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Sample records for west valley uf6 facility

  1. West Valley UF6 Facility. Environmental report and safety evaluation, supplement 1

    International Nuclear Information System (INIS)

    1975-01-01

    Revised pages are provided for the Environmental Report and the Safety Evaluation Report which reflect design changes and more detailed information on the items requested in the USAEC letter to NFS dated September 6, 1974

  2. HEU to LEU Conversion and Blending Facility: UF6 blending alternative to produce LEU UF6 for commercial use

    International Nuclear Information System (INIS)

    1995-09-01

    US DOE is examining options for disposing of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials; the nuclear material will be converted to a form more proliferation- resistant than the original form. Examining options for increasing the proliferation resistance of highly enriched uranium (HEU) is part of this effort. Five technologies for blending HEU will be assessed; blending as UF 6 to produce a UF 6 product for commercial use is one of them. This document provides data to be used in the environmental impact analysis for the UF 6 blending HEU disposition option. Resource needs, employment needs, waste and emissions from plant, hazards, accident scenarios, and intersite transportation are discussed

  3. Scenarios and analytical methods for UF6 releases at NRC-licensed fuel cycle facilities

    International Nuclear Information System (INIS)

    Siman-Tov, M.; Dykstra, J.; Holt, D.D.; Huxtable, W.P.; Just, R.A.; Williams, W.R.

    1984-06-01

    This report identifies and discusses potential scenarios for the accidental release of UF 6 at NRC-licensed UF 6 production and fuel fabrication facilities based on a literature review, site visits, and DOE enrichment plant experience. Analytical tools needed for evaluating source terms for such releases are discussed, and the applicability of existing methods is reviewed. Accident scenarios are discussed under the broad headings of cylinder failures, UF 6 process system failures, nuclear criticality events, and operator errors and are categorized by location, release source, phase of UF 6 prior to release, release flow characteristics, release causes, initiating events, and UF 6 inventory at risk. At least three types of releases are identified for further examination: (1) a release from a liquid-filled cylinder outdoors, (2) a release from a pigtail or cylinder in a steam chest, (3) an indoor release from either (a) a pigtail or liquid-filled cylinder or (b) other indoor source depending on facility design and operating procedures. Indoor release phenomena may be analyzed to determine input terms for a ventilation model by using a time-dependent homogeneous compartment model or a more complex hydrodynamic model if time-dependent, spatial variations in concentrations, temperature, and pressure are important. Analytical tools for modeling directed jets and explosive releases are discussed as well as some of the complex phenomena to be considered in analyzing UF 6 releases both indoors and outdoors

  4. Process for decontamination of surfaces in an facility of natural uranium hexafluoride production (UF6)

    International Nuclear Information System (INIS)

    Almeida, Claudio C. de; Silva, Teresinha M.; Rodrigues, Demerval L.; Carneiro, Janete C.G.G.

    2017-01-01

    The experience acquired in the actions taken during the decontamination process of an IPEN-CNEN / SP Nuclear and Energy Research Institute facility, for the purpose of making the site unrestricted, is reported. The steps of this operation involved: planning, training of facility operators, workplace analysis and radiometric measurements. The facility had several types of equipment from the natural uranium hexafluoride (UF 6 ) production tower and other facility materials. Rules for the transportation of radioactive materials were established, both inside and outside the facility and release of materials and installation

  5. Evaluation of environmental-control technologies for commercial nuclear fuel-conversion (UF6) facilities

    International Nuclear Information System (INIS)

    Perkins, B.L.

    1982-10-01

    At present in the United States, there are two commercial conversion facilities. These facilities process uranium concentrate into UF 6 for shipment to the enrichment facilities. One conversion facility uses a dry hydrofluor process, whereas the other facility uses a process known as the wet solvent extraction-fluorination process. Because of the different processes used in the two plants, waste characteristics, quantities, and treatment practices differ at each facility. Wastes and effluent streams contain impurities found in the concentrate (such as uranium daughters, vanadium, molybdenum, selenium, arsenic, and ammonia) and process chemicals used in the circuit (including fluorine, nitrogen, and hydrogen), as well as small quantities of uranium. Studies of suitable disposal options for the solid wastes and sludges generated at the facilities and the long-term effects of emissions to the ambient environment are needed. 30 figures, 34 tables

  6. Vitrification facility at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    DesCamp, V.A.; McMahon, C.L.

    1996-07-01

    This report is a description of the West Valley Demonstration Project's vitrification facilities from the establishment of the West Valley, NY site as a federal and state cooperative project to the completion of all activities necessary to begin solidification of radioactive waste into glass by vitrification. Topics discussed in this report include the Project's background, high-level radioactive waste consolidation, vitrification process and component testing, facilities design and construction, waste/glass recipe development, integrated facility testing, and readiness activities for radioactive waste processing

  7. West Valley facility spent fuel handling, storage, and shipping experience

    International Nuclear Information System (INIS)

    Bailey, W.J.

    1990-11-01

    The result of a study on handling and shipping experience with spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory (PNL) and was jointly sponsored by the US Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The purpose of the study was to document the experience with handling and shipping of relatively old light-water reactor (LWR) fuel that has been in pool storage at the West Valley facility, which is at the Western New York Nuclear Service Center at West Valley, New York and operated by DOE. A subject of particular interest in the study was the behavior of corrosion product deposits (i.e., crud) deposits on spent LWR fuel after long-term pool storage; some evidence of crud loosening has been observed with fuel that was stored for extended periods at the West Valley facility and at other sites. Conclusions associated with the experience to date with old spent fuel that has been stored at the West Valley facility are presented. The conclusions are drawn from these subject areas: a general overview of the West Valley experience, handling of spent fuel, storing of spent fuel, rod consolidation, shipping of spent fuel, crud loosening, and visual inspection. A list of recommendations is provided. 61 refs., 4 figs., 5 tabs

  8. Release of UF6 from a ruptured model 48Y cylinder at Sequoyah Fuels Corporation Facility: lessons-learned report

    International Nuclear Information System (INIS)

    1986-08-01

    The uranium hexafluoride (UF 6 ) release of January 4, 1986, at the Sequoyah Fuels Corporation facility has been reviewed by a NRC Lessons-Learned Group. A Model 48Y cylinder containing UF 6 ruptured upon being heated after it was grossly overfilled. The UF 6 released upon rupture of the cylinder reacted with airborne moisture to produce hydrofluoric acid (HF) and uranyl fluoride (UO 2 F 2 ). One individual died from exposure to airborne HF and several others were injured. There were no significant immediate effects from exposure to uranyl fluoride. This supplement report contains NRC's response to the recommendations made in NUREG-1198 by the Lessons Learned Group. In developing a response to each of the recommendations, the staff considered actions that should be taken: (1) for the restart of the Sequoyah Fuels Facility; (2) to make near-term improvement; and (3) to improve the regulatory framework

  9. Release of UF6 from a ruptured Model 48Y cylinder at Sequoyah Fuels Corporation Facility: lessons-learned report

    International Nuclear Information System (INIS)

    1986-06-01

    The uranium hexafluoride (UF 6 ) release of January 4, 1986, at the Sequoyah Fuels Corporation facility has been reviewed by a NRC Lessons-Learned Group. A Model 48Y cylinder containing UF 6 ruptured upon being heated after it was grossly overfilled. The Uf 6 released upon rupture of the cylinder reacted with airborne moisture to produce hydrofluoric acid (HF) and uranyl fluoride (UO 2 F 2 ). One individual died from exposure to airborne HF and several others were injured. There were no significant immediate effects from exposure to uranyl fluoride. This report of the Lessons-Learned Group presents discussions and recommendations on the process, operation and design of the facility, as well as on the responses of the licensee, NRC, and other local, state and federal agencies to the incident. It also provides recommendations in the areas of NRC licensing and inspection of fuel facility and certain other NMSS licensees. The implementation of some recommendations will depend on decisions to be made regarding the scope of NRC responsibilities with respect to those aspects of the design and operation of such facilities that are not directly related to radiological safety

  10. Rupture of Model 48Y UF6 cylinder and release of uranium hexafluoride, Sequoyah Fuels Facility, Gore, Oklahoma, January 4, 1986. Volume 1

    International Nuclear Information System (INIS)

    1986-02-01

    At 11:30 a.m. on January 4, 1986, a Model 48Y UF 6 cylinder filled with uranium hexafluoride (UF 6 ) ruptured while it was being heated in a steam chest at the Sequoyah Fuels Conversion Facility near Gore, Oklahoma. One worker died because he inhaled hydrogen fluoride fumes, a reaction product of UF 6 and airborne moisture. Several other workers were injured by the fumes, but none seriously. Much of the facility complex and some offsite areas to the south were contaminated with hydrogen fluoride and a second reaction product, uranyl fluoride. The interval of release was approximately 40 minutes. The cylinder, which had been overfilled, ruptured while it was being heated because of the expansion of UF 6 as it changed from the solid to the liquid phase. The maximum safe capacity for the cylinder is 27,560 pounds of product. Evidence indicates that it was filled with an amount exceeding this limit. 18 figs

  11. An Operator Perspective from a Facility Evaluation of an RFID-Based UF6 Cylinder Accounting and Tracking System

    International Nuclear Information System (INIS)

    Martyn, Rose; Fitzgerald, Peter; Stehle, Nicholas D.; Rowe, Nathan C.; Younkin, James R.

    2011-01-01

    An operational field test of a Radio-Frequency Identification (RFID) system for tracking and accounting UF6 cylinders was conducted at the Global Nuclear Fuel Americas (GNF) fuel fabrication plant in 2009. The Cylinder Accountability and Tracking System (CATS) was designed and deployed by Oak Ridge National Laboratory (ORNL) and evaluated in cooperation with GNF. The system required that passive RFID be attached to several UF6 30B cylinders as they were received at the site; then the cylinders were tracked as they proceeded to interim storage, to processing in an autoclave, and eventually to disposition from the site. This CATS deployment also provided a direct integration of scale data from the site accountability scales. The integration of this information into the tracking data provided an attribute for additional safeguards for evaluation. The field test provided insight into the advantages and challenges of using RFID at an operating nuclear facility. The RFID system allowed operators to interact with the technology and demonstrated the survivability of the tags and reader equipment in the process environment. This paper will provide the operator perspective on utilizing RFID technology for locating cylinders within the facility, thereby tracking the cylinders for process and for Material Control and Accounting functions. The paper also will present the operator viewpoint on RFID implemented as an independent safeguards system.

  12. Functional description of the West Valley Demonstration Project Vitrification Facility

    International Nuclear Information System (INIS)

    Borisch, R.R.; McMahon, C.L.

    1990-07-01

    The primary objective of the West Valley Demonstration Project (WVDP) is the solidification of approximately 2.1 million liters (560,000 gallons) of high-level radioactive waste (HLW) which resulted from the operation of a nuclear fuel reprocessing plant. Since the original plant was not built to accommodate the processing of waste beyond storage in underground tanks, HLW solidification by vitrification presented numerous engineering challenges. Existing facilities required redesign and conversion to meet their new purpose. Vitrification technology and systems needed to be created and then tested. Equipment modifications, identified from cold test results, were incorporated into the final equipment configuration to be used for radioactive (hot) operations. Cold operations have defined the correct sequence and optimal functioning of the equipment to be used for vitrification and have verified the process by which waste will be solidified into borosilicate glass

  13. Views of West Valley area residents concerning the Nuclear Fuel Services facility at West Valley, New York

    International Nuclear Information System (INIS)

    Kamieniecki, S.; Milbrath, L.W.

    1978-06-01

    A number of major findings have emerged from this analysis. Although most people have heard or read about the Nuclear Fuel Services plant at West Valley, few exhibit a high level of knowledge about the issue area. A clear majority of residents living in the region are concerned about the presence of the facility. Many are particularly concerned about the health dangers that can result from radioactive contamination of the environment. People want to see something done about the facility, but do not know exactly what. When forced to choose one out of three possible alternatives, twice as many people preferred to ''completely remove the plant and restore the area'' than either of the two remaining alternatives. People who are concerned about the facility tend to favor removal of the plant and restoration of the area. Nearly three-fourths of West Valley area residents who believe that the plant did not employ enough people to significantly help the economy of the region favor removal of the facility and restoration of the area. The results of this study may help policymakers choose the most acceptable course of action

  14. Preliminary analysis of West Valley Waste Removal System equipment development and mock demonstration facilities

    International Nuclear Information System (INIS)

    Janicek, G.P.

    1981-06-01

    This report defines seven areas requiring further investigation to develop and demonstrate a safe and viable West Valley Waste Removal System. These areas of endeavor are discussed in terms of their minimum facility requirements. It is concluded that utilizing separated specific facilities at different points in time is of a greater advantage than an exact duplication of the West Valley tanks. Savannah River Plant's full-scale, full-circle and half-circle tanks, and their twelfth scale model tank would all be useful to varying degrees but would require modifications. Hanford's proposed full-size mock tank would be useful, but is not seriously considered because its construction may not coincide with West Valley needs. Costs of modifying existing facilities and/or constructing new facilities are assessed in terms of their benefit to the equipment development and mock demonstration. Six facilities were identified for further analysis which would benefit development of waste removal equipment

  15. Overview of the West Valley Vitrification Facility transfer cart control system

    International Nuclear Information System (INIS)

    Bradley, E.C.; Rupple, F.R.

    1993-01-01

    Oak Ridge National Laboratory (ORNL) has designed the control system for the West Valley Demonstration Project Vitrification Facility transfer cart. The transfer cart will transfer canisters of vitrified high-level waste remotely within the Vitrification Facility. The control system will operate the cart under battery power by wireless control. The equipment includes cart mounted control electronics, battery charger, control pendants, engineer's console, and facility antennas

  16. Testing of the West Valley Vitrification Facility transfer cart control system

    International Nuclear Information System (INIS)

    Halliwell, J.W.; Bradley, E.C.

    1995-01-01

    Oak Ridge National Laboratory (ORNL) has designed and tested the control system for the West Valley Demonstration Project Vitrification Facility transfer cart. The transfer cart will transfer canisters of vitrified high-level waste remotely within the Vitrification Facility. The control system operates the cart under battery power by wireless control. The equipment includes cart-mounted control electronics, battery charger, control pendants, engineer's console, and facility antennas. Testing was performed in several phases of development: (1) prototype equipment was built and tested during design, (2) board-level testing was then performed at ORNL during fabrication, and (3) system-level testing was then performed by ORNL at the fabrication subcontractor's facility for the completed cart system. These tests verified (1) the performance of the cart relative to design requirements and (2) operation of various built-in cart features. The final phase of testing is planned to be conducted during installation at the West Valley Vitrification Facility

  17. Environmental assessment for the Waste Water Treatment Facility at the West Valley Demonstration Project and finding of no significant impact

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

    The possible environmental impacts from the construction and operation of a waste water treatment facility for the West Valley Demonstration Project are presented. The West Valley Project is a demonstration project on the solidification of high-level radioactive wastes. The need for the facility is the result of a rise in the work force needed for the project which rendered the existing sewage treatment plant incapable of meeting the nonradioactive waste water treatment needs.

  18. Environmental assessment for the Waste Water Treatment Facility at the West Valley Demonstration Project and finding of no significant impact

    International Nuclear Information System (INIS)

    1992-01-01

    The possible environmental impacts from the construction and operation of a waste water treatment facility for the West Valley Demonstration Project are presented. The West Valley Project is a demonstration project on the solidification of high-level radioactive wastes. The need for the facility is the result of a rise in the work force needed for the project which rendered the existing sewage treatment plant incapable of meeting the nonradioactive waste water treatment needs

  19. Design, construction, and operation of the contact size reduction facility at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Frank, D.E.; Reeves, S.R.; Valenti, P.J.

    1988-05-01

    This paper describes the design, construction and initial operation of the Contact-Handled Size Reduction Facility (CSRF) at the West Valley Demonstration Project. The facility was constructed to size reduce contaminated tanks, piping, and other metallic scrap and package the scrap for disposal. In addition, the CSRF has the capability to decontaminate scrap prior to disposal. The anticipated result of decontaminating the scrap is to reduce waste classified as transuranic or low-level Class B and C to Class A or release for unrestricted use as nonradioactive equipment. 10 figs., 1 tab

  20. West Valley Demonstration Project facilities utilization plan for the existing facilities at the Western New York Nuclear Service Center

    International Nuclear Information System (INIS)

    Skillern, C.G.

    1986-05-01

    In 1980, Congress passed Public Law 96-368, the West Valley Demonstration Project (WVDP) Act. As a primary objective, the Act authorized the US Department of Energy (DOE) to solidify the high-level waste (HLW) stored at the Western New York Nuclear Service Center (WNYNSC) into a form suitable for transportation and disposal in a federal repository. This report will describe how WVDP proposes to use the existing WNYNSC Facilities in an efficient and technically effective manner to comply with Public Law 96-368. In support of the above cited law, the DOE has entered into a ''Cooperative agreement between the United States Department of Energy and the New York State Energy Research and Development Authority on the Western New York Nuclear Service Center at West Valley, New York.'' The state-owned areas turned over to the DOE for use are as follows: Process Plant, Waste Storage, Low-Level Waste Treatment Facility, Service Facilities, Plant Security, and Additional Facilities. The Facilities Utilization Plan (FUP) describes how the state-owned facilities will be utilized to complete the Project; it is divided into five sections as follows: Executive Summary - an overview; Introduction - the WVDP approach to utilizing the WNYNSC Facilities; WVDP Systems - a brief functional description of the system, list of equipment and components to be used and decontamination and decommissioning (D and D) support; WVDP Support Facilities; and Caveats that could effect or change the potential usage of a particular area

  1. Benchmarking the Remote-Handled Waste Facility at the West Valley Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    O. P. Mendiratta; D. K. Ploetz

    2000-02-29

    ABSTRACT Facility decontamination activities at the West Valley Demonstration Project (WVDP), the site of a former commercial nuclear spent fuel reprocessing facility near Buffalo, New York, have resulted in the removal of radioactive waste. Due to high dose and/or high contamination levels of this waste, it needs to be handled remotely for processing and repackaging into transport/disposal-ready containers. An initial conceptual design for a Remote-Handled Waste Facility (RHWF), completed in June 1998, was estimated to cost $55 million and take 11 years to process the waste. Benchmarking the RHWF with other facilities around the world, completed in November 1998, identified unique facility design features and innovative waste pro-cessing methods. Incorporation of the benchmarking effort has led to a smaller yet fully functional, $31 million facility. To distinguish it from the June 1998 version, the revised design is called the Rescoped Remote-Handled Waste Facility (RRHWF) in this topical report. The conceptual design for the RRHWF was completed in June 1999. A design-build contract was approved by the Department of Energy in September 1999.

  2. Benchmarking the Remote-Handled Waste Facility at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Mendiratta, O.P.; Ploetz, D.K.

    2000-01-01

    ABSTRACT Facility decontamination activities at the West Valley Demonstration Project (WVDP), the site of a former commercial nuclear spent fuel reprocessing facility near Buffalo, New York, have resulted in the removal of radioactive waste. Due to high dose and/or high contamination levels of this waste, it needs to be handled remotely for processing and repackaging into transport/disposal-ready containers. An initial conceptual design for a Remote-Handled Waste Facility (RHWF), completed in June 1998, was estimated to cost $55 million and take 11 years to process the waste. Benchmarking the RHWF with other facilities around the world, completed in November 1998, identified unique facility design features and innovative waste processing methods. Incorporation of the benchmarking effort has led to a smaller yet fully functional, $31 million facility. To distinguish it from the June 1998 version, the revised design is called the Rescoped Remote-Handled Waste Facility (RRHWF) in this topical report. The conceptual design for the RRHWF was completed in June 1999. A design-build contract was approved by the Department of Energy in September 1999

  3. Information on the confinement capability of the facility disposal area at West Valley, New York

    International Nuclear Information System (INIS)

    Nicholson, T.J.; Hurt, R.D.

    1985-12-01

    This report summarizes the previous NRC research studies, NRC licensee source term data and recent DOE site investigations that deal with assessment of the radioactive waste inventory and confinement capability of the Facility Disposal Area (FDA) at West Valley, New York. The radioactive waste inventory for the FDA has a total radioactivity of about 135,000 curies (Ci) and is comprised of H-3 (9,500 Ci), Co-60 (64,000 Ci), SR-90/Y-90 (24,300 Ci), Cs-137/Ba-137m (24,400 Ci), and Pu-241 (13,300 Ci). These wastes are buried in the Lavery Till, a glacial till unit comprised of a clayey silt with very low hydraulic conductivity properties. Recent studies of a tributylphosphate-kerosene plume moving through the shallow ground-water flow system in the FDA indicate a need to better assess the fracture flow components of this system particularly the weathered and fractured Lavery Till unit. The analysis of the deeper ground-water flow system studied by the USGS and NYSGS staffs indicated relatively long pathways and travel times to the accessible environment. Mass wasting, endemic to the glacial-filled valley, contributed to the active slumping in the ravines surrounding the FDA and also need attention. 31 refs., 8 figs., 8 tabs

  4. Assessment of the Public Health impact from the accidental release of UF6 at the Sequoyah Fuels Corporation Facility at Gore, Oklahoma (Docket No. 40-8027). Volume 2

    International Nuclear Information System (INIS)

    1986-03-01

    Following the accidental release of UF 6 from the Sequoyah Fuels Facility on January 4, 1986, an Ad Hoc Interagency Public Health Assessment Task Force was established. The Task Force consists of technical staff members from various agencies who have prepared this assessment of the public health impact associated with the accidental release. Volume 2 of the report contains Appendices which provide more detailed information used in the assessment and support the discussion in Volume 1

  5. Analysis of accidental UF6 releases

    International Nuclear Information System (INIS)

    Fan Yumao; Tan Rui; Gao Qifa

    2012-01-01

    As interim substance in the nuclear fuel enrichment process, Uranium Hexafluoride (UF 6 ) is widely applied in nuclear processing, enrichment and fuel fabrication plants. Because of its vivid chemical characteristics and special radiological hazard and chemical toxicity, great attention must be paid to accident of UF 6 leakage. The chemical reactions involved in UF 6 release processes were introduced, therewith potential release styles, pathways and characteristics of diffusion were analyzed. The results indicated that the accidental release process of UF 6 is not a simple passive diffusion. So, specific atmospheric diffusion model related to UF 6 releases need be used in order to analyze and evaluate accurately the accidental consequences. (authors)

  6. Lessons learned at West Valley during facility decontamination for re-use (1982--1988)

    International Nuclear Information System (INIS)

    Tundo, D.; Gessner, R.F.; Lawrence, R.E.

    1988-11-01

    The primary mission of the West Valley Demonstration Project (WVDP) is to solidify a large volume of high-level liquid waste (2.3 million liters -- 600,000 gallons) produced during reprocessing plant operations and stored in underground tanks. This is to be accomplished through the maximum use of existing facilities. This required a significant effort to remove existing equipment and to decontaminate areas for installation of liquid and cement processing systems in a safe environment while maintaining exposure to workers as low as reasonably achievable. The reprocessing plant occupied a building of about 33,000 m 2 (350,000 ft 2 ). When the WVDP was initiated, approximately 6 percent of the plant area was in a non-contaminated condition where personnel could function without protective clothing or radiological controls. From 1982 to 1988, an additional 64 percent of the plant was cleaned up and much of this converted to low- and high-level waste processing areas. The high-level liquid and resulting low-level liquids are now being treated in these areas using an Integrated Radwaste Treatment System (IRTS). The Project has now focused attention on installation, qualification and operation of a vitrification system which will convert the remaining high-level waste into borosilicate glass logs. The stabilized waste will be sent to a Federal Repository for long-term storage. From 1982 to 1988, about 70 technical reports were dealing with specific tasks and cleanup efforts. This report provides an overview of the decontamination and decommissioning work done in that period. The report emphasizes lessons learned during that effort. Significant advances were made in: remote and contact decontamination technology; personnel protection and training; planning and procedures; and radiological controls. 62 refs., 35 figs., 5 tabs

  7. Investigation of the UF6 aerosol behavior in air, (4)

    International Nuclear Information System (INIS)

    Ishida, Junichiro; Sakamoto, Genji; Takeda, Seiichi; Kato, Jinzo

    1979-01-01

    When gaseous uranium hexafluoride (UF 6 ) is released into air, it hydrolizes with moisture in air to produce HF gas and particulate UO 2 F 2 which is visible. The lowest visible concentration in air is about 5 x 10 -8 μCi/cm 3 in case of releasing UF 6 and about 10 -9 μCi/cm 3 in case of released UF 6 cloud. By watching the occurrence of released UF 6 cloud, it is possible to take necessary action without delay. But in the case that there is no one to watch or that the concentration is not high enough to be visible, an alarm monitor system has to be relied on. Therefore the characteristics of the alarm monitors which can detect UF 6 promptly were examined. As UF 6 is hydrolized into gaseous HF and particulate UO 2 F 2 , three monitoring methods are considered; (1) to detect the alpha radiation of uranium, (2) to detect HF gas and (3) to detect airborne particles (aerosol). Performance tests were conducted on an alpha dust monitor, an electrochemical HF monitor, a thin film electrolyte HF monitor and an ionized smoke detector. The relationship between radioactivity concentration and HF concentration was investigated especially regarding with the conditions of released UF 6 amount and the distance from a release point to the observation point. The experimental facilities containing a large glove-box made of SUS and acrylic resin walls, a dust monitor, an HF monitor, a smoke detector and a filter, and the experimental procedure are explained. As the experimental results, the response characteristics of the dust monitor and HF monitor, the relationship of radioactivity concentration to HF concentration in air and the relation of the distance from the release point to the concentration of U and HF are presented. (Nakai, Y.)

  8. Investigation of technology for monitoring UF6 mass flow

    International Nuclear Information System (INIS)

    Cooley, J.N.; Moran, B.W.; Swindle, D.W. Jr.

    1987-06-01

    The applicability of gas flow meters, in-line enrichment monitors, and instruments for measuring uranium or UF 6 concentrations in process streams as a means for verifying declared plant throughput have been investigated. The study was performed to assist the International Atomic Energy Agency in the development of an effective international safeguards approach for aerodynamic uranium enrichment plants. Because the process gas in an aerodynamic enrichment facility is a mixture of UF 6 and H 2 , a mass flow measurement in conjunction with a measurement of the uranium (or UF 6 ) concentration in the process gas is required to quantify the amount of uranium being fed into, and withdrawn from, the cascades for nuclear materials accountability verification. In-line enrichment monitors developed for the US gas centrifuge enrichment plant are found to be applicable only to pure UF 6 streams. Of the five gas flow meters evaluated, the orifice meter and the pitot tube meter are judged the best choices for the proposed applications: the first is recommended for low-velocity gas, small diameter piping; the latter, for high-velocity gas, large diameter piping. Of the six procedures evaluated for measurement of uranium or UF 6 concentration in a mixed process stream, infrared-ultraviolet-visible spectrophotometry is judged to be the best procedure currently available to perform the required measurement. 4 refs., 3 figs., 3 tabs

  9. Review of potential models for UF6 dispersion

    International Nuclear Information System (INIS)

    Sykes, R.I.; Lewellen, W.S.

    1992-07-01

    A survey of existing atmospheric dispersion models has been conducted to determine the most appropriate basis for the development of a model for predicting the consequences of an accidental UF 6 release. The model is required for safety analysis studies and should therefore be computationally efficient. The release of UF 6 involves a number of physical phenomena which make the situation more complicated than passive dispersion of a trace gas. The safety analysis must consider the density variations in the UF 6 cloud, which can be heavier or lighter than the ambient air. The release also involves rapid chemical reactions and associated heat release, which must be modeled. Other Department of Energy storage facilities require a dense gas prediction capability, so the model must be sufficiently general for use with a variety of release scenarios. The special problems associated with UF 6 make it unique, so there are very few models with existing capability for the problem. There are, however, a large number of dense gas dispersion models, some with relevant chemical reaction modeling, that could potentially form the basis of an advanced UF 6 model. We have examined a large selection of possible candidates, and selected 5 models for detailed consideration

  10. Photoionization mass spectrometry of UF6

    International Nuclear Information System (INIS)

    Berkowitz, J.

    1979-01-01

    The photoionization mass spectrum of 238 UF 6 was obtained. At 600 A = 20.66 eV, the relative ionic abundances were as follows: UF 6 + , 1.4; UF 5 + , 100; UF + , 17; UF 3 + , approx. 0.7; UF 2 + , very weak; UF + , very weak; U + , essentially zero. The adiabatic ionization potential for UF 6 was 13.897 +- 0.005 eV. The production of UF 5 + begins at approx. 887 A = 13.98 eV, at which energy the UF 6 + partial cross section abruptly declines and then levels off. This behavior suggests the vague possibility of an isotope effect. The UF 4 + signal begins at approx. 725 A = 17.10 eV, at which energy the UF 5 + signal reaches a plateau value. The UF 5 + photoionization yield curve displays some autoionization structure from its threshold to approx. 750 A

  11. Assessment of the public health impact from the accidental release of UF6 at the Sequoyah Fuels Corporation Facility at Gore, Oklahoma (Docket No. 40-8027, License No. SUB-1010). Main report. Volume 1

    International Nuclear Information System (INIS)

    1986-03-01

    Following the accidental release of UF 6 from the Sequoyah Fuels Facility on January 4, 1986, an Ad Hoc Interagency Public Health Assessment Task Force was established. The Task Force consists of technical staff members from various agencies who have prepared this assessment of the public health impact associated with the accidental release. The assessment consists of two volumes and is based on data from the accident available as of February 14, 1986. Volume 1 of the report describes the effects from the intake of uranium and fluoride and summarizes the findings and recommendations of the Task Force. Volume 2 of the report contains Appendices which provide more detailed information used in the assessment and support the discussion in Volume 1. 57 refs., 26 figs., 12 tabs

  12. West Valley Demonstration Project, West Valley, New York: Annual report

    International Nuclear Information System (INIS)

    1989-01-01

    Under the West Valley Demonstration Project Act, Public Law 96-368, liquid high-level radioactive waste stored at the Western New York Nuclear Services Center, West Valley, New York, that resulted from spent nuclear fuel reprocessing operations conducted between 1966 and 1972, is to be solidified in borosilicate glass and transported to a federal repository for geologic disposal. A major milestone was reached in May 1988 when the Project began reducing the volume of the liquid high-level waste. By the end of 1988, approximately 15 percent of the initial inventory had been processed into two waste streams. The decontaminated low-level liquid waste is being solidified in cement. The high-level waste stream is being stored in an underground tank pending its incorporation into borosilicate glass. Four tests of the waste glass melter system were completed. These tests confirmed equipment operability, control system reliability, and provided samples of waste glass for durability testing. In mid-1988, the Department validated an integrated cost and schedule plan for activities required to complete the production of the waste borosilicate glass. Design of the radioactive Vitrification Facility continued

  13. Chemical exchange between UF6 and UF6- ion in anhydrous hydrofluoric acid

    International Nuclear Information System (INIS)

    Chatelet, J.; Luce, M.; Plurien, P.; Rigny, P.

    1975-01-01

    The chemical exchange between UF 6 and the UF 6 - ion is of potential interest for the separation of U isotopes. In this paper, results concerning the value of the separation factor and the kinetics of the homogeneous exchange are given [fr

  14. Depleted UF6 programmatic environmental impact statement

    International Nuclear Information System (INIS)

    1997-01-01

    The US Department of Energy has developed a program for long-term management and use of depleted uranium hexafluoride, a product of the uranium enrichment process. As part of this effort, DOE is preparing a Programmatic Environmental Impact Statement (PEIS) for the depleted UF 6 management program. This report duplicates the information available at the web site (http://www.ead.anl.gov/web/newduf6) set up as a repository for the PEIS. Options for the web site include: reviewing recent additions or changes to the web site; learning more about depleted UF 6 and the PEIS; browsing the PEIS and related documents, or submitting official comments on the PEIS; downloading all or part of the PEIS documents; and adding or deleting one's name from the depleted UF 6 mailing list

  15. Corrosion of breached UF6 storage cylinders

    International Nuclear Information System (INIS)

    Barber, E.J.; Taylor, M.S.; DeVan, J.H.

    1993-01-01

    This paper describes the corrosion processes that occurred following the mechanical failure of two steel 14-ton storage cylinders containing depleted UF 6 . The failures both were traced to small mechanical tears that occurred during stacking of the cylinders. Although subsequent corrosion processes greatly extended the openings in the wall. the reaction products formed were quite protective and prevented any significant environmental insult or loss of uranium. The relative sizes of the two holes correlated with the relative exposure times that had elapsed from the time of stacking. From the sizes and geometries of the two holes, together with analyses of the reaction products, it was possible to determine the chemical reactions that controlled the corrosion process and to develop a scenario for predicting the rate of hydrolysis of UF 6 , the loss rate of HF, and chemical attack of a breached UF 6 storage cylinder

  16. Ground-water flow and transport modeling of the NRC-licensed waste disposal facility, West Valley, New York

    International Nuclear Information System (INIS)

    Kool, J.B.; Wu, Y.S.

    1991-10-01

    This report describes a simulation study of groundwater flow and radionuclide transport from disposal at the NRC licensed waste disposal facility in West Valley, New York. A transient, precipitation driven, flow model of the near-surface fractured till layer and underlying unweathered till was developed and calibrated against observed inflow data into a recently constructed interceptor trench for the period March--May 1990. The results suggest that lateral flow through the upper, fractured till layer may be more significant than indicated by previous, steady state flow modeling studies. A conclusive assessment of the actual magnitude of lateral flow through the fractured till could however not be made. A primary factor contributing to this uncertainty is the unknown contribution of vertical infiltration through the interceptor trench cap to the total trench inflow. The second part of the investigation involved simulation of the migration of Sr-90, Cs-137 and Pu-239 from the one of the fuel hull disposal pits. A first-order radionuclide leach rate with rate coefficient of 10 -6 /day was assumed to describe radionuclide release into the disposal pit. The simulations indicated that for wastes buried below the fractured till zone, no significant migration would occur. However, under the assumed conditions, significant lateral migration could occur for radionuclides present in the upper, fractured till zone. 23 refs., 68 figs., 12 tabs

  17. Thermal plasma reduction of UF6

    International Nuclear Information System (INIS)

    Fincke, J.R.; Swank, W.D.; Haggard, D.C.

    1995-01-01

    This paper describes the experimental demonstration of a process for the direct plasma reduction of depleted uranium hexafluoride to uranium metal. The process exploits the large departures from equilibrium that can be achieved in the rapid supersonic expansion of a totally dissociated and partially ionized mixture of UF 6 , Ar, He, and H 2 . The process is based on the rapid condensation of subcooled uranium vapor and the relatively slow rate of back reaction between metallic uranium and HF to F 2 to reform stable fluorides. The high translational velocities and rapid cooling result in an overpopulation of atomic hydrogen which persists throughout the expansion process. Atomic hydrogen shifts the equilibrium composition by inhibiting the reformation of uranium-fluorine compounds. This process has the potential to reduce the cost of reducing UF 6 to uranium metal with the added benefit of being a virtually waste free process. The dry HF produced is a commodity which has industrial value

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

    International Nuclear Information System (INIS)

    1975-01-01

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

  19. New regulatory aspects of UF6 transport

    International Nuclear Information System (INIS)

    Biaggio, A.L.; Lee Gonzales, H.M.; Lopez Vietri, J.R.; Novo, R.G.

    1987-01-01

    In nuclear industry, a great amount of uranium is transformed from a chemical form to another. When the fuel cycle requires enrichment, uranium hexafluoride (UF 6) is handled, stored and transported in great quantities. To analyze the risks involved in possible accidents associated with UF 6 , radiological and chemical aspects must be considered. So far, the international practice was based on the adoption of regulations from a particular country (ANSI No. 14.1-1982.U.S.A.). In this way, the adoption of these norms at international level is difficult. For that reason, the International Atomic Energy Agency has attempted to consider the chemical risks associated with UF 6 in order to establish a more universal basis ('Recommendations for Providing Protection during the Transport of Uranium Hexafluoride' IAEA-TECDOC-423, Vienna, June 1987 - Austria). A critical analysis of these recommendations is presented in this work. The coherence and the degree of completion of the new recommendations are evaluated and the safety level is compared with that of the accepted regulations for toxic or corrosive substances and for radioactive materials transport. (Author)

  20. Integrating UF6 Cylinder RF Tracking With Continuous Load Cell Monitoring for Verifying Declared UF6 Feed and Withdrawal Operations Verifying Declared UF6 Feed and Withdrawal Operations

    International Nuclear Information System (INIS)

    Krichinsky, Alan M.; Miller, Paul; Pickett, Chris A.; Richardson, Dave; Rowe, Nathan C.; Whitaker, J. Michael; Younkin, James R.

    2009-01-01

    Oak Ridge National Laboratory is demonstrating the integration of UF6 cylinder tracking, using RF technology, with continuous load cell monitoring (CLCM) at mock UF6 feed and withdrawal (F and W) stations. CLCM and cylinder tracking are two of several continuous-monitoring technologies that show promise in providing integrated safeguards of F and W operations at enrichment plants. Integrating different monitoring technologies allows advanced, automated event processing to screen innocuous events thereby minimizing false alerts to independent inspectors. Traditionally, international inspectors rely on batch verification of material inputs and outputs derived from operator declarations and periodic on-site inspections at uranium enrichment plants or other nuclear processing facilities. Continuously monitoring F and W activities between inspections while providing filtered alerts of significant operational events will substantially increase the amount of valuable information available to inspectors thereby promising to enhance the effectiveness of safeguards and to improve efficiency in conducting on-site inspections especially at large plants for ensuring that all operations are declared.

  1. UV dissociation of vibrationally excited UF6

    International Nuclear Information System (INIS)

    Alexandre, M.; Clerc, M.; Gagnon, R.; Gilbert, M.; Isnard, P.; Nectoux, P.; Rigny, P.; Weulersse, J.M.

    1983-01-01

    Before application of laser photodissociation of UF 6 to the separation of uranium isotopes becomes practical, isotopic selectivity should be optimized. We present here results on the cross sections involved in the irradiation of UF 6 simultaneously with infrared and ultraviolet lasers, as a function of wavelengths, fluence and temperature (at 293 K and 105 K, in an adiabatic expansion). The experiment uses a Nd 3+ YAG pumped lithium niobate optical parametric oscillator as a tunable 16 μ light source. Energies of the order of 1 mJ can be obtained with linewidths smaller than 0.1 cm - . The UV source used is based on ND 3+ YAG pumped dye laser and various frequency mixing schemes. At low temperature the frequency variation of the absorbed infrared energy per molecule depends markedly on the IR fluence phisub(IR) with a maximum value varying as phisub(IR)sup(-1/2) and a frequency extension far beyond the low level absorption spectrum. The absorbed vibrational energy leads to a change in the UV cross section comparable with the effect of a rise in temperature. Using this a model is put forward to express the isotopic selectivity 235 U/ 238 U as a function of UV wavelength and IR irradiation conditions. Experimental results agree with this model, and yield to maximum selectivity close to two [fr

  2. Review of models used for determining consequences of UF6 release: Model evaluation report. Volume 2

    International Nuclear Information System (INIS)

    Nair, S.K.; Chambers, D.B.; Park, S.H.; Radonjic, Z.R.; Coutts, P.T.; Lewis, C.J.; Hammonds, J.S.; Hoffman, F.O.

    1997-11-01

    Three uranium hexafluoride-(UF 6 -) specific models--HGSYSTEM/UF 6 , Science Application International Corporation, and RTM-96; three dense-gas models--DEGADIS, SLAB, and the Chlorine Institute methodology; and one toxic chemical model--AFTOX--are evaluated on their capabilities to simulate the chemical reactions, thermodynamics, and atmospheric dispersion of UF 6 released from accidents at nuclear fuel-cycle facilities, to support Integrated Safety Analysis, Emergency Response Planning, and Post-Accident Analysis. These models are also evaluated for user-friendliness and for quality assurance and quality control features, to ensure the validity and credibility of the results. Model performance evaluations are conducted for the three UF 6 -specific models, using field data on releases of UF 6 and other heavy gases. Predictions from the HGSYSTEM/UF 6 and SAIC models are within an order of magnitude of the field data, but the SAIC model overpredicts beyond an order of magnitude for a few UF 6 -specific data points. The RTM-96 model provides overpredictions within a factor of 3 for all data points beyond 400 m from the source. For one data set, however, the RTM-96 model severely underpredicts the observations within 200 m of the source. Outputs of the models are most sensitive to the meteorological parameters at large distances from the source and to certain source-specific and meteorological parameters at distances close to the source. Specific recommendations are being made to improve the applicability and usefulness of the three models and to choose a specific model to support the intended analyses. Guidance is also provided on the choice of input parameters for initial dilution, building wake effects, and distance to completion of UF 6 reaction with water

  3. Fracture mechanics performance of UF6 containers

    International Nuclear Information System (INIS)

    Gonzalez, M.E.; Iorio, A.F.; Crespi, J.C.

    1993-01-01

    The main purpose of this work was to determine the fracture mechanics performance of UF 6 transport cylinders type ANSI N14.1.30B, which was made from ASTM A 516 Grade 70 steel. It was assumed an internal surface axial crack subjected to stresses due to service, proof and transport accident loads. The KUMAR-GERMAN-SHIH elastoplastic methodology gave adequate results for crack depth estimation. The results validate the leak-before-break criteria for service and proof conditions but not for accident ones. In the last case a non-destructive examination must be done in order to assure the absence of defects larger than one third of the cylinder wall thickness. (Author)

  4. Handling of UF6 in U.S. gaseous diffusion plants

    International Nuclear Information System (INIS)

    Legeay, A.J.

    1978-01-01

    A comprehensive systems analysis of UF 6 handling has been made in the three U.S. gaseous diffusion plants and has resulted in a significant impact on the equipment design and the operating procedures of these facilities. The equipment, facilities, and industrial practices in UF 6 handling operations as they existed in the early 1970's are reviewed with particular emphasis placed on the changes which have been implemented. The changes were applied to the systems and operating methods which evolved from the design, startup, and operation of the Oak Ridge Gaseous Diffusion Plant in 1945

  5. Pilot plant UF6 to UF4 test operations report

    International Nuclear Information System (INIS)

    Bicha, W.J.; Fallings, M.; Gilbert, D.D.; Koch, G.E.; Levine, P.J.; McLaughlin, D.F.; Nuhfer, K.R.; Reese, J.C.

    1987-02-01

    The FMPC site includes a plant designed for the reduction of uranium hexafluoride (UF 6 ) to uranium tetrafluoride (UF 4 ). Limited operation of the upgraded reduction facility began in August 1984 and continued through January 19, 1986. A reaction vessel ruptured on that date causing the plant operation to be shut down. The DOE conducted a Class B investigation with the findings of the investigation board issued in preliminary form in May 1986 and as a final recommendation in July 1986. A two-phase restart of the plant was planned and implemented. Phase I included implementing safety system modifications, changing reaction vessel temperature control strategy, and operating the reduction plant under an 8-week controlled test. The results of the test period are the subject of this report. 41 figs., 11 tabs

  6. Confirmatory measurements of UF6 using the neutron self-interrogation method

    International Nuclear Information System (INIS)

    Stewart, J.E.; Ensslin, N.; Menlove, H.O.; Cowder, L.R.; Polk, P.J.

    1985-01-01

    A passive neutron counting method has been developed for measurement of the 235 U mass in Model 5A cylinders of UF 6 . The unique neutronic properties of UF 6 containing highly enriched uranium (HEU) permit 235 U assay using only passive neutron counting. The sample effectively assays itself by self-interrogation. Shipped from enrichment plants and received at fuel fabrication and conversion facilities, 5A UF 6 cylinders hold up to approx.17 kg of 235 U each. Field measurements at the Portsmouth Gaseous Diffusion Plant (GDP) showed an average assay accuracy of 6.8% (1sigma) for 44 cylinders with enrichments from 6 to 98% and with a range of fill heights. Further measurements on 38 cylinders containing 97%-enriched material yielded an accuracy of 2.8% (1sigma). Typical counting times for these measurements were less than 5 min. An in-plant instrument for receipts confirmation measurements of 5A UF 6 cylinders has been developed for the Savannah River Plant. The Receipts Assay Monitor (RAM) is currently being tested and calibrated. It is designed to confirm declared fissile mass in all incoming 5A cylinders containing HEU in the form of UF 6 . One of the computer-controlled features is a removable cadmium liner for the sample cavity. The liner allows a sample fill-height correction, which significantly improves assay accuracy

  7. Technical documentation of HGSYSTEM/UF6 model

    International Nuclear Information System (INIS)

    Hanna, S.R.; Chang, J.C.; Zhang, J.X.

    1996-01-01

    MMES has been directed to upgrade the safety analyses for the gaseous diffusion plants at Paducah KY and Piketon OH. These will require assessment of consequences of accidental releases of UF 6 to the atmosphere at these plants. The HGSYSTEM model has been chosen as the basis for evaluating UF 6 releases; it includes dispersion algorithms for dense gases and treats the chemistry and thermodynamics of HF, a major product of the reaction of UF 6 with water vapor in air. Objective of this project was to incorporate additional capability into HGSYSTEM: UF 6 chemistry and thermodynamics, plume lift-off algorithms, and wet and dry deposition. The HGSYSTEM modules are discussed. The hybrid HGSYSTEM/UF 6 model has been evaluated in three ways

  8. Method and apparatus for measuring enrichment of UF6

    Science.gov (United States)

    Hill, Thomas Roy [Santa Fe, NM; Ianakiev, Kiril Dimitrov [Los Alamos, NM

    2011-06-07

    A system and method are disclosed for determining the enrichment of .sup.235U in Uranium Hexafluoride (UF6) utilizing synthesized X-rays which are directed at a container test zone containing a sample of UF6. A detector placed behind the container test zone then detects and counts the X-rays which pass through the container and the UF6. In order to determine the portion of the attenuation due to the UF6 gas alone, this count rate may then be compared to a calibration count rate of X-rays passing through a calibration test zone which contains a vacuum, the test zone having experienced substantially similar environmental conditions as the actual test zone. Alternatively, X-rays of two differing energy levels may be alternately directed at the container, where either the container or the UF6 has a high sensitivity to the difference in the energy levels, and the other having a low sensitivity.

  9. Preliminary design of a biological treatment facility for trench water from a low-level radioactive waste disposal area at West Valley, New York

    Energy Technology Data Exchange (ETDEWEB)

    Rosten, R.; Malkumus, D. [Pacific Nuclear, Inc. (United States); Sonntag, T. [New York State Energy Research and Development Authority, NY (United States); Sundquist, J. [Ecology and Environment, Inc. (United States)

    1993-03-01

    The New York State Energy Research and Development Authority (NYSERDA) owns and manages a State-Licensed Low-Level Radioactive Waste Disposal Area (SDA) at West Valley, New York. Water has migrated into the burial trenches at the SDA and collected there, becoming contaminated with radionuclides and organic compounds. The US Environmental Protection Agency issued an order to NYSERDA to reduce the levels of water in the trenches. A treatability study of the contaminated trench water (leachate) was performed and determined the best available technology to treat the leachate and discharge the effluent. This paper describes the preliminary design of the treatment facility that incorporates the bases developed in the leachate treatability study.

  10. West Valley waste removal system study

    International Nuclear Information System (INIS)

    Janicek, G.P.

    1981-04-01

    This study addresses the specific task of removing high-level wastes from underground tanks at Western New York Nuclear Center and delivering them to an onsite waste solidification plant. It begins with a review of the design and construction features of the waste storage tanks pertinent to the waste removal task with particular emphasis on the unique and complex tank internals which severely complicate the task of removal. It follows with a review of tank cleaning techniques used and under study at both Hanford and Savannah River and previous studies proposing the use of these techniques at West Valley. It concludes from these reviews that existing techniques are not directly transferable to West Valley and that a new approach is required utilizing selected feature and attributes from existing methodology. The study also concludes, from an investigation of the constraints imposed by the processing facility, that waste removal will be intermittent, requiring batch transfer over the anticipated 3 years of processing operations. Based on these reviews and conclusions, the study proposes that the acid waste be processed first and that one of the 15,000-gallon acid tanks then be used for batch feeding the neutralized waste. The proposed system would employ commercially available pumping equipment to transfer the wastes from the batch tank to processing via existing process piping. A commercially available mixed-flow pump and eight turbine pumps would homogenize the neutralized waste in conjunction with eight custom-fabricated sluicers for periodic transfer to the batch tank

  11. Results of ultrasonic testing evaluations on UF6 storage cylinders

    International Nuclear Information System (INIS)

    Lykins, M.L.

    1997-02-01

    The three site cylinder management program is responsible for the safe storage of the DOE owned UF 6 storage cylinders at PORTS, PGDP and at the K-25 site. To ensure the safe storage of the UF 6 in the cylinders, the structural integrity of the cylinders must be evaluated. This report represents the latest cylinder integrity investigation that utilized wall thickness evaluations to identify thinning due to atmospheric exposure

  12. Investigation of UF6 behavior in a fire

    International Nuclear Information System (INIS)

    Williams, W.R.

    1988-01-01

    Reactions between UF 6 and combustible gases and the potential for UF 6 -filled cylinders to rupture when exposed to fire are addressed. Although the absence of kinetic data prevents specific identification and quantification of the chemical species formed, potential reaction products resulting from the release of UF 6 into a fire include UF 4 , UO 2 F 2 , HF, C, CF 4 ,COF 2 , and short chain, fluorinated or partially fluorinated hydrocarbons. Such a release adds energy to a fire relative to normal combustion reactions. Time intervals to an assumed point of rupture for UF 6 -filled cylinders exposed to fire are estimated conservatively. Several related studies are also summarized, including a test series in which small UF 6 -filled cylinders were immersed in fire resulting in valve failures and explosive ruptures. It is concluded that all sizes of UF 6 cylinders currently in use may rupture within 30 minutes when totally immersed in a fire. For cylinders adjacent to fires, rupture of the larger cylinders appears much less likely

  13. Electrically Cooled Germanium System for Measurements of Uranium Enrichments in UF6 Cylinders

    International Nuclear Information System (INIS)

    Dvornyak, P.; Koestlbauer, M.; Lebrun, A.; Murray, M.; Nizhnik, V.; Saidler, C.; Twomey, T.

    2010-01-01

    Measurements of Uranium enrichment in UF6 cylinders is a significant part of the IAEA Safeguards verification activities at enrichment and conversion plants. Nowadays, one of the main tools for verification of Uranium enrichment in UF6 cylinders used by Safeguards inspectors is the gamma spectroscopy system with HPGe detector cooled with liquid nitrogen. Electrically Cooled Germanium System (ECGS) is a new compact and portable high resolution gamma spectrometric system free from liquid nitrogen cooling, which can be used for the same safeguards applications. It consists of the ORTEC Micro-trans-SPEC HPGe Portable Spectrometer, a special tungsten collimator and UF6 enrichment measurement software. The enrichment of uranium is determined by of quantifying the area of the 185.7 keV peak provided that the measurement is performed with a detector viewing an infinite thickness of material. Prior starting the verification of uranium enrichment at the facility, the ECGS has to be calibrated with a sample of known uranium enrichment, material matrix, container wall thickness and container material. Evaluation of the ECGS capabilities was performed by carrying out a field test on actual enrichment verification of uranium in UF6 cylinder or other forms of uranium under infinite thickness conditions. The results of these evaluations allow to say that the use of ECGS will enhance practicality of the enrichment measurements and support unannounced inspection activities at enrichment and conversion plants. (author)

  14. Modeling and analyses of postulated UF6 release accidents in gaseous diffusion plant

    International Nuclear Information System (INIS)

    Kim, S.H.; Taleyarkhan, R.P.; Keith, K.D.; Schmidt, R.W.; Carter, J.C.; Dyer, R.H.

    1995-10-01

    Computer models have been developed to simulate the transient behavior of aerosols and vapors as a result of a postulated accident involving the release of uranium hexafluoride (UF 6 ) into the process building of a gaseous diffusion plant. UF 6 undergoes an exothermic chemical reaction with moisture (H 2 O) in the air to form hydrogen fluoride (HF) and radioactive uranyl fluoride (UO 2 F 2 ). As part of a facility-wide safety evaluation, this study evaluated source terms consisting of UO 2 F 2 as well as HF during a postulated UF 6 release accident in a process building. In the postulated accident scenario, ∼7900 kg (17,500 lb) of hot UF 6 vapor is released over a 5 min period from the process piping into the atmosphere of a large process building. UO 2 F 2 mainly remains as airborne-solid particles (aerosols), and HF is in a vapor form. Some UO 2 F 2 aerosols are removed from the air flow due to gravitational settling. The HF and the remaining UO 2 F 2 are mixed with air and exhausted through the building ventilation system. The MELCOR computer code was selected for simulating aerosols and vapor transport in the process building. MELCOR model was first used to develop a single volume representation of a process building and its results were compared with those from past lumped parameter models specifically developed for studying UF 6 release accidents. Preliminary results indicate that MELCOR predicted results (using a lumped formulation) are comparable with those from previously developed models

  15. Technology Assessment for Proof-of-Concept UF6 Cylinder Unique Identification Task 3.1.2 Report – Survey and Assessment of Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Wylie, Joann; Hockert, John

    2014-04-24

    The National Nuclear Security Administration (NNSA) Office of Nonproliferation and International Security’s (NA-24) Next Generation Safeguards Initiative (NGSI) and the nuclear industry have begun to develop approaches to identify and monitor uranium hexafluoride (UF6) cylinders. The NA-24 interest in a global monitoring system for UF6 cylinders relates to its interest in supporting the International Atomic Energy Agency (IAEA) in deterring and detecting diversion of UF6 (e.g., loss of cylinder in transit) and undeclared excess production at conversion and enrichment facilities. The industry interest in a global monitoring system for UF6 cylinders relates to the improvements in operational efficiencies that such a system would provide. This task is part of an effort to survey and assess technologies for a UF6 cylinder to identify candidate technologies for a proof-of-concept demonstration and evaluation for the Cylinder Identification System (CIS).

  16. Anisotropy of the fluorine chemical shift tensor in UF6

    International Nuclear Information System (INIS)

    Rigny, P.

    1965-04-01

    An 19 F magnetic resonance study of polycrystalline UF 6 is presented. The low temperature complex line can be analyzed as the superposition of two distinct lines, which is attributed to a distortion of the UF 6 octahedron in the solid. The shape of the two components is studied. Their width is much larger than the theoretical dipolar width, and must be explained by large anisotropies of the fluorine chemical shift tensors. The resulting shape functions of the powder spectra are determined. The values of the parameters of the chemical shift tensors yield estimates of the characters of the U-F bonds, and this gives some information on the ground state electronic wave function of the UF 6 molecule in the solid. (author) [fr

  17. Update on the status of the West Valley demonstration project

    International Nuclear Information System (INIS)

    Greeves, J.T.; Camper, L.W.; Orlando, D.A.; Glenn, C.J.; Buckley, J.T.; Giardina, P.A.

    2002-01-01

    From 1966 to 1972, under an Atomic Energy Commission (AEC) license, Nuclear Fuel Services (NFS) reprocessed 640 metric tons of spent fuel at its West Valley, New York, facility-, the only commercial spent fuel reprocessing plant in the U.S. The facility shut down in 1972, for modifications to increase its seismic stability and to expand its capacity. In 1976, without restarting the operation, NFS withdrew from the reprocessing business and returned control of the facilities to the site owner, the New York State Energy Research and Development Authority (NYSERDA). The reprocessing activities resulted in about 2.3 million liters (600,000 gallons) of liquid high-level waste (HLW) stored below ground in tanks, other radioactive wastes, and residual radioactive contamination. The West Valley site was licensed by AEC, and then the U.S. Nuclear Regulatory Commission (NRC), until 1981, when the license was suspended to execute the 1980 West Valley Demonstration Project (WVDP) Act. The WVDP Act outlines the responsibilities of the U.S. Department of Energy (DOE), NRC, and NYSERDA at the site, including the NRC's responsibility to develop decommissioning criteria for the site. The Commission published the final policy statement on decommissioning criteria for the WVDP at the West Valley site after considering comments from interested stakeholders. In that regard, the Commission prescribed the License Termination Rule (LTR) criteria for the WVDP at the West Valley site, reflecting the fact that the applicable decommissioning goal for the entire NRC-licensed site is compliance with the requirements of the LTR. This paper will describe the history of the site, provide an update of the status of the decommissioning of the site and an overview of the technical and policy issues facing Federal and State regulators and other stakeholders as they strive to complete the remediation of the site. (author)

  18. Long-term evaluation of fluoroelastomer O-rings in UF6

    International Nuclear Information System (INIS)

    Russell, R.G.; Otey, M.G.; Dippo, G.L.

    1986-01-01

    A major component in the gaseous centrifuge enrichment plant (GCEP) was fluoroelastomer O-rings, which were used to seal the uranium hexafluoride (UF 6 ) gas system. A program utilizing accelerated test conditions was used to help identify the best material out of four selected candidates and to predict the service life of these materials at GCEP conditions. The tests included accelerated temperatures, mechanical stress, and UF 6 exposure. Data were evaluated using the Newman--Keuls 1 ranking system to identify the best material and a zero-order reaction rate equation to help predict service life. This presentation includes a description of the test facility, the materials tested, the types of tests, objectives of the study, service life predictions, and conclusions. The O-rings are predicted to last approx. 30 years, and a high-molecular-weight polymer had the best performance ranking

  19. Conversion of U3O8 to UF6

    International Nuclear Information System (INIS)

    Bodu, R.L.

    1975-01-01

    Three main processes for the production of UF 6 from the uranium ores (yellow cake) is described. The economic aspects of the conversion - capital cost, operating costs and conversion market and the future of conversion - capacity and prices - are discussed. (HPH) [de

  20. UF6 Cylinder Imaging by Fast Neutron Transmission Tomography

    International Nuclear Information System (INIS)

    McElroy, R.; Hausladen, P.; Blackston, M.; Croft, S.

    2015-01-01

    The common use Non-Destructive Assay techniques for the determination of 235 U enrichment and mass of UF6 cylinders used in the production of nuclear reactor fuel require prior knowledge of the physical distribution of the UF6 within the cylinder. The measurement performance for these techniques is typically evaluated based on assumed bounding case distributions of the material. However, little direct data such as radiographic or tomographic images, regarding the distribution of the UF6 within the cylinder is available against which to judge these assumptions. We have developed and tested a prototype active neutron tomographic imaging system employing an Associated Particle Imaging (API) neutron generator and an array of pixelated neutron scintillation counters. This system has been successfully used to obtain the 3-dimensional map of the distribution of UF6 within a type 12B storage cylinder. Results from these measurements are presented and the potential performance and utility of this technique with larger 30B and 48Y cylinders is discussed. (author)

  1. Rupture of Model 48Y UF6 cylinder and release of uranium hexafluoride. Cylinder overfill, March 12-13, 1986. Investigation of a failed UF6 shipping container. Volume 2

    International Nuclear Information System (INIS)

    1986-06-01

    NUREG-1179, Volume 1, reported on the rupture of a Model 48Y uranium hexafluoride (UF 6 ) cylinder and the subsequent release of UF 6 . At the time of publication, a detailed metallurgical examination of the damaged cylinder was under way and results were not available. Subsequent to the publication of Volume 1, a second incident occurred at the Sequoyah Fuels Corporation facility. On March 13, 1986, a Model 48X cylinder was overfilled during a special one-time draining procedure; however, no release of UF 6 occurred. An Augmented Investigation Team investigated this second incident. This report, NUREG-1179, Volume 2, presents the findings made by the Augmented Investigation Team of the March 13 incident and the report of the detailed metallurgical examination conducted by Battelle Columbus Division of the cylinder damaged on January 4, 1986

  2. Review of models used for determining consequences of UF6 release: Development of model evaluation criteria. Volume 1

    International Nuclear Information System (INIS)

    Nair, S.K.; Chambers, D.B.; Park, S.H.; Hoffman, F.O.

    1997-11-01

    The objective of this study is to examine the usefulness and effectiveness of currently existing models that simulate the release of uranium hexafluoride from UF 6 -handling facilities, subsequent reactions of UF 6 with atmospheric moisture, and the dispersion of UF 6 and reaction products in the atmosphere. The study evaluates screening-level and detailed public-domain models that were specifically developed for UF 6 and models that were originally developed for the treatment of dense gases but are applicable to UF 6 release, reaction, and dispersion. The model evaluation process is divided into three specific tasks: model-component evaluation; applicability evaluation; and user interface and quality assurance and quality control (QA/QC) evaluation. Within the model-component evaluation process, a model's treatment of source term, thermodynamics, and atmospheric dispersion are considered and model predictions are compared with actual observations. Within the applicability evaluation process, a model's applicability to Integrated Safety Analysis, Emergency Response Planning, and Post-Accident Analysis, and to site-specific considerations are assessed. Finally, within the user interface and QA/QC evaluation process, a model's user-friendliness, presence and clarity of documentation, ease of use, etc. are assessed, along with its handling of QA/QC. This document presents the complete methodology used in the evaluation process

  3. Investigation of technology for the monitoring of UF6 mass flow in UF6 streams diluted with H2

    International Nuclear Information System (INIS)

    Baker, O.J.; Cooley, J.N.; Hewgley, W.A.; Moran, B.W.; Swindle, D.W. Jr.

