3O8 are given

  15. Plutonium-237: an important research tool for studies of environmental plutonium kinetics

    International Nuclear Information System (INIS)

    The production and use of the photon-emitting isotope plutonium-237 in investigations of the uptake, retention, and distribution of monomeric plutonium (IV) both in an aquatic vertebrate, the channel catfish Ictalurus punctatus, and in a littoral aquatic micro-ecosystem, are presented. The rationale for use of plutonium-237 in environmental studies is discussed. Chelation can either enhance or reduce the uptake of ingested plutonium relative to plutonium hydroxide (monomer) in channel catfish. The highest observed retention (whole body) at 63 days was 3.8% of ingested dose for plutonium-237 citrate, while retention of the fulvate was 0.6%. Reduced uptake of the fulvate complex is due either to its high molecular weight (>10,000) or to its stability in metabolic systems. Increased uptake of plutonium-237 citrate is attributable to instability of the complex in metabolic systems. Tissue distribution studies revealed that relatively little (less than or equal to 10%) of intracardially injected plutonium citrate was excreted. Blood clearance rates were similar to those found in small mammals, with the plutonium being primarily associated with the plasma protein transferrin. The fractional body burdens in bone, liver, and kidney 17 days after injection were 31%, 24%, and 9% of the injection dose, respectively. High kidney burdens relativity to mammals are expected, since the kidney functions as the major site of homopoiesis in teleosts. Absence of significant excretion indicates that a short half-life component of elimination following gut clearance in gavage studies is due to plutonium labeling of the gut

  16. The Criteria For Registration of the Plant Protection Products

    OpenAIRE

    Suat KAYMAK

    2015-01-01

    Plant protection practices are used for the Aims: to increase agricultural production by controlling diseases, pests and weeds that restrict crop production and to improve the quality. Plant Protection Products (PPPs) used in crop production against harmful organisms is one of the indispensable agricultural input in all over the world and also our country. The purpose of the code on the registration of PPPs is to specify the procedures and principles related to the licensing of PPPs that use ...

  17. CSER 97-004: PFP production denitration calciner system

    International Nuclear Information System (INIS)

    The plutonium stabilization program at the Plutonium Finishing Plant (PFP) includes conversion of acidic plutonium nitrate solution into plutonium oxide. Conversion is facilitated through use of a vertical calciner installed in Glovebox HC-23OC-2, which is located in RM 230C of this facility. This evaluation supports the Criticality Prevention Specification for the calcining process inside this glovebox. As the product of the calciner is a high density plutonium oxide, a number of limits are required to insure criticality safety. The containers allowed are product receiver vessels and 0.5 C slip lid cans and polyjars. The limits allow for two ''unit masses'' of 2 V total volume each, separated by a distance of at least 25.4 cm (10 in.). This evaluation allows for operation of the calciner for product densities not in excess of 5.5 g Pu/cm3

  18. CSER 97-004: PFP production denitration calciner system

    Energy Technology Data Exchange (ETDEWEB)

    Hillesland, K.E.

    1997-09-11

    The plutonium stabilization program at the Plutonium Finishing Plant (PFP) includes conversion of acidic plutonium nitrate solution into plutonium oxide. Conversion is facilitated through use of a vertical calciner installed in Glovebox HC-23OC-2, which is located in RM 230C of this facility. This evaluation supports the Criticality Prevention Specification for the calcining process inside this glovebox. As the product of the calciner is a high density plutonium oxide, a number of limits are required to insure criticality safety. The containers allowed are product receiver vessels and 0.5 C slip lid cans and polyjars. The limits allow for two ``unit masses`` of 2 V total volume each, separated by a distance of at least 25.4 cm (10 in.). This evaluation allows for operation of the calciner for product densities not in excess of 5.5 g Pu/cm{sup 3}.

  19. Bioactive Natural Products from Plant Sources

    OpenAIRE

    Vijay Kothari

    2015-01-01

    Botany today has moved far ahead of the days when most of the work in this branch of science was centered on reporting new species from various geographical regions. It was dominated by taxonomists, who held the expertise for identification of various plant species based on their morphological and other characters. Another notable aspect was that of plant physiology. However no heavy emphasis was given on bio prospecting of the vast plant biodiversity. Though almost all ancient cultures had t...

  20. Plutonium storage criteria

    Energy Technology Data Exchange (ETDEWEB)

    Chung, D. [Scientech, Inc., Germantown, MD (United States); Ascanio, X. [Dept. of Energy, Germantown, MD (United States)

    1996-05-01

    The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

  1. Plutonium bioaccumulation in seabirds.

    Science.gov (United States)

    Strumińska-Parulska, Dagmara I; Skwarzec, Bogdan; Fabisiak, Jacek

    2011-12-01

    The aim of the paper was plutonium (²³⁸Pu and ²³⁹⁺²⁴⁰Pu) determination in seabirds, permanently or temporarily living in northern Poland at the Baltic Sea coast. Together 11 marine birds species were examined: 3 species permanently residing in the southern Baltic, 4 species of wintering birds and 3 species of migrating birds. The obtained results indicated plutonium is non-uniformly distributed in organs and tissues of analyzed seabirds. The highest plutonium content was found in the digestion organs and feathers, the smallest in skin and muscles. The plutonium concentration was lower in analyzed species which feed on fish and much higher in herbivorous species. The main source of plutonium in analyzed marine birds was global atmospheric fallout.

  2. Simulated productivity of conceptual, multi-headed tree planting devices

    OpenAIRE

    Ersson, Back Tomas; Jundén, Linus; Lindh, Erik Mattias; Bergsten, Urban

    2014-01-01

    Mechanized tree planting is presently enjoying a revival in Fennoscandia with increased focus on further technical development. To explore the productivity effect of multiple heads on crane-mounted tree planting devices, we used a discrete-event simulation tool in which excavator-mounted one- to four-headed devices reforested clearcuts with variable frequencies of obstacles. During the simulations, the device models either mounded or inverted soil and then planted seedlings. A planting head c...

  3. Terrestrial plant methane production and emission

    DEFF Research Database (Denmark)

    Bruhn, Dan; Møller, Ian M.; Mikkelsen, Teis Nørgaard;

    2012-01-01

    In this minireview, we evaluate all experimental work published on the phenomenon of aerobic methane (CH4) generation in terrestrial plants and plant. Clearly, despite much uncertainty and skepticism, we conclude that the phenomenon is true. Four stimulating factors have been observed to induce a...

  4. PLUTONIUM-CERIUM-COBALT AND PLUTONIUM-CERIUM-NICKEL ALLOYS

    Science.gov (United States)

    Coffinberry, A.S.

    1959-08-25

    >New plutonium-base teroary alloys useful as liquid reactor fuels are described. The alloys consist of 10 to 20 atomic percent cobalt with the remainder plutonium and cerium in any desired proportion, with the plutonium not in excess of 88 atomic percent; or, of from 10 to 25 atomic percent nickel (or mixture of nickel and cobalt) with the remainder plutonium and cerium in any desired proportion, with the plutonium not in excess of 86 atomic percent. The stated advantages of these alloys over unalloyed plutonium for reactor fuel use are a lower melting point and a wide range of permissible plutonium dilution.

  5. Plutonium chemistry of the ocean

    International Nuclear Information System (INIS)

    Plutonium is a man-made element whose behavior in the marine environment is inadequately known at present. It has been studied intensively in connection with production of weapons and power sources and has been characterized as an extremely toxic substance. Nevertheless, only a few dozen measurements have been made of concentrations in seawater and in the associated organisms and sediments. The first of these were as recent as 1964. There are reasons to believe its chemical behavior in the ocean is different from what has been observed on land, and that it will be difficult to predict how plutonium will distribute itself in the ocean. The consequences of increased environmental concentrations of Pu are discussed

  6. Metabolic engineering for the production of plant isoquinoline alkaloids.

    Science.gov (United States)

    Diamond, Andrew; Desgagné-Penix, Isabel

    2016-06-01

    Several plant isoquinoline alkaloids (PIAs) possess powerful pharmaceutical and biotechnological properties. Thus, PIA metabolism and its fascinating molecules, including morphine, colchicine and galanthamine, have attracted the attention of both the industry and researchers involved in plant science, biochemistry, chemical bioengineering and medicine. Currently, access and availability of high-value PIAs [commercialized (e.g. galanthamine) or not (e.g. narciclasine)] is limited by low concentration in nature, lack of cultivation or geographic access, seasonal production and risk of overharvesting wild plant species. Nevertheless, most commercial PIAs are still extracted from plant sources. Efforts to improve the production of PIA have largely been impaired by the lack of knowledge on PIA metabolism. With the development and integration of next-generation sequencing technologies, high-throughput proteomics and metabolomics analyses and bioinformatics, systems biology was used to unravel metabolic pathways allowing the use of metabolic engineering and synthetic biology approaches to increase production of valuable PIAs. Metabolic engineering provides opportunity to overcome issues related to restricted availability, diversification and productivity of plant alkaloids. Engineered plant, plant cells and microbial cell cultures can act as biofactories by offering their metabolic machinery for the purpose of optimizing the conditions and increasing the productivity of a specific alkaloid. In this article, is presented an update on the production of PIA in engineered plant, plant cell cultures and heterologous micro-organisms. PMID:26503307

  7. Prospects for the establishment of plutonium recycle in thermal reactors in the Foratom countries. Status and assessment

    International Nuclear Information System (INIS)

    The paper reviews the technical status of plutonium recycle in thermal reactors in the Foratom countries and assesses the prospect for it becoming established in the future with the implicit assumptions that uranium oxide reprocessing capacity will be installed commensurate with the projected programmes for thermal reactor installation and that there will be no insuperable environmental, security or safeguards obstacles to the use of plutonium as a fuel. It is argued that the feasibility of using plutonium as an alternative to 235U as the fuel for thermal reactors, particularly LWRs, has been extensively demonstrated by a number of Foratom countries and the main problem areas are fuel fabrication and fuel reprocessing. Mixed-oxide fuel fabrication has been well established on the prototype plant scale using low-irradiation plutonium, but it is recognized that the future design of production-scale plants will need to cater for the significantly higher radiation levels from high burnup plutonium and meet stricter environmental requirements on operator dosage and waste arisings. The main constraint on the establishment of recycle up to now has been the lack of available plutonium owing to the absence of significant uranium-oxide fuel reprocessing capacity. An assessment of the plutonium arisings in Europe, based on the projected uranium-oxide reprocessing capacity, shows that by 1990 plutonium, surplus to FBR requirements, should be accumulating by about 10t/a, sufficient to fuel about 8000MW(e) of LWRs. A further constraint would then be the availability and technical problems of mixed-oxide reprocessing, which is one of the areas identified for international collaboration. It is concluded that whilst there is unlikely to be substantial recycle of plutonium in thermal reactors in the Foratom countries before the early 1990s, an incentive could possibly arise about that time. The strength of this incentive will depend on a number of factors including the status of the

  8. International and institutional aspects of reprocessing and plutonium management

    International Nuclear Information System (INIS)

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

  9. Pulmonary carcinogenesis from plutonium-containing particles

    International Nuclear Information System (INIS)

    Induction of lung tumors by various types of radiation is of paramount concern to the nuclear industry. The data presented were obtained by exposing the pulmonary system of Syrian hamsters to particles of zirconium oxide containing various amounts of either plutonium-238 or -239 as the alpha radiation source. These particles were injected intravenously and lodged permanently in the capillary bed of the lung. When less than 20% of the lung tissue was irradiated, simulating the ''hot particle'' mode, tumors were not evident with lung burdens up to 500 nCi plutonium. More diffuse irradiation significantly increased the tumor incidence, with lung burdens of 50 to 150 nCi. When plutonium-laden microspheres were administered intratracheally, tumor production was considerably increased and the addition of 3 mg of iron oxide intratracheally further increased the incidence. Using the zirconium oxide matrix for the carrier of plutonium in aerosol particles produced tumor incidences of up to 50% in Syrian hamsters exposed by inhalation. Initial pulmonary (alveolar) burdens reached 100 nCi of plutonium. Similar inhalation studies using plutonium dioxide alone (no matrix) failed to produce any increase in lung tumorigenesis. The results are discussed in terms of possible mechanisms necessary for lung carcinogenesis. (H.K.)

  10. COLLABORATIVE NEGOTIATIONS A SUCCESSFUL APPROACH FOR NEGOTIATING COMPLIANCE MILESTONES FOR THE TRANSITION OF THE PLUTONIUM FINISHING PLANT (PFP), HANFORD NUCLEAR RESERVATION, AND HANFORD, WASHINGTON

    Energy Technology Data Exchange (ETDEWEB)

    Hebdon, J.; Yerxa, J.; Romine, L.; Hopkins, AM; Piippo, R.; Cusack, L.; Bond, R.; Wang, Oliver; Willis, D.

    2003-02-27

    The Hanford Nuclear Reservation is a former U. S. Department of Energy Defense Production Site. The site is currently listed on the National Priorities List of the Comprehensive Environmental Response Compensation and Liability Act of 1980 (CERCLA) and is undergoing cleanup and environmental restoration. The PFP is a former Plutonium metal production facility. The operating mission of the PFP ended with a DOE Headquarters shutdown letter in October of 1996. Generally, the receipt of a shutdown letter initiates the start of Transition (as the first step of Decommissioning) of a facility. The Hanford site is subject to the Hanford Federal Facilities Compliance Act and Consent Order (HFFCCO), an order on consent signed by the DOE, the U. S. Environmental Protection Agency, (EPA) and the Washington Department of Ecology (WDOE). Under the HFFCCO, negotiations for transition milestones begin within six months after the issuance of a shutdown order. In the case of the PFP, the Nuclear Materials disposition and stabilization activities, a DOE responsibility, were necessary as precursor activities to Transition. This situation precipitated a crisis in the negotiations between the agencies, and formal negotiations initiated in 1997 ended in failure. The negotiations reached impasse on several key regulatory and operational issues. The 1997 negotiation was characterized by a strongly positional style. DOE and the regulatory personnel took hard lines early in the negotiations and were unable to move to resolution of key issues after a year and a half. This resulted in unhappy stakeholders, poor publicity and work delays as well as wounded relationships between DOE and the regulatory community. In the 2000-2001 PFP negotiations, a completely different approach was suggested and eventually initiated: Collaborative Negotiations. The collaborative negotiation style resulted in agreement between the agencies on all key issues within 6 months of initiation. All parties were very

  11. COLLABORATIVE NEGOTIATIONS A SUCCESSFUL APPROACH FOR NEGOTIATING COMPLIANCE MILESTONES FOR THE TRANSITION OF THE PLUTONIUM FINISHING PLANT (PFP), HANFORD NUCLEAR RESERVATION, AND HANFORD, WASHINGTON

    International Nuclear Information System (INIS)

    The Hanford Nuclear Reservation is a former U. S. Department of Energy Defense Production Site. The site is currently listed on the National Priorities List of the Comprehensive Environmental Response Compensation and Liability Act of 1980 (CERCLA) and is undergoing cleanup and environmental restoration. The PFP is a former Plutonium metal production facility. The operating mission of the PFP ended with a DOE Headquarters shutdown letter in October of 1996. Generally, the receipt of a shutdown letter initiates the start of Transition (as the first step of Decommissioning) of a facility. The Hanford site is subject to the Hanford Federal Facilities Compliance Act and Consent Order (HFFCCO), an order on consent signed by the DOE, the U. S. Environmental Protection Agency, (EPA) and the Washington Department of Ecology (WDOE). Under the HFFCCO, negotiations for transition milestones begin within six months after the issuance of a shutdown order. In the case of the PFP, the Nuclear Materials disposition and stabilization activities, a DOE responsibility, were necessary as precursor activities to Transition. This situation precipitated a crisis in the negotiations between the agencies, and formal negotiations initiated in 1997 ended in failure. The negotiations reached impasse on several key regulatory and operational issues. The 1997 negotiation was characterized by a strongly positional style. DOE and the regulatory personnel took hard lines early in the negotiations and were unable to move to resolution of key issues after a year and a half. This resulted in unhappy stakeholders, poor publicity and work delays as well as wounded relationships between DOE and the regulatory community. In the 2000-2001 PFP negotiations, a completely different approach was suggested and eventually initiated: Collaborative Negotiations. The collaborative negotiation style resulted in agreement between the agencies on all key issues within 6 months of initiation. All parties were very

  12. REDUCING TOXICITY CHEMICALS PLANT PROTECTION PRODUCTS

    OpenAIRE

    Litvishko, Valery; Myaskovskaya, Tatiana

    2014-01-01

    The samples of microencapsulated pesticide have been investigated in acute experiments on laboratory animals. The results of the research have determined that microencapsulation can reduce toxicity of plant protection chemicals.

  13. Role of root microbiota in plant productivity.

    Science.gov (United States)

    Tkacz, Andrzej; Poole, Philip

    2015-04-01

    The growing human population requires increasing amounts of food, but modern agriculture has limited possibilities for increasing yields. New crop varieties may be bred to have increased yields and be more resistant to environmental stress and pests. However, they still require fertilization to supplement essential nutrients that are normally limited in the soil. Soil microorganisms present an opportunity to reduce the requirement for inorganic fertilization in agriculture. Microorganisms, due to their enormous genetic pool, are also a potential source of biochemical reactions that recycle essential nutrients for plant growth. Microbes that associate with plants can be considered to be part of the plant's pan-genome. Therefore, it is essential for us to understand microbial community structure and their 'metagenome' and how it is influenced by different soil types and crop varieties. In the future we may be able to modify and better utilize the soil microbiota potential for promoting plant growth. PMID:25908654

  14. Role of root microbiota in plant productivity.

    Science.gov (United States)

    Tkacz, Andrzej; Poole, Philip

    2015-04-01

    The growing human population requires increasing amounts of food, but modern agriculture has limited possibilities for increasing yields. New crop varieties may be bred to have increased yields and be more resistant to environmental stress and pests. However, they still require fertilization to supplement essential nutrients that are normally limited in the soil. Soil microorganisms present an opportunity to reduce the requirement for inorganic fertilization in agriculture. Microorganisms, due to their enormous genetic pool, are also a potential source of biochemical reactions that recycle essential nutrients for plant growth. Microbes that associate with plants can be considered to be part of the plant's pan-genome. Therefore, it is essential for us to understand microbial community structure and their 'metagenome' and how it is influenced by different soil types and crop varieties. In the future we may be able to modify and better utilize the soil microbiota potential for promoting plant growth.

  15. Fused salt processing of impure plutonium dioxide to high-purity plutonium metal

    International Nuclear Information System (INIS)

    A process for converting impure plutonium dioxide (approx. 96% pure) to high-purity plutonium metal (>99.9%) was developed. The process consists of reducing the oxide to an impure plutonium metal intermediate with calcium metal in molten calcium chloride. The impure intermediate metal is cast into an anode and electrorefined to produce high-purity plutonium metal. The oxide reduction step is being done now on a 0.6-kg scale with the resulting yield being >99.5%. The electrorefining is being done on a 4.0-kg scale with the resulting yield being 80 to 85%. The purity of the product, which averages 99.98%, is essentially insensitive to the purity of the feed metal. The yield, however, is directly dependent on the chemical composition of the feed. To date, approximately 250 kg of impure oxide has been converted to pure metal by this processing sequence. The availability of impure plutonium dioxide, together with the need for pure plutonium metal, makes this sequence a valuable plutonium processing tool

  16. Plant Design for the Production of DUAGG

    Energy Technology Data Exchange (ETDEWEB)

    Ferrada, J.J.

    2003-02-04

    The cost of producing DUAGG is an important consideration for any interested private firm in determining whether DUCRETE is economically viable as a material of construction in next-generation spent nuclear fuel casks. This study analyzed this project as if it was a stand-alone project. The capital cost includes engineering design, equipment costs and installation, start up, and management; the study is not intended to be a life-cycle cost analysis. The costs estimated by this study are shown in Table ES.1, and the conclusions of this study are listed in Table ES.2. The development of DUAGG and DUCRETE is a major thrust of the Depleted Uranium Uses Research and Development Project. An obvious use of depleted uranium is as a shielding material (e.g., DUCRETE). DUCRETE is made by replacing the conventional stone aggregate in concrete with DUAGG. One objective of this project is to bring the development of DUCRETE to a point at which a demonstrated basis exists for its commercial deployment. The estimation of the costs to manufacture DUAGG is an important part of this effort. Paul Lessing and William Quapp developed DUAGG and DUCRETE as part of an Idaho National Engineering and Environmental Laboratory (INEEL) program to find beneficial uses for depleted uranium (DU). Subsequently, this technology was licensed to Teton Technologies, Inc. The DUAGG process mixes DUO{sub 2} with sintering materials and additives to form pressed briquettes. These briquettes are sintered at 1300 C, and the very dense sintered briquettes are then crushed and classified into gap-graded size fractions. The graded DUAGG is then ready to be used to make high-strength heavy DUCRETE. The DUCRETE shielding will be placed into an annular steel cask-shell mold, which has internal steel reinforcing bars. The objectives of this study are to (1) use previous DUAGG process developments to design a plant that will produce DUAGG at a baseline rate, (2) determine the size of the equipment required to meet

  17. Recommended plutonium release fractions from postulated fires. Final report

    International Nuclear Information System (INIS)

    This report was written at the request of EG ampersand G Rocky Flats, Inc. in support of joint emergency planning for the Rocky Flats Plant (RFP) by EG ampersand G and the State of Colorado. The intent of the report is to provide the State of Colorado with an independent assessment of any respirable plutonium releases that might occur in the event of a severe fire at the plant. Fire releases of plutonium are of interest because they have been used by EG ampersand G to determine the RFP emergency planning zones. These zones are based on the maximum credible accident (MCA) described in the RFP Final Environmental Impact Statement (FEIS) of 1980, that MCA is assumed to be a large airplane crashing into a RFP plutonium building.The objective of this report was first, to perform a worldwide literature review of relevant release experiments from 1960 to the present and to summarize those findings, and second, to provide recommendations for application of the experimental data to fire release analyses at Rocky Flats. The latter step requires translation between experimental and expected RFP accident parameters, or ''scaling.'' The parameters of particular concern are: quantities of material, environmental parameters such as the intensity of a fire, and the physico-chemical forms of the plutonium. The latter include plutonium metal, bulk plutonium oxide powder, combustible and noncombustible wastes contaminated with plutonium oxide powder, and residues from plutonium extraction processes

  18. Recommended plutonium release fractions from postulated fires. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kogan, V.; Schumacher, P.M.

    1993-12-01

    This report was written at the request of EG&G Rocky Flats, Inc. in support of joint emergency planning for the Rocky Flats Plant (RFP) by EG&G and the State of Colorado. The intent of the report is to provide the State of Colorado with an independent assessment of any respirable plutonium releases that might occur in the event of a severe fire at the plant. Fire releases of plutonium are of interest because they have been used by EG&G to determine the RFP emergency planning zones. These zones are based on the maximum credible accident (MCA) described in the RFP Final Environmental Impact Statement (FEIS) of 1980, that MCA is assumed to be a large airplane crashing into a RFP plutonium building.The objective of this report was first, to perform a worldwide literature review of relevant release experiments from 1960 to the present and to summarize those findings, and second, to provide recommendations for application of the experimental data to fire release analyses at Rocky Flats. The latter step requires translation between experimental and expected RFP accident parameters, or ``scaling.`` The parameters of particular concern are: quantities of material, environmental parameters such as the intensity of a fire, and the physico-chemical forms of the plutonium. The latter include plutonium metal, bulk plutonium oxide powder, combustible and noncombustible wastes contaminated with plutonium oxide powder, and residues from plutonium extraction processes.

  19. Unconventional options for plutonium disposition. Proceedings of a technical committee meeting held in Obninsk, Russian Federation, 7-11 November 1994

    International Nuclear Information System (INIS)

    This publication summarizes discussions and presents selected papers from a Technical Committee meeting that the IAEA convened in Obninsk, near Moscow, Russia, 7-11 November 1994 at the invitation of the Ministry of the Russian Federation on Atomic Energy, and which was hosted by the Institute of Physics and Power Engineering. The meeting focused on the disposition of plutonium produced from the operation of nuclear power plants in areas related to the nuclear fuel cycle. Plutonium is formed in all existing nuclear power plants and the unconsumed part remaining in spent fuel is a generic by-product of nuclear power generation. Over the next 15 to 20 years, a significant amount of plutonium will be produced in nuclear power stations worldwide, adding to amounts already in storage. Additionally, the world's plutonium stocks are being affected by decisions concerning the management and utilization of plutonium recovered from nuclear weapons which are being dismantled. In this context, national strategies are directed at reducing the stockpiles of separated plutonium worldwide, and in further developing technologies capable of safely and securely using and handling plutonium. The purpose of the IAEA's Technical Committee meeting was to consider unconventional approaches for plutonium disposition, both from the points of view of the fuel cycle as a whole and the specific types of nuclear fuel being used. The aims were to obtain technical descriptions of these approaches, engineering judgements on their technological status and development, and reports on national experience in this field. The meeting's results and conclusions are providing valuable guidance for future activities in this subject area. Refs, figs and tabs

  20. Plutonium working group report on environmental, safety and health vulnerabilities associated with the Department's plutonium storage. Volume I: Summary

    International Nuclear Information System (INIS)

    At the conclusion of the Cold War, the Department of Energy (DOE) stopped plutonium processing for nuclear weapons production. Facilities used for that purpose now hold significant quantities of plutonium in various forms. Unless properly stored and handled, plutonium can present environment, safety and health (ES ampersand H) hazards. Improperly stored plutonium poses a variety of hazards. When containers or packaging fail to fully protect plutonium metal from exposure to air, oxidation can occur and cause packaging failures and personnel contamination. Contamination can also result when plutonium solutions leak from bottles, tanks or piping. Plutonium in the form of scrap or residues generated by weapons production are often very corrosive, chemically reactive and difficult to contain. Buildings and equipment that are aging, poorly maintained or of obsolete design contribute to the overall problem. Inadvertent accumulations of plutonium of any form in sufficient quantities within facilities can result in nuclear criticality events that could emit large amounts of radiation locally. Contamination events and precursors of criticality events are causing safety and health concerns for workers at the Department's plutonium facilities. Contamination events also potentially threaten the public and the surrounding environment

  1. Progress on plutonium stabilization

    Energy Technology Data Exchange (ETDEWEB)

    Hurt, D. [Defense Nuclear Facilities Safety Board, Washington, DC (United States)

    1996-05-01

    The Defense Nuclear Facilities Safety Board has safety oversight responsibility for most of the facilities where unstable forms of plutonium are being processed and packaged for interim storage. The Board has issued recommendations on plutonium stabilization and has has a considerable influence on DOE`s stabilization schedules and priorities. The Board has not made any recommendations on long-term plutonium disposition, although it may get more involved in the future if DOE develops plans to use defense nuclear facilities for disposition activities.

  2. PLUTONIUM ELECTROREFINING CELLS

    Science.gov (United States)

    Mullins, L.J. Jr.; Leary, J.A.; Bjorklund, C.W.; Maraman, W.J.