    1986-12-01

    The applicability, availability, and effectiveness of gas flow meters are assessed as a means for verifying the mass flows of pure UF 6 streams diluted with a carrier gas. The initial survey identified the orifice, pitot tube, thermal, vortex shedding, and vortex precession (swirl) meters as promising for the intended use. Subsequent assessments of these flow meters revealed that two - the orifice meter and the pitot tube meter - are the best choices for the proposed applications: the first is recommended for low velocity gas, small diameter piping; the latter, for high velocity gas, large diameter piping. Final selection of the gas flow meters should be based on test loop evaluations in which the proposed meters are subjected to gas flows, temperatures, and pressures representative of those expected in service. Known instruments are evaluated that may be applicable to the measurement of uranium or UF 6 concentration in a UF 6 - H 2 process stream at an aerodynamic enrichment plant. Of the six procedures evaluated, four have been used for process monitoring in a UF 6 environment: gas mass spectrometry, infrared-ultraviolet-visible spectrophotometry, gas chromatography, and acoustic gas analysis. The remaining two procedures, laser fluorimetry and atomic absorption spectroscopy, would require significant development work before they could be used for process monitoring. Infrared-ultravioloet-visible spectrophotometry is judged to be the best procedure currently available to perform the required measurement

  4. Radiation safety at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Hoffman, R.L.

    1997-01-01

    This is a report on the Radiation Safety Program at the West Valley Demonstration Project (WVDP). This Program covers a number of activities that support high-level waste solidification, stabilization of facilities, and decontamination and decommissioning activities at the Project. The conduct of the Program provides confidence that all occupational radiation exposures received during operational tasks at the Project are within limits, standards, and program requirements, and are as low as reasonably achievable

  5. Development of AN Active 238UF6 Gas Target

    Science.gov (United States)

    Eckardt, C.; Enders, J.; Freudenberger, M.; Göök, A.; von Neumann-Cosel, P.; Oberstedt, A.; Oberstedt, S.

    2014-09-01

    Detailed studies of the fission process, e.g., the search for parity nonconservation (PNC) effects, the energy dependence of fission modes or the population of fission isomers, depend on high quality data, therefore requiring high luminosities. An active gas target containing uranium may overcome the deterioration of energy and angular resolution caused by large solid target thicknesses. A single Frisch-grid ionization chamber has been built to test a mixture of standard counting gases (e.g., argon) with depleted uranium hexafluoride (238UF6), utilizing a triple alpha source to evaluate signal quality and drift velocity. For mass fractions of up to 4 percent of 238U the drift velocity increases with rising UF6 content, while a good signal quality and energy resolution is preserved.

  6. Case histories of West Valley spent fuel shipments: Final report

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    In 1983, NRC/FC initiated a study on institutional issues related to spent fuel shipments originating at the former spent fuel processing facility in West Valley, New York. FC staff viewed the shipment campaigns as a one-time opportunity to document the institutional issues that may arise with a substantial increase in spent fuel shipping activity. NRC subsequently contracted with the Aerospace Corporation for the West Valley Study. This report contains a detailed description of the events which took place prior to and during the spent fuel shipments. The report also contains a discussion of the shipment issues that arose, and presents general findings. Most of the institutional issues discussed in the report do not fall under NRC's transportation authority. The case histories provide a reference to agencies and other institutions that may be involved in future spent fuel shipping campaigns. 130 refs., 7 figs., 19 tabs.

  7. Case histories of West Valley spent fuel shipments: Final report

    International Nuclear Information System (INIS)

    1987-01-01

    In 1983, NRC/FC initiated a study on institutional issues related to spent fuel shipments originating at the former spent fuel processing facility in West Valley, New York. FC staff viewed the shipment campaigns as a one-time opportunity to document the institutional issues that may arise with a substantial increase in spent fuel shipping activity. NRC subsequently contracted with the Aerospace Corporation for the West Valley Study. This report contains a detailed description of the events which took place prior to and during the spent fuel shipments. The report also contains a discussion of the shipment issues that arose, and presents general findings. Most of the institutional issues discussed in the report do not fall under NRC's transportation authority. The case histories provide a reference to agencies and other institutions that may be involved in future spent fuel shipping campaigns. 130 refs., 7 figs., 19 tabs

  8. Application of the HGSYSTEM/UF6 model to simulate atmospheric dispersion of UF6 releases from uranium enrichment plants

    International Nuclear Information System (INIS)

    Goode, W.D. Jr.; Bloom, S.G.; Keith, K.D. Jr.

    1995-01-01

    Uranium hexafluoride is a dense, reactive gas used in Gaseous Diffusion Plants (GDPs) to make uranium enriched in the 235 U isotope. Large quantities of UF 6 exist at the GDPs in the form of in-process gas and as a solid in storage cylinders; smaller amounts exist as hot liquid during transfer operations. If liquid UF 6 is released to the environment, it immediately flashes to a solid and a dense gas that reacts rapidly with water vapor in the air to form solid particles of uranyl fluoride and hydrogen fluoride gas. Preliminary analyses were done on various accidental release scenarios to determine which scenarios must be considered in the safety analyses for the GDPS. These scenarios included gas releases due to failure of process equipment and liquid/gas releases resulting from a breach of transfer piping from a cylinder. A major goal of the calculations was to estimate the response time for mitigating actions in order to limit potential off-site consequences of these postulated releases. The HGSYSTEM/UF 6 code was used to assess the consequences of these release scenarios. Inputs were developed from release calculations which included two-phase, choked flow followed by expansion to atmospheric pressure. Adjustments were made to account for variable release rates and multiple release points. Superpositioning of outputs and adjustments for exposure time were required to evaluate consequences based on health effects due to exposures to uranium and HF at a specific location

  9. An rf communications system for the West Valley transfer cart

    International Nuclear Information System (INIS)

    Crutcher, R.I.; Moore, M.R.

    1993-01-01

    A prototype radio frequency communications system for digital data was designed and built by Oak Ridge National Laboratory for use in controlling the vitrification facility transfer cart at the West Valley Nuclear Services facility in New York. The communications system provides bidirectional wireless data transfer between the operator control station and the material transfer cart. The system was designed to operate in radiation fields of 10 4 R/h while withstanding a total integrated dose of 10 7 R of gamma radiation. Implementation of antenna spatial diversity, automatic gain control, and spectral processing improves operation in the reflective environment of the metal-lined reprocessing cells

  10. UF6 fissile mass flow simulation at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Mihalczo, J.T.; March-Leuba, J.; Valentine, T.E.; Mattingly, J.K.; Uckan, T.; McEvers, J.A.

    1997-01-01

    Basis for measuring fissile mass flow in slurries, liquid, and gaseous streams is activation of a fissile stream by neutrons and then detection of delayed radiation from resulting fission products. This paper describes recent simulation measurements with the first prototype of the system for fissile mass flow measurements with HEU UF 6 gas for use in blenddown facilities. Theory was only 15% higher than actual measured; thus calibration factor would be 0.85. This simulation of HEU gas flow confirms well the understanding of the physical phenomena associated with this measurement system

  11. Storage and uses alternatives of depleted UF6

    International Nuclear Information System (INIS)

    Marques, S.; Dotto, R.M.

    1988-01-01

    The U-enrichment of the Angra-1 pellets (Brazil) have generated about 792 ton of depleted-U, which is nowadays beeing stored by URENCO. The possible sending of this compound to Brazil, added to the fact that in the future, NUCLEI (Nuclebras Enriquecimento Isotopico) itself will generate it, reopens the discussion of the destination of this compound. In this context, the necessity, interest and viability aspects of a reconvertion plant of UF 6 in Brazil are getting important and are, in what follows, breafly discussed. (author) [pt

  12. Radiation-Triggered Surveillance for UF6 Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Curtis, Michael M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-12-01

    This paper recommends the use of radiation detectors, singly or in sets, to trigger surveillance cameras. Ideally, the cameras will monitor cylinders transiting the process area as well as the process area itself. The general process area will be surveyed to record how many cylinders have been attached and detached to the process between inspections. Rad-triggered cameras can dramatically reduce the quantity of recorded images, because the movement of personnel and equipment not involving UF6 cylinders will not generate a surveillance review file.

  13. High-level waste characterization at West Valley: Progress report for the period 1982-1985

    International Nuclear Information System (INIS)

    Rykken, L.E.

    1986-01-01

    This is a report on the work that was carried out at West Valley under the Waste Characterization Program. This Program covered a number of tasks in support of the design of facilities for the pretreatment and final encapsulation of the high level waste stored at West Valley. In particular, necessary physical, chemical, and radiological characterization of high-level reprocessing waste stored in two vaulted underground tanks was carried out over the period 1982 to 1985. 21 refs., 77 figs., 28 tabs

  14. Scoping study to expedite development of a field deployable and portable instrument for UF6 enrichment assay

    Energy Technology Data Exchange (ETDEWEB)

    Chan, George; Valentine, John D.; Russo, Richard E.

    2017-09-14

    The primary objective of the present study is to identity the most promising, viable technologies that are likely to culminate in an expedited development of the next-generation, field-deployable instrument for providing rapid, accurate, and precise enrichment assay of uranium hexafluoride (UF6). UF6 is typically involved, and is arguably the most important uranium compound, in uranium enrichment processes. As the first line of defense against proliferation, accurate analytical techniques to determine the uranium isotopic distribution in UF6 are critical for materials verification, accounting, and safeguards at enrichment plants. As nuclear fuel cycle technology becomes more prevalent around the world, international nuclear safeguards and interest in UF6 enrichment assay has been growing. At present, laboratory-based mass spectrometry (MS), which offers the highest attainable analytical accuracy and precision, is the technique of choice for the analysis of stable and long-lived isotopes. Currently, the International Atomic Energy Agency (IAEA) monitors the production of enriched UF6 at declared facilities by collecting a small amount (between 1 to 10 g) of gaseous UF6 into a sample bottle, which is then shipped under chain of custody to a central laboratory (IAEA’s Nuclear Materials Analysis Laboratory) for high-precision isotopic assay by MS. The logistics are cumbersome and new shipping regulations are making it more difficult to transport UF6. Furthermore, the analysis is costly, and results are not available for some time after sample collection. Hence, the IAEA is challenged to develop effective safeguards approaches at enrichment plants. In-field isotopic analysis of UF6 has the potential to substantially reduce the time, logistics and expense of sample handling. However, current laboratory-based MS techniques require too much infrastructure and operator expertise for field deployment and operation. As outlined in the IAEA Department of Safeguards Long

  15. Transport of natural UF6 in a challenging environment

    International Nuclear Information System (INIS)

    Chollet, P.; Presta, A.

    2004-01-01

    At the entrance of the nuclear fuel cycle, the front-end material transportation takes a major and specific place. After years of stability the landscape of front-end industry is going toward significant changes regarding capacity, implementation of new technologies, imbalance of conversion capacity between geographical areas with increasing volumes of natural UF6 to transport and transport issues such as new regulations and denial of shipments by liners and ports. Facing this evolution the front end-industry is re-organizing its environment to increase robustness of the logistical chain: by being active in industrial organizations such as WNTI and WNA to share technical views and develop licensed standard transport equipment usable worldwide by developing other safe and reliable comprehensive logistics solutions as an alternative to conventional transport means. Our paper will describe the solutions under review to meet nuclear fuel cycle companies expectations: qualification of several robust logistics systems chartered vessels for maritime transport of UF6 specific 20' flat racks for safer handling of 48Y cylinders with future thermal protections

  16. Potential detection systems for monitoring UF6 releases

    International Nuclear Information System (INIS)

    Beck, D.E.; Bostick, W.D.; Armstrong, D.P.; McNeely, J.R.; Stockdale, J.A.D.

    1994-09-01

    In the near future, the Nuclear Regulatory Commission (NRC) will begin to regulate the gaseous diffusion plants. Them is a concern that the smoke detectors currently used for uranium hexafluoride (UF 6 ) release detection will not meet NRC safety system requirements such as high reliability and rapid response. The NRC's position is that licensees should utilize state-of-the-art equipment such as hydrogen fluoride (HF) detectors that would provide more dependable detection of a UF 6 release. A survey of the literature and current vendor information was undertaken to define the state-of-the-art and commercial availability of HF (or other appropriate) detection systems. For the purpose of this report, classification of the available HF detection systems is made on the basis of detection principle (e.g., calorimetric, electrochemical, separational, or optical). Emphasis is also placed on whether the device is primarily sensitive to response from a point source (e.g., outleakage in the immediate vicinity of a specific set of components), or whether the device is potentially applicable to remote sensing over a larger area. Traditional HF point source monitoring typically uses gas sampling tubes or coated paper tapes with color developing indicator, portable and small area HF monitors are often based upon electrochemical or extractive/separational systems; and remote sensing by optical systems holds promise for indoor and outdoor large area monitoring (including plant boundary/ambient air monitoring)

  17. Transport of natural UF6 in a challenging environment

    Energy Technology Data Exchange (ETDEWEB)

    Chollet, P.; Presta, A. [COGEMA Logistics (AREVA Group) (France)

    2004-07-01

    At the entrance of the nuclear fuel cycle, the front-end material transportation takes a major and specific place. After years of stability the landscape of front-end industry is going toward significant changes regarding capacity, implementation of new technologies, imbalance of conversion capacity between geographical areas with increasing volumes of natural UF6 to transport and transport issues such as new regulations and denial of shipments by liners and ports. Facing this evolution the front end-industry is re-organizing its environment to increase robustness of the logistical chain: by being active in industrial organizations such as WNTI and WNA to share technical views and develop licensed standard transport equipment usable worldwide by developing other safe and reliable comprehensive logistics solutions as an alternative to conventional transport means. Our paper will describe the solutions under review to meet nuclear fuel cycle companies expectations: qualification of several robust logistics systems chartered vessels for maritime transport of UF6 specific 20' flat racks for safer handling of 48Y cylinders with future thermal protections.

  18. Uranium isotope fractionation resulting from UF6 vapor distillation from containers

    International Nuclear Information System (INIS)

    Hedge, W.D.; Turner, C.M.

    1985-01-01

    This empirical study for possible isotopic fractionation due to UF 6 vapor distillation from valved containers was performed to determine the effects of repeated vapor sampling. Four different experiments were performed, each of which varied by the method of measuring the isotopic contents and/or by the difference in temperature gradients as follows: The ratio of the parent UF 6 to the desublimed UF 6 collected at liquid nitrogen temperature and homogenized was measured by sampling the containers. The ratio of the parent UF 6 to the desublimed UF 6 collected at liquid nitrogen temperature and homogenized was measured by direct comparison to each other without subsampling. The ratio of the parent UF 6 to the desublimed UF 6 collected at liquid nitrogen and ice-water temperatures and homogenized was measured by indirect comparison to a common UF 6 reference material without subsampling. The ratio of the parent UF 6 to the desublimed UF 6 collected at liquid nitrogen temperature without homogenizing was measured by indirect comparison to a common UF 6 reference. Gas-phase, relative mass spectrometry was used for all isotopic measurements. Results of the study indicate that fractionation does occur. The U-235 isotope becomes more enriched in the parent container as the UF 6 is vaporized from it and desublimed into the receiving cylinder; i.e., the vaporized fraction is enriched in the U-238 isotope. The degree of fractionation indicates that the separation is due to the U-238 isotope of UF 6 having a higher vapor pressure than the U-235 isotope of UF 6 . 3 refs., 4 figs., 4 tabs

  19. UF6 breeder reactor power plants for electric power generation

    International Nuclear Information System (INIS)

    Rust, J.H.; Clement, J.D.; Hohl, F.

    1976-01-01

    The reactor concept analyzed is a 233 UF 6 core surrounded by a molten salt (Li 7 F, BeF 2 , ThF 4 ) blanket. Nuclear survey calculations were carried out for both spherical and cylindrical geometries. A maximum breeding ratio of 1.22 was found. Thermodynamic cycle calculations were performed for a variety of Rankine cycles. Optimization of a Rankine cycle for a gas core breeder reactor employing an intermediate heat exchanger gave a maximum efficiency of 37 percent. A conceptual design is presented along with a system layout for a 1000 MW stationary power plant. The advantages of the GCBR are as follows: (1) high efficiency, (2) simplified on-line reprocessing, (3) inherent safety considerations, (4) high breeding ratio, (5) possibility of burning all or most of the long-lived nuclear waste actinides, and (6) possibility of extrapolating the technology to higher temperatures and MHD direct conversion

  20. Study on UF6 condensing receiving system improvement

    International Nuclear Information System (INIS)

    Zhang Zhenxing; Li Yingfeng; Li Zhenfeng; He Ping; Wang Yanping; Tian Yushan

    2012-01-01

    In order to improve receiving capacity of UF 6 condensing system, the pressure release mode is changed through modifying gas phase inlet of the first-grade condenser, thus pressure release time is reduced from 13.1 h to 8.1 h. Be- cause of improvement of utility condensers of the two product lines, both the flexibility of feeding nitrogen and the emergency capacity of condensers are improved greatly. And modification of fluid transferring and sampling system make the remains in system transfer flexibly. The practise shows that metal direct recovery rises to the extent, and capacity of the first-grade condensing receiving system improves 8.4%, which strongly guarantees fluorination production safely, continuously and stably run. (authors)

  1. Environment, safety and health, management and organization compliance assessment, West Valley Demonstration Program, West Valley, New York

    International Nuclear Information System (INIS)

    1989-08-01

    An Environment, Safety and Health ''Tiger Team'' Assessment was conducted at the West Valley Demonstration Project. The Tiger Team was chartered to conduct an onsite, independent assessment of WVDP's environment, safety and health (ES ampersand H) programs to assure compliance with applicable Federal and State laws, regulations, and standards, and Department of Energy Orders. The objective is to provide to the Secretary of Energy the following information: current ES ampersand H compliance status of each facility; specific noncompliance items; ''root causes'' for noncompliance items; evaluation of the adequacy of ES ampersand H organization and resources (DOE and contractor) and needed modifications; and where warranted, recommendations for addressing identified problem areas

  2. Portable load-cell based system for weighing UF6 cylinders

    International Nuclear Information System (INIS)

    Fainberg, A.; Gordon, D.; Dermendjiev, E.; Terrey, D.; Mitchell, R.

    1982-01-01

    A load-cell-based portable weighing system which is capable of verifying the weights of 2.2 tonne 30-inch UF 6 cylinders has been developed by the US National Bureau of Standards (NBS). This system weighs about 13 kg and has an attainable accuracy of about 1 kg. After an initial calibration at NBS, the system is ready for use in the field. Approximately 5 to 10 minutes are needed for assembly, and, if an overhead crane has access to all cylinders to be weighed, from 10 to 15 weighings may be performed in one hour. During the past year the system has been tested at several facilities around the world with satisfactory results and with favorable comments from the facility operators. Results of several tests are presented in this paper

  3. Perekayasaan Heat Exchanger Sebagai Pemanas Umpan Uf 6 Dalam Pabrik Elemen Bakar Nuklir

    OpenAIRE

    Zacharias, Petrus; Pancoko, Marliyadi

    2011-01-01

    DESIGN OF HEAT EXCHANGER FOR HEATING UF6 FEED IN NUCLEAR FUEL ELEMENT PLANT. The process of conversion of UF6 to UO through Integrated Dry Route (IDR) i s done in a rotary kiln reactor. There are two stages of initi al treatment / conditioni ng before inserting the UF 6 in to the reactor : changing UF6 2 solid into the gas phase at a temperature of 60°C in an evaporator, and then, raising the temperature of UF C to 2900 C i n a Heat Exchanger (HE). Therefore it i s necessary to desi gn...

  4. An overview of the West Valley demonstration project

    International Nuclear Information System (INIS)

    Hannum, W.H.; Boswell, M.B.; De Boer, T.K.; Duckworth, J.P.

    1984-01-01

    This session is titled ''DOE Special Waste Management Projects.'' West Valley and TMI are indeed special projects, in that they represent today's problems. They may well have been the two most visible symbols as to how nuclear wastes can poison the entire civilian nuclear power program. Each in its own way has been perceived as a major threat to the environment and to public health and safety; in both cases this threat has been perceived to be grossly more severe than it has been in fact. It is the Department of Energy' intent that both of these problems be made to disappear. This paper serves to introduce a series of paper describing the status of the West Valley Project. In the West Valley case substantial progress is being made and we believe we are well on the way toward transforming what has been a skeleton along the road to progress into positive and unmistakable evidence that high-level nuclear wastes such as those resulting from reprocessing can be managed, understood, and prepared for disposal by a straightforward adaptation and application of existing technologies. Further, we now have evidence that the costs of doing this are not exorbitant. Subsequent papers will describe waste characterization; the plans and designs for solidification; and the ancillary and supporting programs for handling effluents and wastes, for D and D to utilize existing facilities, and environmental support. In this paper we describe the history of this plant and the wastes being used in the demonstration; the legislation and intent of the Project; the accomplishments to date; and the projected schedule and costs

  5. West Valley Demonstration Project annual report to Congress

    International Nuclear Information System (INIS)

    1990-01-01

    By the end of the fiscal year, the West Valley Demonstration Project had processed 757,000 litres of liquid high-level waste, removing most of the radioactive constituents by ion exchange. The radioactive ion exchange material is being stored in an underground tank pending its incorporation, along with sludge still in the tank, into borosilicate glass. The decontaminated salt solution was solidified into a cement low-level waste form which has been reviewed and endorsed by the Nuclear Regulatory Commission. Five tests of the waste glass melter system were completed. A Notice of Intent was published to prepare a joint federal/state Environmental Impact Statement. Design of the Vitrification Facility, a major milestone, was completed and construction of the facility enclosure has begun. A Department of Energy Tiger Team and Technical Safety Appraisal of the Project found no undue risks to worker or public health and safety or the environment

  6. Evaluation of a RF-Based Approach for Tracking UF6 Cylinders at a Uranium Enrichment Plant

    International Nuclear Information System (INIS)

    Pickett, Chris A; Younkin, James R; Kovacic, Donald N; Laughter, Mark D; Hines, Jairus B; Boyer, Brian Martinez

    2008-01-01

    Approved industry-standard cylinders are used globally to handle and store uranium hexafluoride (UF 6 ) feed, product, tails, and samples at uranium enrichment plants. The International Atomic Energy Agency (IAEA) relies on time-consuming physical inspections to verify operator declarations and detect possible diversion of UF 6 . Development of a reliable, automated, and tamper-resistant system for near real-time tracking and monitoring UF 6 cylinders (as they move within an enrichment facility) would greatly improve the inspector function. This type of system can reduce the risk of false or misreported cylinder tare weights, diversion of nuclear material, concealment of excess production, utilization of undeclared cylinders, and misrepresentation of the cylinders contents. This paper will describe a proof-of-concept approach that was designed to evaluate the feasibility of using radio frequency (RF)-based technologies to track individual UF 6 cylinders throughout a portion of their life cycle, and thus demonstrate the potential for improved domestic accountability of materials, and a more effective and efficient method for application of site-level IAEA safeguards. The evaluation system incorporates RF-based identification devices (RFID) which provide a foundation for establishing a reliable, automated, and near real-time tracking system that can be set up to utilize site-specific, rules-based detection algorithms. This paper will report results from a proof-of-concept demonstration at a real enrichment facility that is specifically designed to evaluate both the feasibility of using RF to track cylinders and the durability of the RF equipment to survive the rigors of operational processing and handling. The paper also discusses methods for securely attaching RF devices and describes how the technology can effectively be layered with other safeguard systems and approaches to build a robust system for detecting cylinder diversion. Additionally, concepts for off

  7. TENERIFE program: high temperature experiments on A 4 tons UF6 container

    International Nuclear Information System (INIS)

    Casselman, C.; Duret, B.; Seiler, J.M.; Ringot, C.; Warniez, P.; Wataru, M.; Shiomi, S.; Ozaki, S.; Yamakawa, H.

    1993-01-01

    To know the input of the future thermo-mechanical code, we have to get a better understanding of the thermo-physical evolution of the UF 6 which pressurizes the container. This evolution is function of: a) the heat transfer rate from the fire to the container b) the UF 6 behaviour in the container. These tests are essentially analytical at simulated fire temperatures of between 800 and 1000degC. They use a representative mass of UF 6 (around 4 tons). The tests will not seek to rupture the test container which has a diameter equal to the 48Y container, but shorter length. These tests carried out in realistic conditions (typical thermal gradient at the wall, characteristic period for UF 6 internal mass transfer) should make possible to improve knowledge of two fundamental phenomena: 1) vaporization of UF 6 on contact with the heated wall (around 400degC), a phenomenon which controls the container internal pressurization kinetic, 2) the equivalent conductivity of solid UF 6 , a phenomenon which is linked to the heat transfer by UF 6 vaporization-condensation through the solid's porosities and which depends on the diameter of the container. In addition, they will allow the influence of other parameters to be studied, such as UF 6 container filling mode or the mechanical characteristics of the container material. A UF 6 container fitted with instruments (wall temperature, UF 6 temperature, pressure) is heated by a rapid heat transient in a radiating furnace where the temperature and thermal power supplied can be measured. The test continues until pre-established thresholds have been reached: 1) strain threshold measured on the container surface (strain gauges positioned on the outside), 2) maximum temperature threshold of UF 6 , 3) container internal pressure threshold. (J.P.N.)

  8. Technical safety appraisal of the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    1989-09-01

    This report presents the results of one in a series of Technical Safety Appraisals (TSAs) being conducted of DOE nuclear operations by the Assistant Secretary for Environment, Safety, and Health Office of Safety Appraisals TSAs are one of the ititiatives announced by the Secretary of Energy on September 18, 1985, to enhance the DOE environment, safety and health program. This report presents the results of a TSA of the West Valley Demonstration Project (WVDP). The appraisal was conducted by a team of exerts assembled by the DOE Office of Safety Appraisal and was conducted during onsite visits of June 26-30 and July 10-21, 1989. West Valley, about 30 miles south of Buffalo, New York is the location of the only commercial nuclear fuel reprocessing facility operated in the United States. Nuclear Fuels Services, Inc. (NFS) operated the plant from 1966 to 1972 and processed about 640 metric tons of spent reactor fuel. The reprocessing operation generated about 560,000 gallons of high-level radioactive waste, which was transferred into underground tanks for storage. In 1972 NFS closed the plant and subsequently decided not to reopen it

  9. The applicability of fluoride volatility process to producing UF6 from yellow cake

    International Nuclear Information System (INIS)

    Xia Dechang

    2005-01-01

    The schematic diagrams producing UF 6 from yellow cake are showed in this paper. The characteristics and process improvements of the fluoride volatility process are explained. The applicability of the fluoride volatility process to producing UF 6 from yellow cake is discussed. (authors)

  10. Gas-phase UF6 enrichment monitor for enrichment plant safeguards

    International Nuclear Information System (INIS)

    Strittmatter, R.B.; Tape, J.W.

    1980-03-01

    An in-line enrichment monitor is being developed to provide real-time enrichment data for the gas-phase UF 6 feed stream of an enrichment plant. The nondestructive gamma-ray assay method can be used to determine the enrichment of natural UF 6 with a relative precision of better than 1% for a wide range of pressures

  11. Synthesis and characterization of a new uranium(V) compound: H3O+UF6-

    International Nuclear Information System (INIS)

    Masson, J.P.; Desmoulin, J.P.; Charpin, P.; Bougon, R.

    1976-01-01

    The reaction of equimolar amounts of UF 5 and H 2 O in hydrogen fluoride results in the partial dissolution of UF 5 , yielding a blue-green solution from which the new salt oxonium hexafluorouranate(V)(H 3 O + UF 6 - ) could be isolated as a green crystalline solid. Calorimetric measurements showed H 3 O + UF 6 - to decompose at about 68 0 C and its heat of formation to be equal to -628 +- 2 kcal mol. Its ionic nature in the solid state and in HF solutions was demonstrated from vibrational and electronic spectra. The electronic spectrum is closely similar to those of LiUF 6 , NaUF 6 , and CsUF 6 and differs from those of RbUF 6 and KUF 6 . This adduct shows a strong ESR signal, with g = -0.78 +- 0.10, characteristic of UF 6 - salts. Based on its x-ray powder diffraction pattern, H 3 O + UF 6 - is cubic with a = 5.2229 +- 0.0005 A

  12. West Valley Reprocessing Plant. Safety analysis report, supplement 21

    International Nuclear Information System (INIS)

    1976-01-01

    Supplement No. 21 contains responses to USNRC questions on quality assurance contained in USNRC letter to NFS dated January 22, 1976, revised pages for the safety analysis report, and Appendix IX ''Quality Assurance Manual--West Valley Construction Projects.''

  13. Qualification for Safeguards Purposes of UF6 Sampling using Alumina – Results of the Evaluation Campaign of ABACC-Cristallini Method

    OpenAIRE

    ESTAEBAN ADOLFO; GAUTIER EDUARDO; MACHADO DA SILVA LUIS; FERNANDEZ MORENO SONIA; RENHA JR GERALDO; DIAS FABIO; PEREIRA DE OLIVEIRA JUNIOR OLIVIO; AMMARAGGI DAVID; MASON PETER; SORIANO MICHAEL; CROATTO PAUL; ZULEGER EVELYN; GIAQUINTO JOSEPH; HEXEL COLE; VERCOUTER THOMAS

    2017-01-01

    The procedure currently used to sample material from process lines in uranium enrichment plants consists of collecting the uranium hexafluoride (UF6) in gaseous phase by desublimation inside a metal sampling cylinder cooled with liquid nitrogen or in certain facilities in a fluorothene P-10 tube type. The ABACC-Cristallini method (A-C method) has been proposed to collect the UF6 (gas) by adsorption in alumina (Al2O3) in the form of uranyl fluoride (UO2F2) (solid). This method uses a fluor...

  14. Vitrification process equipment design for the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Chapman, C.C.; Drosjack, W.P.

    1988-10-01

    The vitrification process and equipment design is nearing completion for the West Valley Project. This report provides the basis and current status for the design of the major vessels and equipment within the West Valley Vitrification Plant. A review of the function and key design features of the equipment is also provided. The major subsystems described include the feed preparation and delivery systems, the melter, the canister handling systems, and the process off-gas system. 11 refs., 33 figs., 4 tabs

  15. Nuclear wastes at West Valley, New York

    International Nuclear Information System (INIS)

    Lester, R.K.; Rose, D.J.

    1977-01-01

    A two-tiered approach is proposed for separating questions of who manages nuclear wastes from who pays for the management. The proper role of the Federal government in the nuclear fuel cycle is explored in the historical context of the West Valley, New York reprocessing plant, which operated on a private basis from 1966 to 1972. The plant reprocessed 600 metric tons for fuel and produced 600,000 gallons of liquid high-level radioactive waste, most of which remains in a carbon steel tank waiting for the Nuclear Regulatory Commission or some other agency to assume responsibility for it. A review of the plant's purposes, operations, and shutdown illustrates the difficulties of establising policies and rules for managing the wastes. Future use of the site will dictate the extent of decontamination and decommissioning that is needed, while legal and political issues of responsibility will also affect the rules. The case is made for conducting the cleanup as an experiment, using a prudent, rational, resolute, and charitable approach to taking necessary risks. A step-by-step process of decision and rule-making is proposed as an acknowledgement of the fact that all the answers are not known. ERDA is felt to be the best-suited for management, with guidelines formulated by the NRC. Financial responsibility could be divided between the National Science Foundation and Federal and state governments

  16. Emergency preparedness and response in case of a fire accident with (UF6) packages tracking Suez Canal

    International Nuclear Information System (INIS)

    Salama, M.

    2004-01-01

    Egypt has a unique problem - the Suez Canal. Radioactive cargo passing regularly through the canal carrying new and spent reactor fuel. Moreover there are also about 1000 metric tons of uranium hexaflouride (UF6) passing through the canal every year. In spite of all precautions taken in the transportation, accidents with packages containing (UF 6 ) and shipped through the Suez Canal, accidents may arise even though the probability is minimal. These accidents, may be accompanied by injuries or death of persons and damage to property. Due to the radiation and criticality hazards of (UF 6 ) and its high risk of chemical toxicity. The probability of a fire accident with a cargo carrying (UF 6 ) during its crossing the Suez Canal can cause serious chemical toxic and radiological hazards, particularly if the accident occurred close or near to one of the three densely populated cities (Port-Said, Ismailia, and Suez), which are located along the Suez Canal, west bank. The government of Egypt has elaborated a national radiological emergency plan inorder to face probable radiological accidents, which may be arised inside the country. Arrangements have been also elaborated for the medical care of any persons who, might be injured or contaminated, or who, have been exposed to severe radiation doses. The motivation of the present paper was undertaken to visualize a fire accident scenario occurring in industrial packages containing UF6 on board of a Cargo crossing the Suez Canal near Port-Said City. The accident scenario and emergency response actions taken during the different phases of the accident are going to be presented and discussed. The proposed emergency response actions taken to face the accident are going to be also presented. The work presented had revealed the importance of public awareness will be needed for populations located in densely populated areas along Suez Canal bank inorder to react timely and effectively to avoid the toxic and radiological hazards

  17. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2007

    Energy Technology Data Exchange (ETDEWEB)

    West Valley Environmental Services LLC (WVES) and URS - Washington Division

    2008-12-17

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2007. The report summarizes the calendar year (CY) 2007 environmental protection program at the WVDP. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment.

  18. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2007

    International Nuclear Information System (INIS)

    2008-01-01

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2007. The report summarizes the calendar year (CY) 2007 environmental protection program at the WVDP. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment

  19. 2D modelling of a UF6 container in a fire

    International Nuclear Information System (INIS)

    Duret, B.; Seiler, J.M.

    1993-01-01

    We present some results on 2D thermal modelisation of the behaviour of UF6 in a fire. A cylindrical container is engulfed by a high temperature space where the heat transfer is expected to occur by radiation only. During the first minutes, we assume that the thermal resistance is between the external wall and the UF6 solid, the heat transfer can be split up into three kinds: 1) conduction to solid UF6 through a contact surface. 2) radiative transfer. 3) gas layer with a small heat conductance. This thermal resistance is initially determined by the UF6 filling type, shape and also is time dependant by thermal dilatation effects. On the onset of liquifying the heat transfer increases because of the larger liquid exchange. The liquid and boiling heat flow is then calculated by a model on the basis of classical correlations in vertical cavities. Numerical evaluations have been performed with a finite element model using: ANSYS. With a realistic hypothesis, the effect of the following parameters is estimated: thermal conductivity of UF6 solid, contact surface fraction, UF6 emissivity, gas gap thickness, liquid UF6 wall exchange, solid liquid transition criteria, non condensation factor k. (J.P.N.)

  20. FTIR spectroscopy of UF6 clustering in a supersonic Laval nozzle

    International Nuclear Information System (INIS)

    Tanimura, Shinobu; Okada, Yoshiki; Takeuchi, Kazuo

    1996-01-01

    The clustering of UF 6 seeded in Ar was observed in a continuous supersonic Laval nozzle flow. The onset conditions for UF 6 clustering were investigated by measuring the FTIR spectra of UF 6 monomer and clusters in the nozzle. The onset conditions for the clustering, temperature, density of UF 6 (or partial pressure), and cooling rate, were determined. The onset temperature determined here was higher by 40-50 K than that determined by a light-scattering method. The frequency shift of the main peak of the UF 6 clusters from the monomer peak was about -17 cm -1 , which was smaller than the shift of the crystalline UF 6 by about 11 cm -1 . The increase in temperature caused by the heat of condensation and the change of the spectra of UF 6 clusters with the growth after the onset were also observed. It was shown that the clustering rate due to the collision between the monomer and cluster is much higher than that due to the collision between the monomers. 19 refs., 9 figs

  1. An aerial radiological survey of the West Valley Demonstration Project and surrounding area, West Valley, New York

    International Nuclear Information System (INIS)

    Berry, H.A.

    1991-09-01

    An aerial radiological survey of the West Valley Demonstration Project and the surrounding area was conducted from mid-August through early September 1984 by EG ampersand G Energy Measurements, Inc. for the United States Department of Energy. The radiological survey was part of the United States Department of Energy Comprehensive Integrated Remote Sensing (CIRS) program, which provides state-of-the-art remote sensing to support the needs of the various DOE facilities. The survey consisted of airborne measurements of both natural and man-made gamma radiation emanating from the terrestrial surface. These measurements allowed an estimate of the distribution of isotopic concentrations in the area surrounding the project site. Results are reported as isopleths superimposed on aerial photographs of the area. Gamma ray energy spectra are also presented for the net man-made radionuclides. 8 refs., 16 figs., 9 tabs

  2. Preliminary Hazard Analysis applied to Uranium Hexafluoride - UF6 production plant

    International Nuclear Information System (INIS)

    Tomzhinsky, David; Bichmacher, Ricardo; Braganca Junior, Alvaro; Peixoto, Orpet Jose

    1996-01-01

    The purpose of this paper is to present the results of the Preliminary hazard Analysis applied to the UF 6 Production Process, which is part of the UF 6 Conversion Plant. The Conversion Plant has designed to produce a high purified UF 6 in accordance with the nuclear grade standards. This Preliminary Hazard Analysis is the first step in the Risk Management Studies, which are under current development. The analysis evaluated the impact originated from the production process in the plant operators, members of public, equipment, systems and installations as well as the environment. (author)

  3. Reimiep 87. An interlaboratory U-235 enrichment determination by gamma measurement on solid UF6 sample

    International Nuclear Information System (INIS)

    Aparo, M.; Cresti, P.

    1988-01-01

    Gamma spectroscopy technique, based on the measurement of U 235 186 KeV flux, is now currently used for the determination of Uranium enrichment in different material of nuclear fuel cycle, namely: Uranium metallic, UO 2 pellets, UF 6 liquid or solid. The present paper describes the use of such a technique and the obtained results in determining the U 235 /U atomic isotopic abundance on a certified UF 6 solid sample. The measurements have been carried out in the frame work of the partecipation to the ''UF 6 Interlaboratory Measurements Evaluation Programme'' organized by CBNM/Geel with the support of the ESARDA (European Safeguards Research and Development Association)

  4. The electron spectrum of UF6 recorded in the gas phase

    Science.gov (United States)

    Mârtensson, N.; Malmquist, P.-Å.; Svensson, S.; Johansson, B.

    1984-06-01

    Gas phase core and valence electron spectra from UF6, excited by AlKα monochromatized x rays, in the binding energy range 0-1000 eV are presented. It is shown that the AlKα excited valence electron spectrum can be used to reassign the highest occupied molecular orbital (HOMO) in UF6. Many-body effects on the core levels are discussed and core level lifetimes are determined. The shift between solid phase and gas phase electron binding energies for core lines is used to discuss the U5 f population in UF6.

  5. Emergency preparedness and response in case of a fire accident with UF6 packages traversing the Suez Canal

    International Nuclear Information System (INIS)

    Salama, M.

    2004-01-01

    Egypt has a unique problem, the Suez Canal. Radioactive cargo passes regularly through the canal carrying new and spent reactor fuel. There are also about 1000 metric tonnes of uranium hexafluoride (UF 6 ) passing through the canal every year. In spite of all the precautions taken in the transport, accidents with packages containing UF 6 shipped through the Suez Canal may arise, even though the probability is minimal. Such accidents may be accompanied by injuries to or death of persons and damage to property including radiation and criticality hazards and high chemical toxicity, particularly if the accident occurred close to one of the three densely populated cities (Port Said, Ismailia and Suez), which are located along the west bank of the Suez Canal. The government of Egypt has established a national radiological emergency plan in order to deal with any radiological accidents which may arise inside the country. This paper considers the effect of a fire accident to industrial packages containing UF 6 on board a cargo ship passing along the Suez Canal near Port Said City. The accident scenario and emergency response actions taken during the different phases of the accident are presented and discussed. The paper highlights the importance of public awareness for populations located in densely populated areas along the bank of the Suez Canal, in order to react in a timely and effective way to avoid the toxic and radiological hazards resulting from such a type of accident. The possibility of upgrading the capabilities of civil defence and fire-fighting personnel is also discussed (author)

  6. Validation of the Cristallini Sampling Method for UF6 by High Precision Double-Spike Measurements

    OpenAIRE

    RICHTER STEPHAN; JAKOBSSON ULF; HIESS JOE; AMARAGGI D.

    2017-01-01

    The so-called "Cristallini Method" for sampling of UF6 by adsorption and hydrolysis in alumina pellets inside a fluorothene P-10 tube was developed by the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) several years ago. This method has several advantages compared to the currently used sampling method, for which UF6 is distilled into a stainless steel tube for transportation, with hydrolysis and isotopic analysis being performed after shipping to the analyt...

  7. Presentation and interpretation of field experiments of gaseous UF6 releases in the atmosphere

    International Nuclear Information System (INIS)

    Crabol, B.; Boulaud, D.; Deville-Cavelin, G.

    1992-01-01

    An experimental programme concerning the behaviour of UF 6 released in gaseous phase in the atmosphere has been conducted in the years 1986-1989 by the french Atomic Energy Commission and Eurodif. Three field tests have been performed on the CEA/CESTA experimental site. These experiments permitted to get informations about the kinetics of the hydrolysis reaction of the UF 6 , the behaviour of the hydrolysis products in the atmosphere and the granulometry of the solid particles

  8. Rod consolidation at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Bailey, W.J.

    1986-12-01

    A rod consolidation demonstration with irradiated pressurized water reactor fuel was recently conducted by personnel from Nuclear Assurance Corporation and West Valley Nuclear Services Company at the West Valley Demonstration Project in West Valley, New York. The rod consolidation demonstration involved pulling all of the fuel rods from six fuel Assemblies. In general, the rod pulling proceeded smoothly. The highest compaction ratio attained was 1:8:1. Among the total of 1074 fuel rods were some known degraded rods (they had collapsed cladding, a result of in-reactor fuel densification), but no rods were broken or dropped during the demonstration. One aim was to gather information on the effect of rod consolidation operations on the integrity of the fuel rods during subsequent handling and storage. Another goal was to collect information on the condition and handling of intact, damaged, and failed fuel that has been in storage for an extended period. 9 refs., 8 figs., 1 tab

  9. Criticality safety review of 2 1/2-, 10-, and 14-ton UF6 cylinders

    International Nuclear Information System (INIS)

    Broadhead, B.L.

    1991-10-01

    Currently, UF 6 cylinders designed to contain 2 1/2 tons of UF 6 are classified as Fissile Class 2 packages with a transport index (TI) of 5 for the purpose of transportation. The 10-ton UF 6 cylinders are classified as Fissile Class 1 with no TI assigned for transportation. The 14-ton cylinders, although not certified for transport with enrichments greater than 1 wt % because they have no approved overpack, can be used in on-site operations for enrichments greater than 1 wt %. The maximum 235 U enrichments for these cylinders are 5.0 wt % for the 2 1/2-ton cylinder and 4.5 wt % for the 10- and 14-ton cylinders. This work reviews the suitability for reclassification of the 2 1/2-ton UF 6 packages as Fissile Class 1 with a maximum 235 U enrichment of 5 wt %. Additionally, the 10- and 14-ton cylinders are reviewed to address a change in maximum 235 U enrichment from 4.5 to 5 wt %. Based on this evaluation, the 2 1/2-ton UF 6 cylinders meet the 10 CFR.71 criteria for Fissile Class 1 packages, and no TI is needed for criticality safety purposes; however, a TI may be required based on radiation from the packages. Similarly, the 10- and 14-ton UF 6 packages appear acceptable for a maximum enrichment rating change to 5 wt % 235 U. 11 refs., 13 figs., 7 tabs

  10. Evaluation of tecniques for controlling UF6 release clouds in the GAT environmental chamber

    International Nuclear Information System (INIS)

    Lux, C.J.

    1982-01-01

    Studies designed to characterize the reaction between UF 6 and atmospheric moisture, evaluate environmental variables of UF 6 cloud formation and ultimate cloud fate, and UF 6 release cloud control procedure have been conducted in the 1200 cu. ft. GAT environmental chamber. In earlier chamber experiments, 30 separate UF 6 release tests indicated that variations of atmospheric conditions and sample sizes had no significant effect on UO 2 F 2 particle size distribution, release cloud formation, or cloud settling rates. During the past year, numerous procedures have been evaluated for accelerating UF 6 cloud knockdown in a series of 37 environmental chamber releases. Knockdown procedures included: coarse water spray; air jet; steam spray (electrostatically charged and uncharged); carbon dioxide; Freon-12; fine water mist (uncharged); boric acid mist (charged and uncharged); and an ionized dry air stream. UF 6 hydrolysis cloud settling rates monitored by a laser/powermeter densitometer, indicated the relative effectiveness of various cloud knockdown techniques. Electrostatically charged boric acid/water mist, and electrostatically ionized dry air were both found to be very effective, knocking down the UO 2 F 2 release cloud particles in two to five minutes. Work to adapt these knockdown techniques for use under field conditions is continuing, taking into account recovery of the released uranium as well as nuclear criticality constraints

  11. Natural phenomena evaluations of the K-25 site UF6 cylinder storage yards

    International Nuclear Information System (INIS)

    Fricke, K.E.

    1996-01-01

    The K-25 Site UF 6 cylinder storage yards are used for the temporary storage of UF 6 normal assay cylinders and long-term storage of other UF 6 cylinders. The K-25 Site UF 6 cylinder storage yards consist of six on-site areas: K-1066-B, K-1066-E, K-1066-F, K-1066-J, K-1066-K and K-1066-L. There are no permanent structures erected on the cylinder yards, except for five portable buildings. The operating contractor for the K-25 Site is preparing a Safety Analysis Report (SAR) to examine the safety related aspects of the K-25 Site UF 6 cylinder storage yards. The SAR preparation encompasses many tasks terminating in consequence analysis for the release of gaseous and liquid UF 6 , one of which is the evaluation of natural phenomena threats, such as earthquakes, floods, and winds. In support of the SAR, the six active cylinder storage yards were evaluated for vulnerabilities to natural phenomena, earthquakes, high winds and tornados, tornado-generated missiles, floods (local and regional), and lightning. This report summarizes those studies. 30 refs

  12. From the Lab to the real world : sources of error in UF6 gas enrichment monitoring

    International Nuclear Information System (INIS)

    Lombardi, Marcie L.

    2012-01-01

    Safeguarding uranium enrichment facilities is a serious concern for the International Atomic Energy Agency (IAEA). Safeguards methods have changed over the years, most recently switching to an improved safeguards model that calls for new technologies to help keep up with the increasing size and complexity of today's gas centrifuge enrichment plants (GCEPs). One of the primary goals of the IAEA is to detect the production of uranium at levels greater than those an enrichment facility may have declared. In order to accomplish this goal, new enrichment monitors need to be as accurate as possible. This dissertation will look at the Advanced Enrichment Monitor (AEM), a new enrichment monitor designed at Los Alamos National Laboratory. Specifically explored are various factors that could potentially contribute to errors in a final enrichment determination delivered by the AEM. There are many factors that can cause errors in the determination of uranium hexafluoride (UF 6 ) gas enrichment, especially during the period when the enrichment is being measured in an operating GCEP. To measure enrichment using the AEM, a passive 186-keV (kiloelectronvolt) measurement is used to determine the 235 U content in the gas, and a transmission measurement or a gas pressure reading is used to determine the total uranium content. A transmission spectrum is generated using an x-ray tube and a 'notch' filter. In this dissertation, changes that could occur in the detection efficiency and the transmission errors that could result from variations in pipe-wall thickness will be explored. Additional factors that could contribute to errors in enrichment measurement will also be examined, including changes in the gas pressure, ambient and UF 6 temperature, instrumental errors, and the effects of uranium deposits on the inside of the pipe walls will be considered. The sensitivity of the enrichment calculation to these various parameters will then be evaluated. Previously, UF 6 gas enrichment

  13. Cleanup criteria for the West Valley demonstration project

    International Nuclear Information System (INIS)

    Parrott, J.D.

    1999-01-01

    The US Nuclear Regulatory Commission (NRC) is prescribing decontamination and decommissioning (cleanup) criteria for the West Valley Demonstration Project and the West Valley, New York, site. The site is contaminated with various forms of residual radioactive contamination and contains a wide variety of radioactive waste. The NRC is planning to issue cleanup criteria for public comment in Fall 1999. Due to the complexity of the site, and the newness of NRC's cleanup criteria policy, applying NRC's cleanup criteria to this site will be an original regulatory undertaking. (author)

  14. West Valley Demonstration Project site environmental report calendar year 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    This report represents a single, comprehensive source of off-site and on-site environmental monitoring data collected during 1998 by environmental monitoring personnel for the West Valley Demonstration Project (WVDP), West Valley, New York. The environmental monitoring program and results are discussed in the body of this report. The monitoring data are presented in the appendices. The data collected provide an historical record of radionuclide and radiation levels from natural and manmade sources in the survey area and document the quality of the groundwater on and around the WVDP and the quality of the air and water discharged by the WVDP.

  15. West Valley Demonstration Project site environmental report, calendar year 1999

    Energy Technology Data Exchange (ETDEWEB)

    None Available

    2000-06-01

    This report represents a single, comprehensive source of off-site and on-site environmental monitoring data collected during 1999 by environmental monitoring personnel for the West Valley Demonstration Project (WVDP), West Valley, New York. The environmental monitoring program and results are discussed in the body of this report. The monitoring data are presented in the appendices. The data collected provide an historical record of radionuclide and radiation levels from natural and manmade sources in the survey area and document the quality of the groundwater on and around the WVDP and the quality of the air and water discharged by the WVDP.

  16. West Valley Demonstration Project site environmental report, calendar year 1997

    Energy Technology Data Exchange (ETDEWEB)

    None

    1998-06-01

    This report represents a single, comprehensive source of off-site and on-site environmental monitoring data collected during 1997 by environmental monitoring personnel for the West Valley Demonstration Project (WVDP), West Valley, New York. The environmental monitoring program and results are discussed in the body of this report. The monitoring data are presented in the appendices. The data collected provide an historical record of radionuclide and radiation levels from natural and manmade sources in the survey area and document the quality of the groundwater on and around the WVDP and the quality of the air and water discharged by the WVDP.

  17. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2004

    International Nuclear Information System (INIS)

    2005-01-01

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2004. The report summarizes the environmental protection program at the West Valley Demonstration Project for CY 2004

  18. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2004

    Energy Technology Data Exchange (ETDEWEB)

    West Valley Nuclear Services Company (WVNSCO) and URS Group, Inc.

    2005-09-30

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2004. The report summarizes the environmental protection program at the West Valley Demonstration Project for CY 2004.

  19. Neutron methods for measuring 235U content in UF6 gas

    International Nuclear Information System (INIS)

    Stromswold, D.C.; Peurrung, A.J.; Reeder, P.L.; Pappas, R.A.; Sunberg, D.S.

    1996-10-01

    In the United States and Russia, UF 6 gas streams of highly enriched uranium and lower enrichment uranium am being blended to reduce the stockpile of the highly enriched material. The resultant uranium is no longer useful for weapons, but is suitable as fuel for nuclear reactors. A method to verify the blending of high- and low-enrichment uranium was developed at Pacific Northwest National Laboratory (PNNL) for the U.S. Department of Energy, Office of Research and Development (NN-20). In the United States, blending occurs at the U.S. Department of Energy's Portsmouth Gaseous Diffusion Plant located near Portsmouth, Ohio. In Russia, the blending takes place at Novouralsk. The United States is purchasing the blended product produced in Russia in a program to reduce the availability of enriched uranium that can be used for weapons production. Monitoring the 235 U mass flux of the input stream having the highly enriched uranium will provide confidence that high-enrichment uranium is being consumed in the blending process, and monitoring the output stream will provide an on-line measure of the 235 U in the mixed product. The Portsmouth plant is a potential test facility for non-destructive technology to monitor blending. In addition, monitoring the blending at Portsmouth can support International Atomic Energy Agency activities on controlling and reducing enriched uranium stockpiles

  20. The COMURHEX 2 project. Investing in UF6 long-term security of supply

    International Nuclear Information System (INIS)

    Bouzon, Pierre; Lacombe, Philippe; Durante, Pierre; Teyssier, Patrick

    2008-01-01

    The front-end nuclear fuel supply chain for LWRs encompasses four major industrial stages that are mining and concentration, conversion, enrichment, and eventually fuel fabrication. The different stages involve uranium in different chemical and physical forms. Enrichment of the 235-U fissile isotope requires gaseous UF6. As the standard output of mine is U3O8, referred to as ''yellow cake'', a purely chemical stage is therefore needed to fluorinate U3O8 and turn it into UFe: this is the conversion stage. U3O8 inventories management is thus performed at the conversion sites.Purification of the mining concentrates is also needed prior to actual conversion into UFe. This step is important because the front-end supply chain facilities have strict specifications concerning impurities. The conversion stage may involve intermediary products, namely UO3 and/or UF4, depending on the industrial scheme implemented. With the Comurhex 2 project, AREVA is not only shaping the future of conversion market and contributing to the security of supply of its customers, but it is also developing innovative techniques and reorganizing the conversion process steps. Providing such guaranteed and valuable conversion supply with a brand new plant is our strong commitment to a sustainable nuclear fuel cycle. And AREVA is the first that has launched such a project, looking further ahead. The three main axes of sustainable development, economical, social, and environmental, are truly taken into account in the development of the new project.

  1. Decontamination and decommissioning of the West Valley Reprocessing Plant

    International Nuclear Information System (INIS)

    Daugherty, H.F.; Keel, R.

    1986-11-01

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

  2. Stand development of trembling aspen in Canaan Valley, West Virginia

    Science.gov (United States)

    James S. Rentch; James T. Anderson

    2008-01-01

    In wetlands of Canaan Valley, West Virginia, trembling aspen occurs as a disjunct population well south of its primary natural range. Based on sample data from 15 stands, we found that aspen occurs as nearly monospecific stands or clones. Eight stands had median ages between 30 and 40 yrs, and we suggest that stand initiation was related to changes in land use after...

  3. Injection of radioactive waste by hydraulic fracturing at West Valley, New York. Volume 2. Text

    International Nuclear Information System (INIS)

    1978-05-01

    Results of a preliminary study are presented of the technical feasibility of radioactive waste disposal by hydraulic fracturing and injection into shale formations below the Nuclear Fuel Services Incorporated site at West Valley, New York. At this time there are approximately 600,000 gallons of high level neutralized Purex waste, including both the supernate (liquid) and sludge, and a further 12,000 gallons of acidic Thorex waste stored in tanks at the West Valley facilities. This study assesses the possibility of combining these wastes in a suitable grout mixture and then injecting them into deep shale formations beneath the West Valley site as a means of permanent disposal. The preliminary feasibility assessment results indicated that at the 850 to 1,250 feet horizons, horizontal fracturing and injection could be effectively achieved. However, a detailed safety analysis is required to establish the acceptability of the degree of isolation. The principal concerns regarding isolation are due to existing and possible future water supply developments within the area and the local effects of the buried valley. In addition, possible future natural gas developments are of concern. The definition of an exclusion zone may be appropriate to avoid problems with these developments. The buried valley may require the injections to be limited to the lower horizon depending on the results of further investigations

  4. The integrated melter off-gas treatment systems at the West Valley Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Vance, R.F. [West Valley Nuclear Services Co., Inc., NY (United States)

    1995-02-01

    The West Valley Demonstration Project was established by Public Law 96-368, the {open_quotes}West Valley Demonstration Project Act, {close_quotes} on October 1, l980. Under this act, Congress directed the Department of Energy to carry out a high level radioactive waste management demonstration project at the Western New York Nuclear Service Center in West Valley, New York. The purpose of this project is to demonstrate solidification techniques which can be used for preparing high level radioactive waste for disposal. In addition to developing this technology, the West Valley Demonstration Project Act directs the Department of Energy to: (1) develop containers suitable for permanent disposal of the high level waste; (2) transport the solidified high level waste to a Federal repository; (3) dispose of low level and transuranic waste produced under the project; and (4) decontaminate and decommission the facilities and materials associated with project activities and the storage tanks originally used to store the liquid high level radioactive waste. The process of vitrification will be used to solidify the high level radioactive liquid wastes into borosilicate glass. This report describes the functions, the controlling design criteria, and the resulting design of the melter off-gas treatment systems which are used in the vitrification process.

  5. Decommissioning alternatives for the West Valley, New York, Fuel Reprocessing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Munson, L F; Nemec, J F; Koochi, A K

    1978-06-01

    The methodology and numerical values of NUREG-0278 were applied to four decommissioning alternatives for the West Valley Fuel Reprocessing Plant. The cost and impacts of the following four alternatives for the process building, fuel receiving and storage, waste tank farm, and auxiliary facilities were assessed: (1) layaway, (2) protective storage, (3) preparation for alternate nuclear use, and (4) dismantlement. The estimated costs are 5.7, 11, 19, and 31 million dollars, respectively. (DLC)

  6. Decommissioning alternatives for the West Valley, New York, Fuel Reprocessing Plant

    International Nuclear Information System (INIS)

    Munson, L.F.; Nemec, J.F.; Koochi, A.K.

    1978-06-01

    The methodology and numerical values of NUREG-0278 were applied to four decommissioning alternatives for the West Valley Fuel Reprocessing Plant. The cost and impacts of the following four alternatives for the process building, fuel receiving and storage, waste tank farm, and auxiliary facilities were assessed: (1) layaway, (2) protective storage, (3) preparation for alternate nuclear use, and (4) dismantlement. The estimated costs are 5.7, 11, 19, and 31 million dollars, respectively

  7. UF6 overfilling prevention at Eurodif production Georges Besse plant

    Energy Technology Data Exchange (ETDEWEB)

    Reneaud, J.M. [Eurodif Production, Pierrelatte (France)

    1991-12-31

    Risk of overfilling exists on different equipments of Georges BESSE Plant: cylinders, desublimers and intermediate tanks. The preventive measures are composed of technical devices: desublimers weighing, load monitoring alarms, automatic controls ... and procedures, training, safety organization. In thirteen years of operation, some incidents have occurred but none of them has caused any personal injuries. They are related and discussed. The main factors involved in the Sequoyah fuel facility accident on 1/4/1986 have been analyzed and taken into account.

  8. Analyses of postulated accidental releases of UF6 inside process buildings

    International Nuclear Information System (INIS)

    Oliveira Neto, Jose Messias de; Nunes, Beatriz Guimaraes; Dias, Cristiane

    2009-01-01

    Uranium Hexafluoride is a material used in the various processes which comprise the front end of the nuclear fuel cycle (conversion, enrichment and fuel fabrication). Confinement of UF 6 is a very important safety requirement since this material is highly reactive and presents safety hazards to humans. The present paper discusses the safety relevant aspects of accidental releases of UF 6 inside process confinement buildings. Postulated accidental scenarios are analyzed and their consequences evaluated. Implant releases rates are estimated using computer code predictions. A time dependent homogeneous compartment model is used to predict concentrations of UF 6 , hydrogen fluoride and uranyl fluoride inside a confinement building, as well as to evaluate source terms released to the atmosphere. These source terms can be used as input to atmospheric dispersion models to evaluate consequences to the environment. The results can also be used to define adequate protective measures for emergency situations. (author)

  9. Electron affinity of UF6. Final report, March 1, 1976--June 30, 1977

    International Nuclear Information System (INIS)

    Rothe, E.W.

    1977-06-01

    Ionization reactions are observed in crossed molecular beams, usually of thermal energy, alkalis and MoF 6 , WF 6 and UF 6 . Previous studies have indicated large electron affinities for these hexafluorides, and this is confirmed here. Ionization at thermal energies proceeds with the alkali dimers, A 2 , for all three hexafluorides, but with alkali atoms, A, only for UF 6 . Several ionization paths are observed, allowing the deduction of molecular energies. A few experiments are done with eV-range beams. Lower limits for the elecron affinities are 4.5, 3.3, 4.9, 4.3 and 1.9 eV for MoF 6 , MoF 5 , WF 6 , UF 6 and UF 5 , respectively. Possible mechanisms are discussed

  10. FINDING SOLUTIONS AT THE WEST VALLEY DEMONSTRATION PROJECT

    International Nuclear Information System (INIS)

    Drake, John L.; Gramling, James M.; Houston, Helene M.

    2003-01-01

    The United States Department of Energy Office of Environmental Management (DOE-EM) faces a number of sizeable challenges as it begins to transform its mission from managing risk to reducing and eliminating risk throughout the DOE Complex. One of the greatest challenges being addressed by DOE-EM as this transformation takes place is accelerating the deactivation and decommissioning of thousands of facilities within the DOE Complex that were once used to support nuclear-related programs and projects. These facilities are now unused and aging. Finding solutions to complete the cleanup of these aging facilities more safely, efficiently, and effectively while reducing costs is critical to successfully meeting DOE-EM's cleanup challenge. The Large-Scale Demonstration and Deployment Project (LSDDP) of Hot Cells at the West Valley Demonstration Project (WVDP) is a near-term project funded through the DOE's National Energy Technology Laboratory (DOE-NETL) for the specific purpose of identifying, evaluating, demonstrating, and deploying commercially available technologies that are capable of streamlining the cleanup of hot cells in unused facilities while improving worker safety. Two DOE project sites are participating in this LSDDP: the WVDP site in West Valley, New York and the Hanford River Corridor Project (RCP) site in Richland, Washington. The WVDP site serves as the host site for the project. Technologies considered for demonstration and potential deployment at both LSDDP sites are targeted for application in hot cells that require the use of remote and semi-remote techniques to conduct various cleanup-related activities because of high radiation or high contamination levels. These hot cells, the type of cleanup activities being conducted, and technologies selected for demonstration are the main topics discussed in this paper. The range of cleanup-related activities addressed include in-situ characterization, size-reduction, contamination control, decontamination, in

  11. The toxic and radiological risk equivalence approach in UF6 transport

    International Nuclear Information System (INIS)

    Ringot, C.; Hamard, J.

    1988-12-01

    After a brief description of the safety in transport of UF 6 , we discuss the equivalence of the radioactive and chemical risks in UF 6 transport regulations. As the concept of low specific activity appears to be ill-suited for a toxic gas, we propose a quantity of material limit designated T 2 (equivalent to A 2 for radioactive substances) for packagings unable to withstand accident conditions (9 m drop, 800 0 C fire environment for 30 minutes). It is proposed that this limit be chosen for the amount of release acceptable after AIEA tests. Different possible scenarios are described, with fire assumed to be the most severe toxic risk situation

  12. Nuclear criticality safety aspects of gaseous uranium hexafluoride (UF6) in the diffusion cascade

    International Nuclear Information System (INIS)

    Huffer, J.E.

    1997-04-01

    This paper determines the nuclear safety of gaseous UF 6 in the current Gaseous Diffusion Cascade and auxiliary systems. The actual plant safety system settings for pressure trip points are used to determine the maximum amount of HF moderation in the process gas, as well as the corresponding atomic number densities. These inputs are used in KENO V.a criticality safety models which are sized to the actual plant equipment. The ENO V.a calculation results confirm nuclear safety of gaseous UF 6 in plant operations

  13. An Unattended Verification Station for UF6 Cylinders: Development Status

    International Nuclear Information System (INIS)

    Smith, E.; McDonald, B.; Miller, K.; Garner, J.; March-Leuba, J.; Poland, R.

    2015-01-01

    In recent years, the International Atomic Energy Agency (IAEA) has pursued innovative techniques and an integrated suite of safeguards measures to address the verification challenges posed by advanced centrifuge technologies and the growth in separative work unit capacity at modern centrifuge enrichment plants. These measures would include permanently installed, unattended instruments capable of performing the routine and repetitive measurements previously performed by inspectors. Among the unattended instruments currently being explored by the IAEA is an Unattended Cylinder Verification Stations (UCVS) that could provide independent verification of the declared relative enrichment, U-235 mass and total uranium mass of all declared cylinders moving through the plant, as well as the application and verification of a ''Non-destructive Assay Fingerprint'' to preserve verification knowledge on the contents of each cylinder throughout its life in the facility. As IAEA's vision for a UCVS has evolved, Pacific Northwest National Laboratory (PNNL) and Los Alamos National Laboratory have been developing and testing candidate non-destructive assay (NDA) methods for inclusion in a UCVS. Modeling and multiple field campaigns have indicated that these methods are capable of assaying relative cylinder enrichment with a precision comparable to or substantially better than today's high-resolution handheld devices, without the need for manual wall-thickness corrections. In addition, the methods interrogate the full volume of the cylinder, thereby offering the IAEA a new capability to assay the absolute U-235 mass in the cylinder, and much-improved sensitivity to substituted or removed material. Building on this prior work, and under the auspices of the United States Support Programme to the IAEA, a UCVS field prototype is being developed and tested. This paper provides an overview of: a) hardware and software design of the prototypes, b) preparation

  14. Testing and evaluation of used UF6 shipping packages

    International Nuclear Information System (INIS)

    Barlow, C.R.; Ziehlke, K.T.; Pryor, W.A.; Housholder, W.R.

    1986-01-01

    Damage to shipping packages and their components, whether due to normal environmental exposure or because of unforeseen accidents, requires occasional reevaluation and requalification to assure the suitability of the packages for continued service. Pressure tests have been conducted on used 30B cylinders that were involved in a warehouse fire to assess the possible damaging effects of the exposure. Deteriorated and mechanically damaged overpacks which had absorbed large quantities of water in service were subjected to drying tests, foam properties were evaluated, and a rehabilitation procedure was developed to allow return of such packages to service. Protective shipping packages show deterioration with extended service, principally structural damage from rough handling and rust damage from exposure to weather and from storage practices which may promote absorption of water by the insulating foam. The structural and thermal properties of the phenolic foam insulation from used shipping packages were found to be not adversely affected by absorbed water, and they were not degraded by the drying process. In order to slow or avoid continuing rust damage in renovated packages, however, a process was developed for drying the foam in commercial facilities prior to restoration work on used or damaged containers. Two 2-1/2-ton steel transport cylinders, type 30B, were involved in a warehouse fire where portions of the cylinders were estimated to have reached a temperature of 1600 0 F. The cylinders were empty at the time of the fire and thus were not in the protective packages in which full product cylinders are handled while in transit. Hydrostatic burst tests showed that the integrity of the cylinders was not degraded by the fire exposure. They withstood test pressures in excess of 10 times the design pressure, and showed a volume expansion of 30% above the original capacity before rupturing in a completely ductile fashion

  15. Laboratory work in support of West Valley glass development

    International Nuclear Information System (INIS)

    Bunnell, L.R.

    1988-05-01

    Over the past six years, Pacific Northwest Laboratory (PNL) has conducted several studies in support of waste glass composition development and testing of glass compositions suitable for immobilizing the nuclear wastes stored at West Valley, New York. As a result of pilot-scale testing conducted by PNL, the glass composition was changed from that originally recommended in response to changes in the waste stream, and several processing-related problems were discovered. These problems were solved, or sufficiently addressed to determine their likely effect on the glass melting operations to be conducted at West Valley. This report describes the development of the waste glass composition, WV-205, and discusses solutions to processing problems such as foaming and insoluble sludges, as well as other issues such as effects of feed variations on processing of the resulting glass. An evaluation of the WV-205 glass from a repository perspective is included in the appendix to this report

  16. Depleted UF6 Management Information Network - A resource for the public,

    Science.gov (United States)

    Depleted UF6 Management Information Network Web Site is an online repository of information about the U.S ) and DUF6, research and development efforts for beneficial uses of DU, DOE's program for management of line DUF6 Guide DUF6 Guide line Introductory information about depleted uranium: how it is created

  17. Durability testing with West Valley borosilicate glass composition- Phase II

    International Nuclear Information System (INIS)

    Macedo, P.B.; Finger, S.M.; Barkatt, A.A.; Pegg, I.L.; Feng, X.; Freeborn, W.P.

    1988-06-01

    This report presents the research performed by the Catholic University of America Vitreous State Laboratory (VSL) during FY 1987 in support of the West Valley Demonstration Project (WVDP) nuclear waste vitrification process. A principal objective of this work is the optimization of the glass composition be used for the vitrification of the liquid high-level waste generated at West Valley during nuclear fuel reprocessing. This report discusses (1) the experimental investigations to optimize the reference glass composition (the current leading candidates are WVCM-50 and ATM-10) for the WVDP vitrification process; (2) the systematic experimental investigation performed to determine the effects of compositional variations in WVCM-50 and WV-205 reference glasses on their viscosity and durability (including initial results of long-term leach tests of WVCM-50 under repository conditions); (3) the development of short-time and predictive leach tests; (4) the development of a process model for the West Valley vitrification process which predicts the range of glass compositions which may be encountered during normal operations and the effects of deviations in process control parameters; and (5) the development of product models for predicting the durability and viscosity of nuclear waste glasses

  18. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2009

    Energy Technology Data Exchange (ETDEWEB)

    West Valley Environmental Services LLC (WVES) and URS Corporation

    2010-09-17

    The West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2009. The report, prepared by the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2009. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program by the DOE ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental regulations and directives, evaluation of data collected in 2009 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  19. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2011

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2012-09-27

    The West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2011. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2011. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2011 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  20. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2012

    Energy Technology Data Exchange (ETDEWEB)

    Rendall, John D. [CH2M HILL • B& amp; W West Valley, LLC (CHBWV); Steiner, Alison F. [URS Professional Solutions (URSPS); Klenk, David P. [CH2M HILL • B& amp; W West Valley, LLC (CHBWV)

    2013-09-19

    The West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2012. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2012. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2012 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  1. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2010

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2011-09-28

    The West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2010. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2010. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE's effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations and directives, evaluation of data collected in 2010 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  2. West Valley Demonstration Project Annual Site Environmental Report (ASER) Calendar Year (2016)

    Energy Technology Data Exchange (ETDEWEB)

    Steiner, Alison F. [CH2M Hill BWXT West Valley, LLC, NY (United States); Pendl, Michael P. [CH2M Hill BWXT West Valley, LLC, NY (United States); Steiner, II, Robert E. [CH2M Hill BWXT West Valley, LLC, NY (United States); Fox, James R. [CH2M Hill BWXT West Valley, LLC, NY (United States); Hoch, Jerald J. [CH2M Hill BWXT West Valley, LLC, NY (United States); Williams, Janice D. [CH2M Hill BWXT West Valley, LLC, NY (United States); Wrotniak, Chester M. [CH2M Hill BWXT West Valley, LLC, NY (United States); Werchowski, Rebecca L. [CH2M Hill BWXT West Valley, LLC, NY (United States)

    2017-09-12

    West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2016. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2016. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2016 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  3. West Valley Demonstration Project Annual Site Environmental Report (ASER) for Calendar Year 2015

    International Nuclear Information System (INIS)

    Rendall, John D.; Steiner, Alison F.; Pendl, Michael P.; Biedermann, Charles A.; Steiner II, Robert E.; Fox, James R.; Hoch, Jerald J.; Wrotniak, Chester M.; Werchowski, Rebecca L.

    2016-01-01

    West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2015. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2015. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE's effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2015 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  4. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2010

    International Nuclear Information System (INIS)

    2011-01-01

    The West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2010. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2010. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE's effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations and directives, evaluation of data collected in 2010 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  5. West Valley Demonstration Project Annual Site Environmental Report (ASER) for Calendar Year 2014

    Energy Technology Data Exchange (ETDEWEB)

    Rendall, John D. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Steiner, Alison F. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Pendl, Michael P. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Biedermann, Charles A. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Steiner, II, Robert E. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Fox, James R. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Hoch, Jerald J. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Werchowski, Rebecca L. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States)

    2015-09-15

    West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2014. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2014. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2014 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  6. West Valley Demonstration Project Annual Site Environmental Report (ASER) for Calendar Year 2015

    Energy Technology Data Exchange (ETDEWEB)

    Rendall, John D. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Steiner, Alison F. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Pendl, Michael P. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Biedermann, Charles A. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Steiner, II, Robert E. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Fox, James R. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Hoch, Jerald J. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Wrotniak, Chester M. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States); Werchowski, Rebecca L. [CH2M HILL BWXT West Valley, LLC, West Valley, NY (United States)

    2016-09-15

    West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2015. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2015. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2015 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  7. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2009

    International Nuclear Information System (INIS)

    2010-01-01

    The West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2009. The report, prepared by the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2009. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE's effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program by the DOE ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental regulations and directives, evaluation of data collected in 2009 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  8. Low-Level Legacy Waste Processing Experience at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Valenti, P.J.; Rowell, L.E.; Kurasch, D.H.; Moore, H.R.

    2006-01-01

    This paper presents detailed results and lessons learned from the very challenging and highly successful 2005 low level radioactive waste sorting, packaging, and shipping campaign that removed over 95% of the available inventory of 350,000 ft 3 of legacy low level waste at the West Valley Demonstration Project near West Valley, New York. First some programmatic perspective and site history is provided to provide pertinent context for DOE's waste disposal mandates at the site. This is followed by a detailed description of the waste types, the storage locations, the containers, and the varied sorting and packaging facilities used to accomplish the campaign. The overall sorting and packaging protocols for this inventory of wastes are defined. This is followed by detailed sorting data and results concluding with lessons learned. (authors)

  9. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2013

    Energy Technology Data Exchange (ETDEWEB)

    Rendall, John D. [CH2MHILL • B& W West Valley, LLC (CHBWV); Steiner, Alison F. [CH2MHILL • B& W West Valley, LLC (CHBWV); Pendl, Michael P. [CH2MHILL • B& W West Valley, LLC (CHBWV)

    2014-09-16

    West Valley Demonstration Project (WVDP) Annual Site Environmental Report (ASER) for Calendar Year 2013. The report, prepared for the U.S. Department of Energy West Valley Demonstration Project office (DOE-WVDP), summarizes the environmental protection program at the WVDP for calendar year (CY) 2013. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment. The report is a key component of DOE’s effort to keep the public informed of environmental conditions at the WVDP. The quality assurance protocols applied to the environmental monitoring program ensure the validity and accuracy of the monitoring data. In addition to demonstrating compliance with environmental laws, regulations, and directives, evaluation of data collected in 2013 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  10. HGSYSTEMUF6, Simulating Dispersion Due to Atmospheric Release of Uranium Hexafluoride (UF6)

    International Nuclear Information System (INIS)

    Hanna, G; Chang, J.C.; Zhang, J.X.; Bloom, S.G.; Goode, W.D. Jr; Lombardi, D.A.; Yambert, M.W.

    2001-01-01

    1 - Description of program or function: HGSYSTEMUF6 is a suite of models designed for use in estimating consequences associated with accidental, atmospheric release of Uranium Hexafluoride (UF 6 ) and its reaction products, namely Hydrogen Fluoride (HF), and other non-reactive contaminants which are either negatively, neutrally, or positively buoyant. It is based on HGSYSTEM Version 3.0 of Shell Research LTD., and contains specific algorithms for the treatment of UF 6 chemistry and thermodynamics. HGSYSTEMUF6 contains algorithms for the treatment of dense gases, dry and wet deposition, effects due to the presence of buildings (canyon and wake), plume lift-off, and the effects of complex terrain. The models components of the suite include (1) AEROPLUME/RK, used to model near-field dispersion from pressurized two-phase jet releases of UF6 and its reaction products, (2) HEGADAS/UF6 for simulating dense, ground based release of UF 6 , (3) PGPLUME for simulation of passive, neutrally buoyant plumes (4) UF6Mixer for modeling warm, potentially reactive, ground-level releases of UF 6 from buildings, and (5) WAKE, used to model elevated and ground-level releases into building wake cavities of non-reactive plumes that are either neutrally or positively buoyant. 2 - Methods: The atmospheric release and transport of UF 6 is a complicated process involving the interaction between dispersion, chemical and thermodynamic processes. This process is characterized by four separate stages (flash, sublimation, chemical reaction entrainment and passive dispersion) in which one or more of these processes dominate. The various models contained in the suite are applicable to one or more of these stages. For example, for modeling reactive, multiphase releases of UF 6 , the AEROPLUME/RK component employs a process-splitting scheme which numerically integrates the differential equations governing dispersion, UF 6 chemistry, and thermodynamics. This algorithm is based on the assumption that

  11. Finite element modelling of fire situations in UF6 transport containers; Modelado por elementos finitos de situaciones de incendio en contenedores para el transporte de UF6

    Energy Technology Data Exchange (ETDEWEB)

    Basombrio, F G

    1997-12-31

    In this report we describe some runs made with the code FASES2. They concern different situations associated to fires originated by accidents in the transport of containers filled with UF6. Such situations have been inspired in cases taken from the current literature, and related to numerical modelling or experiments. We aim to consign the most relevant aspects of such runs, with the future purpose of comparing them with the predictions made with simpler lumped models. In such a way, it will be possible to calibrate the simple models with the results coming from detailed models. (author). 6 refs., 12 figs.

  12. Viability Study for an Unattended UF_6 Cylinder Verification Station: Phase I Final Report

    International Nuclear Information System (INIS)

    Smith, Leon E.; Miller, Karen A.; Garner, James R.; Branney, Sean; McDonald, Benjamin S.; Webster, Jennifer B.; Zalavadia, Mital A.; Todd, Lindsay C.; Kulisek, Jonathan A.; Nordquist, Heather; Deshmukh, Nikhil S.; Stewart, Scott

    2016-01-01

    In recent years, the International Atomic Energy Agency (IAEA) has pursued innovative techniques and an integrated suite of safeguards measures to address the verification challenges posed by the front end of the nuclear fuel cycle. Among the unattended instruments currently being explored by the IAEA is an Unattended Cylinder Verification Station (UCVS) that could provide automated, independent verification of the declared relative enrichment, "2"3"5U mass, total uranium mass and identification for all declared UF_6 cylinders in a facility (e.g., uranium enrichment plants and fuel fabrication plants). Under the auspices of the United States and European Commission Support Programs to the IAEA, a project was undertaken to assess the technical and practical viability of the UCVS concept. The US Support Program team consisted of Pacific Northwest National Laboratory (PNNL, lead), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL) and Savanah River National Laboratory (SRNL). At the core of the viability study is a long-term field trial of a prototype UCVS system at a Westinghouse fuel fabrication facility. A key outcome of the study is a quantitative performance evaluation of two nondestructive assay (NDA) methods being considered for inclusion in a UCVS: Hybrid Enrichment Verification Array (HEVA), and Passive Neutron Enrichment Meter (PNEM). This report provides context for the UCVS concept and the field trial: potential UCVS implementation concepts at an enrichment facility; an overview of UCVS prototype design; field trial objectives and activities. Field trial results and interpretation are presented, with a focus on the performance of PNEM and HEVA for the assay of over 200 ''typical'' Type 30B cylinders, and the viability of an ''NDA Fingerprint'' concept as a high-fidelity means to periodically verify that the contents of a given cylinder are consistent with previous scans. A modeling study, combined with field-measured instrument

  13. Transport of UF6 in compliance with TS-R-1

    International Nuclear Information System (INIS)

    Dekker, B.G.

    2004-01-01

    The IAEA Regulations TS-R-1 (ST-1, Revised) 1996 Edition include requirements for packages containing uranium hexafluoride (UF6); these are the first and only substance-specific requirements in the IAEA regulations. These requirements have already particularly affected, and will further affect, the transport of non-fissile and fissile excepted UF 6 and the packages used for these transports. Non-fissile and fissile excepted UF6 (ASTM C 787) has been transported worldwide for decades in a safe and reliable manner, using internationally standardised packages. Under the auspices of the World Nuclear Transport Institute (WNTI), an industry working group has been evaluating the existing packages against the requirements in TS-R-1. As new requirements came into effect, there were new challenges for the use of these standard packages, including the free drop test and the thermal requirements. In close cooperation with the WNTI HEXT Industry Working Group, a consortium of UF6 producers/users has worked together on the design and development, testing and certification of technical solutions for modification and optimisation of the existing packages to comply with TS-R-1. This paper reviews the existing standard packages against the requirements in TS-R-1. An update is also given describing the enhancements to the standard packages that have been designed and developed recently. The paper also describes how these solutions have been tested and certified, as well as the status of implementation. Finally, a review is made of the options that are available internationally to transport UF6 in compliance with TS-R-1. (author)

  14. Load-cell-based weighing system for weighing 9.1- and 12.7-tonne UF6 cylinders

    International Nuclear Information System (INIS)

    McAuley, W.A.; Kane, W.R.

    1986-01-01

    For the independent verification of UF 6 cylinder masses by the International Atomic Energy Agency (IAEA) at uranium enrichment facilities, an 18-tonne capacity Load-Cell-Based Weighing System (LCBWS) has been developed. The system was developed at Brookhaven National Laboratory and the Oak Ridge Gaseous Diffusion Plant and calibrated at the US National Bureau of Standards. The principal components of the LCBWS are two load cells, with readout and ancillary equipment, and a lifting fixture that couples the load cells to a cylinder. Initial experience with the system demonstrates that it has the advantages of transportability, ease of application, stability, and an attainable accuracy of 2 kg or better for a full cylinder

  15. Cost estimates supporting West Valley DEIS

    International Nuclear Information System (INIS)

    Pirro, J.

    1981-01-01

    An Environmental Impact Statement (EIS) is being prepared which considers alternate means for solidifying the high level liquid wastes (HLLW) at the Western New York Nuclear Service Center (WNYNSC). For this purpose three basic scenarios were considered. In the first scenario, the HLLW is converted into terminal waste form of borosilicate glass. Before vitrification, the non-radioactive chemical salts are separated from the radioactive and transuranic (TRU) constituents in the HLLW. In the second scenario, the HLLW is converted into an intermediate form-fused salt. The stored HLLW is dewatered and melted and the solids are transported to a Department of Energy (DOE) site. The fused salt will be processed of the DOE site at a later date where it will be converted to a vitrified form in a facility that will be constructed to treat HLLW stored at that site. The vitrified salt will be eventually removed for permanent disposal at a Federal repository. In the third scenario, the HLLW is solidified in the existing HLLW storage tanks with cement and returned for on-site disposal in the existing tanks or additional tanks as needed to accommodate the volume. To support the EIS, the costs to accomplish each of the alternatives is provided. The purpose of this cost estimate is to provide a common basis to evaluate the expenditures required to immobilize the HLLW presently stored at the WNYNSC

  16. Application of fixed bed trapping technology for the removal of low concentration UF6 from plant gaseous effluent streams

    International Nuclear Information System (INIS)

    Russell, R.G.

    1987-01-01

    For the trapping of UF 6 in nitrogen, NaF > Al 2 O 3 > CaSO 4 . UF 6 inlet concentration has little effect on loading of alumina. Velocity shows an effect on UF 6 loading on alumina, with higher loading at low velocity. There is no significant difference in UF 6 loading between alumina 201A and 202HF. UF 6 outlet concentrations prior to breakthrough were measured to be as low as 2 O 3 until breakthrough (6.6% vs 5.3%), after which NaF experiences more loading (7.5% vs 11.5% at 1 ppM in the outlet). Higher trap loadings at lower pressures for both NaF and Al 2 O 3 . Al 2 O 3 was more efficient than NaF at higher velocities

  17. Hydrogeology and water quality of the West Valley Creek Basin, Chester County, Pennsylvania

    Science.gov (United States)

    Senior, Lisa A.; Sloto, Ronald A.; Reif, Andrew G.

    1997-01-01

    liter as phosphorus) were measured in a stream that receives treated sewage effluent. Discharge of water containing elevated sulfate (about 250 milligrams per liter) from quarry dewatering operations contributes to die increase in sulfate concentration (of 10 to 40 milligrams per liter) in base flow downstream from the quarry. The chloride load at all stream sites is greater than the load contributed by precipitation and mineral weathering to the basin, indicating anthropogenic sources of chloride throughout the basin. The diversity index of the benthic invertebrate community has increased since 1973 at the longterm biological monitoring site on West Valley Creek, indicating an improvement in stream quality. The improvement probably is related to controls on discharges and banning of pesticides, such as DOT, in the 1970's. Concentrations of dissolved constituents, except for chloride, determined for base flow in the autumn do not appear to have changed since 1971. Application of the seasonal Kendall test for trend indicates that concentrations of chloride in base flow have increased since 1971; this increase may be related to the increase in urbanization in the basin. The benthic community structure at the West Valley Creek site in 1991 indicates slight nutrient enrichment.Lithium was detected in ground water and surface water downgradient from two lithiumprocessing facilities. Until 1991, lithium was discharged into a losing reach of West Valley Creek, thus introducing lithium into the ground-water system. The potential for cross-contamination between the ground-water and surface-water systems is great, as demonstrated by the detection of lithium in ground water and surface water downstream and downgradient from the two lithium-processing facilities. The lithium that was discharged into the creek acts as a conservative tracer in gaining reaches of West Valley Creek, maintaining a mass balance and characteristic isotopic signature. Lithium-7/lithium-6 ratios were

  18. 1982 environmental-monitoring program report for the West Valley Demonstration Project site

    International Nuclear Information System (INIS)

    1983-05-01

    This report is prepared and submitted in accordance with the requirements of DOE Order 5484.1 and presents environmental monitoring program data collected at the West Valley Demonstration Project (WVDP) site from February 26, 1982, through December 31, 1982. The WVDP objective is to solidify approximately 600,000 gallons of high-level liquid radioactive waste stored at the former Nuclear Fuel Services reprocessing facility at West Valley, New York. Nuclear Fuel Services conducted an environmental monitoring program in accordance with Nuclear Regulatory Commission requirements which were appropriate for shutdown maintenance operations conducted at the site. That program was embraced by West Valley Nuclear Services Company (WVNS) at the time of transition (February 26, 1982) and will be modified to provide a comprehensive monitoring program in preparation for waste solidification operations scheduled for startup in June 1988. As such, the data presented in this report is considered preoperational in nature in accordance with DOE Order 5484.1, Chapter III, Paragraph 1. The environmental monitoring program planned for the operating phase of the project will be fully implemented by fiscal year 1985 and will provide at least two years of preoperational data prior to startup

  19. Modelling of the behaviour of a UF_6 container in a fire

    International Nuclear Information System (INIS)

    Pinton, Eric

    1996-01-01

    This thesis is justified by the safety needs about storage and transport of UF_6 containers. To define their behaviour under fire conditions, a modelling was developed. Before tackling the numerical modelling, a phenomenological interpretation with experimental results of containers inside a furnace (800 C) during a fixed period was carried out. The internal heat transfers were considerably improved with these results. The 2D elaborated model takes into account most of the physical phenomena encountered in this type of situation (boiling, evaporation, condensation, radiant heat transfers through an absorbing gas, convection, pressurisation, thermal contact resistance, UF_6 expansion, solid core sinking in the liquid, elastic and plastic deformations of the steel container). This model was successfully confronted with experiments. (author) [fr

  20. Calculational criticality analyses of 10- and 20-MW UF6 freezer/sublimer vessels

    International Nuclear Information System (INIS)

    Jordan, W.C.

    1993-02-01

    Calculational criticality analyses have been performed for 10- and 20-MW UF 6 freezer/sublimer vessels. The freezer/sublimers have been analyzed over a range of conditions that encompass normal operation and abnormal conditions. The effects of HF moderation of the UF 6 in each vessel have been considered for uranium enriched between 2 and 5 wt % 235 U. The results indicate that the nuclearly safe enrichments originally established for the operation of a 10-MW freezer/sublimer, based on a hydrogen-to-uranium moderation ratio of 0.33, are acceptable. If strict moderation control can be demonstrated for hydrogen-to-uranium moderation ratios that are less than 0.33, then the enrichment limits for the 10-MW freezer/sublimer may be increased slightly. The calculations performed also allow safe enrichment limits to be established for a 20-NM freezer/sublimer under moderation control

  1. Releases of UF6 to the atmosphere after a potential fire in a cylinder storage yard

    International Nuclear Information System (INIS)

    Lombardi, D.A.; Williams, W.R.; Anderson, J.C.

    1997-01-01

    Uranium hexafluoride (UF 6 ), a toxic material, is stored in just over 6200 cylinders at the K-25 site in Oak Ridge, Tennessee. The safety analysis report (SAR) for cylinder yard storage operations at the plant required the development of accident scenarios for the potential release of UF 6 to the atmosphere. In accordance with DOE standards and guidance, the general approach taken in this SAR was to examine the functions and contents of the cylinder storage yards to determine whether safety-significant hazards were present for workers in the immediate vicinity, workers on-site, the general public off-site, or the environment. and to evaluate the significance of any hazards that were found. A detailed accident analysis was performed to determine a set of limiting accidents that have potential for off-site consequences. One of the limiting accidents identified in the SAR was the rupture of a cylinder engulfed in a fire

  2. Sampling and characterization of aerosols formed in the atmospheric hydrolysis of UF6

    International Nuclear Information System (INIS)

    Bostick, W.D.; McCulla, W.H.; Pickrell, P.W.; Branam, D.A.

    1983-01-01

    When gaseous UF 6 is released into the atmosphere, it rapidly reacts with ambient moisture to form an aerosol of uranyl fluoride and HF. As part of our Safety Analysis program, we have performed several experimental releases of UF 6 (from natural uranium) in contained volumes in order to investigate techniques for sampling and characterizing the aerosol materials. The aggregrate particle morphology and size distribution have been found to be dependent upon several conditions, including the relative humidity at the time of the release and the elapse time after the release. Aerosol composition and settling rate have been investigated using isokinetic samplers for the separate collection of UO 2 F 2 and HF, and via laser spectroscopic remote sensing (Mie scatter and infrared spectroscopy). 8 references

  3. The regulations and the problems of their implementation in UF6 transport

    International Nuclear Information System (INIS)

    Devillers, C.; Grenier, M.; Ringot, C.; Warniez, P.

    1988-12-01

    UF 6 is currently transported in packagings which were developed in the sixties - standardized and used all over the world, these packagings perform their duty adequately. Nevertheless, the growing amounts of UF 6 and the changes in the regulations now raises the problem of compliance of these packagings with the latter. The problems which deserve special attention are: selection of the packaging type in terms of the origin and the enrichment, design of valve covers, behaviour at low temperatures, regulatory requirements in handling, tying down cleaning and unloading, allowable dose rate increase in case of minor mishaps, behaviour in fire, taking into account the toxicity, identification of special features required in the case of controlled moderation of fissile packages, transport conditions of empty packagings containing heels. In this paper are reviewed the results of this analysis, which is limited to the case of transport using cylinders of 48Y and 30B

  4. West Valley demonstration project: Implementation of the kerosene mitigation plan

    International Nuclear Information System (INIS)

    Blickwedehl, R.R.; Goodman, J.; Valenti, P.J.

    1987-05-01

    An aggressive program was implemented to mitigate the migration of radioactive kerosene believed to have originated from the West Valley NRC-Licensed Disposal Area (NDA) disposal trenches designated as SH-10 and SH-11 (Special Holes 10 and 11). This report provides a historical background of the events leading to the migration problem, the results of a detailed investigation to determine the location and source of the kerosene migration, the remediation plan to mitigate the migration, and the actions taken to successfully stabilize the kerosene. 7 refs., 19 figs., 1 tab

  5. Analysis of an indirect neutron signature for enhanced UF_6 cylinder verification

    International Nuclear Information System (INIS)

    Kulisek, J.A.; McDonald, B.S.; Smith, L.E.; Zalavadia, M.A.; Webster, J.B.

    2017-01-01

    The International Atomic Energy Agency (IAEA) currently uses handheld gamma-ray spectrometers combined with ultrasonic wall-thickness gauges to verify the declared enrichment of uranium hexafluoride (UF_6) cylinders. The current method provides relatively low accuracy for the assay of "2"3"5U enrichment, especially for natural and depleted UF_6. Furthermore, the current method provides no capability to assay the absolute mass of "2"3"5U in the cylinder due to the localized instrument geometry and limited penetration of the 186-keV gamma-ray signature from "2"3"5U. Also, the current verification process is a time-consuming component of on-site inspections at uranium enrichment plants. Toward the goal of a more-capable cylinder assay method, the Pacific Northwest National Laboratory has developed the hybrid enrichment verification array (HEVA). HEVA measures both the traditional 186-keV direct signature and a non-traditional, high-energy neutron-induced signature (HEVA_N_T). HEVA_N_T enables full-volume assay of UF_6 cylinders by exploiting the relatively larger mean free paths of the neutrons emitted from the UF_6. In this work, Monte Carlo modeling is used as the basis for characterizing HEVA_N_T in terms of the individual contributions to HEVA_N_T from nuclides and hardware components. Monte Carlo modeling is also used to quantify the intrinsic efficiency of HEVA for neutron detection in a cylinder-assay geometry. Modeling predictions are validated against neutron-induced gamma-ray spectra from laboratory measurements and a relatively large population of Type 30B cylinders spanning a range of enrichments. Implications of the analysis and findings on the viability of HEVA for cylinder verification are discussed, such as the resistance of the HEVA_N_T signature to manipulation by the nearby placement of neutron-conversion materials.

  6. UF6 reconversion experience by means of Sumitomo ADU process at JCO

    International Nuclear Information System (INIS)

    Ogawa, H.; Yamazaki, N.

    1994-01-01

    Since 1973, Japan Nuclear Fuel Conversion Co., Ltd. (JCO), a leading company in Japan on nuclear fuel manufacturing, has been involved in UF 6 reconversion to ceramic grade uranium dioxide (UO 2 ) for LWR fuel by means of the original ADU process developed by Sumitomo Metal Mining Co., Ltd.. This paper deals with the details of the Sumitomo ADU process as well as the performance results of it, especially from the standpoint of product quality

  7. Computer-optimized γ-NDA geometries for uranium enrichment verification of gaseous UF6

    International Nuclear Information System (INIS)

    Wichers, V.A.; Aaldijk, J.K.; Betue, P.A.C. de; Harry, R.J.S.

    1993-05-01

    An improved collimator pair of novel design tailored for deposit independent enrichment verification of gaseous UF 6 at low pressures in cascade-to-header pipes of small diameters in centrifuge enrichment plants is presented. The designs are adapted for use in a dual-geometry arrangement for simultaneous measurements with both detection geometries. The average measurement time with the dual-geometry arrangement is approximately half an hour for deposit-to-gas activity ratios as high as 20. (orig.)

  8. Materials considerations for UF6 gas-core reactor. Interim report for preliminary design study

    International Nuclear Information System (INIS)

    Wagner, P.

    1977-04-01

    The limiting materials problem in a high-temperature UF 6 core reactor is the corrosion of the core containment vessel. The UF 6 , the lower fluorides of uranium, and the fluorine that exist at the anticipated reactor operating conditions (1000 K and about one atmosphere UF 6 ) are all corrosive. Because of this, the materials evaluation effort for this reactor design study has concentrated on the identification of a viable system for the containment vessel that meets both the materials and neutronic requirements. A study of the literature has revealed that the most promising corrosion-resistant candidates are Ni or Ni-Al alloys. One of the conclusions of this work is that the containment vessel use a nickel liner or clad since the use of Ni as a structural member is precluded by its relative blackness to thermal neutrons. Estimates of corrosion rates of Ni and Ni-Al alloys, the effects of the pressure and temperature of F 2 on the corrosion rates, calculated equilibrium gas compositions at reactor core operating conditions, suggested methods of fabrication, and recommendations for future research and development are included

  9. UF6 Density and Mass Flow Measurements for Enrichment Plants using Acoustic Techniques

    Energy Technology Data Exchange (ETDEWEB)

    Good, Morris S.; Smith, Leon E.; Warren, Glen A.; Jones, Anthony M.; Ramuhalli, Pradeep; Roy, Surajit; Moran, Traci L.; Denslow, Kayte M.; Longoni, Gianluca

    2017-09-01

    A key enabling capability for enrichment plant safeguards being considered by the International Atomic Energy Agency (IAEA) is high-accuracy, noninvasive, unattended measurement of UF6 gas density and mass flow rate. Acoustic techniques are currently used to noninvasively monitor gas flow in industrial applications; however, the operating pressures at gaseous centrifuge enrichment plants (GCEPs) are roughly two orders magnitude below the capabilities of commercial instrumentation. Pacific Northwest National Laboratory is refining acoustic techniques for estimating density and mass flow rate of UF6 gas in scenarios typical of GCEPs, with the goal of achieving 1% measurement accuracy. Proof-of-concept laboratory measurements using a surrogate gas for UF6 have demonstrated signatures sensitive to gas density at low operating pressures such as 10–50 Torr, which were observed over the background acoustic interference. Current efforts involve developing a test bed for conducting acoustic measurements on flowing SF6 gas at representative flow rates and pressures to ascertain the viability of conducting gas flow measurements under these conditions. Density and flow measurements will be conducted to support the evaluation. If successful, the approach could enable an unattended, noninvasive approach to measure mass flow in unit header pipes of GCEPs.

  10. The state-of-the-practice in low enriched UF6 isotopic measurements in the European Community: results of REIMEP UF6

    International Nuclear Information System (INIS)

    Bolle, W. de; Damen, R.; Bievre, P. de; Nagel, W.; Meyer, H.; Lycke, W.; Wolters, W.H.

    1991-01-01

    After the interruption of the SALE programme, CBNM has established a Regular European Interlaboratory Measurement Evaluation Programme (REIMEP) with the support of the ESARDA Working Group for techniques and standards for destructive analysis (WGDA), the ESARDA Working Group for techniques and standards for non-destructive analysis (WGNDA) and the IAEA. On the basis of a questionnaire with answers from 41 laboratories, 36 laboratories have announced their interest for such a programme. In this paper we report on the 1986/87 round of the programme establishing the measurement capability or State Of the Practice in UF 6 isotopic measurements by methods left at the discretion of the participants (thermal ionization mass spectrometry, electron impact mass spectrometry and gamma-ray spectrometry). Pictures of the State Of the Practice are presented as graphs displaying participants results

  11. Photochemical removal of NpF6 and PuF6 from UF6 gas streams

    International Nuclear Information System (INIS)

    Beitz, J.V.; Williams, C.W.

    1990-01-01

    A novel photochemical method of removing reactive fluorides from UF 6 gas has been discovered. This method reduces generated waste to little more than the volume of the removed impurities, minimizes loss of UF 6 , and can produce a recyclable by-product, fluorine gas. In our new method, impure UF 6 , is exposed to ultraviolet light which dissociates the UF 6 to UF 5 and fluorine atom. Impurities which chemically react with UF 5 are reduced and form solid compounds easily removed from the gas while UF 5 is converted back to UF 6 . Proof-of-concept testing involved UF 6 containing NpF 6 and PuF 6 with CO added as a fluorine atom scavenger. In a single photolysis step, greater than 5000-fold reduction of PuF 6 was demonstrated while reducing NpF 6 by more than 40-fold. This process is likely to remove corrosion and fission product fluorides that are more reactive than UF 6 and has been demonstrated without an added fluorine atom scavenger by periodically removing photogenerated fluorine gas. 44 refs., 3 figs., 2 tabs

  12. Evaluation of a dry process for conversion of U-AVLIS product to UF6. Milestone U361

    International Nuclear Information System (INIS)

    1992-05-01

    A technical and engineering evaluation has been completed for a dry UF 6 production system to convert the product of an initial two-line U-AVLIS plant. The objective of the study has been to develop a better understanding of process design requirements, capital and operating costs, and demonstration requirements for this alternate process. This report summarizes the results of the study and presents various comparisons between the baseline and alternate processes, building on the information contained in UF 6 Product Alternatives Review Committee -- Final Report. It also provides additional information on flowsheet variations for the dry route which may warrant further consideration. The information developed by this study and conceptual design information for the baseline process will be combined with information to be developed by the U-AVLIS program and by industrial participants over the next twelve months to permit a further comparison of the baseline and alternate processes in terms of cost, risk, and compatibility with U-AVLIS deployment schedules and strategies. This comparative information will be used to make a final process flowsheet selection for the initial U-AVLIS plant by March 1993. The process studied is the alternate UF 6 production flowsheet. Process steps are (1) electron-beam distillation to reduce enriched product iron content from about 10 wt % or less, (2) hydrofluorination of the metal to UF 4 , (3) fluorination of UF 4 to UF 6 , (4) cold trap collection of the UF 6 product, (5) UF 6 purification by distillation, and (6) final blending and packaging of the purified UF 6 in cylinders. A preliminary system design has been prepared for the dry UF 6 production process based on currently available technical information. For some process steps, such information is quite limited. Comparisons have been made between this alternate process and the baseline plant process for UF 6 production

  13. Scoping study to expedite development of a field deployable and portable instrument for UF6 enrichment assay

    OpenAIRE

    Chan, CYG; Valentine, JD; Russo, RE

    2017-01-01

    The primary objective of the present study is to identity the most promising, viable technologies that are likely to culminate in an expedited development of the next-generation, field-deployable instrument for providing rapid, accurate, and precise enrichment assay of uranium hexafluoride (UF6). UF6 is typically involved, and is arguably the most important uranium compound, in uranium enrichment processes. As the first line of defense against proliferation, accurate analytical techniques t...

  14. A West Valley Demonstration Project Milestone - Achieving Certification to Ship Waste to the Nevada Test Site

    International Nuclear Information System (INIS)

    Jackson, J. P.; Pastor, R. S.

    2002-01-01

    The West Valley Demonstration Project (WVDP) has successfully pretreated and vitrified nearly all of the 600,000 gallons of liquid high-level radioactive waste that was generated at the site of the only commercial nuclear fuel reprocessing plant to have operated in the United States. Low-level waste (LLW) generated during the course of the cleanup effort now requires disposal. Currently the WVDP only ships Class A LLW for off-site disposal. It has been shipping Class A wastes to Envirocare of Utah, Inc. since 1997. However, the WVDP may also have a future need to ship Class B and Class C waste, which Envirocare is not currently authorized to accept. The Nevada Test Site (NTS), a U.S. Department of Energy (DOE) facility, can accept all three waste classifications. The WVDP set a goal to receive certification to begin shipping Class A wastes to NTS by 2001. Formal certification/approval was granted by the DOE Nevada Operations Office on July 12, 2001. This paper discusses how the WVDP contractor, West Valley Nuclear Services Company (WVNSCO), completed the activities required to achieve NTS certification in 2001 to ship waste to its facility. The information and lessons learned provided are significant because the WVDP is the only new generator receiving certification based on an NTS audit in January 2001 that resulted in no findings and only two observations--a rating that is unparalleled in the DOE Complex

  15. Calculations of electronic structure of UF6 molecule and crystal UO2 with relativistic pseudopotential

    International Nuclear Information System (INIS)

    Ehvarestov, R.A.; Panin, A.I.; Bandura, A.V.

    2008-01-01

    Account of relativistic effects on the properties of uranium hexafluoride is testified. Detailed comparison of single electron energies spectrum revealed in nonrelativistic (by Hartree-Fock method), relativistic (by Dirac-Fock method), and scalar-relativistic (using relativistic potential of atomic uranium frame) has been conducted. Optimization procedures of atomic basis in LCAO calculations of molecules and crystals permissive taking into account distortion of atomic orbitals when chemical bonding are discussed, and optimization effect of atomic basis on the results of scalar-relativistic calculations of UF 6 molecule properties is analyzed. Calculations of electronic structure and properties of UO 2 crystal having relativistic and nonrelativistic pseudopotentials have been realized [ru

  16. Development and design of a UF6 gas pressure meter for 42 mm pipes

    International Nuclear Information System (INIS)

    Peters, E.; Wichers, V.A.

    1995-08-01

    X-ray fluorescence (XRF) has proved to be a feasible method of measuring the pressure of UF 6 -gas for enrichment verification purposes. Complications will arise under extreme conditions, such as high uranium deposit to gas ratios, pipe diameters smaller than 40 mm and pressures less than 100 Pa. This report presents an experimental analysis of the XRF method for design worst case conditions for 42 outer diameter cascade-to-header pipes and the development of a prototype measurement device. This prototype is integrated in the construction of the enrichment verification system. (orig.)

  17. Method of absorbing UF6 from gaseous mixtures in alkamine absorbents

    International Nuclear Information System (INIS)

    Lafferty, R.H.; Smiley, S.H.; Radimer, K.J.

    1976-01-01

    A method is described for recovering UF 6 from gaseous mixtures by absorption in a liquid. The liquid absorbent must have a relatively low viscosity and at least one component of the absorbent is an alkamine having less than 3 carbon atoms bonded to the amino nitrogen, less than 2 of the carbon atoms other than those bonded to the amino nitrogen are free of the hydroxy radical and precipitate the absorbed uranium from the absorbent. At least one component of the absorbent is chosen from the group consisting of ethanolamine, diethanolamine, and 3-methyl-3-amino-propane-diol-1,2

  18. Finite element modelling of fire situations in UF6 transport containers

    International Nuclear Information System (INIS)

    Basombrio, F.G.

    1996-01-01

    In this report we describe some runs made with the code FASES2. They concern different situations associated to fires originated by accidents in the transport of containers filled with UF6. Such situations have been inspired in cases taken from the current literature, and related to numerical modelling or experiments. We aim to consign the most relevant aspects of such runs, with the future purpose of comparing them with the predictions made with simpler lumped models. In such a way, it will be possible to calibrate the simple models with the results coming from detailed models. (author). 6 refs., 12 figs

  19. Recent characterization activities of Midway Valley as a potential repository surface facility site

    International Nuclear Information System (INIS)

    Gibson, J.D.; Wesling, J.R.; Swan, F.H.; Bullard, T.F.

    1992-01-01

    Midway Valley, located at the eastern base of Yucca Mountain, Nye County, Nevada, has been identified as a possible location for the surface facilities of a potential high-level nuclear-waste repository. This structural and topographic valley is bounded by two north- trending, down-to-the-west normal faults: the Paintbrush Canyon fault on the east and the Bow Ridge fault on the west. Surface and near-surface geological data have been acquired from Midway Valley during the past three years with particular emphasis on evaluating the existence of Quaternary faults. A detailed (1:6000) surficial geological map has been prepared based on interpretation of new and existing aerial photographs, field mapping, soil pits, and trenches. No evidence was found that would indicate displacement of these surficial deposits along previously unrecognized faults. However, given the low rates of Quaternary faulting and the extensive areas that are covered by late Pleistocene to Holocene deposits south of Sever Wash, Quaternary faulting between known faults cannot be precluded based on surface evidence alone. Middle to late Pleistocene alluvial fan deposits (Unit Q3) exist at or near the surface throughout Midway Valley. Confidence is increased that the potential for surface fault rupture in Midway Valley can be assessed by excavations that expose the deposits and soils associated with Unit Q3 or older units (middle Pleistocene or earlier)

  20. Poultry Slaughter facility Zambezi Valley, Mozambique

    NARCIS (Netherlands)

    Vernooij, A.G.; Wilschut, S.

    2015-01-01

    This business plan focuses on the establishment of a slaughterhouse, one of the essential elements of a sustainable and profitable poultry meat value chain. There is a growing demand for poultry meat in the Zambezi Valley, and currently a large part of the consumed broilers comes from other parts of

  1. Business plan Hatchery Facility Zambezi Valley, Mozambique

    NARCIS (Netherlands)

    Vernooij, A.G.; Wilschut, S.

    2015-01-01

    This business plan focuses on the establishment of a hatchery, one of the essential elements of a sustainable and profitable poultry meat value chain. There is a growing demand for poultry meat in the Zambezi Valley, and currently a large part of the consumed broilers comes from other parts of the

  2. West Valley Reprocessing Plant. Safety analysis report, supplement 20

    International Nuclear Information System (INIS)

    1976-01-01

    Supplement 20 is comprised of changed pages for the SAR which reflect: (1) the change in design basis fuel fed to the process from a minimum of 180 days after reactor discharge to a minimum of 210 days and an effective 24 months after reactor discharge; (2) the design objective of NFS that the concentrations of radionuclides, other than tritium, will not exceed the concentration limits of 10 CFR 20, Appendix B, Table II, column 2, when measured at the discharge from NFS' lagoon system to the on-site waterway; (3) incorporation of modifications to fuel receiving and storage area; (4) an updating of the general information presented in Chapter 1.0; and (5) additional data from the new meteorological tower at West Valley and recent changes in demographic projections

  3. WEST VALLEY DEMONSTRATION PROJECT ANNUAL SITE ENVIRONMENTAL REPORT CALENDAR YEAR 2002

    International Nuclear Information System (INIS)

    2003-01-01

    This annual environmental monitoring report for the West Valley Demonstration Project (WVDP or Project) is published to inform those with interest about environmental conditions at the WVDP. In accordance with U.S. Department of Energy (DOE) Order 231.1, Environment, Safety, and Health Reporting, the report summarizes calendar year (CY) 2002 environmental monitoring data so as to describe the performance of the WVDP's environmental management system, confirm compliance with standards and regulations, and highlight important programs. In 2002, the West Valley Demonstration Project, the site of a DOE environmental cleanup activity operated by West Valley Nuclear Services Co. (WVNSCO), was in the final stages of stabilizing high-level radioactive waste (HLW) that remained at the site after commercial nuclear fuel reprocessing had been discontinued in the early 1970s. The Project is located in western New York State, about 30 miles south of Buffalo, within the New York State-owned Western New York Nuclear Service Center (WNYNSC). The WVDP is being conducted in cooperation with the New York State Energy Research and Development Authority (NYSERDA). Ongoing work activities at the WVDP during 2002 included: (1) completing HLW solidification and melter shutdown; (2) shipping low-level radioactive waste off-site for disposal; (3) constructing a facility where large high-activity components can be safely packaged for disposal; (4) packaging and removing spent materials from the vitrification facility; (5) preparing environmental impact statements for future activities; (6) removing as much of the waste left behind in waste tanks 8D-1 and 8D-2 as was reasonably possible; (7) removing storage racks, canisters, and debris from the fuel receiving and storage pool, decontaminating pool walls, and beginning shipment of debris for disposal; (8) ongoing decontamination in the general purpose cell and the process mechanical cell (also referred to as the head end cells); (9) planning

  4. WEST VALLEY DEMONSTRATION PROJECT ANNUAL SITE ENVIRONMENTAL REPORT CALENDAR YEAR 2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-09-12

    This annual environmental monitoring report for the West Valley Demonstration Project (WVDP or Project) is published to inform those with interest about environmental conditions at the WVDP. In accordance with U.S. Department of Energy (DOE) Order 231.1, Environment, Safety, and Health Reporting, the report summarizes calendar year (CY) 2002 environmental monitoring data so as to describe the performance of the WVDP's environmental management system, confirm compliance with standards and regulations, and highlight important programs. In 2002, the West Valley Demonstration Project, the site of a DOE environmental cleanup activity operated by West Valley Nuclear Services Co. (WVNSCO), was in the final stages of stabilizing high-level radioactive waste (HLW) that remained at the site after commercial nuclear fuel reprocessing had been discontinued in the early 1970s. The Project is located in western New York State, about 30 miles south of Buffalo, within the New York State-owned Western New York Nuclear Service Center (WNYNSC). The WVDP is being conducted in cooperation with the New York State Energy Research and Development Authority (NYSERDA). Ongoing work activities at the WVDP during 2002 included: (1) completing HLW solidification and melter shutdown; (2) shipping low-level radioactive waste off-site for disposal; (3) constructing a facility where large high-activity components can be safely packaged for disposal; (4) packaging and removing spent materials from the vitrification facility; (5) preparing environmental impact statements for future activities; (6) removing as much of the waste left behind in waste tanks 8D-1 and 8D-2 as was reasonably possible; (7) removing storage racks, canisters, and debris from the fuel receiving and storage pool, decontaminating pool walls, and beginning shipment of debris for disposal; (8) ongoing decontamination in the general purpose cell and the process mechanical cell (also referred to as the head end cells); (9

  5. Hydraulic breakage of tanks for the transport of uranium hexafluoride (UF6)

    International Nuclear Information System (INIS)

    Biaggio, A.L.; Lee Gonzales, H.M.; Lopez Vietri, J.R.; Novo, R.G.

    1987-01-01

    To begin with, the tank models that are proposed by the international norms for the transport and storage of hexafluoride of uranium (UF 6 ) are briefly described. The operations related to the transport in its different forms are also described, particularly those that can produce the hydraulic breakage of tanks during its course or in later stages, when incorrectly performed. With reference to those operations, the most important physicochemical properties of UF 6 as for safety are analyzed. A quantitative evaluation of the deviations of parameters that are controlled during the heating of tanks, comparing them with the normative nominal values, is performed. Adopting some simplifying hypothesis, a general study, applicable to all tank models proposed by norms, is carried out to determine the temperature at which the hydraulic breakage takes place when they are heated in closed-valve conditions. A curve is obtained by plotting the hydraulic breakage temperature against the filling degree. To conclude, the values obtained are compared with the results of other theoretical studies on this subject. (Author)

  6. Optimization of the isotopic analysis of UF6 by quadrupole mass spectrometry technique

    International Nuclear Information System (INIS)

    Porto, Peterson

    2006-01-01

    In the present work a procedure for determination of the isotopic ratio 238 U/ 235 U in UF 6 samples was established using a quadrupole mass spectrometer with ionization by electron impact and ion detection by Faraday cup or electron multiplier. For this, the following items were optimized in the spectrometer: the parameters in the ion source that provided the most intense peak, with good shape, for the corresponding mass of the most abundant isotope; the resolution that reduced the non linear effects and the number of analytic cycles that reduced the uncertainty in the results. The measurement process was characterized with respect to the effects of mass discrimination, linearity and memory effect. The mass discrimination showed to be linearly dependent of the sample pressure in the batch volume, for the pressure ranges from 0.15 to 0.30 mbar and from 0.30 to 0.40 mbar. The spectrometer was shown linear in the measurement of isotopic ratios between 0.005 and 0.045. The memory factor for the ion source and for the introduction system were, respectively, 1.000 ± 0.001 and 1.003 ± 0.003; the first one can be ignored, the second one can be eliminated by washing the batch volume with the new sample. A methodology for routine analysis of UF 6 samples and the determination of the uncertainties were set up in details as well. (author)

  7. Evaluation of coverage of enriched UF6 cylinder storage lots by existing criticality accident alarms

    International Nuclear Information System (INIS)

    Lee, B.L. Jr.; Dobelbower, M.C.; Woollard, J.E.; Sutherland, P.J.; Tayloe, R.W. Jr.

    1995-03-01

    The Portsmouth Gaseous Diffusion Plant (PORTS) is leased from the US Department of Energy (DOE) by the United States Enrichment Corporation (USEC), a government corporation formed in 1993. PORTS is in transition from regulation by DOE to regulation by the Nuclear Regulatory Commission (NRC). One regulation is 10 CFR Part 76.89, which requires that criticality alarm systems be provided for the site. PORTS originally installed criticality accident alarm systems in all building for which nuclear criticality accidents were credible. Currently, however, alarm systems are not installed in the enriched uranium hexafluoride (UF 6 ) cylinder storage lots. This report analyzes and documents the extent to which enriched UF 6 cylinder storage lots at PORTS are covered by criticality detectors and alarms currently installed in adjacent buildings. Monte Carlo calculations are performed on simplified models of the cylinder storage lots and adjacent buildings. The storage lots modelled are X-745B, X-745C, X745D, X-745E, and X-745F. The criticality detectors modelled are located in building X-343, the building X-344A/X-342A complex, and portions of building X-330 (see Figures 1 and 2). These criticality detectors are those located closest to the cylinder storage lots. Results of this analysis indicate that the existing criticality detectors currently installed at PORTS are largely ineffective in detecting neutron radiation from criticality accidents in most of the cylinder storage lots at PORTS, except sometimes along portions of their peripheries

  8. The approach of toxic and radiological risk equivalence in UF6 transport

    International Nuclear Information System (INIS)

    Ringot, C.; Hamard, J.

    1989-01-01

    After a brief description of the present situation concerning the safety of the transport of UF6 and the new regulation project which is being developed under the behalf of IAEA, the equivalence of radioactive and chemical risks is considered for UF6 transport regulations. The concept of low specific activity appearing misfitting to toxic gas, it is proposed a quantity limit of material, T 2 (equivalent to A 2 for radioactive materials), for packagings which do not resist to accidental conditions, (9 m drop, 800 0 C, 30 minutes fire environment). It is proposed that this limit is chosen as the release rate which is acceptable after the IAEA tests for packages having a capacity higher than T 2 kilograms. The fire being considered as the most severe situation for the toxic risk, different possible scenarios are described. This approach of risk equivalence leads to impose that the packaging resists a 800 0 C - 30 minutes fire and that in this condition the release is less than T 2 . The problem of the behaviour of the shell and the openings (in particular the valve) is raised in this context [fr

  9. Criticality Safety Evaluation for 30B and 48X UF6 Cylinders for Transportation and Storage

    International Nuclear Information System (INIS)

    Mokhatri, Homami Zahra; Nematollahi, Mohammadreza; Kamyab, Shahabeddin

    2011-01-01

    30B and 48X cylinders are two standard containers have been used for transportation and storage of uranium hexafluoride with 21/2-ton and 10-ton loading capacity, respectively. For the sake of nuclear safety, the long-term safe storage and transportation of the cylinders are necessary to be concerned. Safe limits in handling and storage of 30B and 48X cylinders from the criticality safety considerations, has been investigated in this paper, by using the MCNP.4C code with ENDF/B-VI library data for the neutron cross sections. An infinite array model (with and without over pack) incorporating an internal H/U ratio of 0.088 was then developed to determine the optimal interstitial moderation. The maximum k eff value for the conditions of optimal interstitial moderation with the premise of no water leakage into the UF 6 cylinder has been shown to be 0.79209 ± 0.0011 for the 30B cylinder and 0.7625±0.0013 for 48X cylinder with 5 wt % 235 U enrichment. Based on this evaluation, the 30B and 48X UF 6 cylinders with 5 wt % 235 U enrichment meet the 10 CFR part 71 criteria for Fissile Class I packages, even in the worst case, and has a Transport Index (TI) of zero for criticality safety purposes

  10. Uranium isotope exchange between gaseous UF6 and solid UF5

    International Nuclear Information System (INIS)

    Yato, Yumio; Kishimoto, Yoichiro; Sasao, Nobuyuki; Suto, Osamu; Funasaka, Hideyuki

    1996-01-01

    Based on a collision model, a new rate equation is derived for uranium isotope exchange between gaseous UF 6 and solid UF 5 by considering the number of UF 5 molecules on the solid surface to be dependent on time. The reaction parameters included in the equation are determined from the experimental data and compared with the previous ones. A remarkable agreement is found between the particle sizes of UF 5 estimated from the reaction parameter and from the direct observation with an electron microscope. The rate equation given in this work fully satisfies the related mass conservation and furthermore includes explicitly the terms related to the UF 6 density and the mean size of UF 5 particles, both of which are considered to cause an important effect on the reaction. This remarkable feature facilitates the simulation studies on this reaction under various conditions. The long term behavior of a simulated exchange reaction is studied under the condition considered to be close to that in a recovery zone of the MLIS process. The result indicates that the reaction is virtually limited to the solid surface under this conditions and thus the depletion of 235 UF 5 concentration averaged over the whole UF 5 particles is not significant even after 200 h of the exchange reaction

  11. Computational fluid dynamics tracking of UF6 reaction products release into a gaseous diffusion plant cell housing

    International Nuclear Information System (INIS)

    Wendel, M.W.; Chen, N.C.J.; Kim, S.H.; Taleyarkhan, R.P.; Keith, K.D.; Schmidt, R.W.

    1996-01-01

    A three-dimensional (3-D) computational fluid dynamics (CFD) model has been developed using CFDS-FLOW3D Version 3.3 to model the transport of aerosol products formed during a release of uranium hexafluoride (UF 6 ) into a gaseous diffusion plant (GDP) process building. As part of a facility-wide safety evaluation, a one-dimensional (1-D) analysis of aerosol/vapor transport following such an hypothesized severe accident is being performed. The objective of this study is to supplement the 1-D analysis with more detailed 3-D results. Specifically, the goal is to quantify the distribution of aerosol passing out of the process building during the hypothetical accident. This work demonstrates a useful role for CFD in large 3-D problems, where some experimental data are available for calibrating key parameters and the desired results are global (total time-integrated aerosol flow rates across a few boundary surfaces) as opposed to local velocities, temperatures, or heat transfer coefficients

  12. An overview of waste management systems at the West Valley demonstration project

    International Nuclear Information System (INIS)

    McIntosh, T.W.; Bixby, W.W.; Krauss, J.E.; Leap, D.R.

    1988-01-01

    In 1980, the United States Congress passed into law the West Valley Demonstration Project Act authorizing the Department of Energy (DOE) to conduct a nuclear waste management project at a former commercial nuclear fuel reprocessing facility located in West Valley, New York. The Project's main objective is to solidify approximately two million litres of high-level radioactive liquid waste into a form suitable for transport to a federal repository for final disposal. The majority of the liquid waste was produced as a by-product of the PUREX extraction process and is stored in an underground steel tank. A waste characterization program has shown that the neutralized waste has settled into two distinct layers: a clear alkaline liquid (supernatant) layer and a dense precipitate (sludge) layer. The principle radioactive elements in the waste are cesium 137 (supernatant) and strontium 90 (sludge). This paper describes the overall project strategy, the waste management systems, the present project engineering and construction status and the project schedule leading to radioactive operation

  13. Measurement of 235U content and flow of UF6 using delayed neutrons or gamma rays following induced fission

    International Nuclear Information System (INIS)

    Stromswold, D.C.; Peurrung, A.J.; Reeder, P.L.; Perkins, R.W.

    1996-06-01

    Feasibility experiments conducted at Pacific Northwest National Laboratory demonstrate that either delayed neutrons or energetic gamma rays from short-lived fission products can be used to monitor the blending of UF 6 gas streams. A 252 Cf neutron source was used to induce 235 U fission in a sample, and delayed neutrons and gamma rays were measured after the sample moved open-quotes down-stream.close quotes The experiments used a UO 2 powder that was transported down the pipe to simulate the flowing UF 6 gas. Computer modeling and analytic calculation extended the test results to a flowing UF 6 gas system. Neutron or gamma-ray measurements made at two downstream positions can be used to indicate both the 235 U content and UF 6 flow rate. Both the neutron and gamma-ray techniques have the benefits of simplicity and long-term reliability, combined with adequate sensitivity for low-intrusion monitoring of the blending process. Alternatively, measuring the neutron emission rate from (a, n) reactions in the UF 6 provides an approximate measure of the 235 U content without using a neutron source to induce fission

  14. Uniform deposition of uranium hexafluoride (UF6): Standardized mass deposits and controlled isotopic ratios using a thermal fluorination method

    Energy Technology Data Exchange (ETDEWEB)

    McNamara, Bruce K.; O’Hara, Matthew J.; Casella, Andrew M.; Carter, Jennifer C.; Addleman, R. Shane; MacFarlan, Paul J.

    2016-07-01

    Abstract: We report a convenient method for the generation of volatile uranium hexafluoride (UF6) from solid uranium oxides and other uranium compounds, followed by uniform deposition of low levels of UF6 onto sampling coupons. Under laminar flow conditions, UF6 is shown to interact with surfaces within the chamber to a highly predictable degree. We demonstrate the preparation of uranium deposits that range between ~0.01 and 470±34 ng∙cm-2. The data suggest the method can be extended to creating depositions at the sub-picogram∙cm-2 level. Additionally, the isotopic composition of the deposits can be customized by selection of the uranium source materials. We demonstrate a layering technique whereby two uranium solids, each with a different isotopic composition, are employed to form successive layers of UF6 on a surface. The result is an ultra-thin deposit of UF6 that bears an isotopic signature that is a composite of the two uranium sources. The reported deposition method has direct application to the development of unique analytical standards for nuclear safeguards and forensics.

  15. Testing of the Model 48-14 overpack for UF6 cylinders

    International Nuclear Information System (INIS)

    Stitt, D.H.

    1983-01-01

    Shipment of UF 6 enriched to 1.0% or greater assay 235 U currently is done in either the 30-B overpack or the Paducah tiger overpack. The former contains a 2-1/2 ton cylinder, 30 in. in diameter, while the latter contains a 10-ton cylinder, 48 in. in diameter. There are apparent economy and safety considerations associated with shipping in the larger containers due to the reduced number of shipments and connect and disconnect operations. Further reductions in connect and disconnect operations and shipping costs could be achieved through use of the 14-ton cylinder for shipment of enriched material. With this thought, a program was initiated in 1980 to develop a protective overpack for the Model 48Y cylinder. Two prototype overpacks of wood and stainless steel construction were fabricated. The results from the drop tests and the thermal exposure test are presented

  16. Determination of the isotopic ratio 235U/238U in UF6 using quadrupole mass spectrometry

    International Nuclear Information System (INIS)

    Kusahara, Helena Sueco

    1979-01-01

    In this work measurements of isotope ratios 235 U / 23 '8U in uranium hexafluoride are carried out using a quadrupole mass spectrometer. The operational parameters, which affect the final precision of the results, are standardized. Optimized procedures for the preparation of uranium hexafluoride samples by fluorination of uranium oxides using cobalt trifluoride method are established. Careful attention is given to the process of purification of uranium hexafluoride samples by fractional distillation. Adequate statistical methods for analysing the results obtained for single ratio measurements as well as the ratio ' of isotopic ratios of sample and standard ar.e developed. A precision of about 10 -4 for single ratio measurements and accuracy of about 0,3% for the ratio of sample and standard ratios are obtained. These results agree with the values which have been obtained using magnetic mass spectrometers. The procedures and methods established in this work can be employed in the systematic uranium isotope analysis in UF 6 form. (author)

  17. Fission product range effects on HEU fissile gas monitoring for UF6 gas

    International Nuclear Information System (INIS)

    Munro, J.K. Jr.; Valentine, T.E.; Perez, R.B.