    1963-07-16

    Electrorefining cells for obtaining 99.98% plutonium are described. The cells consist of an impure liquid plutonium anode, a molten PuCl/sub 3/-- alkali or alkaline earth metal chloanode, a molten PuCl/sub 3/-alkali or alkaline earth metal chloride electrolyte, and a nonreactive cathode, all being contained in nonreactive ceramic containers which separate anode from cathode by a short distance and define a gap for the collection of the purified liquid plutonium deposited on the cathode. Important features of these cells are the addition of stirrer blades on the anode lead and a large cathode surface to insure a low current density. (AEC)

  3. Separation Method of Uranium and Plutonium From Large Amount of Neptunium

    Institute of Scientific and Technical Information of China (English)

    SU; Yu-lan; JIN; Hua; YING; Zhe-cong; ZHAO; Sheng-yang

    2013-01-01

    Uranium and plutonium are limited strictly in the neptunium product.To eliminate the influence of neptunium matrix on determination of uranium and plutonium,a new separation method of uranium and plutonium from large amount of neptunium by TEVA column has been developed,which is illustrated in Fig.1.

  4. Extraction behavior of uranium(VI), plutonium(VI) and some fission products with gamma pre-irradiated n-dodecane solutions of n,n'-dihexyl substituted amides

    International Nuclear Information System (INIS)

    The extraction behavior of uranium(VI), plutonium(IV) and some fission products like zirconium(IV), ruthenium(III) and europium(III) from 3.5M nitric acid with γ-irradiated organic phase pre-equilibrated n-dodecane solutions of dihexyl derivatives of hexanamide (DHHA), octanamide (DHOA) and decanamide (DHDA) has been investigated as a function of absorbed dose upto 184x104 Gy. The results indicate that the extraction of uranium(VI) decreases gradually with dose upto 72x104 Gy and becomes almost constant thereafter, while, the extraction of plutonium(IV) decreases upto a dose of 20x104 Gy and then increases rapidly up to a dose of 82x104 Gy indicating synergistic effects of radiolytic products formed at higher doses. Extraction of zirconium(IV) increases gradually upto a dose 72x104 Gy. Europium(III) does not get extracted with any of these amides in the entire dose range (0-184x104 Gy) studied, however, ruthenium shows insignificant increase in extraction with dose. The decrease in D values noticed in the case of plutonium and zirconium after the dose of 72x104 Gy which was attributed to the third phase formation and emulsification. Infrared studies confirm the final products of radiolysis as the respective amines and carboxylic acids. The degraded amide contents have been estimated by quantitative IR spectrophotometric technique. Extraction data obtained for uranium(VI) and plutonium(IV) with TBP/n-dodecane system have also been compared under similar experimental conditions. (author). 30 refs., 1 fig., 3 tabs

  5. Design criteria -- Reactor plant modifications for increased production and 100-C Area Alterations (Sections A and B) CG-558. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Russ, M.H.

    1954-08-10

    This document defines the basic criteria to be used in the preparation of detailed design for Project CG-558, Reactor Plant Modification for Increased Production and for Project CG-600, 100-C Area Alterations. It has been determined that the most economical method of increasing plutonium production within the next five years is by the modernization and improvement of the 100-B, 100-C, 100-D, 100-DR, 100-F, and 100-H reactor plants. These reactors are currently incapable of operating at their maximum potential power levels because of a limited availability of process cooling water. As a result of this programs, it is estimated that 1650-2350 megawatts of total additional production will be achieved. The purpose of this document is to set forth the design for certain modifications and additions to Hanford reactors and their supporting facilities as required to obtain higher power levels and improve the safety of reactor operation.

  6. Comparison of Authorization/Registration/Notification Processes among Biocidal Products, Cosmetics, Plant Protection Products and Human Medicinal Products

    OpenAIRE

    Söyleriz, Yüksel

    2015-01-01

    In this study, comparison of the authorization/registration/notification processes of biocidal products, cosmetics, plant protection products and medicinal products are made and in this respect, the situation in EU is assessed.

  7. Plutonium spectrophotometric analysis

    International Nuclear Information System (INIS)

    Plutonium ions in solution have absorption spectra so different that it is possible to use them for analytical purposes. Detailed studies have been performed in nitric solutions. Some very convenient methods for the determination of plutonium and its oxidation states, especially the ratios Pu(III):Pu(IV) and Pu(IV):Pu(VI) in a mixture of both, have been developed. These methods are described in this paper, including: a) Absorption spectra for plutonium (III), (IV), (VI) and mixtures. b) Relative extinction coefficients for the above mentioned species. c) Dependences of the relative extinction coefficients on the nitric acid concentration and the plutonium VI deviation from the Beer-Lambert law. The developed methods are simple and rapid and then, suitable in process control. Accuracy is improved when relative absorbance measurements are performed or controlled the variables which have effect on the spectra and extinction coefficients. (Author)

  8. Plutonium dissolution process

    Science.gov (United States)

    Vest, Michael A.; Fink, Samuel D.; Karraker, David G.; Moore, Edwin N.; Holcomb, H. Perry

    1996-01-01

    A two-step process for dissolving plutonium metal, which two steps can be carried out sequentially or simultaneously. Plutonium metal is exposed to a first mixture containing approximately 1.0M-1.67M sulfamic acid and 0.0025M-0.1M fluoride, the mixture having been heated to a temperature between 45.degree. C. and 70.degree. C. The mixture will dissolve a first portion of the plutonium metal but leave a portion of the plutonium in an oxide residue. Then, a mineral acid and additional fluoride are added to dissolve the residue. Alteratively, nitric acid in a concentration between approximately 0.05M and 0.067M is added to the first mixture to dissolve the residue as it is produced. Hydrogen released during the dissolution process is diluted with nitrogen.

  9. Production planning modernization: The case plywood plant

    OpenAIRE

    Laamanen, Jani

    2015-01-01

    In the last 20 years, an interest for efficient use of capital, labour, and natural resources has risen among consumers and manufacturers. Although order lists may be slightly adapted for production, its flexibility is the main driver of efficiency. Due to the flexibility, the manufacturer is able to cope with customer demands, such as quick and exact delivery times or unique product specifications. The company that succeeds in fulfilling customer demands without losing production efficiency,...

  10. New salty waffle products "Fish Krekis" with fish & plant semifinished products

    Directory of Open Access Journals (Sweden)

    Fedorova Dina

    2016-04-01

    Full Text Available The study examines the directions of expansion of the range of wafer snack products of high nutritional value by using fish & plant semifinished products. The study scientifically grounds the benefits of using the new fish & plant semifinished products in manufacturing waffle salty snack products. The data provided in the article prove that the use of the fish & plant semifinished products & herbal ingredients enable a range of the new wafer snack products «Fish krekis» with high content of proteins, organic calcium, fiber and vitamins, with improved consumer properties, as well as more efficient use of Ukrainian raw fish materials.

  11. Minutes of the 28th Annual Plutonium Sample Exchange Meeting. Part II: metal sample exchange

    International Nuclear Information System (INIS)

    Contents of this publication include the following list of participating laboratories; agenda; attendees; minutes of October 25 and 26 meeting; and handout materials supplied by speakers. The handout materials cover the following: statistics and reporting; plutonium - chemical assay 100% minus impurities; americium neptunium, uranium, carbon and iron data; emission spectroscopy data; plutonium metal sample exchange; the calorimetry sample exchange; chlorine determination in plutonium metal using phyrohydrolysis; spectrophotometric determination of 238-plutonium in oxide; plutonium measurement capabilities at the Savannah River Plant; and robotics in radiochemical laboratory

  12. Field study to obtain plutonium contents of old field vegetation and soil under humid climatic conditions

    International Nuclear Information System (INIS)

    Soil and vegetation at the Savannah River Plant were analyzed for plutonium. The data indicate that vacuumed samples have the greatest concentration of plutonium, that resuspension and fallout of plutonium is a principal contributor to the plutonium concentration of vegetation because the 238Pu concentrations are more closely aligned to source term values than soil values under field conditions, and that laboratory uptake studies may underestimate the plutonium content of vegetation growing under field conditions adjacent to a fuel reprocessing facility. (U.S.)

  13. Minutes of the 28th Annual Plutonium Sample Exchange Meeting. Part II: metal sample exchange

    Energy Technology Data Exchange (ETDEWEB)

    1984-01-01

    Contents of this publication include the following list of participating laboratories; agenda; attendees; minutes of October 25 and 26 meeting; and handout materials supplied by speakers. The handout materials cover the following: statistics and reporting; plutonium - chemical assay 100% minus impurities; americium neptunium, uranium, carbon and iron data; emission spectroscopy data; plutonium metal sample exchange; the calorimetry sample exchange; chlorine determination in plutonium metal using phyrohydrolysis; spectrophotometric determination of 238-plutonium in oxide; plutonium measurement capabilities at the Savannah River Plant; and robotics in radiochemical laboratory.

  14. Plants for water recycling, oxygen regeneration and food production

    Science.gov (United States)

    Bubenheim, D. L.

    1991-01-01

    During long-duration space missions that require recycling and regeneration of life support materials the major human wastes to be converted to usable forms are CO2, hygiene water, urine and feces. A Controlled Ecological Life Support System (CELSS) relies on the air revitalization, water purification and food production capabilities of higher plants to rejuvenate human wastes and replenish the life support materials. The key processes in such a system are photosynthesis, whereby green plants utilize light energy to produce food and oxygen while removing CO2 from the atmosphere, and transpiration, the evaporation of water from the plant. CELSS research has emphasized the food production capacity and efforts to minimize the area/volume of higher plants required to satisfy all human life support needs. Plants are a dynamic system capable of being manipulated to favour the supply of individual products as desired. The size and energy required for a CELSS that provides virtually all human needs are determined by the food production capacity. Growing conditions maximizing food production do not maximize transpiration of water; conditions favoring transpiration and scaling to recycle only water significantly reduces the area, volume, and energy inputs per person. Likewise, system size can be adjusted to satisfy the air regeneration needs. Requirements of a waste management system supplying inputs to maintain maximum plant productivity are clear. The ability of plants to play an active role in waste processing and the consequence in terms of degraded plant performance are not well characterized. Plant-based life support systems represent the only potential for self sufficiency and food production in an extra-terrestrial habitat.

  15. Bioconversion potential of plant enzymes for the production of pharmaceuticals

    NARCIS (Netherlands)

    Pras, N; Woerdenbag, HJ; vanUden, W

    1995-01-01

    Plant enzymes are able to catalyze regio- and stereospecific reactions. Freely suspended and immobilized plant cells as well as enzyme preparations can therefore be applied for the production of pharmaceuticals by bioconversion, as such or in combination with chemical syntheses. This review paper de

  16. Optimization of Jatropha curcas pure plant oil production

    NARCIS (Netherlands)

    Subroto, Erna

    2015-01-01

    The use of pure plant oils as fuel, either directly or after conversion of the oil to bio-diesel, is considered to be one of the potential contributions to the transformation of the current fossil oil based economy to a sustainable bio-based one. The production of oil producing seeds using plants th

  17. Examination of the potential for diversion or clandestine dual use of a pebble-bed reactor to produce plutonium

    International Nuclear Information System (INIS)

    This paper explores the susceptibility of Pebble-Bed Reactors (PBRs) to be used overtly or covertly for the production of plutonium for nuclear weapons. The basic assumption made for the consideration of overt production is that a country would purchase a PBR with the ostensible motive of producing electric power; then, after the power plant was built, the country would divert the facility entirely to the production of weapons material. It is assumed that the country would then have to manufacture production pebbles from natural uranium. The basic assumption made for covert production is that the country would obtain and use a PBR for power production, but that it would clandestinely feed plutonium production pebbles through the reactor in such small numbers that the perturbation on power plant operation would be very difficult to detect. This paper shows the potential rate of plutonium production under such constraints. It is demonstrated that the PBR is a very poor choice for either form of proliferation-intent use. (author)

  18. Enhanced methanol production in plants provides broad spectrum insect resistance.

    Directory of Open Access Journals (Sweden)

    Sameer Dixit

    Full Text Available Plants naturally emit methanol as volatile organic compound. Methanol is toxic to insect pests; but the quantity produced by most of the plants is not enough to protect them against invading insect pests. In the present study, we demonstrated that the over-expression of pectin methylesterase, derived from Arabidopsis thaliana and Aspergillus niger, in transgenic tobacco plants enhances methanol production and resistance to polyphagous insect pests. Methanol content in the leaves of transgenic plants was measured using proton nuclear spectroscopy (1H NMR and spectra showed up to 16 fold higher methanol as compared to control wild type (WT plants. A maximum of 100 and 85% mortality in chewing insects Helicoverpa armigera and Spodoptera litura larvae was observed, respectively when fed on transgenic plants leaves. The surviving larvae showed less feeding, severe growth retardation and could not develop into pupae. In-planta bioassay on transgenic lines showed up to 99 and 75% reduction in the population multiplication of plant sap sucking pests Myzus persicae (aphid and Bemisia tabaci (whitefly, respectively. Most of the phenotypic characters of transgenic plants were similar to WT plants. Confocal microscopy showed no deformities in cellular integrity, structure and density of stomata and trichomes of transgenic plants compared to WT. Pollen germination and tube formation was also not affected in transgenic plants. Cell wall enzyme transcript levels were comparable with WT. This study demonstrated for the first time that methanol emission can be utilized for imparting broad range insect resistance in plants.

  19. Plant Natural Products Targeting Bacterial Virulence Factors.

    Science.gov (United States)

    Silva, Laura Nunes; Zimmer, Karine Rigon; Macedo, Alexandre José; Trentin, Danielle Silva

    2016-08-24

    Decreased antimicrobial efficiency has become a global public health issue. The paucity of new antibacterial drugs is evident, and the arsenal against infectious diseases needs to be improved urgently. The selection of plants as a source of prototype compounds is appropriate, since plant species naturally produce a wide range of secondary metabolites that act as a chemical line of defense against microorganisms in the environment. Although traditional approaches to combat microbial infections remain effective, targeting microbial virulence rather than survival seems to be an exciting strategy, since the modulation of virulence factors might lead to a milder evolutionary pressure for the development of resistance. Additionally, anti-infective chemotherapies may be successfully achieved by combining antivirulence and conventional antimicrobials, extending the lifespan of these drugs. This review presents an updated discussion of natural compounds isolated from plants with chemically characterized structures and activity against the major bacterial virulence factors: quorum sensing, bacterial biofilms, bacterial motility, bacterial toxins, bacterial pigments, bacterial enzymes, and bacterial surfactants. Moreover, a critical analysis of the most promising virulence factors is presented, highlighting their potential as targets to attenuate bacterial virulence. The ongoing progress in the field of antivirulence therapy may therefore help to translate this promising concept into real intervention strategies in clinical areas. PMID:27437994

  20. Plant Products for Pharmacology: Application of Enzymes in Their Transformations

    Directory of Open Access Journals (Sweden)

    Marie Zarevúcka

    2008-12-01

    Full Text Available Different plant products have been subjected to detailed investigations due to their increasing importance for improving human health. Plants are sources of many groups of natural products, of which large number of new compounds has already displayed their high impact in human medicine. This review deals with the natural products which may be found dissolved in lipid phase (phytosterols, vitamins etc.. Often subsequent convenient transformation of natural products may further improve the pharmacological properties of new potential medicaments based on natural products. To respect basic principles of sustainable and green procedures, enzymes are often employed as efficient natural catalysts in such plant product transformations. Transformations of lipids and other natural products under the conditions of enzyme catalysis show increasing importance in environmentally safe and sustainable production of pharmacologically important compounds. In this review, attention is focused on lipases, efficient and convenient biocatalysts for the enantio- and regioselective formation / hydrolysis of ester bond in a wide variety of both natural and unnatural substrates, including plant products, eg. plant oils and other natural lipid phase compounds. The application of enzymes for preparation of acylglycerols and transformation of other natural products provides big advantage in comparison with employing of conventional chemical methods: Increased selectivity, higher product purity and quality, energy conservation, elimination of heavy metal catalysts, and sustainability of the employed processes, which are catalyzed by enzymes. Two general procedures are used in the transformation of lipid-like natural products: (a Hydrolysis/alcoholysis of triacylglycerols and (b esterification of glycerol. The reactions can be performed under conventional conditions or in supercritical fluids/ionic liquids. Enzyme-catalyzed reactions in supercritical fluids combine the

  1. Proposal of environmental quality standards for plant protection products

    OpenAIRE

    Kontiokari, Venla; Mattsoff, Leona

    2011-01-01

    Plant protection products are used in agriculture and forestry to protect crops from weeds, pests and plant diseases. These products are developed to be toxic to target species, but they are often toxic to non-target species also. Since they are spread purposely into the environment, they may also leach to surface waters. The Water Framework Directive (WFD) of the European Parliament and Council was adopted in 2000. The purpose of this Directive is the protection of inland surface and grou...

  2. Catalytic production of aromatics and olefins from plant materials

    Energy Technology Data Exchange (ETDEWEB)

    Haag, W.O.; Rodewald, P.G.; Weisz, P.B.

    1980-08-01

    Hydrocarbons and hydrocarbon-like plant materials offer the possibility of relatively simple and energy-efficient processing to liquid fuels or petrochemicals. The use of such highly reduced photosynthesis products as potential fuels has been advocated by Calvin and coworkers, and Buchanan and coworkers have evaluated several hundred plant species for the presence of hydrocarbons. The yield of extracted oils may exceed 10 wt % of the plant dry weight. Some field growth studies of the most promising of these plants are underway, e.g., by Calvin in California, by Native Plants, Inc., and by the Diamond Shamrock Co., in conjunction with the University of Arizona, mostly with Euphorbia and related genera. Exploratory studies were performed to determine if direct catalytic upgrading of the hydrocarbon-like plant constituents could be carried out. A preliminary report has been published recently. A variety of plant materials were shown to be upgraded to liquid premium fuels by relatively simple catalytic processing over Mobil's shape selective zeolite, ZSM-5. The present paper contains additional information on the conversion of a variety of plant materials with special emphasis on the production of petrochemicals, and discusses key mechanistic aspects of the reactions. Feedstocks were chosen to represent different types of plant materials: corn oil, castor oil and jojoba seed oil; plant extracts from Euphorbia lathyrus and Grindelia squarrosa; and hydrocarbons obtained by tapping of trees such as copaiba oil and natural rubber latex.

  3. State regulation and power plant productivity: background and recommendations

    International Nuclear Information System (INIS)

    This report was prepared by representatives of several state regulatory agencies. It is a guide to some of the activities currently under way in state agencies to promote increased availability of electrical generating power plants. Standard measures of plant performance are defined and the nature of data bases that report such measures is discussed. It includes reviews of current state, federal, and industry programs to enhance power plant productivity and provides detailed outlines of programs in effect in California, Illinois, Michigan, New York, North Carolina, Ohio, and Texas. A number of actions are presented that could be adopted by state regulatory agencies, depending on local conditions. They include: develop a commission position or policy statement to encourage productivity improvements by utilities; coordinate state efforts with ongoing industry and government programs to improve the acquisition of power plant performance data and the maintenance of quality information systems; acquire the capability to perform independent analyses of power plant productivity; direct the establishment of productivity improvement programs, including explicit performance objectives for both existing and planned power plants, and a performance program; establish a program of incentives to motivate productivity improvement activities; and participate in ongoing efforts at all levels and initiate new actions to promote productivity improvements

  4. Fuel ethanol production using nuclear-plant steam

    International Nuclear Information System (INIS)

    In the United States, the production of fuel ethanol from corn for cars and light trucks has increased from about 6 billion liters per year in 2000 to 19 billion liters per year in 2006. A third of the world's liquid fuel demands could ultimately be obtained from biomass. The production of fuel ethanol from biomass requires large quantities of steam. For a large ethanol plant producing 380 million liters of fuel ethanol from corn per year, about 80 MW(t) of 1-MPa (∼180 deg. C) steam is required. Within several decades, the steam demand for ethanol plants in the United States is projected to be tens of gigawatts, with the worldwide demand being several times larger. This market may become the largest market for cogeneration of steam from nuclear electric power plants. There are strong incentives to use steam from nuclear power plants to meet this requirement. The cost of low-pressure steam from nuclear power plants is less than that of natural gas, which is now used to make steam in corn-to-ethanol plants. Steam from nuclear power plants reduces greenhouse gases compared with steam produced from fossil fuels. While ethanol is now produced from sugarcane and corn, the next-generation ethanol plants will use more abundant cellulose feedstocks. It is planned that these plants will burn the lignin in the cellulosic feedstocks to provide the required steam. Lignin is the primary non-sugar-based component in cellulosic biomass that can not be converted to ethanol. Low-cost steam from nuclear plants creates the option of converting the lignin to other liquid fuels and thus increase the liquid fuel production per unit of biomass. Because liquid fuel production from biomass is ultimately limited by the availability of biomass, steam from nuclear plants can ultimately increase the total liquid fuels produced from biomass. (author)

  5. Harnessing plant-microbe interactions for enhancing farm productivity

    OpenAIRE

    Macdonald, Catriona; Singh, Brajesh

    2013-01-01

    Declining soil fertility and farm productivity is a major global concern in order to achieve food security for a burgeoning world population. It is reported that improving soil health alone can increase productivity by 10–15% and in combination with efficient plant traits, farm productivity can be increased up to 50–60%. In this article we explore the emerging microbial and bioengineering technologies, which can be employed to achieve the transformational increase in farm productivity and can...

  6. Ceramification: A plutonium immobilization process

    Energy Technology Data Exchange (ETDEWEB)

    Rask, W.C. [Dept. of Energy, Golden, CO (United States); Phillips, A.G. [Rocky Flats Environmental Technology Site, Golden, CO (United States)

    1996-05-01

    This paper describes a low temperature technique for stabilizing and immobilizing actinide compounds using a combination process/storage vessel of stainless steel, in which measured amounts of actinide nitrate solutions and actinide oxides (and/or residues) are systematically treated to yield a solid article. The chemical ceramic process is based on a coating technology that produces rare earth oxide coatings for defense applications involving plutonium. The final product of this application is a solid, coherent actinide oxide with process-generated encapsulation that has long-term environmental stability. Actinide compounds can be stabilized as pure materials for ease of re-use or as intimate mixtures with additives such as rare earth oxides to increase their degree of proliferation resistance. Starting materials for the process can include nitrate solutions, powders, aggregates, sludges, incinerator ashes, and others. Agents such as cerium oxide or zirconium oxide may be added as powders or precursors to enhance the properties of the resulting solid product. Additives may be included to produce a final product suitable for use in nuclear fuel pellet production. The process is simple and reduces the time and expense for stabilizing plutonium compounds. It requires a very low equipment expenditure and can be readily implemented into existing gloveboxes. The process is easily conducted with less associated risk than proposed alternative technologies.

  7. Production of Aromatic Plant Terpenoids in Recombinant Baker's Yeast.

    Science.gov (United States)

    Emmerstorfer-Augustin, Anita; Pichler, Harald

    2016-01-01

    Plant terpenoids are high-value compounds broadly applied as food additives or fragrances in perfumes and cosmetics. Their biotechnological production in yeast offers an attractive alternative to extraction from plants. Here, we provide two optimized protocols for the production of the plant terpenoid trans-nootkatol with recombinant S. cerevisiae by either (I) converting externally added (+)-valencene with resting cells or (II) cultivating engineered self-sufficient production strains. By synthesis of the hydrophobic compounds in self-sufficient production cells, phase transfer issues can be avoided and the highly volatile products can be enriched in and easily purified from n-dodecane, which is added to the cell broth as second phase. PMID:26843167

  8. Harnessing plant-microbe interactions for enhancing farm productivity.

    Science.gov (United States)

    Macdonald, Catriona; Singh, Brajesh

    2014-01-01

    Declining soil fertility and farm productivity is a major global concern in order to achieve food security for a burgeoning world population. It is reported that improving soil health alone can increase productivity by 10-15% and in combination with efficient plant traits, farm productivity can be increased up to 50-60%. In this article we explore the emerging microbial and bioengineering technologies, which can be employed to achieve the transformational increase in farm productivity and can simultaneously enhance environmental outcomes i.e., low green house gas (GHG) emissions. We argue that metagenomics, meta-transcriptomics and metabolomics have potential to provide fundamental knowledge on plant-microbes interactions necessary for new innovations to increase farm productivity. Further, these approaches provide tools to identify and select novel microbial/gene resources which can be harnessed in transgenic and designer plant technologies for enhanced resource use efficiencies.

  9. LITERATURE REVIEW ON THE SORPTION OF PLUTONIUM, URANIUM, NEPTUNIUM, AMERICIUM AND TECHNETIUM TO CORROSION PRODUCTS ON WASTE TANK LINERS

    Energy Technology Data Exchange (ETDEWEB)

    Li, D.; Kaplan, D.

    2012-02-29

    The Savannah River Site (SRS) has conducted performance assessment (PA) calculations to determine the risk associated with closing liquid waste tanks. The PA estimates the risk associated with a number of scenarios, making various assumptions. Throughout all of these scenarios, it is assumed that the carbon-steel tank liners holding the liquid waste do not sorb the radionuclides. Tank liners have been shown to form corrosion products, such as Fe-oxyhydroxides (Wiersma and Subramanian 2002). Many corrosion products, including Fe-oxyhydroxides, at the high pH values of tank effluent, take on a very strong negative charge. Given that many radionuclides may have net positive charges, either as free ions or complexed species, it is expected that many radionuclides will sorb to corrosion products associated with tank liners. The objective of this report was to conduct a literature review to investigate whether Pu, U, Np, Am and Tc would sorb to corrosion products on tank liners after they were filled with reducing grout (cementitious material containing slag to promote reducing conditions). The approach was to evaluate radionuclides sorption literature with iron oxyhydroxide phases, such as hematite ({alpha}-Fe{sub 2}O{sub 3}), magnetite (Fe{sub 3}O{sub 4}), goethite ({alpha}-FeOOH) and ferrihydrite (Fe{sub 2}O{sub 3} {center_dot} 0.5H{sub 2}O). The primary interest was the sorption behavior under tank closure conditions where the tanks will be filled with reducing cementitious materials. Because there were no laboratory studies conducted using site specific experimental conditions, (e.g., high pH and HLW tank aqueous and solid phase chemical conditions), it was necessary to extend the literature review to lower pH studies and noncementitious conditions. Consequently, this report relied on existing lower pH trends, existing geochemical modeling, and experimental spectroscopic evidence conducted at lower pH levels. The scope did not include evaluating the appropriateness

  10. A new chemical assay standard for plutonium

    International Nuclear Information System (INIS)

    This paper reports on a study of the structural and thermal aspects of alkali metal double sulfates of plutonium has led to a new chemical assay standard for plutonium, K4Pu(SO4)4. The compound is obtained by dehydration of the dihydrate, K4Pu(SO4)4 · 2H2O. Anhydrous K4Pu(SO4)4 was evaluated for its purity, solubility, stoichiometry, and stability for a 2-year period. Chemical analyses for plutonium and sulfate and emission spectrographic and mass spectrometric analyses for impurity elements showed that the compound is stoichiometric, with a total impurity content of less than 250 ppm. Analysis for plutonium in store samples confirmed that the product is stable to α-radiolytic and atmospheric conditions and that it decomposes only above 700 degrees C. The evaluations done on preparations of up to 100 g per batch favor its selection as a better chemical assay standard for plutonium than Pu(SO4)2·4H2O

  11. Roots, plant production and nutrient use efficiency.

    NARCIS (Netherlands)

    Willigen, de P.; Noordwijk, van M.