    1997-01-01

    The amount of 235 U in UF 6 flowing in a pipe can be monitored by counting gamma rays emitted from fission fragments carried along by the flowing gas. Neutron sources are mounted in an annular sleeve that is filled with moderator material and surrounds the pipe. This provides a source of thermal neutrons to produce the fission fragments. Those fragments that remain in the gas stream following fission are carried past a gamma detector. A typical fragment will be quite unstable, giving up energy as it decays to a more stable isotope with a significant amount of this energy being emitted in the form of gamma rays. A given fragment can emit several gamma rays over its lifetime. The gamma ray emission activity level of a distribution of fission fragments decreases with time. The monitoring system software uses models of these processes to interpret the gamma radiation counting data measured by the gamma detectors

  18. UF6 test loop for evaluation and implementation of international enrichment plant safeguards

    International Nuclear Information System (INIS)

    Cooley, J.N.; Fields, L.W.; Swindle, D.W. Jr.

    1987-06-01

    A functional test loop capable of simulating UF 6 flows, pressures, and pipe deposits characteristic of gas centrifuge enrichment plant piping has been designed and fabricated by the Enrichment Safeguards Program of Martin Marietta Energy Systems, Inc., for use by International Atomic Energy Agency (IAEA) at its Safeguards Analytical Laboratory in Seibersdorf, Austria. Purpose of the test loop is twofold: (1) to enable the IAEA to evaluate and to calibrate enrichment safeguards measurement instrumentation to be used in limited frequency-unannounced access (LFUA) inspection strategy measurements at gas centrifuge enrichment plants and (2) to train IAEA inspectors in the use of such instrumentation. The test loop incorporates actual sections of cascade header pipes from the centrifuge enrichment plants subject to IAEA inspections. The test loop is described, applications for its use by the IAEA are detailed, and results from an initial demonstration session using the test loop are summarized

  19. Theoretical study of relativistic effects in the electronic structure and chemical bonding of UF6

    International Nuclear Information System (INIS)

    Onoe, Jun; Takeuchi, Kazuo; Sekine, Rika; Nakamatsu, Hirohide; Mukoyama, Takeshi; Adachi, Hirohiko.

    1992-01-01

    We have performed the relativistic molecular orbital calculation for the ground state of UF 6 , using the discrete-variational Dirac-Slater method (DV-DS), in order to elucidate the relativistic effects in the electronic structure and chemical bonding. Compared with the electronic structure calculated by the non-relativistic Hartree-Fock-Slater (DV-X α )MO method, not only the direct relativistic effects (spin-orbit splitting etc), but also the indirect effect due to the change in screening core potential charge are shown to be important in the MO level structure. From the U-F bond overlap population analysis, we found that the U-F bond formation can be explained only by the DV-DS, not by the DV-X α . The calculated electronic structure in valence energy region (-20-OeV) and excitation energies in UV region are in agreement with experiments. (author)

  20. High frequency titration in non-aqueous solvents. Application to HF and UF6

    International Nuclear Information System (INIS)

    Neveu, Claude

    1965-01-01

    In this research thesis, the author first presents the main theoretical notions regarding high frequency titration, notably by studying characteristic curves, i.e. the titration meter indication with respect to conductibility. He reports the use of this method for the study of various reactions in non-aqueous medium: reaction of AlCl 3 with pyridine in acetonitrile, of AlCl 3 with HCl in tetrachloroethane and in nitromethane. He also reports the attempt of application of this method to the titration of HF in presence of UF 6 in CCl 4 as solvent, or by using F acceptors like BF 3 , PF 5 or ClF 3 as reactants [fr

  1. Development of on-line uranium enrichment monitor of gaseous UF6 for uranium enrichment plant

    International Nuclear Information System (INIS)

    Lu Xuesheng; Liu Guorong; Jin Huimin; Zhao Yonggang; Li Jinghuai; Hao Xueyuan; Ying Bin; Yu Zhaofei

    2013-01-01

    An on-line enrichment monitor was developed to measure the enrichment of UF 6 , flowing through the processing pipes in uranium enrichment plant. A Nal (Tl) detector was used to measure the count rates of the 185.7 keV γ-ray emitted from 235 U, and the total quantity of uranium was determined from thermodynamic characteristics of gaseous uranium hexafluoride. The results show that the maximum relative standard deviation is less than 1% when the measurement time is 120 s or more and the pressure is more than 2 kPa in the measurement chamber. Uranium enrichment of gaseous uranium hexafluoride in the output end of cascade can be monitored continuously by using the device. It should be effective for nuclear materials accountability verifications and materials balance verification at uranium enrichment plant. (authors)

  2. 235U enrichment determination on UF6 cylinders with CZT detectors

    Science.gov (United States)

    Berndt, Reinhard; Mortreau, Patricia

    2018-04-01

    Measurements of uranium enrichment in UF6 transit cylinders are an important nuclear safeguards verification task, which is performed using a non-destructive assay method, the traditional enrichment meter, which involves measuring the count rate of the 186 keV gamma ray. This provides a direct measure of the 235U enrichment. Measurements are typically performed using either high-resolution detectors (Germanium) with e-cooling and battery operation, or portable devices equipped with low resolution detectors (NaI). Despite good results being achieved when measuring Low Enriched Uranium in 30B type cylinders and natural uranium in 48Y type containers using both detector systems, there are situations, which preclude the use of one or both of these systems. The focus of this work is to address some of the recognized limitations in relation to the current use of the above detector systems by considering the feasibility of an inspection instrument for 235U enrichment measurements on UF6 cylinders using the compact and light Cadmium Zinc Telluride (CZT) detectors. In the present work, test measurements were carried out, under field conditions and on full-size objects, with different CZT detectors, in particular for situations where existing systems cannot be used e.g. for stacks of 48Y type containers with depleted uranium. The main result of this study shows that the CZT detectors, actually a cluster of four μCZT1500 micro spectrometers provide as good results as the germanium detector in the ORTEC Micro-trans SPEC HPGe Portable spectrometer, and most importantly in particular for natural and depleted uranium in 48Y cylinders.

  3. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: conversion of recycle uranium to UF6

    International Nuclear Information System (INIS)

    Roddy, J.W.; Blanco, R.E.; Finney, B.C.; Hill, G.S.; Moore, R.E.; Witherspoon, J.P.

    1977-04-01

    A cost/benefit study was made to determine the cost and effectiveness of various radioactive waste (radwaste) treatment systems for decreasing the amount of radioactive materials released from a model recycle uranium conversion and uranium hexafluoride (UF 6 ) production plant and to determine the radiological impact (dose commitment) of the released radioactive materials on the environment. This study is designed to assist the US NRC in defining the term ''as low as reasonably achievable'' as it applies to these nuclear facilities. The base case model plant is representative of a licensable UF 6 production plant and has an annual capacity of 1500 metric tons of uranium. Additional radwaste treatment systems are added to the base case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The cost for the added waste treatment operations and the corresponding dose commitments is calculated for each case. In the final analysis, radiological dose is plotted vs the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. The methodology used in estimating the costs is presented

  4. Thermodynamic properties of a high pressure subcritical UF6He gas volume (irradiated by an external source)

    International Nuclear Information System (INIS)

    Sterritt, D.E.; Lalos, G.T.; Schneider, R.T.

    1976-12-01

    A computer simulation study concerning a compressed fissioning UF 6 gas is presented. The compression is to be achieved by a ballistic piston compressor. Data on UF 6 obtained with this compressor were incorporated in the simulation study. As a neutron source to create the fission events in the compressed gas, a fast burst reactor was considered. The conclusion is that it takes a neutron flux in excess of 10 15 n/cm 2 -s to produce measurable increases in pressure and temperature, while a flux in excess of 10 19 n/cm 2 -s would probably damage the compressor

  5. West Valley Demonstration Project low-level and transuranic waste assay and methodology

    International Nuclear Information System (INIS)

    McVay, C.W.

    1987-03-01

    In the decontamination and decommissioning of the West Valley Nuclear Facility, waste materials are being removed and packaged in a variety of waste containers which require classification in accordance with USNRC 10 CFR 61 and DOE 5820.2 criteria. Low-Level and Transuranic waste assay systems have been developed to efficiently assay and classify the waste packages. The waste is assayed by segmented gamma scanning, passive neutron techniques, dose rate conversion, and/or radiochemical laboratory analysis. The systems are capable of handling all the waste forms currently packaged as part of the Project. The above systems produce a list of nuclides present with their concentrations and determines the classification of the waste packages based on criteria outlined in DOE Order 5820.2 and USNRC 10 CFR 61.55. 9 refs., 12 figs., 8 tabs

  6. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2008

    Energy Technology Data Exchange (ETDEWEB)

    West Valley Environmental Services LLC (WVES) and URS - Washington Division

    2009-09-24

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2008. The report summarizes the calendar year (CY) 2008 environmental monitoring program data at the WVDP so as to describe the performance of the WVDP’s environmental management system (EMS), confirm compliance with standards and regulations, and highlight important programs. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of the environment, continual improvement, prevention and/or minimization of pollution, public outreach, and stakeholder involvement. In addition to demonstrating compliance with environmental regulations and directives, evaluation of data collected in 2008 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  7. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2008

    International Nuclear Information System (INIS)

    2009-01-01

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2008. The report summarizes the calendar year (CY) 2008 environmental monitoring program data at the WVDP so as to describe the performance of the WVDP's environmental management system (EMS), confirm compliance with standards and regulations, and highlight important programs. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of the environment, continual improvement, prevention and/or minimization of pollution, public outreach, and stakeholder involvement. In addition to demonstrating compliance with environmental regulations and directives, evaluation of data collected in 2008 continued to indicate that WVDP activities pose no threat to public health or safety, or to the environment.

  8. Seismic investigation of the Nuclear Fuel Services, Inc., Reprocessing Plant at West Valley, New York

    International Nuclear Information System (INIS)

    Endebrock, E.G.; Bartholomew, R.J.; Bennett, J.G.; Brasier, R.I.; Corcoran, W.F.

    1978-03-01

    An investigation was undertaken to determine the earthquake level at which the Nuclear Fuel Service, Inc., Reprocessing Plant at West Valley, New York, could first experience a predefined structural failure. The effort was divided into tasks of evaluating soil-structure interaction, determining overall facility motion, and analyzing the substructures. The analysis included using two- and three-dimensional finite element computer codes. Shear wall failure, cell flexural failure (beam action), and foundation (pile) failure were identified as possible structural failure types. The cells that contain radioactive materials and that are required to confine such materials during an earthquake should remain intact up to 0.20 g's. At the same loading, the piles supporting the confinement cells could undergo displacements sufficient to cause fracture of piping between nonmonolithically connected cells

  9. Operating experience during high-level waste vitrification at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Valenti, P.J.; Elliott, D.I.

    1999-01-01

    This report provides a summary of operational experiences, component and system performance, and lessons learned associated with the operation of the Vitrification Facility (VF) at the West Valley Demonstration Project (WVDP). The VF was designed to convert stored high-level radioactive waste (HLW) into a stable waste form (borosilicate glass) suitable for disposal in a federal repository. Following successful completion on nonradioactive test, HLW processing began in July 1995. Completion of Phase 1 of HLW processing was reached on 10 June 1998 and represented the processing of 9.32 million curies of cesium-137 (Cs-137) and strontium-90 (Sr-90) to fill 211 canisters with over 436,000 kilograms of glass. With approximately 85% of the total estimated curie content removed from underground waste storage tanks during Phase 1, subsequent operations will focus on removal of tank heel wastes

  10. Heat transfer characteristics of UF6 in a container heated from outer surface. Pt. 1. Thermal hydraulic analysis method taking account of phase change and volume expansion

    International Nuclear Information System (INIS)

    Wataru, Masumi; Gomi, Yoshio; Yamakawa, Hidetsugu; Tsumune, Daisuke

    1995-01-01

    Natural UF6 is transported in a steel container from foreign countries to the enrichment plant in Japan. If the container meets fire accident, it is heated by fire (800degC) and rupture of the container may occur. For the safety point of view, it is necessary to know whether rupture occurs or not. Because UF6 has a radiological and chemical hazards, it is difficult to perform a demonstration test with UF6. So thermal calculation method has to be developed. The rupture is caused by UF6 gaseous pressure or volume expansion of liquid UF6. To know time history of internal pressure and temperature distribution in the container, it is important to evaluate thermal phenomena of UF6. When UF6 is heated, it changes from solid to liquid or gas at low temperature (64degC) and then its volume expands little by little. In this study, thermal calculation method has been developed taking phase change and thermal expansion of UF6 into account. In the calculation, a two-dimensional model is adopted and natural convection of liquid UF6 is analyzed. As a result of this study, numerical solutions have been obtained taking phase change and volume expansion into account. (author)

  11. PGDP [Paducah Gaseous Diffusion Plant]-UF6 handling, sampling, analysis and associated QC/QA and safety related procedures

    International Nuclear Information System (INIS)

    Harris, R.L.

    1987-01-01

    This document is a compilation of Paducah Gaseous Diffusion Plant procedures on UF 6 handling, sampling, and analysis, along with associated QC/QA and safety related procedures. It was assembled for transmission by the US Department of Energy to the Korean Advanced Energy Institute as a part of the US-Korea technical exchange program

  12. Uniform deposition of uranium hexafluoride (UF6): Standardized mass deposits and controlled isotopic ratios using a thermal fluorination method.

    Science.gov (United States)

    McNamara, Bruce K; O'Hara, Matthew J; Casella, Andrew M; Carter, Jennifer C; Addleman, R Shane; MacFarlan, Paul J

    2016-07-01

    We report a convenient method for the generation of volatile uranium hexafluoride (UF6) from solid uranium oxides and other U compounds, followed by uniform deposition of low levels of UF6 onto sampling coupons. Under laminar flow conditions, UF6 is shown to interact with surfaces within a fixed reactor geometry to a highly predictable degree. We demonstrate the preparation of U deposits that range between approximately 0.01 and 500ngcm(-2). The data suggest the method can be extended to creating depositions at the sub-picogramcm(-2) level. The isotopic composition of the deposits can be customized by selection of the U source materials and we demonstrate a layering technique whereby two U solids, each with a different isotopic composition, are employed to form successive layers of UF6 on a surface. The result is an ultra-thin deposit that bears an isotopic signature that is a composite of the two U sources. The reported deposition method has direct application to the development of unique analytical standards for nuclear safeguards and forensics. Further, the method allows access to very low atomic or molecular coverages of surfaces. Copyright © 2016 Elsevier B.V. All rights reserved.

  13. Measurement of 235U enrichment in UF6 by passive gamma spectrometry

    International Nuclear Information System (INIS)

    Sawai, Hideo; Ochiai, Ken-ichi; Kaya, Akira

    1979-01-01

    For the assay of UF 6 , a single-channel analyzer (SCA) system of a passive gamma spectrometer has been developed. Basic measuring conditions were studied: such as the effects of sample density and heterogeneity and the effects of cylinder material and wall thickness. Called ''enrichment analyzer'', the system is operated to carry out the measurement and calculation of 235 U enrichment by a directive of the program in a calculator. The resulting data are available in real time output. Measurements were carried out in two modes: ''all way'' mode which measured in the rotation of the cylinder and the up-and-down motion of the detector, and ''spot'' mode which measured at one point on the cylinder. The average accuracy was about 1.8% in case of the former, and 3.2% in case of the latter. It was shown that the ''all way'' mode is preferable, but the ''spot'' mode is also necessary for the assay of large cylinders such as 30 A type. (J.P.N.)

  14. Application of a Kalman filter to UF6 gaseous diffusion plant freezer/sublimer systems

    International Nuclear Information System (INIS)

    Ruppel, F.R.

    1992-03-01

    A signal is required to control the flow of UF 6 in gaseous diffusion plant freezer/sublimer systems. The original strategy envisioned for deriving a flow signal was to take the derivative of the freezer/sublimer weigh cell signal. However, the derivative of the digitized weight signal is noisy, preventing good control. In addition, a bias is introduced into the weight derivative signal because a refrigerant is circulated through a shell-and-tube heat exchanger inside the freezer/sublimer. The weight of the refrigerant is included in the weight measured by the weigh cell. If the circulation rate of the refrigerent is not steady state, a bias exists. Measurements of upstream pressure, vessel pressure, and output to the system control valve are available to the control system. Thus, if the flow through the control valve is characterized properly by the measurements, a Kalman filter can be used in conjunction with these auxiliary inputs and the weigh cell input to overcome the noise and bias problem and provide an improve estimate of flow rate. A discussion of the development and the current status of a Kalman filter used for this application is given. 5 refs

  15. Technical and administrative approach for the West Valley Demonstration Project Safety Program

    International Nuclear Information System (INIS)

    Newsom, P.C.; Roberts, C.J.; Yuchien Yuan; Marchetti, S.

    1987-06-01

    The principal objective of the West Valley Demonstration Project (WVDP) is to vitrify the 2.2 million liters of high-level radioactive waste (HLW) stored at the Western New York Nuclear Service Center (WNYNSC). This simple statement of purpose, however, does not convey a sense of the complexity of the undertaking. The vitrification task is not only complex in and of itself, but requires a myriad of other activities to be accomplished on an intricate and fast paced schedule in order to support it. The West Valley Demonstration Project Act (P.L 96-368), U.S. Department of Energy Order DOE-5481.1A, Idaho Operations Office Order ID-5481.1 and standard nuclear industry practice all require that proposed systems and operations involving hazards not routinely encountered by the general public be analyzed to identify potential hazards and consequences, and to assure that reasonable measures are taken to eliminate, control, or mitigate these potential consequences. Virtually every substantive aspect of the WVDP involves hazards beyond those routinely encountered and accepted by the general public. In order to assure the safety of the public and the workers at the WVDP, a system of hazard identification, categorization, analysis and review has been established. In parallel with this system, a procedure for developing the minimum design specifications and quality assurance requirements has been developed for Project systems, components, and structures which play a role in the safety of a specific major facility or the overall Project. 29 refs., 3 figs., 6 tabs

  16. West Valley Demonstration Project, Waste Management Area #3 -- Closure Alternative I

    Energy Technology Data Exchange (ETDEWEB)

    Marschke, Stephen F. [Environmental Measurements Laboratory (EML), New York, NY (United States)

    2000-06-30

    The Draft Environmental Impact Statement for the completion of the West Valley Demonstration Project and closure and/or long-term management of facilities at the Western New York Nuclear Service Center divided the site into Waste Management Areas (WMAs), and for each WMA, presented the impacts associated with five potential closure alternatives. This report focuses on WMA 3 (the High-Level Waste (HLW) Storage Area (Tanks 8D-1 and 8D-2), the Vitrification Facility and other facilities) and closure Alternative I (the complete removal of all structures, systems and components and the release of the area for unrestricted use), and reestimates the impacts associated with the complete removal of the HLW tanks, and surrounding facilities. A 32-step approach was developed for the complete removal of Tanks 8D-1 and 8D-2, the Supernatant Treatment System Support Building, and the Transfer Trench. First, a shielded Confinement Structure would be constructed to reduce the shine dose rate and to control radioactivity releases. Similarly, the tank heels would be stabilized to reduce potential radiation exposures. Next, the tank removal methodology would include: 1) excavation of the vault cover soil, 2) removal of the vault roof, 3) cutting off the tank’s top, 4) removal of the stabilized heel remaining inside the tank, 5) cutting up the tank’s walls and floor, 6) removal of the vault’s walls, the perlite blocks, and vault floor, and 7) radiation surveying and backfilling the resulting hole. After the tanks are removed, the Confinement Structure would be decontaminated and dismantled, and the site backfilled and landscaped. The impacts (including waste disposal quantities, emissions, work-effort, radiation exposures, injuries and fatalities, consumable materials used, and costs) were estimated based on this 32 step removal methodology, and added to the previously estimated impacts for closure of the other facilities within WMA 3 to obtain the total impacts from

  17. Y Chromosome analysis of prehistoric human populations in the West Liao River Valley, Northeast China.

    Science.gov (United States)

    Cui, Yinqiu; Li, Hongjie; Ning, Chao; Zhang, Ye; Chen, Lu; Zhao, Xin; Hagelberg, Erika; Zhou, Hui

    2013-09-30

    The West Liao River valley in Northeast China is an ecologically diverse region, populated in prehistory by human populations with a wide range of cultures and modes of subsistence. To help understand the human evolutionary history of this region, we performed Y chromosome analyses on ancient human remains from archaeological sites ranging in age from 6500 to 2700 BP. 47 of the 70 individuals provided reproducible results. They were assigned into five different Y sub-haplogroups using diagnostic single nucleotide polymorphisms, namely N1 (xN1a, N1c), N1c, C/C3e, O3a (O3a3) and O3a3c. We also used 17 Y short tandem repeat loci in the non-recombining portion of the Y chromosome. There appears to be significant genetic differences between populations of the West Liao River valley and adjacent cultural complexes in the prehistoric period, and these prehistoric populations were shown to carry similar haplotypes as present-day Northeast Asians, but at markedly different frequencies. Our results suggest that the prehistoric cultural transitions were associated with immigration from the Yellow River valley and the northern steppe into the West Liao River valley. They reveal the temporal continuity of Y chromosome lineages in populations of the West Liao River valley over 5000 years, with a concurrent increase in lineage diversity caused by an influx of immigrants from other populations.

  18. Semiportable load-cell-based weighing system prototype of 18.14-metric-ton (20-ton) capacity for UF6 cylinder weight verifications: description and testing procedure

    International Nuclear Information System (INIS)

    McAuley, W.A.

    1984-01-01

    The 18.14-metric-ton-capacity (20-ton) Load-Cell-Based Weighing System (LCBWS) prototype tested at the Oak Ridge (Tennessee) Gaseous Diffusion Plant March 20-30, 1984, is semiportable and has the potential for being highly accurate. Designed by Brookhaven National Laboratory, it can be moved to cylinders for weighing as opposed to the widely used operating philosophy of most enrichment facilities of moving cylinders to stationary accountability scales. Composed mainly of commercially available, off-the-shelf hardware, the system's principal elements are two load cells that sense the weight (i.e., force) of a uranium hexafluoride (UF 6 ) cylinder suspended from the LCBWS while the cylinder is in the process of being weighed. Portability is achieved by its attachment to a double-hook, overhead-bridge crane. The LCBWS prototype is designed to weigh 9.07- and 12.70-metric ton (10- and 14-ton) UF 6 cylinders. A detailed description of the LCBWS is given, design information and criteria are supplied, a testing procedure is outlined, and initial test results are reported. A major objective of the testing is to determine the reliability and accuracy of the system. Other testing objectives include the identification of (1) potential areas for system improvements and (2) procedural modifications that will reflect an improved and more efficient system. The testing procedure described includes, but is not limited to, methods that account for temperature sensitivity of the instrumentation, the local variation in the acceleration due to gravity, and buoyance effects. Operational and safety considerations are noted. A preliminary evaluation of the March test data indicates that the LCBWS prototype has the potential to have an accuracy in the vicinity of 1 kg

  19. Correlation study among the International Atomic Energy Agency standards and market standards on management system applicable to a UF6 conversion plant operation

    International Nuclear Information System (INIS)

    Oliveira, Dirceu Paulo de

    2008-01-01

    The Agency - International Atomic Energy Agency (IAEA), following the market trend of the management system integration, has decided to revise the quality assurance standards - IAEA 50-C/SG-Q publishing, in 2006, the standard on Management System (MS). IAEA GS-R-3 and its IAEA GS-G-3.1 guide. Also, the IAEA is about to publish a supplementary guide - IAEA DS349, which consider the integration of several functions involved in management of nuclear facilities, such as: safety, health, environmental and quality, ensuring that nuclear safety is not compromised. Conversion plants of 'Yellowcake' in UF 6 use and process radioactive materials, as well as other substances normally found in the chemical conventional industry, inserting themselves in the organization profile that require a high pattern of definition, implementation and continuous improvement of their MS and, therefore, should consider an approach of management integrated system (MIS). Taking a UF 6 conversion plant as focus, the correlation was performed among the Agency MS standards and those of the market - ISO 9001, ISO 14001 and OHSAS 18001, as well as with the Agency drafts standards on safety (DS316 and DS344), concluding that, in structuring an MIS, in compliance with the Agency MS standards, except for some adjustments, the ISO 9001, ISO 14001, and OHSAS 18001 are going to be met. On the other hand, the structuring of MIS should identify other requirements on safety, health and environmental, which also consider the conventional chemical and industrial characteristics that are out of the scope (ionizing radiation) of the safety standards of the Agency. The research proposes a documental procedure for a MIS applicable to this plant, providing elements for rationalization and contents of the identified documentation, for the promotion of the integration of the considered MS functions. (author)

  20. Analysis of enriched HF-UF6 systems. Influence by impurity and density upon the value of the multiplication

    International Nuclear Information System (INIS)

    Acosta, N.B.; Canavese, S.I.; Lopez, M.L.

    1990-01-01

    The purpose of this paper is analyzing the influence of impurity in hydrogen fluoride and in density variation (UF 6 -HF) upon the value of the effective multiplication factor (Kef) in enriched uranium hexafluoride and hydrogen fluoride systems. The identification of the values of such multiplication factors were performed by means of the Monte-Carlo (MONK V.II) code, which is specific for criticality problems. Diverse systems were considered by keeping the same geometry and varying the density value and the impurity percentages, while the assumptions made for each model were described on a case-by-case basis. Also, systems with and without water infinite reflector were evaluated. Finally, an analysis is made of the influence of each parameter upon the effective multiplication factor, in the postulated enriched UF 6 -HF systems. (Author) [es

  1. Conceptual design for the field test and evaluation of the gas-phase UF6 enrichment meter

    International Nuclear Information System (INIS)

    Strittmatter, R.B.; Leavitt, J.N.; Slice, R.W.

    1980-12-01

    An in-line enrichment monitor is being developed to provide real-time enrichment data for the gas-phase UF 6 feed stream of an enrichment plant. Data from proof-of-principle measurements using a laboratory prototype system are presented. A conceptual design for an enrichment monitor to be field tested and evaluated at the Oak Ridge Gaseous Diffusion Plant is reported

  2. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2003

    International Nuclear Information System (INIS)

    2004-01-01

    This Annual Site Environmental Report for the West Valley Demonstration Project (WVDP or Project) is published to inform those with interest about environmental conditions at the WVDP. In accordance with U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting, the report summarizes calendar year (CY) 2003 environmental monitoring data so as to describe the performance of the WVDP's environmental management system (EMS), confirm compliance with standards and regulations, and highlight important programs. During 2003, cleanup of radioactive waste from the former nuclear fuels reprocessing plant that shut down operations in the 1970s was continued at the WVDP. The Project is located in western New York State, about 30 miles south of Buffalo, within the New York State-owned Western New York Nuclear Service Center (WNYNSC). The WVDP is being conducted in cooperation with the New York State Energy Research and Development Authority. Work activities at the WVDP during 2003 included: (1) maintaining canisters of vitrified high-level waste in a shielded facility; (2) shipping low-level radioactive waste offsite for disposal; (3) shipping packaged spent nuclear fuel assemblies to Idaho National Engineering and Environmental Laboratory; (4) constructing a facility where large high-activity components can be safely size-reduced and packaged for disposal; (5) decontaminating the fuel storage pool and the cask unloading pool; (6) decontaminating the general purpose cell and the process mechanical cell (also referred to as the head end cells); (7) cleanup of waste in the plutonium purification cell (south) and extraction cell number 2 in the main plant; (8) planning for decontamination and dismantlement of the vitrification facility; (9) continuing preparation of the Decommissioning and/or Long-Term Stewardship Environmental Impact Statement; and (10) monitoring the environment and managing contaminated areas within the Project facility premises

  3. Characterization of the solid, airborne materials created when UF6 reacts with moist air flowing in single-pass mode

    International Nuclear Information System (INIS)

    Pickrell, P.W.

    1985-10-01

    A series of experiments has been performed in which UF 6 was released into flowing air in order to characterize the solid particulate material produced under non-static conditions. In two of the experiments, the aerosol was allowed to stagnate in a static chamber after release and examined further but in the other experiments characterization was done only on material collected a few seconds after release. Transmission electron microscopy and mass measurement by cascaded impactor were used to characterize the aerosol particles which were usually single spheroids with little agglomeration in evidence. The goal of the work is to determine the chemistry and physics of the UF 6 -atmospheric moisture reaction under a variety of conditions so that information about resulting species and product morphologies is available for containment and removal (knockdown) studies as well as for dispersion plume modeling and toxicology studies. This report completes the milestone for reporting the information obtained from releases of UF 6 into flowing rather than static air. 26 figs., 3 tabs

  4. Tree culture of smallholder farmers practicing agroforestry in Gunung Salak Valley, West Java, Indonesia

    DEFF Research Database (Denmark)

    Rahman, Syed Ajijur; Sunderland, Terry; Roshetko, James M.

    2016-01-01

    This paper investigates the types of agroforestry system that exist in Gunung Salak Valley, West Java, Indonesia in order to characterize the differences in their basic structure and associated crop plant diversity. Data were collected through rapid rural appraisal, field observation and focus...

  5. West Valley Reprocessing Plant. IE inspection report No. 75-8

    International Nuclear Information System (INIS)

    1975-01-01

    Results of an inspection of the West Valley Processing Plant on October 20-23, 1975 are reported. The inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector. No items of noncompliance were observed

  6. West Valley high-level nuclear waste glass development: a statistically designed mixture study

    Energy Technology Data Exchange (ETDEWEB)

    Chick, L.A.; Bowen, W.M.; Lokken, R.O.; Wald, J.W.; Bunnell, L.R.; Strachan, D.M.

    1984-10-01

    The first full-scale conversion of high-level commercial nuclear wastes to glass in the United States will be conducted at West Valley, New York, by West Valley Nuclear Services Company, Inc. (WVNS), for the US Department of Energy. Pacific Northwest Laboratory (PNL) is supporting WVNS in the design of the glass-making process and the chemical formulation of the glass. This report describes the statistically designed study performed by PNL to develop the glass composition recommended for use at West Valley. The recommended glass contains 28 wt% waste, as limited by process requirements. The waste loading and the silica content (45 wt%) are similar to those in previously developed waste glasses; however, the new formulation contains more calcium and less boron. A series of tests verified that the increased calcium results in improved chemical durability and does not adversely affect the other modeled properties. The optimization study assessed the effects of seven oxide components on glass properties. Over 100 melts combining the seven components into a wide variety of statistically chosen compositions were tested. Viscosity, electrical conductivity, thermal expansion, crystallinity, and chemical durability were measured and empirically modeled as a function of the glass composition. The mathematical models were then used to predict the optimum formulation. This glass was tested and adjusted to arrive at the final composition recommended for use at West Valley. 56 references, 49 figures, 18 tables.

  7. Injection of radioactive waste by hydraulic fracturing at West Valley, New York. Volume 3. Appendices

    International Nuclear Information System (INIS)

    1978-05-01

    Ten appendices are included: log data, elastic constants for transversely isotropic elastic media by ultrasonic velocity measurement, fracture toughness anisotropy of West Valley shale, in-situ stress measurement techniques, stress measurement data, hydraulic fracturing measurements, enhancement of horizontal crack initiation by jetting, finite element programs for analysis of crack propagation and for groundwater flow analysis, and well data

  8. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2006

    International Nuclear Information System (INIS)

    2007-01-01

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2006. The report summarizes calendar year (CY) 2006 environmental monitoring data so as to describe the performance of the WVDP's environmental management system (EMS), confirm compliance with standards and regulations, and highlight important programs that protect public health and safety and the environment

  9. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2005

    International Nuclear Information System (INIS)

    West Valley Nuclear Services Company WVNSCO and URS Group, Inc.

    2006-01-01

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2005. The report summarizes calendar year (CY) 2005 environmental monitoring data so as to describe the performance of the WVDP's environmental management system (EMS), confirm compliance with standards and regulations, and highlight important programs

  10. Public meeting: Western New York Nuclear Service Center options study. [Problem of West Valley plant

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-04-01

    This document is a transcript of the meeting, with additional written comments. The main topic is the West Valley Processing Plant and how to dispose of it and its high-level wastes. Objective is to get public input on this topic. (DLC)

  11. Design of equipment used for high-level waste vitrification at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Vance, R.F.; Brill, B.A.; Carl, D.E.

    1997-06-01

    The equipment as designed, started, and operated for high-level radioactive waste vitrification at the West Valley Demonstration Project in western New York State is described. Equipment for the processes of melter feed make-up, vitrification, canister handling, and off-gas treatment are included. For each item of equipment the functional requirements, process description, and hardware descriptions are presented

  12. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2006

    Energy Technology Data Exchange (ETDEWEB)

    West Valley Nuclear Services Company (WVNSCO) and URS Group, Inc.

    2007-09-27

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2006. The report summarizes calendar year (CY) 2006 environmental monitoring data so as to describe the performance of the WVDP’s environmental management system (EMS), confirm compliance with standards and regulations, and highlight important programs that protect public health and safety and the environment.

  13. West Valley Demonstration Project Annual Site Environmental Report Calendard Year 2005

    Energy Technology Data Exchange (ETDEWEB)

    West Valley Nuclear Services Company (WVNSCO) and URS Group, Inc.

    2006-09-21

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2005. The report summarizes calendar year (CY) 2005 environmental monitoring data so as to describe the performance of the WVDP's environmental management system (EMS), confirm compliance with standards and regulations, and highlight important programs.

  14. Laboratory and pilot-plant studies on the conversion of uranyl nitrate hexahydrate to UF6 by fluidized-bed processes

    International Nuclear Information System (INIS)

    Youngblood, E.L.; Urza, I.J.; Cathers, G.I.

    1977-06-01

    This report describes laboratory and pilot-plant studies on the conversion of uranyl nitrate hexahydrate (UNH) to UF 6 and on purification of the UF 6 . Experimental laboratory studies on the removal of residual nitrate from uranium trioxide (UO 3 ) calcine and the fluorination of technetium and subsequent sorption on MgF 2 were conducted to support the pilot-plant work. Two engineering-scale pilot plants utilizing fluidized-bed processes were constructed for equipment and process testing of the calcination of UNH to UO 3 and the direct fluorination of UO 3 to UF 6

  15. Evaluation of the location and recency of faulting near prospective surface facilities in Midway Valley, Nye County, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Swan, F.H.; Wesling, J.R.; Angell, M.M.; Thomas, A.P.; Whitney, J.W.; Gibson, J.D.

    2002-01-17

    Evaluation of surface faulting that may pose a hazard to prospective surface facilities is an important element of the tectonic studies for the potential Yucca Mountain high-level radioactive waste repository in southwestern Nevada. For this purpose, a program of detailed geologic mapping and trenching was done to obtain surface and near-surface geologic data that are essential for determining the location and recency of faults at a prospective surface-facilities site located east of Exile Hill in Midway Valley, near the eastern base of Yucca Mountain. The dominant tectonic features in the Midway Valley area are the north- to northeast-trending, west-dipping normal faults that bound the Midway Valley structural block-the Bow Ridge fault on the west side of Exile Hill and the Paint-brush Canyon fault on the east side of the valley. Trenching of Quaternary sediments has exposed evidence of displacements, which demonstrate that these block-bounding faults repeatedly ruptured the surface during the middle to late Quaternary. Geologic mapping, subsurface borehole and geophysical data, and the results of trenching activities indicate the presence of north- to northeast-trending faults and northwest-trending faults in Tertiary volcanic rocks beneath alluvial and colluvial sediments near the prospective surface-facilities site. North to northeast-trending faults include the Exile Hill fault along the eastern base of Exile Hill and faults to the east beneath the surficial deposits of Midway Valley. These faults have no geomorphic expression, but two north- to northeast-trending zones of fractures exposed in excavated profiles of middle to late Pleistocene deposits at the prospective surface-facilities site appear to be associated with these faults. Northwest-trending faults include the West Portal and East Portal faults, but no disruption of Quaternary deposits by these faults is evident. The western zone of fractures is associated with the Exile Hill fault. The eastern

  16. Evaluation of the location and recency of faulting near prospective surface facilities in Midway Valley, Nye County, Nevada

    International Nuclear Information System (INIS)

    Swan, F.H.; Wesling, J.R.; Angell, M.M.; Thomas, A.P.; Whitney, J.W.; Gibson, J.D.

    2002-01-01

    Evaluation of surface faulting that may pose a hazard to prospective surface facilities is an important element of the tectonic studies for the potential Yucca Mountain high-level radioactive waste repository in southwestern Nevada. For this purpose, a program of detailed geologic mapping and trenching was done to obtain surface and near-surface geologic data that are essential for determining the location and recency of faults at a prospective surface-facilities site located east of Exile Hill in Midway Valley, near the eastern base of Yucca Mountain. The dominant tectonic features in the Midway Valley area are the north- to northeast-trending, west-dipping normal faults that bound the Midway Valley structural block-the Bow Ridge fault on the west side of Exile Hill and the Paint-brush Canyon fault on the east side of the valley. Trenching of Quaternary sediments has exposed evidence of displacements, which demonstrate that these block-bounding faults repeatedly ruptured the surface during the middle to late Quaternary. Geologic mapping, subsurface borehole and geophysical data, and the results of trenching activities indicate the presence of north- to northeast-trending faults and northwest-trending faults in Tertiary volcanic rocks beneath alluvial and colluvial sediments near the prospective surface-facilities site. North to northeast-trending faults include the Exile Hill fault along the eastern base of Exile Hill and faults to the east beneath the surficial deposits of Midway Valley. These faults have no geomorphic expression, but two north- to northeast-trending zones of fractures exposed in excavated profiles of middle to late Pleistocene deposits at the prospective surface-facilities site appear to be associated with these faults. Northwest-trending faults include the West Portal and East Portal faults, but no disruption of Quaternary deposits by these faults is evident. The western zone of fractures is associated with the Exile Hill fault. The eastern

  17. Evaluation of the Location and Recency of Faulting Near Prospective Surface Facilities in Midway Valley, Nye County, Nevada

    Science.gov (United States)

    Swan, F.H.; Wesling, J.R.; Angell, M.M.; Thomas, A.P.; Whitney, J.W.; Gibson, J.D.

    2001-01-01

    Evaluation of surface faulting that may pose a hazard to prospective surface facilities is an important element of the tectonic studies for the potential Yucca Mountain high-level radioactive waste repository in southwestern Nevada. For this purpose, a program of detailed geologic mapping and trenching was done to obtain surface and near-surface geologic data that are essential for determining the location and recency of faults at a prospective surface-facilities site located east of Exile Hill in Midway Valley, near the eastern base of Yucca Mountain. The dominant tectonic features in the Midway Valley area are the north- to northeast-trending, west-dipping normal faults that bound the Midway Valley structural block-the Bow Ridge fault on the west side of Exile Hill and the Paint-brush Canyon fault on the east side of the valley. Trenching of Quaternary sediments has exposed evidence of displacements, which demonstrate that these block-bounding faults repeatedly ruptured the surface during the middle to late Quaternary. Geologic mapping, subsurface borehole and geophysical data, and the results of trenching activities indicate the presence of north- to northeast-trending faults and northwest-trending faults in Tertiary volcanic rocks beneath alluvial and colluvial sediments near the prospective surface-facilities site. North to northeast-trending faults include the Exile Hill fault along the eastern base of Exile Hill and faults to the east beneath the surficial deposits of Midway Valley. These faults have no geomorphic expression, but two north- to northeast-trending zones of fractures exposed in excavated profiles of middle to late Pleistocene deposits at the prospective surface-facilities site appear to be associated with these faults. Northwest-trending faults include the West Portal and East Portal faults, but no disruption of Quaternary deposits by these faults is evident. The western zone of fractures is associated with the Exile Hill fault. The eastern

  18. Validation of Cristallini Sampling Method for UF6 by High Precision Double-Spike Measurements Collaboration between JRC-G.2, Team METRO and SGAS/IAEA

    OpenAIRE

    RICHTER Stephan; HIESS Joe; JAKOBSSON Ulf

    2016-01-01

    The so-called "Cristallini Method" for sampling of UF6 by adsorption and hydrolysis in alumina pellets inside a fluorothene P-10 tube has been developed by the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC) several years ago [1]. This method has several advantages compared to the currently used sampling method, for which UF6 is distilled into a stainless steel tube for transportation, with hydrolysis and isotopic analysis being performed after shipping to t...

  19. Extremely low temperature behaviour of the thermodynamical properties of gaseous UF6 under an exact quantum approach

    International Nuclear Information System (INIS)

    Amarante, J.A.A. do.

    1979-10-01

    The thermodynamic functions of molecules of type XF 6 are calculated under an exact quantum-mechanical approach, which also yields general expressions valid for other types of molecules. The formalism is used to analyse the behavior of gaseous UF 6 at very low temperatures (around and below 1 0 K), where symmetry effects due to Pauli principle lead to results which are very markedly different from those obtained with the semi-classical approximation. It is shown that this approximation becomes sufficiently accurate only for temperatures about ten times the rotational temperature. (Author) [pt

  20. Argon/UF6 plasma exhaust gas reconstitution experiments using preheated fluorine and on-line diagnostics. [fissioning uranium plasma core reactor design

    Science.gov (United States)

    Roman, W. C.

    1979-01-01

    The feasibility of employing a flowing, high-temperature, pure fluorine/UF6 regeneration system to efficiently convert a large fraction of the effluent plasma exhaust back to pure UF6 was demonstrated. The custom built T.O.F. mass spectrometer sampling system permitted on-line measurements of the UF6 concentration at different locations in the exhaust system. Negligible amounts ( 100 ppm) of UF6 were detected in the axial bypass exhaust duct and the exhaust ducts downstream of the cryogenic trap system used to collect the UF6, thus verifying the overall system efficiency over a range of operating conditions. Use of a porous Monel duct as part of the exhaust duct system, including provision for injection of pure fluorine, provided a viable technique to eliminate uranium compound residue on the inside surface of the exhaust ducts. Typical uranium compound mass deposition per unit area of duct was 2 micron g/sq cm. This porous duct technique is directly applicable to future uranium compound transfer exhaust systems. Throughout these experiments, additional basic data on the corrosion aspects of hot, pressurized UF6/fluorine were also accumulated.

  1. Final report, Task 3: possible uses of the Nuclear Fuel Services, Inc. reprocessing plant at West Valley, New York

    International Nuclear Information System (INIS)

    1978-01-01

    The West Valley Plant could readily be used for work on reprocessing of alternative fuels, spiking, coprocessing (including CIVEX), waste solidification, and the recovery of radioactive gases. The plant could be easily modified for any scale between small-scale experimental work to production-scale demonstration, involving virtually any combination of fissile/fertile fuel materials that might be used in the future. The use of this plant for the contemplated experimental work would involve lower capital costs than the use of other facilities at DOE sites, except possibly for spiking of recovered products; the operating costs would be no greater than at other sites. The work on reprocessing of alternative fuels and coprocessing could commence within about one year; on recovery of radioactive gases, in 3 to 5 years; on spiking, in 4 years; and on waste solidification demonstration, in about 5 years. The contemplated work could be begun at this plant at least as early as at Barnwell, although work on spiking of recovered products could probably be started in existing hot cells earlier than at West Valley

  2. Statistical methods to monitor the West Valley off-gas system

    International Nuclear Information System (INIS)

    Eggett, D.L.

    1990-01-01

    This paper reports on the of-gas system for the ceramic melter operated at the West Valley Demonstration Project at West Valley, NY, monitored during melter operation. A one-at-a-time method of monitoring the parameters of the off-gas system is not statistically sound. Therefore, multivariate statistical methods appropriate for the monitoring of many correlated parameters will be used. Monitoring a large number of parameters increases the probability of a false out-of-control signal. If the parameters being monitored are statistically independent, the control limits can be easily adjusted to obtain the desired probability of a false out-of-control signal. The principal component (PC) scores have desirable statistical properties when the original variables are distributed as multivariate normals. Two statistics derived from the PC scores and used to form multivariate control charts are outlined and their distributional properties reviewed

  3. Selection of a reference process for treatment of the West Valley alkaline waste

    International Nuclear Information System (INIS)

    Holton, L.K.; Wise, B.M.; Bray, L.A.; Pope, J.M.; Carl, D.E.

    1984-08-01

    As part of the West Valley Demonstration Project (WVDP) the alkaline PUREX supernatant stored in Tank 8D2 will be partially decontaminated by the removal of radiocesium. Four processes for removal of radiocesium from the alkaline supernatant were studied through experimentation and engineering analysis to identify a reference approach for the WVDP. These processes included the use of a zeolite inorganic ion-exchanger (Linde Ionsiv IE-95), an organic ion exchange resin (Duolite CS-100), and two precipitation processes; one using sodium tetraphenylboron (NaTPB) and the other using phosphotungstic acid (PTA). Based upon process performance, safety and environmental considerations, process and equipment complexity and impacts to the waste vitrification system, the zeolite ion-exchange process has been selected by West Valley Nuclear Services, Inc., as the reference supernatant treatment process for the WVDP. This paper will summarize the technical basis for the selection of the zeolite ion-exchange process. 4 figures, 2 tables

  4. Fulfilling information needs of environmental groups: the current West Valley experience

    International Nuclear Information System (INIS)

    Hoffman, W.D.

    1986-01-01

    This paper addresses the justification for environmental group communications and the options available in formatting such a dialogue. The West Valley program is explained including realized and potential project benefits. The environmental communications program in place at the West Valley Demonstration Project (WVDP) was instituted in the throes of a challenging scenario. The site had just been chosen by the US Department of Energy (DOE) to demonstrate the cleanup of high-level nuclear wastes with a relatively new technology. The former nuclear fuel reprocessing operator had maintained a closed door communications policy. Consequently, the initial reaction of environmental groups to the project was one of suspicion and fear. The WVDP information exchange involves regularly bringing persons to the site, many of whom are antinuclear and initially skeptical of the project. Many have indicated their early concern about the site has been alleviated; furthermore, they are impressed with the purpose of the project and its commitment to safety

  5. Fulfilling information needs of environmental groups: the current West Valley experience

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, W.D.

    1986-07-15

    This paper addresses the justification for environmental group communications and the options available in formatting such a dialogue. The West Valley program is explained including realized and potential project benefits. The environmental communications program in place at the West Valley Demonstration Project (WVDP) was instituted in the throes of a challenging scenario. The site had just been chosen by the US Department of Energy (DOE) to demonstrate the cleanup of high-level nuclear wastes with a relatively new technology. The former nuclear fuel reprocessing operator had maintained a closed door communications policy. Consequently, the initial reaction of environmental groups to the project was one of suspicion and fear. The WVDP information exchange involves regularly bringing persons to the site, many of whom are antinuclear and initially skeptical of the project. Many have indicated their early concern about the site has been alleviated; furthermore, they are impressed with the purpose of the project and its commitment to safety.

  6. Temperature evaluation of UF6 and cluster detection in nozzle expansion using low-resolution infrared absorption spectroscopy

    International Nuclear Information System (INIS)

    Sbampato, M.E.; Antunes, L.M.D.; Miranda, S.F.; Sena, S.C.; Santos, A.M.

    1998-01-01

    The continuous supersonic expansion of pure gaseous UF 6 and mixtures of UF 6 with argon and nitrogen through a bidimensional nozzle was studied using low-resolution infrared spectroscopy in the ν 3 absorption band region. The experiments were carried out in order to calculate the molecular temperature of the beam and also to verify cluster formation in the expansion. The molecular beam temperature evaluation was based on the measurements of the low-resolution bandwidth, which were compared to simulated spectra results. The temperatures were also evaluated using the measured pressure at the end of the nozzle by a Pitot tube. In the conditions where no cluster formation was observed the calculated theoretical temperatures using an equilibrium expansion model are in good agreement with the data obtained through the analysis of the experimental spectra and through the Pitot tube pressure measurement. Cluster formation was observed for temperatures below about 120 K. In these conditions the infrared spectra showed shoulders in the region above 630 cm -1 and a shoulder or band between 616 and 600 cm -1 . (orig.)

  7. The integrated melter off-gas treatment systems at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Vance, R.F.

    1991-12-01

    The West Valley Demonstration project was established by an act of Congress in 1980 to solidify the high level radioactive liquid wastes produced from operation of the Western New York Nuclear Services Center from 1966 to 1972. The waste will be solidified as borosilicate glass. This report describes the functions, the controlling design criteria, and the resulting design of the melter off-gas treatment systems

  8. Hydrological functioning of West-African inland valleys explored with a critical zone model

    Science.gov (United States)

    Hector, B.; Cohard, J. M.; Séguis, L.; Peugeot, C.; Galle, S.

    2017-12-01

    In west Africa, recurrent floods are still a major issue, and hydropower has been recognized as an important development pathway. Furthermore, inland valleys carry an important agronomic potential, which could meet the necessary increase of the crop production associated with the strong demographic rates of the region. This can lead to land cover and subsequent hydrologic changes. However, the hydrological role of the inland valleys in the humid, hard rock-dominated Sudanian area is not yet well understood, specifically for streamflow (Q) generation processes. We address both the questions of the hydrological functioning of inland valleys in the Sudanian area of West-Africa and the impact of land cover changes on these systems through deterministic sensitivity experiments using a physically-based critical zone model (ParFlow-CLM) applied on a synthetic catchment which comprises an inland valley. The conceptual lithological/pedological model for the catchment includes the main features of such a hydrological elementary unit derived from the literature and from a previously published model based on data from a highly instrumented elementary catchment. Model forcings and parameters are based on data from the AMMA-CATCH observation service and multiple field experiments. We found yearly water budgets were much more sensitive to vegetation distribution than lithology features of the inland valley (presence of the low permeability layer commonly found below the inland valley and the hydrodynamic properties of upstream and lateral areas). Yearly evapotranspiration budget between a fully tree-covered and an herbaceous-covered catchment increases between 6 and 21% of the precipitation of the year (depending on the tested cases) which reduces considerably the yearly streamflow budgets ( 30%). On the other hand, the lithology distribution has clear impacts on the spatial distribution of water storage dynamics.

  9. Results from a 'Proof-of-Concept' Demonstration of RF-Based Tracking of UF6 Cylinders during a Processing Operation at a Uranium Enrichment Plant

    International Nuclear Information System (INIS)

    Pickett, Chris A; Kovacic, Donald N; Whitaker, J Michael; Younkin, James R; Hines, Jairus B; Laughter, Mark D; Morgan, Jim; Carrick, Bernie; Boyer, Brian; Whittle, K.

    2008-01-01

    Approved industry-standard cylinders are used globally for processing, storing, and transporting uranium hexafluoride (UF 6 ) at uranium enrichment plants. To ensure that cylinder movements at enrichment facilities occur as declared, the International Atomic Energy Agency (IAEA) must conduct time-consuming periodic physical inspections to validate facility records, cylinder identity, and containment. By using a robust system design that includes the capability for real-time unattended monitoring (of cylinder movements), site-specific rules-based event detection algorithms, and the capability to integrate with other types of monitoring technologies, one can build a system that will improve overall inspector effectiveness. This type of monitoring system can provide timely detection of safeguard events that could be used to ensure more timely and appropriate responses by the IAEA. It also could reduce reliance on facility records and have the additional benefit of enhancing domestic safeguards at the installed facilities. This paper will discuss the installation and evaluation of a radio-frequency- (RF-) based cylinder tracking system that was installed at a United States Enrichment Corporation Centrifuge Facility. This system was installed primarily to evaluate the feasibility of using RF technology at a site and the operational durability of the components under harsh processing conditions. The installation included a basic system that is designed to support layering with other safeguard system technologies and that applies fundamental rules-based event processing methodologies. This paper will discuss the fundamental elements of the system design, the results from this site installation, and future efforts needed to make this technology ready for IAEA consideration

  10. Experimental data developed to support the selection of a treatment process for West Valley alkaline supernatant

    Energy Technology Data Exchange (ETDEWEB)

    Bray, L.A.; Holton, L.K.; Myers, T.R.; Richardson, G.M.; Wise, B.M.

    1984-01-01

    At the request of West Valley Nuclear Services Co., Inc., the Pacific Northwest Laboratory (PNL) has studied alternative treatment processes for the alkaline PUREX waste presently being stored in Tank 8D2 at West Valley, New York. Five tasks were completed during FY 1983: (1) simulation and characterization of the alkaline supernatant and sludge from the tank. The radiochemical and chemical distributions between the aqueous and solid phase were determined, and the efficiency of washing sludge with water to remove ions such as Na/sup +/ and SO/sub 4//sup 2 -/ was investigated; (2) evaluation of a sodium tetraphenylboron (Na-TPB) precipitation process to recover cesium (Cs) and a sodium titanate (Na-TiA) sorption process to recover strontium (Sr) and plutonium (Pu) from the West Valley Alkaline supernatant. These processes were previously developed and tested at the US Department of Energy's Savannah River Plant; (3) evaluation of an organic cation-exchange resin (Duolite CS-100) to recover Cs and Pu from the alkaline supernatant followed by an organic macroreticular cation exchange resin (Amberlite IRC-718) to recover Sr; (4) evaluation of an inorganic ion exchanger (Linde Ionsiv IE-95) to recover Cs, Sr, and Pu from the alkaline supernatant; and (5) evaluation of Dowex-1,X8 organic anion exchange resin to recover technetium (Tc) from alkaline supernatant. The findings of these tasks are reported. 21 references, 36 figures, 34 tables.

  11. Environmental assessment for the treatment of Class A low-level radioactive waste and mixed low-level waste generated by the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    1995-11-01

    The U.S. Department of Energy (DOE) is currently evaluating low-level radioactive waste management alternatives at the West Valley Demonstration Project (WVDP) located on the Western New York Nuclear Service Center (WNYNSC) near West Valley, New York. The WVDP's mission is to vitrify high-level radioactive waste resulting from commercial fuel reprocessing operations that took place at the WNYNSC from 1966 to 1972. During the process of high-level waste vitrification, low-level radioactive waste (LLW) and mixed low-level waste (MILLW) will result and must be properly managed. It is estimated that the WVDP's LLW storage facilities will be filled to capacity in 1996. In order to provide sufficient safe storage of LLW until disposal options become available and partially fulfill requirements under the Federal Facilities Compliance Act (FFCA), the DOE is proposing to use U.S. Nuclear Regulatory Commission-licensed and permitted commercial facilities in Oak Ridge, Tennessee; Clive, Utah; and Houston, Texas to treat (volume-reduce) a limited amount of Class A LLW and MLLW generated from the WVDP. Alternatives for ultimate disposal of the West Valley LLW are currently being evaluated in an environmental impact statement. This proposed action is for a limited quantity of waste, over a limited period of time, and for treatment only; this proposal does not include disposal. The proposed action consists of sorting, repacking, and loading waste at the WVDP; transporting the waste for commercial treatment; and returning the residual waste to the WVDP for interim storage. For the purposes of this assessment, environmental impacts were quantified for a five-year operating period (1996 - 2001). Alternatives to the proposed action include no action, construction of additional on-site storage facilities, construction of a treatment facility at the WVDP comparable to commercial treatment, and off-site disposal at a commercial or DOE facility

  12. Geomorphic and erosion studies at the Western New York Nuclear Service Center, West Valley, New York

    International Nuclear Information System (INIS)

    Boothroyd, J.C.; Timson, B.S.; Dana, R.H. Jr.

    1979-12-01

    This report is one in a series of related reports presenting the results of a study to evaluate the containment capability of a low-level, solid radioactive waste-burial ground at West valley, NY. This project is the first portion of a detailed geomorphic and erosion study of the reach of Buttermilk Creek adjacent to the waste-burial site. Buttermilk Creek valley is being actively modified by fluvial transport, lateral channel scour, and landsliding. High surface runoff rates create highly variable but enhanced stream flows that result in coarse-gravel sediment transport within the active channel. The active channel morphology indicates that braided stream processes are common in Buttermilk, leading to active channel down-cutting and lateral migration. Where lateral migration of the active channel has undercut valley wall slopes, large-scale landsliding enhances valley wall retreat. A major site of historical and recent slide activity lies adjacent to the low-level burial trenches. Initial, post-glacial Buttermilk Creek incision began before 9920 +- 240 B.P., the age of the oldest dated fluvial terrace. Future evolution of the system is expected to proceed by Buttermilk valley lowering, tributary and landslide widening, and stream capture

  13. West Valley Demonstration Project vitrification process equipment Functional and Checkout Testing of Systems (FACTS)

    International Nuclear Information System (INIS)

    Carl, D.E.; Paul, J.; Foran, J.M.; Brooks, R.

    1990-01-01

    The Vitrification Facility (VF) at the West Valley Demonstration Project was designed to convert stored radioactive waste into a stable glass for disposal in a federal repository. The Functional and Checkout Testing of Systems (FACTS) program was conducted from 1984 to 1989. During this time new equipment and processes were developed, installed, and implemented. Thirty-seven FACTS tests were conducted, and approximately 150,000 kg of glass were made by using nonradioactive materials to simulate the radioactive waste. By contrast, the planned radioactive operation is expected to produce approximately 500,000 kg of glass. The FACTS program demonstrated the effectiveness of equipment and procedures in the vitrification system, and the ability of the VF to produce quality glass on schedule. FACTS testing also provided data to validate the WVNS waste glass qualification method and verify that the product glass would meet federal repository acceptance requirements. The system was built and performed to standards which would have enabled it to be used in radioactive service. As a result, much of the VF tested, such as the civil construction, feed mixing and holding vessels, and the off-gas scrubber, will be converted for radioactive operation. The melter was still in good condition after being at temperature for fifty-eight of the sixty months of FACTS. However, the melter exceeded its recommended design life and will be replaced with a similar melter. Components that were not designed for remote operation and maintenance will be replaced with remote-use items. The FACTS testing was accomplished with no significant worker injury or environmental releases. During the last FACTS run, the VF processes approximated the remote-handling system that will be used in radioactive operations. Following this run the VF was disassembled for conversion to a radioactive process. Functional and checkout testing of new components will be performed prior to radioactive operation

  14. Evaluation of low-level radioactive waste characterization and classification programs of the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Taie, K.R.

    1994-01-01

    The West Valley Demonstration Project (WVDP) is preparing to upgrade their low-level radioactive waste (LLW) characterization and classification program. This thesis describes a survey study of three other DOE sites conducted in support of this effort. The LLW characterization/classification programs of Oak Ridge National Laboratory, Savannah River Site, and Idaho National Engineering Laboratory were critically evaluated. The evaluation was accomplished through tours of each site facility and personnel interviews. Comparative evaluation of the individual characterization/classification programs suggests the WVDP should purchase a real-time radiography unit and a passive/active neutron detection system, make additional mechanical modifications to the segmented gamma spectroscopy assay system, provide a separate building to house characterization equipment and perform assays away from waste storage, develop and document a new LLW characterization/classification methodology, and make use of the supercompactor owned by WVDP

  15. ENDOMETRIOSIS IN A COHORT OF WOMEN LIVING IN THE KANAWHA RIVER VALLEY IN WEST VIRGINIA: BLOOD LEVELS OF NON-DIOXIN-LIKE PCBs AND RELATIONSHIP WITH BMI AND AGE

    Science.gov (United States)

    Industrial activities, specifically from petroleum and chemical manufacturing facilities, in the Kanawha River Valley (KRV) of West Virginia have resulted in releases of dioxin and dioxin-like chemicals (DLCs). I Most of the dioxin found in this region has resulted from the produ...

  16. Los Alamos DP West Plutonium Facility decontamination project

    International Nuclear Information System (INIS)

    Garde, R.; Cox, E.J.; Valentine, A.M.

    1982-01-01

    The DP West Plutonium Facility operated by the Los Alamos National Laboratory, Los Alamos, New Mexico, was decontaminated between April 1978 and April 1981. The facility was constructed in 1944 to 1945 to produce plutonium metal and fabricate parts for nuclear weapons. It was continually used as a plutonium processing and research facility until mid-1978. Decontamination operations included dismantling and removing gloveboxes and conveyor tunnels; removing process systems, utilities, and exhaust ducts; and decontaminating all remaining surfaces. This report describes glovebox and conveyor tunnel separations, decontamination techniques, health and safety considerations, waste management procedures, and costs of the operation

  17. Standard test method for determination of bromine and chlorine in UF6 and uranyl nitrate by X-Ray fluorescence (XRF) spectroscopy

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2001-01-01

    1.1 This method covers the determination of bromine (Br) and chlorine (Cl) in uranium hexafluoride (UF6) and uranyl nitrate solution. The method as written covers the determination of bromine in UF6 over the concentration range of 0.2 to 8 μg/g, uranium basis. The chlorine in UF6 can be determined over the range of 4 to 160 μg/g, uranium basis. Higher concentrations may be covered by appropriate dilutions. The detection limit for Br is 0.2 μg/g uranium basis and for Cl is 4 μg/g uranium basis. 1.2 This standard may involve hazardous materials, operations and equipment. This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  18. Estimation of time to rupture in a fire using 6FIRE, a lumped parameter UF6 cylinder transient heat transfer/stress analysis model

    International Nuclear Information System (INIS)

    Williams, W.R.; Anderson, J.C.

    1995-01-01

    The transportation of UF 6 is subject to regulations requiring the evaluation of packaging under a sequence of hypothetical accident conditions including exposure to a 30-min 800 degree C (1475 degree F) fire [10 CFR 71.73(c)(3)]. An issue of continuing interest is whether bare cylinders can withstand such a fire without rupturing. To address this issue, a lumped parameter heat transfer/stress analysis model (6FIRE) has been developed to simulate heating to the point of rupture of a cylinder containing UF 6 when it is exposed to a fire. The model is described, then estimates of time to rupture are presented for various cylinder types, fire temperatures, and fill conditions. An assessment of the quantity of UF 6 released from containment after rupture is also presented. Further documentation of the model is referenced

  19. Operational strategy for soil concentration predictions of strontium/yttrium-90 and cesium-137 in surface soil at the West Valley Demonstration Project site

    International Nuclear Information System (INIS)

    Myers, J.A.

    1995-01-01

    There are difficulties associated with the assessment of the interpretation of field measurements, determination of guideline protocols and control and disposal of low level radioactive contaminated soil in the environmental health physics field. Questions are raised among scientists and in public forums concerning the necessity and high costs of large area soil remediation versus the risks of low-dose radiation health effects. As a result, accurate soil activity assessments become imperative in decontamination situations. The West Valley Demonstration Project (WVDP), a US Department of Energy facility located in West Valley, New York is managed and operated by West Valley Nuclear Services Co., Inc. (WVNS). WVNS has identified contaminated on-site soil areas with a mixed variety of radionuclides (primarily fission product). Through the use of data obtained from a previous project performed during the summer of 1994 entitled ''Field Survey Correlation and Instrumentation Response for an In Situ Soil Measurement Program'' (Myers), the WVDP offers a unique research opportunity to investigate the possibility of soil concentration predictions based on exposure or count rate responses returned from a survey detector probe. In this study, correlations are developed between laboratory measured soil beta activity and survey probe response for the purposes of determining the optimal detector for field use and using these correlations to establish predictability of soil activity levels

  20. Next Generation Safeguards Initiative: Overview and Policy Context of UF6 Cylinder Tracking Program

    Energy Technology Data Exchange (ETDEWEB)

    Boyer, Brian D [Los Alamos National Laboratory; Whitaker, J. Michael [ORNL; White-Horton, Jessica L. [ORNL; Durbin, Karyn R. [NNSA

    2012-07-12

    Thousands of cylinders containing uranium hexafluoride (UF{sub 6}) move around the world from conversion plants to enrichment plants to fuel fabrication plants, and their contents could be very useful to a country intent on diverting uranium for clandestine use. Each of these large cylinders can contain close to a significant quantity of natural uranium (48Y cylinder) or low-enriched uranium (LEU) (30B cylinder) defined as 75 kg {sup 235}U which can be further clandestinely enriched to produce 1.5 to 2 significant quantities of high enriched uranium (HEU) within weeks or months depending on the scale of the clandestine facility. The National Nuclear Security Administration (NNSA) Next Generation Safeguards Initiative (NGSI) kicked off a 5-year plan in April 2011 to investigate the concept of a unique identification system for UF{sub 6} cylinders and potentially to develop a cylinder tracking system that could be used by facility operators and the International Atomic Energy Agency (IAEA). The goal is to design an integrated solution beneficial to both industry and inspectorates that would improve cylinder operations at the facilities and provide enhanced capabilities to deter and detect both diversion of low-enriched uranium and undeclared enriched uranium production. The 5-year plan consists of six separate incremental tasks: (1) define the problem and establish the requirements for a unique identification (UID) and monitoring system; (2) develop a concept of operations for the identification and monitoring system; (3) determine cylinder monitoring devices and technology; (4) develop a registry database to support proof-of-concept demonstration; (5) integrate that system for the demonstration; and (6) demonstrate proof-of-concept. Throughout NNSA's performance of the tasks outlined in this program, the multi-laboratory team emphasizes that extensive engagement with industry stakeholders, regulatory authorities and inspectorates is essential to its success.

  1. Monitoring the mass of UF6 gas and uranium deposits in aluminium pipes using X-ray fluorescence and X-ray transmission gauges

    International Nuclear Information System (INIS)

    Packer, T.W.; Smith, S.M.

    1984-12-01

    In order to determine the enrichment of UF 6 gas in centrifuge plant pipework it is necessary to measure the mass of the gas (pressure) and the mass per unit area of any uranium deposited on the pipe. This paper shows that it is possible to determine the pressure of the UF 6 gas in pipes 120 mm in diameter using an energy-dispersive X-ray fluorescence spectrometer. Results are also given of transmission measurements made using a low power X-ray generator operated at two different applied voltages. A method of using the two measurements to determine the mass per unit area of deposited uranium is described. (author)

  2. A Radiation-Triggered Surveillance System for UF6 Cylinder Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Curtis, Michael M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Myjak, Mitchell J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-09-23

    This report provides background information and representative scenarios for testing a prototype radiation-triggered surveillance system at an operating facility that handles uranium hexafluoride (UF6) cylinders. The safeguards objective is to trigger cameras using radiation, or radiation and motion, rather than motion alone, to reduce significantly the number of image files generated by a motion-triggered system. The authors recommend the use of radiation-triggered surveillance at all facilities where cylinder paths are heavily traversed by personnel. The International Atomic Energy Agency (IAEA) has begun using surveillance cameras in the feed and withdrawal areas of gas centrifuge enrichment plants (GCEPs). The cameras generate imagery using elapsed time or motion, but this creates problems in areas occupied 24/7 by personnel. Either motion-or-interval-based triggering generates thousands of review files over the course of a month. Since inspectors must review the files to verify operator material-flow-declarations, a plethora of files significantly extends the review process. The primary advantage of radiation-triggered surveillance is the opportunity to obtain full-time cylinder throughput verification versus what presently amounts to part-time verification. Cost savings should be substantial, as the IAEA presently uses frequent unannounced inspections to verify cylinder-throughput declarations. The use of radiation-triggered surveillance allows the IAEA to implement less frequent unannounced inspections for the purpose of flow verification, but its principal advantage is significantly shorter and more effective inspector video reviews.

  3. An unattended verification station for UF6 cylinders: Field trial findings

    Science.gov (United States)

    Smith, L. E.; Miller, K. A.; McDonald, B. S.; Webster, J. B.; Zalavadia, M. A.; Garner, J. R.; Stewart, S. L.; Branney, S. J.; Todd, L. C.; Deshmukh, N. S.; Nordquist, H. A.; Kulisek, J. A.; Swinhoe, M. T.

    2017-12-01

    In recent years, the International Atomic Energy Agency (IAEA) has pursued innovative techniques and an integrated suite of safeguards measures to address the verification challenges posed by the front end of the nuclear fuel cycle. Among the unattended instruments currently being explored by the IAEA is an Unattended Cylinder Verification Station (UCVS), which could provide automated, independent verification of the declared relative enrichment, 235U mass, total uranium mass, and identification for all declared uranium hexafluoride cylinders in a facility (e.g., uranium enrichment plants and fuel fabrication plants). Under the auspices of the United States and European Commission Support Programs to the IAEA, a project was undertaken to assess the technical and practical viability of the UCVS concept. The first phase of the UCVS viability study was centered on a long-term field trial of a prototype UCVS system at a fuel fabrication facility. A key outcome of the study was a quantitative performance evaluation of two nondestructive assay (NDA) methods being considered for inclusion in a UCVS: Hybrid Enrichment Verification Array (HEVA), and Passive Neutron Enrichment Meter (PNEM). This paper provides a description of the UCVS prototype design and an overview of the long-term field trial. Analysis results and interpretation are presented with a focus on the performance of PNEM and HEVA for the assay of over 200 "typical" Type 30B cylinders, and the viability of an "NDA Fingerprint" concept as a high-fidelity means to periodically verify that material diversion has not occurred.

  4. Utilization of the NFS West Valley Installation for spent fuel storage

    International Nuclear Information System (INIS)

    MacDonald, R.W.

    1978-04-01

    Several thousand MT of capacity of AFR storage will be required in the 1980's. The pool at NFS has capacity for an additional 60 MT of BWR fuel or 150 MT of PWR assemblies. Zircaloy-clad LWR fuel can be stored in pools for up to 100 years. Environmental effects are discussed. Expansion of the pool capacity for as much as 1000 MT more, either by using more compact storage racks or constructing a new pool or an independent pool, is considered. Some indication of the environmental impacts of expanded fuel storage capacity at West Valley is offered by experience at Barnwell

  5. Functions and Requirements for West Valley Demonstration Project Tank Lay-up

    International Nuclear Information System (INIS)

    Elmore, Monte R.; Henderson, Colin

    2002-01-01

    Documents completion of Milestone A.1-1, ''Issue Functions and Requirements for WVDP Tank Lay-Up,'' in Technical Task Plan TTP RL3-WT21A - ''Post-Retrieval and Pre-Closure HLW Tank Lay-Up.'' This task is a collaborative effort among Pacific Northwest National Laboratory, Jacobs Engineering Group Inc., and West Valley Nuclear Services (WVNS). Because of the site-specific nature of this task, the involvement of WVNS personnel is critical to the success of this task

  6. Surface decontamination in the old storage shed number 99 of the General Plan of IPEN/CNEN-SP, containing production equipment of natural uranium hexafluoride (UF6), aiming at its decommissioning

    International Nuclear Information System (INIS)

    Almeida, Claudio C. de; Cambises, Paulo B.S.; Paiva, Julio E. de; Paiva, Julio E. de; Silva, Teresina M.; Rodrigues, Demerval L.

    2013-01-01

    This paper presents the steps adopted in the operation planned for the decontamination of surfaces in the old storage shed number 99 the general layout of the Energy Research and Nuclear IPEN-CNEN/SP, Brazil, and contained various types of equipment originating from production hexafluoride natural uranium (UF6). This operation involved the planning, training of operators of the facility, analysis of workplaces and radiometric surveys for monitoring of external radiation and surface contamination. The training involved the procedures for decontamination of surfaces, segregation of materials and practical procedures for individual monitoring of contamination outside of the body. Were also established rules for the transport of radioactive materials in the internal and external facility and release of material and sites already decontaminated

  7. Summary and evaluation of existing geological and geophysical data near prospective surface facilities in Midway Valley, Yucca Mountain Project, Nye County, Nevada

    International Nuclear Information System (INIS)

    Gibson, J.D.; Swan, F.H.; Wesling, J.R.; Bullard, T.F.; Perman, R.C.; Angell, M.M.; DiSilvestro, L.A.

    1992-01-01

    Midway Valley, located at the eastern base of the Yucca Mountain in southwestern Nevada, is the preferred location of the surface facilities for the potential high-level nuclear waste repository at Yucca Mountain. One goal in siting these surface facilities is to avoid faults that could produce relative displacements in excess of 5 cm in the foundations of the waste-handling buildings. This study reviews existing geologic and geophysical data that can be used to assess the potential for surface fault rupture within Midway Valley. Dominant tectonic features in Midway Valley are north-trending, westward-dipping normal faults along the margins of the valley: the Bow Ridge fault to the west and the Paintbrush Canyon fault to the east. Published estimates of average Quaternary slip rates for these faults are very low but the age of most recent displacement and the amount of displacement per event are largely unknown. Surface mapping and interpretive cross sections, based on limited drillhole and geophysical data, suggest that additional normal faults, including the postulated Midway Valley fault, may exist beneath the Quaternary/Tertiary fill within the valley. Existing data, however, are inadequate to determine the location, recency, and geometry of this faulting. To confidently assess the potential for significant Quaternary faulting in Midway Valley, additional data are needed that define the stratigraphy and structure of the strata beneath the valley, characterize the Quaternary soils and surfaces, and establish the age of faulting. The use of new and improved geophysical techniques, combined with a drilling program, offers the greatest potential for resolving subsurface structure in the valley. Mapping of surficial geologic units and logging of soil pits and trenches within these units must be completed, using accepted state-of-the-art practices supported by multiple quantitative numerical and relative age-dating techniques

  8. West Valley demonstration project: alternative processes for solidifying the high-level wastes

    International Nuclear Information System (INIS)

    Holton, L.K.; Larson, D.E.; Partain, W.L.; Treat, R.L.

    1981-10-01

    In 1980, the US Department of Energy (DOE) established the West Valley Solidification Project as the result of legislation passed by the US Congress. The purpose of this project was to carry out a high level nuclear waste management demonstration project at the Western New York Nuclear Service Center in West Valley, New York. The DOE authorized the Pacific Northwest Laboratory (PNL), which is operated by Battelle Memorial Institute, to assess alternative processes for treatment and solidification of the WNYNSC high-level wastes. The Process Alternatives Study is the suject of this report. Two pretreatment approaches and several waste form processes were selected for evaluation in this study. The two waste treatment approaches were the salt/sludge separation process and the combined waste process. Both terminal and interim waste form processes were studied. The terminal waste form processes considered were: borosilicate glass, low-alkali glass, marbles-in-lead matrix, and crystallinolecular potential and molecular dynamics calculations of the effect are yet to be completed. Cous oxide was also investigated. The reaction is first order in nitrite ion, second order in hydrogen ion, and between zero and first order in hydroxylamine monosulfonate, depending on the concentration

  9. Slurry feed variability in West Valley's melter feed tank and sampling system

    International Nuclear Information System (INIS)

    Fow, C.L.; Kurath, D.E.; Pulsipher, B.A.; Bauer, B.P.

    1989-04-01

    The present plan for disposal of high-level wastes at West Valley is to vitrify the wastes for disposal in deep geologic repository. The vitrification process involves mixing the high-level wastes with glass-forming chemicals and feeding the resulting slurry to a liquid-fed ceramic melter. Maintaining the quality of the glass product and proficient melter operation depends on the ability of the melter feed system to produce and maintain a homogeneous mixture of waste and glass-former materials. To investigate the mixing properties of the melter feed preparation system at West Valley, a statistically designed experiment was conducted using synthetic melter feed slurry over a range of concentrations. On the basis of the statistical data analysis, it was found that (1) a homogeneous slurry is produced in the melter feed tank, (2) the liquid-sampling system provides slurry samples that are statistically different from the slurry in the tank, and (3) analytical measurements are the major source of variability. A statistical quality control program for the analytical laboratory and a characterization test of the actual sampling system is recommended. 1 ref., 5 figs., 1 tab

  10. Selection of a reference process for treatment of the West Valley alkaline waste

    International Nuclear Information System (INIS)

    Bray, L.A.; Holton, L.K.; Wise, B.M.; Carl, D.E.; Pope, J.M.

    1984-01-01

    As part of the West Valley Demonstration Project (WVDP) the alkaline PUREX supernatant stored in Tank 8D2 will be partially decontaminated by the removal of radiocesium. Four processes for removal of radiocesium from the alkaline supernatant were studied through experimentation and engineering analysis to identify a reference approach for the WVDP. These processes included the use of a zeolite inorganic ion-exchanger (Linde Ionsiv IE-95, Ionsiv is a trademark of Union Carbide Company), an organic ion exchange resin (Duolite CS-100, Duolite is a registered trademark of Diamond Shamrock Co) and two precipitation processes; one using sodium tetraphenylboron (NaTPB) and the other using phosphotungsthC acid (PTA). Based upon process performance, safety and environmental considerations, process and equipment complexity and impacts to the waste vitrification system, the zeolite ion-exchange process has been selected by West Valley Nuclear Services, Inc., as the reference supernatant treatment process for the WVDP. This paper summarizes the technical basis for the selection of the zeolite ion-exchange process

  11. Evaluation of process alternatives for solidification of the West Valley high-level liquid wastes

    International Nuclear Information System (INIS)

    Holton, L.K.; Larson, D.E.

    1982-01-01

    The Department of Energy (DOE) established the West Valley Solidification Project (WVSP) in 1980. The project purpose is to demonstrate removal and solidification of the high-level liquid wastes (HLLW) presently stored in tanks at the Western New York Nuclear Service Center (WNYNSC), West Valley, New York. As part of this effort, the Pacific Northwest Laboratory (PNL) conducted a study to evaluate process alternatives for solidifcation of the WNYNSC wastes. Two process approaches for waste handling before solidification, together with solidification processes for four terminal and four interim waste forms, were considered. The first waste-handling approach, designated the salt/sludge separation process, involves separating the bulk of the nonradioactive nuclear waste constituents from the radioactive waste constituents, and the second waste-handling approach, designated the combined-waste process, involves no waste segregation prior to solidification. The processes were evaluated on the bases of their (1) readiness for plant startup by 1987, (2) relative technical merits, and (3) process cost. The study has shown that, based on these criteria, the salt/sludge separation process with a borosilicate glass waste form is preferred when producing a terminal waste form. It was also concluded that if an interim waste form is to be used, the preferred approach would be the combined waste process with a fused-salt waste form

  12. West Valley Demonstration Project site environmental report for calendar year 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    The West Valley Demonstration Project (WVDP), the site of a US Department of Energy environmental cleanup activity operated by West Valley Nuclear Services Co., Inc., (WVNS), is in the process of solidifying liquid high-level radioactive waste remaining at the site after commercial nuclear fuel reprocessing was discontinued. The Project is located in Western New York State, about 30 miles south of Buffalo, within the New York State-owned Western New York Nuclear Service Center (WNYNSC). This report represents a single, comprehensive source of off-site and on-site environmental monitoring data collected during 1996 by environmental monitoring personnel. The environmental monitoring program and results are discussed in the body of this report. The monitoring data are presented in the appendices. Appendix A is a summary of the site environmental monitoring schedule. Appendix B lists the environmental permits and regulations pertaining to the WVDP. Appendices C through F contain summaries of data obtained during 1996 and are intended for those interested in more detail than is provided in the main body of the report.

  13. Impact of valley fills on streamside salamanders in southern West Virginia

    Science.gov (United States)

    Wood, Petra Bohall; Williams, Jennifer M.

    2013-01-01

    Valley fills associated with mountaintop-removal mining bury stream headwaters and affect water quality and ecological function of reaches below fills. We quantified relative abundance of streamside salamanders in southern West Virginia during 2002 in three streams below valley fills (VFS) and in three reference streams (RS). We surveyed 36 10- × 2-m stream transects, once in summer and fall, paired by order and structure. Of 2,343 salamanders captured, 66.7% were from RS. Total salamanders (adults plus larvae) were more abundant in RS than VFS for first-order and second-order reaches. Adult salamanders had greater abundance in first-order reaches of RS than VFS. Larval salamanders were more abundant in second-order reaches of RS than VFS. No stream width or mesohabitat variables differed between VFS and RS. Only two cover variables differed. Silt cover, greater in VFS than RS first-order reaches, is a likely contributor to reduced abundance of salamanders in VFS. Second-order RS had more boulder cover than second-order VFS, which may have contributed to the higher total and larval salamander abundance in RS. Water chemistry assessments of our VFS and RS reported elevated levels of metal and ion concentrations in VFS, which can depress macroinvertebrate populations and likely affect salamander abundance. Valley fills appear to have significant negative effects on stream salamander abundance due to alterations in habitat structure, water quality and chemistry, and macroinvertebrate communities in streams below fills.

  14. Water quality and processes affecting dissolved oxygen concentrations in the Blackwater River, Canaan Valley, West Virginia

    Science.gov (United States)

    Waldron, M.C.; Wiley, J.B.

    1996-01-01

    The water quality and environmental processes affecting dissolved oxygen were determined for the Blackwater River in Canaan Valley, West Virginia. Canaan Valley is oval-shaped (14 miles by 5 miles) and is located in the Allegheny Mountains at an average elevation of 3,200 feet above sea level. Tourism, population, and real estate development have increased in the past two decades. Most streams in Canaan Valley are a dilute calcium magnesium bicarbonate-type water. Streamwater typicaly was soft and low in alkalinity and dissolved solids. Maximum values for specific conductance, hardness, alkalinity, and dissolved solids occurred during low-flow periods when streamflow was at or near baseflow. Dissolved oxygen concentrations are most sensitive to processes affecting the rate of reaeration. The reaeration is affected by solubility (atmospheric pressure, water temperature, humidity, and cloud cover) and processes that determine stream turbulence (stream depth, width, velocity, and roughness). In the headwaters, photosynthetic dissolved oxygen production by benthic algae can result in supersaturated dissolved oxygen concentrations. In beaver pools, dissolved oxygen consumption from sediment oxygen demand and carbonaceous biochemical oxygen demand can result in dissolved oxygen deficits.

  15. COGEMA's UMF [Uranium Management Facility

    International Nuclear Information System (INIS)

    Lamorlette, G.; Bertrand, J.P.

    1988-01-01

    The French government-owned corporation, COGEMA, is responsible for the nuclear fuel cycle. This paper describes the activities at COGEMA's Pierrelatte facility, especially its Uranium Management Facility. UF6 handling and storage is described for natural, enriched, depleted, and reprocessed uranium. UF6 quality control specifications, sampling, and analysis (halocarbon and volatile fluorides, isotopic analysis, uranium assay, and impurities) are described. In addition, the paper discusses the filling and cleaning of containers and security at UMF

  16. HGSYSTEM/UF6 model enhancements for plume rise and dispersion around buildings, lift-off of buoyant plumes, and robustness of numerical solver

    International Nuclear Information System (INIS)

    Hanna, S.R.; Chang, J.C.

    1997-01-01

    The HGSYSTEM/UF 6 model was developed for use in preparing Safety Analysis Reports (SARs) by estimating the consequences of possible accidental releases of UF 6 to the atmosphere at the gaseous diffusion plants (GDPs) located in Portsmouth, Ohio, and Paducah, Kentucky. Although the latter report carries a 1996 date, the work that is described was completed in late 1994. When that report was written, the primary release scenarios of interest were thought to be gas pipeline and liquid tank ruptures over open terrain away from the influence of buildings. However, upon further analysis of possible release scenarios, the developers of the SARs decided it was necessary to also consider accidental releases within buildings. Consequently, during the fall and winter of 1995-96, modules were added to HGSYSTEM/UF 6 to account for flow and dispersion around buildings. The original HGSYSTEM/UF 6 model also contained a preliminary method for accounting for the possible lift-off of ground-based buoyant plumes. An improved model and a new set of wind tunnel data for buoyant plumes trapped in building recirculation cavities have become available that appear to be useful for revising the lift-off algorithm and modifying it for use in recirculation cavities. This improved lift-off model has been incorporated in the updated modules for dispersion around buildings

  17. Assessment of Reusing 14-Ton, Thin-Wall, Depleted UF6 Cylinders as LLW Disposal Containers

    International Nuclear Information System (INIS)

    O'Connor, D.G.; Poole, A.B.; Shelton, J.H.

    2000-01-01

    Approximately 700,000 MT of DUF 6 is stored, or will be produced under a current agreement with the USEC, at the Paducah site in Kentucky, Portsmouth site in Ohio, and ETTP site in Tennessee. On July 21, 1998, the 105th Congress approved Public Law 105-204, which directed that facilities be built at the Kentucky and Ohio sites to convert DUF 6 to a stable form for disposition. On July 6, 1999, the Department of Energy (DOE) issued the ''Final Plan for the Conversion of Depleted Uranium Hexafluoride as Required by Public Law 105-204'', in which DOE committed to develop a ''Depleted Uranium Hexafluoride Materials Use Roadmap''. On September 1,2000, DOE issued the ''Draft Depleted Uranium Hexafluoride Materials Use Roadmap'' (Roadmap), which provides alternate paths for the long-term storage, beneficial use, and eventual disposition of each product form and material that will result from the DUF 6 conversion activity. One of the paths being considered for DUF 6 cylinders is to reuse the empty cylinders as containers to transport and dispose of LLW, including the converted DU. The Roadmap provides results of the many alternate uses and disposal paths for conversion products and the empty DUF 6 storage cylinders. As a part of the Roadmap, evaluations were conducted of cost savings, technical maturity, barriers to implementation, and other impacts. Results of these evaluations indicate that using the DUF 6 j storage cylinders as LLW disposal containers could provide moderate cost savings due to the avoided cost of purchasing LLW packages and the avoided cost of disposing of the cylinders. No significant technical or institutional .issues were identified that.would make using cylinders as LLW packages less effective than other disposition paths. Over 58,000 cylinders have been used, or will be used, to store DUF 6 . Over 5 1,000 of those cylinders are 14TTW cylinders with a nominal wall thickness of 5/16-m (0.79 cm). These- 14TTW cylinders, which have a nominal diameter

  18. A nuclear criticality safety assessment of the loss of moderation control in 2 1/2 and 10-ton cylinders containing enriched UF6

    International Nuclear Information System (INIS)

    Newvahner, R.L.; Pryor, W.A.

    1991-01-01

    Moderation control for maintaining nuclear criticality safety in 2-1/2-ton, 10-ton, and 14-ton cylinders containing enriched uranium hexafluoride (UF 6 ) has been used safely within the nuclear industry for over thirty years, and is dependent on cylinder integrity and containment. This assessment evaluates the loss of moderation control by the breaching of containment and entry of water into the cylinders. The first objective of this study was to estimate the required amounts of water entering these large UF 6 cylinders to react with, and to moderate the uranium compounds sufficiently to cause criticality. Hypothetical accident situations were modeled as a uranyl fluoride (UO 2 F 2 ) slab above a UF 6 hemicylinder, and a UO 2 sphere centered within a UF 6 hemicylinder. These situations were investigated by computational analyses utilizing the KENO V.a Monte Carlo Computer Code. The results were used to estimate both the masses of water required for criticality, and the limiting masses of water that could be considered safe. The second objective of the assessment was to calculate the time available for emergency control actions before a criticality would occur, i.e., a ''safetime,'' for various sources of water and different size openings in a breached cylinder. In the situations considered, except the case for a fire hose, the safetime appears adequate for emergency control actions. The assessment shows that current practices for handling moderation controlled cylinders of low enriched UF 6 , along with the continuation of established personnel training programs, ensure nuclear criticality safety for routine and emergency operations. 2 refs., 5 figs., 1 tab

  19. A summary of recent refinements to the WAKE dispersion model, a component of the HGSYSTEM/UF6 model suite

    International Nuclear Information System (INIS)

    Yambert, M.W.; Lombardi, D.A.; Goode, W.D. Jr.; Bloom, S.G.

    1998-08-01

    The original WAKE dispersion model a component of the HGSYSTEM/UF 6 model suite, is based on Shell Research Ltd.'s HGSYSTEM Version 3.0 and was developed by the US Department of Energy for use in estimating downwind dispersion of materials due to accidental releases from gaseous diffusion plant (GDP) process buildings. The model is applicable to scenarios involving both ground-level and elevated releases into building wake cavities of non-reactive plumes that are either neutrally or positively buoyant. Over the 2-year period since its creation, the WAKE model has been used to perform consequence analyses for Safety Analysis Reports (SARs) associated with gaseous diffusion plants in Portsmouth (PORTS), Paducah (PGDP), and Oak Ridge. These applications have identified the need for additional model capabilities (such as the treatment of complex terrain and time-variant releases) not present in the original utilities which, in turn, has resulted in numerous modifications to these codes as well as the development of additional, stand-alone postprocessing utilities. Consequently, application of the model has become increasingly complex as the number of executable, input, and output files associated with a single model run has steadily grown. In response to these problems, a streamlined version of the WAKE model has been developed which integrates all calculations that are currently performed by the existing WAKE, and the various post-processing utilities. This report summarizes the efforts involved in developing this revised version of the WAKE model

  20. Method and equipment for continuous transformation of UF6 into (NH4)2U2O7

    International Nuclear Information System (INIS)

    Fuller, R.R.

    1975-01-01

    Uranium hexafluoride is, in a three-stage method, transformed into ammonium diuvanate which can be calcined to UO 2 of good ceramic quality. At the solution of UF 6 in water, UO 2 F 2 and HF form in condsiderably acid solution. This aqueous hydrolysis solution is with standardized using NH 4 O 4 (24-29% NH 3 ) at a pH-value between 5.0 and 6.0 and brought into a precipitation tank. The bulk of the ammonium diuvanate then precipitating is drained in the lower portion of the tank and added again to the suspension, close to the surface of the fluid, under intensive pressure. The intensive vigorous revolution of the entire tank content affects the size of the particles and the size of the surface of the precipitating uranate as well. The equipment for the calcination of the ammonium diuvanate is described. The method represents an improvement of the method described in OS 2162578; the pellets produced are more satisfying to critical requirements. (UWI) [de

  1. Interventions Against West Nile Virus, Rift Valley Fever Virus, and Crimean-Congo Hemorrhagic Fever Virus: Where Are We?

    NARCIS (Netherlands)

    Kortekaas, J.A.; Ergonul, O.; Moormann, R.J.M.

    2010-01-01

    ARBO-ZOONET is an international network financed by the European Commission's seventh framework program. The major goal of this initiative is capacity building for the control of emerging viral vector-borne zoonotic diseases, with a clear focus on West Nile virus, Rift Valley fever virus, and

  2. Decontamination of the Scrap Removal Room at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Bridenbaker, W.A.; Clemons, L.

    1987-02-01

    This report describes the decontamination and decommissioning (D and D) of the Scrap Removal Room (SRR) at the West Valley Demonstration Project (WVDP). The SRR is an area in the former reprocessing plant that is required for use in support of D and D for other plant areas. The SRR contained a 6.8 Mg (7.5-ton) crane for loading waste material into a shielded truck cask. It became radioactively contaminated during fuel reprocessing from 1966 to 1972. This report describes the work performed to accomplish the D and D objectives of removing existing piping and equipment and of reducing radiation and contamination levels, to As-Low-As-Reasonably-Achievable (ALARA) levels for the installation of new equipment. Also reported are pre- and post-radiological conditions, personnel exposure, radioactive waste volume collected, cost and schedule data, and lessons learned

  3. Decontamination of the extraction sample aisle at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Vance, R.F.

    1986-09-01

    This report describes the decontamination and decommissioning (D and D) of the Extraction Sample Aisle (XSA) at the West Valley Demonstration Project. The XSA is one of several areas in the former reprocessing plant required for use in support of the solidification of high-level waste. The XSA contained three glove boxes which housed sample stations. It became radioactively contaminated during fuel reprocessing from 1966 to 1972. This report describes the work performed to accomplish the D and D objectives of removing existing piping and equipment and of reducing radiation and contamination levels, to As-Low-As-Reasonably-Achievable (ALARA) levels for the installation of new equipment. Also reported are pre- and post-radiological conditions, personnel exposure, radioactive waste volume collected, cost and schedule data, and lessons learned

  4. Supplement analysis 2 of environmental impacts resulting from modifications in the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    1998-01-01

    The West Valley Demonstration Project, located in western New York, has approximately 600,000 gallons of liquid high-level radioactive waste (HLW) in storage in underground tanks. While corrosion analysis has revealed that only limited tank degradation has taken place, the failure of these tanks could release HLW to the environment. Congress requires DOE to demonstrate the technology for removal and solidification of HLW. DOE issued the Final Environmental Impact Statement (FEIS) in 1982. The purpose of this second supplement analysis is to re-assess the 1982 Final Environmental Impact Statement's continued adequacy. This report provides the necessary and appropriate data for DOE to determine whether the environmental impacts presented by the ongoing refinements in the design, process, and operations of the Project are considered sufficiently bounded within the envelope of impacts presented in the FEIS and supporting documentation

  5. Characterization of the head end cells at the West Valley Nuclear Fuel Reprocessing Plant

    International Nuclear Information System (INIS)

    Vance, R.F.

    1986-11-01

    The head-end cells at the West Valley Nuclear Fuel Reprocessing Plant are characterized in this report. These cells consist of the Process Mechanical Cell (PMC) where irradiated nuclear fuel was trimmed of excess hardware and sheared into short segments; and the General Purpose Cell (GPC) where the segments were collected and stored prior to dissolution, and leached hulls were packaged for disposal. Between 1966 and 1972, while Nuclear Fuels Services operated the plant, these cells became highly contaminated with radioactive materials. The purpose of this characterization work was to develop technical information as a basis of decontamination and decommissioning planning and engineering. It was accomplished by performing remote in-cell visual examinations, radiation surveys, and sampling. Supplementary information was obtained from available written records, out-of-cell inspections, and interviews with plant personnel

  6. Lessons learned from the West Valley spent nuclear fuel shipment within the United States

    International Nuclear Information System (INIS)

    Tyacke, M.J.; Anderson, T.

    2004-01-01

    This paper describes the lessons learned from the U.S. Department of Energy (DOE) transportation of 125 DOE-owned commercial spent nuclear fuel (SNF) assemblies by railroad from the West Valley Demonstration Project to the Idaho National Engineering and Environmental Laboratory (INEEL). On July 17, 2003, DOE made the largest single shipment of commercial SNF in the history of the United States. This was a highly visible and political shipment that used two specially designed Type B transportation and storage casks. This paper describes the background and history of the shipment. It discusses the technical challenges for licensing Type B packages for hauling large quantities of SNF, including the unique design features, testing and analysis. This paper also discusses the preshipment planning, preparations, coordination, route evaluation and selection, carrier selection and negotiations, security, inspections, tracking, and interim storage at the INEEL

  7. West Valley Demonstration Project community relations plan FY 1990/91

    International Nuclear Information System (INIS)

    Damerow, M.W.

    1989-09-01

    The purpose of the Community Relations Plan is to fully inform the community about the West Valley Demonstration Project (WVDP) and provide opportunities for public input. A sound approach to community relations is essential to the creation and maintenance of public awareness and community support. The WVDP is a matter of considerable public interest because it deals with nuclear waste. The mission of the WVDP is to solve an existing environmental concern by solidifying high-level radioactive waste and transporting the solidified waste to a federal repository for permanent disposal. The public requires evidence of the continued commitment and demonstrated progress of the industry and government in carrying out the mission in order to sustain confidence that the WVDP is being managed well and will be discussed successfully completed. For this reason, a comprehensive communication plan is essential for the successful completion of the WVDP

  8. The public visits a nuclear waste site: Survey results from the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Hoffman, W.D.

    1987-01-01

    This paper discusses the results of the 1986 survey taken at the West Valley Demonstration Project Open House where a major nuclear waste cleanup is in progress. Over 1400 people were polled on what they think is most effective in educating the public on nuclear waste. A demographic analysis describes the population attending the event and their major interests in the project. Responses to attitudinal questions are examined to evaluate the importance of radioactive waste cleanup as an environmental issue and a fiscal responsibility. Additionally, nuclear power is evaluated on its public perception as an energy resource. The purpose of the study is to find out who visits a nuclear waste site and why, and to measure their attitudes on nuclear issues

  9. Washing water treatment process for UF_6 cylinder by adjusting evaporation technology in a low temperature and low pressure

    International Nuclear Information System (INIS)

    Kim, Ki-tae; Ju, Young-jong; Cho, Nam-chan; Kim, Yun-kwan; Jin, Chang-suk

    2016-01-01

    The liquid waste is treated in this procedure; 1) Add NaOH to the liquid waste and filter the mixture with a screen. 2) Screened residue is dried and then stored in a uranium storage. 3) liquid part is moved to a storage tank and radioactivity is measured in the liquid. 5) If the concentration of radioactivity is lower than corresponding regulation limit, the liquid moved to a reaction tank and evaporated with additional low concentration HF in 105℃. 6) Radioactivity of distillate is measured and the value is lower than regulation, it is treated with a thermal decomposition process and discharged to the atmosphere in gas state. 7) Solid waste produced in the evaporation step is managed as solid nuclear waste. The treatment procedure mentioned above has disadvantageous points, producing large amount of solid waste as well as, high energy and chemical consumption. In this study, liquid waste from a real scaled cylinder wash process is applied to evaporation system to confirm feasibility of the application of evaporation and, to reduce waste production and energy consumption. Liquid radioactive wastewater from a real scaled UF6 cylinder wash process was applied to evaporation treatment system. Radioactive concentration in gross alpha was removed 99.9% in the evaporation system. And the concentration in distillate was lower than the discharge regulation. Removal of U-235 was 99.9% in the process. And 15 other kinds of radionuclides in the raw wastewater were removed completely. Secondary waste production of the evaporation system is 15g/L

  10. The Ohio River Valley CO2 Storage Project AEP Mountaineer Plan, West Virginia

    Energy Technology Data Exchange (ETDEWEB)

    Neeraj Gupta

    2009-01-07

    This report includes an evaluation of deep rock formations with the objective of providing practical maps, data, and some of the issues considered for carbon dioxide (CO{sub 2}) storage projects in the Ohio River Valley. Injection and storage of CO{sub 2} into deep rock formations represents a feasible option for reducing greenhouse gas emissions from coal-burning power plants concentrated along the Ohio River Valley area. This study is sponsored by the U.S. Department of Energy (DOE) National Energy Technology Laboratory (NETL), American Electric Power (AEP), BP, Ohio Coal Development Office, Schlumberger, and Battelle along with its Pacific Northwest Division. An extensive program of drilling, sampling, and testing of a deep well combined with a seismic survey was used to characterize the local and regional geologic features at AEP's 1300-megawatt (MW) Mountaineer Power Plant. Site characterization information has been used as part of a systematic design feasibility assessment for a first-of-a-kind integrated capture and storage facility at an existing coal-fired power plant in the Ohio River Valley region--an area with a large concentration of power plants and other emission sources. Subsurface characterization data have been used for reservoir simulations and to support the review of the issues relating to injection, monitoring, strategy, risk assessment, and regulatory permitting. The high-sulfur coal samples from the region have been tested in a capture test facility to evaluate and optimize basic design for a small-scale capture system and eventually to prepare a detailed design for a capture, local transport, and injection facility. The Ohio River Valley CO{sub 2} Storage Project was conducted in phases with the ultimate objectives of demonstrating both the technical aspects of CO{sub 2} storage and the testing, logistical, regulatory, and outreach issues related to conducting such a project at a large point source under realistic constraints. The site

  11. Scaled Vitrification System III (SVS III) Process Development and Laboratory Tests at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Jain, V.; Barnes, S.M.; Bindi, B.G.; Palmer, R.A.

    2000-01-01

    At the West Valley Demonstration Project (WVDP),the Vitrification Facility (VF)is designed to convert the high-level radioactive waste (HLW)stored on the site to a stable glass for disposal at a Department of Energy (DOE)-specified federal repository. The Scaled Vitrification System III (SVS-III)verification tests were conducted between February 1995 and August 1995 as a supplemental means to support the vitrification process flowsheet, but at only one seventh the scale.During these tests,the process flowsheet was refined and optimized. The SVS-III test series was conducted with a focus on confirming the applicability of the Redox Forecasting Model, which was based on the Index of Feed Oxidation (IFO)developed during the Functional and Checkout Testing of Systems (FACTS)and SVS-I tests. Additional goals were to investigate the prototypical feed preparation cycle and test the new target glass composition. Included in this report are the basis and current designs of the major components of the Scale Vitrification System and the results of the SVS-III tests.The major subsystems described are the feed preparation and delivery, melter, and off-gas treatment systems. In addition,the correlation between the melter's operation and its various parameters;which included feed rate,cold cap coverage,oxygen reduction (redox)state of the glass,melter power,plenum temperature,and airlift analysis;were developed

  12. The End of the Line, Preparing the Main Plant Process Building for Demolition at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Rowell, L.E.; Kurasch, D.H.; Hackett, M.; Gorsuch, G.; Sullivan, D.W.

    2009-01-01

    The West Valley Demonstration Project (WVDP) Act of 1980 authorized the Department of Energy to conduct a high-level radioactive waste management demonstration project at the site of the former Spent Fuel Reprocessing Plant in West Valley, New York to demonstrate solidification techniques to prepare high-level liquid waste for disposal. The reprocessing facility at this site was the only commercial NRC-licensed spent fuel reprocessing plant to have operated in the United States. The spent fuel reprocessing operations ended in 1972 and DoE's cleanup operations have been underway since 1982. High-level waste solidification was safely concluded in 2002 and follow-on activities at the site have been concentrated on facility decontamination and waste management and off-site disposal. Among the features that remain at the WVDP site is the highly-contaminated Main Plant Process Building (MPPB). The five-story reinforced concrete structure, which was formerly used to reprocess irradiated nuclear fuel, contains residual levels of contamination in some areas that prohibit safe human entry. DoE's long-range plans for the site include demolition of the MPPB. Current site contractor, West Valley Environmental Services LLC (WVES), while actively working to dismantle equipment and decontaminate areas inside the MPPB, has developed a conceptual two-phase plan for demolishing the structure that provides a cost-effective, lower-dose alternative to conventional demolition techniques. This paper discusses the current condition of the MPPB and the demolition-ready preparations conducted in the facility thus far. This paper also introduces the concept of a two-part surgical demolition plan that has been proposed and is being evaluated as a safe method of demolishing the structure. The practical applications that support feasibility for the demolition approach are being demonstrated through current work applications in the MPPB. The Inside-Out Demolition proposal for the MPPB is a safe

  13. Acute toxicity of the hydrolysis products of uranium hexafluoride (UF6) when inhaled by the rat and guinea pig. Final report

    International Nuclear Information System (INIS)

    Leach, L.J.; Gelein, R.M.; Panner, B.J.; Yulie, C.L.; Cox, C.C.; Balys, M.M.; Rolchigo, P.M.

    1984-04-01

    This report presents the experimental animal data base from which human health consequences may be predicted from exposures mimicing accidental discharges of uranium hexafluoride (UF 6 ) in the uranium industry. Rats or guinea pigs were exposed for two, five, or ten minutes duration to air having 0.44 g U/m 3 + 0.16 g HF/m 3 to 276.67 g U/m 3 + 94.07 g HF/m 3 . Survivors of each exposure were observed for 14 days for signs of U or HF intoxication. Selected animals were necropsied and samples of major organs were studied histopathologically. When enriched UF 6 (94 percent 235 U) was used, the urine and feces from each animal were measured daily for U content. Selected samples of urine were bioassayed in order to trace the course of renal injury during the two week postexposure period. 28 references, 51 figures, 23 tables

  14. ERDA test facilities, East Mesa Test Site. Geothermal resource investigations, Imperial Valley, California

    Energy Technology Data Exchange (ETDEWEB)

    1976-01-01

    Detailed specifications which must be complied with in the construction of the ERDA Test Facilities at the East Mesa Site for geothermal resource investigations in Imperial Valley, California are presented for use by prospective bidders for the construction contract. The principle construction work includes a 700 gpm cooling tower with its associated supports and equipment, pipelines from wells, electrical equipment, and all earthwork. (LCL)

  15. Research of heat releasing element of an active zone of gaseous nuclear reactor with pumped through nuclear fuel - uranium hexafluoride (UF6)

    International Nuclear Information System (INIS)

    Batyrbekov, G.; Batyrbekov, E.; Belyakova, E.; Kunakov, S.; Koltyshev, S.

    1996-01-01

    The purpose of the offered project is learning physics and substantiation of possibility of creation gaseous nuclear reactor with pumped through nuclear fuel-hexafluoride of uranium (Uf6).Main problems of this work are'. Determination of physic-chemical, spectral and optical properties of non-equilibrium nuclear - excited plasma of hexafluoride of uranium and its mixtures with other gases. Research of gas dynamics of laminar, non-mixing two-layer current of gases of hexafluoride of uranium and helium at availability and absence of internal energy release in hexafluoride of uranium with the purpose to determinate a possibility of isolation of hexafluoride of uranium from walls by inert helium. Creation and research of gaseous heat releasing element with pumped through fuel Uf6 in an active zone of research nuclear WWR-K reactor. Objects of a research: Non-equilibrium nuclear - excited plasma of hexafluoride of uranium and its mixtures with other gases. With use of specially created ampoules will come true in-reactor probe and spectral diagnostics of plasma. Calculations of kinetics with the account of main elementary processes proceeding in it, will be carried out. Two-layer non-mixed streams of hexafluoride of uranium and helium at availability and absence of internal energy release. Conditions of obtaining and characteristics of such streams will be investigated. Gaseous heat releasing element with pumped through fuel - Uf6 in an active zone of nuclear WWR-K reactor

  16. Long-term management of liquid high-level radioactive wastes stored at the Western New York Nuclear Service Center, West Valley. Final environmental impact statement

    International Nuclear Information System (INIS)

    1982-06-01

    The statement assesses and compares environmental implications of possible alternatives for long-term management of the liquid high-level radioactive wastes stored in underground tanks at the Western New York Nuclear Service Center in West Valley, New York. Four basic alternatives, as well as options within these alternatives, have been considered in the EIS: (1) onsite processing to a terminal waste form for shipment and disposal in a federal repository (the preferred alternative); (2) onsite conversion to a solid interim form for shipment to a federal waste facility for later processing to a terminal form and shipment and subsequent disposal in a federal repository; (3) mixing the liquid wastes with cement and other additives, pouring it back into the existing tanks, and leaving onsite; and (4) no action (continued storage of the wastes in liquid form in the underground tanks at West Valley). Mitigative measures for environmental impacts have been considered for all alternatives. No significant stresses on supplies or irreversible and irretrievable resources are anticipated, and no scarce resource would be required

  17. The Sodium Process Facility at Argonne National Laboratory-West

    International Nuclear Information System (INIS)

    Michelbacher, J.A.; Henslee, S.P.; McDermott, M.D.; Price, J.R.; Rosenberg, K.E.; Wells, P.B.

    1998-01-01

    Argonne National Laboratory-West (ANL-W) has approximately 680,000 liters of raw sodium stored in facilities on site. As mandated by the State of Idaho and the US Department of Energy (DOE), this sodium must be transformed into a stable condition for land disposal. To comply with this mandate, ANL-W designed and built the Sodium Process Facility (SPF) for the processing of this sodium into a dry, sodium carbonate powder. The major portion of the sodium stored at ANL-W is radioactively contaminated. The sodium will be processed in three separate and distinct campaigns: the 290,000 liters of Fermi-1 primary sodium, the 50,000 liters of the Experimental Breeder Reactor-II (EBR-II) secondary sodium, and the 330,000 liters of the EBR-II primary sodium. The Fermi-1 and the EBR-II secondary sodium contain only low-level of radiation, while the EBR-II primary sodium has radiation levels up to 0.5 mSv (50 mrem) per hour at 1 meter. The EBR-II primary sodium will be processed last, allowing the operating experience to be gained with the less radioactive sodium prior to reacting the most radioactive sodium. The sodium carbonate will be disposed of in 270 liter barrels, four to a pallet. These barrels are square in cross-section, allowing for maximum utilization of the space on a pallet, minimizing the required landfill space required for disposal

  18. The Sodium Process Facility at Argonne National Laboratory-West

    Energy Technology Data Exchange (ETDEWEB)

    Michelbacher, J.A.; Henslee, S.P. McDermott, M.D.; Price, J.R.; Rosenberg, K.E.; Wells, P.B.

    1998-07-01

    Argonne National Laboratory-West (ANL-W) has approximately 680,000 liters of raw sodium stored in facilities on site. As mandated by the State of Idaho and the US Department of Energy (DOE), this sodium must be transformed into a stable condition for land disposal. To comply with this mandate, ANL-W designed and built the Sodium Process Facility (SPF) for the processing of this sodium into a dry, sodium carbonate powder. The major portion of the sodium stored at ANL-W is radioactively contaminated. The sodium will be processed in three separate and distinct campaigns: the 290,000 liters of Fermi-1 primary sodium, the 50,000 liters of the Experimental Breeder Reactor-II (EBR-II) secondary sodium, and the 330,000 liters of the EBR-II primary sodium. The Fermi-1 and the EBR-II secondary sodium contain only low-level of radiation, while the EBR-II primary sodium has radiation levels up to 0.5 mSv (50 mrem) per hour at 1 meter. The EBR-II primary sodium will be processed last, allowing the operating experience to be gained with the less radioactive sodium prior to reacting the most radioactive sodium. The sodium carbonate will be disposed of in 270 liter barrels, four to a pallet. These barrels are square in cross-section, allowing for maximum utilization of the space on a pallet, minimizing the required landfill space required for disposal.

  19. Assessment of the feasibility of studying the potential health effects of the West Valley Solidification Project. Phase II

    International Nuclear Information System (INIS)

    Matanoski, G.M.

    The activities at West Valley involve potential exposure to ionizing radiation. The health effects from radiation are well known and the projected levels of exposure in this situation are so low as to pose no known health hazard in the community. In such a situation it is not reasonable to propose an expensive, comprehensive and physically invasive screening program for the public unless one could justify the benefits. This report describes a feasible population-based surveillance or disease monitoring system which could be implemented in the West Valley area in order to assess the relevance of any changes in incidence of disease which might be attributable to radiation. The proposed plan is both practical and inexpensive. It would anticipate any potential changes in the health status of the population and provide a means to objectively interpret such changes before major concerns develop

  20. Experimental transmission of West Nile Virus and Rift Valley Fever Virus by Culex pipiens from Lebanon.

    Directory of Open Access Journals (Sweden)

    Renée Zakhia

    2018-01-01

    Full Text Available West Nile virus (WNV and Rift Valley fever virus (RVFV are two emerging arboviruses transmitted by Culex pipiens species that includes two biotypes: pipiens and molestus. In Lebanon, human cases caused by WNV and RVFV have never been reported. However, the introduction of these viruses in the country is likely to occur through the migratory birds and animal trades. In this study, we evaluated the ability of Cx. pipiens, a predominant mosquito species in urban and rural regions in Lebanon, to transmit WNV and RVFV. Culex egg rafts were collected in the West Bekaa district, east of Lebanon and adult females of Cx. pipiens were experimentally infected with WNV and RVFV Clone 13 strain at titers of 1.6×108 and 1.33×107 plaque forming units (PFU/mL, respectively. We estimated viral infection, dissemination and transmission at 3, 7, 14 and 19 days post infection (dpi. Results showed that infection was higher for WNV than for RVFV from 3 dpi to 19 dpi. Viral dissemination and transmission started from 3 dpi for WNV; and only from 19 dpi for RVFV. Moreover, Cx. pipiens were able to excrete in saliva a higher number of viral particles of WNV (1028 ± 405 PFU/saliva at 19 dpi than RVFV (42 PFU/saliva at 19 dpi. Cx. pipiens from Lebanon are efficient experimental vectors of WNV and to a lower extent, RVFV. These findings should stimulate local authorities to establish an active entomological surveillance in addition to animal surveys for both viruses in the country.

  1. West Valley low-level radioactive waste site revisited: Microbiological analysis of leachates

    Energy Technology Data Exchange (ETDEWEB)

    Gillow, J.B.; Francis, A.J.

    1990-10-01

    The abundance and types of microorganisms in leachate samples from the West Valley low-level radioactive waste disposal site were enumerated. This study was undertaken in support of the study conducted by Ecology and Environment, Inc., to assess the extent of radioactive gas emissions from the site. Total aerobic and anaerobic bacteria were enumerated as colony forming units (CFU) by dilution agar plate technique, and denitrifiers, sulfate-reducers and methanogens by the most probable number technique (MPN). Of the three trenches 3, 9, and 11 sampled, trench 11 contained the most number of organisms in the leachate. Concentrations of carbon-14 and tritium were highest in trench 11 leachate. Populations of aerobes and anaerobes in trench 9 leachate were one order of magnitude less than in trench 11 leachate while the methanogens were three orders of magnitude greater than in trench 11 leachate. The methane content from trench 9 was high due to the presence of a large number of methanogens; the gas in this trench also contained the most radioactivity. Trench 3 leachate contained the least number of microorganisms. Comparison of microbial populations in leachates sampled from trenches 3 and 9 during October 1978 and 1989 showed differences in the total number of microbial types. Variations in populations of the different types of organisms in the leachate reflect the changing nutrient conditions in the trenches. 14 refs., 3 figs., 4 tabs.

  2. Selection of the treatment method for the West Valley alkaline supernatant

    International Nuclear Information System (INIS)

    Carl, D.E.; Leonard, I.M.

    1987-02-01

    As part of the West Valley Demonstration Project (WVDP), th PUREX supernatant stored in Tank 8d-2 will be partially decontaminated before encapsulation in the final glass form. This report discusses selection of a method for removing Cs-137, the major radioactive ion in the supernatant. Methods considered were: (1) electrodialysis; (2) hyperfiltration; (3) precipitation with ferrocyanide, NaTPB, or PTA; (4) organic ion exchange using Cs-100 or a biologically derived media; (5) chelation using DeVoe/Holbein compostions; and (6) inorganic ion exchange using Durasil, natural zeolities, IE-95 or IE-96 media. Several different methods of using inorganic ion exchange media were also reviewed including (1) four columns with elution, and (2) two, three, or four columns without elution. After the careful evaluation of experimental data with all process constraints taken into account, the inorganic exchange media IE-96 (Linde Ionsiv IE-96 synthetic zeolite) was chosen for WVDP cesium recovery. IE-96 was chosen for the following reasons: high sorption rate, a decontamination factor (DF) over 1000, excellent exchange capacity at WVDP conditions, compatability with the glass formers used for borosilicate glass in direct melter feed applications, and a history of successful application in radio chemical seperation for waste streams. 34 refs., 29 figs., 27 tabs

  3. TARZAN: A REMOTE TOOL DEPLOYMENT SYSTEM FOR THE WEST VALLEY DEVELOPMENT PROJECT

    International Nuclear Information System (INIS)

    Thompson, Bruce R.; Veri, James

    1999-01-01

    RedZone Robotics, Inc. undertook a development project to build Tarzan, a Remote Tool Delivery system to work inside nuclear waste storage tanks 8D-1 and 8D-2 at the West Valley Demonstration Project (WVDP). The removal of waste deposits from large storage tanks poses significant challenges during tank operations and closure. Limited access, the presence of chemical, radiological, and /or explosive hazards, and the need to deliver retrieval equipment to all regions of the tank exceed the capabilities of most conventional methods and equipment. Remotely operated devices for mobilizing and retrieving waste materials are needed. Some recent developments have been made in this area. However, none of these developments completely and cost-effectively address tanks that are congested with internal structures (e.g., support columns, cooling coils, fixed piping, etc.). The Tarzan system consists of the following parts: Locomotor which is deployed in the tank for inspection and cleanup; Hydraulic power unit providing system power for the locomotor and deployment unit; and Control system providing the man machine interface to control, coordinate and monitor the system. This document presents the final report on the Tarzan project

  4. Characterization of the Process Mechanical Cell at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Drake, John; Schneider, Ken; Choroser, Jeff; Hughes, Karl

    2003-01-01

    The West Valley Demonstration Project has initiated decontamination and dismantlement (D and D) of the most highly radioactive and contaminated cells in a former spent nuclear fuel reprocessing plant. The goals of the D and D project are to remove loose debris in the cells and estimate the residual radioactivity level of legacy plant equipment. To support accomplishment of these goals, a unique characterization approach was developed to gather the information to meet anticipated Waste Isolation Pilot Plant (WIPP) acceptance criteria for remote-handled transuranic waste, and to facilitate segregation and packaging operations. Implementation of the characterization approach included the development and use of innovative, remote technology for measuring gamma radiation within the hot cell. The technology was used to identify and quantify radiation from individual debris items in radiation fields up to 2,000 R/hr (20 sieverts/hr). Sampling and analysis of the debris were also performed via remote handling means. Significant challenges associated with characterizing the highly radioactive and highly contaminated hot cells were encountered. The innovative solutions for meeting these challenges are applicable throughout the Department of Energy Complex and help support the goal of targeting D and D efforts toward reducing risks to public health and the environment

  5. Development of derived investigation levels for use in internal dosimetry at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Johnson, P.

    1991-01-01

    The objective was to determine if the routine intemal dosimetry program at the West Valley Demonstration Project is capable of meeting the performance objective of 1 mSv annual effective dose equivalent due to internal contamination. With the use of the computer code REMedy the annual effective dose equivalent is calculated. Some of the radionuclides of concern result in an annual effective dose equivalent that exceeds the performance objective. Although the results exceed the performance objective, in all but two cases they do not exceed the US DOE regulatory limits. In these instances the Th-232 and Am-241 were determined to exceed the committed dose equivalent limit to their limiting tissue. In order to document the potential missed dose for regulatory compliance, Sr-90 is used as an indicator for Th-232. For Am-241 an investigation as to whether or not the minimum detectable amount can be lowered is performed. The derived investigation levels as a result of this project are 4.9E3 Bq/lung count for Co-60, 2.2E4 Bq/lung count for Cs-137, 1.9 Bq/1 for Sr-90 and for radionuclides other than Sr-90 any value greater than or equal to three standard deviations above their net count is considered to require further investigation

  6. West Valley low-level radioactive waste site revisited: Microbiological analysis of leachates

    International Nuclear Information System (INIS)

    Gillow, J.B.; Francis, A.J.

    1990-10-01

    The abundance and types of microorganisms in leachate samples from the West Valley low-level radioactive waste disposal site were enumerated. This study was undertaken in support of the study conducted by Ecology and Environment, Inc., to assess the extent of radioactive gas emissions from the site. Total aerobic and anaerobic bacteria were enumerated as colony forming units (CFU) by dilution agar plate technique, and denitrifiers, sulfate-reducers and methanogens by the most probable number technique (MPN). Of the three trenches 3, 9, and 11 sampled, trench 11 contained the most number of organisms in the leachate. Concentrations of carbon-14 and tritium were highest in trench 11 leachate. Populations of aerobes and anaerobes in trench 9 leachate were one order of magnitude less than in trench 11 leachate while the methanogens were three orders of magnitude greater than in trench 11 leachate. The methane content from trench 9 was high due to the presence of a large number of methanogens; the gas in this trench also contained the most radioactivity. Trench 3 leachate contained the least number of microorganisms. Comparison of microbial populations in leachates sampled from trenches 3 and 9 during October 1978 and 1989 showed differences in the total number of microbial types. Variations in populations of the different types of organisms in the leachate reflect the changing nutrient conditions in the trenches. 14 refs., 3 figs., 4 tabs

  7. Preconceptual design study for solidifying high-level waste: West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Hill, O.F.

    1981-04-01

    This report presents a preconceptual design study for processing radioactive high-level liquid waste presently stored in underground tanks at Western New York Nuclear Service Center (WNYNSC) near West Valley, New York, and for incorporating the radionculides in that waste into a solid. The high-level liquid waste accumulated from the operation of a chemical reprocessing plant by the Nuclear Fuel Services, Inc. from 1966 to 1972. The high-level liquid waste consists of approximately 560,000 gallons of alkaline waste from Purex process operations and 12,000 gallons of acidic (nitric acid) waste from one campaign of processing thoria fuels by a modified Thorex process (during this campaign thorium was left in the waste). The alkaline waste contains approximately 30 million curies and the acidic waste contains approximately 2.5 million curies. The reference process described in this report is concerned only with chemically processing the high-level liquid waste to remove radionuclides from the alkaline supernate and converting the radionuclide-containing nonsalt components in the waste into a borosilicate glass

  8. Hydrogeologic framework and occurrence, movement, and chemical characterization of groundwater in Dixie Valley, west-central Nevada

    Science.gov (United States)

    Huntington, Jena M.; Garcia, C. Amanda; Rosen, Michael R.

    2014-01-01

    Dixie Valley, a primarily undeveloped basin in west-central Nevada, is being considered for groundwater exportation. Proposed pumping would occur from the basin-fill aquifer. In response to proposed exportation, the U.S. Geological Survey, in cooperation with the Bureau of Reclamation and Churchill County, conducted a study to improve the understanding of groundwater resources in Dixie Valley. The objective of this report is to characterize the hydrogeologic framework, the occurrence and movement of groundwater, the general water quality of the basin-fill aquifer, and the potential mixing between basin-fill and geothermal aquifers in Dixie Valley. Various types of geologic, hydrologic, and geochemical data were compiled from previous studies and collected in support of this study. Hydrogeologic units in Dixie Valley were defined to characterize rocks and sediments with similar lithologies and hydraulic properties influencing groundwater flow. Hydraulic properties of the basin-fill deposits were characterized by transmissivity estimated from aquifer tests and specific-capacity tests. Groundwater-level measurements and hydrogeologic-unit data were combined to create a potentiometric surface map and to characterize groundwater occurrence and movement. Subsurface inflow from adjacent valleys into Dixie Valley through the basin-fill aquifer was evaluated using hydraulic gradients and Darcy flux computations. The chemical signature and groundwater quality of the Dixie Valley basin-fill aquifer, and potential mixing between basin-fill and geothermal aquifers, were evaluated using chemical data collected from wells and springs during the current study and from previous investigations. Dixie Valley is the terminus of the Dixie Valley flow system, which includes Pleasant, Jersey, Fairview, Stingaree, Cowkick, and Eastgate Valleys. The freshwater aquifer in the study area is composed of unconsolidated basin-fill deposits of Quaternary age. The basin-fill hydrogeologic unit

  9. Analysis of risk and dose when using thermal protection on non-fissile and fissile-excepted UF6 48-inch cylinder packages

    International Nuclear Information System (INIS)

    Chambers, D.B.; Lowe, L.M.; Elizabeth Darrough, M.; Jones, R.H.