    1987-01-01

    The role of roots in obtaining high crop production levels as well as a high nutrient use efficiency is discussed. Mathematical models of diffusion and massflow of solutes towards roots are developed for a constant daily uptake requirement. Analytical solutions are given for simple and more complica

  12. PRODUCTION OF BIOPESTICIDES FROM WASTEWATER PLANT BIOSOLIDS

    Science.gov (United States)

    The control of different kinds of insects and pests that affect agriculture, forestry or that are disease vectors has been done extensively by the use of chemical insecticides. The use of chemical insecticides has been successful in controlling these pests but their production is...

  13. Earthworms increase plant production: a meta- analysis

    NARCIS (Netherlands)

    Groenigen, van J.W.; Lubbers, I.M.; Vos, H.M.J.; Brown, G.G.; Deyn, de G.B.; Groenigen, van K.J.

    2014-01-01

    To meet the challenge of feeding a growing world population with minimal environmental impact, we need comprehensive and quantitative knowledge of ecological factors affecting crop production. Earthworms are among the most important soil dwelling invertebrates. Their activity affects both biotic and

  14. Plant diversity surpasses plant functional groups and plant productivity as driver of soil biota in the long term.

    Directory of Open Access Journals (Sweden)

    Nico Eisenhauer

    Full Text Available BACKGROUND: One of the most significant consequences of contemporary global change is the rapid decline of biodiversity in many ecosystems. Knowledge of the consequences of biodiversity loss in terrestrial ecosystems is largely restricted to single ecosystem functions. Impacts of key plant functional groups on soil biota are considered to be more important than those of plant diversity; however, current knowledge mainly relies on short-term experiments. METHODOLOGY/PRINCIPAL FINDINGS: We studied changes in the impacts of plant diversity and presence of key functional groups on soil biota by investigating the performance of soil microorganisms and soil fauna two, four and six years after the establishment of model grasslands. The results indicate that temporal changes of plant community effects depend on the trophic affiliation of soil animals: plant diversity effects on decomposers only occurred after six years, changed little in herbivores, but occurred in predators after two years. The results suggest that plant diversity, in terms of species and functional group richness, is the most important plant community property affecting soil biota, exceeding the relevance of plant above- and belowground productivity and the presence of key plant functional groups, i.e. grasses and legumes, with the relevance of the latter decreasing in time. CONCLUSIONS/SIGNIFICANCE: Plant diversity effects on biota are not only due to the presence of key plant functional groups or plant productivity highlighting the importance of diverse and high-quality plant derived resources, and supporting the validity of the singular hypothesis for soil biota. Our results demonstrate that in the long term plant diversity essentially drives the performance of soil biota questioning the paradigm that belowground communities are not affected by plant diversity and reinforcing the importance of biodiversity for ecosystem functioning.

  15. Capabilities for managing high-volume production of electric engineering equipment at the Electrochemical Production Plant

    Energy Technology Data Exchange (ETDEWEB)

    Podlednev, V.M.

    1996-04-01

    The Electromechanical Production Plant is essentially a research center with experimental facilities and power full testing base. Major products of the plant today include heat pipes and devices of their basis of different functions and power from high temperature ranges to cryogenics. This report describes work on porous titanium and carbon-graphite current collectors, electrocatalyst synthesis, and electrocatalyst applications.

  16. Nematicide impacts on nematodes and feedbacks on plant productivity in a plant diversity gradient

    Science.gov (United States)

    Eisenhauer, Nico; Ackermann, Michael; Gass, Svenja; Klier, Matthias; Migunova, Varvara; Nitschke, Norma; Ruess, Liliane; Sabais, Alexander C. W.; Weisser, Wolfgang W.; Scheu, Stefan

    2010-09-01

    A major issue in current ecological research is the effect of biodiversity on ecosystem functioning. Although several studies reported a positive diversity - productivity relationship, the role of soil animals has been largely neglected. Nematodes are among the most widespread and important herbivores causing substantial yield losses in agriculture; however, impacts of nematodes on the diversity - productivity relationship in semi-natural plant communities have not been investigated until today. In the framework of the Jena Experiment (Thuringia, Germany) we established control and nematicide treated subplots to manipulate nematode densities on plots varying in plant species (1-16) and functional group richness (1-4). We explored the interacting effects of nematicide application and plant diversity on the main trophic groups of nematodes and on aboveground plant productivity. Nematicide application reduced the number of nematodes significantly, particularly that of plant feeders and predators. The negative impact of nematicide application on plant and bacterial feeders depended however on the diversity of the plant community. Total plant shoot biomass tended to decrease in the presence of ambient nematode densities. In detail, nematode effects varied however with plant functional group identity by reducing only the shoot biomass of herbs significantly but not that of legumes. Furthermore, the shoot biomass of grasses tended to decrease in the presence of ambient nematode densities. In contrast to total shoot biomass, nematodes decreased grass shoot biomass only in high diverse but not in low diverse plant communities. Thus, the present study for the first time highlights that nematodes likely modify the community structure und functions of semi-natural plant communities by altering the competition between plant functional groups and by attenuating the diversity - productivity relationship.

  17. Measurement of radiocaesium, radiostrontium, and plutonium in whole diets, following deposition of radioactivity in the UK originating from the Chernobyl power plant accident

    International Nuclear Information System (INIS)

    Radionuclide contamination of whole diets as a result of the Chernobyl accident has been measured following the collection of individual diets from adults and children during 1 week in June 1986. The study was conducted in three different parts of the UK, to represent rural areas of both high and low deposition of Chernobyl fallout, and an urban area where the food supply was likely to be derived from a more diverse range of sources. The overall caesium-137 plus caesium-134 concentrations in the diets was less than 5 Bq kg-1 fresh weight, and ranged from less than 0.8 Bq kg-1 to 22 Bq kg-1, the highest levels being found in diets from the high deposition area. The isotopic ratios confirmed contamination to have been predominantly of Chernobyl origin. These levels of radiocaesium would have given rise to an average committed effective dose equivalent to age 70 of less than 0.4 microSv, with a range of less than 0.05 microSv to 1.9 microSv, from intakes in the study week. The opportunity was also taken to analyse the samples for weapons fallout contamination, that is, strontium-89/strontium-90 and plutonium-239/plutonium-240. No diet contained strontium above the reporting level of 0.2 Bq kg-1 but 18% of the diets contained plutonium above the limits of detection (0.1 mBq kg-1), the highest of these being 12 mBq kg-1, found in a diet from one of the low deposition areas

  18. Fertiliser products from biogas plants; Biokaasulaitosten lopputuotteet lannoitevalmisteina

    Energy Technology Data Exchange (ETDEWEB)

    Marttinen, S.; Paavola, T.; Ervasti, S. [and others

    2013-02-01

    The use of end-products from biogas plants was studied from the perspective of plant nutrition and agriculture. The tasks included development of generally applicable methods for determining nitrogen and phosphorus in different fertiliser products in order to predict their fertiliser effect. The degradation of the products in soil was also studied. The work included both laboratory and field scale experiments. Additionally, the stability and possible phytotoxicity of the products was studied. The content of harmful contaminants and microbiological risks of the products were determined. The aim was to offer information on the characteristics and usability of the products for producers and users of the products and for supervising officials. Of the analysis methods tested, 1:60 water extraction was the best general method to describe the content of soluble, plant-available nitrogen in different organic fertiliser products. In liquid fertiliser products, nitrogen is more readily available for plants than in solid products and the fertilising effect is comparable to that of mineral fertilisers. The fertilising effect of solid organic fertiliser products is somewhat lower than that of mineral fertilisers due to surface application and mixing into the cultivation layer. This results in lower plant-availability than with mineral fertilisers which are injected into soil. Solid products contain significant amounts of total phosphorus, the solubility of which is low. As it may be solubilised over long periods of time, the 1:5 water extraction required by the current Finnish legislation of fertiliser products underestimates the usability of phosphorus. Due to the more sensitive yield response of organic fertiliser products to changes in conditions, as opposed to mineral fertilisers, it is also recommended to use an application strategy in which part of the soluble nitrogen originates from organic fertilisers and part from mineral fertilisers. Also due to legislative

  19. Biodiversity influences plant productivity through niche-efficiency.

    Science.gov (United States)

    Liang, Jingjing; Zhou, Mo; Tobin, Patrick C; McGuire, A David; Reich, Peter B

    2015-05-01

    The loss of biodiversity is threatening ecosystem productivity and services worldwide, spurring efforts to quantify its effects on the functioning of natural ecosystems. Previous research has focused on the positive role of biodiversity on resource acquisition (i.e., niche complementarity), but a lack of study on resource utilization efficiency, a link between resource and productivity, has rendered it difficult to quantify the biodiversity-ecosystem functioning relationship. Here we demonstrate that biodiversity loss reduces plant productivity, other things held constant, through theory, empirical evidence, and simulations under gradually relaxed assumptions. We developed a theoretical model named niche-efficiency to integrate niche complementarity and a heretofore-ignored mechanism of diminishing marginal productivity in quantifying the effects of biodiversity loss on plant productivity. Based on niche-efficiency, we created a relative productivity metric and a productivity impact index (PII) to assist in biological conservation and resource management. Relative productivity provides a standardized measure of the influence of biodiversity on individual productivity, and PII is a functionally based taxonomic index to assess individual species' inherent value in maintaining current ecosystem productivity. Empirical evidence from the Alaska boreal forest suggests that every 1% reduction in overall plant diversity could render an average of 0.23% decline in individual tree productivity. Out of the 283 plant species of the region, we found that large woody plants generally have greater PII values than other species. This theoretical model would facilitate the integration of biological conservation in the international campaign against several pressing global issues involving energy use, climate change, and poverty.

  20. Impact of Fission Products Impurity on the Plutonium Content of Metal- and Oxide- Fuels in Sodium Cooled Fast Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hikaru Hiruta; Gilles Youinou

    2013-09-01

    This short report presents the neutronic analysis to evaluate the impact of fission product impurity on the Pu content of Sodium-cooled Fast Reactor (SFR) metal- and oxide- fuel fabrication. The similar work has been previously done for PWR MOX fuel [1]. The analysis will be performed based on the assumption that the separation of the fission products (FP) during the reprocessing of UOX spent nuclear fuel assemblies is not perfect and that, consequently, a certain amount of FP goes into the Pu stream used to fabricate SFR fuels. Only non-gaseous FPs have been considered (see the list of 176 isotopes considered in the calculations in Appendix 1 of Reference 1). Throughout of this report, we define the mixture of Pu and FPs as PuFP. The main objective of this analysis is to quantify the increase of the Pu content of SFR fuels necessary to maintain the same average burnup at discharge independently of the amount of FP in the Pu stream, i.e. independently of the PuFP composition. The FP losses are considered element-independent, i.e., for example, 1% of FP losses mean that 1% of all non-gaseous FP leak into the Pu stream.

  1. Plutonium - radiological protection

    International Nuclear Information System (INIS)

    For the protection of persons exposed to plutonium isotopes and higher actinides there are five important requirements. First it is essential to evaluate all the appropriate data and develop basic dose standards for control of exposure of body organs, particularly bone, liver and lung; these must be comparable to standards for exposure to external gamma and X-radiation. Secondly, from these basic standards, values for maximum permissible concentrations in air and permissible annual intakes must be derived using metabolic models for plutonium in humans. As part of the biological monitoring of workers it is necessary to make assessments of the amount of plutonium in the body either by measurement of the excretion rate of plutonium in the urine or by external counting of gamma or X-radiations over the chest or contaminated wound site. For the treatment of cases of high over-exposure therapeutic techniques should be available for accelerating the excretion or removal of the radioactivity from the body. Finally, plans must be made to cover the possibility of a large release of plutonium into the environment and these should include acceptable values for ground contamination levels. (auth)

  2. Plutonium disproportionation: the ambiguity phenomenon.

    Science.gov (United States)

    Silver, G L

    2003-05-01

    Plutonium oxidation-state studies may yield ambiguous results if the parameters are not carefully chosen. The effect can be related to environmental plutonium as illustrated by an example. PMID:12735968

  3. DOE Plutonium Disposition Study: Pu consumption in ALWRs

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE's System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE's Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document, Volume 1, presents a technical description of the various elements of the System 80 + Standard Plant Design upon which the Plutonium Disposition Study was based. The System 80 + Standard Design is fully developed and directly suited to meeting the mission objectives for plutonium disposal. The bass U02 plant design is discussed here

  4. Chemical species of plutonium in Hanford radioactive tank waste

    International Nuclear Information System (INIS)

    Large quantities of radioactive wastes have been generated at the Hanford Site over its operating life. The wastes with the highest activities are stored underground in 177 large (mostly one million gallon volume) concrete tanks with steel liners. The wastes contain processing chemicals, cladding chemicals, fission products, and actinides that were neutralized to a basic pH before addition to the tanks to prevent corrosion of the steel liners. Because the mission of the Hanford Site was to provide plutonium for defense purposes, the amount of plutonium lost to the wastes was relatively small. The best estimate of the amount of plutonium lost to all the waste tanks is about 500 kg. Given uncertainties in the measurements, some estimates are as high as 1,000 kg (Roetman et al. 1994). The wastes generally consist of (1) a sludge layer generated by precipitation of dissolved metals from aqueous wastes solutions during neutralization with sodium hydroxide, (2) a salt cake layer formed by crystallization of salts after evaporation of the supernate solution, and (3) an aqueous supernate solution that exists as a separate layer or as liquid contained in cavities between sludge or salt cake particles. The identity of chemical species of plutonium in these wastes will allow a better understanding of the behavior of the plutonium during storage in tanks, retrieval of the wastes, and processing of the wastes. Plutonium chemistry in the wastes is important to criticality and environmental concerns, and in processing the wastes for final disposal. Plutonium has been found to exist mainly in the sludge layers of the tanks along with other precipitated metal hydrous oxides. This is expected due to its low solubility in basic aqueous solutions. Tank supernate solutions do not contain high concentrations of plutonium even though some tanks contain high concentrations of complexing agents. The solutions also contain significant concentrations of hydroxide which competes with other

  5. Chemical species of plutonium in Hanford radioactive tank waste

    Energy Technology Data Exchange (ETDEWEB)

    Barney, G.S.

    1997-10-22

    Large quantities of radioactive wastes have been generated at the Hanford Site over its operating life. The wastes with the highest activities are stored underground in 177 large (mostly one million gallon volume) concrete tanks with steel liners. The wastes contain processing chemicals, cladding chemicals, fission products, and actinides that were neutralized to a basic pH before addition to the tanks to prevent corrosion of the steel liners. Because the mission of the Hanford Site was to provide plutonium for defense purposes, the amount of plutonium lost to the wastes was relatively small. The best estimate of the amount of plutonium lost to all the waste tanks is about 500 kg. Given uncertainties in the measurements, some estimates are as high as 1,000 kg (Roetman et al. 1994). The wastes generally consist of (1) a sludge layer generated by precipitation of dissolved metals from aqueous wastes solutions during neutralization with sodium hydroxide, (2) a salt cake layer formed by crystallization of salts after evaporation of the supernate solution, and (3) an aqueous supernate solution that exists as a separate layer or as liquid contained in cavities between sludge or salt cake particles. The identity of chemical species of plutonium in these wastes will allow a better understanding of the behavior of the plutonium during storage in tanks, retrieval of the wastes, and processing of the wastes. Plutonium chemistry in the wastes is important to criticality and environmental concerns, and in processing the wastes for final disposal. Plutonium has been found to exist mainly in the sludge layers of the tanks along with other precipitated metal hydrous oxides. This is expected due to its low solubility in basic aqueous solutions. Tank supernate solutions do not contain high concentrations of plutonium even though some tanks contain high concentrations of complexing agents. The solutions also contain significant concentrations of hydroxide which competes with other

  6. Characterization and stability of thin oxide films on plutonium surfaces

    Science.gov (United States)

    Flores, H. G. García; Roussel, P.; Moore, D. P.; Pugmire, D. L.

    2011-02-01

    X-ray photoelectron spectroscopy (XPS) and Auger electron spectroscopy (AES) were employed to study oxide films on plutonium metal surfaces. Measurements of the relative concentrations of oxygen and plutonium, as well as the resulting oxidation states of the plutonium (Pu) species in the near-surface region are presented. The oxide product of the auto-reduction (AR) of plutonium dioxide films is evaluated and found to be an oxide species which is reduced further than what is expected. The results of this study show a much greater than anticipated extent of auto-reduction and challenge the commonly held notion of the stoichiometric stability of Pu 2O 3 thin-films. The data indicates that a sub-stoichiometric plutonium oxide (Pu 2O 3 - y ) exists at the metal-oxide interface. The level of sub-stoichiometry is shown to depend, in part, on the carbidic contamination of the metal surface.

  7. METHOD OF PRODUCING PLUTONIUM TETRAFLUORIDE

    Science.gov (United States)

    Tolley, W.B.; Smith, R.C.

    1959-12-15

    A process is presented for preparing plutonium tetrafluoride from plutonium(IV) oxalate. The oxalate is dried and decomposed at about 300 deg C to the dioxide, mixed with ammonium bifluoride, and the mixture is heated to between 50 and 150 deg C whereby ammonium plutonium fluoride is formed. The ammonium plutonium fluoride is then heated to about 300 deg C for volatilization of ammonium fluoride. Both heating steps are preferably carried out in an inert atmosphere.

  8. Plutonium contaminated materials research programme. Progress Report for 1983/84 from the Plutonium Contaminated Materials Working Party

    International Nuclear Information System (INIS)

    Plutonium contaminated material (PCM) is a generic term applied to a wide variety of materials which have become contaminated by plutonium compounds, by virtue of their use inside the primary containment of fuel cycle plants, but which generally have low beta gamma content. The report falls under the headings: introduction; organisation and role of the PCMWP; management practices; 1983/84 progress report (a) reduction of arisings; (b) plutonium measurement; (c) treatment of solid PCM; (d) treatment of alpha bearing liquid wastes; (e) actinide chemistry; (f) engineering objectives. (U.K.)

  9. Accelerator-based conversion (ABC) of reactor and weapons plutonium

    International Nuclear Information System (INIS)

    An accelerator-based conversion (ABC) system is presented that is capable of rapidly burning plutonium in a low-inventory sub-critical system. The system also returns fission power to the grid and transmutes troublesome long-lived fission products to short lived or stable products. Higher actinides are totally fissioned. The system is suited not only to controlled, rapid burning of excess weapons plutonium, but to the long range application of eliminating or drastically reducing the world total inventory of plutonium. Deployment of the system will require the successful resolution of a broad range of technical issues introduced in the paper

  10. Studies of a liquid anode for plutonium electrorefining

    International Nuclear Information System (INIS)

    They are developing a solvent anode as an alternate method for producing plutonium metal of high purity by an electrorefining process. The goals are to produce metal of 99.98% purity with an anode residue containing less than 2% of the plutonium in the feed material. If they are successful, they will design and demonstrate a system utilizing semi-continuous and remotely controlled operations. Establishing a solvent anode method should lead to improved yields and a substantial reduction in the amount of residues generated by the electrorefining process. The new method should be a viable pyrochemical technique for recovering both plutonium and uranium from spent reactor fuel. Initially, the anode consists of a tantalum rod immersed in a pool of liquid cadmium at 7400C. Impure plutonium or a solid anode residue is in contact with the cadmium. As current passes through the anode, plutonium in the cadmium is oxidized and transfers into the molten salt as tripositive plutonium. More plutonium dissolves into the cadmium and the oxidation continues. The tri-positive plutonium is carried through the salt to the cathode, where it is reduced to pure, liquid metal. This metal, which is heavier than the salt, drips from the cathode into an annulus between the anode and cathode compartments and forms a product ring

  11. Modelling energy consumption in a manufacturing plant using productivity KPIs

    Energy Technology Data Exchange (ETDEWEB)

    Gallachoir, Brian O.; Cahill, Caiman (Sustainable Energy Research Group, Dept. of Civil and Environmental Engineering, Univ. College Cork (Ireland))

    2009-07-01

    Energy efficiency initiatives in industrial plants are often focused on getting energy-consuming utilities and devices to operate more efficiently, or on conserving energy. While such device-oriented energy efficiency measures can achieve considerable savings, greater energy efficiency improvement may be achieved by improving the overall productivity and quality of manufacturing processes. The paper highlights the observed relationship between productivity and energy efficiency using aggregated data on unit consumption and production index data for Irish industry. Past studies have developed simple top-down models of final energy consumption in manufacturing plants using energy consumption and production output figures, but these models do not help identify opportunities for energy savings that could achieved through increased productivity. This paper proposes an improved and innovative method of modelling plant final energy demand that introduces standard productivity Key Performance Indicators (KPIs) into the model. The model demonstrates the relationship between energy consumption and productivity, and uses standard productivity metrics to identify the areas of manufacturing activity that offer the most potential for improved energy efficiency. The model provides a means of comparing the effect of device-oriented energy efficiency measures with the potential for improved energy efficiency through increased productivity.

  12. Hydride-catalyzed corrosion of plutonium by air: Initiation by plutonium monoxide monohydride

    International Nuclear Information System (INIS)

    Chemistry and kinetics of air reactions with plutonium monoxide monohydride (PuOH) and with mixtures of the oxide hydride and plutonium metal are defined by results of pressure-volume-temperature (PVT) measurements. Test with specimens prepared by total and partial corrosion of plutonium in 0.05 M sodium chloride solution show that reaction of residual water continues to generate H2 after liquid water is removed by evacuation. Rapid exposure of PuOH to air at room temperature does not produce a detectable reaction, but similar exposure of a partially corroded metal sample containing Pu and PuOH results in hydride (PuHx)-catalyzed corrosion of the residual Pu. Kinetics of he first-order reaction resulting in formation of the PuHx catalyst and of the indiscriminate reaction of N2 and O2 with plutonium metal are defined. The rate of the catalyzed Pu+air reaction is independent of temperature (Ea = 0), varies as the square of air pressure, and equals 0.78 ± 0.03 g Pu/cm2 min in air at one atmosphere. The absence of pyrophoric behavior for PuOH and differences in the reactivities of PuOH and PuOH + Pu mixtures are attributed to kinetic control by gaseous reaction products. Thermodynamic properties of the oxide hydride are estimated, particle size distributions of corrosion products are presented, and potential hazards associated with products formed by aqueous corrosion of plutonium are discussed

  13. Automated production of plant-based vaccines and pharmaceuticals.

    Science.gov (United States)

    Wirz, Holger; Sauer-Budge, Alexis F; Briggs, John; Sharpe, Aaron; Shu, Sudong; Sharon, Andre

    2012-12-01

    A fully automated "factory" was developed that uses tobacco plants to produce large quantities of vaccines and other therapeutic biologics within weeks. This first-of-a-kind factory takes advantage of a plant viral vector technology to produce specific proteins within the leaves of rapidly growing plant biomass. The factory's custom-designed robotic machines plant seeds, nurture the growing plants, introduce a viral vector that directs the plant to produce a target protein, and harvest the biomass once the target protein has accumulated in the plants-all in compliance with Food and Drug Administration (FDA) guidelines (e.g., current Good Manufacturing Practices). The factory was designed to be time, cost, and space efficient. The plants are grown in custom multiplant trays. Robots ride up and down a track, servicing the plants and delivering the trays from the lighted, irrigated growth modules to each processing station as needed. Using preprogrammed robots and processing equipment eliminates the need for human contact, preventing potential contamination of the process and economizing the operation. To quickly produce large quantities of protein-based medicines, we transformed a laboratory-based biological process and scaled it into an industrial process. This enables quick, safe, and cost-effective vaccine production that would be required in case of a pandemic.

  14. Biomass Yield of Different Plants for Biogass Production

    OpenAIRE

    Balodis, Oskars; Bartuševics, Jānis; Gaile, Zinta

    2015-01-01

    In order to investigate yield potential of plants probably suitable for biogas production preliminary field trials were carried out at Research and Study farm “Vecauce” in 2010 using eight annual plant species: maize, winter oil-seed rape, oil radish, sunflower, foxtail millet, millet, hemp and amaranth. All species (except oil radish) were represented with several varieties, and some species were harvested at 2-3 development stages. Obtained fresh biomass yield was from 33.05 (millet „Rudes‟...

  15. Using Plant Functional Traits to Explain Diversity–Productivity Relationships

    OpenAIRE

    Christiane Roscher; Jens Schumacher; Marlén Gubsch; Annett Lipowsky; Alexandra Weigelt; Nina Buchmann; Bernhard Schmid; Ernst-Detlef Schulze

    2012-01-01

    BACKGROUND: The different hypotheses proposed to explain positive species richness-productivity relationships, i.e. selection effect and complementarity effect, imply that plant functional characteristics are at the core of a mechanistic understanding of biodiversity effects. METHODOLOGY/PRINCIPAL FINDINGS: We used two community-wide measures of plant functional composition, (1) community-weighted means of trait values (CWM) and (2) functional trait diversity based on Rao's quadratic diversit...

  16. Foreign investment and international plant configuration: whither the product cycle?

    OpenAIRE

    Belderbos, R; Sleuwaegen, Leo

    2001-01-01

    We analyze the determinants of the decision to invest abroad in particular configurations of overseas plants for 120 Japanese firms active in 36 well-defined electronic product markets. We find support for a structured internationalization decision model in which the decision to produce abroad and the choice for a specific international plant configuration are treated as nested strategic options. Drivers at the industry and firm level push firms to consider overseas investment, and locational...

  17. Present possibilities of protein concentrates production from plant sources

    OpenAIRE

    KRISTINOVÁ, Helena

    2011-01-01

    The aim of the bachelor thesis was gather information about present possibilities of proteins concentrates production from plant sources. I focused on dried pea (Pisum sativum L.), soybean (Glycine soja) and potato tuber (Solanum tuberosum L.). The protein concentrates from leguminous plants are produced by three basic processes, i.e. acid leasing (at ~pH 4.5), extracting with aqueous alcohol (60 - 90%), and denaturing the protein with moist heat before extraction with water. Pea protein is p...