    2004-01-01

    An industry consortium of owners of large (i.e., the 48-inch or 48X and 48Y) cylinders commissioned an independent study to evaluate the safety of using thermal protective covers on the cylinders and the likelihood that the cylinders would experience the regulations' hypothetical thermal accident. The study examined the demonstrable risks of the protective covers, i.e., increased dose to workers and the potential for accidents associated with the extra handling, vs. the theoretical risk of the UF 6 cylinders' encountering the hypothetical fire, to evaluate the appropriateness of using the thermal protective covers

  10. A Mock UF6 Feed and Withdrawal System for Testing Safeguards Monitoring Systems and Strategies Intended for Nuclear Fuel Enrichment and Processing Plants

    International Nuclear Information System (INIS)

    Krichinsky, Alan M.; Bates, Bruce E.; Chesser, Joel B.; Koo, Sinsze; Whitaker, J. Michael

    2009-01-01

    This report describes an engineering-scale, mock UF6 feed and withdrawal (F and W) system, its operation, and its intended uses. This system has been assembled to provide a test bed for evaluating and demonstrating new methodologies that can be used in remote, unattended, continuous monitoring of nuclear material process operations. These measures are being investigated to provide independent inspectors improved assurance that operations are being conducted within declared parameters, and to increase the overall effectiveness of safeguarding nuclear material. Testing applicable technologies on a mock F and W system, which uses water as a surrogate for UF6, enables thorough and cost-effective investigation of hardware, software, and operational strategies before their direct installation in an industrial nuclear material processing environment. Electronic scales used for continuous load-cell monitoring also are described as part of the basic mock F and W system description. Continuous monitoring components on the mock F and W system are linked to a data aggregation computer by a local network, which also is depicted. Data collection and storage systems are described only briefly in this report. The mock UF 6 F and W system is economical to operate. It uses a simple process involving only a surge tank between feed tanks and product and withdrawal (or waste) tanks. The system uses water as the transfer fluid, thereby avoiding the use of hazardous UF 6 . The system is not tethered to an operating industrial process involving nuclear materials, thereby allowing scenarios (e.g., material diversion) that cannot be conducted otherwise. These features facilitate conducting experiments that yield meaningful results with a minimum of expenditure and quick turnaround time. Technologies demonstrated on the engineering-scale system lead to field trials (described briefly in this report) for determining implementation issues and performance of the monitoring technologies under

  11. Occupational Safety and Health Program at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    L. M. Calderon

    1999-01-01

    The West Valley Nuclear Services Co. LLC (WVNS) is committed to provide a safe, clean, working environment for employees, and to implement U.S. Department of Energy (DOE) requirements affecting worker safety. The West Valley Demonstration Project (WVDP) Occupational Safety and Health Program is designed to protect the safety, health, and well-being of WVDP employees by identifying, evaluating, and controlling biological, chemical, and physical hazards in the work place. Hazards are controlled within the requirements set forth in the reference section at the end of this report. It is the intent of the WVDP Occupational Safety and Health Program to assure that each employee is provided with a safe and healthy work environment. This report shows the logical path toward ensuring employee safety in planning work at the WVDP. In general, planning work to be performed safely includes: combining requirements from specific programs such as occupational safety, industrial hygiene, radiological control, nuclear safety, fire safety, environmental protection, etc.; including WVDP employees in the safety decision-making processes; pre-planning using safety support re-sources; and integrating the safety processes into the work instructions. Safety management principles help to define the path forward for the WVDP Occupational Safety and Health Program. Roles, responsibilities, and authority of personnel stem from these ideals. WVNS and its subcontractors are guided by the following fundamental safety management principles: ''Protection of the environment, workers, and the public is the highest priority. The safety and well-being of our employees, the public, and the environment must never be compromised in the aggressive pursuit of results and accomplishment of work product. A graded approach to environment, safety, and health in design, construction, operation, maintenance, and deactivation is incorporated to ensure the protection of the workers, the public, and the environment

  12. Development of analytical cell support for vitrification at the West Valley Demonstration Project. Topical report

    Energy Technology Data Exchange (ETDEWEB)

    Barber, F.H.; Borek, T.T.; Christopher, J.Z. [and others

    1997-12-01

    Analytical and Process Chemistry (A&PC) support is essential to the high-level waste vitrification campaign at the West Valley Demonstration Project (WVDP). A&PC characterizes the waste, providing information necessary to formulate the recipe for the target radioactive glass product. High-level waste (HLW) samples are prepared and analyzed in the analytical cells (ACs) and Sample Storage Cell (SSC) on the third floor of the main plant. The high levels of radioactivity in the samples require handling them in the shielded cells with remote manipulators. The analytical hot cells and third floor laboratories were refurbished to ensure optimal uninterrupted operation during the vitrification campaign. New and modified instrumentation, tools, sample preparation and analysis techniques, and equipment and training were required for A&PC to support vitrification. Analytical Cell Mockup Units (ACMUs) were designed to facilitate method development, scientist and technician training, and planning for analytical process flow. The ACMUs were fabricated and installed to simulate the analytical cell environment and dimensions. New techniques, equipment, and tools could be evaluated m in the ACMUs without the consequences of generating or handling radioactive waste. Tools were fabricated, handling and disposal of wastes was addressed, and spatial arrangements for equipment were refined. As a result of the work at the ACMUs the remote preparation and analysis methods and the equipment and tools were ready for installation into the ACs and SSC m in July 1995. Before use m in the hot cells, all remote methods had been validated and four to eight technicians were trained on each. Fine tuning of the procedures has been ongoing at the ACs based on input from A&PC technicians. Working at the ACs presents greater challenges than had development at the ACMUs. The ACMU work and further refinements m in the ACs have resulted m in a reduction m in analysis turnaround time (TAT).

  13. Development of analytical cell support for vitrification at the West Valley Demonstration Project. Topical report

    International Nuclear Information System (INIS)

    Barber, F.H.; Borek, T.T.; Christopher, J.Z.

    1997-12-01

    Analytical and Process Chemistry (A ampersand PC) support is essential to the high-level waste vitrification campaign at the West Valley Demonstration Project (WVDP). A ampersand PC characterizes the waste, providing information necessary to formulate the recipe for the target radioactive glass product. High-level waste (HLW) samples are prepared and analyzed in the analytical cells (ACs) and Sample Storage Cell (SSC) on the third floor of the main plant. The high levels of radioactivity in the samples require handling them in the shielded cells with remote manipulators. The analytical hot cells and third floor laboratories were refurbished to ensure optimal uninterrupted operation during the vitrification campaign. New and modified instrumentation, tools, sample preparation and analysis techniques, and equipment and training were required for A ampersand PC to support vitrification. Analytical Cell Mockup Units (ACMUs) were designed to facilitate method development, scientist and technician training, and planning for analytical process flow. The ACMUs were fabricated and installed to simulate the analytical cell environment and dimensions. New techniques, equipment, and tools could be evaluated m in the ACMUs without the consequences of generating or handling radioactive waste. Tools were fabricated, handling and disposal of wastes was addressed, and spatial arrangements for equipment were refined. As a result of the work at the ACMUs the remote preparation and analysis methods and the equipment and tools were ready for installation into the ACs and SSC m in July 1995. Before use m in the hot cells, all remote methods had been validated and four to eight technicians were trained on each. Fine tuning of the procedures has been ongoing at the ACs based on input from A ampersand PC technicians. Working at the ACs presents greater challenges than had development at the ACMUs. The ACMU work and further refinements m in the ACs have resulted m in a reduction m in

  14. Phase 1 Characterization sampling and analysis plan West Valley demonstration project.

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, R. L. (Environmental Science Division)

    2011-06-30

    The Phase 1 Characterization Sampling and Analysis Plan (CSAP) provides details about environmental data collection that will be taking place to support Phase 1 decommissioning activities described in the Phase 1 Decommissioning Plan for the West Valley Demonstration Project, Revision 2 (Phase I DP; DOE 2009). The four primary purposes of CSAP data collection are: (1) pre-design data collection, (2) remedial support, (3) post-remediation status documentation, and (4) Phase 2 decision-making support. Data collection to support these four main objectives is organized into two distinct data collection efforts. The first is data collection that will take place prior to the initiation of significant Phase 1 decommissioning activities (e.g., the Waste Management Area [WMA] 1 and WMA 2 excavations). The second is data collection that will occur during and immediately after environmental remediation in support of remediation activities. Both data collection efforts have a set of well-defined objectives that encompass the data needs of the four main CSAP data collection purposes detailed in the CSAP. The main body of the CSAP describes the overall data collection strategies that will be used to satisfy data collection objectives. The details of pre-remediation data collection are organized by WMA. The CSAP contains an appendix for each WMA that describes the details of WMA-specific pre-remediation data collection activities. The CSAP is intended to expand upon the data collection requirements identified in the Phase 1 Decommissioning Plan. The CSAP is intended to tightly integrate with the Phase 1 Final Status Survey Plan (FSSP). Data collection described by the CSAP is consistent with the FSSP where appropriate and to the extent possible.

  15. The sodium process facility at Argonne National Laboratory - West

    International Nuclear Information System (INIS)

    Michelbacher, J.A.; Henslee, S.P.; McDermott, M.D.; Price, J.R.; Rosenberg, K.E.; Wells, P.B.

    1997-01-01

    Argonne National Laboratory - West (ANL-W) has approximately 680,000 liters (180,000 gallons) of raw sodium stored in facilities on site. As mandated by the State of Idaho and the United States Department of Energy (DOE), this sodium must be transformed into a stable condition for land disposal. To comply with this mandate, ANL-W designed and built the Sodium Process Facility (SPF) for the processing of this sodium into a dry, sodium carbonate powder. The major portion of the sodium stored at ANL-W is radioactively contaminated. The SPF was designed to react elemental sodium to sodium carbonate through two-stages involving caustic process and carbonate process steps. The sodium is first reacted to sodium hydroxide in the caustic process step. The caustic process step involves the injection of sodium into a nickel reaction vessel filled with a 50 wt% solution of sodium hydroxide. Water is also injected, controlling the boiling point of the solution. In the carbonate process, the sodium hydroxide is reacted with carbon dioxide to form sodium carbonate. This dry powder, similar in consistency to baking soda, is a waste form acceptable for burial in the State of Idaho as a non-hazardous, radioactive waste. The caustic process was originally designed and built in the 1980s for reacting the 290,000 liters (77,000 gallons) of primary sodium from the Fermi-1 Reactor to sodium hydroxide. The hydroxide was slated to be used to neutralize acid products from the PUREX process at the Hanford site. However, changes in the DOE mission precluded the need for hydroxide and the caustic process was never operated. With the shutdown of the Experimental Breeder Reactor-II (EBR-II), the necessity for a facility to react sodium was identified. In order to comply with Resource Conservation and Recovery Act (RCRA) requirements, the sodium had to be converted into a waste form acceptable for disposal in a Sub-Title D low-level radioactive waste disposal facility. Sodium hydroxide is a RCRA

  16. Late Quaternary pollen records from the Lower Cobb Valley and adjacent areas, north-west Nelson, New Zealand

    International Nuclear Information System (INIS)

    Shulmeister, J.; McLea, W.L.; Singer, C.; McKay, R.M.; Hosie, C.

    2003-01-01

    Ten pollen records from the Cobb Valley and adjacent areas in North-West Nelson are described. Collectively they provide a vegetation record extending from the Last Glacial Maximum to the present day. During the Last Glacial Maximum the uplands of North-West Nelson were glaciated. By about 17,000 radiocarbon years BP ice had retreated some distance up the Cobb River Valley and a podocarp heath and tussockland vegetation covered non-glaciated areas. By 14,000 radiocarbon years BP, the valley floor and adjacent lower ridges were occupied by montane podocarp forest dominated by Phyllocladus and Halocarpus. Beech forest expanded into some sites as early as 13,000 yr BP but the modern beech cover was not established until the Holocene. Forest cover has fluctuated in response to disturbance over the Holocene, but the most significant recent change, which is related to clearing for pastoralism in the last two centuries, has had surprisingly little impact on the pollen records. (author). 40 refs., 11 figs., 1 tab

  17. The geology and mineral deposits of Tantalite Valley, Warmbad district, South West Africa

    International Nuclear Information System (INIS)

    Von Backstroem, J.W.

    1976-04-01

    The Tantalite Valley Complex, a poorly mineralised (Cu and Ni sulphides) body of roughly concentric peridotite-gabbroid intrusions was emplaced along a major zone of dislocation (the Tantallite Valley Lineament) into a metasedimentary sequence of migmatites and gneisses which, together with the complex, have experienced a complex metamorphic and tectonic history. A number of large mineralised pegmatites (producers of minerals of Nb, Ta, Bi, Li and Be over the past two decades), was intruded about 1000 Ma ago [af

  18. Thermal reactions of uranium metal, UO 2, U 3O 8, UF 4, and UO 2F 2 with NF 3 to produce UF 6

    Science.gov (United States)

    McNamara, Bruce; Scheele, Randall; Kozelisky, Anne; Edwards, Matthew

    2009-11-01

    This paper demonstrates that NF 3 fluorinates uranium metal, UO 2, UF 4, UO 3, U 3O 8, and UO 2F 2·2H 2O to produce the volatile UF 6 at temperatures between 100 and 550 °C. Thermogravimetric and differential thermal analysis reaction profiles are described that reflect changes in the uranium fluorination/oxidation state, physiochemical effects, and instances of discrete chemical speciation. Large differences in the onset temperatures for each system investigated implicate changes in mode of the NF 3 gas-solid surface interaction. These studies also demonstrate that NF 3 is a potential replacement fluorinating agent in the existing nuclear fuel cycle and in actinide volatility reprocessing.

  19. Cost-effectiveness of safety measures to reduce public risk associated with the transportation of UF6 by truck and trains

    International Nuclear Information System (INIS)

    Hubert, Philippe; Pages, Pierre

    1989-01-01

    The present case study deals with the problem of uranium hexafluoride transportation by truck and train. It consists of a probabilistic risk assessment of the potential hazards to the public that can arise from the traffic that will take place in France in 1990. The specificity of UF 6 is that it presents both chemical and radiological hazards. But, whatever the transported material, road traffic entails a risk of its own. Thus three kinds of risks are assessed for natural, depleted and enriched uranium hexafluoride. These assessments are the basis of a cost-effectiveness analysis which deals with such safety measures as using a protective overpack, avoiding populated areas and escorting the trucks

  20. Crystal field effect in the uranium compounds - model calculations for CsUF6, Cs2UCl6 and UCl4

    International Nuclear Information System (INIS)

    Gajek, Z.; Mulak, J.

    1987-01-01

    A practical crystal field model allowing one to estimate the crystal field parameters from first principles is presented and applied to the actinide compounds. The model results directly from the renormalization (and reduction) procedure of the true Schroedinger equation for an effective Hamiltonian acting on the 5f spin-orbitals only. In practice this approach becomes convergent with the ab initio model of Newman. Three ionic uranium compounds: CsUF 6 , Cs 2 UCl 6 and UCl 4 have served as examples of the application. The results obtained, particularly for the first two compounds, are in good agreement with the experimental data. The contributions of different mechanisms responsible for the crystal field effect are discussed. (author)

  1. Role of Facilities Available and Un-Available in Attracting of Tourist in Swat Valley Pakistan

    Directory of Open Access Journals (Sweden)

    Akbar Jalaluddin

    2017-01-01

    Full Text Available Natural landscape is an important resource for mountainous regions and play crucial role in tourism development. Tourism play a key role in economic development of a country. Developing tourist areas is the key to meet the expectations of mountain inhabitants, tourists, and the general public outside of mountainous areas. In order to know tourist perception, problems, and role of landscape & horticulture plants in the field of tourism. A research study entitled “Role of facilities available and un-available in attracting of tourist in swat valley Pakistan “The data was collected from the respondents through a questionnaire survey and analyzed using percentages, frequencies and Chi-square test (where applicable. The analyzed data revealed that most of the respondent (55 % considered natural green environment as a reason for their visit and 67 % respondents wanted to visit with their friends and were satisfied with the tourist area, respectively. Most of the respondent (39 % observed throwing of surplus food as major waste materials which turned the beautiful green environment into unattractive environment. Most of the visitors (52 % dislike un-cleanliness of the locality, 74% respondents felt ill effect due to deforestation.53 % tourist disagree with the current maintenance of the locality by tourism department. The most missed facilities were non availability of dustbins and children playing areas. 75 % respondents agreed with the fact that most of the people (local inhabitants as well as tourist were unaware with regard to maintenance activities of the area 15.7 % respondent agreed that road system should be improved to access most of the greenery in the locality, respectively to aware local people and tourist regarding maintenance of the locality will improve tourism in Swat valley. The studies need to be develop for the improvement of existing as well as artificial landscape of the tourist area (Kalam and Malamjabba of Swat valley.

  2. Decontamination of the product handling area at the West Valley Demonstration Project: Final topical report for period July 1985 to February 1986

    International Nuclear Information System (INIS)

    Phillips, E.C.

    1986-06-01

    The purpose of this report is to describe the decontamination and decommissioning (D and D) preparations of an existing facility at the West Valley Demonstration Project (WVDP), the Product Handling Area (PHA), to be part of a Liquid Waste Treatment System (LWTS) in conjunction with the Cement Solidification System (CSS). Two interconnected facilities, the Uranium Product Cell (UPC) and the Uranium Loadout Area (ULO), form the PHA. Both of these facilities contain large tanks. Both of the tanks in the UPC are suitable for use as components of the LWTS. In addition, the UPC is the only existing means of access to the bottom of the Product Purification Cell (PPC) in which some of the equipment for the LWTS will be installed. Consequently, this report describes the decontamination of the PHA from a radioactively contaminated environment to one which may be entered in street clothes. Of the two facilities of the PHA, the UPC was the more highly contaminated prior to decontamination. Decontamination of the UPC has been completed leaving most of the surfaces in the facility smearably clean. Decontamination of the UPC consisted of washing all surfaces, draining the floor sump, removing unneeded piping, installing a back flow filter system, painting all surfaces, installing rubber matting on the floor and placing new stainless steel covering on the UPC ledge. Decontamination operations in the ULO have been completed and were similar to those in the UPC consisting of decontaminating by hand wipedown, removing contamination fixed in paint, and applying new paint. In addition, two pumps and a concrete pump niche were removed. Prior to decontamination, surface contamination was present in the ULO. After decontamination, most of the surfaces in the ULO were clean of smearable contamination. D and D Operations were initiated in the PHA in July 1985 and completed in February 1986. 13 figs., 9 tabs

  3. Decontamination of the Warm Aisles at the West Valley Demonstration Project. Final topical report, January 1985-February 1986

    International Nuclear Information System (INIS)

    Allen, J.C.

    1986-06-01

    The West Valley Demonstration Project is a DOE project to solidify in a glass form the 2,120 m 3 (560,000 gallons) of liquid high-level waste stored in two underground steel tanks at the site of the world's first commercial nuclear fuel reprocessing plant, West Valley, New York. One project objective is to utilize as much of the existing plant areas as practical for the installation of solidification support systems. Previously, Extraction Cell Three (XC3) and the Product Purification Cell (PPC) had been chosen as the location of the Liquid Waste Treatment System (LWTS). Subsequently, it was decided that areas of the Upper Warm Aisle (UWA) and the Lower Warm Aisle (LWA) which are located adjacent to the south wall of XC3 and PPC would also be needed for the installation of LWTS equipment. Shielded concrete niches which contained pumps and valve manifolds are located in the warm aisles. One pump niche and one valve manifold niche in the UWA and one pump niche in the LWA were identified as needed for the LWTS. Also, it was necessary to remove some equipment which was located outside the niches. Subsequently, decontamination plans were made and carried out to prepare these areas for modification and installation activities. Predecontamination survey activities began in January 1985, and decontamination operations were completed in February 1986. Decontamination efforts, results, and lessons learned are reported

  4. Design and operating features of the high-level waste vitrification system for the West Valley demonstration project

    International Nuclear Information System (INIS)

    Siemens, D.H.; Beary, M.M.; Barnes, S.M.; Berger, D.N.; Brouns, R.A.; Chapman, C.C.; Jones, R.M.; Peters, R.D.; Peterson, M.E.

    1986-03-01

    A liquid-fed joule-heated ceramic melter system is the reference process for immobilization of the high-level liquid waste in the US and several foreign countries. This system has been under development for over ten years at Pacific Northwest Laboratory and other national laboratories operated for the US Department of Energy. Pacific Northwest Laboratory contributed to this research through its Nuclear Waste Treatment Program and used applicable data to design and test melters and related systems using remote handling of simulated radioactive wastes. This report describes the equipment designed in support of the high-level waste vitrification program at West Valley, New York. Pacific Northwest Laboratory worked closely with West Valley Nuclear Services Company to design a liquid-fed ceramic melter, a liquid waste preparation and feed tank and pump, an off-gas treatment scrubber, and an enclosed turntable for positioning the waste canisters. Details of these designs are presented including the rationale for the design features and the alternatives considered

  5. Aquatic habitats of Canaan Valley, West Virginia: Diversity and environmental threats

    Science.gov (United States)

    Snyder, C.D.; Young, J.A.; Stout, B. M.

    2006-01-01

    We conducted surveys of aquatic habitats during the spring and summer of 1995 in Canaan Valley, WV, to describe the diversity of aquatic habitats in the valley and identify issues that may threaten the viability of aquatic species. We assessed physical habitat and water chemistry of 126 ponds and 82 stream sites, and related habitat characteristics to landscape variables such as geology and terrain. Based on our analyses, we found two issues likely to affect the viability of aquatic populations in the valley. The first issue was acid rain and the extent to which it potentially limits the distribution of aquatic and semi-aquatic species, particularly in headwater portions of the watershed. We estimate that nearly 46%, or 56 kilometers of stream, had pH levels that would not support survival and reproduction of Salvelinuw fontinalis (brook trout), one of the most acid-tolerant fishes in the eastern US. The second issue was the influence of Castor canadensis (beaver) activity. In the Canaan Valley State Park portion of the valley, beaver have transformed 4.7 kilometers of stream (approximately 17% of the total) to pond habitat through their dam building. This has resulted in an increase in pond habitat, a decrease in stream habitat, and a fragmented stream network (i.e., beaver ponds dispersed among stream reaches). In addition, beaver have eliminated an undetermined amount of forested riparian area through their foraging activities. Depending on the perspective, beaver-mediated changes can be viewed as positive or negative. Increases in pond habitat may increase habitat heterogeneity with consequent increases in biological diversity. In contrast, flooding associated with beaver activity may eliminate lowland wetlands and associated species, create barriers to fish dispersal, and possibly contribute to low dissolved oxygen levels in the Blackwater River. We recommend that future management strategies for the wildlife refuge be viewed in the context of these two issues

  6. Comparison of the rotary calciner-metallic melter and the slurry-fed ceramic melter technologies for vitrifying West Valley high-level wastes

    International Nuclear Information System (INIS)

    Chapman, C.C.

    1983-01-01

    Two processes which are believed applicable and available for vitrification of West Valley's high-level (HLW) wastes were technically evaluated and compared. The rotary calciner-metallic melter (AVH) and the slurry-fed ceramic melter (SFCM) were evaluated under the following general categories: process flow sheet, remote operability, safety and environmental considerations, and estimated cost and schedules

  7. Geologic and hydrologic research at the Western New York Nuclear Service Center, West Valley, New York. Final report, August 1982-December 1983

    International Nuclear Information System (INIS)

    Albanese, J.R.; Anderson, S.L.; Fakundiny, R.H.; Potter, S.M.; Rogers, W.B.; Whitbeck, L.F.; LaFleur, R.G.; Boothroyd, J.C.; Timson, B.S.

    1984-06-01

    This report is the last in a series by the New York State Geological Survey on studies funded by the US Nuclear Regulatory Commission. The report covers five important aspects of the geology and hydrology of the Western New York Nuclear Service Center, near West Valley, New York: geomorphology, stratigraphy, sedimentology, surface water, and radionuclide analyses. We reviewed past research on these subjects and present new data obtained in the final phase of NYSGS research at the site. Also presented are up-to-date summaries of the present knowledge of geomorphology and stratigraphy. The report contains a significant bibliography of previous West Valley studies. Appendices include a report on the Fall 1983 Drilling Project and the procedures used, history and prognosis of Cattaraugus Creek and tributaries down cutting, and bar modification and landslide processes of Buttermilk Valley. 100 references, 7 figures, 7 tables

  8. Emerging vector-borne diseases in dromedaries in Tunisia: West Nile, bluetongue, epizootic haemorrhagic disease and Rift Valley fever.

    Science.gov (United States)

    Hassine, Thameur B; Amdouni, Jihane; Monaco, Federica; Savini, Giovanni; Sghaier, Soufien; Selimen, Imed B; Chandoul, Walid; Hamida, Khaled B; Hammami, Salah

    2017-03-31

    A total of 118 sera were collected during 2016 from two groups of dromedaries from Kebili and Medenine governorates in the south of Tunisia. The aim of this study was to provide the first serological investigation of four emerging vector-borne diseases in two groups of dromedaries in Tunisia. Sera were tested by ELISA and serum neutralisation test to identify West Nile virus (WNV), bluetongue virus (BTV), epizootic haemorrhagic disease virus (EHDV) and Rift Valley fever virus (RVFV). In the first group, the seroprevalence for BTV was 4.6%, while in the second group, it was 25.8% for WNV and 9.7% for BTV. Only serotype 1 was detected for BTV in the two groups. No evidence for circulation of RVF and EHD viruses was revealed. Results indicated that dromedaries can be infected with BTV and WNV, suggesting that this species might play a significant role in the epizootiology of these viral diseases in Tunisia and neighbouring countries.

  9. Culex pipiens, an experimental efficient vector of West Nile and Rift Valley fever viruses in the Maghreb region.

    Directory of Open Access Journals (Sweden)

    Fadila Amraoui

    Full Text Available West Nile fever (WNF and Rift Valley fever (RVF are emerging diseases causing epidemics outside their natural range of distribution. West Nile virus (WNV circulates widely and harmlessly in the old world among birds as amplifying hosts, and horses and humans as accidental dead-end hosts. Rift Valley fever virus (RVFV re-emerges periodically in Africa causing massive outbreaks. In the Maghreb, eco-climatic and entomologic conditions are favourable for WNV and RVFV emergence. Both viruses are transmitted by mosquitoes belonging to the Culex pipiens complex. We evaluated the ability of different populations of Cx. pipiens from North Africa to transmit WNV and the avirulent RVFV Clone 13 strain. Mosquitoes collected in Algeria, Morocco, and Tunisia during the summer 2010 were experimentally infected with WNV and RVFV Clone 13 strain at titers of 10(7.8 and 10(8.5 plaque forming units/mL, respectively. Disseminated infection and transmission rates were estimated 14-21 days following the exposure to the infectious blood-meal. We show that 14 days after exposure to WNV, all mosquito st developed a high disseminated infection and were able to excrete infectious saliva. However, only 69.2% of mosquito strains developed a disseminated infection with RVFV Clone 13 strain, and among them, 77.8% were able to deliver virus through saliva. Thus, Cx. pipiens from the Maghreb are efficient experimental vectors to transmit WNV and to a lesser extent, RVFV Clone 13 strain. The epidemiologic importance of our findings should be considered in the light of other parameters related to mosquito ecology and biology.

  10. Decontamination and decommissioning of the extraction chemical room at the West Valley Demonstration Project. Final topical report, December 1982-April 1984

    International Nuclear Information System (INIS)

    Phillips, E.C.

    1985-12-01

    The purpose of this report is to describe the preparation of a facility for use in decontaminating and decommissioning (D and D) extraction cells at the West Valley Demonstration Project (WVDP). In order to prepare such a facility, it was necessary to decontaminate, decommission and equip the Extraction Chemical Room (XCR) at the WVDP. This report describes the D and D of the XCR from a radioactively contaminated condition to an essentially shirt sleeve environment. Also included is a description of the changes made to the XCR for use in the D and D of the extraction cells which are located beneath the floor of the XCR. In the XCR prior to D and D, radiological surveys indicated a maximum radiation field of 5 mrad/hr, due to sources internal to the room, and 20,000 dpm beta/100 cm 2 surface contamination. A radiation source external to the XCR caused a hot spot with a 9 mrad/hr exposure rate inside the XCR. The D and D of the XCR, located on the fifth floor elevation 48.8 m of the reprocessing plant at the WVDP, has been completed. D and D operations included removal of piping, tanks, supports, and equipment to provide a clean work area of about 278.7 m 2 and 5.2 m high. Subsequent to the removal of piping and equipment, a new floor was installed in part of the room and equipment for use in the D and D of the extraction cells was added. The equipment included a large containment tent over the extraction cell hatches, a jib crane, two gantries, a monorail crane, an air transporter, and a temporary ventilation system. D and D operations in the XCR were initiated in December 1982 and the completed facility was available for use in February 1984

  11. Analysis of Hanford-based Options for Sustainable DOE Facilities on the West Coast

    Energy Technology Data Exchange (ETDEWEB)

    Warwick, William M.

    2012-06-30

    Large-scale conventional energy projects result in lower costs of energy (COE). This is true for most renewable energy projects as well. The Office of Science is interested in its facilities meeting the renewable energy mandates set by Congress and the Administration. Those facilities on the west coast include a cluster in the Bay Area of California and at Hanford in central Washington State. Land constraints at the California facilities do not permit large scale projects. The Hanford Reservation has land and solar insolation available for a large scale solar project as well as access to a regional transmission system that can provide power to facilities in California. The premise of this study is that a large-scale solar project at Hanford may be able to provide renewable energy sufficient to meet the needs of select Office of Science facilities on the west coast at a COE that is competitive with costs in California despite the lower solar insolation values at Hanford. The study concludes that although the cost of solar projects continues to decline, estimated costs for a large-scale project at Hanford are still not competitive with avoided power costs for Office of Science facilities on the west coast. Further, although it is possible to transmit power from a solar project at Hanford to California facilities, the costs of doing so add additional costs. Consequently, development of a large- scale solar project at Hanford to meet the renewable goals of Office of Science facilities on the west coast is currently uneconomic. This may change as solar costs decrease and California-based facilities face increasing costs for conventional and renewable energy produced in the state. PNNL should monitor those cost trends.

  12. Sediment Thickness and a WEST-EAST Geologic Cross Section in the Caracas Valley

    OpenAIRE

    KANTAK, PETER; SCHMITZ, MICHAEL; AUDEMARD, FRANCK

    2005-01-01

    Caracas is located at the Caribbean - South America plate boundary zone, with an associated strike slip fault system, which accommodates the relative movement of both plates and is responsible for the seismic hazard in the region. The damage pattern of the 1967 Caracas earthquake emphasized the existence of important site effects due to the sedimentary basin fill of the Caracas valley. A revised map of the sedimentary thickness was developed during this study, based on drill holes (mostly fro...

  13. Case study and lessons learned from the ammonium nitrate explosion at the West Fertilizer facility

    Energy Technology Data Exchange (ETDEWEB)

    Laboureur, Delphine M.; Han, Zhe; Harding, Brian Z.; Pineda, Alba; Pittman, William C.; Rosas, Camilo; Jiang, Jiaojun; Mannan, M. Sam, E-mail: mannan@tamu.edu

    2016-05-05

    Highlights: • In-depth technical analysis of the West, Texas ammonium nitrate incident. • Regulatory analysis for compliance with federal, state and local regulations. • Facility siting and land use planning implications. • Need for local coordination of risk information and emergency planning. - Abstract: In West, Texas on April 17, 2013, a chemical storage and distribution facility caught fire followed by the explosion of around 30 tons of ammonium nitrate while the emergency responders were trying to extinguish the fire, leading to 15 fatalities and numerous buildings, businesses and homes destroyed or damaged. This incident resulted in devastating consequences for the community around the facility, and shed light on a need to improve the safety management of local small businesses similar to the West facility. As no official report on the findings of the incident has been released yet, this article first investigates the root causes of the incident, and presents a simplified consequence analysis. The article reviews the regulations applicable to this type of facility and recommended emergency response procedures to identify gaps between what happened in West and the current regulations, and discusses how the current regulations could be modified to prevent or minimize future losses. Finally, the federal response that followed the incident until the publication of this paper is summarized.

  14. Case study and lessons learned from the ammonium nitrate explosion at the West Fertilizer facility

    International Nuclear Information System (INIS)

    Laboureur, Delphine M.; Han, Zhe; Harding, Brian Z.; Pineda, Alba; Pittman, William C.; Rosas, Camilo; Jiang, Jiaojun; Mannan, M. Sam

    2016-01-01

    Highlights: • In-depth technical analysis of the West, Texas ammonium nitrate incident. • Regulatory analysis for compliance with federal, state and local regulations. • Facility siting and land use planning implications. • Need for local coordination of risk information and emergency planning. - Abstract: In West, Texas on April 17, 2013, a chemical storage and distribution facility caught fire followed by the explosion of around 30 tons of ammonium nitrate while the emergency responders were trying to extinguish the fire, leading to 15 fatalities and numerous buildings, businesses and homes destroyed or damaged. This incident resulted in devastating consequences for the community around the facility, and shed light on a need to improve the safety management of local small businesses similar to the West facility. As no official report on the findings of the incident has been released yet, this article first investigates the root causes of the incident, and presents a simplified consequence analysis. The article reviews the regulations applicable to this type of facility and recommended emergency response procedures to identify gaps between what happened in West and the current regulations, and discusses how the current regulations could be modified to prevent or minimize future losses. Finally, the federal response that followed the incident until the publication of this paper is summarized.

  15. Groundwater discharge by evapotranspiration, Dixie Valley, west-central Nevada, March 2009-September 2011

    Science.gov (United States)

    Garcia, C. Amanda; Huntington, Jena M; Buto, Susan G.; Moreo, Michael T.; Smith, J. LaRue; Andraski, Brian J.

    2014-01-01

    With increasing population growth and land-use change, urban communities in the desert Southwest are progressively looking toward remote basins to supplement existing water supplies. Pending applications by Churchill County for groundwater appropriations from Dixie Valley, Nevada, a primarily undeveloped basin east of the Carson Desert, have prompted a reevaluation of the quantity of naturally discharging groundwater. The objective of this study was to develop a revised, independent estimate of groundwater discharge by evapotranspiration (ETg) from Dixie Valley using a combination of eddy-covariance evapotranspiration (ET) measurements and multispectral satellite imagery. Mean annual ETg was estimated during water years 2010 and 2011 at four eddy-covariance sites. Two sites were in phreatophytic shrubland dominated by greasewood, and two sites were on a playa. Estimates of total ET and ETg were supported with vegetation cover mapping, soil physics considerations, water‑level measurements from wells, and isotopic water sourcing analyses to allow partitioning of ETg into evaporation and transpiration components. Site-based ETg estimates were scaled to the basin level by combining remotely sensed imagery with field reconnaissance. Enhanced vegetation index and brightness temperature data were compared with mapped vegetation cover to partition Dixie Valley into five discharging ET units and compute basin-scale ETg. Evapotranspiration units were defined within a delineated groundwater discharge area and were partitioned as (1) playa lake, (2) playa, (3) sparse shrubland, (4) moderate-to-dense shrubland, and (5) grassland.

  16. Use of HGSYSTEM/UF6 and MACCS2 for the Building 9204-2E safety analysis report consequence analysis: General overview and comparison of models

    International Nuclear Information System (INIS)

    Lombardi, D.A.; Brock, W.R.

    1998-01-01

    Building 9204-2E is used for assembly, disassembly, and storage of weapons components, and quality operations. The building, built in 1971, is a three story structure approximately 101 m long, 51 m wide, and 21 m high located in the western exclusion area of the Y-12 Plant, Oak Ridge, Tennessee. For these activities, several types of hazardous and radioactive materials are used and stored in Building 9204-2E. During a fire, criticality event, or other accident, the potential exists for the release of uranium and other hazardous materials from the building to the atmosphere. A Safety Analysis Report (SAR) is being prepared for Building 9204-2E, in which the consequences of such releases to on-site workers and the off-site public are being analyzed. Consequence estimates from accidental airborne releases are generally calculated using computer models that simulate dispersion and transport of the plume as it travels downwind. For the Building 9204-2E SAR, two candidate atmospheric dispersion candidate models have bene identified for use: (1) the Heavy Gas System-Uranium Hexafluoride (HGSYSTEM/UF 6 ) Model Suite, and (2) the MELCOR Accident Consequence Code System-2 (MACCS2). The purpose of this paper is to provide a general description of the two model suites and compared model results for generic release cases, representative of those that will be analyzed in the Building 9204-2E SAR. Recommendations for use of the model suites in the SAR are also discussed

  17. Statistical modeling of the abundance of vectors of West African Rift Valley fever in Barkédji, Senegal.

    Directory of Open Access Journals (Sweden)

    Cheikh Talla

    Full Text Available Rift Valley fever is an emerging mosquito-borne disease that represents a threat to human and animal health. The exophilic and exophagic behavior of the two main vector in West Africa (Aedes vexans and Culex poicilipes, adverse events post-vaccination, and lack of treatment, render ineffective the disease control. Therefore it is essential to develop an information system that facilitates decision-making and the implementation of adaptation strategies. In East Africa, RVF outbreaks are linked with abnormally high rainfall, and can be predicted up to 5 months in advance by modeling approaches using climatic and environmental parameters. However, the application of these models in West Africa remains unsatisfactory due to a lack of data for animal and human cases and differences in the dynamics of the disease emergence and the vector species involved in transmission. Models have been proposed for West Africa but they were restricted to rainfall impact analysis without a spatial dimension. In this study, we developed a mixed Bayesian statistical model to evaluate the effects of climatic and ecological determinants on the spatiotemporal dynamics of the two main vectors. Adult mosquito abundance data were generated from July to December every fortnight in 2005-2006 at 79 sites, including temporary ponds, bare soils, shrubby savannah, wooded savannah, steppes, and villages in the Barkédji area. The results demonstrate the importance of environmental factors and weather conditions for predicting mosquito abundance. The rainfall and minimum temperature were positively correlated with the abundance of Cx. poicilipes, whereas the maximum temperature had negative effects. The rainfall was negatively correlated with the abundance of Ae. vexans. After combining land cover classes, weather conditions, and vector abundance, our model was used to predict the areas and periods with the highest risks of vector pressure. This information could support decision

  18. Depleted UF6 Internet Resources

    Science.gov (United States)

    government agencies, international organizations, trade associations, private entities and information ) Honeywell General Atomics International Organizations International Atomic Energy Agency (IAEA) Nuclear , Recommendation 95-1 Administrative Governmental Organizations Department of Defense Department of Transportation

  19. Geohydrology and Water Quality of the Valley-Fill Aquifer System in the Upper Sixmile Creek and West Branch Owego Creek Valleys in the Town of Caroline, Tompkins County, New York

    Science.gov (United States)

    Miller, Todd S.

    2009-01-01

    In 2002, the U.S. Geological Survey, in cooperation with the Town of Caroline and Tompkins County Planning Department, began a study of the valley-fill aquifer system in upper Sixmile Creek and headwaters of West Branch Owego Creek valleys in the Town of Caroline, NY. The purpose of the study is to provide geohydrologic data to county and town planners as they develop a strategy to manage and protect their water resources. The first aquifer reach investigated in this series is in the Town of Caroline and includes the upper Sixmile Creek valley and part of West Branch Owego Creek valley. The portions of the valley-fill aquifer system that are comprised of saturated coarse-grained sediments including medium to coarse sand and sandy gravel form the major aquifers. Confined sand and gravel units form the major aquifers in the western and central portions of the upper Sixmile Creek valley, and an unconfined sand and gravel unit forms the major aquifer in the eastern portion of the upper Sixmile Creek valley and in the headwaters of the West Branch Owego Creek valley. The valley-fill deposits are thinnest near the edges of the valley where they pinch out along the till-mantled bedrock valley walls. The thickness of the valley fill in the deepest part of the valley, at the western end of the study area, is about 100 feet (ft); the thickness is greater than 165 ft on top of the Valley Heads Moraine in the central part of the valley. An estimated 750 people live over and rely on groundwater from the valley-fill aquifers in upper Sixmile Creek and West Branch Owego Creek valleys. Most groundwater withdrawn from the valley-fill aquifers is pumped from wells with open-ended 6-inch diameter casings; the remaining withdrawals are from shallow dug wells or cisterns that collect groundwater that discharges to springs (especially in the Brooktondale area). The valley-fill aquifers are the sources of water for about 200 households, several apartment complexes, two mobile home parks

  20. Large quaternary landslides in the central appalachian valley and ridge province near Petersburg, West Virginia

    Science.gov (United States)

    Southworth, C. Scott

    1988-01-01

    Geological mapping and photointerpretation of side-looking airborne radar images and color-infrared aerial photographs reveal two large Quaternary landslides in the Valley and Ridge province of the central Appalachians near Petersburg, W. Va. The Elkhorn Mountain rock avalanche occurs on the thrust-faulted northwestern flank of the Elkhorn Mountain anticlinorium. A minimum of 7 ?? 106 m3 of quartzite colluvium was transported more than 3 km from a 91 m high escarpment of Silurian Tuscarora Quartzite. The extensively vegetated deposit may owe, in part, its transport and weathering to periglacial conditions during the Pleistocene. In contrast, the Gap Mountain rock block slide is a single allochthonous block that is 1.2 km long, 0.6 km wide, and at least 60 m thick. The 43 ?? 106 m3 block is composed of limestone of the Helderberg Group and the Oriskany Sanstone of Early Devonian age. Planar detachment probably occurred along a dissolution bedding plane near the Shriver Chert and the Oriskany Sandstone contact. Failure probably was initiated by downcutting of the South Branch Potomac River during the Pleistocene. Landslides of this magnitude suggest accelerated erosion during periglacial climates in the Pleistocene. The recognition of these large slope failures may provide evidence of paleoclimatic conditions and, thereby, increase our understanding of the geomorphologic development of the Valley and Ridge province. ?? 1988.

  1. Human Costs Assessment - The Impacts of Flooding & Nonstructural Solutions. Tug Fork Valley, West Virginia & Kentucky.

    Science.gov (United States)

    1980-04-01

    to the outside world (especially in the West Virginia side). New people are being drawn in and there is a continuing out migration. Franchised ...all of these businesses are local ones suggesting the skillful entrepreneurship of area people and the recognition of Goody’s existence in the larger...chain stores and franchise businesses. The net effect is that here is another instance in which the Tug Fork people are dependent upon outsiders. King

  2. Los Alamos DP West Plutonium Facility decontamination project, 1978-1981

    International Nuclear Information System (INIS)

    Garde, R.; Cox, E.J.; Valentine, A.M.

    1982-09-01

    The DP West Plutonium Facility operated by the Los Alamos National Laboratory, Los Alamos, New Mexico was decontaminated between April 1978 and April 1981. The facility was constructed in 1944 to 1945 to produce plutonium metal and fabricate parts for nuclear weapons. It was continually used as a plutonium processing and research facility until mid-1978. Decontamination operations included dismantling and removing gloveboxes and conveyor tunnels; removing process systems, utilities, and exhaust ducts; and decontaminating all remaining surfaces. This report describes glovebox and conveyor tunnel separations, decontamination techniques, health and safety considerations, waste management procedures, and costs of the operation

  3. Conceptual design for vitrification of HLW at West Valley using a rotary calciner/metallic melter

    International Nuclear Information System (INIS)

    Giraud, J.P.; Conord, J.P.; Saverot, P.M.

    1984-01-01

    The CEA has had an extensive research program in the field of vitrification technology for over 24 years, and several testing facilities were used throughout all phases of development and engineering: The Vulcain facility comprises a vitrification hot cell and four auxiliary hot cells. Vulcain allows the production of 2-kg samples of active glass. The off-gas treatment system allows testing the DF of each equipment. The auxiliary cells are equipped with leach-rate tests, diffusion tests, and irradiation tests on the glass samples. The Atlas facility is a reproduction of AVM calcination and vitrification furnaces at 1/2 scale enclosed in a glove box. This facility is used for testing ruthenium volatility and containment in the vitrification process. The full-scale AVM inactive pilot facility is used for testing calcination and vitrification of new compositions of high-level waste and for developing new types of vitrification furnaces. The inactive test loop is for testing air cooling of glass containers. The full-scale AVH inactive pilot facility is used for testing AVH technology and has been in operation since late 1981

  4. The Holocene sedimentary history of the Kangerlussuaq Fjord-valley fill, West Greenland

    DEFF Research Database (Denmark)

    Storms, Joep E.A.; de Winter, Ilja L.; Overeem, Irina

    2012-01-01

    valleys. Based on published and new land- and sea-based geophysical data, radiocarbon dates and geological observations we have characterized the infill and reconstructed the sedimentation history during the Holocene. Based on a revised sea level curve and data presented in this paper we defined three...... depocenters by a flood plain which transferred sediment from the GIS to the Keglen delta. Ongoing sea level fall due to glacio-isostastic uplift combined with a gradually cooler and dryer climate resulted in terrace formation along the Watson River flood plain. Around 4000 yr BP, the GIS margin reached its...... most landward location and began to advance to its present location. The final phase (Phase III; channels...

  5. Tennessee Valley region study: potential year 2000 radiological dose to population resulting from nuclear facility operations

    International Nuclear Information System (INIS)

    1978-06-01

    A companion report, DOE/ET-0064/1, presents a geographic, cultural, and demographic profile of the Tennessee Valley Region study area. This report describes the calculations of radionuclide release and transport and of the resultant dose to the regional population, assuming a projected installed capacity of 220,000 MW in the year 2000, of which 144,000 MW would be nuclear. All elements of the fuel cycle were assumed to be in operation. The radiological dose was calculated as a one-year dose based on ingestion of 35 different food types as well as for nine non-food pathways, and was reported as dose to the total body and for six specific organs for each of four age groups (infant, child, teen, and adult). Results indicate that the average individual would receive an incremental dose of 7 x 10 -4 millirems in the year 2000 from the operation of nuclear facilities within and adjacent to the region, five orders of magnitude smaller than the dose from naturally occurring radiation in the area. The major contributor to dose was found to be tritium, and the most significant pathways were immersion in air, inhalation of air, transpiration of tritium (absorption through the skin), and exposure radionuclide-containing soil. 60 references

  6. Regulatory analysis and lessons learned from the LLRW [low-level radioactive waste] disposal area at West Valley, New York: Final report

    International Nuclear Information System (INIS)

    1986-12-01

    The New York State Energy Research and Development Authority has sponsored a project to develop an integrated set of site management plans for the West Valley low-level radioactive waste (LLRW) disposal area. The plans were directed to upgrade the disposal area so that passive custodial care and monitoring activities would be sufficient to protect public health and safety and the environment. Tasks 5 and 6, Regulatory Analysis and Lessons Learned, are the subject of this report. The regulatory analysis identified areas of inconsistencies between the historic site operations and the current state and federal LLRW disposal regulations and guidelines. The lessons learned task identified the causes of the disposal problems at West Valley, discussed the lessons learned, and described the responses developed by the NRC and industry to the lessons learned. 85 refs., 6 figs., 19 tabs

  7. Conversion and Blending Facility Highly enriched uranium to low enriched uranium as uranium hexafluoride. Revision 1

    International Nuclear Information System (INIS)

    1995-01-01

    This report describes the Conversion and Blending Facility (CBF) which will have two missions: (1) convert surplus HEU materials to pure HEU UF 6 and a (2) blend the pure HEU UF 6 with diluent UF 6 to produce LWR grade LEU-UF 6 . The primary emphasis of this blending be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. The chemical and isotopic concentrations of the blended LEU product will be held within the specifications required for LWR fuel. The blended LEU product will be offered to the United States Enrichment Corporation (USEC) to be sold as feed material to the commercial nuclear industry

  8. Holocene palaeosols and aeolian activities in the Umimmalissuaq valley, West Greenland

    DEFF Research Database (Denmark)

    Müller, Michael; Thiel, Christine; Kühn, Peter

    2016-01-01

    Aeolian sand sheets and active dunefields preserve an ancient Holocene land surface represented by palaeosols that occur around the present ice margin in the Kangerlussuaq area, West Greenland. To determine the relation between Holocene aeolian activities and periods of soil formation, both...... margin (60 wt%) are comparable with aeolian sand sheets currently formed at greater distances (4–5 km) from the present ice margin. We propose a transport distance for fine....... This period was characterised by low but constant aeolian activity. Since aeolian activity intensified after around 300 cal. yr b2k and is still resulting in active dunefields with coarse and medium sand accumulation, the ice margin must have reached its present position at that time....

  9. Argonne-West facility requirements for a radioactive waste treatment demonstration

    International Nuclear Information System (INIS)

    Dwight, C.C.; Felicione, F.S.; Black, D.B.; Kelso, R.B.; McClellan, G.C.

    1995-01-01

    At Argonne National Laboratory-West (ANL-W), near Idaho Falls, Idaho, facilities that were originally constructed to support the development of liquid-metal reactor technology are being used and/or modified to meet the environmental and waste management research needs of DOE. One example is the use of an Argonne-West facility to conduct a radioactive waste treatment demonstration through a cooperative project with Science Applications International Corporation (SAIC) and Lockheed Idaho Technologies Company. The Plasma Hearth Process (PBP) project will utilize commercially-adapted plasma arc technology to demonstrate treatment of actual mixed waste. The demonstration on radioactive waste will be conducted at Argonne's Transient Reactor Test Facility (TREAT). Utilization of an existing facility for a new and different application presents a unique set of issues in meeting applicable federal state, and local requirements as well as the additional constraints imposed by DOE Orders and ANL-W site requirements. This paper briefly describes the PHP radioactive demonstrations relevant to the interfaces with the TREAT facility. Safety, environmental design, and operational considerations pertinent to the PHP radioactive demonstration are specifically addressed herein. The personnel equipment, and facility interfaces associated with a radioactive waste treatment demonstration are an important aspect of the demonstration effort. Areas requiring significant effort in preparation for the PBP Project being conducted at the TREAT facility include confinement design, waste handling features, and sampling and analysis considerations. Information about the facility in which a radioactive demonstration will be conducted, specifically Argonne's TREAT facility in the case of PHP, may be of interest to other organizations involved in developing and demonstrating technologies for mixed waste treatment

  10. Decontamination and decommissioning of Extraction Cell 3 at the West Valley Demonstration Project. Topical report, January 1982-April 1985

    International Nuclear Information System (INIS)

    Jones, E.D.

    1985-12-01

    This report describes the decontamination and decommissioning (D and D) of Extraction Cell 3 (XC-3) at the West Valley Demonstration Project. XC-3 is one of several cells in the former reprocessing plant required for use in support of the solidification of high-level waste. It became radioactively contaminated during nuclear fuel reprocessing from 1966 to 1972. XC-3 contained systems used in the final uranium extraction cycle. Several pump niche and sample box drains were routed into the cell. The report describes the work performed to accomplish the D and D objectives of removing existing piping and equipment from XC-3 and to reducing radiation and contamination levels, to allow installation of equipment for the Liquid-Waste Treatment System (LWTS). Contaminated debris and equipment inside the cell were removed, packaged and stored for future disposition. Interior surfaces (walls, floor, and ceiling) of the cell were then decontaminated to a radiation level that allowed entry without the use of protective clothing or respiratory protection

  11. Earthquake precursory studies in Kangra valley of North West Himalayas, India, with special emphasis on radon emission

    International Nuclear Information System (INIS)

    Kumar, Arvind; Singh, Surinder; Mahajan, Sandeep; Bajwa, Bikramjit Singh; Kalia, Rajeev; Dhar, Sunil

    2009-01-01

    The continuous soil gas radon monitoring is carried out at Palampur and the daily monitoring of radon concentration in water is carried out at Dharamshala region of Kangra valley of North West Himalayas, India, a seismic zone V, to study the correlation of radon anomalies in relation to seismic activities. In this study, radon monitoring in soil was carried out by using barasol probe manufactured by Algade France, whereas the radon content in water was recorded using RAD 7 radon monitoring system of Durridge Company USA. The effect of meteorological parameters viz. temperature, pressure, wind velocity, rainfall, and humidity on radon emission has been studied. The seasonal average value and standard deviation of radon in soil and water is calculated to find the radon anomaly to minimize the effect of meteorological parameters on radon emission. The radon anomalies observed in the region have been correlated with the seismic events of M≥2 reported by Wadia Institute of Himalayas Geology Dehradoon and Indian Meteorological Department, New Delhi in NW Himalayas within 250 km distance from the monitoring stations.

  12. Emerging vector-borne diseases in dromedaries in Tunisia: West Nile, bluetongue, epizootic haemorrhagic disease and Rift Valley fever

    Directory of Open Access Journals (Sweden)

    Thameur B. Hassine

    2017-03-01

    Full Text Available A total of 118 sera were collected during 2016 from two groups of dromedaries from Kebili and Medenine governorates in the south of Tunisia. The aim of this study was to provide the first serological investigation of four emerging vector-borne diseases in two groups of dromedaries in Tunisia. Sera were tested by ELISA and serum neutralisation test to identify West Nile virus (WNV, bluetongue virus (BTV, epizootic haemorrhagic disease virus (EHDV and Rift Valley fever virus (RVFV. In the first group, the seroprevalence for BTV was 4.6%, while in the second group, it was 25.8% for WNV and 9.7% for BTV. Only serotype 1 was detected for BTV in the two groups. No evidence for circulation of RVF and EHD viruses was revealed. Results indicated that dromedaries can be infected with BTV and WNV, suggesting that this species might play a significant role in the epizootiology of these viral diseases in Tunisia and neighbouring countries.

  13. Geotechnical analysis of soil samples from test trench at Western New York Nuclear Service Center, West Valley, New York

    International Nuclear Information System (INIS)

    Fickies, R.H.; Fakundiny, R.H.; Mosley, E.T.

    1979-04-01

    In July 1977, a deep research trench was excavated and soil samples collected at the Western New York Nuclear Services Center, West Valley, NY. The glacial till horizons sampled are considered to be representative of the till serving as a burial medium at the nearby low-level radioactive waste burial ground. A series of laboratory tests were conducted consisting of unit weight, moisture content, Atterberg limits, unconfined compression, dispersion, swell, permeability, and consolidation. These laboratory analyses and field observations indicate that the till exposed in the research trench is a generally dense mixture of silt and clay of low to medium plasticity, with minor amounts of fine to coarse sand and fine gravel. The till has a generally low coefficient of permeability in the range of 10 -7 cm/s horizontal and 10 -8 cm/s vertical. A network of vertical fractures exists in the upper 15 feet of weathered till which may allow some downward percolation of surface runoff. The test data indicates that the maximum depth to which these fractures could possibly penetrate is 50 feet

  14. Comparison of avifaunal diversity in and around Neora Valley National Park, West Bengal, India

    Directory of Open Access Journals (Sweden)

    U.S. Roy

    2011-10-01

    Full Text Available Anthropogenic intervention has led to conversion of much of the global diversity by means of habitat alterations. The present study was carried out to investigate the importance of habitat quality and habitat heterogeneity for the diversity, distribution and abundance of avifauna in and around Neora Valley National Park (NVNP during April-May 2010. A total of 73 bird species belonging to 25 families were recorded during the present study applying a modified point count method. Forest edges were found to be most diverse with a total count of 54 bird species having an abundance of 172.53 number of birds ha-1. Study areas with human settlements was represented by a total species count of 24 with an abundance of 130.39 number of birds ha-1 while a total species count of 22 with an abundance of 69.32 number of birds ha-1 was recorded from thick vegetation assemblage with close canopy cover. This site specific occurrence pattern for avifauna was reflected in the study of diversity indices. The highest Shannon-Wiener general diversity score of 3.77 was recorded for bird species from forest edges. Study areas with dense canopy closure were found to support more habitat specialist bird species while areas having human settlements harboured more opportunistic bird species. An overall negative influence of human settlements on bird diversity, distribution and abundance was evidenced from the present study and needs further investigation. Moreover, intensive studies will certainly enrich our knowledge of avian diversity and distribution pattern from the present study location.

  15. Geochemistry of trace elements and REE in phosphate deposits of el Sibaiya west AREA, nile valley

    International Nuclear Information System (INIS)

    Aly, M.M.; Hussein, H.A.; Elkammar, A.A.; Mahdy, A.I.

    1994-01-01

    The present work deals essentially with the study of the geochemistry of trace elements and rare earth elements (REE s) patterns in the upper cretaceous phosphate deposit in El Sibaiya west area located on the western side of the River Nile. About 20 Km south from Esna town, upper Egypt. It was evident throughout this study that the average shale normalized pattern of six analyzed rare earth elements indicates that the phosphate deposits under study were deposited under marine environment. In addition some geochemical ratios such as Cl/Br and Na/Br have been proposed as indicators of the paleosalinity of the upper cretaceous tethys compared with the nowadays sea. Uranium equilibrium status of the studied phosphate deposits suggests a remarkably secondary enrichment at the lower horizon at the expense of the upper one due to downward leaching. Such secondary enrichment of uranium is thought to take place under oxidizing vadose conditions by the action of descending meteoric water. 6 fig., 4 tab

  16. The Ohio River Valley CO2 Storage Project AEP Mountaineer Plant, West Virginia Numerical Simulation and Risk Assessment Report

    Energy Technology Data Exchange (ETDEWEB)

    Neeraj Gupta

    2008-03-31

    A series of numerical simulations of carbon dioxide (CO{sub 2}) injection were conducted as part of a program to assess the potential for geologic sequestration in deep geologic reservoirs (the Rose Run and Copper Ridge formations), at the American Electric Power (AEP) Mountaineer Power Plant outside of New Haven, West Virginia. The simulations were executed using the H{sub 2}O-CO{sub 2}-NaCl operational mode of the Subsurface Transport Over Multiple Phases (STOMP) simulator (White and Oostrom, 2006). The objective of the Rose Run formation modeling was to predict CO{sub 2} injection rates using data from the core analysis conducted on the samples. A systematic screening procedure was applied to the Ohio River Valley CO{sub 2} storage site utilizing the Features, Elements, and Processes (FEP) database for geological storage of CO{sub 2} (Savage et al., 2004). The objective of the screening was to identify potential risk categories for the long-term geological storage of CO{sub 2} at the Mountaineer Power Plant in New Haven, West Virginia. Over 130 FEPs in seven main classes were assessed for the project based on site characterization information gathered in a geological background study, testing in a deep well drilled on the site, and general site conditions. In evaluating the database, it was apparent that many of the items were not applicable to the Mountaineer site based its geologic framework and environmental setting. Nine FEPs were identified for further consideration for the site. These FEPs generally fell into categories related to variations in subsurface geology, well completion materials, and the behavior of CO{sub 2} in the subsurface. Results from the screening were used to provide guidance on injection system design, developing a monitoring program, performing reservoir simulations, and other risk assessment efforts. Initial work indicates that the significant FEPs may be accounted for by focusing the storage program on these potential issues. The

  17. Cement waste form qualification report: WVDP [West Valley Demonstration Project] PUREX decontaminated supernatant

    International Nuclear Information System (INIS)

    McVay, C.W.; Stimmel, J.R.; Marchetti, S.

    1988-08-01

    This report provides a summary of work performed to develop a cement-based, low-level waste formulation suitable for the solidification of decontaminated high-level waste liquid produced as a by-product of PUREX spent fuel reprocessing. The resultant waste form is suitable for interim storage and is intended for ultimate disposal as low-level Class C waste; it also meets the stability requirements of the NRC Branch Technical Position on Waste Form Qualification, May 1983 and the requirements of 10 CFR 61. A recipe was developed utilizing only Portland Type I cement based on an inorganic salts simulant of the PUREX supernatant. The qualified recipe was tested full scale in the production facility and was observed to produce a product with entrained air, low density, and lower-than-expected compressive strength. Further laboratory scale testing with actual decontaminated supernatant revealed that set retarders were present in the supernatant, precluding setting of the product and allowing the production of ''bleed water.'' Calcium nitrate and sodium silicate were added to overcome the set retarding effect and produced a final product with improved performance when compared to the original formulation. This report describes the qualification process and qualification test results for the final product formulation. 7 refs., 38 figs., 21 tabs

  18. Quantitative risk assessment of the New York State operated West Valley Radioactive Waste Disposal Area.

    Science.gov (United States)

    Garrick, B John; Stetkar, John W; Bembia, Paul J

    2010-08-01

    This article is based on a quantitative risk assessment (QRA) that was performed on a radioactive waste disposal area within the Western New York Nuclear Service Center in western New York State. The QRA results were instrumental in the decision by the New York State Energy Research and Development Authority to support a strategy of in-place management of the disposal area for another decade. The QRA methodology adopted for this first of a kind application was a scenario-based approach in the framework of the triplet definition of risk (scenarios, likelihoods, consequences). The measure of risk is the frequency of occurrence of different levels of radiation dose to humans at prescribed locations. The risk from each scenario is determined by (1) the frequency of disruptive events or natural processes that cause a release of radioactive materials from the disposal area; (2) the physical form, quantity, and radionuclide content of the material that is released during each scenario; (3) distribution, dilution, and deposition of the released materials throughout the environment surrounding the disposal area; and (4) public exposure to the distributed material and the accumulated radiation dose from that exposure. The risks of the individual scenarios are assembled into a representation of the risk from the disposal area. In addition to quantifying the total risk to the public, the analysis ranks the importance of each contributing scenario, which facilitates taking corrective actions and implementing effective risk management. Perhaps most importantly, quantification of the uncertainties is an intrinsic part of the risk results. This approach to safety analysis has demonstrated many advantages of applying QRA principles to assessing the risk of facilities involving hazardous materials.

  19. In-situ arsenic remediation in Carson Valley, Douglas County, west-central Nevada

    Science.gov (United States)

    Paul, Angela P.; Maurer, Douglas K.; Stollenwerk, Kenneth G.; Welch, Alan H.

    2010-01-01

    Conventional arsenic remediation strategies primarily involve above-ground treatment that include costs involved in the disposal of sludge material. The primary advantages of in-situ remediation are that building and maintaining a large treatment facility are not necessary and that costs associated with the disposal of sludge are eliminated. A two-phase study was implemented to address the feasibility of in-situ arsenic remediation in Douglas County, Nevada. Arsenic concentrations in groundwater within Douglas County range from 1 to 85 micrograms per liter. The primary arsenic species in groundwater at greater than 250 ft from land surface is arsenite; however, in the upper 150 ft of the aquifer arsenate predominates. Where arsenite is the primary form of arsenic, the oxidation of arsenite to arsenate is necessary. The results of the first phase of this investigation indicated that arsenic concentrations can be remediated to below the drinking-water standard using aeration, chlorination, iron, and pH adjustment. Arsenic concentrations were remediated to less than 10 micrograms per liter in groundwater from the shallow and deep aquifer when iron concentrations of 3-6 milligrams per liter and pH adjustments to less than 6 were used. Because of the rapid depletion of dissolved oxygen, the secondary drinking-water standards for iron (300 micrograms per liter) and manganese (100 micrograms per liter) were exceeded during treatment. Treatment was more effective in the shallow well as indicated by a greater recovery of water meeting the arsenic standard. Laboratory and field tests were included in the second phase of this study. Laboratory column experiments using aquifer material indicated the treatment process followed during the first phase of this study will continue to work, without exceeding secondary drinking-water standards, provided that groundwater was pre-aerated and an adequate number of pore volumes treated. During the 147-day laboratory experiment, no

  20. Comparison of peak discharges among sites with and without valley fills for the July 8-9, 2001 flood in the headwaters of Clear Fork, Coal River basin, mountaintop coal-mining region, southern West Virginia

    Science.gov (United States)

    Wiley, Jeffrey B.; Brogan, Freddie D.

    2003-01-01

    The effects of mountaintop-removal mining practices on the peak discharges of streams were investigated in six small drainage basins within a 7-square-mile area in southern West Virginia. Two of the small basins had reclaimed valley fills, one basin had reclaimed and unreclaimed valley fills, and three basins did not have valley fills. Indirect measurements of peak discharge for the flood of July 8-9, 2001, were made at six sites on streams draining the small basins. The sites without valley fills had peak discharges with 10- to 25-year recurrence intervals, indicating that rainfall intensities and totals varied among the study basins. The flood-recurrence intervals for the three basins with valley fills were determined as though the peak discharges were those from rural streams without the influence of valley fills, and ranged from less than 2 years to more than 100 years.

  1. Use of nuclear facilities at Argonne-West to support new environmental missions

    International Nuclear Information System (INIS)

    Black, D.B.; Dwight, C.C.; Lineberry, M.J.

    1994-08-01

    At Argonne National Laboratory-West, facilities that were originally constructed to support the development of liquid-metal reactor technology are being used to meet the environmental and waste management need of the US Department of Energy. These needs include waste characterization, waste testing, and waste treatment technology development. Waste characterization and repackaging activities are being performed in the Hot Fuel Examination Facility for the Waste Isolation Pilot Plant (WIPP) Experimental Test Program. Characterization activities include sampling the gas in actual waste containers, categorizing waste contents for their gas generation potential, and extracting solid samples. A new waste testing project will utilize the Zero Powered Physics Reactor facility. In the workroom of these facility, laboratory gas generation experiments will be conducted with contact-handled transuranic waste. Both the characterization and waste testing activities are part of the effort to prepare the WIPP performance assessment. Waste treatment demonstrations have or will be conducted at the Transient Reactor Test facility and involve private sector participants. The demonstrations involve the development of thermal treatment for materials containing residual amounts of plutonium using plasma-arc technology. The success of these new programs is largely due to experience gained from past missions in such areas as radiological control and nuclear safety

  2. Classification of High-Rise Residential Building Facilities: A Descriptive Survey on 170 Housing Scheme in Klang Valley

    Directory of Open Access Journals (Sweden)

    Abd Wahab Siti Rashidah Hanum

    2016-01-01

    Full Text Available High-rise residential building is a type of housing that has multi-dwelling units built on the same land. This type of housing has become popular each year in urban area due to the increasing cost of land. There are several common facilities provided in high-rise residential building. For example playground, swimming pool, gymnasium, 24 hours security system such as CCTV, access card and so on. Thus, maintenance works of the common facilities must be well organised. The purpose of this paper is to identify the classification of facilities provided at high rise residential building. The survey was done on 170 high-rise residential schemes by using stratified random sampling technique. The scope of this research is within Klang Valley area. This area is rapidly developed with high-rise residential building. The objective of this survey is to list down all the facilities provided in each sample of the schemes. The result, there are nine classification of facilities provided for high-rise residential building.

  3. Spirit's West Valley Panorama

    Science.gov (United States)

    2008-01-01

    NASA'S Mars Exploration Rover Spirit captured this westward view from atop a low plateau where Sprit spent the closing months of 2007. After several months near the base of the plateau called 'Home Plate' in the inner basin of the Columbia Hills range inside Gusev Crater, Spirit climbed onto the eastern edge of the plateau during the rover's 1,306th Martian day, or sol, (Sept. 5, 2007). It examined rocks and soils at several locations on the southern half of Home Plate during September and October. It was perched near the western edge of Home Plate when it used its panoramic camera (Pancam) to take the images used in this view on sols 1,366 through 1,369 (Nov. 6 through Nov. 9, 2007). With its daily solar-energy supply shrinking as Martian summer turned to fall, Spirit then drove to the northern edge of Home Plate for a favorable winter haven. The rover reached that northward-tilting site in December, in time for the fourth Earth-year anniversary of its landing on Mars. Spirit reached Mars on Jan. 4, 2004, Universal Time (Jan. 3, 2004, Pacific Standard Time). It landed at a site at about the center of the horizon in this image. This panorama covers a scene spanning left to right from southwest to northeast. The western edge of Home Plate is in the foreground, generally lighter in tone than the more distant parts of the scene. A rock-dotted hill in the middle distance across the left third of the image is 'Tsiolkovski Ridge,' about 30 meters or 100 feet from the edge of Home Plate and about that same distance across. A bump on the horizon above the left edge of Tsiolkovski Ridge is 'Grissom Hill,' about 8 kilometers or 5 miles away. At right, the highest point of the horizon is 'Husband Hill,' to the north and about 800 meters or half a mile away. This view combines separate images taken through Pancam filters centered on wavelengths of 753 nanometers, 535 nanometers and 432 nanometers to produce an approximately true-color panorama.

  4. West Valley feasibility study

    International Nuclear Information System (INIS)

    Pirro, J.

    1981-01-01

    This report presents the results of a technical assessment of decontamination alternative prepared for the Western New York Nuclear Service Center (WNYNSC). The purpose of the assessment is to determine the recommended method for decontamination of cell surfaces and decontamination and removal of fuel reprocessing cell equipment to permit manual entry into the cells for the installation of waste solidification equipment. The primary cells of interest are the PMC, GPC, and CPC because they offer the largest usable volume for the solidification program. The secondary cells include XC-1, XC-2, XC-3 and the PPC which may be needed to support the solidification program. Five decontamination assessments were evaluated (A-E). The assessments included the estimated cost, occupational exposure, duration, manpower, waste volume generated, and final cell radiation levels achieved with the alternative decontamination methods. The methods varied from thorough destructive decontamination to equipment removal without decontamination followed by cell wall and floor decontamination. The recommended method for the primary cells is to utilize the remote manipulators and cranes to the maximum extent possible to decontaminate equipment and cell surfaces remotely, and to remove the equipment for temporary on-site storage. The recommended method for secondary cell decontamination is to remotely decontaminate the cells to the maximum extent possible prior to manned entry for contact-removal of the fuel reprocessing equipment (Assessment D). Assessment A is expected to cost $8,713,500 in 1980 dollars (including a 25% contingency) and will result in an occupational exposure of 180.3 manRem. Assessment D is expected to cost $11,039,800 and will result in an occupational exposure of 259 manRems

  5. West Valley feasibility study

    Energy Technology Data Exchange (ETDEWEB)

    Pirro, J.

    1981-01-01

    This report presents the results of a technical assessment of decontamination alternative prepared for the Western New York Nuclear Service Center (WNYNSC). The purpose of the assessment is to determine the recommended method for decontamination of cell surfaces and decontamination and removal of fuel reprocessing cell equipment to permit manual entry into the cells for the installation of waste solidification equipment. The primary cells of interest are the PMC, GPC, and CPC because they offer the largest usable volume for the solidification program. The secondary cells include XC-1, XC-2, XC-3 and the PPC which may be needed to support the solidification program. Five decontamination assessments were evaluated (A-E). The assessments included the estimated cost, occupational exposure, duration, manpower, waste volume generated, and final cell radiation levels achieved with the alternative decontamination methods. The methods varied from thorough destructive decontamination to equipment removal without decontamination followed by cell wall and floor decontamination. The recommended method for the primary cells is to utilize the remote manipulators and cranes to the maximum extent possible to decontaminate equipment and cell surfaces remotely, and to remove the equipment for temporary on-site storage. The recommended method for secondary cell decontamination is to remotely decontaminate the cells to the maximum extent possible prior to manned entry for contact-removal of the fuel reprocessing equipment (Assessment D). Assessment A is expected to cost $8,713,500 in 1980 dollars (including a 25% contingency) and will result in an occupational exposure of 180.3 manRem. Assessment D is expected to cost $11,039,800 and will result in an occupational exposure of 259 manRems.

  6. Gravity and magnetic data of Midway Valley, southwest Nevada

    International Nuclear Information System (INIS)

    Ponce, D.A.; Langenheim, V.E.; Sikora, R.F.

    1993-01-01

    Detailed gravity and ground magnetic data collected along five traverses across Midway Valley on the eastern flank of Yucca Mountain in southwest Nevada are described. These data were collected as part of an effort to evaluate faulting in the vicinity of proposed surface facilities for a potential nuclear waste repository at Yucca Mountain. Geophysical data show that Midway Valley is bounded by large gravity and magnetic anomalies associated with the Bow Ridge and Paintbrush Canyon faults, on the west side of Exile Hill and on the west flank of Fran Ridge, respectively. In addition, Midway Valley itself is characterized by a number of small-amplitude anomalies that probably reflect small-scale faulting beneath Midway Valley

  7. Intimate partner violence in pregnancy among antenatal attendees at health facilities in West Pokot county, Kenya.

    Science.gov (United States)

    Owaka, Isaac Ogweno; Nyanchoka, Margaret Keraka; Atieli, Harryson Etemesi

    2017-01-01

    The objective of this study was to investigate factors contributing to intimate partner violence in pregnancy among antenatal attendees at the health facilities in West Pokot Sub-County. The study was done in West Pokot Sub-County. Using cross sectional study design, a total of 238 antenatal attendees were systematically sampled for the study. Four focused group discussions and 20 key informant interviews were conducted for qualitative data collection. Qualitative data was consolidated into various themes while bivariate and logistic regression analysis was done to determine factors associated with experience of IPV in the index of pregnancy with P ≤ 0.05 being considered significant. The study found prevalence of overall, physical, psychological and sexual IPV in pregnancy to be 66.9%, 29.9%, 55.8% and 39.2% respectively. After adjusting for confounders, Overall IPV in pregnancy was significantly associated with Alcohol intake by partner (OR 2.116, 95% CI 1.950-2.260, P 0.000) and partner's level of education (OR 1.265, 95% CI 1.079-1.487, P 0.031), while psychological and sexual IPV was significantly associated with age of partner (OR 2.292, 95% CI 2.123-2.722, P 0.007) and age of pregnant women (OR 1.174, 95% CI 1.001-1.397 P 0.049) respectively. The care offered to antenatal attendees experiencing IPV was not in line with WHO guidelines and standard on handling gender based violence cases. The study finding indicates that IPV in pregnancy among antenatal attendees in West Pokot is very high. This unearths the gaps on gender based violence interventions in the maternal and child health programs.

  8. Ecological aspects in construction of West Siberian oil field surface facilities

    International Nuclear Information System (INIS)

    Scvortzov, I.D.; Crushin, P.N.

    1991-01-01

    The exploitation of arctic regions, where permanently frozen grounds are widespread, leads to problems concerning the climate and the geo-cryological environment. One of the most urgent tasks is to minimize effects on the environment, otherwise irreversible, catastrophic processes, the deterioration of permafrost into swamps, fouling subsoil waters and rivers, ground surface pollution with petroleum products, and destruction of fish and birds, may occur. The measures aimed at providing the environmental ecological equilibrium during the exploitation of the northern oil deposits of West Siberia are described in this paper. These measures are worked out during the design stage. Then appropriate engineering decisions and product procedures are chosen, where much prominence is given to reliability of the oil and gas field facilities. The paper includes information about developing measures for the preventive systematic maintenance of the oil pipelines, maintenance schedule, prediction of accidents and certain procedures for their rectification

  9. Oak Ridge National Laboratory West End Treatment Facility simulated sludge vitrification demonstration, Revision 1

    International Nuclear Information System (INIS)

    Cicero, C.A.; Bickford, D.F.; Bennert, D.M.; Overcamp, T.J.

    1994-01-01

    Technologies are being developed by the US Department of Energy's (DOE) Nuclear Facility sites to convert hazardous and mixed wastes to a form suitable for permanent disposal. Vitrification, which has been declared the Best Demonstrated Available Technology for high-level radioactive waste disposal by the EPA, is capable of producing a highly durable wasteform that minimizes disposal volumes through organic destruction, moisture evaporation, and porosity reduction. However, this technology must be demonstrated over a range of waste characteristics, including compositions, chemistries, moistures, and physical characteristics to ensure that it is suitable for hazardous and mixed waste treatment. These wastes are typically wastewater treatment sludges that are categorized as listed wastes due to the process origin or organic solvent content, and usually contain only small amounts of hazardous constituents. The Oak Ridge National Laboratory's (ORNL) West End Treatment Facility's (WETF) sludge is considered on of these representative wastes. The WETF is a liquid waste processing plant that generates sludge from the biodenitrification and precipitation processes. An alternative wasteform is needed since the waste is currently stored in epoxy coated carbon steel tanks, which have a limited life. Since this waste has characteristics that make it suitable for vitrification with a high likelihood of success, it was identified as a suitable candidate by the Mixed Waste Integrated Program (MWIP) for testing at CU. The areas of special interest with this sludge are (1) minimum nitrates, (2) organic destruction, and (3) waste water treatment sludges containing little or no filter aid

  10. Lessons learned from recent safety related incidents at A Canadian uranium conversion facility

    International Nuclear Information System (INIS)

    Jaferi, Jafir

    2013-01-01

    This paper presents the Canadian Nuclear Safety Commission's (CNSC) regulatory requirements for nuclear fuel facility licensees to report any situation or incident that results or is likely to result in a hazard to the health or safety of any person or the environment and to submit its incident investigation report with cause(s) of the incident and corrective actions taken or planned. In addition, the paper presents two recent safety-related incidents that occurred at a uranium conversion facility in Canada along with their consequences, causes, corrective actions and any lessons learned. The first incident resulted in a release of uranium hexafluoride (UF6) inside the UF6 cylinder filling station and the second one resulted in a spill of uranium tetrafluoride (UF 4 ) slurry inside the UF6 plant. Both incidents had no impact on the workers or the environment. (authors)

  11. COHORT OF WOMEN LIVING IN OR NEAR A HIGHLY INDUSTRIALIZED AREA OF KANAWHA RIVER VALLEY IN WEST VIRGINIA: ENDOMETRIOSIS AND BLOOD LEVELS OF DIOXIN AND DIOXIN-LIKE CHEMICALS

    Science.gov (United States)

    Introduction Historical releases of dioxin and dioxin-like chemicals with subsequent impacts to environmental media in the Kanawha River Valley (KRV) of West Virginia have been well documented.' The bulk of dioxin found in this area appears to be derived from the production of 2,...

  12. A retrospective tiered environmental assessment of the Mount Storm Wind Energy Facility, West Virginia,USA

    Energy Technology Data Exchange (ETDEWEB)

    Efroymson, Rebecca Ann [ORNL; Day, Robin [No Affiliation; Strickland, M. Dale [Western EcoSystems Technology

    2012-11-01

    Bird and bat fatalities from wind energy projects are an environmental and public concern, with post-construction fatalities sometimes differing from predictions. Siting facilities in this context can be a challenge. In March 2012 the U.S. Fish and Wildlife Service (USFWS) released Land-based Wind Energy Guidelines to assess collision fatalities and other potential impacts to species of concern and their habitats to aid in siting and management. The Guidelines recommend a tiered approach for assessing risk to wildlife, including a preliminary site evaluation that may evaluate alternative sites, a site characterization, field studies to document wildlife and habitat and to predict project impacts, post construction studies to estimate impacts, and other post construction studies. We applied the tiered assessment framework to a case study site, the Mount Storm Wind Energy Facility in Grant County, West Virginia, USA, to demonstrate the use of the USFWS assessment approach, to indicate how the use of a tiered assessment framework might have altered outputs of wildlife assessments previously undertaken for the case study site, and to assess benefits of a tiered ecological assessment framework for siting wind energy facilities. The conclusions of this tiered assessment for birds are similar to those of previous environmental assessments for Mount Storm. This assessment found risk to individual migratory tree-roosting bats that was not emphasized in previous preconstruction assessments. Differences compared to previous environmental assessments are more related to knowledge accrued in the past 10 years rather than to the tiered structure of the Guidelines. Benefits of the tiered assessment framework include good communication among stakeholders, clear decision points, a standard assessment trajectory, narrowing the list of species of concern, improving study protocols, promoting consideration of population-level effects, promoting adaptive management through post

  13. Use to titanium-treated zeolite for plutonium, strontium, and cesium removal from West Valley alkaline wastes and sludge wash wastes

    International Nuclear Information System (INIS)

    Bray, L.A.; Hara, F.T.

    1993-01-01

    Zeolite (IONSIV IE-96) treated with a titanium (Ti) solution will extract traces of plutonium (Pu), strontium (Sr), and cesium (Cs) found in the West Valley Nuclear Services Co., Inc. (WVNS) alkaline supernatant and alkaline sludge water washes. Small ion exchange columns containing Ti-treated zeolite have been successfully tested at WVNS and Pacific Northwest Laboratory (PNL) for the removal of Pu. Full-scale ion exchange processing of sludge wash solution is now being developed at WVNS for use in FY 1992. Commercial manufacturing options for the production of the Ti-treated zeolite were investigated. The Ti-treated zeolite may have application at Hanford and at other U.S. Department of Energy (DOE) sites for the removal of low-level concentrations of Cs, Sr, and Pu from alkaline waste streams

  14. FY94 site characterization and multilevel well installation at a west Bear Creek Valley research site on the Oak Ridge Reservation

    International Nuclear Information System (INIS)

    Moline, G.R.; Schreiber, M.E.

    1996-03-01

    The goals of this project are to collect data that will assist in determining what constitutes a representative groundwater sample in fractured shale typical of much of the geology underlying the ORR waste disposal sites, and to determine how monitoring-well construction and sampling methods impact the representativeness of the sample. This report details the FY94 field activities at a research site in west Bear Creek Valley on the Oak Ridge Reservation (ORR). These activities funded by the Energy Systems Groundwater Program Office through the Oak Ridge Reservation Hydrologic and Geologic Studies (ORRHAGS) task, focus on developing appropriate sampling protocols for the type of fractured media that underlies many of the ORR waste disposal sites. Currently accepted protocols were developed for porous media and are likely to result in nonrepresentative samples in fractured systems

  15. Combining hydrology and mosquito population models to identify the drivers of Rift Valley fever emergence in semi-arid regions of West Africa.

    Science.gov (United States)

    Soti, Valérie; Tran, Annelise; Degenne, Pascal; Chevalier, Véronique; Lo Seen, Danny; Thiongane, Yaya; Diallo, Mawlouth; Guégan, Jean-François; Fontenille, Didier

    2012-01-01

    Rift Valley fever (RVF) is a vector-borne viral zoonosis of increasing global importance. RVF virus (RVFV) is transmitted either through exposure to infected animals or through bites from different species of infected mosquitoes, mainly of Aedes and Culex genera. These mosquitoes are very sensitive to environmental conditions, which may determine their presence, biology, and abundance. In East Africa, RVF outbreaks are known to be closely associated with heavy rainfall events, unlike in the semi-arid regions of West Africa where the drivers of RVF emergence remain poorly understood. The assumed importance of temporary ponds and rainfall temporal distribution therefore needs to be investigated. A hydrological model is combined with a mosquito population model to predict the abundance of the two main mosquito species (Aedes vexans and Culex poicilipes) involved in RVFV transmission in Senegal. The study area is an agropastoral zone located in the Ferlo Valley, characterized by a dense network of temporary water ponds which constitute mosquito breeding sites. The hydrological model uses daily rainfall as input to simulate variations of pond surface areas. The mosquito population model is mechanistic, considers both aquatic and adult stages and is driven by pond dynamics. Once validated using hydrological and entomological field data, the model was used to simulate the abundance dynamics of the two mosquito species over a 43-year period (1961-2003). We analysed the predicted dynamics of mosquito populations with regards to the years of main outbreaks. The results showed that the main RVF outbreaks occurred during years with simultaneous high abundances of both species. Our study provides for the first time a mechanistic insight on RVFV transmission in West Africa. It highlights the complementary roles of Aedes vexans and Culex poicilipes mosquitoes in virus transmission, and recommends the identification of rainfall patterns favourable for RVFV amplification.

  16. Combining hydrology and mosquito population models to identify the drivers of Rift Valley fever emergence in semi-arid regions of West Africa.

    Directory of Open Access Journals (Sweden)

    Valérie Soti

    Full Text Available BACKGROUND: Rift Valley fever (RVF is a vector-borne viral zoonosis of increasing global importance. RVF virus (RVFV is transmitted either through exposure to infected animals or through bites from different species of infected mosquitoes, mainly of Aedes and Culex genera. These mosquitoes are very sensitive to environmental conditions, which may determine their presence, biology, and abundance. In East Africa, RVF outbreaks are known to be closely associated with heavy rainfall events, unlike in the semi-arid regions of West Africa where the drivers of RVF emergence remain poorly understood. The assumed importance of temporary ponds and rainfall temporal distribution therefore needs to be investigated. METHODOLOGY/PRINCIPAL FINDINGS: A hydrological model is combined with a mosquito population model to predict the abundance of the two main mosquito species (Aedes vexans and Culex poicilipes involved in RVFV transmission in Senegal. The study area is an agropastoral zone located in the Ferlo Valley, characterized by a dense network of temporary water ponds which constitute mosquito breeding sites. The hydrological model uses daily rainfall as input to simulate variations of pond surface areas. The mosquito population model is mechanistic, considers both aquatic and adult stages and is driven by pond dynamics. Once validated using hydrological and entomological field data, the model was used to simulate the abundance dynamics of the two mosquito species over a 43-year period (1961-2003. We analysed the predicted dynamics of mosquito populations with regards to the years of main outbreaks. The results showed that the main RVF outbreaks occurred during years with simultaneous high abundances of both species. CONCLUSION/SIGNIFICANCE: Our study provides for the first time a mechanistic insight on RVFV transmission in West Africa. It highlights the complementary roles of Aedes vexans and Culex poicilipes mosquitoes in virus transmission, and recommends

  17. Tuberculosis Laboratory Diagnosis Quality Assurance among Public Health Facilities in West Amhara Region, Ethiopia.

    Science.gov (United States)

    Shiferaw, Melashu Balew; Hailu, Hiwot Amare; Fola, Abebe Alemu; Derebe, Mulatu Melese; Kebede, Aimro Tadese; Kebede, Abayneh Admas; Emiru, Manamnot Agegne; Gelaw, Zelalem Dessie

    2015-01-01

    Reliable smear microscopy is an important component of Directly Observed Treatment Scheme (DOTS) strategy for TB control program in countries with limited resources. Despite external quality assessment is established in Ethiopia, there is lower TB detection rate (48%) in Amhara region compared to the World Health Organization (WHO) estimate (70%). This highlights the quality of smear microscopy needs to be evaluated. Therefore, the aim of this study was to assess the quality of sputum smear microscopy performance among health center laboratories in West Amhara region, Ethiopia. A cross sectional study was conducted from July 08, 2013 to July 07, 2014. Data were collected from 201 public health center laboratories using a structured questionnaire. Slides were collected based on Lot Quality Assurance Sampling (LQAS) method and rechecked blindly by trained laboratory technologists. The data were entered into EPI info V.7 and smear quality indicators and AFB results were analyzed by SPSS version 20. Among 201 laboratories enrolled in this study, 47 (23.4%) laboratories had major errors. Forty one (20.4%) laboratories had a total of 67 false negative and 29 (14.4%) laboratories had a total of 68 false positive results. Specimen quality, smear thickness and evenness were found poor in 134 (66.7%), 133 (66.2%) and 126 (62.7%) laboratories, respectively. Unavailability of microscope lens cleaning solution (AOR: 2.90; 95% CI: 1.25-6.75; P: 0.013) and dirty smears (AOR: 2.65; 95% CI: 1.14-6.18; P: 0.024) were correlated with false negative results whereas no previous EQA participation (AOR: 3.43; 95% CI: 1. 39-8.45; P: 0.007) was associated with false positive results. The performance of health facilities for sputum smear microscopy was relatively poor in West Amhara region. Hence, strengthening the EQA program and technical support on sputum smear microscopy are recommended to ensure quality tuberculosis diagnostic service.

  18. Tuberculosis Laboratory Diagnosis Quality Assurance among Public Health Facilities in West Amhara Region, Ethiopia.

    Directory of Open Access Journals (Sweden)

    Melashu Balew Shiferaw

    Full Text Available Reliable smear microscopy is an important component of Directly Observed Treatment Scheme (DOTS strategy for TB control program in countries with limited resources. Despite external quality assessment is established in Ethiopia, there is lower TB detection rate (48% in Amhara region compared to the World Health Organization (WHO estimate (70%. This highlights the quality of smear microscopy needs to be evaluated. Therefore, the aim of this study was to assess the quality of sputum smear microscopy performance among health center laboratories in West Amhara region, Ethiopia.A cross sectional study was conducted from July 08, 2013 to July 07, 2014. Data were collected from 201 public health center laboratories using a structured questionnaire. Slides were collected based on Lot Quality Assurance Sampling (LQAS method and rechecked blindly by trained laboratory technologists. The data were entered into EPI info V.7 and smear quality indicators and AFB results were analyzed by SPSS version 20.Among 201 laboratories enrolled in this study, 47 (23.4% laboratories had major errors. Forty one (20.4% laboratories had a total of 67 false negative and 29 (14.4% laboratories had a total of 68 false positive results. Specimen quality, smear thickness and evenness were found poor in 134 (66.7%, 133 (66.2% and 126 (62.7% laboratories, respectively. Unavailability of microscope lens cleaning solution (AOR: 2.90; 95% CI: 1.25-6.75; P: 0.013 and dirty smears (AOR: 2.65; 95% CI: 1.14-6.18; P: 0.024 were correlated with false negative results whereas no previous EQA participation (AOR: 3.43; 95% CI: 1. 39-8.45; P: 0.007 was associated with false positive results.The performance of health facilities for sputum smear microscopy was relatively poor in West Amhara region. Hence, strengthening the EQA program and technical support on sputum smear microscopy are recommended to ensure quality tuberculosis diagnostic service.

  19. Heber Ethanol Fuel Facility, Imperial Valley, California. Quarterly report No. 2, March 1981-May 1981

    Energy Technology Data Exchange (ETDEWEB)

    1981-08-01

    The purposed project is a commercial-scale ethanol-fuel facility with a capacity of twenty million gallons per year of fuel-grade ethanol. In addition, 70,000 tons per year of distillers dried grains will be produced. The following tasks and issues are addressed: process engineering - process descriptions, plant layout, and design; economics and finance - overview of capital and operating costs; environmental analysis - preliminary project description; and permit processing and legal issues. (MHR)

  20. Rock-avalanche dynamics revealed by large-scale field mapping and seismic signals at a highly mobile avalanche in the West Salt Creek valley, western Colorado

    Science.gov (United States)

    Coe, Jeffrey A.; Baum, Rex L.; Allstadt, Kate E.; Kochevar, Bernard; Schmitt, Robert G.; Morgan, Matthew L.; White, Jonathan L.; Stratton, Benjamin T.; Hayashi, Timothy A.; Kean, Jason W.

    2016-01-01

    On 25 May 2014, a rain-on-snow–induced rock avalanche occurred in the West Salt Creek valley on the northern flank of Grand Mesa in western Colorado (United States). The avalanche mobilized from a preexisting rock slide in the Green River Formation and traveled 4.6 km down the confined valley, killing three people. The avalanche was rare for the contiguous United States because of its large size (54.5 Mm3) and high mobility (height/length = 0.14). To understand the avalanche failure sequence, mechanisms, and mobility, we conducted a forensic analysis using large-scale (1:1000) structural mapping and seismic data. We used high-resolution, unmanned aircraft system imagery as a base for field mapping, and analyzed seismic data from 22 broadband stations (distances earth and tracked these forces using curves in the avalanche path. Our results revealed that the rock avalanche was a cascade of landslide events, rather than a single massive failure. The sequence began with an early morning landslide/debris flow that started ∼10 h before the main avalanche. The main avalanche lasted ∼3.5 min and traveled at average velocities ranging from 15 to 36 m/s. For at least two hours after the avalanche ceased movement, a central, hummock-rich core continued to move slowly. Since 25 May 2014, numerous shallow landslides, rock slides, and rock falls have created new structures and modified avalanche topography. Mobility of the main avalanche and central core was likely enhanced by valley floor material that liquefied from undrained loading by the overriding avalanche. Although the base was likely at least partially liquefied, our mapping indicates that the overriding avalanche internally deformed predominantly by sliding along discrete shear surfaces in material that was nearly dry and had substantial frictional strength. These results indicate that the West Salt Creek avalanche, and probably other long-traveled avalanches, could be modeled as two layers: a thin, liquefied

  1. Tennessee Valley region study: potential year 2000 radiological dose to population resulting from nuclear facility operations. [Includes glossary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-06-01

    A companion report, DOE/ET-0064/1, presents a geographic, cultural, and demographic profile of the Tennessee Valley Region study area. This report describes the calculations of radionuclide release and transport and of the resultant dose to the regional population, assuming a projected installed capacity of 220,000 MW in the year 2000, of which 144,000 MW would be nuclear. All elements of the fuel cycle were assumed to be in operation. The radiological dose was calculated as a one-year dose based on ingestion of 35 different food types as well as for nine non-food pathways, and was reported as dose to the total body and for six specific organs for each of four age groups (infant, child, teen, and adult). Results indicate that the average individual would receive an incremental dose of 7 x 10/sup -4/ millirems in the year 2000 from the operation of nuclear facilities within and adjacent to the region, five orders of magnitude smaller than the dose from naturally occurring radiation in the area. The major contributor to dose was found to be tritium, and the most significant pathways were immersion in air, inhalation of air, transpiration of tritium (absorption through the skin), and exposure radionuclide-containing soil. 60 references.

  2. Feeding the nuclear fuel cycle with a long term view; AREVA's front-end business units, uranium mining, UF6 conversion and isotopic enrichment

    International Nuclear Information System (INIS)

    Capus, G.A.P.; Autegert, R.

    2005-01-01

    As a leading provider of technological solutions for nuclear power generation and electricity transmission, the AREVA group has the unique capability of offering a fully integrated fuel supply, when requested by its customers. At the core of the AREVA group, COGEMA Front End Division is an essential part of the overall fuel supply chain. Composed of three Business Units and gathering several subsidiaries and joint 'ventures, this division enjoys several leading positions as shown by its market shares and historical production records. Current Uranium market evolutions put the natural uranium supply under focus. The uranium conversion segment also recently revealed some concerning evolutions. And no doubt, the market pressure will soon be directed also at the enrichment segment. Looking towards the long term, AREVA strongly believes that a nuclear power renewal is needed, especially to help limiting green house effect gas release. Therefore, to address future supplies needed to fuel the existing fleet of nuclear power plants, but also new ones, the AREVA group is planning very significant investments to build new facilities in all the three front-end market segments. As far as uranium mining is concerned, these new mines will be based upon uranium reserves of outstanding quality. As for uranium conversion and enrichment, two large projects will be based on the most advanced technologies. This paper is aimed at recalling COGEMA Front End Division experience, the current status of its plants and operating entities and will provide a detailed overview of its major projects. (authors)

  3. Technology, safety and costs of decommissioning reference nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Elder, H.K.

    1986-05-01

    The radioactive wastes expected to result from decommissioning nuclear fuel cycle facilities are reviewed and classified in accordance with 10 CFR 61. Most of the wastes from the MOX plant (exclusive of the lagoon wastes) will require interim storage (11% Class A 49 m 3 ; 89% interim storage, 383 m 3 ). The MOX plant lagoon wastes are Class A waste (2930 m 3 ). All of the wastes from the U-Fab and UF 6 plants are designated as Class A waste (U-Fab 1090 m 3 , UF 6 1259 m 3 )

  4. Ground-water hydrology and subsurface migration of radioisotopes at a low-level solid radioactive-waste disposal site, West Valley, New York

    International Nuclear Information System (INIS)

    Prudic, D.E.; Randall, A.D.

    1979-01-01

    Burial trenches for disposal of solid radioactive waste at West Valley, NY, are excavated in till that has very low hydraulic conductivity (about 5 x 10 -8 centimeters per second). Fractures and root tubes with chemically oxidized and/or reduced soil in their walls extend 3 to 4.5 meters below natural land surface. Preliminary simulations of pressure heads with a digital model suggest that hydraulic conductivity is an order of magnitude greater in the fractured till near land surface than at greater depth. Hydraulic gradients are predominantly downward, even beneath small valleys. The upper part of a body of underlying lacustrine silt is unsaturated; in the lower, saturated part, slow lateral flow may occur. In the older trenches, water began to build up in 1971, overflowed briefly in 1975, and was pumped out in 1975--76. Water levels rose abruptly during major rainstorms in mid-1975, indicating rapid infiltration through cracks in the cover material. The new trenches have maintained low, stable water levels, perhaps because of thicker, more compact cover and less waste settlement; pressure heads near these trenches are low, locally approaching zero, perhaps because of slight infiltration and limited near-surface storage. Peak tritium concentrations in test-hole cores (generally 10 -5 to 10 -3 microcuries per milliliter) were found within 3 meters of land surface and are attributed to surface contamination. Concentrations declined rapidly with depth within the fractured till; secondary peaks found at about 9 meters in three holes are attributed to lateral migration from trenches. Other radioisotopes were detected only near land surface. Samples from the walls of shallow fractures revealed no accumulation of radioisotopes

  5. Ground-water hydrology and subsurface migration of radioisotopes at a low-level solid radioactive-waste disposal site, West Valley, New York

    International Nuclear Information System (INIS)

    Prudic, D.E.; Randall, A.D.

    1977-07-01

    Burial trenches for disposal of solid radioactive waste at West Valley, N.Y. are excavated in till that has very low hydraulic conductivity (about 5 x 10 -8 centimeters per second). Fractures and root tubes with chemically oxidized and(or) reduced soil in their walls extend 3 to 4.5 meters below natural land surface. Preliminary simulations of pressure heads with a digital model suggest that hydraulic conductivity is an order of magnitude greater in the fractured till near land surface than at greater depth. Hydraulic gradients are predominantly downward, even beneath small valleys. The upper part of a body of underlying lacustrine silt is unsaturated; in the lower, saturated part, slow lateral flow may occur. In the older trenches, water began to build up in 1971, overflowed briefly in 1975, and was pumped out in 1975--76. Water levels rose abruptly during major rainstorms in mid-1975, indicating rapid infiltration through cracks in the cover material. The new trenches have maintained low, stable water levels, perhaps because of thicker, more compact cover and less waste settlement; pressure heads near these trenches are low, locally approaching zero, perhaps because of slight infiltration and limited near-surface storage. Peak tritium concentrations in test-hole cores (generally 10 -5 to 10 -3 microcuries per milliliter) were found within 3 meters of land surface and are attributed to surface contamination. Concentrations declined rapidly with depth within the fractured till; secondary peaks found at about 9 meters in three holes are attributed to lateral migration from trenches. Other radioisotopes were detected only near land surface. Samples from the walls of shallow fractures revealed no accumulation of radioisotopes

  6. Criticality safety strategy for the Fuel Cycle Facility electrorefiner at Argonne National Laboratory, West

    International Nuclear Information System (INIS)

    Mariani, R.D.; Benedict, R.W.; Lell, R.M.; Turski, R.B.; Fujita, E.K.

    1993-01-01

    The Integral Fast Reactor being developed by Argonne National Laboratory (ANL) combines the advantages of metal-fueled, liquid-metal-cooled reactors and a closed fuel cycle. Presently, the Fuel Cycle Facility (FCF) at ANL-West in Idaho Falls, Idaho is being modified to recycle spent metallic fuel from Experimental Breeder Reactor II as part of a demonstration project sponsored by the Department of Energy. A key component of the FCF is the electrorefiner (ER) in which the actinides are separated from the fission products. In the electrorefining process, the metal fuel is anodically dissolved into a high-temperature molten salt and refined uranium or uranium/plutonium products are deposited at cathodes. In this report, the criticality safety strategy for the FCF ER is summarized. FCF ER operations and processes formed the basis for evaluating criticality safety and control during actinide metal fuel refining. In order to show criticality safety for the FCF ER, the reference operating conditions for the ER had to be defined. Normal operating envelopes (NOES) were then defined to bracket the important operating conditions. To keep the operating conditions within their NOES, process controls were identified that can be used to regulate the actinide forms and content within the ER. A series of operational checks were developed for each operation that wig verify the extent or success of an operation. The criticality analysis considered the ER operating conditions at their NOE values as the point of departure for credible and incredible failure modes. As a result of the analysis, FCF ER operations were found to be safe with respect to criticality

  7. Precipitation and runoff simulations of select perennial and ephemeral watersheds in the middle Carson River basin, Eagle, Dayton, and Churchill Valleys, west-central Nevada

    Science.gov (United States)

    Jeton, Anne E.; Maurer, Douglas K.

    2011-01-01

    The effect that land use may have on streamflow in the Carson River, and ultimately its impact on downstream users can be evaluated by simulating precipitation-runoff processes and estimating groundwater inflow in the middle Carson River in west-central Nevada. To address these concerns, the U.S. Geological Survey, in cooperation with the Bureau of Reclamation, began a study in 2008 to evaluate groundwater flow in the Carson River basin extending from Eagle Valley to Churchill Valley, called the middle Carson River basin in this report. This report documents the development and calibration of 12 watershed models and presents model results and the estimated mean annual water budgets for the modeled watersheds. This part of the larger middle Carson River study will provide estimates of runoff tributary to the Carson River and the potential for groundwater inflow (defined here as that component of recharge derived from percolation of excess water from the soil zone to the groundwater reservoir). The model used for the study was the U.S. Geological Survey's Precipitation-Runoff Modeling System, a physically based, distributed-parameter model designed to simulate precipitation and snowmelt runoff as well as snowpack accumulation and snowmelt processes. Models were developed for 2 perennial watersheds in Eagle Valley having gaged daily mean runoff, Ash Canyon Creek and Clear Creek, and for 10 ephemeral watersheds in the Dayton Valley and Churchill Valley hydrologic areas. Model calibration was constrained by daily mean runoff for the 2 perennial watersheds and for the 10 ephemeral watersheds by limited indirect runoff estimates and by mean annual runoff estimates derived from empirical methods. The models were further constrained by limited climate data adjusted for altitude differences using annual precipitation volumes estimated in a previous study. The calibration periods were water years 1980-2007 for Ash Canyon Creek, and water years 1991-2007 for Clear Creek. To

  8. Cosmogenic 10Be ages from the Meirs and Garwood Valleys, Denton Hills, West Antarctica, suggest an absence in LGM Ice Sheet expansion.

    Science.gov (United States)

    Fink, David; Joy, Kurt; Storey, Bryan

    2014-05-01

    It has been hypothesised that during interglacials, thinning of the Ross Ice Shelf allowed a more open water environment with increased local precipitation. This resulted in outlet glaciers, which drain the Transantarctic Mountains and fed by the East Antarctic Ice Sheet, advancing during moist warmer periods, apparently out of phase with colder arid dry periods. Significantly the ice core record during these warm periods also shows increased accumulation continent wide The geomorphology of the Denton Hills in the Royal Society Range, West Antarctica, is a result of Miocene fluvial incision reworked by subsequent glacial advances throughout the Quaternary. The Garwood and Miers glacial valleys drain ice across the Denton Hills into the Shelf, and should thus show maximum extent during interstadials. To understand the chronology of late Quaternary glaciations, 15 granitic boulders from terminal moraines were sampled for 10Be and 26Al cosmogenic dating. Obtaining reliable exposure ages of erratics within moraines that represent timing of deposition (i.e. glacial advances) is problematic in polar regions, where glacial activity is principally controlled by ice sheet dynamics. Recycling of previously exposed debris, uncertainty in provenance of glacially transported boulders and a lack of a post-depositional hydrologic process to remove previously exposed material from a valley system, leads to ambiguities in multiple exposure ages from a single coeval glacial landform. More importantly, cold-based ice advance can leave a landform unmodified resulting in young erratics deposited on bedrock that shows weathering and/or inconsistent age-altitude relationships. Primarily, inheritance becomes a difficulty in qualifying exposure ages from polar regions. Preliminary results from the Garwood and Miers Valleys indicate that glaciers in the Denton Hills had begun to retreat from their last maximum positions no later than 23-37 ka, and thus the local last glacial maximum

  9. Surficial geologic map of the Heath-Northfield-Southwick-Hampden 24-quadrangle area in the Connecticut Valley region, west-central Massachusetts

    Science.gov (United States)

    Stone, Janet R.; DiGiacomo-Cohen, Mary L.

    2010-01-01

    The surficial geologic map layer shows the distribution of nonlithified earth materials at land surface in an area of 24 7.5-minute quadrangles (1,238 mi2 total) in west-central Massachusetts. Across Massachusetts, these materials range from a few feet to more than 500 ft in thickness. They overlie bedrock, which crops out in upland hills and as resistant ledges in valley areas. The geologic map differentiates surficial materials of Quaternary age on the basis of their lithologic characteristics (such as grain size and sedimentary structures), constructional geomorphic features, stratigraphic relationships, and age. Surficial materials also are known in engineering classifications as unconsolidated soils, which include coarse-grained soils, fine-grained soils, and organic fine-grained soils. Surficial materials underlie and are the parent materials of modern pedogenic soils, which have developed in them at the land surface. Surficial earth materials significantly affect human use of the land, and an accurate description of their distribution is particularly important for assessing water resources, construction aggregate resources, and earth-surface hazards, and for making land-use decisions. This work is part of a comprehensive study to produce a statewide digital map of the surficial geology at a 1:24,000-scale level of accuracy. This report includes explanatory text, quadrangle maps at 1:24,000 scale (PDF files), GIS data layers (ArcGIS shapefiles), metadata for the GIS layers, scanned topographic base maps (TIF), and a readme.txt file.

  10. Development of the West Virginia University Small Microgravity Research Facility (WVU SMiRF)

    Science.gov (United States)

    Phillips, Kyle G.

    West Virginia University (WVU) has created the Small Microgravity Research Facility (SMiRF) drop tower through a WVU Research Corporation Program to Stimulate Competitive Research (PSCoR) grant on its campus to increase direct access to inexpensive and repeatable reduced gravity research. In short, a drop tower is a tall structure from which experimental payloads are dropped, in a controlled environment, and experience reduced gravity or microgravity (i.e. "weightlessness") during free fall. Currently, there are several methods for conducting scientific research in microgravity including drop towers, parabolic flights, sounding rockets, suborbital flights, NanoSats, CubeSats, full-sized satellites, manned orbital flight, and the International Space Station (ISS). However, none of the aforementioned techniques is more inexpensive or has the capability of frequent experimentation repeatability as drop tower research. These advantages are conducive to a wide variety of experiments that can be inexpensively validated, and potentially accredited, through repeated, reliable research that permits frequent experiment modification and re-testing. Development of the WVU SMiRF, or any drop tower, must take a systems engineering approach that may include the detailed design of several main components, namely: the payload release system, the payload deceleration system, the payload lifting and transfer system, the drop tower structure, and the instrumentation and controls system, as well as a standardized drop tower payload frame for use by those researchers who cannot afford to spend money on a data acquisition system or frame. In addition to detailed technical development, a budgetary model by which development took place is also presented throughout, summarized, and detailed in an appendix. After design and construction of the WVU SMiRF was complete, initial calibration provided performance characteristics at various payload weights, and full-scale checkout via

  11. Assessment of UF6 Equation of State

    Energy Technology Data Exchange (ETDEWEB)

    Brady, P; Chand, K; Warren, D; Vandersall, J

    2009-02-11

    A common assumption in the mathematical analysis of flows of compressible fluids is to treat the fluid as a perfect gas. This is an approximation, as no real fluid obeys the perfect gas relationships over all temperature and pressure conditions. An assessment of the validity of treating the UF{sub 6} gas flow field within a gas centrifuge with perfect gas relationships has been conducted. The definition of a perfect gas is commonly stated in two parts: (1) the gas obeys the thermal equation of state, p = {rho}RT (thermally perfect), and, (2) the gas specific heats are constant (calorically perfect). Analysis indicates the thermally perfect assumption is valid for all flow conditions within the gas centrifuge, including shock fields. The low operating gas pressure is the primary factor in the suitability of the thermally perfect equation of state for gas centrifuge computations. UF{sub 6} is not calorically perfect, as the specific heats vary as a function of temperature. This effect is insignificant within the bulk of the centrifuge gas field, as gas temperatures vary over a narrow range. The exception is in the vicinity of shock fields, where temperature, pressure, and density gradients are large, and the variation of specific heats with temperature should be included in the technically detailed analyses. Results from a normal shock analysis incorporating variable specific heats is included herein, presented in the conventional form of shock parameters as a function of inlet Mach Number. The error introduced by assuming constant specific heats is small for a nominal UF{sub 6} shock field, such that calorically perfect shock relationships can be used for scaling and initial analyses. The more rigorous imperfect gas analysis should be used for detailed analyses.

  12. Final Environmental Statement related to the decommissioning of the Rare Earths Facility, West Chicago, Illinois. Docket No. 40-2061

    International Nuclear Information System (INIS)

    1983-05-01

    This Final Environmental Statement is issued by the US Nuclear Regulatory Commission in response to the plan proposed by Kerr-McGee Chemical Corporation for the decommissioning of their Rare Earths Facility located in West Chicago, Illinois. The statement considers the Kerr-McGee preferred plan and various alternatives to that plan. The action proposed by the Commission is the renewal of the Kerr-McGee license to allow stabilization of wastes onsite and for possession of the wastes under license for an indeterminate time. The license could be terminated at a later date if certain specified requirements were met

  13. Re-emergence of Rift Valley fever virus in Barkedji (Senegal, West Africa) in 2002-2003: identification of new vectors and epidemiological implications.

    Science.gov (United States)

    Ba, Y; Sall, A A; Diallo, D; Mondo, M; Girault, L; Dia, I; Diallo, M

    2012-09-01

    The Rift Valley fever virus (RVFV) is a threat that must not be neglected, as the consequences of RVFV are dramatic, both for human and animal health. This virus is a zoonotic virus that already has demonstrated a real capacity for re-emerging after long periods of silence, as observed in Barkedji (Senegal, West Africa) in 2002. In this article we present the 2nd emergence in Barkedji after the 1st manifestation in 1993, and for the 1st time the circulation of RVFV during 2 consecutive years among mosquito populations in Senegal. As part of the entomological surveillance program undertaken since 1990 to detect circulation of the RVFV in Barkedji, 108,336 mosquitoes belonging to 34 species and 5 genera were collected in 2002-2003. Aedes vexans and Culex poicilipes, previously known to be vectors of RVFV in Senegal, comprised 88.7% of the total collection. In 2002, Ae. vexans was the most abundant mosquito, followed by Cx. poicilipes; the opposite situation was observed in 2003. In 2002, 29 and 10 RVFV isolates were obtained from Cx. poicilipes (minimum infection rate [MIR] = 0.13%) and Ae. vexans (MIR = 0.02%) pools, respectively and the MIR for the 2 species were significantly different (chi2 = 34.65; df = 1, P < 0.001). In 2003, 7 RVFV strains were isolated from Cx. poicilipes (3, MIR = 0.03), Mansonia africana (2, MIR = 0.08), Ae. fowleri (1), and Ma. uniformis (1, MIR = 0.05). The 3 latter species were found to be associated with RVFV for the 1st time in Senegal. A significant decrease in MIR was observed from 2002 to 2003 (chi2 6.28; df = 1, P = 0.01) for Cx. poicilipes, the only species involved in the transmission during the 2 sampling years.

  14. Decontamination of the chemical crane room and decontamination and decommissioning of the extraction chemical room at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Phillips, E.C.; Golden, M.P.

    1986-01-01

    This paper describes the decontamination of the Chemical Crane Room (CCR) of the West Valley Plant and the Extraction Chemical Room (XCR) from radioactively contaminated conditions to essentially shirt sleeve environments. In both cases, subsequent use re-contaminated the rooms. Prior to decontamination, general exposure rates in the CCR were 50 to 100 mR/hr with hot spots as high as 2000 mR/hr. Smearable levels on the floor were in the range of 10 5 to 10 6 dpm per 100/cm 2 . Respiratory protection was mandatory for entry. In the Extraction Chemical Room (XCR) prior to decontamination and decommissioning (D/D), radiological surveys indicated a maximum radiation field of 5 mR/hr, due to sources internal to the room, and 20,000 dpm beta/100 cm 2 surface contamination. A radiation source external to the XCR caused a hot spot with a 9 mR/hr exposure rate inside the XCR. The CCR, located at the north end of the Chemical Process Cell (CPC) is for the storage and servicing of two bridge cranes used in the CPC. Decontamination and exposure reduction in the CCR has been completed using vacuum cleaning, damp wipe down, and surface grinding followed by shielding and painting. The decontamination and decommissioning of the Extraction Chemical Room (XCR), located on the fifth floor elevation (160') of the reprocessing plant at the WVDP, has been completed. D/D operations included removal of piping, tanks, supports, and equipment to provide a clean work area of about 3000 square feet and 17 feet high

  15. 76 FR 11259 - Notice of Intent To Prepare an Environmental Impact Statement for the Proposed Rasmussen Valley...

    Science.gov (United States)

    2011-03-01

    ... operation, a small support staging facility would be constructed at the active mining site immediately west... cooperating agency. The mining and reclamation plans have been developed and submitted for agency review of proposed open pit mining operations at the Rasmussen Valley Phosphate Federal Mineral Lease I-05975, in...

  16. Computer software configuration management plan for 200 East/West Liquid Effluent Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Graf, F.A. Jr.

    1995-02-27

    This computer software management configuration plan covers the control of the software for the monitor and control system that operates the Effluent Treatment Facility and its associated truck load in station and some key aspects of the Liquid Effluent Retention Facility that stores condensate to be processed. Also controlled is the Treated Effluent Disposal System`s pumping stations and monitors waste generator flows in this system as well as the Phase Two Effluent Collection System.

  17. Computer software configuration management plan for 200 East/West Liquid Effluent Facilities

    International Nuclear Information System (INIS)

    Graf, F.A. Jr.

    1995-01-01

    This computer software management configuration plan covers the control of the software for the monitor and control system that operates the Effluent Treatment Facility and its associated truck load in station and some key aspects of the Liquid Effluent Retention Facility that stores condensate to be processed. Also controlled is the Treated Effluent Disposal System's pumping stations and monitors waste generator flows in this system as well as the Phase Two Effluent Collection System

  18. Aerial radiological survey of the United States Department of Energy's Battelle Nuclear Science Facility, West Jefferson, Ohio, date of survey: May 1977

    International Nuclear Information System (INIS)

    Feimster, E.L.

    1979-05-01

    An aerial radiological survey to measure terrestrial gamma radiation was carried out over the United States Department of Energy's Battelle Nuclear Science Facility located in West Jefferson, Ohio. Gamma ray data were collected over a 5.5 km 2 area centered on the facility by flying east-west lines spaced 61 m apart. Processed data indicated that on-site radioactivity was primarily due to radionuclides currently being processed due to the hot lab operations. Off-site data showed the radioactivity to be due to naturally occurring background radiation consistent with variations due to geologic base terrain and land use of similar areas

  19. Bench-scale treatability testing of biological, UV oxidation, distillation, and ion-exchange treatment of trench water from a low-level radioactive waste disposal area at West Valley, New York

    Energy Technology Data Exchange (ETDEWEB)

    Sundquist, J.A.; Gillings, J.C. [Ecology and Environment, Inc. (United States); Sonntag, T.L. [New York State Energy Research and Development Authority (United States); Denault, R.P. [Pacific Nuclear, Inc. (United States)

    1993-03-01

    Ecology and Environment, Inc. (E and E), under subcontract to Pacific Nuclear Services (PNS), conducted for the New York State Energy Research and Development Authority (NYSERDA) treatability tests to support the selection and design of a treatment system for leachate from Trench 14 of the West Valley State-Licensed, Low-Level Radioactive Waste Disposal Area (SDA). In this paper E and E presents and discusses the treatability test results and provides recommendations for the design of the full-scale treatment system.

  20. Practice of using the educational facilities in some West-European countries

    International Nuclear Information System (INIS)

    Elagin, Yu.P.

    1995-01-01

    A review deals with results on using multifunctional educational facilities, choice of their optimal number with simulation of NPP sites in European countries. The role of instructors, the content of educational program, tasks of individual retraining are considered. Cost benefit analysis is made. 5 refs

  1. Geotechnical analysis of soil samples and study of a research trench at the Western New York Nuclear Service Center, West Valley, New York. Topical report 1 Oct 78-14 Feb 80

    International Nuclear Information System (INIS)

    Hoffman, V.C.; Fickies, R.H.; Dana, R.H. Jr; Ragan, V.

    1980-10-01

    This report is the result of a study which was the second part of an investigation, involving geotechnical analysis of soil samples from the West Valley burial site with respect to containment capability. In general, the results of standard engineering tests in soil from the West Valley site confirm the results predicted by testing performed during the first part of this study in 1977. The soil was submerged for almost 2 years and samples showed some increase in moisture content accompanied by a decrease in unit weight. Changes in the plasticity of the soil during this period were not significant, however, shrinkage limits were significantly different from earlier tests. This is probably attributable to a difference in testing procedure. The minimum developed cohesion for the soil in the wall Research Trench 111 was estimated to be 18.9kN/sq meters. In shallow softened soils the developed cohesion at failure under submerged conditions was estimated to be 2.54N/sq meters and failure under sudden drawdown conditions was estimated to be 4.79kN/sq meters

  2. Report on toxicological studies concerning exposures to UF6 and UF6 hydrolysis products

    International Nuclear Information System (INIS)

    Just, R.A.

    1984-07-01

    This report presents estimates of the toxicity of uranium and hydrogen fluoride. Recommendations for the use of this information in safety analysis reports are given. 6 references, 2 figures, 4 tables

  3. Selenium in ecosystems within the mountaintop coal mining and valley-fill region of southern West Virginia-assessment and ecosystem-scale modeling

    Science.gov (United States)

    Presser, Theresa S.

    2013-01-01

    Coal and associated waste rock are among environmental selenium (Se) sources that have the potential to affect reproduction in fish and aquatic birds. Ecosystems of southern West Virginia that are affected by drainage from mountaintop coal mines and valleys filled with waste rock in the Coal, Gauley, and Lower Guyandotte watersheds were assessed during 2010 and 2011. Sampling data from earlier studies in these watersheds (for example, Upper Mud River Reservoir) and other mining-affected watersheds also are included to assess additional hydrologic settings and food webs for comparison. Basin schematics give a comprehensive view of sampled species and Se concentration data specific to location and date. Food-web diagrams document the progression of Se trophic transfer across suspended particulate material, invertebrates, and fish for each site to serve as the basis for developing an ecosystem-scale model to predict Se exposure within the hydrologic conditions and food webs of southern West Virginia. This approach integrates a site-specific predator’s dietary exposure pathway into modeling to ensure an adequate link to Se toxicity and, thus, to species vulnerability. Site-specific fish abundance and richness data in streams documented various species of chub, shiner, dace, darters, bass, minnow, sunfish, sucker, catfish, and central stoneroller (Campostoma anomalum), mottled sculpin (Cottus bairdii), and least brook lamprey (Lampetra aepyptera). However, Se assessment species for streams, and hence, model species for streams, were limited to creek chub (Semotilus atromaculatus) and central stoneroller. Both of these species of fish are generally considered to have a high tolerance for environmental stress based on traditional comparative fish community assessment, with creek chub being present at all sites. Aquatic insects (mayfly, caddisfly, stonefly, dobsonfly, chironomid) were the main invertebrates sampled in streams. Collection of suspended particulate material

  4. Fire hazards analysis for W-413, West Area Tank Farm Storage and Staging Facility

    International Nuclear Information System (INIS)

    Huckfeldt, R.A.; Lott, D.T.

    1994-01-01

    In accordance with DOE Order 5480.7A, a Fire Hazards Analysis must be performed for all new facilities. The purpose of the analysis is to comprehensively assess the risk from fire within individual fire areas in relation to proposed fire protection so as to ascertain whether the fire protection objectives of the Order are met. The Order acknowledges a graded approach commensurate with the hazards involved. Tank Farms Operations must sore/stage material and equipment such as pipes, fittings, conduit, instrumentation and others related items until work packages are ready to work. Consumable materials, such as nut, bolts and welding rod, are also requires to be stored for routine and emergency work. Connex boxes and open storage is currently used for much of the storage because of the limited space at and 272WA. Safety issues based on poor housekeeping and material deteriorating due to weather damage has resulted from this inadequate storage space. It has been determined that a storage building in close proximity to the Tank Farm work force would be cost effective. This facility is classified as a safety class 4 building

  5. Classification of High-Rise Residential Building Facilities: A Descriptive Survey on 170 Housing Scheme in Klang Valley

    OpenAIRE

    Abd Wahab Siti Rashidah Hanum; Che Ani Adi Irfan; Sairi Ahmad; Mohd Tawil Norngainy; Abd Razak Mohd Zulhanif

    2016-01-01

    High-rise residential building is a type of housing that has multi-dwelling units built on the same land. This type of housing has become popular each year in urban area due to the increasing cost of land. There are several common facilities provided in high-rise residential building. For example playground, swimming pool, gymnasium, 24 hours security system such as CCTV, access card and so on. Thus, maintenance works of the common facilities must be well organised. The purpose of this paper ...

  6. Effects of land use changes on water and nitrogen flows at the scale of West African inland valleys: an explorative model.

    NARCIS (Netherlands)

    Ridder, de N.; Stomph, T.J.; Fresco, L.O.

    1997-01-01

    Land use and cover, as influenced by agricultural practices, and the changes in these with increasing pressure on land, are among the factors determining water flows in inland valleys. Changing water flows affect nitrogen flows both at the plot level and at levels higher than plots. We present a

  7. ESARDA approach to facility oriented safeguards problems

    International Nuclear Information System (INIS)

    Stewart, R.

    1979-01-01

    The paper outlines the brief history of a Working Group composed of nuclear fuel plant operators, safeguards research workers and safeguards inspectors who are examining facility orientated problems of nuclear materials control and verification activities. The working program is reviewed together with some examples of various problems and the way the group is collaborating to develop solutions by pooling resources and effort. Work in European low enriched uranium fabrication plants from UF 6 to finished fuel is discussed in connection with mesurement practices, real time accounting, error propagation and analysis, verification and surveillance

  8. Radionuclide migration pathways analysis for the Oak Ridge Central Waste Disposal Facility on the West Chestnut Ridge site

    International Nuclear Information System (INIS)

    Pin, F.G.; Witherspoon, J.P.; Lee, D.W.; Cannon, J.B.; Ketelle, R.H.

    1984-10-01

    A dose-to-man pathways analysis is performed for disposal of low-level radioactive waste at the Central Waste Disposal Facility on the West Chestnut Ridge Site. Both shallow land burial (trench) and aboveground (tumulus) disposal methods are considered. The waste volumes, characteristics, and radionuclide concentrations are those of waste streams anticipated from the Oak Ridge National Laboratory, the Y-12 Plant, and the Oak Ridge Gaseous Diffusion Plant. The site capacity for the waste streams is determined on the basis of the pathways analysis. The exposure pathways examined include (1) migration and transport of leachate from the waste disposal units to the Clinch River (via the groundwater medium for trench disposal and Ish Creek for tumulus disposal) and (2) those potentially associated with inadvertent intrusion following a 100-year period of institutional control: an individual resides on the site, inhales suspended particles of contaminated dust, ingests vegetables grown on the plot, consumes contaminated water from either an on-site well or from a nearby surface stream, and receives direct exposure from the contaminated soil. It is found that either disposal method would provide effective containment and isolation for the anticipated waste inventory. However, the proposed trench disposal method would provide more effective containment than tumuli because of sorption of some radionuclides in the soil. Persons outside the site boundary would receive radiation doses well below regulatory limits if they were to ingest water from the Clinch River. An inadvertent intruder could receive doses that approach regulatory limits; however, the likelihood of such intrusions and subsequent exposures is remote. 33 references, 31 figures, 28 tables

  9. Mathematics in energy related research at the Tennessee Valley Authority, at Union Carbide's Oak Ridge Facilities, and at University of Tennessee College of Engineering. Final report

    International Nuclear Information System (INIS)

    Barett, L.K.

    1979-05-01

    This report contains a description of the work performed under the Department of Energy Contract No. ER078-S-05-5944 to the University of Tennessee. The major objective of this contract was to survey and to classify a selection of the mathematics used in energy-related activities at the Tennessee Valley Authority (TVA), at Union Carbide's Oak Ridge Facilities (UCORF), and at the University of Tennessee College of Engineering (UTCE). Eighty-seven projects were identified at these organizations in which mathematics plays a significant modeling or problem-solving role. Uniform abstracts of these projects are included in this report, as well as abstracts of twenty-seven presentations by TVA and UCORF personnel on the topic of mathematics in energy research, at the 1978 Fall SIAM meeting. Classifications of these one hundred and fourteen abstracts are given in terms of the energy area or function involved and in terms of the mathematical disciplines used in the activity. Only a selection of the mathematical activity at the TVA, UCORF, and UTCE involved in energy research was obtained due to time and budget constraints. However, it was possible to make some important observations and recommendations based upon these sample data, and these are included in the summary of this report

  10. An assessment of the effectiveness of personal visual observation for a uranium enrichment facility (2)

    International Nuclear Information System (INIS)

    Bando, Masatsugu; Okamoto, Tsuyoshi

    2003-01-01

    In a centrifuge uranium enrichment facility, a large number of unit cascades are operated to produce low enriched uranium for nuclear power reactors. Some thousands of UF 6 gas centrifuges are installed in unit cascade. If a new type of advanced centrifuge is developed in the near future, the number of stages and UF 6 gas centrifuges in the unit cascade would decrease dramatically. Furthermore, an integrated type of centrifuge, which is composed of a few tens of centrifuges, is adopted from the point of economic view, the piping arrangement among UF 6 gas centrifuges can be more simplified. It can be said that the simpler the piping arrangement, the less the operation time we are required to make any diverted cascade with the help of re-arrangement of the unit cascade piping. When two type of centrifuge, conventional and advanced centrifuge are used in the uranium enrichment facility, we predicted an inspection effort of personal visual observation for inspector by Game Theory. In our mathematical model, an activity of inspection in a cascade area is simplified into two-person non-cooperative game between inspector and facility operator. As a result of our calculation, it became clear that total inspection effort is likely to increase unless the integrated type of centrifuge is installed. (author)

  11. Hydrogeologic data and water-quality data from a thick unsaturated zone at a proposed wastewater-treatment facility site, Yucca Valley, San Bernardino County, California, 2008-11

    Science.gov (United States)

    O'Leary, David; Clark, Dennis A.; Izbicki, John A.