  18. Applications of curium measurements for safeguarding at large-scale reprocessing plants

    International Nuclear Information System (INIS)

    Safeguarding the plutonium passing through a large-scale reprocessing plant (such as one with 800 t of uranium per year) involves nondestructive assay measurements for plutonium at key points. The gamma-ray and neutron signals from the plutonium are generally hidden by the much larger backgrounds from fission products and actinides, so indirect measurements are routinely used. The intense neutron emission rate from spent fuel is from curium. In a spent fuel assembly at the head-end of a plant, the curium neutrons are used to deduce the amount of plutonium present. Coincidence and multiplicity counting are alternative ways to measure neutrons from spent fuel; they have advantages over total neutron counting in certain conditions and offer new opportunities for examining assemblies. New uses for measurements of curium's neutrons are proposed to safeguard waste streams. From a year's work at a large-scale plant, 4 to 7 kg of plutonium can remain in leached hulls and 4 to 22 kg of plutonium can remain in the vitrified high-level liquid waste. While the plutonium in these wastes has the safeguards advantage of being dilute, it is important to verify (a) that the many kilograms involved are in fact present and (b) that the declared masses are not higher than the actual amounts so that more concentrated plutonium cannot pass through the plant by masquerading as waste. Curium measurements on spent fuel assemblies, the accountability tank, and leached hulls would form a safeguards system around all the inputs and outputs of a plant's head-end where the plutonium is always intimately mixed with the curium. A neutron measurement of the vitrified waste would help identify the presence of a diversion path upstream because essentially all of the curium measured in the spent fuel assemblies should also be found in the vitrified waste (on a batch basis). 7 refs., 4 figs

  19. Performance optimization of the Växtkraft biogas production plant

    International Nuclear Information System (INIS)

    Highlights: ► Pre-treatment of ley crop can increase the biogas plant performance. ► Membrane filtration can increase the capacity of the biogas plant. ► Mechanical pre-treatment of the ley crop shows the highest energy efficiency. ► Using a distributor to spread the residues as fertilizer show promising results. -- Abstract: All over the world there is a strong interest and also potential for biogas production from organic residues as well as from different crops. However, to be commercially competitive with other types of fuels, efficiency improvements of the biogas production process are needed. In this paper, results of improvements studies done on a full scale co-digestion plant are presented. In the plant organic wastes from households and restaurants are mixed and digested with crops from pasture land. The areas for improvement of the plant addressed in this paper are treatment of the feed material to enhance the digestion rate, limitation of the ballast of organics in the water stream recirculated in the process, and use of the biogas plant residues at farms. Results from previous studies on pre-treatment and membrane filtration of recirculated process water are combined for an estimation of the total improvement potential. Further, the possibility of using neural networks to predict biogas production using historical data from the full-scale biogas plant was investigated. Results from an investigation using the process residues as fertilizer are also presented. The results indicate a potential to increase the biogas yield from the process with up to over 30% with pre-treatment of the feed and including membrane filtration in the process. Neural networks have the potential to be used for prediction of biogas production. Further, it is shown that the residues from biogas production can be used as fertilizers but that the emission of N2O from the fertilized soil is dependent on the soil type and spreading technology.

  20. Plant extracts as natural antioxidants in meat and meat products.

    Science.gov (United States)

    Shah, Manzoor Ahmad; Bosco, Sowriappan John Don; Mir, Shabir Ahmad

    2014-09-01

    Antioxidants are used to minimize the oxidative changes in meat and meat products. Oxidative changes may have negative effects on the quality of meat and meat products, causing changes in their sensory and nutritional properties. Although synthetic antioxidants have already been used but in recent years, the demand for natural antioxidants has been increased mainly because of adverse effects of synthetic antioxidants. Thus most of the recent investigations have been directed towards the identification of natural antioxidants from various plant sources. Plant extracts have been prepared using different solvents and extraction methods. Grape seed, green tea, pine bark, rosemary, pomegranate, nettle and cinnamon have exhibited similar or better antioxidant properties compared to some synthetic ones. This review provides the recent information on plant extracts used as natural antioxidants in meat and meat products, specifically red meat. PMID:24824531

  1. Control of Listeria monocytogenes in food production plants

    Directory of Open Access Journals (Sweden)

    Dimitrijević Mirjana

    2008-01-01

    Full Text Available L. monocytogenes has been established in different plants for the production of food, including dairy plants, abattoirs, plants for the processing of fish, as well as those for the production of ready-to-eat (RTE food and this fact is being considered as the primary mechanism of food contamination with this bacteria. There is also the factor of numerous and diverse contaminated production equipment, because it has certain parts that are inaccessible for the necessary cleaning and disinfection. The temperature, position, as well as the material of the work surface are also linked to the contamination of plants with this bacteria. Investigations carried out so far have helped toward the better understanding of the manner and time of contamination of food items in the course of the production process, but there are still unresolved problems, including most certainly the biggest one - the adherence of bacteria and the creation of a biofilm, when the bacteria is in that condition more resistant to so-called stress factors which are usually used in the food industry for the purpose of decontamination of the surfaces with which foods come into contact. The control of L. monocytogenes in food production plants is possible primarily by using an integrated programme, compatible with the systems Hazard Analysis Critical Control Point (HACCP and Good Hygiene Practice (GHP, necessary in the production of food that is safe for the consumer. Essentially, the control measures that can contribute to reducing the incidence of findings of L.monocytogenes in the finished product, as well as the reducing of the level of contamination with this bacteria are linked, on the one hand, with hygiene procedures in the production process, and, on the other, with the applied technological procedures.

  2. Production of biopharmaceutical compounds in plants: Potential and applications

    International Nuclear Information System (INIS)

    Full text: Plants are gaining widespread acceptance as a suitable system for the large-scale production of recombinant proteins. As molecular farming has come of age, there have been technological developments on many levels, including transfection methods, control of gene expression, protein targeting, the use of different crops as production platforms, and modifications to alter the structural and functional properties of the recombinant product. The skepticism that received this technology when first envisaged has turned into a cautious optimism. A wide variety of proteins can be produced in plants and they are almost indistinguishable from their native counterparts. Over the last few years, there has been a continuing commercial development of novel plant-based expression platforms accompanied by success in tackling some of the limitations of plants as bioreactors, such as low yields and inconsistent product quality that have limited the approval of plant-derived pharmaceuticals. Indeed, one of the most important driving factors has been yield improvement, as product yield has a significant impact on economic feasibility. Strategies to improve the recombinant protein yield in plants include the development of novel promoters, the improvement of protein stability and accumulation, and the improvement of downstream processing technologies. Attention is now shifting from basic research towards commercial exploitation, and molecular farming is reaching the stage at which it may challenge established production technologies based on bacteria, yeast, and cultured mammalian cells. There are already several plant-produced proteins on the market including one at a large scale. Several plant-derived recombinant pharmaceutical proteins are reaching the final stages of clinical evaluation, and more are in the development pipeline. The low cost of plant-based vaccines make them ideal for large-scale programs in poor countries. It is hoped that the issue of IP does not

  3. Root traits contributing to plant productivity under drought

    Directory of Open Access Journals (Sweden)

    Louise eComas

    2013-11-01

    Full Text Available Geneticists and breeders are positioned to breed plants with root traits that improve productivity under drought. However, a better understanding of root functional traits and how traits are related to whole plant strategies to increase crop productivity under different drought conditions is needed. Root traits associated with maintaining plant productivity under drought include small fine root diameters, long specific root length (SRL, and considerable root length density, especially at depths in soil with available water. In environments with late season water deficits, small xylem diameters in targeted seminal roots save soil water deep in the soil profile for use during crop maturation and result in improved yields. Capacity for deep root growth and large xylem diameters in deep roots may also improve root acquisition of water when ample water at depth is available. Xylem pit anatomy that makes xylem less ‘leaky’ and prone to cavitation warrants further exploration holding promise that such traits may improve plant productivity in water-limited environments without negatively impacting yield under adequate water conditions. Rapid resumption of root growth following soil rewetting may improve plant productivity under episodic drought. Genetic control of many of these traits through breeding appears feasible. Several recent reviews have covered methods for screening root traits but an appreciation for the complexity of root systems (e.g. functional differences between fine and coarse roots needs to be paired with these methods to successfully identify relevant traits for crop improvement. Screening of root traits at early stages in plant development can proxy traits at mature stages but verification is needed on a case by case basis that traits are linked to increased crop productivity under drought. Examples in lesquerella (Physaria and rice (Oryza show approaches to phenotyping of root traits and current understanding of root trait

  4. Root traits contributing to plant productivity under drought.

    Science.gov (United States)

    Comas, Louise H; Becker, Steven R; Cruz, Von Mark V; Byrne, Patrick F; Dierig, David A

    2013-11-05

    Geneticists and breeders are positioned to breed plants with root traits that improve productivity under drought. However, a better understanding of root functional traits and how traits are related to whole plant strategies to increase crop productivity under different drought conditions is needed. Root traits associated with maintaining plant productivity under drought include small fine root diameters, long specific root length, and considerable root length density, especially at depths in soil with available water. In environments with late season water deficits, small xylem diameters in targeted seminal roots save soil water deep in the soil profile for use during crop maturation and result in improved yields. Capacity for deep root growth and large xylem diameters in deep roots may also improve root acquisition of water when ample water at depth is available. Xylem pit anatomy that makes xylem less "leaky" and prone to cavitation warrants further exploration holding promise that such traits may improve plant productivity in water-limited environments without negatively impacting yield under adequate water conditions. Rapid resumption of root growth following soil rewetting may improve plant productivity under episodic drought. Genetic control of many of these traits through breeding appears feasible. Several recent reviews have covered methods for screening root traits but an appreciation for the complexity of root systems (e.g., functional differences between fine and coarse roots) needs to be paired with these methods to successfully identify relevant traits for crop improvement. Screening of root traits at early stages in plant development can proxy traits at mature stages but verification is needed on a case by case basis that traits are linked to increased crop productivity under drought. Examples in lesquerella (Physaria) and rice (Oryza) show approaches to phenotyping of root traits and current understanding of root trait genetics for breeding.

  5. Existing large steam power plant upgraded for hydrogen production

    Energy Technology Data Exchange (ETDEWEB)

    Galanti, L.; Franzoni, A.; Traverso, A.; Massardo, A.F. [University of Genoa, Genoa (Italy)

    2011-05-15

    This paper presents and discusses the results of a complete thermoeconomic analysis of an integrated power plant for co-production of electricity and hydrogen via pyrolysis and gasification processes fed by various coals and mixture of coal and biomass, applied to an existing large steam power plant (ENEL Brindisi power plant - 660 MWe). Two different technologies for the syngas production section are considered: pyrolysis process and direct pressurized gasification. Moreover, the proximity of a hydrogen production and purification plants to an existing steam power plant favors the inter-exchange of energy streams, mainly in the form of hot water and steam, which reduces the costs of auxiliary equipment. The high quality of the hydrogen would guarantee its usability for distributed generation and for public transport. The results were obtained using WTEMP thermoeconomic software, developed by the Thermochemical Power Group of the University of Genoa, and this project has been carried out within the framework of the FISR National project 'Integrated systems for hydrogen production and utilization in distributed power generation'.

  6. Development of advanced controlled-potential coulometry system for accountability analysis of plutonium in reprocessing facility

    Energy Technology Data Exchange (ETDEWEB)

    Kuno, Takehiko; Sato, Soichi; Ikeda, Hisashi [Techinical Service Division, Tokai Reprocessing Center, Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan). Tokai Works; Holland, Micheal K.; Cordaro, Joseph V. [Westinghouse Savannah River Co., Aiken, SC (United States)

    2000-12-01

    A controlled-potential coulometry system (CPC) has been developed to analyze the accountability of plutonium products at the Tokai Reprocessing Plant (TRP). There has been demand to standardize CPC as highly accurate analysis method because, since 1995, the International organization for Standards (ISO) has been advocating ISO12183. To increase TRP's CPC system efficiency, a high performance potentiostat and a high performance coulometer (the principal measuring instruments used in the CPC system) were designed and constructed in collaboration with Westinghouse Savannah River Company (WSRC). Also, the optimization of the procedure was examined. As a results of these efforts, the latest CPC system (complying with ISO12183) has demonstrated long-term measurement reliability of up to 0.1% for 20 mg of plutonium. (author)

  7. Plant-based fertilizers for organic vegetable production

    DEFF Research Database (Denmark)

    Sørensen, Jørn Nygaard; Thorup-Kristensen, Kristian

    2011-01-01

    fertility, the term “mobile green manures” is used for green-manure crops that are harvested in one field and then moved as a whole and used as fertilizer in other fields. To further investigate mobile-green-manure crops for use as efficient fertilizers, pot and field experiments were conducted......To ensure high yield and quality in organic vegetable production, crops often require additional fertilizer applied during the season. Due to the risk of contamination of edible plant products from slurry, plant-based fertilizers may be used as an alternative. The purpose of our work was to develop...

  8. Graphical analysis of French nuclear power plant production date

    Energy Technology Data Exchange (ETDEWEB)

    Jourdan, J.P. [Electricite de France (EDF), Projet Production EPR 1, 93 - Saint-Denis (France)

    2001-07-01

    The analysis of values of plant production uses here an original method of graphical analysis. This method clarifies various difficulties of analysing big experience feedback databases among which the language interpretation and distinctions between scarce events and multi-annual events. In general, the method shows the logical processes that production values obey (pure chance logic, administrative logic, and willpower) This method of graphical analysis provides a tool to observe and question in a concrete way so that each person involved can put the events in which he played a role into the general context of other plants. It is a deductible method to improve this big and complex system. (author)

  9. Dry sample storage system for an analytical laboratory supporting plutonium processing

    Energy Technology Data Exchange (ETDEWEB)

    Treibs, H.A.; Hartenstein, S.D.; Griebenow, B.L.; Wade, M.A.

    1990-07-25

    The Special Isotope Separation (SIS) plant is designed to provide removal of undesirable isotopes in fuel grade plutonium by the atomic vapor laser isotope separation (AVLIS) process. The AVLIS process involves evaporation of plutonium metal, and passage of an intense beam of light from a laser through the plutonium vapor. The laser beam consists of several discrete wavelengths, tuned to the precise wavelength required to ionize the undesired isotopes. These ions are attracted to charged plates, leaving the bulk of the plutonium vapor enriched in the desired isotopes to be collected on a cold plate. Major portions of the process consist of pyrochemical processes, including direct reduction of the plutonium oxide feed material with calcium metal, and aqueous processes for purification of plutonium in residues. The analytical laboratory for the plant is called the Material and Process Control Laboratory (MPCL), and provides for the analysis of solid and liquid process samples.

  10. Dry sample storage system for an analytical laboratory supporting plutonium processing

    International Nuclear Information System (INIS)

    The Special Isotope Separation (SIS) plant is designed to provide removal of undesirable isotopes in fuel grade plutonium by the atomic vapor laser isotope separation (AVLIS) process. The AVLIS process involves evaporation of plutonium metal, and passage of an intense beam of light from a laser through the plutonium vapor. The laser beam consists of several discrete wavelengths, tuned to the precise wavelength required to ionize the undesired isotopes. These ions are attracted to charged plates, leaving the bulk of the plutonium vapor enriched in the desired isotopes to be collected on a cold plate. Major portions of the process consist of pyrochemical processes, including direct reduction of the plutonium oxide feed material with calcium metal, and aqueous processes for purification of plutonium in residues. The analytical laboratory for the plant is called the Material and Process Control Laboratory (MPCL), and provides for the analysis of solid and liquid process samples

  11. The disposition of weapons plutonium in MOX fuel

    International Nuclear Information System (INIS)

    During the years 1994 and 1995, increasing interest has been shown worldwide in the management and disposition of excess weapons plutonium. Several basic solutions have been proposed and the U.S. Government has initiated preparation of a Programmatic Environmental Impact Statement (PEIS) on plutonium disposition options. This presentation addresses aspects of the primary alternative that is favored by the National Academy of Sciences and by the ANS Blue Ribbon panel's report on plutonium disposition options, the use of plutonium from weapons in mixed uranium/plutonium oxide (MOX) fuel to generate electricity in presently operating Light Water Reactors (LWRs). The advantages of such an option are two-fold. First, an analogous large-scale industrial activity exists nowadays: civilian plutonium, separated in reprocessing plants, is steadily recycled in existing PWR and BWR European reactors. This gives the opportunity, if decided, to go ahead almost immediately with an effective disposition of military plutonium. On the other hand, several benefits can be withdrawn from this strategy, such as economic soundness, resource and energy conservation, environment credibility and proliferation resistance

  12. Recycling of plutonium and uranium in water reactor fuels

    International Nuclear Information System (INIS)

    The purpose of the meeting was to make a review of the present knowledge relevant to plutonium and uranium recycling, MOX fuel, on-going programmes, today's industrial capabilities and future plans for development. For countries with commitments to reprocessing, MOX fuel is attractive and will be more so as discharge burnups increase and as the time between discharge and reprocessing optimized. Fabrication experience on MOX fuel has accumulated for many years in several countries and one has been able to cope with the extension of capacities of the plants, as required by MOX fuel implementation, and with the requirements specific to massive use in power reactors. Standards fabrication processes have proven to be adaptable in large quantities and have yielded products satisfying all present specifications. A large body of irradiation experience for some time on various MOX and RepU materials. On the basis of a comparison with UO2, no adverse effect has been observed. Problems like isotopic homogeneity, solubility, alternative processes like gelation deserve further attention. It is encouraging to note that parameters linked to materials obtained by different fabrication routes can be taken into account by existing codes, to an extent similar to various UO2 fuels, provided an adequate data base is available. The fabrication capacities are the limiting factor for MOX penetration in reactors, where a 30 to 50% recycling rate is therefore sufficient. The use of plutonium in 100% MOX reactors or in more advanced reactors deserves more study. The increase of plutonium inventory may influence safety and licensing analysis, but all the safety criteria can be met. On the whole, the experience reported in this meeting pointed to a general consensus of the attractiveness of recycling and the already demonstrated ability of several countries to cope with all questions raised by MOX substitution of UO2 fuel. Refs, figs and tabs

  13. Ethylene production throughout growth and development of plants

    Science.gov (United States)

    Wheeler, Raymond M.; Peterson, Barbara V.; Stutte, Gary W.

    2004-01-01

    Ethylene production by 10 or 20 m2 stands of wheat, soybean, lettuce, potato, and tomato was monitored throughout growth and development in an atmospherically closed plant chamber. Chamber ethylene levels varied among species and rose during periods of canopy expansion and rapid growth for all species. Following this, ethylene levels either declined during seed fill and maturation for wheat and soybean, or remained relatively constant for potato and tomato (during flowering and early fruit development). Lettuce plants were harvested during rapid growth and peak ethylene production. Chamber ethylene levels increased rapidly during tomato ripening, reaching concentrations about 10 times that measured during vegetative growth. The highest ethylene production rates during vegetative growth ranged from 1.6 to 2.5 nmol m-2 d-1 during rapid growth of lettuce and wheat stands, or about 0.3 to 0.5 nmol g-1 fresh weight per hour. Estimates of stand ethylene production during tomato ripening showed that rates reached 43 nmol m-2 d-1 in one study and 93 nmol m-2 d-1 in a second study with higher lighting, or about 50x that of the rate during vegetative growth of tomato. In a related test with potato, the photoperiod was extended from 12 to 24 hours (continuous light) at 58 days after planting (to increase tuber yield), but this change in the environment caused a sharp increase in ethylene production from the basal rate of 0.4 to 6.2 nmol m-2 d-1. Following this, the photoperiod was changed back to 12 h at 61 days and ethylene levels decreased. The results suggest three separate categories of ethylene production were observed with whole stands of plants: 1) production during rapid vegetative growth, 2) production during climacteric fruit ripening, and 3) production from environmental stress.

  14. 9 CFR 590.24 - Egg products plants requiring continuous inspection.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Egg products plants requiring..., DEPARTMENT OF AGRICULTURE EGG PRODUCTS INSPECTION INSPECTION OF EGGS AND EGG PRODUCTS (EGG PRODUCTS INSPECTION ACT) Scope of Inspection § 590.24 Egg products plants requiring continuous inspection. No plant...

  15. Catalyzed electrolytic plutonium oxide dissolution

    International Nuclear Information System (INIS)

    Catalyzed electrolytic plutonium oxide dissolution (CEPOD) was first demonstrated at Pacific Northwest Laboratory (PNL) in early 1974 in work funded by the Exxon Corporation. The work, aimed at dissolution of Pu-containing residues remaining after the dissolution of spent mixed-oxide reactor fuels, was first publicly disclosed in 1981. The process dissolves PuO2 in an anolyte containing small (catalytic) amounts of elements that form kinetically fast, strongly oxidizing ions. These are continuously regenerated at the anode. Catalysts used, in their oxidized form, include Ag2+, Ce4+, Co3+, and AmO22+. This paper reviews the chemistry involved in CEPOD and the results of its application to the dissolution of the Pu content of a variety of PuO2-containing materials such as off-standard oxide, fuels dissolution residues, incinerator ash, contaminated soils, and other scraps or wastes. Results are presented for both laboratory-scale and plant-scale dissolves

  16. Electrochemically Modulated Separation for Plutonium Safeguards

    Energy Technology Data Exchange (ETDEWEB)

    Pratt, Sandra H.; Breshears, Andrew T.; Arrigo, Leah M.; Schwantes, Jon M.; Duckworth, Douglas C.

    2013-12-31

    Accurate and timely analysis of plutonium in spent nuclear fuel is critical in nuclear safeguards for detection of both protracted and rapid plutonium diversions. Gamma spectroscopy is a viable method for accurate and timely measurements of plutonium provided that the plutonium is well separated from the interfering fission and activation products present in spent nuclear fuel. Electrochemically modulated separation (EMS) is a method that has been used successfully to isolate picogram amounts of Pu from nitric acid matrices. With EMS, Pu adsorption may be turned "on" and "off" depending on the applied voltage, allowing for collection and stripping of Pu without the addition of chemical reagents. In this work, we have scaled up the EMS process to isolate microgram quantities of Pu from matrices encountered in spent nuclear fuel during reprocessing. Several challenges have been addressed including surface area limitations, radiolysis effects, electrochemical cell performance stability, and chemical interferences. After these challenges were resolved, 6 µg Pu was deposited in the electrochemical cell with approximately an 800-fold reduction of fission and activation product levels from a spent nuclear fuel sample. Modeling showed that these levels of Pu collection and interference reduction may not be sufficient for Pu detection by gamma spectroscopy. The main remaining challenges are to achieve a more complete Pu isolation and to deposit larger quantities of Pu for successful gamma analysis of Pu. If gamma analyses of Pu are successful, EMS will allow for accurate and timely on-site analysis for enhanced Pu safeguards.

  17. Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP - Project W-460

    CERN Document Server

    Weiss, E V

    2000-01-01

    This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP.

  18. Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP Project W-460

    Energy Technology Data Exchange (ETDEWEB)

    WEISS, E.V.

    2000-03-06

    This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP.

  19. Instrumentation for studying binder burnout in an immobilized plutonium ceramic wasteform

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, M; Pugh, D; Herman, C

    2000-04-21

    The Plutonium Immobilization Program produces a ceramic wasteform that utilizes organic binders. Several techniques and instruments were developed to study binder burnout on full size ceramic samples in a production environment. This approach provides a method for developing process parameters on production scale to optimize throughput, product quality, offgas behavior, and plant emissions. These instruments allow for offgas analysis, large-scale TGA, product quality observation, and thermal modeling. Using these tools, results from lab-scale techniques such as laser dilametry studies and traditional TGA/DTA analysis can be integrated. Often, the sintering step of a ceramification process is the limiting process step that controls the production throughput. Therefore, optimization of sintering behavior is important for overall process success. Furthermore, the capabilities of this instrumentation allows better understanding of plant emissions of key gases: volatile organic compounds (VOCs), volatile inorganics including some halide compounds, NO{sub x}, SO{sub x}, carbon dioxide, and carbon monoxide.

  20. Cameroonian medicinal plants: Pharmacology and derived natural products

    Directory of Open Access Journals (Sweden)

    Thomas Efferth

    2010-10-01

    Full Text Available Many developing countries including Cameroon have mortality patterns that reflect high levels of infectious diseases and the risk of death during pregnancy and childbirth, in addition to cancers, cardiovascular diseases and chronic respiratory diseases that account for most deaths in the developed world. Several medicinal plants are used traditionally for their treatment. In this review, plants used in Cameroonian traditional medicine with evidence for the activities of their crude extracts and/or derived products have been discussed. A considerable number of plant extracts and isolated compounds possess significant antimicrobial, antiparasitic including anti-malarial, anti-proliferative, anti-inflammatory, anti-diabetes, and antioxidant effects. Most of the biologically active compounds belong to terpenoids, phenolics and alkaloids. Terpenoids from Cameroonian plants showed best activities as anti-parasitic, but rather poor antimicrobial effects. The best antimicrobial, anti-proliferative and antioxidant compounds were phenolics. In conclusion, many medicinal plants traditionally used in Cameroon to treat various ailments displayed good activities in vitro. This explains the endeavor of Cameroonian research institutes in drug discovery from indigenous medicinal plants. However, much work is still to be done to standardize methodologies and to study the mechanisms of action of isolated natural products.

  1. Plant traits mediate consumer and nutrient control on plant community productivity and diversity.

    Science.gov (United States)

    Eskelinen, Anu; Harrison, Susan; Tuomi, Maria

    2012-12-01

    The interactive effects of consumers and nutrients on terrestrial plant communities, and the role of plant functional traits in mediating these responses, are poorly known. We carried out a six-year full-factorial field experiment using mammalian herbivore exclusion and fertilization in two habitat types (fertile and infertile alpine tundra heaths) that differed in plant functional traits related to resource acquisition and palatability. Infertile habitats were dominated by species with traits indicative of a slow-growing strategy: high C:N ratio, low specific leaf area, and high condensed tannins. We found that herbivory counteracted the effect of fertilization on biomass, and that this response differed between the two habitats and was correlated with plant functional traits. Live biomass dominated the treatment responses in infertile habitats, whereas litter accumulation dominated the treatment responses in fertile habitats and was strongly negatively associated with resident community tannin concentration. Species richness declined under herbivore exclusion and fertilization in fertile habitats, where litter accumulation was greatest. Community means of plant C:N ratio predicted treatment effects on diversity: fertilization decreased and herbivory increased dominance in communities originally dominated by plants with high C:N, while fertilization increased and herbivory diminished dominance in communities where low C:N species were abundant. Our results highlight the close interdependence between consumer effects, soil nutrients, and plant functional traits and suggest that plant traits may provide an improved understanding of how consumers and nutrients influence plant community productivity and diversity.

  2. Estimated discard limits for plutonium-238 recovery processing in the plutonium processing building

    Energy Technology Data Exchange (ETDEWEB)

    Luthy, D.F.; Bond, W.H.

    1975-03-26

    This manual is intended as a basis for plutonium-238 recovery costs and as a guide for removal of plutonium-bearing wastes from the gloveboxes to be safely and economically discarded. Waste materials contaminated with plutonium-238 are generated from in-house production, analytical, process development, recovery and receipts from off-site. The contaminated materials include paper, rags, alpha-box gloves, piping, valves, filters, etc. General categories for all types of plutonium waste have been established by the ERDA and are reflected in this manual. There are numerous processes used in plutonium recovery, such as dissolution, ultrasonic cleaning, ion exchange, etc. One or more of these processes are needed to extract the plutonium-238 from waste materials, purify it and convert it to an oxide acceptable for reuse. This manual is presented in two parts: Part I gives a breakdown and brief explanation of the direct costs for plutonium-238 I recovery, derived from budget data. Direct costs include direct labor (operating personnel), operational materials and supplies, health physics direct labor, calorimetry labor, analytical labor, and engineering direct labor (total costs for Method I). Budgeted costs for labor and material were used in the derivation of discard limits. The data presented is then used to calculate the cost per hour for recovery, as it applies to the three different methods of calculating discard limits referred to, in this manual, as Method I (calculation stated above), Method II and Method III. The cost for Method II is derived by adding to the cost of Method I, payroll related expenses. Method III is then calculated by adding over-head expenses to the total cost of Method II.

  3. Nuclear driven water decomposition plant for hydrogen production

    Science.gov (United States)

    Parker, G. H.; Brecher, L. E.; Farbman, G. H.

    1976-01-01

    The conceptual design of a hydrogen production plant using a very-high-temperature nuclear reactor (VHTR) to energize a hybrid electrolytic-thermochemical system for water decomposition has been prepared. A graphite-moderated helium-cooled VHTR is used to produce 1850 F gas for electric power generation and 1600 F process heat for the water-decomposition process which uses sulfur compounds and promises performance superior to normal water electrolysis or other published thermochemical processes. The combined cycle operates at an overall thermal efficiency in excess of 45%, and the overall economics of hydrogen production by this plant have been evaluated predicated on a consistent set of economic ground rules. The conceptual design and evaluation efforts have indicated that development of this type of nuclear-driven water-decomposition plant will permit large-scale economic generation of hydrogen in the 1990s.

  4. Picture card tool for holistic planning in organic plant production

    OpenAIRE

    Fog, Erik; Jørgen E. Olesen; Noe, Egon; Sørensen, Peter; Melander, Bo

    2013-01-01

    Presentation of a new tool for strategic farm planning and improving farm management. The tool is based on picture cards and is meant as an important help for the advisory service for organic farmers. The tool can help the farm manager to raise the yields and the economic performance in organic plant production.

  5. Advanced fuels for plutonium management in pressurized water reactors

    International Nuclear Information System (INIS)

    Several fuel concepts are under investigation at CEA with the aim of manage plutonium inventories in pressurized water reactors. This options range from the use of mature technologies like MOX adapted in the case of MOX-EUS (enriched uranium support) and COmbustible Recyclage A ILot (CORAIL) assemblies to more innovative technologies using IMF like DUPLEX and advanced plutonium assembly (APA). The plutonium burning performances reported to the electrical production go from 7 to 60 kg (TW h)-1. More detailed analysis covering economic, sustainability, reliability and safety aspects and their integration in the whole fuel cycle would allow identifying the best candidate

  6. Plutonium in the environment - bibliographic study and quantification

    International Nuclear Information System (INIS)

    This document deals with the different isotopes of plutonium. It intends to summarize the main features of plutonium behaviour from sources inside installation to the environment and man, and is expected to report the current knowledge about the different parameters used in the models for environmental and radiological impact assessment. The objective is to gather scientific information useful for deciders in case of accident or for regulation purposes. It gives main information on radiological and chemical characteristics which are necessary to understand transfers between compartments. Then it reports information on normal and accidental historical sources and present releases. The next part deals with transfer parameters in the installations and in environment. Parameters that influence its behaviour are examined, inside installations (physico-chemical forms and events that lead to releases), and outside in the environment for deposition to soils and transfer to plants, and animal products. A full chapter is dedicated to presentation of typical assessments, for each isotope and for mixture, and correspondence between activity, mass and dose reference levels are presented and discussed. Transfer and behaviour in man and effects on health are finally presented. (author)

  7. Dominant plant taxa predict plant productivity responses to CO2 enrichment across precipitation and soil gradients

    Science.gov (United States)

    Fay, Philip A.; Newingham, Beth A.; Polley, H. Wayne; Morgan, Jack A.; LeCain, Daniel R.; Nowak, Robert S.; Smith, Stanley D.

    2015-01-01

    The Earth's atmosphere will continue to be enriched with carbon dioxide (CO2) over the coming century. Carbon dioxide enrichment often reduces leaf transpiration, which in water-limited ecosystems may increase soil water content, change species abundances and increase the productivity of plant communities. The effect of increased soil water on community productivity and community change may be greater in ecosystems with lower precipitation, or on coarser-textured soils, but responses are likely absent in deserts. We tested correlations among yearly increases in soil water content, community change and community plant productivity responses to CO2 enrichment in experiments in a mesic grassland with fine- to coarse-textured soils, a semi-arid grassland and a xeric shrubland. We found no correlation between CO2-caused changes in soil water content and changes in biomass of dominant plant taxa or total community aboveground biomass in either grassland type or on any soil in the mesic grassland (P > 0.60). Instead, increases in dominant taxa biomass explained up to 85 % of the increases in total community biomass under CO2 enrichment. The effect of community change on community productivity was stronger in the semi-arid grassland than in the mesic grassland, where community biomass change on one soil was not correlated with the change in either the soil water content or the dominant taxa. No sustained increases in soil water content or community productivity and no change in dominant plant taxa occurred in the xeric shrubland. Thus, community change was a crucial driver of community productivity responses to CO2 enrichment in the grasslands, but effects of soil water change on productivity were not evident in yearly responses to CO2 enrichment. Future research is necessary to isolate and clarify the mechanisms controlling the temporal and spatial variations in the linkages among soil water, community change and plant productivity responses to CO2 enrichment. PMID

  8. High-Temperature Oxidation of Plutonium Surrogate Metals and Alloys

    Energy Technology Data Exchange (ETDEWEB)

    Sparks, Joshua C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Krantz, Kelsie E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Christian, Jonathan H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Washington, II, Aaron L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-07-27

    The Plutonium Management and Disposition Agreement (PMDA) is a nuclear non-proliferation agreement designed to remove 34 tons of weapons-grade plutonium from Russia and the United States. While several removal options have been proposed since the agreement was first signed in 2000, processing the weapons-grade plutonium to mixed-oxide (MOX) fuel has remained the leading candidate for achieving the goals of the PMDA. However, the MOX program has received its share of criticisms, which causes its future to be uncertain. One alternative pathway for plutonium disposition would involve oxidizing the metal followed by impurity down blending and burial in the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico.

  9. High-Temperature Oxidation of Plutonium Surrogate Metals and Alloys

    Energy Technology Data Exchange (ETDEWEB)

    Sparks, Joshua C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Krantz, Kelsie E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Christian, Jonathan H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Washington, II, Aaron L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-07-27

    The Plutonium Management and Disposition Agreement (PMDA) is a nuclear non-proliferation agreement designed to remove 34 tons of weapons-grade plutonium from Russia and the United States. While several removal options have been proposed since the agreement was first signed in 2000, processing the weapons-grade plutonium to mixed-oxide (MOX) fuel has remained the leading candidate for achieving the goals of the PMDA. However, the MOX program has received its share of criticisms, which causes its future to be uncertain. One alternative pathway for plutonium disposition would involve oxidizing the metal followed by impurity down blending and burial in the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. This pathway was investigated by use of a hybrid microwave and a muffle furnace with Fe and Al as surrogate materials. Oxidation occurred similarly in the microwave and muffle furnace; however, the microwave process time was significantly faster.

  10. Environmental Behaviour of Plutonium Accidentally Released at Thule, Greenland

    DEFF Research Database (Denmark)

    Aarkrog, Asker

    1977-01-01

    The environmental contamination resulting from the B-52 accident in 1968 at Thule was studied by scientific expeditions in 1968, 1970 and 1974. The contamination was mainly confined to the marine environment, where plutonium was preferentially located in the sediments and the benthic fauna....... Plutonium concentrations down through the sediment layers decayed exponentially with a half-depth of 1-2 cm. The horizontal distribution of the plutonium may be described by an exponential expression: mCi 239,240Pn km-2 = 460e-0.28R or by a power function: mCl 239,240Pu km-2 = 370 R-1.2, where R....... From 1968 to 1970 the 239,240Pu concentrations in the biota decreased by an order of magnitude, since 1970 the decrease has been less evident. In 1970 and 1974 there were no indications of increased plutonium concentrations in surface seawater or in sea plants or zooplankton. Higher animals...

  11. Plutonium releases from the 1957 fire at Rocky Flats

    International Nuclear Information System (INIS)

    The Colorado Department of Public Health and Environment sponsored a study to reconstruct contaminant doses to the public from the Rock Flats nuclear weapons plant. This analysis of the September 1957 fire in a plutonium fabrication building that breached the building air filtration system is part of the Colorado Department of Public Health and Environment study. The plutonium release from this fire is estimated using environmental data collected around the time of the fire and an air dispersion model. The approximate upper bound on the total plutonium release from the fire is 1.9 GBq (0.05 Ci), with an uncertainty of about two orders of magnitude. Off-site air concentrations and deposition of plutonium resulting from the approximate upper-bound release are estimated. The highest predicted off-site effective dose resulting from the approximate upper-bound release is about 13 μSv (1.3 mrem)

  12. Preparation of fused chloride salts for use in pyrochemical plutonium recovery operations at Los Alamos

    International Nuclear Information System (INIS)

    The Plutonium Metal Technology Group at Los Alamos routinely uses pyrochemical processes to produce and purify plutonium from impure sources. The basic processes (metal production, metal purification, and residue treatment) involve controlling oxidation and reduction reactions between plutonium and its compounds in molten salts. Current production methods are described, as well as traditional approaches and recent developments in the preparation of solvent salts for electrorefining, molten salt extraction, lean metal (pyroredox) purification, and direct oxide reduction

  13. Preparation of fused chloride salts for use in pyrochemical plutonium recovery operations at Los Alamos

    Energy Technology Data Exchange (ETDEWEB)

    Fife, K.W.; Bowersox, D.F.; Christensen, D.C.; Williams, J.D.

    1986-07-01

    The Plutonium Metal Technology Group at Los Alamos routinely uses pyrochemical processes to produce and purify plutonium from impure sources. The basic processes (metal production, metal purification, and residue treatment) involve controlling oxidation and reduction reactions between plutonium and its compounds in molten salts. Current production methods are described, as well as traditional approaches and recent developments in the preparation of solvent salts for electrorefining, molten salt extraction, lean metal (pyroredox) purification, and direct oxide reduction.

  14. Plant biotechnology for sustainable production of energy and co-products

    Energy Technology Data Exchange (ETDEWEB)

    Scheffran, Juergen [Hamburg Univ. (Germany). Inst. for Geography; Widholm, Jack M. (eds.) [Illinois Univ., Urbana, IL (United States). Dept. of Crop Sciences; Mascia, Peter N.

    2010-07-01

    The successful use of plant biomass for the sustainable production of energy and co-products such as chemicals is critically important for the future of humanity. Large scale exploitation of biomass is needed to decrease the production of greenhouse gases and help mitigate global warming, to provide energy security in the face of declining petroleum reserves, to improve balance of payment imbalances, and to spur local economic development. This volume discusses such uses of plant biomass as well as ways to improve the productivity and composition of plant species, including trees, perennial and annual grasses, oil-producing plants and algae, that have the potential to produce substrates such as sugar, starch, oil and cell walls, as well as energy and co-product substrates. The problems of invasiveness and gene dispersal are discussed, as are ways to mitigate these. Among the topics covered are models for integrated biorefineries to produce many co-product chemicals, the use of corn stover to power ethanol plants, life cycle analysis of biofuels, and criteria for biomass sustainability and certification. This is indeed an exciting and fast-moving time for advocates of plant biomass-based technology. (orig.)

  15. Biogas and mineral fertiliser production from plant residues of phytoremediation

    Energy Technology Data Exchange (ETDEWEB)

    Chu, Thi Thu Ha

    2011-07-01

    The former uranium mining site in Ronneburg, Thuringia, Germany was known as a big source of uranium with more than 113,000 tons of uranium mined from 1946 to 1990. This area has been remediated since the nineties of the last century. However, nowadays the site in Ronneburg is still specially considered because of the heterogeneous contamination by many heavy metals and the vegetation can be affected. Three plant species including Indian mustard - Brassica juncea L., triticale - x. Triticosecale Wittmaek and sunflower - Helianthus annuus L. were seeded as accumulators of heavy metals and radionuclides in the phytoremediation process in 2009 and 2010 in Ronneburg. The subsequent utilization of the plant residues after phytoremediation is of special consideration. Batch fermentation of harvested plant materials under the mesophilic condition showed that all of the investigated plant materials had much higher biogas production than liquid cow manure except triticale root, of which biogas yield per volatile solid was not significantly higher than the one of sludge. The highest biogas yields (311 L{sub N}/kg FM and 807 L{sub N}/kg VS) were achieved from the spica of triticale after 42 days of retention of anaerobic digestion. Triticale shoot residues generated higher biogas and methane yields than the previously reported triticale materials that were harvested from the uncontaminated soil Triticale was considered as the highest potential species in biogas production, beside the best growth ability on the acidic soil at the test field site with highest biomass production. Biogas yield of Indian mustard shoot was also high but dramatically varied from 2009 to 2010. Digestates after anaerobic digestion of plant residues contained various macronutrients such as nitrogen, potassium, phosphorus and sulphur, and various micronutrients such as iron, manganes, zinc, etc. The accumulation levels of heavy metals in the investigated plant materials were not the hindrance factors

  16. Modulation of endothelial nitric oxide by plant-derived products.

    Science.gov (United States)

    Schmitt, Christoph A; Dirsch, Verena M

    2009-09-01

    Nitric oxide (NO), produced by endothelial nitric oxide synthase (eNOS), is recognised as a central anti-inflammatory and anti-atherogenic principle in the vasculature. Decreased availability of NO in the vasculature promotes the progression of cardiovascular diseases. Epidemiological and clinical studies have demonstrated that a growing list of natural products, as components of the daily diet or phytomedical preparations, may improve vascular function by enhancing NO bioavailability. In this article we first outline common pathways modulating endothelial NO production or bioavailability to provide a basis for subsequent mechanistic discussions. Then we comprehensively review natural products and plant extracts known to positively influence eNOS activity and/or endothelial function in vitro or in vivo. We will discuss red wine, highlighting polyphenols, oligomeric procyanidins (OPC) and resveratrol as modulators of endothelial NO production. Other dietary products and their active components known to activate eNOS include cocoa (OPC and its monomer (-)-epicatechin), pomegranates (polyphenols), black and green tea (flavanoids, especially epigallocatechin gallate), olive oil (oleic acid and polyphenols), soy (genistein), and quercetin, one of the most abundant flavonoids in plants. In addition, phytomedical preparations made from ginkgo, hawthorn and ginseng, as well as formulations used in traditional Chinese Medicine, have been shown to affect endothelial NO production. Recurring phytochemical patterns among active fractions and purified compounds are discussed. In summary, there is increasing evidence that several single natural products and plant extracts influence endothelial NO production. Identification of such compounds and characterisation of their cellular actions may increase our knowledge of the regulation of endothelial NO production and could provide valuable clues for the prevention or treatment of cardiovascular diseases. PMID:19497380

  17. Preparation of plutonium hexafluoride. Recovery of plutonium from waste dross (1962); Preparation de l'hexafluorure de plutonium. Recuperation du plutonium des scories d'elaboration (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Gendre, R. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1962-07-01

    The object of this work is to study the influence of various physical factors on the rate of fluorination of solid plutonium tetrafluoride by fluorine. In a horizontal oven with a circulation for pure fluorine at atmospheric pressure and 520 deg. C, at a fluorine rate of 9 litres/hour, it is possible to transform 3 g of tetrafluoride to hexafluoride with about 100 per cent transformation and a recovery yield of over 90 per cent, in 4 to 5 hours. The fluorination rate is a function of the temperature, of the fluorine flow-rate, of the crucible surface, of the depth of the tetrafluoride layer and of the reaction time. It does not depend on the diffusion of the fluorine into the solid but is determined by the reaction at the gas-solid interface and obeys the kinetic law (1 - T{sub T}){sup 1/3} = kt + 1. The existence of intermediate fluorides, in particular Pu{sub 4} F{sub 17}, is confirmed by a break in the Arrhenius plot at about 370 deg. C, by differences in the fluorination rates inside the tetrafluoride layer, and by reversible colour changes. The transformation to hexafluoride occurs with a purification with respect of the foreign elements present in the initial plutonium. Recovery of plutonium from waste dross: The study is based on the transformation of occluded plutonium particles to gaseous hexafluoride which is then decomposed thermally to the tetrafluoride which can be reintroduced directly in the production circuit. Under the conditions considered this process is not applicable industrially. After milling, it is possible to separate the dross into enriched (75 per cent Pu in 2.6 per cent by weight of dross) and depleted portions. By prolonged fluorination (16 hours) of the various fractions it is possible to recover about 80 per cent of the plutonium. A treatment plant using fluidization, as described at the end of this study, should make it possible to substantially improve the yield. (author) [French] L'objet de l'etude est l

  18. Plutonium in the environment - bibliographic study and quantification; Impacts environnemental et sanitaire des isotopes du plutonium, etude bibliographique et quantification

    Energy Technology Data Exchange (ETDEWEB)

    Guetat, Ph.; Monfort, M.; Ansoborlo, E. [CEA Marcoule, Dir. de l' Energie Nucleaire, 30 (France); Bion, L.; Moulin, V.; Reiller, P.; Vercouter, Th. [CEA Saclay, Dir. de l' Energie Nucleaire, 91 - Gif sur Yvette (France); Boucher, L.; Jourdain, F.; Van Dorpe, F. [CEA Cadarache, Dir. de l' Energie Nucleaire, 13 - Saint Paul lez Durance (France); Comte, A.; Flury Heard, A.; Fritsch, P.; Menetrier, F. [CEA Fontenay-aux-Roses, Dir. des Sciences du Vivant, 92 (France)

    2008-07-01

    This document deals with the different isotopes of plutonium. It intends to summarize the main features of plutonium behaviour from sources inside installation to the environment and man, and is expected to report the current knowledge about the different parameters used in the models for environmental and radiological impact assessment. The objective is to gather scientific information useful for deciders in case of accident or for regulation purposes. It gives main information on radiological and chemical characteristics which are necessary to understand transfers between compartments. Then it reports information on normal and accidental historical sources and present releases. The next part deals with transfer parameters in the installations and in environment. Parameters that influence its behaviour are examined, inside installations (physico-chemical forms and events that lead to releases), and outside in the environment for deposition to soils and transfer to plants, and animal products. A full chapter is dedicated to presentation of typical assessments, for each isotope and for mixture, and correspondence between activity, mass and dose reference levels are presented and discussed. Transfer and behaviour in man and effects on health are finally presented. (author)

  19. EXAFS/XANES studies of plutonium-loaded sodalite/glass waste forms

    International Nuclear Information System (INIS)

    A sodalite/glass ceramic waste form is being developed to immobilize highly radioactive nuclear wastes in chloride form, as part of an electrochemical cleanup process. Two types of simulated waste forms were studied: where the plutonium was alone in an LiCl/KCl matrix and where simulated fission-product elements were added representative of the electrometallurgical treatment process used to recover uranium from spent nuclear fuel also containing plutonium and a variety of fission products. Extended X-ray absorption fine structure spectroscopy (EXAFS) and X-ray absorption near-edge spectroscopy (XANES) studies were performed to determine the location, oxidation state, and particle size of the plutonium within these waste form samples. Plutonium was found to segregate as plutonium(IV) oxide with a crystallite size of at least 4.8 nm in the non-fission-element case and 1.3 nm with fission elements present. No plutonium was observed within the sodalite in the waste form made from the plutonium-loaded LiCl/KCl eutectic salt. Up to 35% of the plutonium in the waste form made from the plutonium-loaded simulated fission-product salt may be segregated with a heavy-element nearest neighbor other than plutonium or occluded internally within the sodalite lattice

  20. EXAFS/XANES studies of plutonium-loaded sodalite/glass waste forms

    Science.gov (United States)

    Richmann, Michael K.; Reed, Donald T.; Kropf, A. Jeremy; Aase, Scott B.; Lewis, Michele A.

    2001-09-01

    A sodalite/glass ceramic waste form is being developed to immobilize highly radioactive nuclear wastes in chloride form, as part of an electrochemical cleanup process. Two types of simulated waste forms were studied: where the plutonium was alone in an LiCl/KCl matrix and where simulated fission-product elements were added representative of the electrometallurgical treatment process used to recover uranium from spent nuclear fuel also containing plutonium and a variety of fission products. Extended X-ray absorption fine structure spectroscopy (EXAFS) and X-ray absorption near-edge spectroscopy (XANES) studies were performed to determine the location, oxidation state, and particle size of the plutonium within these waste form samples. Plutonium was found to segregate as plutonium(IV) oxide with a crystallite size of at least 4.8 nm in the non-fission-element case and 1.3 nm with fission elements present. No plutonium was observed within the sodalite in the waste form made from the plutonium-loaded LiCl/KCl eutectic salt. Up to 35% of the plutonium in the waste form made from the plutonium-loaded simulated fission-product salt may be segregated with a heavy-element nearest neighbor other than plutonium or occluded internally within the sodalite lattice.

  1. Process modeling of plutonium conversion and MOX fabrication for plutonium disposition

    International Nuclear Information System (INIS)

    Two processes are currently under consideration for the disposition of 35 MT of surplus plutonium through its conversion into fuel for power production. These processes are the ARIES process, by which plutonium metal is converted into a powdered oxide form, and MOX fuel fabrication, where the oxide powder is combined with uranium oxide powder to form ceramic fuel. This study was undertaken to determine the optimal size for both facilities, whereby the 35 MT of plutonium metal will be converted into fuel and burned for power. The bounding conditions used were a plutonium concentration of 3--7%, a burnup of 20,000--40,000 MWd/MTHM, a core fraction of 0.1 to 0.4, and the number of reactors ranging from 2--6. Using these boundary conditions, the optimal cost was found with a plutonium concentration of 7%. This resulted in an optimal throughput ranging from 2,000 to 5,000 kg Pu/year. The data showed minimal costs, resulting from throughputs in this range, at 3,840, 2,779, and 3,497 kg Pu/year, which results in a facility lifetime of 9.1, 12.6, and 10.0 years, respectively

  2. Estimating seed production of common plants in seasonally flooded wetlands

    Science.gov (United States)

    Laubhan, Murray K.; Fredrickson, Leigh H.

    1992-01-01

    We developed a technique to quickly estimate seed production of common moist-soil plants because previously reported methods were too time consuming to be of value to waterfowl resource managers. Eleven regression equations were developed for 13 plant species in the upper Mississippi Alluvial Valley and the Rio Grande Valley, New Mexico. Estimated time to collect a sample was 1.5 minutes. Easily measured vegetation characteristics such as inflorescence number, inflorescence length, and plant height were used as independent variables to estimate seed mass of known mass samples. Coefficients of determination (R2) ranged from 0.79 for rice flatsedge (Cyperus iria) to 0.96 for smartweeds (Polygonum spp.). The accuracy and precision of equations tested using independent data indicate that the technique can be used to detect changes in seed mass of moist-soil plants in seasonally flooded impoundments. Because of the small sample area per plot used (0.0625 m2) and changes in the density of plants within an impoundment, we recommend that as many samples as economically feasible be collected to reliably estimate seed production.

  3. Mini digester and biogas production from plant biomass

    Directory of Open Access Journals (Sweden)

    P. Vindis

    2009-08-01

    Full Text Available Purpose: The aim of the paper is to present the construction of a mini digester for biogas production from different agriculture plant biomass and other organic wastes. The amount of biogas production (methane is observed by the mini digester.Design/methodology/approach: The mini digester consisting of twelve units was built and some measurements with agriculture plant biomass were performed according to DIN 38414 part 8. Four tests simultaneously with three repetitions can be performed.Findings: With the mini digester the amount of biogas production is observed. The parameters such as biogas production and biogas composition from maize and sugar beet silage in certain ratio were measured and calculated. The highest biogas and methane yield was 493 NI kg VS-1 or 289 NI CH4 kg VS-1.Research limitations/implications: The scope of substrates for the anaerobic digestion process is on the increase so the interest in the use of the biogas as a source of a renewable energy is very high. With mini digester it is possible to observe the amount of biogas (methane production and so the most suitable plant giving the maximum methane yield, can be determined.Practical implications: The aim of biogas as renewable source of energy is to replace fossil fuels with sustainable energy production systems and to fulfil the requirements of the Kyoto Protocol. On big farms the liquid manure and different energy crops can be used for biogas production. That can improve the economical efficiency of the farm and reduce the CO2 emissions.Originality/value: Mini digester for biogas production was built as special equipment. The quality of produced biogas is determined with a gas analyser GA 45.

  4. Strong association of fallout plutonium with humic and fulvic acid as compared to uranium and 137Cs in Nishiyama soils from Nagasaki, Japan

    International Nuclear Information System (INIS)

    To investigate the formation of mobile organic plutonium, the plutonium contents of the fulvic (FA) and humic (HA) acids were analyzed from the soil samples obtained at Nishiyama, Nagasaki, Japan. The percentages of the plutonium bound strongly to HA and to FA vs. the total plutonium in the soil were 5-10% and 1%, respectively, at the depth of 0-0.1 m, much higher values than those of 137Cs and uranium. After being weathered for 51 years under a temperate climate, the initial highfired oxides of fallout plutonium have become as chemically reactive plutonium from nuclear fuel reprocessing plants. (author)

  5. Vertical distributions of plutonium isotopes in marine sediment cores off the Fukushima coast after the Fukushima Dai-ichi Nuclear Power Plant accident

    Directory of Open Access Journals (Sweden)

    W. T. Bu

    2013-04-01

    Full Text Available The Fukushima Dai-ichi Nuclear Power Plant (FDNPP accident led to the release of large amounts of radionuclides into the atmosphere as well as direct discharges into the sea. In contrast to the intensive studies on the distribution of the released high volatility fission products, such as 131I, 134Cs and 137Cs, similar studies of the actinides, especially the Pu isotopes, are limited. To obtain the vertical distribution of Pu isotopes in marine sediments and to better assess the possible contamination of Pu from the FDNPP accident in the marine environment, we determined the activities of 239+240Pu and 241Pu as well as the atom ratios of 240Pu/239Pu and 241Pu/239Pu in sediment core samples collected in the western North Pacific off Fukushima from July 2011 to July 2012. We also measured surface sediment samples collected from seven Japanese estuaries before the FNDPP accident to establish the comprehensive background baseline data. The observed results of both the Pu activities and the Pu atom ratios for the sediments in the western North Pacific were comparable to the baseline data, suggesting that the FDNPP accident did not cause detectable Pu contamination to the studied regions prior to the sampling time. The Pu isotopes in the western North Pacific 30 km off the Fukushima coast originated from global fallout and Pacific Proving Ground close-in fallout.

  6. Plant Glutathione Biosynthesis: Diversity in Biochemical Regulation and Reaction Products

    Directory of Open Access Journals (Sweden)

    Ashley eGalant

    2011-09-01

    Full Text Available In plants, exposure to temperature extremes, heavy metal-contaminated soils, drought, air pollutants, and pathogens results in the generation of reactive oxygen species that alter the intracellular redox environment, which in turn influences signaling pathways and cell fate. As part of their response to these stresses, plants produce glutathione. Glutathione acts as an antioxidant by quenching reactive oxygen species, and is involved in the ascorbate-glutathione cycle that eliminates damaging peroxides. Plants also use glutathione for the detoxification of xenobiotics, herbicides, air pollutants (sulfur dioxide and ozone, and toxic heavy metals. Two enzymes catalyze glutathione synthesis: glutamate-cysteine ligase (GCL, and glutathione synthetase (GS. Glutathione is a ubiquitous protective compound in plants, but the structural and functional details of the proteins that synthesize it, as well as the potential biochemical mechanisms of their regulation, have only begun to be explored. As discussed here, the core reactions of glutathione synthesis are conserved across various organisms, but plants have diversified both the regulatory mechanisms that control its synthesis and the range of products derived from this pathway. Understanding the molecular basis of glutathione biosynthesis and its regulation will expand our knowledge of this component in the plant stress response network.

  7. Africanos, tráfico atlántico y cimarrones en las fronteras entre la Guyana Francesa y la América portuguesa, siglo XVIII

    Directory of Open Access Journals (Sweden)

    Flávio dos Santos Gomes

    2011-01-01

    Full Text Available El artículo analiza las experiencias históricas de los cimarrones en un área de fronter atlántica continental entre la Guyana Francesa y la América portuguesa durante el siglo XVII. Las expectativas de los fugitivos africanos se abordan relacionando el movimiento del tráfico atlántico de esclavos-sus variaciones, los volúmenes y las procedencias-. De esta forma se reflexiona sobre los ambientes sociales, étnicos y geográficos que fueron encontrados y recreados en las selvas de estas zonas fronterizas. En un territorio de conflictos, enfrentamientos, disputas coloniales y expectativas de identidades, surgieron espacios de cooperación, donde los colonos europeos y las poblaciones de indígenas y de africanos se reinventaron como culturas y comunidades. Los circuitos demográficos del tráfico atlántico estaban conectados a la experiencia de africanos de diversas procedencias y a la posibilidad de encuentro de estos, a través de las fugas y de las comunidades transétnicas en una zona de frontera transnacional durante la Colonia.

  8. Processing biogas plant digestates into value-added products - BIOVIRTA

    Energy Technology Data Exchange (ETDEWEB)

    Paavola, T. (MTT Agrifood Research Finland, Jokioinen (Finland)), e-mail: teija.paavola@mtt.fi; Torniainen, M. (Finnish Food Safety Authority, EVIRA, Helsinki (Finland)), e-mail: merja.torniainen@evira.fi; Kaparaju, P. (Jyvaeskylae Univ. (Finland)), e-mail: prasad.kaparaju@jyu.fi (and others)

    2011-11-15

    The objective of BIOVIRTA project is to develop technologies and practices with which digestates, originating from anaerobic digestion of different organic wastes and by-products can be refined to value-added and safe products for various end-uses. It is expected that the operational preconditions for biogas plants will be significantly enhanced when the end-products are proven safe and applicable. Selection of the raw materials for anaerobic co-digestion is the main operational strategy that could influence the nutrient content in the digestate. This has been clearly established in the laboratory and full-scale studies with various digestates originating from different raw materials. The nutrient content in the digestate also affects the opportunities to produce refined digestate products. In this project, the possibilities for several processing technologies, e.g. mechanical separation, stripping, and struvite production have been intensively evaluated for the production of different digestate products. Their mass balances have also been estimated. The feasibility for the use of the digestate products has been assessed based on their chemical and hygienic quality and for various end-uses, including as organic fertiliser and/or soil improver in crop production. The results of these field-experiments showed that the yield of barley fertilised with digestate products was comparable to inorganic fertilisers. (orig.)

  9. Mycorrhizal Productivity Following Woody Plant Invasion of Grassland

    Science.gov (United States)

    Boutton, T. W.; Rowe, H. I.; Ariza, M. C.; Miller, R. M.; Filley, T. R.

    2008-12-01

    Mycorrhizal fungi play an important role in soil carbon storage and dynamics through the production of recalcitrant organic compounds (e.g., glomalin and chitin), and through the production of hyphae which entangle and enmesh soil particles to form aggregates which physically protect organic matter from decomposer organisms. Despite these important functions, little is known regarding rates of mycorrhizal productivity and how these rates might be influenced by changes in plant community composition. We quantified mycorrhizal production in a subtropical savanna parkland in southern Texas where woody plants have invaded areas that were once open grassland. Mycorrhizal ingrowth bags (3 x 10 cm) were made from 50 μm nylon mesh, filled with sterile sand (200-600 μm particle size), and deployed in the field in triplicate in remnant grasslands (n=15), and in woody plant stands (n=13) ranging in age from 15 to 86 yrs. Ingrowth bags were installed in May and harvested in Oct 2007 after 156 days. Hyphae were isolated by flotation/filtration, cleaned thoroughly to remove sand, freeze-dried, and weighed. Microscopic examination indicated that nearly all hyphae recovered from ingrowth bags were from arbuscular mycorrhizal fungi. During the ingrowth period, nearly 4X more hyphal biomass accumulated in wooded areas (9.00 ± 3.84 g m- 2) compared to remnant grasslands (2.35 ± 0.56 g m-2). Hyphal productivity rates increased linearly with woody plant stand age (r = 0.89) from 15 ± 4 mg m-2 day-1 in grasslands (time 0) up to 58-98 mg m-2 day-1 in wooded areas >65 yrs old. When these productivity rates are annualized, we find that hyphal productivity represents approximately 4% of aboveground net primary productivity (ANPP) in wooded areas, and 2% of ANPP in remnant grasslands. These observations are consistent with concurrent studies showing that glomalin concentrations and chitinase enzyme activity both increase in soils with time following woody encroachment into grassland

  10. The effect of economic variables over a biodiesel production plant

    Energy Technology Data Exchange (ETDEWEB)

    Marchetti, J.M., E-mail: jmarchetti@plapiqui.edu.ar [Planta Piloto de Ingenieria Quimica (UNS-CONICET), Camino La Carrindanga km 7, 8000 Bahia Blanca (Argentina)

    2011-09-15

    Highlights: {yields} Influence of the mayor economic parameters for biodiesel production. {yields} Variations of profitability of a biodiesel plant due to changes in the market scenarios. {yields} Comparison of economic indicators of a biodiesel production facility when market variables are modified. - Abstract: Biodiesel appears as one of the possible alternative renewable fuels to substitute diesel fuel derived from petroleum. Several researches have been done on the technical aspects of biodiesel production in an attempt to develop a better and cleaner alternative to the conventional process. Economic studies have been carried out to have a better understanding of the high costs and benefits of different technologies in the biodiesel industry. In this work it is studied the effect of the most important economic variables of a biodiesel production process over the general economy of a conventional plant which employs sodium methoxide as catalyst. It has been analyzed the effect of the oil price, the amount of free fatty acid, the biodiesel price, the cost of the glycerin, the effect due to the modification on the methanol price, the washing water price, and several others. Small variations on some of the major market variables would produce significant effects over the global economy of the plant, making it non profitable in some cases.

  11. A mechanism for plutonium pyrophoricity

    International Nuclear Information System (INIS)

    Two-stage mechanism of plutonium pyrophoricity, based on metal warm-up under impact of heat released by Pu2O3 layer oxidation, preliminarily formed as a result of dioxide layer reduction on plutonium surface, is proposed. It is shown that the above mechanism satisfactorily explains the available experimental data, including effect of various factors on ignition temperature of metallic plutonium. 48 refs.; 6 figs

  12. The Complexity of Bioactive Natural Products in Plants

    DEFF Research Database (Denmark)

    Frisch, Tina

    Plants produce a diverse range of bioactive natural products promoting their fitness. These specialized metabolites may serve as chemical defence against herbivores and pathogens and may inhibit the growth and development of competing species. Hydroxynitrile glucosides and glucosinolates are two...... classes of defence compounds, which have diverging properties, but also share common biosynthetic features. Hydroxynitrile glucosides are produced in species across the plant kingdom, whereas glucosinolates are found almost exclusively within the Brassicales, which generally does not contain...... these two plant species interesting gateways for addressing these questions of evolution. The presented research demonstrates that the biosynthetic pathway for the hydroxynitrile glucoside alliarinoside in A. petiolata does not follow the general scheme for hydroxynitrile glucoside biosynthesis in other...

  13. Classification of explosives transformation products in plant tissue

    Energy Technology Data Exchange (ETDEWEB)

    Larson, S.L.; Jones, R.P. (Army Corps of Engineers, Vicksburg, MI (United States). Waterways Experiment Station); Escalon, L.; Parker, D. (AScI Corp., McLean, VA (United States))

    1999-06-01

    Explosives contamination in surface or groundwater used for the irrigation of food crops and phytoremediation of explosives-contaminated soil or water using plant-assisted biodegradation have brought about concerns as to the fate of explosives in plants. Liquid scintillation counting, high-performance liquid chromatography, and gel permeation chromatography were utilized to characterize explosives (hexahydro-1,3,5-trinitro-1,3,5-triazine and trinitrotoluene) and their metabolites in plant tissues obtained from three separate studies. Analyzing tissues of yellow nutsedge (Cyperus esculentus), corn (Zea mays), lettuce (Lacuta sativa), tomato (Lyopersicum esculentum), radish (Raphanus sativus), and parrot feather (Myriophyllum aquaticum) from three studies where exposure to explosives at nontoxic levels occurred showed that extensive transformation of the explosive contaminant occurred, variations were noted in uptake and transformation between terrestrial and aquatic plants, the products had significantly higher polarity and water solubility than the parent compounds, and the molecular sizes of the transformation products were significantly greater than those of the parent compounds.

  14. Plutonium worker dosimetry.

    Science.gov (United States)

    Birchall, Alan; Puncher, M; Harrison, J; Riddell, A; Bailey, M R; Khokryakov, V; Romanov, S

    2010-05-01

    Epidemiological studies of the relationship between risk and internal exposure to plutonium are clearly reliant on the dose estimates used. The International Commission on Radiological Protection (ICRP) is currently reviewing the latest scientific information available on biokinetic models and dosimetry, and it is likely that a number of changes to the existing models will be recommended. The effect of certain changes, particularly to the ICRP model of the respiratory tract, has been investigated for inhaled forms of (239)Pu and uncertainties have also been assessed. Notable effects of possible changes to respiratory tract model assumptions are (1) a reduction in the absorbed dose to target cells in the airways, if changes under consideration are made to the slow clearing fraction and (2) a doubling of absorbed dose to the alveolar region for insoluble forms, if evidence of longer retention times is taken into account. An important factor influencing doses for moderately soluble forms of (239)Pu is the extent of binding of dissolved plutonium to lung tissues and assumptions regarding the extent of binding in the airways. Uncertainty analyses have been performed with prior distributions chosen for application in epidemiological studies. The resulting distributions for dose per unit intake were lognormal with geometric standard deviations of 2.3 and 2.6 for nitrates and oxides, respectively. The wide ranges were due largely to consideration of results for a range of experimental data for the solubility of different forms of nitrate and oxides. The medians of these distributions were a factor of three times higher than calculated using current default ICRP parameter values. For nitrates, this was due to the assumption of a bound fraction, and for oxides due mainly to the assumption of slower alveolar clearance. This study highlights areas where more research is needed to reduce biokinetic uncertainties, including more accurate determination of particle transport rates

  15. Determination of plutonium isotopes in marine sediments off the Fukushima coast following the Fukushima Dai-ichi Nuclear Power Plant accident

    Directory of Open Access Journals (Sweden)

    W. T. Bu

    2013-01-01

    Full Text Available The Fukushima Dai-ichi Nuclear Power Plant (FDNPP accident led to the release of large amounts of radionuclides into the atmosphere as well as direct discharges into the sea. In contrast to the intensive studies on the distribution of the released high volatility fission products, such as 131I, 134Cs and 137Cs, similar studies of the actinides, especially the Pu isotopes, are limited. To obtain the vertical distribution of Pu isotopes in marine sediments and to better assess the possible contamination of Pu from the FDNPP accident in the marine environment, we determined the activities of 239+240Pu and 241Pu as well as the atom ratios of 240Pu / 239Pu and 241Pu / 239Pu in sediment core samples collected in the western North Pacific off Fukushima from July 2011 to July 2012. We also measured surface sediment samples collected from seven Japanese estuaries before the FNDPP accident to establish the comprehensive background baseline data. The observed results of both the Pu activities and the Pu atom ratios for the sediments in the western North Pacific were comparable to the baseline data, suggesting that the FDNPP accident did not cause detectable Pu contamination to the studied regions prior to the sampling time. The Pu isotopes in the western North Pacific 30 km off Fukushima coast originated from global fallout and Pacific Proving Ground close-in fallout.

  16. Recovery of plutonium from carbonate wash solutions

    International Nuclear Information System (INIS)

    A novel method has been developed for recovery of plutonium and uranium from carbonate wash solutions generated during solvent wash process involved in the reprocessing of high burn up FBTR fuel. The proposed method involves a selective coprecipitation of Pu and U by adding ammonium hydroxide to the pre acidified carbonate wash solution. Substantial removal of DBP by successive steps of coprecipitation, completely eliminates the possibility of undesired solid formation which is mainly due to the presence of high content of DBP. By adopting this method, an excellent decontamination factor for DBP has been achieved without any crud/solid formation. Phosphate content in the final oxide product meets the product specifications. Flowsheet condition necessary for the recovery process for plutonium from the aqueous carbonate solution is formulated and adopted in the CORAL facility. (author)

  17. ''Distribution and behaviour of plutonium in the waters of the channel and of the seine estuary''

    International Nuclear Information System (INIS)

    Excess dissolved plutonium has been measured in the coastal waters of the Channel, from Granville to Boulogne, probably due to sorption-desorption processus. In the Seine estuary, in situ measurements and experimental studies showed that the plutonium desorbs himself from particles in low salinity waters. The desorbed plutonium originates in marine and/or fluvial dissolved Pu. Marine dissolved Pu(V), originating from La Hague plant discharges and from atlantic waters, is reduced and sorbed when the salinity decreases onto estuarial particles: Isotopic Activity Ration 238Pu/239, Pu(IR) of marine dissolved Pu(V) is about 0.7. Fluvial dissolved plutonium originates from atmospheric fallout and from an internal river source: fallout plutonium (IR=0.05) is unreactive with salinity while 45% of river plutonium (IR>1.7) flocculates at 0.5 g l-1. Desorbed plutonium may have various origins, depending on the Seine liquid discharges and on the tidal coefficient. When the marine waters do not migrate upstream, the low salinity waters encounters particles marked essentially with marine plutonium and the IR of desorbed Pu is about 0.7. The activities of desorbed plutonium are too low to have any influence on the distribution of plutonium in the coastal waters on the Seine Bay. When the marine waters migrate upstream, the low salinity waters meet particles marked essentially with river plutonium (IR>1.7) and desorbed plutonium has a very high IR. These estuarine conditions are encountered five to seven month a year and implicate an increase of the IR of 0.1 of the plutonium present in the coastal waters of the Seine bay (1.2.-1.3.). (author)

  18. Product distribution from a chosen plant to customers

    OpenAIRE

    Spálenková, Michaela

    2009-01-01

    The aim of the work is to give a detailed insight into the ways and methods of product distribution as used by a food industry manufacturing plant. Distribution chain management from a marketing and logistics point of view is analysed focusing on transport options and potential. Theoretical basis and terms definition are provided, the emphasis being laid on the function of distribution, its intermediaries, and channels in terms of logistics costs. The work describes options a company has when...

  19. Power plant project success through total productive generation

    Energy Technology Data Exchange (ETDEWEB)

    Kaivola, R.; Tamminen, L.

    1996-11-01

    The Total Productive Generation concept (TPG) defines the lines of action adopted by IVO Generation Services Ltd (IGS) for the operation and maintenance of power plants. The TPG concept is based on procedures tested in practice. The main idea of TPG is continuous development of quality, which is a joint effort of the entire staff. Its objective is to benefit IGS`s own staff and, in particular, the company`s customers. (orig.)

  20. MODERN WAYS OF INULIN PRODUCTION FROM PLANT MATERIALS

    Directory of Open Access Journals (Sweden)

    Lisovoy V. V.

    2016-04-01

    Full Text Available The article presents the results of the patent research in the field of modern production technologies of Inulin from plant material. It has been established that the differences of the currently known methods of production of inulin are concluded in selecting raw materials pretreatment inulin-containing modes type extractant and extraction methods, methods of purification inulincontaining extract and methods for producing the final product. A significant amount of Inulin production methods is based on use of freshly feedstock. A number of methods have been patented involving the extraction Inulin from plant raw materials previously stabilized by drying. In most of the methods, inulin extraction is carried out at elevated temperatures with water or aqueous salt solutions. Several technologies involve extraction with organic solvents at low temperatures. Have been patented several processes in which the extraction is replaced by a separation process using inulincontaining juice and physical and mechanical methods. Some of the known processes provide for the extraction process to further operations, such as blanching vegetable raw materials, sonication, vibration impact, processing enzymes. The most promising direction to improve manufacturing technology of inulin from fresh plant raw materials is to conduct research on the use of electromagnetic fields at microwave frequencies, the inactivating effects of which on enzyme systems is an established fact that, in turn, would eliminate the use of chemical agents for inactivation of oxidative enzymes. In addition, considering that more effective are the methods for the preparation of inulin from freshly harvested plant material, are relevant researches on development of innovative technologies to prepare it for storage and its storage, which will provide inhibition of unwanted biochemical and microbiological processes that occur during storage and lead to a loss of inulin

  1. The impact of spatial externalities : Skills, education and plant productivity

    OpenAIRE

    Wixe, Sofia

    2015-01-01

    This paper analyses the role of a broad range of spatial externalities in explaining average labour productivity of Swedish manufacturing plants. The main findings show positive effects from general urbanization economies and labour market matching, as well as a negative effect from within-industry diversity. These results confirm previous research despite methodological differences,which implies wider generalizability. Additionally, the empirical findings support Marshall–Arrow–Romer (MAR) a...

  2. 1990 production costs operating steam-electric plants

    International Nuclear Information System (INIS)

    In 1990 U.S. electric utilities generated more than 2.8 billion net megawatt hours (MWhr) of electricity from all sources--a slight increase of 0.8% from the 1989 total of 2.78 billion MWhr, but substantially less than the 1989 increase of 2.8% over 1988. Steam-electric plants, which produce electricity by burning fossil fuels or by nuclear fission, typically generate 90% of all U.S. electricity. Utilization of the nation's fossil-fueled steam-electric power plants during 1990 was down about 2% from 1989, primarily because nuclear plant generation increased 9%. (Hydroelectric plant output was up 6% from 1989.) Nuclear power's 1990 contribution to total electric utility generation was up about 1% from 1989 to 20.5%. This paper includes specific 1990 production cost data for 798 steam-electric plants, of which 428 are fueled with coal or lignite, 284 are gas- and/or oil-fired, 73 are nuclear, 6 are geothermal, 4 are wood-fired, and 3 burn refuse or refuse-derived fuel (RDF)

  3. Productivity is a poor predictor of plant species richness

    Science.gov (United States)

    Adler, Peter B.; Seabloom, Eric W.; Borer, Elizabeth T.; Hillebrand, Helmut; Hautier, Yann; Hector, Andy; Harpole, W. Stanley; O'Halloran, Lydia R.; Grace, James B.; Anderson, T. Michael; Bakker, Jonathan D.; Biederman, Lori A.; Brown, Cynthia S.; Buckley, Yvonne M.; Calabrese, Laura B.; Chu, Cheng-Jin; Cleland, Elsa E.; Collins, Scott L.; Cottingham, Kathryn L.; Crawley, Michael J.; Damschen, Ellen Ingman; Davies, Kendi F.; DeCrappeo, Nicole M.; Fay, Philip A.; Firn, Jennifer; Frater, Paul; Gasarch, Eve I.; Gruner, Daneil S.; Hagenah, Nicole; Lambers, Janneke Hille Ris; Humphries, Hope; Jin, Virginia L.; Kay, Adam D.; Kirkman, Kevin P.; Klein, Julia A.; Knops, Johannes M.H.; La Pierre, Kimberly J.; Lambrinos, John G.; Li, Wei; MacDougall, Andrew S.; McCulley, Rebecca L.; Melbourne, Brett A.; Mitchell, Charles E.; Moore, Joslin L.; Morgan, John W.; Mortensen, Brent; Orrock, John L.; Prober, Suzanne M.; Pyke, David A.; Risch, Anita C.; Schuetz, Martin; Smith, Melinda D.; Stevens, Carly J.; Sullivan, Lauren L.; Wang, Gang; Wragg, Peter D.; Wright, Justin P.; Yang, Louie H.

    2011-01-01

    For more than 30 years, the relationship between net primary productivity and species richness has generated intense debate in ecology about the processes regulating local diversity. The original view, which is still widely accepted, holds that the relationship is hump-shaped, with richness first rising and then declining with increasing productivity. Although recent meta-analyses questioned the generality of hump-shaped patterns, these syntheses have been criticized for failing to account for methodological differences among studies. We addressed such concerns by conducting standardized sampling in 48 herbaceous-dominated plant communities on five continents. We found no clear relationship between productivity and fine-scale (meters-2) richness within sites, within regions, or across the globe. Ecologists should focus on fresh, mechanistic approaches to understanding the multivariate links between productivity an

  4. Ethylene production by plants in a closed environment

    Science.gov (United States)

    Wheeler, R. M.; Peterson, B. V.; Sager, J. C.; Knott, W. M.

    Ethylene production by 20-m^2 stands of wheat, soybean, lettuce and potato was monitored throughout growth and development in NASA's Controlled Ecological Life Support System (CELSS) Biomass Production Chamber. Chamber ethylene concentrations rose during periods of rapid growth for all four species, reaching 120 parts per billion (ppb) for wheat, 60 ppb for soybean, and 40 to 50 ppb for lettuce and potato. Following this, ethylene concentrations declined during seed fill and maturation (wheat and soybean), or remained relatively constant (potato). Lettuce plants were harvested during rapid growth and peak ethylene production. The highest ethylene production rates (unadjusted for chamber leakage) ranged from 0.04 to 0.06 ml m^-2 day^-1 during rapid growth of lettuce and wheat stands, or approximately 0.8 to 1.1 nl g^-1 fresh weight h^-1 Results suggest that ethylene production by plants is a normal event coupled to periods of rapid metabolic activity, and that ethylene removal or control measures should be considered for growing crops in a tightly closed CELSS.

  5. Enhancement of Plant Productivity in the Post-Genomics Era.

    Science.gov (United States)

    Thao, Nguyen Phuong; Tran, Vietnam Lam-Son Phan

    2016-08-01

    Obtaining high plant yield is not always achievable in agricultural activity as it is determined by various factors, including cultivar quality, nutrient and water supplies, degree of infection by pathogens, natural calamities and soil conditions, which affect plant growth and development. More noticeably, sustainable plant productivity to provide sufficient food for the increasing human population has become a thorny issue to scientists in the era of unpredictable global climatic changes, appearance of more tremendous or multiple stresses, and land restriction for cultivation. Well-established agricultural management by agrotechnological means has shown no longer to be effective enough to confront with this challenge. Instead, in order to maximize the production, it is advisable to implement such practices in combination with biological applications. Nowadays, high technologies are widely adopted into agricultural production, biological diversity conservation and crop improvement. Wang et al. has nicely outlined the utilization of DNA-based technologies in this field. Among these are the applications of (i) DNA markers into cultivar identification, seed purity analysis, germplasm resource evaluation, heterosis prediction, genetic mapping, cloning and breeding; and (ii) gene expression data in supporting the description of crop phenology, the analytic comparison of crop growth under stress versus non-stress conditions, or the study of fertilizer effects. Besides, various purposes of using transgenic technologies in agriculture, such as generating cultivars with better product quality, better tolerance to biotic or abiotic stress, are also discussed in the review. One of the important highlights in this issue is the review of the benefits brought by high-throughput sequencing technology, which is also known as next-generation sequencing (NGS). It is not so difficult to recognize that its application has allowed us to carry out biological studies at much deeper level

  6. AVLIS Production Plant work breakdown structure and Dictionary

    Energy Technology Data Exchange (ETDEWEB)

    1984-11-15

    The work breakdown structure has been prepared for the AVLIS Production Plant to define, organize, and identify the work efforts and is summarized in Fig. 1-1 for the top three project levels. The work breakdown structure itself is intended to be the primary organizational tool of the AVLIS Production Plant and is consistent with the overall AVLIS Program Work Breakdown Structure. It is designed to provide a framework for definition and accounting of all of the elements that are required for the eventual design, procurement, and construction of the AVLIS Production Plant. During the present phase of the AVLIS Project, the conceptual engineering phase, the work breakdown structure is intended to be the master structure and project organizer of documents, designs, and cost estimates. As the master project organizer, the key role of the work breakdown structure is to provide the mechanism for developing completeness in AVLIS cost estimates and design development of all hardware and systems. The work breakdown structure provides the framework for tracking, on a one-to-one basis, the component design criteria, systems requirements, design concepts, design drawings, performance projections, and conceptual cost estimates. It also serves as a vehicle for contract reporting. 12 figures, 2 tables.

  7. AVLIS Production Plant work breakdown structure and Dictionary

    International Nuclear Information System (INIS)

    The work breakdown structure has been prepared for the AVLIS Production Plant to define, organize, and identify the work efforts and is summarized in Fig. 1-1 for the top three project levels. The work breakdown structure itself is intended to be the primary organizational tool of the AVLIS Production Plant and is consistent with the overall AVLIS Program Work Breakdown Structure. It is designed to provide a framework for definition and accounting of all of the elements that are required for the eventual design, procurement, and construction of the AVLIS Production Plant. During the present phase of the AVLIS Project, the conceptual engineering phase, the work breakdown structure is intended to be the master structure and project organizer of documents, designs, and cost estimates. As the master project organizer, the key role of the work breakdown structure is to provide the mechanism for developing completeness in AVLIS cost estimates and design development of all hardware and systems. The work breakdown structure provides the framework for tracking, on a one-to-one basis, the component design criteria, systems requirements, design concepts, design drawings, performance projections, and conceptual cost estimates. It also serves as a vehicle for contract reporting. 12 figures, 2 tables

  8. Crystalline ceramics: Waste forms for the disposal of weapons plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Ewing, R.C.; Lutze, W. [New Mexico Univ., Albuquerque, NM (United States); Weber, W.J. [Pacific Northwest Lab., Richland, WA (United States)

    1995-05-01

    At present, there are three seriously considered options for the disposition of excess weapons plutonium: (i) incorporation, partial burn-up and direct disposal of MOX-fuel; (ii) vitrification with defense waste and disposal as glass ``logs``; (iii) deep borehole disposal (National Academy of Sciences Report, 1994). The first two options provide a safeguard due to the high activity of fission products in the irradiated fuel and the defense waste. The latter option has only been examined in a preliminary manner, and the exact form of the plutonium has not been identified. In this paper, we review the potential for the immobilization of plutonium in highly durable crystalline ceramics apatite, pyrochlore, monazite and zircon. Based on available data, we propose zircon as the preferred crystalline ceramic for the permanent disposition of excess weapons plutonium.

  9. Standard specification for sintered (Uranium-Plutonium) dioxide pellets

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2001-01-01

    1.1 This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. This specification may not completely cover the requirements for pellets fabricated from weapons-derived plutonium. 1.2 This specification does not include (1) provisions for preventing criticality accidents or (2) requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, federal, state, and local regulations pertaining to possessing, processing, shipping, or using source or special nuclear material. Examples of U.S. government documents are Code of Federal Regulations Title 10, Part 50Domestic Licensing of Production and Utilization Facilities; Code of Federal Regulations Title 10, Part 71Packaging and Transportation of Radioactive Material; and Code of Federal Regulations Tit...

  10. Separation of trace elemental impurities from plutonium oxide matrics by solvent extraction

    International Nuclear Information System (INIS)

    Plutonium oxide and uranium oxide are the main products of the PUREX process. Plutonium oxide and uranium oxide are the source materials used in the manufacture of ceramic grade oxide fuels for nuclear reactors. Among the various chemical specifications for plutonium oxide, trace elemental impurities are one of them. Presently, in the PREFRE laboratory, trace elemental assay in PuO2 by ICP-AES is carried out using this Pu-matrix separation method

  11. Recovery of plutonium from electrorefining anode heels at Savannah River

    International Nuclear Information System (INIS)

    In a joint effort, the Savannah River Laboratory (SRL), Savannah River Plant (SRP), and the Rocky Flats Plant (RFP) have developed two processes to recover plutonium from electrorefining anode heel residues. Aqueous dissolution of anode heel metal was demonstrated at SRL on a laboratory scale and on a larger pilot scale using either sulfamic acid or nitric acid-hydrazine-fluoride solutions. This direct anode heel metal dissolution requires the use of a geometrically favorable dissolver. The second process developed involves first diluting the plutonium in the anode heel residues by alloying with aluminum. The alloyed anode heel plutonium can then be dissolved using a nitric acid-fluoride-mercury(II) solution in large non-geometrically favorable equipment where nuclear safety is ensured by concentration control

  12. PREPARATION OF HALIDES OF PLUTONIUM

    Science.gov (United States)

    Garner, C.S.; Johns, I.B.

    1958-09-01

    A dry chemical method is described for preparing plutonium halides, which consists in contacting plutonyl nitrate with dry gaseous HCl or HF at an elevated temperature. The addition to the reaction gas of a small quantity of an oxidizing gas or a reducing gas will cause formation of the tetra- or tri-halide of plutonium as desired.

  13. The economics of plutonium recycle

    International Nuclear Information System (INIS)

    The individual cost components and the total fuel cycle costs for natural uranium and uranium-plutonium mixed oxide fuel cycles for CANDU-PHW reactors are discussed. A calculation is performed to establish the economic conditions under which plutonium recycle would be economically attractive. (auth)

  14. Enhancement of Plant Productivity in the Post-Genomics Era.

    Science.gov (United States)

    Thao, Nguyen Phuong; Tran, Vietnam Lam-Son Phan

    2016-08-01

    Obtaining high plant yield is not always achievable in agricultural activity as it is determined by various factors, including cultivar quality, nutrient and water supplies, degree of infection by pathogens, natural calamities and soil conditions, which affect plant growth and development. More noticeably, sustainable plant productivity to provide sufficient food for the increasing human population has become a thorny issue to scientists in the era of unpredictable global climatic changes, appearance of more tremendous or multiple stresses, and land restriction for cultivation. Well-established agricultural management by agrotechnological means has shown no longer to be effective enough to confront with this challenge. Instead, in order to maximize the production, it is advisable to implement such practices in combination with biological applications. Nowadays, high technologies are widely adopted into agricultural production, biological diversity conservation and crop improvement. Wang et al. has nicely outlined the utilization of DNA-based technologies in this field. Among these are the applications of (i) DNA markers into cultivar identification, seed purity analysis, germplasm resource evaluation, heterosis prediction, genetic mapping, cloning and breeding; and (ii) gene expression data in supporting the description of crop phenology, the analytic comparison of crop growth under stress versus non-stress conditions, or the study of fertilizer effects. Besides, various purposes of using transgenic technologies in agriculture, such as generating cultivars with better product quality, better tolerance to biotic or abiotic stress, are also discussed in the review. One of the important highlights in this issue is the review of the benefits brought by high-throughput sequencing technology, which is also known as next-generation sequencing (NGS). It is not so difficult to recognize that its application has allowed us to carry out biological studies at much deeper level

  15. Non-Convex Costs and Capital Utilization: A Study of Production Scheduling at Automobile Assembly Plants

    OpenAIRE

    Hall, George J.

    1997-01-01

    This paper studies how managers at automobile assembly plants organize production across time. Detailed data from eleven single-source automobile assembly plants display considerable cross-plant heterogeneity. At plants which make low- and medium-selling vehicles the capital stock often sits idle, production is more variable than sales, and week-long shutdowns are often used to vary output. In contrast, at plants which make high-selling vehicles, the capital stock rarely sits idle, production...

  16. Indicators of energy efficiency in ammonia productions plants

    Directory of Open Access Journals (Sweden)

    Flavio V. Tavares

    2013-07-01

    Full Text Available This paper presents and analyzes tools for the assessment of energy efficiency in ammonia production plants using key performance indicators (KPI. Monitoring the consumption of inputs in the industry could generate reductions in greenhouse gas emissions while simultaneously producing gains in energy efficiency in industrial operations. The continuous monitoring of performance indicators relative to emissions data and the consumption of natural resources allows for effective and direct intervention, resulting in improvements in production processes and operating practices. The use of such information by operating teams, in conjunction with management actions focused on continuous improvement, could lead to energy efficiency gains, a reduction in greenhouse gas emissions, and make production processes more profitable.

  17. The Fabrication of Plutonium from Highly Irradiated Reactor Fuel

    International Nuclear Information System (INIS)

    Plutonium that has been separated from highly irradiated, or recycled, reactor fuel contains substantial percentages of 238Pu, 240 Pu, 241Pu and 242Pu. These isotopes and their daughter products are sources of increased gamma and neutron radiation, which affects the costs, the facilities and the techniques of fabricating the plutonium into reactor fuel elements. The commercial application of recycled power-reactor plutonium will depend, to a large extent, upon the ability of the fabricators to process, fabricate and use plutonium derived from highly irradiated fuels economically and safely. Experimental fuel elements are being fabricated at Argonne National Laboratory for a long-range study of the effects on reactor neutronics of various plutonium isotopic compositions that range from nearly pure 239Pu to plutonium that is principally 242Pu. A secondary purpose of this work was to determine the gamma and neutron rates of radiation dosage to personnel and to gain practical experience during the fabrication of typical compositions of plutonium from power reactors. The first step in this study was to develop a computer programme for calculating the rates of radiation dosage to personnel encountered during the fabrication of plutonium metal fuel elements of any isotopic composition versus time after fabrication. The effects of mass, geometry, shield composition and thickness, and time of operator exposure may be factored into the programme and the total operator radiation exposure predicted. The second stage was to compare the calculated exposures with measured radiation exposures during the fabrication of plutonium metal and oxide fuel elements containing 10, 30 and 50% of the higher plutonium isotopes. The fabrication of 2-kg batches of plutonium was accomplished unshielded gloveboxes with lightly leaded gloves. Glove-hand contact with the plutonium was avoided, and the operator time spent at the glovebox face was limited. The weekly exposure of each operator to

  18. Plant compounds insecticide activity against Coleoptera pests of stored products

    Energy Technology Data Exchange (ETDEWEB)

    Moreira, Marcio Dionizio; Picanco, Marcelo Coutinho; Guedes, Raul Narciso Carvalho; Campos, Mateus Ribeiro de; Silva, Gerson Adriano; Martins, Julio Claudio [Universidade Federal de Vicosa (UFV), MG (Brazil). Dept. de Biologia Animal]. E-mail: marcio.dionizio@gmail.com; picanco@ufv.br; guedes@ufv.br; mateusc3@yahoo.com.br; agronomiasilva@yahoo.com.br

    2007-07-15

    The objective of this work was to screen plants with insecticide activity, in order to isolate, identify and assess the bioactivity of insecticide compounds present in these plants, against Coleoptera pests of stored products: Oryzaephilus surinamensis L. (Silvanidae), Rhyzopertha dominica F. (Bostrichidae) and Sitophilus zeamais Mots. (Curculionidae). The plant species used were: basil (Ocimum selloi Benth.), rue (Ruta graveolens L.), lion's ear (Leonotis nepetifolia (L.) R.Br.), jimson weed (Datura stramonium L.), baleeira herb (Cordia verbenacea L.), mint (Mentha piperita L.), wild balsam apple (Mormodica charantia L.), and billy goat weed or mentrasto (Ageratum conyzoides L.). The insecticide activity of hexane and ethanol extracts from those plants on R. dominica was evaluated. Among them, only hexane extract of A. conyzoides showed insecticide activity; the hexane extract of this species was successively fractionated by silica gel column chromatography, for isolation and purification of the active compounds. Compounds 5,6,7,8,3',4',5'-heptamethoxyflavone; 5,6,7,8,3'-pentamethoxy-4',5'-methilenedioxyflavone and coumarin were identified. However, only coumarin showed insecticide activity against three insect pests (LD{sub 50} from 2.72 to 39.71 mg g{sup -1} a.i.). The increasing order of insects susceptibility to coumarin was R. dominica, S. zeamais and O. surinamensis. (author)

  19. Arco to enter European PGE production with new Rotterdam plant

    International Nuclear Information System (INIS)

    Arco Chemical (Newtown Square, PA) will enter production of propylene glycol ethers (PGEs) in Europe by building a 70,000-m.t./year plant at its Rotterdam site. Arco's board has approved the project, with construction to begin this year and completion expected in mid-1995. 'This new plant supports the company's long-standing strategy to increase its downstream integration in value-added derivatives of propylene oxide,' says Jack Oppasser, president of Arco Chemical Europe (Maidenhead, U.K.). 'It allows the company to sustain its strong position in the growing European glycol ether market.' Arco's move represents a challenge to Dow Europe (Horgen, Switzerland), which dominates the European PGE market. Dow is Europe's biggest producer of PGEs, with its Dowanol brands commanding a share greater than 50% of the estimated 90,000-m.t./year methyl-based PGE market. This was recently boosted by completion of the expansion of its plant at Stade, Germany, from 60,000 m.t./year to 110,000 m.t./year. While Arco does not currently make PGEs in Europe, it is the second-largest supplier, with about 15,000 m.t.-20,000 m.t./year, via 'third-party manufacturing arrangements' with European producers, including BP Chemicals, and imports from its 90-million lbs/year plant at Bayport, TX. However, Arco refuses to comment on this because of 'antitrust aspects.'

  20. Subchronic inhalation of carbon tetrachloride alters the tissue retention of acutely inhaled plutonium-239 nitrate in F344 rats and syrian golden hamsters

    International Nuclear Information System (INIS)

    Carbon tetrachloride (CCl4) has been used extensively in the nuclear weapons industry, so it is likely that nuclear plant workers have been exposed to both CCl4 and plutonium compounds. Future exposures may occur during open-quotes cleanupclose quotes operations at weapons productions sites such as the Hanford, Washington, and Rocky Flats, Colorado, facilities. Inhalation of 20 and 100 ppm CCl4 by hamsters reduces uptake of 239Pu solubilized from lung, shunting the 239Pu to the skeleton

  1. Algorithm of actions to identify and reduce risks in the production of milk and plant products

    Directory of Open Access Journals (Sweden)

    L. E. Glagoleva

    2016-01-01

    Full Text Available Foods with a new generation of functional and improved consumer properties, corresponds to the modern concepts of nutrition science and consumer needs. functional food production is a major global trend in food science and the subject of innovation. One of the important trends is the use of plant complexes and plant food systems. Using the plant complexes (PC and plant food systems (PFS provides a number of benefits: improved consumer properties of the product, do not need to change the process, it is possible to control directional rheological properties and consistency of the finished products, reduced the number of risk points in the production cycle. This paper describes the development of an algorithm of action to identify and mitigate risks in the production of milk and plant products. Also conducted a risk analysis, identified and assessed the risks in the process of production, installed capacity of available resources to reduce the level of risk. Established and submitted to the critical control points in production processes, as well as the critical limits for each critical control points, and the procedure for corrective action in case of violations of the past. During the study, measured changes in the quantitative and qualitative composition of microflora of semi-finished and Quantity of Mesophilic Aerobic and Facultative Anaerobic Microorganisms (QMAFAnM. To determine QMAFAnM samples were taken: 1 – cheesecakes (control, 2 – cheesecakes with RPS. Microbiological studies analyzed frozen-conjugated semi-finished products was determined within 90 days. It is clear from the data that the cottage cheese with semi-finished products have a lower RPM 11.7%. Analyzing the data, it is possible to conclude that the physico-chemical, organoleptic and microbiological indicators of products was developed to set standards on cheese semi-finished products. multilevel structure that characterizes the quality indicators has been developed and is

  2. Characterizing surplus US plutonium for disposition

    Energy Technology Data Exchange (ETDEWEB)

    Allender, Jeffrey S.; Moore, Edwin N.

    2013-02-26

    The United States (US) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition (OFMD) of the National Nuclear Security Administration (NNSA) and the DOE Office of Environmental Management (DOE-EM). SRNL manages a broad program of item tracking through process history, laboratory analysis, and non-destructive assay. A combination of analytical techniques allows SRNL to predict the isotopic and chemical properties that qualify materials for disposition through the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The research also defines properties that are important for other disposition paths, including disposal to the Waste Isolation Pilot Plant (WIPP) as transuranic waste (TRUW) or to high-level waste (HLW) systems.

  3. Genetical Studies On Haploid Production In Some Ornamental Plants

    International Nuclear Information System (INIS)

    Haploid are plants with a gametophytic chromosome number and doubled haploid are dihaploids that have undergone chromosome duplication. The production of haploid and doubled haploid (DHs) through gametic embryogenesis allows a single-step development of complete homozygous lines from heterozygous parents, shortening the time required to produce homozygous plants in comparison with the conventional breeding methods that employ several generations of selfing. The production of haploid and DHs provides a particularly attractive biotechnological tool, and the development of haploidy technology and protocols to produce homozygous plants has had a significant impact on agricultural systems. Nowadays, these bio technologies represent an integral part of the breeding programmes of many agronomically important crops. There are several available methods to obtain haploid and DHs, of which in vitro anther or isolated microspore culture are the most effective and widely used (Germana Maria 2011). Tissue culture techniques, particularly short-term culture procedures such as shoot-tip culture and regeneration from primary explants, have been proposed as methods for obtaining large numbers of plants identical to the plant used as an explant source( Evans et al., 1984). Nicotiana spp. are one of the most important commercial crops in the world ( Liu and Zhang, 2008). Nicotiana alata is member from family solanacea, it is ornamental plant and the diploid cells contains 18 chromosomes. Nitsch (1969) reported the first production of haploid plants through anther culture and regeneration of plants of Nicotiana alata, For these reasons they have been considered to suitable candidates for model species in somatic cell genetics research( Bourgin et al., 1979). Radiobiological studies on plant tissues in culture may provide information on the cell growth behavior, radiosensitivity and the induction of mutations. The radiosensitivity of plants and calli can be manifested mostly in three

  4. Operation of plant to produce Mo-99 from fission products

    International Nuclear Information System (INIS)

    As it is well known, the production of Mo-99/Tc-99m generators has an outstanding place in radioisotope programs of the Argentine National Atomic Energy Commission. The basic raw material is Mo-99 from fission of U-235. In 1985 the production plant of this radionuclide began to operate, according to an adaptation of the method that was developed in Kernforschungszentrum Karlsruhe. The present work describes the target irradiation conditions in the reactor RA-3 (mini plates of U/Al alloy with 90% enriched uranium), the flow diagram and the operative conditions of the production process. The containment, filtration and removal conditions of the generated fission gases and the disposal of liquid and solid wastes are also analyzed. On the basis of the experience achieved in the development of more than twenty production processes, process efficiency is analyzed, taking into account the theoretical evaluation resulting from the application of the computer program 'Origin'(ORML) to the conditions of our case. The purity characteristics of the final product are reported (Zr-95 0,1 ppm; Nb-95 1 ppm; Ru-103 20 ppm; I-131 10 ppm) as well as the chemical characteristics that make it suitable to be used in the production of Mo-99/I c-99m generators. (Author)

  5. PLANT PROTECTION PRODUCT RESIDUES IN AGRICULTURAL PRODUCTS OF SLOVENE ORIGIN FOUND IN 2008

    Directory of Open Access Journals (Sweden)

    Helena BAŠA ČESNIK

    2012-01-01

    Full Text Available In the year 2008, 166 apple, bean, carrot, cucumber, lettuce, pear, potato and spinach samples from Slovene producers were analysed for plant protection product residues. The samples were analysed for the presence of 158 different active compounds using three analytical methods. In two samples (1.2% exceeded maximum residue levels (MRLs were determined which is better than the results of the monitoring of pesticide residues in the products of plant origin in the 27 European Union, Member States (EU MS and 2 European Free Trade Association (EFTA States: Norway and Iceland in 2008 (2.2%. The most frequently found active substance in agricultural products was dithiocarbamates. Products which contained 4 or more active substances per sample were apples and pears.

  6. Plant ecology. Worldwide evidence of a unimodal relationship between productivity and plant species richness.

    Science.gov (United States)

    Fraser, Lauchlan H; Pither, Jason; Jentsch, Anke; Sternberg, Marcelo; Zobel, Martin; Askarizadeh, Diana; Bartha, Sandor; Beierkuhnlein, Carl; Bennett, Jonathan A; Bittel, Alex; Boldgiv, Bazartseren; Boldrini, Ilsi I; Bork, Edward; Brown, Leslie; Cabido, Marcelo; Cahill, James; Carlyle, Cameron N; Campetella, Giandiego; Chelli, Stefano; Cohen, Ofer; Csergo, Anna-Maria; Díaz, Sandra; Enrico, Lucas; Ensing, David; Fidelis, Alessandra; Fridley, Jason D; Foster, Bryan; Garris, Heath; Goheen, Jacob R; Henry, Hugh A L; Hohn, Maria; Jouri, Mohammad Hassan; Klironomos, John; Koorem, Kadri; Lawrence-Lodge, Rachael; Long, Ruijun; Manning, Pete; Mitchell, Randall; Moora, Mari; Müller, Sandra C; Nabinger, Carlos; Naseri, Kamal; Overbeck, Gerhard E; Palmer, Todd M; Parsons, Sheena; Pesek, Mari; Pillar, Valério D; Pringle, Robert M; Roccaforte, Kathy; Schmidt, Amanda; Shang, Zhanhuan; Stahlmann, Reinhold; Stotz, Gisela C; Sugiyama, Shu-ichi; Szentes, Szilárd; Thompson, Don; Tungalag, Radnaakhand; Undrakhbold, Sainbileg; van Rooyen, Margaretha; Wellstein, Camilla; Wilson, J Bastow; Zupo, Talita

    2015-07-17

    The search for predictions of species diversity across environmental gradients has challenged ecologists for decades. The humped-back model (HBM) suggests that plant diversity peaks at intermediate productivity; at low productivity few species can tolerate the environmental stresses, and at high productivity a few highly competitive species dominate. Over time the HBM has become increasingly controversial, and recent studies claim to have refuted it. Here, by using data from coordinated surveys conducted throughout grasslands worldwide and comprising a wide range of site productivities, we provide evidence in support of the HBM pattern at both global and regional extents. The relationships described here provide a foundation for further research into the local, landscape, and historical factors that maintain biodiversity.

  7. Plant ecology. Worldwide evidence of a unimodal relationship between productivity and plant species richness.

    Science.gov (United States)

    Fraser, Lauchlan H; Pither, Jason; Jentsch, Anke; Sternberg, Marcelo; Zobel, Martin; Askarizadeh, Diana; Bartha, Sandor; Beierkuhnlein, Carl; Bennett, Jonathan A; Bittel, Alex; Boldgiv, Bazartseren; Boldrini, Ilsi I; Bork, Edward; Brown, Leslie; Cabido, Marcelo; Cahill, James; Carlyle, Cameron N; Campetella, Giandiego; Chelli, Stefano; Cohen, Ofer; Csergo, Anna-Maria; Díaz, Sandra; Enrico, Lucas; Ensing, David; Fidelis, Alessandra; Fridley, Jason D; Foster, Bryan; Garris, Heath; Goheen, Jacob R; Henry, Hugh A L; Hohn, Maria; Jouri, Mohammad Hassan; Klironomos, John; Koorem, Kadri; Lawrence-Lodge, Rachael; Long, Ruijun; Manning, Pete; Mitchell, Randall; Moora, Mari; Müller, Sandra C; Nabinger, Carlos; Naseri, Kamal; Overbeck, Gerhard E; Palmer, Todd M; Parsons, Sheena; Pesek, Mari; Pillar, Valério D; Pringle, Robert M; Roccaforte, Kathy; Schmidt, Amanda; Shang, Zhanhuan; Stahlmann, Reinhold; Stotz, Gisela C; Sugiyama, Shu-ichi; Szentes, Szilárd; Thompson, Don; Tungalag, Radnaakhand; Undrakhbold, Sainbileg; van Rooyen, Margaretha; Wellstein, Camilla; Wilson, J Bastow; Zupo, Talita

    2015-07-17

    The search for predictions of species diversity across environmental gradients has challenged ecologists for decades. The humped-back model (HBM) suggests that plant diversity peaks at intermediate productivity; at low productivity few species can tolerate the environmental stresses, and at high productivity a few highly competitive species dominate. Over time the HBM has become increasingly controversial, and recent studies claim to have refuted it. Here, by using data from coordinated surveys conducted throughout grasslands worldwide and comprising a wide range of site productivities, we provide evidence in support of the HBM pattern at both global and regional extents. The relationships described here provide a foundation for further research into the local, landscape, and historical factors that maintain biodiversity. PMID:26185249

  8. Disturbance of deposition and removal of plutonium

    International Nuclear Information System (INIS)

    The chelation therapy using DTPA (diethylenetriaminepentaacetic acid) and a new drug, CBMIDA [catechol 3, 6-bis (methyleiminodiacetic acid)] showing more effectiveness on removal of plutonium and lower toxicity than DTPA, is available for occupational exposure but is difficult for public exposure, because there are many reluctant problems on their toxicities, administration routes and times, physical conditions of victims etc. We demonstrated that active amino acid calcium (AAACa), a natural product which mixed oyster shell electrolysate and amino acids of seaweeds, could remove plutonium from bone and liver in rats. The removing methods of radionuclides using the bioavailability of AAACa will be utilized for public exposures and resolve the reluctant problems accompanied with a chelation therapy for occupational exposure. (author)

  9. a Plutonium Ceramic Target for Masha

    Science.gov (United States)

    Wilk, P. A.; Shaughnessy, D. A.; Moody, K. J.; Kenneally, J. M.; Wild, J. F.; Stoyer, M. A.; Patin, J. B.; Lougheed, R. W.; Ebbinghaus, B. B.; Landingham, R. L.; Oganessian, Yu. Ts.; Yeremin, A. V.; Dmitriev, S. N.

    2005-09-01

    We are currently developing a plutonium ceramic target for the MASHA mass separator. The MASHA separator will use a thick plutonium ceramic target capable of tolerating temperatures up to 2000 °C. Promising candidates for the target include oxides and carbides, although more research into their thermodynamic properties will be required. Reaction products will diffuse out of the target into an ion source, where they will then be transported through the separator to a position-sensitive focal-plane detector array. Experiments on MASHA will allow us to make measurements that will cement our identification of element 114 and provide for future experiments where the chemical properties of the heaviest elements are studied.

  10. Thermal and Physical Properties of Plutonium Dioxide Produced from the Oxidation of Metal: a Data Summary

    Energy Technology Data Exchange (ETDEWEB)

    Wayne, David M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-01-13

    The ARIES Program at the Los Alamos National Laboratory removes plutonium metal from decommissioned nuclear weapons, and converts it to plutonium dioxide in a specially-designed Direct Metal Oxidation furnace. The plutonium dioxide is analyzed for specific surface area, particle size distribution, and moisture content. The purpose of these analyses is to certify that the plutonium dioxide powder meets or exceeds the specifications of the end-user, and the specifications for the packaging and transport of nuclear materials. Analytical results from plutonium dioxide from ARIES development activities, from ARIES production activities, from muffle furnace oxidation of metal, and from metal that was oxidized over a lengthy time interval in air at room temperature, are presented. The processes studied produce plutonium dioxide powder with distinct differences in measured properties, indicating the significant influence of oxidation conditions on physical properties.

  11. Thermal and Physical Properties of Plutonium Dioxide Produced from the Oxidation of Metal: a Data Summary

    International Nuclear Information System (INIS)

    The ARIES Program at the Los Alamos National Laboratory removes plutonium metal from decommissioned nuclear weapons, and converts it to plutonium dioxide in a specially-designed Direct Metal Oxidation furnace. The plutonium dioxide is analyzed for specific surface area, particle size distribution, and moisture content. The purpose of these analyses is to certify that the plutonium dioxide powder meets or exceeds the specifications of the end-user, and the specifications for the packaging and transport of nuclear materials. Analytical results from plutonium dioxide from ARIES development activities, from ARIES production activities, from muffle furnace oxidation of metal, and from metal that was oxidized over a lengthy time interval in air at room temperature, are presented. The processes studied produce plutonium dioxide powder with distinct differences in measured properties, indicating the significant influence of oxidation conditions on physical properties.

  12. Uranium production as byproduct from Yarimca (Turkey) phosphoric acid plant

    International Nuclear Information System (INIS)

    Full text: This paper deals with uranium production from the phosphoric acid products of Yarimca Fertilizer Plant. After examination of the phosphate rocks consumed in this plant and the acid products, solvent extraction tests were conducted to determine the effects of acid concentration, solvent concentration in kerosene, contact time and acid solvent ratio on the recoveries of uranium. 98 percent of total uranium in acid was recovered in the organic phase by applying 5 stage extraction. Following the extraction tests, acidic and basic stripping were applied to organic phase and uranium was precipitated as yellow cake from the stripping solutions. In the stripping tests mainly aqueous and organic phase ratio and the stripping time were investigated using HCl and Na2CO3 as stripping agents. Na2CO3 has provided higher uranium recoveries both at the short time and low ratio of the stripping solution. Yellow cakes were produced containing 13-18.4 percent U3o8 from acidic and 30-46.4 percent U3O8 from basic stripping solutions

  13. Solar enriched methane production: Assessment of plant potentialities and applications

    Directory of Open Access Journals (Sweden)

    Vincenzo Piemonte

    2010-04-01

    Full Text Available The crucial environmental issue due to fossil fuel use in our society and industries and more and more perceived by the communities is stimulating the development of innovative technologies with the scope of reducing GHGs and pollutants emissions, improving plants efficiency and exploiting renewable energy sources. The idea proposed in the present work links this context: a novel hybrid plant for the production of a mixture of methane and hydrogen (20%vol, called enriched-methane, from a steam reforming reactor whose heat duty is supplied by a concentrating solar power (CSP plant by means of a molten salt stream is here conceived, modelled and assessed. The enriched-methane mixture can be applied in methane internal combustion engines (ICE reducing CO, CO2, unburned emissions and improving engine efficiency. Moreover, the residual sensible heat of solar-heated molten salt stream can be used to generate medium-pressure steam and to produce electricity by a steam-turbine. Therefore, the plant proposed is co-generative, producing both hydrogen and electricity from a solar source. The behaviour of methane steam reforming reactor is simulated by means of a 2D mathematical model and the design of a cogenerative solar plant is proposed, evaluating its potentialities in terms of MWh of electricity produced and number of vehicles fed by enriched-methane. A single CSP module (surface requirement = 1.5 hectares coupled with a 4-tubes-and-shell shaped reactor is able to produce 686 tons/year of hydrogen, equivalent to 3.430 tons/year of 20%vol H2-CH4 mixture and 3.097 MWh/year of clean electricity.

  14. Conceptual Design for the Pilot-Scale Plutonium Oxide Processing Unit in the Radiochemical Processing Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Lumetta, Gregg J.; Meier, David E.; Tingey, Joel M.; Casella, Amanda J.; Delegard, Calvin H.; Edwards, Matthew K.; Jones, Susan A.; Rapko, Brian M.

    2014-08-05

    This report describes a conceptual design for a pilot-scale capability to produce plutonium oxide for use as exercise and reference materials, and for use in identifying and validating nuclear forensics signatures associated with plutonium production. This capability is referred to as the Pilot-scale Plutonium oxide Processing Unit (P3U), and it will be located in the Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory. The key unit operations are described, including plutonium dioxide (PuO2) dissolution, purification of the Pu by ion exchange, precipitation, and conversion to oxide by calcination.

  15. Measuring NO Production by Plant Tissues and Suspension Cultured Cells

    Institute of Scientific and Technical Information of China (English)

    Jan Vitecek; Vilem Reinohl; Russell L.Jones

    2008-01-01

    We describe an inexpensive and reliable detector for measuring NO emitted in the gas phase from plants.The method relies on the use of a strong oxidizer to convert NO to NO2 and subsequent capture of NO2 by a Griess reagent trap.The set-up approaches the sensitivity for NO comparable to that of instruments based on chemiluminescence and photoacoustic detectors.We demonstrate the utility of our set-up by measuring NO produced by a variety of well established plant sources.NO produced by nitrate reductase (NR) in tobacco leaves and barley aleurone was readily detected,as was the production of NO from nitrite by the incubation medium of barley aleurone.Arabidopsis mutants that overproduce NO or lack NO-synthase (AtNOS1) also displayed the expected NO synthesis phenotype when assayed by our set-up.We could also measure NO production from elicitor-treated suspension cultured cells using this set-up.Further,we have focused on the detection of NO by a widely used fluorescent probe 4-amino-5-methylamino-2',7'-difluorofluorescein (DAF-FM).Our work points to the pitfalls that must be avoided when using DAF-FM to detect the production of NO by plant tissues.In addition to the dramatic effects that pH can have on fluorescence from DAF-FM,the widely used NO scavengers 2-phenyl-4,4,5,5-tetramethylimidazoline-l-oxyl-3-oxide (PTIO) and 2-(4-carboxyphenyl)-4,4,5,5-tetramethylimidazoline-1-oxyl-3-oxide (cPTIO) can produce anomalous and unexpected results.Perhaps the most serious drawback of DAF-FM is its ability to bind to dead cells and remain NO-sensitive.

  16. A system for automated, dismantlement of plutonium weapons components

    International Nuclear Information System (INIS)

    The development of advanced dismantlement technologies will play an integral part on the changing role of the DOE. As an important component to this effort, the ARIES (Automated Retirement and Integrated Extraction System) System is designed to provide a test bed for the development of technology for the dismantlement of the primaries of nuclear weapons (pits). The ARIES system will integrate and automate the processes of pit disassembly, plutonium, plutonium removal, preparation of oxide from plutonium metal, decontamination of non-plutonium parts, and in-line measurement of the products and wastes by state-of-the-art non-destructive assay (NDA) methods. No integrated method now exists for the dismantlement and recovery of nuclear material from many weapons designs. Even those assemblies for which recovery techniques have been established require extensive manual handling (with associated personnel exposure to radiation) and result in considerable waste generation during dismantlement. The disposition of excess plutonium will require a facility to disassemble and remove plutonium from the pits. ARIES will provide the methods to satisfy this goal while at the same time reducing waste generation, lowering personnel radiation exposures, and operating to the highest standards of safety and security. A description of the ARIES system is given

  17. Advanced Multi-Product Coal Utilization By-Product Processing Plant

    Energy Technology Data Exchange (ETDEWEB)

    John Groppo; Thomas Robl

    2006-09-30

    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 an investigation of the secondary classification characteristics of the ash feedstock excavated from the lower ash pond at Ghent Station.

  18. Integration of oxygen membranes for oxygen production in cement plants

    DEFF Research Database (Denmark)

    Puig Arnavat, Maria; Søgaard, Martin; Hjuler, Klaus;

    2015-01-01

    a concentrated CO2 source that can be used for enhanced oil recovery, in combination with biomass gasification and electrolysis for synthesis gas production, or possibly sequestered. The cases with oxygen enriched air provide very promising economic figures of merit with discounted payback periods slightly......The present paper describes the integration of oxygen membranes in cement plants both from an energy, exergy and economic point of view. Different configurations for oxygen enrichment of the tertiary air for combustion in the pre-calciner and full oxy-fuel combustion in both pre-calciner and kiln...

  19. Functional-structural plant modelling in crop production

    OpenAIRE

    VOS, J; Marcelis, L.F.M.; de Visser; Struik, P.C.; Evers, J.B.

    2007-01-01

    Functional-structural plant models (FSPMs) describe in quantitative terms the development over time of the three-dimensional (3D) structure of plants as governed by physiological processes and affected by environmental factors. FSPMs are particularly suited to analyse problems in which the spatial structure of the plant or its canopy is an essential factor to explain, e.g., plant competition (intra-plant, inter-plant, inter-species) and the effects of plant configuration and plant manipulatio...

  20. Degrading the Plutonium Produced in Fast Breeder Reactor Blankets

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Jor-Shan; Kuno, Yusuke [Tokyo University, 7-3-1, Hongo, Bunkyo-ku, Tokyo, 113-8656 (Japan)

    2009-06-15

    Plutonium quality, defined as the plutonium isotopic composition, is an important measure for proliferation-resistance (PR) of a nuclear energy system. The quality of the plutonium produced in the blanket assemblies of a fast breeder reactor could be as good as or better than the weapons-grade (WG). The presence of such good quality plutonium is a proliferation concern. There are various options to degrade the plutonium produced in the breeder blanket. The obvious one is to blend the blanket plutonium with those produced from the reactor core during reprocessing. Other options try to prevent the generation of good quality plutonium (Pu). The Protected Plutonium Production (P{sup 3}) Project proposed by Tokyo Institute of Technology (TIT)1,2,3 advocates the doping of certain amount of neptunium (Np), or americium (Am) in fresh blanket fuel for irradiation. The increased production of {sup 238}Pu, {sup 240}Pu and {sup 242}Pu by neutron capture in {sup 237}Np and Am would degrade the blanket plutonium. However, as {sup 237}Np is a controlled material according to IAEA, its use as doping material in fresh blanket fuel presents a concern for nuclear proliferation. In addition, the fabrication of fresh blanket fuel with inclusion of americium would be complicated due to the emission of intense low-energy gamma radiation from {sup 241}Am. Am is normally accompanied by Cm since the separation of those 2 elements is very difficult. Fuel containing both Am and Cm may make Safeguards measurement difficult. A variation would be doping the fresh blanket fuel with minor actinide (e.g., a group of neptunium, americium, and curium), or with separated reactor-grade (RG) plutonium. The drawback of such schemes would be the need for glove boxes in fresh blanket fuel fabrication. It is possible to fuel the breeder blankets with recycled (reprocessed) uranium oxide. The recycled uranium, recovered from reprocessing, contains {sup 236}U, which when irradiated in the blanket would

  1. Integrated development and testing plan for the plutonium immobilization project

    International Nuclear Information System (INIS)

    This integrated plan for the DOE Office of Fissile Materials Disposition (MD) describes the technology development and major project activities necessary to support the deployment of the immobilization approach for disposition of surplus weapons-usable plutonium. The plan describes details of the development and testing (D and T) tasks needed to provide technical data for design and operation of a plutonium immobilization plant based on the ceramic can-in-canister technology (''Immobilization Fissile Material Disposition Program Final Immobilization Form Assessment and Recommendation'', UCRL-ID-128705, October 3, 1997). The plan also presents tasks for characterization and performance testing of the immobilization form to support a repository licensing application and to develop the basis for repository acceptance of the plutonium form. Essential elements of the plant project (design, construction, facility activation, etc.) are described, but not developed in detail, to indicate how the D and T results tie into the overall plant project. Given the importance of repository acceptance, specific activities to be conducted by the Office of Civilian Radioactive Waste Management (RW) to incorporate the plutonium form in the repository licensing application are provided in this document, together with a summary of how immobilization D and T activities provide input to the license activity. The ultimate goal of the Immobilization Project is to develop, construct, and operate facilities that will immobilize from about 18 to 50 tonnes (MT) of U.S. surplus weapons usable plutonium materials in a manner that meets the ''spent fuel'' standard (Fissile Materials Storage and Disposition Programmatic Environmental Impact Statement Record of Decision, ''Storage and Disposition Final PEIS'', issued January 14, 1997, 62 Federal Register 3014) and is acceptable for disposal in a geologic repository. In the can-in-canister technology, this is accomplished by encapsulating the

  2. Plant layout and pick-and-place strategies for improving performances in secondary packaging plants of food products

    OpenAIRE

    GAY, PAOLO; Belforte, Gustavo

    2013-01-01

    The aim of secondary packaging plants is to pick food products from a conveyor belt and to place them into boxes. The typical configuration of these packaging plants consists of a set of sequential robot stations, performing pick and place cycles from one conveyor to another parallel one, which transport the products and the boxes to be filled. Depending on the relative movement of the two conveyors, the plant operates in co-current or counter-current flow configuration. Undesired perturbatio...

  3. Plant-microbe interactions: Plant hormone production by phylloplane fungi. Research report

    Energy Technology Data Exchange (ETDEWEB)

    Tuomi, T.; Ilvesoksa, J.; Rosenqvist, H.

    1993-06-23

    The molds Botrytis cinerea, Cladosporium cladosporioides and the yeast Aureobasidium pullulans, isolated from the leaves of three short-rotation Salix clones, were found to produce indole-3-acetic acid (a growth promoter of plants). Abscisic acid (a growth inhibitor of plants) production was detected in B. cinerea. The contents of indole-3-acetic acid and abscisic acid in the leaves of the Salix clones and the amounts of fungal propagules in these leaves were also measured, in order to evaluate whether the amounts of plant growth regulators produced by the fungi would make a significant contribution to the hormonal quantities of the leaves. The content of abscisic acid, and to a lesser degree that of indole-3-acetic acid, showed a positive correlation with the frequency of infection by the hormone producing organisms. The amounts of hormone producing fungi on leaves that bore visible colonies were, however, not sufficiently high to support the argument that neither the fungal production of abscisic nor indole-3-acetic acid would to a significant degree contribute to the hormonal contents of the leaves of the Salix clones.

  4. In plant activation: an inducible, hyperexpression platform for recombinant protein production in plants.

    Science.gov (United States)

    Dugdale, Benjamin; Mortimer, Cara L; Kato, Maiko; James, Tess A; Harding, Robert M; Dale, James L

    2013-07-01

    In this study, we describe a novel protein production platform that provides both activation and amplification of transgene expression in planta. The In Plant Activation (INPACT) system is based on the replication machinery of tobacco yellow dwarf mastrevirus (TYDV) and is essentially transient gene expression from a stably transformed plant, thus combining the advantages of both means of expression. The INPACT cassette is uniquely arranged such that the gene of interest is split and only reconstituted in the presence of the TYDV-encoded Rep/RepA proteins. Rep/RepA expression is placed under the control of the AlcA:AlcR gene switch, which is responsive to trace levels of ethanol. Transgenic tobacco (Nicotiana tabacum cv Samsun) plants containing an INPACT cassette encoding the β-glucuronidase (GUS) reporter had negligible background expression but accumulated very high GUS levels (up to 10% total soluble protein) throughout the plant, within 3 d of a 1% ethanol application. The GUS reporter was replaced with a gene encoding a lethal ribonuclease, barnase, demonstrating that the INPACT system provides exquisite control of transgene expression and can be adapted to potentially toxic or inhibitory compounds. The INPACT gene expression platform is scalable, not host-limited, and has been used to express both a therapeutic and an industrial protein.

  5. Recovery of plutonium by pyroredox processing

    International Nuclear Information System (INIS)

    Using pyrochemical oxidation and reduction, we have developed a process to recover the plutonium in impure scrap with less than 95% plutonium. This plutonium metal was further purified by pyrochemical electrorefining. During development of the procedures, depleted electrorefining anodes were processed, and over 80% of the plutonium was recovered as high-purity metal in one electrorefining cycle. Over 40 kg of plutonium has been recovered from 55 kg of impure anodes with our procedures. 6 refs., 7 figs., 4 tabs

  6. INNOVATIVE FRESH WATER PRODUCTION PROCESS FOR FOSSIL FUEL PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    James F. Klausner; Renwei Mei; Yi Li; Mohamed Darwish; Diego Acevedo; Jessica Knight

    2003-09-01

    This report describes the annual progress made in the development and analysis of a Diffusion Driven Desalination (DDD) system, which is powered by the waste heat from low pressure condensing steam in power plants. The desalination is driven by water vapor saturating dry air flowing through a diffusion tower. Liquid water is condensed out of the air/vapor mixture in a direct contact condenser. A thermodynamic analysis demonstrates that the DDD process can yield a fresh water production efficiency of 4.5% based on a feed water inlet temperature of only 50 C. An example is discussed in which the DDD process utilizes waste heat from a 100 MW steam power plant to produce 1.51 million gallons of fresh water per day. The main focus of the initial development of the desalination process has been on the diffusion tower. A detailed mathematical model for the diffusion tower has been described, and its numerical implementation has been used to characterize its performance and provide guidance for design. The analysis has been used to design a laboratory scale diffusion tower, which has been thoroughly instrumented to allow detailed measurements of heat and mass transfer coefficient, as well as fresh water production efficiency. The experimental facility has been described in detail.

  7. Low temperature oxidation of plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, Art J. [Lawrence Livermore National Laboratory, Livermore, California 94551 (United States); Roussel, Paul [AWE, Aldermaston, Reading, Berkshire, RG7 4PR (United Kingdom)

    2013-05-15

    The initial oxidation of gallium stabilized {delta}-plutonium metal at 193 K has been followed using x-ray photoelectron spectroscopy. On exposure to Langmuir quantities of oxygen, plutonium rapidly forms a trivalent oxide followed by a tetravalent plutonium oxide. The growth modes of both oxides have been determined. Warming the sample in vacuum, the tetravalent oxide reduces to the trivalent oxide. The kinetics of this reduction reaction have followed and the activation energy has been determined to be 38.8 kJ mol{sup -1}.

  8. Low temperature oxidation of plutonium

    International Nuclear Information System (INIS)

    The initial oxidation of gallium stabilized δ-plutonium metal at 193 K has been followed using x-ray photoelectron spectroscopy. On exposure to Langmuir quantities of oxygen, plutonium rapidly forms a trivalent oxide followed by a tetravalent plutonium oxide. The growth modes of both oxides have been determined. Warming the sample in vacuum, the tetravalent oxide reduces to the trivalent oxide. The kinetics of this reduction reaction have followed and the activation energy has been determined to be 38.8 kJ mol−1.

  9. Plutonium oxidation states in seawater

    International Nuclear Information System (INIS)

    Studies of the oxidation-state distribution of plutonium in the ocean illustrate the need to characterize seawater by means of the pH, the EH, and quantitative complexation parameters. The parameters are combined in an easy-to-use equation that determines the fractions of the four oxidation states. Similar analyses have been applied to plutonium in other solutions, and the same methods can be applied to seawater. An appendix shows how to estimate and interpret the alpha coefficient for tetravalent plutonium using published information for tetravalent thorium

  10. Microbial Products Trigger Amino Acid Exudation from Plant Roots1

    Science.gov (United States)

    Phillips, Donald A.; Fox, Tama C.; King, Maria D.; Bhuvaneswari, T.V.; Teuber, Larry R.

    2004-01-01

    Plants naturally cycle amino acids across root cell plasma membranes, and any net efflux is termed exudation. The dominant ecological view is that microorganisms and roots passively compete for amino acids in the soil solution, yet the innate capacity of roots to recover amino acids present in ecologically relevant concentrations is unknown. We find that, in the absence of culturable microorganisms, the influx rates of 16 amino acids (each supplied at 2.5 μm) exceed efflux rates by 5% to 545% in roots of alfalfa (Medicago sativa), Medicago truncatula, maize (Zea mays), and wheat (Triticum aestivum). Several microbial products, which are produced by common soil microorganisms such as Pseudomonas bacteria and Fusarium fungi, significantly enhanced the net efflux (i.e. exudation) of amino acids from roots of these four plant species. In alfalfa, treating roots with 200 μm phenazine, 2,4-diacetylphloroglucinol, or zearalenone increased total net efflux of 16 amino acids 200% to 2,600% in 3 h. Data from 15N tests suggest that 2,4-diacetylphloroglucinol blocks amino acid uptake, whereas zearalenone enhances efflux. Thus, amino acid exudation under normal conditions is a phenomenon that probably reflects both active manipulation and passive uptake by microorganisms, as well as diffusion and adsorption to soil, all of which help overcome the innate capacity of plant roots to reabsorb amino acids. The importance of identifying potential enhancers of root exudation lies in understanding that such compounds may represent regulatory linkages between the larger soil food web and the internal carbon metabolism of the plant. PMID:15347793

  11. Pyrochemical conversion of weapon-grade plutonium into plutonium oxide

    International Nuclear Information System (INIS)

    One of the objectives of the French-Russian studies conducted from 1993 to 1996 under the AIDA-MOX 1 program was to define a reference process for converting the weapon-grade plutonium excess (designated W-Pu) into plutonium dioxide for further use as MOX fuel in existing nuclear reactors. Among the different selected options, one is performed in molten alkali chlorides bath at high temperature. Several laboratory-scale tests have permitted to demonstrate the feasibility of this conversion in this medium. The main results described in this paper -conversion yield, plutonium purification beside gallium, americium and other impurities, - tend to confirm that pyrochemical processes could offer potential interests if however the plutonium oxide sinterability is proved in next tests. (authors)

  12. Learning more about plutonium; En savoir plus sur le plutonium

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    This digest brochure explains what plutonium is, where it comes from, how it is used, its recycling into Mox fuel, its half life, historical discovery, its presence in the environment, toxicity and radioactivity. (J.S.)

  13. Modeling and control for closed environment plant production systems

    Science.gov (United States)

    Fleisher, David H.; Ting, K. C.; Janes, H. W. (Principal Investigator)

    2002-01-01

    A computer program was developed to study multiple crop production and control in controlled environment plant production systems. The program simulates crop growth and development under nominal and off-nominal environments. Time-series crop models for wheat (Triticum aestivum), soybean (Glycine max), and white potato (Solanum tuberosum) are integrated with a model-based predictive controller. The controller evaluates and compensates for effects of environmental disturbances on crop production scheduling. The crop models consist of a set of nonlinear polynomial equations, six for each crop, developed using multivariate polynomial regression (MPR). Simulated data from DSSAT crop models, previously modified for crop production in controlled environments with hydroponics under elevated atmospheric carbon dioxide concentration, were used for the MPR fitting. The model-based predictive controller adjusts light intensity, air temperature, and carbon dioxide concentration set points in response to environmental perturbations. Control signals are determined from minimization of a cost function, which is based on the weighted control effort and squared-error between the system response and desired reference signal.

  14. Simulated productivity of one- and two-armed tree planting machines

    OpenAIRE

    Ersson, Back Tomas; Jundén, Linus; Bergsten, Urban; Servin, Martin

    2013-01-01

    To increase mechanized planting, planting machine productivity must increase in order to improve cost-efficiency. To determine if excavators with two crane arms could potentially help to increase planting machine productivity under Nordic clearcut conditions, we modelled one- armed and semi-automated two-armed excavators with one- and two-headed planting devices. Using a recently developed tool for discrete-event simulation, these machine models then mounded and planted seedlings on terrain m...

  15. Pyrochemical processing of plutonium. Technology review report

    International Nuclear Information System (INIS)

    Non-aqueous processes are now in routine use for direct conversion of plutonium oxide to metal, molten salt extraction of americium, and purification of impure metals by electrorefining. These processes are carried out at elevated temperatures in either refractory metal crucibles or magnesium-oxide ceramics in batch-mode operation. Direct oxide reduction is performed in units up to 700 gram PuO2 batch size with molten calcium metal as the reductant and calcium chloride as the reaction flux. Americium metal is removed from plutonium metal by salt extraction with molten magnesium chloride. Electrorefining is used to isolate impurities from molten plutonium by molten salt ion transport in a controlled potential oxidation-reduction cell. Such cells can purify five or more kilograms of impure metal per 5-day electrorefining cycle. The product metal obtained is typically > 99.9% pure, starting from impure feeds. Metal scrap and crucible skulls are recovered by hydriding of the metallic residues and recovered either as impure metal or oxide feeds

  16. Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Stephen Schey

    2009-07-01

    Cooperative Agreement DE-FC07-06ID14788 was executed between the U.S. Department of Energy, Electric Transportation Applications, and Idaho National Laboratory to investigate the economics of producing hydrogen by electrolysis using electricity generated by nuclear power. The work under this agreement is divided into the following four tasks: Task 1 – Produce Data and Analyses Task 2 – Economic Analysis of Large-Scale Alkaline Electrolysis Task 3 – Commercial-Scale Hydrogen Production Task 4 – Disseminate Data and Analyses. Reports exist on the prospect that utility companies may benefit from having the option to produce electricity or produce hydrogen, depending on market conditions for both. This study advances that discussion in the affirmative by providing data and suggesting further areas of study. While some reports have identified issues related to licensing hydrogen plants with nuclear plants, this study provides more specifics and could be a resource guide for further study and clarifications. At the same time, this report identifies other area of risks and uncertainties associated with hydrogen production on this scale. Suggestions for further study in some of these topics, including water availability, are included in the report. The goals and objectives of the original project description have been met. Lack of industry design for proton exchange membrane electrolysis hydrogen production facilities of this magnitude was a roadblock for a significant period. However, recent design breakthroughs have made costing this facility much more accurate. In fact, the new design information on proton exchange membrane electrolyzers scaled to the 1 kg of hydrogen per second electrolyzer reduced the model costs from $500 to $100 million. Task 1 was delayed when the original electrolyzer failed at the end of its economic life. However, additional valuable information was obtained when the new electrolyzer was installed. Products developed during this study

  17. Plutonium's human guinea pigs

    International Nuclear Information System (INIS)

    In 1993, the inquiry of an American journalist, Eileen Welson, has revealed to the general public that in the 1940s and 1950s people were used as human samples to study the effects of radiation, without their knowledge. The shock, occurred in American opinion has led to the creation of an inquiry commission, which keeps revealing new documents. The latter shows the existence of so many hundreds of experiments of this type carried out in a spirit too close to that of the Nazi physicians. Injections of plutonium sub 2 sub 3 sub 8 and sub 2 sub 3 sub 9 or enriched uranium, exposition to radioactive clouds, massive irradiation by x-rays,... etc. those practice have persisted till the 1970s. (author). 22 refs., 10 figs

  18. INNOVATIVE FRESH WATER PRODUCTION PROCESS FOR FOSSIL FUEL PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    James F. Klausner; Renwei Mei; Yi Li; Jessica Knight

    2004-09-01

    An innovative Diffusion Driven Desalination (DDD) process was recently described where evaporation of mineralized water is driven by diffusion within a packed bed. The energy source to drive the process is derived from low pressure condensing steam within the main condenser of a steam power generating plant. Since waste heat is used to drive the process, the main cost of fresh water production is attributed to the energy cost of pumping air and water through the packed bed. This report describes the annual progress made in the development and analysis of a Diffusion Driven Desalination (DDD) system. A combined thermodynamic and dynamic analysis demonstrates that the DDD process can yield a fresh water production of 1.03 million gallon/day by utilizing waste heat from a 100 MW steam power plant based on a condensing steam pressure of only 3'' Hg. Throughout the past year, the main focus of the desalination process has been on the diffusion tower and direct contact condenser. Detailed heat and mass transfer analyses required to size and analyze these heat and mass transfer devices are described. An experimental DDD facility has been fabricated, and temperature and humidity data have been collected over a range of flow and thermal conditions. The analyses agree quite well with the current data and the information available in the literature. Direct contact condensers with and without packing have been investigated. It has been experimentally observed that the fresh water production rate is significantly enhanced when packing is added to the direct contact condensers.

  19. Preliminary safety evaluation for the plutonium stabilization and packaging system

    Energy Technology Data Exchange (ETDEWEB)

    Shapley, J.E., Fluor Daniel Hanford

    1997-03-14

    This Preliminary Safety Evaluation (PSE) describes and analyzes the installation and operation of the Plutonium Stabilization and Packaging System (SPS) at the Plutonium Finishing Plant (PFP). The SPS is a combination of components required to expedite the safe and timely storage of Plutonium (Pu) oxide. The SPS program will receive site Pu packages, process the Pu for storage, package the Pu into metallic containers, and safely store the containers in a specially modified storage vault. The location of the SPS will be in the 2736- ZB building and the storage vaults will be in the 2736-Z building of the PFP, as shown in Figure 1-1. The SPS will produce storage canisters that are larger than those currently used for Pu storage at the PFP. Therefore, the existing storage areas within the PFP secure vaults will require modification. Other modifications will be performed on the 2736-ZB building complex to facilitate the installation and operation of the SPS.

  20. In vitro study of natural plant products against oral bacteria

    Institute of Scientific and Technical Information of China (English)

    Siddiqui R; Siti AsmaH; Tang L; Jie CC; Rosliza AR; Roziawati Y

    2009-01-01

    Objective:To analyze the effect of selected plant product against several bacterial which commonly causes oral infection.It was hope that in future,this product will become the remedy for treatment of oral infection and with the hope that it can substitute antibiotics.Methods:A total of 5 species of oral bacteria from American Type Culture Collection (ATCC)were employed in this study(S.mutans,S.aureus,P.aeruginosa,S.sobri-nus and L.salivarius).Three types of natural plants crude extracts were used (garlic,curry leaves and cloves).Bactericidal and bacteriostatic effects of these herbs were tested.Results:It was shown garlic had an-tibacterial effects on all bacteria.The Minimal Inhibitory Concentration (MIC in g/mL)of garlic towards S. aureus,P.aeruginosa,S.mutans,S.sobrinus and L.salivarius were 0.3,1.8,1.2,0.5 and 1.8,respectively. There was significant difference among the MIC of garlic on tested bacteria.It was more potent toward S.au-reus.The curry leaf solution on the other hand,did not show any zone of inhibition in all bacteria plates but adversely showed enhanced growth of those bacteria.Clove had shown its antibacterial effects on S.aureus and P.aeruginosa.The clove was more potent toward S.aureus with the MIC of 0.45 g/mL.P.aeruginosa was more sensitive to clove compared to garlic.For S.aureus,it was more sensitive to garlic compared to clove. Conclusion:The antibacterial activity of garlic and clove crude extracts shown in our study further confirm these natural plants'potential usage in therapeutic use for oral diseases or infections.This could be the platform for the interested party to do research and development on it and to produce oral health products which are more affordable for lower economic income groups and with fewer side effects as seen in synthetic drug.