    2015-01-01

    The Hi-Desert Water District, in the community of Yucca Valley, California, is considering constructing a wastewater-treatment facility and using the reclaimed water to recharge the aquifer system through surface spreading. The Hi-Desert Water District is concerned with possible effects of this recharge on water quality in the underlying groundwater system; therefore, an unsaturated-zone monitoring site was constructed by the U.S. Geological Survey (USGS) to characterize the unsaturated zone, monitor a pilot-scale recharge test, and, ultimately, to monitor the flow of reclaimed water to the water table once the treatment facility is constructed.

  12. Groundwater-level change and evaluation of simulated water levels for irrigated areas in Lahontan Valley, Churchill County, west-central Nevada, 1992 to 2012

    Science.gov (United States)

    Smith, David W.; Buto, Susan G.; Welborn, Toby L.

    2016-09-14

    The acquisition and transfer of water rights to wetland areas of Lahontan Valley, Nevada, has caused concern over the potential effects on shallow aquifer water levels. In 1992, water levels in Lahontan Valley were measured to construct a water-table map of the shallow aquifer prior to the effects of water-right transfers mandated by the Fallon Paiute-Shoshone Tribal Settlement Act of 1990 (Public Law 101-618, 104 Stat. 3289). From 1992 to 2012, approximately 11,810 water-righted acres, or 34,356 acre-feet of water, were acquired and transferred to wetland areas of Lahontan Valley. This report documents changes in water levels measured during the period of water-right transfers and presents an evaluation of five groundwater-flow model scenarios that simulated water-level changes in Lahontan Valley in response to water-right transfers and a reduction in irrigation season length by 50 percent.Water levels measured in 98 wells from 2012 to 2013 were used to construct a water-table map. Water levels in 73 of the 98 wells were compared with water levels measured in 1992 and used to construct a water-level change map. Water-level changes in the 73 wells ranged from -16.2 to 4.1 feet over the 20-year period. Rises in water levels in Lahontan Valley may correspond to annual changes in available irrigation water, increased canal flows after the exceptionally dry and shortened irrigation season of 1992, and the increased conveyance of water rights transferred to Stillwater National Wildlife Refuge. Water-level declines generally occurred near the boundary of irrigated areas and may be associated with groundwater pumping, water-right transfers, and inactive surface-water storage reservoirs. The largest water-level declines were in the area near Carson Lake.Groundwater-level response to water-right transfers was evaluated by comparing simulated and observed water-level changes for periods representing water-right transfers and a shortened irrigation season in areas near Fallon

  13. Lessons Learned From The 200 West Pump And Treatment Facility Construction Project At The US DOE Hanford Site - A Leadership For Energy And Environmental Design (LEED) Gold-Certified Facility

    International Nuclear Information System (INIS)

    Dorr, Kent A.; Ostrom, Michael J.; Freeman-Pollard, Jhivaun R.

    2012-01-01

    CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built in an accelerated manner with American Recovery and Reinvestment Act (ARRA) funds and has attained Leadership in Energy and Environmental Design (LEED) GOLD certification, which makes it the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. There were many contractual, technical, configuration management, quality, safety, and LEED challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility. This paper will present the Project and LEED accomplishments, as well as Lessons Learned by CHPRC when additional ARRA funds were used to accelerate design, procurement, construction, and commissioning of the 200 West Groundwater Pump and Treatment (2W PandT) Facility to meet DOE's mission of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012

  14. Lessons Learned From The 200 West Pump And Treatment Facility Construction Project At The US DOE Hanford Site - A Leadership For Energy And Environmental Design (LEED) Gold-Certified Facility

    Energy Technology Data Exchange (ETDEWEB)

    Dorr, Kent A. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Ostrom, Michael J. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Freeman-Pollard, Jhivaun R. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

    2012-11-14

    CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built in an accelerated manner with American Recovery and Reinvestment Act (ARRA) funds and has attained Leadership in Energy and Environmental Design (LEED) GOLD certification, which makes it the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. There were many contractual, technical, configuration management, quality, safety, and LEED challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility. This paper will present the Project and LEED accomplishments, as well as Lessons Learned by CHPRC when additional ARRA funds were used to accelerate design, procurement, construction, and commissioning of the 200 West Groundwater Pump and Treatment (2W P&T) Facility to meet DOE's mission of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012.

  15. Spatial interpolation of GPS PWV and meteorological variables over the west coast of Peninsular Malaysia during 2013 Klang Valley Flash Flood

    Science.gov (United States)

    Suparta, Wayan; Rahman, Rosnani

    2016-02-01

    Global Positioning System (GPS) receivers are widely installed throughout the Peninsular Malaysia, but the implementation for monitoring weather hazard system such as flash flood is still not optimal. To increase the benefit for meteorological applications, the GPS system should be installed in collocation with meteorological sensors so the precipitable water vapor (PWV) can be measured. The distribution of PWV is a key element to the Earth's climate for quantitative precipitation improvement as well as flash flood forecasts. The accuracy of this parameter depends on a large extent on the number of GPS receiver installations and meteorological sensors in the targeted area. Due to cost constraints, a spatial interpolation method is proposed to address these issues. In this paper, we investigated spatial distribution of GPS PWV and meteorological variables (surface temperature, relative humidity, and rainfall) by using thin plate spline (tps) and ordinary kriging (Krig) interpolation techniques over the Klang Valley in Peninsular Malaysia (longitude: 99.5°-102.5°E and latitude: 2.0°-6.5°N). Three flash flood cases in September, October, and December 2013 were studied. The analysis was performed using mean absolute error (MAE), root mean square error (RMSE), and coefficient of determination (R2) to determine the accuracy and reliability of the interpolation techniques. Results at different phases (pre, onset, and post) that were evaluated showed that tps interpolation technique is more accurate, reliable, and highly correlated in estimating GPS PWV and relative humidity, whereas Krig is more reliable for predicting temperature and rainfall during pre-flash flood events. During the onset of flash flood events, both methods showed good interpolation in estimating all meteorological parameters with high accuracy and reliability. The finding suggests that the proposed method of spatial interpolation techniques are capable of handling limited data sources with high

  16. Preliminary gravity and magnetic models across Midway Valley and Yucca Wash, Yucca Mountain, Nevada

    International Nuclear Information System (INIS)

    Ponce, D.A.; Langenheim, V.E.

    1994-01-01

    Detailed gravity and ground magnetic data collected along ten traverses across Midway Valley and Yucca Wash on the eastern flank of Yucca Mountain in southwest Nevada are interpreted. These data were collected as part of an effort to evaluate faulting in the vicinity of proposed surface facilities for a potential nuclear waste repository at Yucca Mountain. Geophysical data show that Midway Valley is bounded by large gravity and magnetic anomalies associated with the Bow Ridge and Paintbrush Canyon faults, on the west side of Exile Hill and on the west flank of Fran Ridge, respectively. In addition, Midway Valley itself is characterized by a number of small-amplitude anomalies that probably reflect small-scale faulting beneath Midway Valley. Gravity and magnetic data across the northwest trending Yucca Wash and the inferred Yucca Wash fault indicate no major vertical offsets greater than 100 m using a density contrast of 0.2 to 0.3 g/cm 3 along the proposed Yucca Wash fault. In addition, a broad magnetic high coincides with the approximate location of the hydrologic gradient and probably reflects moderately magnetic Topopah Spring Tuff or lavas in the Calico Hills Formation

  17. Design and operational considerations of United States commercial nea-surface low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Birk, Sandra M.

    1997-01-01

    Low-level radioactive waste disposal standards and techniques in the United States have evolved significantly since the early 1960's. Six commercial LLW disposal facilities(Barnwell, Richland, Ward Valley, Sierra Blanca, Wake County and Boyd County) operated and proposed between 1962 and 1997. This report summarizes each site's design and operational considerations for near-surface disposal of low-level radioactive waste. These new standards and mitigating efforts at closed facilities (Sheffield, Maxey Flats, Beatty and West Valley) have helped to ensure that the public has been safely protected from LLW. 15 refs

  18. Use of risk information to safety regulation. Fabrication facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    A procedure of ISA (Integrated Safety Analysis) for uranium fuel fabrication/enrichment facilities has been under the development aiming to utilize risk information for safety regulations in this project. Activities in the fiscal year 2012 are summarized in the paper. There are two major activities in the year. First one is a study on ISA procedure for external events such as earthquakes. Second one is that for chemical consequences such as UF6 and HF. Other than the activities a fundamental study on a policy of utilizing risk information was conducted. The outline and results are provided in the chapter 1 and 2 respectively. (author)

  19. Women's social networks and use of facility delivery services for uncomplicated births in North West Ethiopia: a community-based case-control study.

    Science.gov (United States)

    Asrese, Kerebih; Adamek, Margaret E

    2017-12-28

    High maternal mortality has remained an unmet public health challenge in the developing world. Maternal mortality in Ethiopia is among the highest in the world. Since most maternal deaths occur during labor, delivery, and the immediate postpartum period, facility delivery with skilled birth attendants is recommended to reduce maternal mortality. Nonetheless, the majority of women in Ethiopia give birth at home. Individual attributes and availability and accessibility of services deter service utilization. The role of social networks that may facilitate or constrain service use is not well studied. Community-based case-control study was conducted between February and March 2014 in Jabi Tehinan District, North West Ethiopia. Retrospective data were collected from 134 women who had uncomplicated births at health facilities and 140 women who had uncomplicated births at home within a year preceding the survey. Interviews were held with eight women who had uncomplicated births at health facilities and 11 who had uncomplicated births at home. The quantitative data were entered and analyzed using SPSS for Windows versions 16.0 and hierarchical logistic regression model was used for analysis. The qualitative data were transcribed verbatim and data were used to substantiate the quantitative data. The results indicated that social network variables were significantly associated with the use of health facilities for delivery. Taking social networks into account improved the explanation of facility use for delivery services over women's individual attributes. Women embedded within homogeneous network members (Adjusted OR 2.53; 95% CI: 1.26-5.06) and embedded within high SBA endorsement networks (Adjusted OR 7.97; 95% CI: 4.07-12.16) were more likely to deliver at health facilities than their counterparts. Women living in urban areas (Adjusted OR 3.32; 95% CI: 1.37-8.05) and had better knowledge of obstetric complications (Adjusted OR 3.01; 95% CI: 1.46-6.18) were more likely to

  20. Post-remedial-action radiological survey report for the Plutonium Facility of the Battelle Memorial Institute, Columbus Division, West Jefferson Complex, West Jefferson, Ohio, April 1980-June 1982

    International Nuclear Information System (INIS)

    Flynn, K.F.; Justus, A.L.; Sholeen, C.M.; Smith, W.H.; Wynveen, R.A.

    1987-01-01

    The post-remedial-action surveys involved only the remaining, newer segment of the original Plutonium Facility and those outdoor environs at the former location of the buried autoclave and old holding tanks. The assessment activities conducted during the three surveys included determination of surface contamination levels, both fixed and removable, through direct instrument and smear surveys; measurement of ambient external penetrating radiation levels at 1-meter heights throughout the involved areas; measurement of the concentrations of radon, thoron, and actinon daughters and longer-lived radionuclides within air samples; and determination of concentrations of uranium, plutonium, americium, neptunium, the thorium-232 decay chain, and the radium-226 decay chain in soil and other material samples from the involved areas. The direct instrument and smear surveys were performed on all accessible floor, wall, and overhead surfaces and ductwork in the laboratory and corridor areas, mechanical room, and men's locker room, where the false ceiling, formerly at the 12-ft level, had been removed. In the office areas, the accessible floors, walls, and overheads were surveyed to the height of the existing 8-ft false ceiling. Although the office areas were adjacent to, not part of, the affected areas, it was possible that radioactive materials could have been carried by the ventilation system, spilled, or otherwise tracked into these adjacent areas. In some building areas, surfaces might hae been retiled, painted, or otherwise covered since the beginning of use of radioactive materials; however, the instruments used for the direct survey had some capability to detect beta-gamma activity on the underlying surfaces. 5 refs., 8 figs., 8 tabs

  1. Integration of traditional birth attendants into prevention of mother-to-child transmission at primary health facilities in Kaduna, North-West Nigeria

    Directory of Open Access Journals (Sweden)

    Reward O. Nsirim

    2016-05-01

    Full Text Available One of the fundamental challenges to implementing successful prevention of mother-tochild transmission (PMTCT programs in Nigeria is the uptake of PMTCT services at health facilities. Several issues usually discourage many pregnant women from receiving antenatal care services at designated health facilities within their communities. The CRS Nigeria PMTCT Project funded by the Global Fund in its Round 9 Phase 1 in Nigeria, sought to increase demand for HIV counseling and testing services for pregnant women at 25 supported primary health centers (PHCs in Kaduna State, North-West Nigeria by integrating traditional birth attendants (TBAs across the communities where the PHCs were located into the project. Community dialogues were held with the TBAs, community leaders and women groups. These dialogues focused on modes of mother to child transmission of HIV and the need for TBAs to refer their clients to PHCs for testing. Subsequently, data on number of pregnant women who were counseled, tested and received results was collected on a monthly basis from the 25 facilities using the national HIV/AIDS tools. Prior to this integration, the average number of pregnant women that were counseled, tested and received results was 200 pregnant women across all the 25 health facilities monthly. After the integration of TBAs into the program, the number of pregnant women that were counseled, tested and received results kept increasing month after month up to an average of 1500 pregnant women per month across the 25 health facilities. TBAs can thus play a key role in improving service uptake and utilization for pregnant women at primary health centers in the community – especially in the context of HIV/AIDS. They thus need to be integrated, rather than alienated, from primary healthcare service delivery.

  2. Integration of Traditional Birth Attendants into Prevention of Mother-to-Child Transmission at Primary Health Facilities in Kaduna, North-West Nigeria.

    Science.gov (United States)

    Nsirim, Reward O; Iyongo, Joseph A; Adekugbe, Olayinka; Ugochuku, Maureen

    2015-03-31

    One of the fundamental challenges to implementing successful prevention of mother-to-child transmission (PMTCT) programs in Nigeria is the uptake of PMTCT services at health facilities. Several issues usually discourage many pregnant women from receiving antenatal care services at designated health facilities within their communities. The CRS Nigeria PMTCT Project funded by the Global Fund in its Round 9 Phase 1 in Nigeria, sought to increase demand for HIV counseling and testing services for pregnant women at 25 supported primary health centers (PHCs) in Kaduna State, North-West Nigeria by integrating traditional birth attendants (TBAs) across the communities where the PHCs were located into the project. Community dialogues were held with the TBAs, community leaders and women groups. These dialogues focused on modes of mother to child transmission of HIV and the need for TBAs to refer their clients to PHCs for testing. Subsequently, data on number of pregnant women who were counseled, tested and received results was collected on a monthly basis from the 25 facilities using the national HIV/AIDS tools. Prior to this integration, the average number of pregnant women that were counseled, tested and received results was 200 pregnant women across all the 25 health facilities monthly. After the integration of TBAs into the program, the number of pregnant women that were counseled, tested and received results kept increasing month after month up to an average of 1500 pregnant women per month across the 25 health facilities. TBAs can thus play a key role in improving service uptake and utilization for pregnant women at primary health centers in the community - especially in the context of HIV/AIDS. They thus need to be integrated, rather than alienated, from primary healthcare service delivery.

  3. Valley Fever

    Science.gov (United States)

    ... valley fever. These fungi are commonly found in soil in specific regions. The fungi's spores can be stirred into the air by ... species have a complex life cycle. In the soil, they grow as a mold with long filaments that break off into airborne ...

  4. Draft environmental statement related to the decommissioning of the Rare Earths Facility, West Chicago, Illinois. Docket No. 40-2061. Kerr-McGee Chemical Corporation

    International Nuclear Information System (INIS)

    1982-05-01

    This Draft Environmental Impact Statement is issued by the US Nuclear Regulatory Commission in response to the plan proposed by Kerr-McGee Chemical Corporation for the decommissioning of their Rare Earths Facility located in West Chicago, Illinois. The statement considers the Kerr-McGee preferred plan and various alternatives to that plan. The action proposed by the Commission is the renewal of the Kerr-McGee license to allow safe storage of the radioactive wastes onsite for a period of 5 years. At the end of this period, the following alternatives will be evaluated: (1) Renewal of the license for an additional period of 5 years and the possible imposition of additional conditions or remedial actions; (2) Removal of the material to a licensed low-level waste disposal site; and (3) Termination of the license and transfer of the property to federal or state ownership

  5. 2015 In-Situ Gamma-Ray Assay of the West Cell Line in the 235-F Plutonium Fuel Form Facility

    Energy Technology Data Exchange (ETDEWEB)

    Brand, A. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Aucott, T. J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); DiPrete, D. P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-02-01

    In November and December 2015, scientists from SRNL took a series of in-situ gamma-ray measurements through the windows in front of Cells 6-9 on the west line of the PuFF facility using a shielded, 120% high-purity germanium detector. The detector efficiency was estimated using a combination of MCNP simulations and empirical measurements. Where possible, the distribution of the Pu-238 in the cells was determined using the Germanium Gamma-ray Imager (GeGI). This distribution was then fed into the MCNP model to quantify the Pu-238 in each cell. Data analysis was performed using three gamma rays emitted by Pu-238 (99.85 keV, 152.7 keV, and 766.4 keV) providing three independent estimates of the mass of Pu-238 holdup in each of the cells.

  6. Supplement to the final environmental statement related to the decommissioning of the rare earths facility, West Chicago, Illinois: Volume 1: Main test and appendices A-G

    International Nuclear Information System (INIS)

    1989-04-01

    This Supplement to the Final Environmental Statement (SFES) assesses the impacts of permanent disposal of wastes located at the Kerr-McGee Rare Earths Facility in West Chicago, Illinois. In this SFES, additional alternative sites are analyzed, the analysis is more detailed, and the NRC expressly considers the suitability of these sites for permanent waste disposal. The analysis describes the Proposed Action, which is permanent disposal of the wastes in an above-grade disposal cell at the West Chicago site, and four alternatives for permanent disposal at other sites in Illinois. The four alternatives are: Alternative A, disposal at an active surface coal mine in a deep-trench disposal cell; Alternative B, disposal in a reclaimed surface coal mine in a deep-trench disposal cell; Alternative C, disposal in an underground coal mine in a worked-out panel; and Alternative D, disposal on a farmland site in a partially above-grade disposal cell. The environmental issues considered in the impact assessment are topography, air quality, socioeconomics, land resources, archaeology, mineral resources, water resources, ecology, and radiation exposure. A cost-benefit analysis of the Proposed Action and its alternatives is also presented. Based on the information and analysis given within this SFES, the NRC concluded that the Proposed Action is the preferred course of action. 220 refs., 7 figs., 125 Tabs

  7. 27 CFR 9.66 - Russian River Valley.

    Science.gov (United States)

    2010-04-01

    ... Springs map. (22) Proceed 4.8 miles north-northwest along Mark West Springs Road, which becomes Porter Creek Road, to its intersection with Franz Valley Road, a light-duty road to the north of Porter Creek...

  8. US DOE surplus facilities management program (SFMP). International technology exchange activities

    International Nuclear Information System (INIS)

    Broderick, J.

    1986-01-01

    The Surplus Facilities Management Program is one of five remedial action programs established by the US Department of Energy (DOE) to eliminate potential hazards to the public and environment from radioactive contamination. These programs provide remedial actions at various facilities and sites previously used by the US Government in national atomic energy programs. Included are uranium ore milling sites, nuclear materials production plants, and research and development facilities. The DOE's five remedial action programs are: the Grand Junction Remedial Action Project; the Formerly Utilized Sites Remedial Action Project; the West Valley Demonstration Project; and the Surplus Facilities Management Program. The Surplus Facilities Management Program (SWMP) was established by DOE in 1978. There are presently over 300 shutdown facilities in the SFMP located at sites across the United States and in Puerto Rico. In some cases, remedial action involves decontaminating and releasing a facility for some other use. In other instances, facilities are completely demolished and removed from the site

  9. An Updated Performance Assessment For A New Low-Level Radioactive Waste Disposal Facility In West Texas - 12192

    Energy Technology Data Exchange (ETDEWEB)

    Dornsife, William P.; Kirk, J. Scott; Shaw, Chris G. [Waste Control Specialists LLC, Andrews, Texas (United States)

    2012-07-01

    This Performance Assessment (PA) submittal is an update to the original PA that was developed to support the licensing of the Waste Control Specialists LLC Low-Level Radioactive Waste (LLRW) disposal facility. This update includes both the Compact Waste Facility (CWF) and the Federal Waste Facility (FWF), in accordance with Radioactive Material License (RML) No. R04100, License Condition (LC) 87. While many of the baseline assumptions supporting the initial license application PA were incorporated in this update, a new transport code, GoldSim, and new deterministic groundwater flow codes, including HYDRUS and MODFLOWSURFACT{sup TM}, were employed to demonstrate compliance with the performance objectives codified in the regulations and RML No. R04100, LC 87. A revised source term, provided by the Texas Commission on Environmental Quality staff, was used to match the initial 15 year license term. This updated PA clearly confirms and demonstrates the robustness of the characteristics of the site's geology and the advanced engineering design of the disposal units. Based on the simulations from fate and transport models, the radiation doses to members of the general public and site workers predicted in the initial and updated PA were a small fraction of the criterion doses of 0.25 mSv and 50 mSv, respectively. In a comparison between the results of the updated PA against the one developed in support of the initial license, both clearly demonstrated the robustness of the characteristics of the site's geology and engineering design of the disposal units. Based on the simulations from fate and transport models, the radiation doses to members of the general public predicted in the initial and updated PA were a fraction of the allowable 25 mrem/yr (0.25 m sievert/yr) dose standard for tens-of-thousands of years into the future. Draft Texas guidance on performance assessment (TCEQ, 2004) recommends a period of analysis equal to 1,000 years or until peak doses from

  10. West Valley Demonstration Project annual report

    International Nuclear Information System (INIS)

    1986-01-01

    In FY 1985 the most challenging goal of the Project to date, the start of verification testing of major subsystems of the Vitrification System, was accomplished. Individual testing of subsystems was completed in FY 1985 allowing for the start of integrated testing of all major portions of the Vitrification System. Other accomplishments during this period included completion of cleanup of the first of several former reprocessing cells, the first phase of testing and operation of the system which will solidify low-level liquid wastes and the beginning of construction to support installation of the Supernatant Treatment System which will be used to remove the radioactive fission products from the supernatant

  11. 27 CFR 9.41 - Lancaster Valley.

    Science.gov (United States)

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Lancaster Valley. 9.41 Section 9.41 Alcohol, Tobacco Products and Firearms ALCOHOL AND TOBACCO TAX AND TRADE BUREAU, DEPARTMENT... through the town of Gap and along Mine Ridge to the 76°07′30″ west longitude line in Paradise Township. (9...

  12. Environmental Assessment for the Strategic Petroleum Reserve West Hackberry Facility Raw Water Intake Pipeline Replacement Cameron and Calcasieu Parishes, Louisiana

    Energy Technology Data Exchange (ETDEWEB)

    N/A

    2004-08-31

    The proposed action and three alternatives, including a No Build alternative, were evaluated along the existing RWIPL alignment to accommodate the placement of the proposed RWIPL. Construction feasibility, reasonableness and potential environmental impacts were considered during the evaluation of the four actions (and action alternatives) for the proposed RWIPL activities. Reasonable actions were identified as those actions which were considered to be supported by common sense and sound technical principles. Feasible actions were those actions which were considered to be capable of being accomplished, practicable and non-excessive in terms of cost. The evaluation process considered the following design specifications, which were determined to be important to the feasibility of the overall project. The proposed RWIPL replacement project must therefore: (1) Comply with the existing design basis and criteria, (2) Maintain continuity of operation of the facility during construction, (3)Provide the required service life, (4) Be cost effective, (5)Improve the operation and maintenance of the pipeline, and (6) Maintain minimal environmental impact while meeting the performance requirements. Sizing of the pipe, piping construction materials, construction method (e.g., open-cut trench, directional drilling, etc.) and the acquisition of new Right-of-Way (ROW) were additionally evaluated in the preliminary alternative identification, selection and screening process.

  13. A CASE STUDY DEMONSTRATING U.S. EPA GUIDANCE FOR EVALUATING LANDFILL GAS EMISSIONS FROM CLOSED OR ABANDONED FACILITIES--BUSH VALLEY LANDFILL, HARFORD COUNTY, MARYLAND

    Science.gov (United States)

    The purpose of the activities described in this document is to provide a demonstration of the procedures and methodologies described within the "Guidance for Evaluating Landfill Gas Emissions from Closed or Abandoned Facilities" (Guidance). This demonstration provides an example ...

  14. Social accountability in primary health care in West and Central Africa: exploring the role of health facility committees.

    Science.gov (United States)

    Lodenstein, Elsbet; Mafuta, Eric; Kpatchavi, Adolphe C; Servais, Jean; Dieleman, Marjolein; Broerse, Jacqueline E W; Barry, Alpha Amadou Bano; Mambu, Thérèse M N; Toonen, Jurrien

    2017-06-13

    Social accountability has been emphasised as an important strategy to increase the quality, equity, and responsiveness of health services. In many countries, health facility committees (HFCs) provide the accountability interface between health providers and citizens or users of health services. This article explores the social accountability practices facilitated by HFCs in Benin, Guinea and the Democratic Republic of Congo. The paper is based on a cross-case comparison of 11 HFCs across the three countries. The HFCs were purposefully selected based on the (past) presence of community participation support programs. The cases were derived from qualitative research involving document analysis as well as interviews and focus group discussions with health workers, citizens, committee members, and local authorities. Most HFCs facilitate social accountability by engaging with health providers in person or through meetings to discuss service failures, leading to changes in the quality of services, such as improved health worker presence, the availability of night shifts, the display of drug prices and replacement of poorly functioning health workers. Social accountability practices are however often individualised and not systematic, and their success depends on HFC leadership and synergy with other community structures. The absence of remuneration for HFC members does not seem to affect HFC engagement in social accountability. Most HFCs in this study offer a social accountability forum, but the informal and non-systematic character and limited community consultation leave opportunities for the exclusion of voices of marginalised groups. More inclusive, coherent and authoritative social accountability practices can be developed by making explicit the mandate of HFC in the planning, monitoring, and supervision of health services; providing instruments for organising local accountability processes; strengthening opportunities for community input and feedback; and

  15. Supplement to the Final Environmental Statement related to the decommissioning of the Rare Earths Facility, West Chicago, Illinois (Docket No. 40-2061): Volume 2, Appendix H

    International Nuclear Information System (INIS)

    1989-04-01

    This Supplement to the Final Environmental Statement is issued by the US Nuclear Regulatory Commission in response to the Atomic Safety and Licensing Board's ruling that the staff must supplement the Final Environmental Statement in order to evaluate the impact of permanent disposal of the Kerr-McGee Rare Earths Facility wastes located at West Chicago, Illinois. The statement considers the Kerr-McGee preferred plan and various alternatives to the plan. The action proposed by the Commission is the renewal of the Kerr-McGee license to allow disposal of wastes onsite and for possession of the wastes under license for an indeterminate time. The license could be terminated at a later date if certain specified requirements were met. NUREG-0904 was published in draft for comment in June 1987. Comments have been received and are published with their responses in this report. Volume 1 contains the main text and Appendices A thru G. Volume 2 contains the comments received and their responses

  16. Design assessment for the Melton Valley Storage Tanks capacity increase at Oak Ridge National Laboratory under the Federal Facility Agreement, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1995-11-01

    This project was initiated to find ways to increase storage capacity for the liquid low-level waste (LLLW) system at the Oak Ridge National Laboratory and satisfy the Federal Facility Agreement (FFA) requirement for the transfer of LLW from existing tank systems not in full FFA compliance

  17. Prevalence, risk factors of human papillomavirus infection and papanicolaou smear pattern among women attending a tertiary health facility in south-west Nigeria

    Directory of Open Access Journals (Sweden)

    Olatunji Mathew Kolawole

    2015-12-01

    Full Text Available Aim: Cervical cancer amongst Nigerian women has been on the increase in the past decade, and is regarded as the second highest cause of cancer deaths among Nigerian women. This study was aimed at determining the prevalence, risk factors of HPV infection, and Papanicolaou smear pattern amongst a cohort of women attending the Gynaecology clinic of a tertiary health facility in Ido-Ekiti, South west Nigeria. Method: This was a cross-sectional study involving the screening of women between the ages of 15-64 years for cervical intraepithelial neoplasia using Papanicolaou smear staining technique and serological diagnosis using IgG enzyme linked immunosorbent assay kits. Respondents were selected through convenience sampling of subjects, while interviewer- administered questionnaire and clinical report form were also used to collect data, and data was analyzed using SPSS version 17. Results: Of the 200 blood samples examined for Human papillomavirus infection, 135 (67.5% were sero-positive while 65 (32.5% were sero-negative. For cervical cytology using Papanicolaou smear, 14 (7% were positive (had presence of cervical abnormality while 186 (93% were negative (had no cervical abnormality. Result showed a direct relationship between seropositivity, development of cervical intraepithelial neoplasia and Human papillomavirus infection. The risk factors for the development of HPV infection included age, type of marriage, parity, history of genital infection and tobacco usage. Non circumcision of male partner was also found to be a risk factor. Conclusion: The presence of abnormal cervical cytology and high level of serological positivity clearly showed why there is need for a holistic approach to the screening, vaccination methodologies and early detection of HPV infection in the country. [TAF Prev Med Bull 2015; 14(6.000: 453-459

  18. Evaluation of environmental control technologies for commercial uranium nuclear fuel fabrication facilities

    International Nuclear Information System (INIS)

    Perkins, B.L.

    1983-01-01

    At present in the United States, there are seven commercial light-water reactor uranium fuel fabrication facilities. Effluent wastes from these facilities include uranium, nitrogen, fluorine, and organic-containing compounds. These effluents may be either discharged to the ambient environment, treated and recycled internally, stored or disposed of on-site, sent off-site for treatment and/or recovery, or sent off-site for disposal (including disposal in low-level waste burial sites). Quantities of waste generated and treatment techniques vary greatly depending on the facility and circuits used internally at the facility, though in general all the fluorine entering the facility as UF 6 is discharged as waste. Further studies to determine techniques and procedures that might minimize dose (ALARA) and to give data on possible long-term effects of effluent discharge and waste disposal are needed

  19. Environmental Management Waste Management Facility Proxy Waste Lot Profile 6.999 for Building K-25 West Wing, East Tennessee Technology Park, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Rigsby V.P.

    2009-02-12

    In 1989, the Oak Ridge Reservation (ORR), which includes the East Tennessee Technology Park (ETTP), was placed on the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) National Priorities List. The Federal Facility Agreement (FFA) (DOE 1992), effective January 1, 1992, now governs environmental restoration activities conducted under CERCLA at the ORR. Following signing of the FFA, U.S. Department of Energy (DOE), U.S. Environmental Protection Agency (EPA), and the state of Tennessee signed the Oak Ridge Accelerated Cleanup Plan Agreement on June 18, 2002. The purpose of this agreement is to define a streamlined decision-making process to facilitate the accelerated implementation of cleanup, resolve ORR milestone issues, and establish future actions necessary to complete the accelerated cleanup plan by the end of fiscal year 2008. While the FFA continues to serve as the overall regulatory framework for remediation, the Accelerated Cleanup Plan Agreement supplements existing requirements to streamline the decision-making process. Decontamination and decommissioning (D&D) activities of Bldg. K-25, the original gaseous diffusion facility, is being conducted by Bechtel Jacobs Company LLC (BJC) on behalf of the DOE. The planned CERCLA action covering disposal of building structure and remaining components from the K-25 building is scheduled as a non-time-critical CERCLA action as part of DOE's continuous risk reduction strategy for ETTP. The K-25 building is proposed for D&D because of its poor physical condition and the expense of surveillance and maintenance activities. The K-25/K-27 D&D Project proposes to dispose of the commingled waste listed below from the K-25 west side building structure and remaining components and process gas equipment and piping at the Environmental Management Waste Management Facility (EMWMF) under waste disposal proxy lot (WPXL) 6.999: (1) Building structure (e.g. concrete floors [excluding basement

  20. Makran Mountain Range, Indus River Valley, Pakistan, India

    Science.gov (United States)

    1984-01-01

    The enormous geologic pressures exerted by continental drift can be very well illustrated by the long northward curving parallel folded mountain ridges and valleys of the coastal Makran Range of Pakistan (27.0N, 66.0E). As a result of the collision of the northward bound Indian sub-continent into the Asian Continent, the east/west parallel range has been bent in a great northward arc and forming the Indus River valley at the interface of the collision.

  1. Detailed study of selenium and other constituents in water, bottom sediment, soil, alfalfa, and biota associated with irrigation drainage in the Uncompahgre Project area and in the Grand Valley, west-central Colorado, 1991-93

    Science.gov (United States)

    Butler, D.L.; Wright, W.G.; Stewart, K.C.; Osmundson, B.C.; Krueger, R.P.; Crabtree, D.W.

    1996-01-01

    In 1985, the U.S. Department of the Interior began a program to study the effects of irrigation drainage in the Western United States. These studies were done to determine whether irrigation drainage was causing problems related to human health, water quality, and fish and wildlife resources. Results of a study in 1991-93 of irrigation drainage associated with the Uncompahgre Project area, located in the lower Gunnison River Basin, and of the Grand Valley, located along the Colorado River, are described in this report. The focus of the report is on the sources, distribution, movement, and fate of selenium in the hydrologic and biological systems and the effects on biota. Generally, other trace- constituent concentrations in water and biota were not elevated or were not at levels of concern. Soils in the Uncompahgre Project area that primarily were derived from Mancos Shale contained the highest concentrations of total and watrer-extractable selenium. Only 5 of 128\\x11alfalfa samples had selenium concentrations that exceeded a recommended dietary limit for livestock. Selenium data for soil and alfalfa indicate that irrigation might be mobilizing and redistributing selenium in the Uncompahgre Project area. Distribution of dissolved selenium in ground water is affected by the aqueous geochemical environment of the shallow ground- water system. Selenium concentrations were as high as 1,300\\x11micrograms per liter in water from shallow wells. The highest concentrations of dissolved selenium were in water from wells completed in alluvium overlying the Mancos Shale of Cretaceous age; selenium concentrations were lower in water from wells completed in Mancos Shale residuum. Selenium in the study area could be mobilized by oxidation of reduced selenium, desorption from aquifer sediments, ion exchange, and dissolution. Infiltration of irrigation water and, perhaps nitrate, provide oxidizing conditions for mobilization of selenium from alluvium and shale residuum and for

  2. A radiological dose assessment for the Port Hope conversion facility

    International Nuclear Information System (INIS)

    Garisto, N.C.; Cooper, F.; Janes, A.; Stager, R.; Peters, R.

    2011-01-01

    The Port Hope Conversion Facility (PHCF) receives uranium trioxide for conversion to uranium hexafluoride (UF 6 ) or uranium dioxide (UO 2 ). The PHCF Site has a long history of industrial use. A Radiological Dose Assessment was undertaken as part of a Site Wide Risk Assessment. This assessment took into account all possible human receptors, both workers and members of the public. This paper focuses on a radiological assessment of dose to members of the public. The doses to members of the public from terrestrial pathways were added to the doses from aquatic pathways to obtain overall dose to receptors. The benchmark used in the assessment is 1 mSv/y. The estimated doses related to PHCF operations are much lower than the dose limit. (author)

  3. New Prototype Safeguards Technology Offers Improved Confidence and Automation for Uranium Enrichment Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Brim, Cornelia P.

    2013-04-01

    An important requirement for the international safeguards community is the ability to determine the enrichment level of uranium in gas centrifuge enrichment plants and nuclear fuel fabrication facilities. This is essential to ensure that countries with nuclear nonproliferation commitments, such as States Party to the Nuclear Nonproliferation Treaty, are adhering to their obligations. However, current technologies to verify the uranium enrichment level in gas centrifuge enrichment plants or nuclear fuel fabrication facilities are technically challenging and resource-intensive. NNSA’s Office of Nonproliferation and International Security (NIS) supports the development, testing, and evaluation of future systems that will strengthen and sustain U.S. safeguards and security capabilities—in this case, by automating the monitoring of uranium enrichment in the entire inventory of a fuel fabrication facility. One such system is HEVA—hybrid enrichment verification array. This prototype was developed to provide an automated, nondestructive assay verification technology for uranium hexafluoride (UF6) cylinders at enrichment plants.

  4. Japan-IAEA sefeguards demonstration programme in the gas centrifuge uranium enrichment facility

    International Nuclear Information System (INIS)

    Akiba, Mitsunori; Iwamoto, Tomonori; Omae, Masayoshi

    1985-01-01

    The Hexa-partite Safequard Project was started for the purpose of examining the effective techniques of safeguards for gas centrifuge uranium enrichment facilities. By the proposal of respective participating countries, it was decided to carry out the verifying test of various safeguard techniques at the actual plants. Japan carried out the verifying test of safeguard techniques at the Ningyotoge uranium enrichment pilot plant in June, 1982, and from November, 1983, to August, 1984. The contents of this test is reported. In Japan, this verifying test was positioned as a part of JASPAS (Japanese project of supporting IAEA safeguards). The verifying test of realtime and in-operation inventories, the verifying test of IAEA load cell type weighing machines for UF 6 cylinders, the verifying test of the measurement of the degree of enrichment in UF 6 cylinders by nondestructive test, the verifying test of confinement/watch system, and the verifying test of IAEA gas phase uranium enrichment monitors were carried out. The results were presented as the data for examination in the HSP, and evaluated as useful, informative and well compiled. It is necessary to pursue more cost-effective approaches. (Kako, I.)

  5. Valley polarization in bismuth

    Science.gov (United States)

    Fauque, Benoit

    2013-03-01

    The electronic structure of certain crystal lattices can contain multiple degenerate valleys for their charge carriers to occupy. The principal challenge in the development of valleytronics is to lift the valley degeneracy of charge carriers in a controlled way. In bulk semi-metallic bismuth, the Fermi surface includes three cigar-shaped electron valleys lying almost perpendicular to the high symmetry axis known as the trigonal axis. The in-plane mass anisotropy of each valley exceeds 200 as a consequence of Dirac dispersion, which drastically reduces the effective mass along two out of the three orientations. According to our recent study of angle-dependent magnetoresistance in bismuth, a flow of Dirac electrons along the trigonal axis is extremely sensitive to the orientation of in-plane magnetic field. Thus, a rotatable magnetic field can be used as a valley valve to tune the contribution of each valley to the total conductivity. As a consequence of a unique combination of high mobility and extreme mass anisotropy in bismuth, the effect is visible even at room temperature in a magnetic field of 1 T. Thus, a modest magnetic field can be used as a valley valve in bismuth. The results of our recent investigation of angle-dependent magnetoresistance in other semi-metals and doped semiconductors suggest that a rotating magnetic field can behave as a valley valve in a multi-valley system with sizeable mass anisotropy.

  6. 27 CFR 9.216 - Upper Mississippi River Valley.

    Science.gov (United States)

    2010-04-01

    ...), east of St. Paul at Oakbury in Washington County. From the beginning point, proceed east on Interstate... Winnebago County to U.S. Highway 20 at Cherry Valley; then (6) Proceed west on U.S. Highway 20 to Illinois...), south of St. Paul; then (15) Follow Interstate Highway 494 (beltway) northeast into Washington County...

  7. Evaluation of approximate original contour and postmining land use in West Virginia. Final report

    International Nuclear Information System (INIS)

    1999-05-01

    The Office of Surface Mining (OSM) has been working diligently with the West Virginia Division of Environmental Protection (WVDEP) to improve the State's administration of its approved program in two areas: (1) the standards used by the WVDEP in evaluating whether a particular postmining and land configuration constitutes a return to AOC (approximate original contour); and (2) the postmining land uses which WVDEP approves when it grants a waiver from the AOC requirement. In conjunction with OSM, the WVDEP recently announced proposed new procedures that should both enable the permit reviewer to more easily determine when a site achieves AOC and limit the placement of excess spoil in valleys and streams. In addition, OSM is developing a policy document that will clarify the acceptable postmining land uses for mountaintop-removal and steep slope mining operations with AOC variances. In particular, this document addresses the issue of whether commercial forestry, agriculture, and public facilities, including recreational facilities constitute approvable postmining land uses

  8. Greening Turner Valley

    International Nuclear Information System (INIS)

    Byfield, M.

    2010-01-01

    This article discussed remedial activities undertaken in the Turner Valley. Remedial action in the valley must satisfy the financial concerns of engineers and investors as well as the environmental concerns of residents and regulators. Natural gas production in the Turner Valley began in 1914. The production practices were harmful and wasteful. Soil and water pollution was not considered a problem until recently. The impacts of cumulative effects and other pollution hazards are now being considered as part of many oil and gas environmental management programs. Companies know it is cheaper and safer to prevent pollutants from being released, and more efficient to clean them up quickly. Oil and gas companies are also committed to remediating historical problems. Several factors have simplified remediation plans in the Turner Valley. Area real estate values are now among the highest in Alberta. While the valley residents are generally friendly to the petroleum industry, strong communication with all stakeholders in the region is needed. 1 fig.

  9. pVT-Second Virial Coefficients B(T ), Viscosity η(T ), and Self-Diffusion ρD(T) of the Gases: BF3, CF4, SiF4, CCl4, SiCl4, SF6, MoF6, WF6, UF6, C(CH3)4, and Si(CH3)4 Determined by Means of an Isotropic Temperature-Dependent Potential

    Science.gov (United States)

    Zarkova, L.; Hohm, U.

    2002-03-01

    We present results on self-consistent calculations of second pVT-virial coefficients B(T), viscosity data η(T), and diffusion coefficients ρD(T) for eleven heavy globular gases: boron trifluoride (BF3), carbon tetrafluoride (CF4), silicon tetrafluoride (SiF4), carbon tetrachloride (CCl4), silicon tetrachloride (SiCl4), sulfur hexafluoride (SF6), molybdenum hexafluoride (MoF6), tungsten hexafluoride (WF6), uranium hexafluoride (UF6), tetramethyl methane (C(CH3)4, TMM), and tetramethyl silane (Si(CH3)4, TMS). The calculations are performed mainly in the temperature range between 200 and 900 K by means of isotropic n-6 potentials with temperature-dependent separation rm(T) and potential well depth ɛ(T). The potential parameters at T=0 K (ɛ, rm, n) and the enlargement of the first level radii δ are obtained solving an ill-posed problem of minimizing the squared deviations between experimental and calculated values normalized to their relative experimental error. The temperature dependence of the potential is obtained as a result of the influence of vibrational excitation on binary interactions. This concept of the isotropic temperature-dependent potential (ITDP) is presented in detail where gaseous SF6 will serve as an example. The ITDP is subsequently applied to all other gases. This approach and the main part of the results presented here have already been published during 1996-2000. However, in some cases the data are upgraded due to the recently improved software (CF4, SF6) and newly found experimental data (CF4, SiF4, CCl4, SF6).

  10. Sutter Buttes-the lone volcano in California's Great Valley

    Science.gov (United States)

    Hausback, Brain P.; Muffler, L.J. Patrick; Clynne, Michael A.

    2011-01-01

    The volcanic spires of the Sutter Buttes tower 2,000 feet above the farms and fields of California's Great Valley, just 50 miles north-northwest of Sacramento and 11 miles northwest of Yuba City. The only volcano within the valley, the Buttes consist of a central core of volcanic domes surrounded by a large apron of fragmental volcanic debris. Eruptions at the Sutter Buttes occurred in early Pleistocene time, 1.6 to 1.4 million years ago. The Sutter Buttes are not part of the Cascade Range of volcanoes to the north, but instead are related to the volcanoes in the Coast Ranges to the west in the vicinity of Clear Lake, Napa Valley, and Sonoma Valley.

  11. Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility - 13113

    Energy Technology Data Exchange (ETDEWEB)

    Dorr, Kent A.; Freeman-Pollard, Jhivaun R.; Ostrom, Michael J. [CH2M HILL Plateau Remediation Company, P.O. Box 1600, MSIN R4-41, 99352 (United States)

    2013-07-01

    CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE's mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team's successful integration of the project's core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE's mission objective, as well as attainment of LEED GOLD certification (Figure 1), which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. (authors)

  12. Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility - 13113

    International Nuclear Information System (INIS)

    Dorr, Kent A.; Freeman-Pollard, Jhivaun R.; Ostrom, Michael J.

    2013-01-01

    CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE's mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team's successful integration of the project's core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE's mission objective, as well as attainment of LEED GOLD certification (Figure 1), which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. (authors)

  13. Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility

    Energy Technology Data Exchange (ETDEWEB)

    Dorr, Kent A.; Ostrom, Michael J.; Freeman-Pollard, Jhivaun R.

    2013-01-11

    CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy’s (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE’s mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team’s successful integration of the project’s core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE’s mission objective, as well as attainment of LEED GOLD certification, which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award.

  14. Draft supplement to the final environmental statement related to the decommissioning of the Rare Earths Facility, West Chicago, Illinois (Docket No. 40-2061): Kerr-McGee Chemical Corporation

    International Nuclear Information System (INIS)

    1987-06-01

    This Draft Supplemental Environmental Statement (DSES) assesses the impacts of permanent disposal of wastes located at the Kerr-McGee Rare Earths Facility in West Chicago, Illinois. The assessments presented in the DSES augment and update those described in the Final Environmental Statement (FES) that was issued by the US Nuclear Regulatory Commission (NRC) in May 1983. In this DSES, additional alternative sites are analyzed, the analysis is more detailed, and the NRC expressly considers the suitability of these sites for permanent waste disposal. The analysis describes the Proposed Action, which is permanent disposal of the wastes in an above-grade disposal cell at the West Chicago site, and four alternatives for permanent disposal at other sites in Illinois. The four alternatives are: Alternative A, disposal at an active surface coal mine in a deep-trench disposal cell; Alternative B, disposal in a reclaimed surface coal mine in a deep-trench disposal cell; Alternative C, disposal in an underground coal mine in a worked-out panel; and Alternative D, disposal on a farmland site in a partially above-grade disposal cell. The environmental issues considered in the impact assessment are topography, air quality, socioeconomics, land resources, archaeology, mineral resources, water resources, ecology, and radiation exposure. A cost-benefit analysis of the Proposed Action and its alternatives is also presented. Based on the information and analysis given within this DSES, the NRC concluded that the Proposed Action is the preferred course of action

  15. FEMO, A FLOW AND ENRICHMENT MONITOR FOR VERIFYING COMPLIANCE WITH INTERNATIONAL SAFEGUARDS REQUIREMENTS AT A GAS CENTRIFUGE ENRICHMENT FACILITY

    International Nuclear Information System (INIS)

    Gunning, John E.; Laughter, Mark D.; March-Leuba, Jose A.

    2008-01-01

    A number of countries have received construction licenses or are contemplating the construction of large-capacity gas centrifuge enrichment plants (GCEPs). The capability to independently verify nuclear material flows is a key component of international safeguards approaches, and the IAEA does not currently have an approved method to continuously monitor the mass flow of 235U in uranium hexafluoride (UF6) gas streams. Oak Ridge National Laboratory is investigating the development of a flow and enrichment monitor, or FEMO, based on an existing blend-down monitoring system (BDMS). The BDMS was designed to continuously monitor both 235U mass flow and enrichment of UF6 streams at the low pressures similar to those which exists at GCEPs. BDMSs have been installed at three sites-the first unit has operated successfully in an unattended environment for approximately 10 years. To be acceptable to GCEP operators, it is essential that the instrument be installed and maintained without interrupting operations. A means to continuously verify flow as is proposed by FEMO will likely be needed to monitor safeguards at large-capacity plants. This will enable the safeguards effectiveness that currently exists at smaller plants to be maintained at the larger facilities and also has the potential to reduce labor costs associated with inspections at current and future plants. This paper describes the FEMO design requirements, operating capabilities, and development work required before field demonstration.

  16. West Africa

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

    freelance

    considered by many as a successful model of river basin organization. NBA, after years of ... a Regional Water Protocol for West Africa, following the model of the SADC ...... protection of water against pollution of all kinds (urban, industrial,.

  17. Ward Valley transfer stalled by Babbitt

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    Interior Secretary Bruce Babbitt announced on November 24 that he would not authorize the land transfer for the proposed low-level waste disposal site at Ward Valley, California, until a legal challenge to the facility's license and environmental impact statement is resolved. Even if the matter is resolved quickly, there exists the possibility that yet another hearing will be held on the project, even though state courts in California have stated flatly that no such hearings are required

  18. Ward Valley transfer stalled by Babbitt

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    Interior Secretary Bruce Babbitt announced on November 24 that he would not authorize the land transfer for the proposed low-level waste disposal site at Ward Valley, California, until a legal challenge to the facility's license and environmental impact statement is resolved. Even if the matter is resolved quickly, there exists the possibility that yet another hearing will be held on the project, even though state courts in California have stated flatly that no such hearings are required.

  19. 75 FR 13808 - Missouri & Valley Park Railroad Corporation-Discontinuance of Service Exemption-in St Louis...

    Science.gov (United States)

    2010-03-23

    ... DEPARTMENT OF TRANSPORTATION Surface Transportation Board [STB Docket No. AB-1057X] Missouri & Valley Park Railroad Corporation--Discontinuance of Service Exemption--in St Louis County, MO On March 3... Subdivision between milepost 18.36 and milepost 20.50, near West Valley Park, St. Louis County, MO.\\2\\ The...

  20. Decontamination and renovation of the Master/Slave Manipulator Repair Shop and the Chemical Crane Room at the West Valley Demonstration Project. Final topical report, June 1982-June 1983

    International Nuclear Information System (INIS)

    Phillips, E.C.; Golden, M.P.

    1986-01-01

    This report describes the decontamination and renovation of the Master/Slave Manipulator Repair Shop (MSMRS) and the Chemical Crane Room (CCR) at the WVDP from radioactively contaminated conditions to essentially shirt sleeve environments. In both cases, subsequent use recontaminated the rooms. Before decontamination, general exposure rates as high as 20 mrad/hr and surface contamination as high as 10 5 dpm/100 cm 2 were measured in the MSMRS, while general exposure rates in the CCR were 50 to 100 mrad/hr with hot spots as high as 2000 mrad/hr. Smearable levels on the floor in each room were in the range of 10 5 to 10 6 dpm per 100/cm 2 . Respiratory protection was mandatory for entry into the CCR. The MSMRS, located at the north end of the Process Building on ground elevation, is needed for the refurbishment of plant manipulators and other equipment. The MSMRS has been decontaminated and renovated as follows: all tools, equipment and furnishings were removed, the walls were stripped and repainted, and the contaminated concrete floor was removed and disposal of as low-level waste. A new concrete floor was poured and a stainless steel liner covering the entire floor and extending 45.7 cm up the walls was added to provide the WVDP with a shop facility that can be easily decontaminated. Decontamination of the MSMRS has been completed and the facility is available for service. The CCR, located at the north end of the Chemical Process Cell (CPC) is for the storage and servicing of two bridge cranes used in the CPC. Decontamination and exposure reduction in the CCR has been completed using vacuum cleaning, damp wipe down, and surface grinding followed by shielding and painting

  1. The regulation of uranium refineries and conversion facilities in Canada

    International Nuclear Information System (INIS)

    Didyk, J.P.

    1986-04-01

    The nuclear regulatory process as it applies to uranium refineries and conversion facilities in Canada is reviewed. In the early 1980s, Eldorado Resources Limited proposed to construct and operate new facilities for refining yellowcake and for the production of uranium hexafluoride (UF 6 ). These projects were subject to regulation by the Atomic Energy Control Board (AECB). A description of the AECB's comprehensive licensing process covering all stages of siting, construction, operation and eventual decommissioning of nuclear facilities is traced as it was applied to the Eldorado projects. The AECB's concern with occupational health and safety, with public health and safety and with the protection of the environment in so far as it affects public health and safety is emphasized. Some regulatory difficulties encountered during the project's development which led to opening up the licensing process to public input and closer coordination of regulatory activities with other provincial and federal regulatory agencies are described. The Board's regulatory operational compliance program for uranium refineries and conversion facilities is summarized

  2. Debris Flow Occurrence and Sediment Persistence, Upper Colorado River Valley, CO.

    Science.gov (United States)

    Grimsley, K J; Rathburn, S L; Friedman, J M; Mangano, J F

    2016-07-01

    Debris flow magnitudes and frequencies are compared across the Upper Colorado River valley to assess influences on debris flow occurrence and to evaluate valley geometry effects on sediment persistence. Dendrochronology, field mapping, and aerial photographic analysis are used to evaluate whether a 19th century earthen, water-conveyance ditch has altered the regime of debris flow occurrence in the Colorado River headwaters. Identifying any shifts in disturbance processes or changes in magnitudes and frequencies of occurrence is fundamental to establishing the historical range of variability (HRV) at the site. We found no substantial difference in frequency of debris flows cataloged at eleven sites of deposition between the east (8) and west (11) sides of the Colorado River valley over the last century, but four of the five largest debris flows originated on the west side of the valley in association with the earthen ditch, while the fifth is on a steep hillslope of hydrothermally altered rock on the east side. These results suggest that the ditch has altered the regime of debris flow activity in the Colorado River headwaters as compared to HRV by increasing the frequency of debris flows large enough to reach the Colorado River valley. Valley confinement is a dominant control on response to debris flows, influencing volumes of aggradation and persistence of debris flow deposits. Large, frequent debris flows, exceeding HRV, create persistent effects due to valley geometry and geomorphic setting conducive to sediment storage that are easily delineated by valley confinement ratios which are useful to land managers.

  3. Water resources of Parowan Valley, Iron County, Utah

    Science.gov (United States)

    Marston, Thomas M.

    2017-08-29

    Parowan Valley, in Iron County, Utah, covers about 160 square miles west of the Red Cliffs and includes the towns of Parowan, Paragonah, and Summit. The valley is a structural depression formed by northwest-trending faults and is, essentially, a closed surface-water basin although a small part of the valley at the southwestern end drains into the adjacent Cedar Valley. Groundwater occurs in and has been developed mainly from the unconsolidated basin-fill aquifer. Long-term downward trends in groundwater levels have been documented by the U.S. Geological Survey (USGS) since the mid-1950s. The water resources of Parowan Valley were assessed during 2012 to 2014 with an emphasis on refining the understanding of the groundwater and surface-water systems and updating the groundwater budget.Surface-water discharge of five perennial mountain streams that enter Parowan Valley was measured from 2013 to 2014. The total annual surface-water discharge of the five streams during 2013 to 2014 was about 18,000 acre-feet (acre-ft) compared to the average annual streamflow of about 22,000 acre-ft from USGS streamgages operated on the three largest of these streams from the 1940s to the 1980s. The largest stream, Parowan Creek, contributes more than 50 percent of the annual surface-water discharge to the valley, with smaller amounts contributed by Red, Summit, Little, and Cottonwood Creeks.Average annual recharge to the Parowan Valley groundwater system was estimated to be about 25,000 acre-ft from 1994 to 2013. Nearly all recharge occurs as direct infiltration of snowmelt and rainfall on the Markagunt Plateau east of the valley. Smaller amounts of recharge occur as infiltration of streamflow and unconsumed irrigation water near the east side of the valley on alluvial fans associated with mountain streams at the foot of the Red Cliffs. Subsurface flow from the mountain block to the east of the valley is a significant source of groundwater recharge to the basin-fill aquifer

  4. Virgin Valley opal district, Humboldt County, Nevada

    Science.gov (United States)

    Staatz, Mortimer Hay; Bauer, Herman L.

    1951-01-01

    The Virgin Valley opal district, Humboldt County, Nevada, is near the Oregon-Nevada border in the Sheldon Game Refuge. Nineteen claims owned by Jack and Toni Crane were examined, sampled, and tested radiometrically for uranium. Numerous discontinuous layers of opal are interbedded with a gently-dipping series of vitric tuff and ash which is at least 300 ft thick. The tuff and ash are capped by a dark, vesicular basalt in the eastern part of the area and by a thin layer of terrace qravels in the area along the west side of Virgin Valley. Silicification of the ash and tuff has produced a rock that ranges from partly opalized rock that resembles silicified shale to completely altered rock that is entirely translucent, and consists of massive, brown and pale-green opal. Carnotite, the only identified uranium mineral, occurs as fracture coatings or fine layers in the opal; in places, no uranium minerals are visible in the radioactive opal. The opal layers are irregular in extent and thickness. The exposed length of the layers ranges from 8 to 1, 200 ft or more, and the thickness of the layers ranges from 0. 1 to 3. 9 ft. The uranium content of each opal layer, and of different parts of the same layer, differs widely. On the east side of Virgin Valley four of the seven observed opal layers, nos. 3, 4, 5, and 7, are more radioactive than the average; and the uranium content ranges from 0. 002 to 0. 12 percent. Two samples, taken 5 ft apart across opal layer no. 7, contained 0. 003 and 0. -049 percent uranium. On the west side of the valley only four of the fifteen observed opal layers, nos; 9, , 10, 14, and 15, are more radioactive than the average; and the uranium content ranges from 0. 004 to 0. 047 percent. Material of the highest grade was found in a small discontinuous layer of pale-green opal (no. 4) on the east side of Virgin Valley. The grade of this layer ranged from 0. 027 to 0. 12 percent uranium.

  5. Food Insecurity, Nutritional Status, and Factors Associated with Malnutrition among People Living with HIV/AIDS Attending Antiretroviral Therapy at Public Health Facilities in West Shewa Zone, Central Ethiopia.

    Science.gov (United States)

    Gebremichael, Delelegn Yilma; Hadush, Kokeb Tesfamariam; Kebede, Ermiyas Mulu; Zegeye, Robel Tezera

    2018-01-01

    In resource limited settings, HIV/AIDS patients lack access to sufficient nutritious foods, which poses challenges to the success of antiretroviral therapy. HIV/AIDS and malnutrition are still major public health problems in Ethiopia. Though measuring nutritional status is an essential part of ART program, little evidence exists on food insecurity and nutritional status of HIV/AIDS patients in Ethiopia. Hence, the study aimed to determine food insecurity and nutritional status and contextual determinants of malnutrition among HIV/AIDS patients in West Shewa Zone, Ethiopia. Institution-based cross-sectional study was conducted among HIV/ADIS patients who have been attending antiretroviral therapy at public health facilities in West Shewa Zone from April to May 2016, Ethiopia. The sample size was 512 and study participants were selected from each facilities using systematic random sampling method. Data were collected using pretested questionnaire by trained data collectors. Data were entered to Epi-Info 3.5.1 for Windows and analyzed using SPSS version 22. Logistic regression analyses were conducted to determine independent factors associated with malnutrition. Prevalence of malnutrition was 23.6% (95% CI: 19.7%-27.4%) and prevalence of household food insecurity was 35.2% (95% CI: 31.1%-39.0%). Factors significantly associated with malnutrition among HIV/AIDS patients were unemployment (AOR = 3.4; 95% CI: 1.8-5.3), WHO clinical stages III/IV (AOR = 3.3; 95% CI: 1.8-6.5), CD4 count less than 350 cells/ μ l (AOR = 2.0; 95% CI: 1.8-4.2), tuberculosis (AOR = 2.3; 95% CI: 1.3-4.9), duration on antiretroviral therapy (AOR = 1.8; 95% CI: 1.2-2.9), and household food insecurity (AOR = 5.3; 95% CI: 2.5-8.3). The findings revealed high prevalence of malnutrition and household food insecurity among HIV/AIDS patients attended ART. The negative interactive effects of undernutrition, inadequate food consumption, and HIV infection demand effective cross-sectorial integrated

  6. Food Insecurity, Nutritional Status, and Factors Associated with Malnutrition among People Living with HIV/AIDS Attending Antiretroviral Therapy at Public Health Facilities in West Shewa Zone, Central Ethiopia

    Directory of Open Access Journals (Sweden)

    Delelegn Yilma Gebremichael

    2018-01-01

    Full Text Available Background. In resource limited settings, HIV/AIDS patients lack access to sufficient nutritious foods, which poses challenges to the success of antiretroviral therapy. HIV/AIDS and malnutrition are still major public health problems in Ethiopia. Though measuring nutritional status is an essential part of ART program, little evidence exists on food insecurity and nutritional status of HIV/AIDS patients in Ethiopia. Hence, the study aimed to determine food insecurity and nutritional status and contextual determinants of malnutrition among HIV/AIDS patients in West Shewa Zone, Ethiopia. Methods. Institution-based cross-sectional study was conducted among HIV/ADIS patients who have been attending antiretroviral therapy at public health facilities in West Shewa Zone from April to May 2016, Ethiopia. The sample size was 512 and study participants were selected from each facilities using systematic random sampling method. Data were collected using pretested questionnaire by trained data collectors. Data were entered to Epi-Info 3.5.1 for Windows and analyzed using SPSS version 22. Logistic regression analyses were conducted to determine independent factors associated with malnutrition. Results. Prevalence of malnutrition was 23.6% (95% CI: 19.7%–27.4% and prevalence of household food insecurity was 35.2% (95% CI: 31.1%–39.0%. Factors significantly associated with malnutrition among HIV/AIDS patients were unemployment (AOR = 3.4; 95% CI: 1.8–5.3, WHO clinical stages III/IV (AOR = 3.3; 95% CI: 1.8–6.5, CD4 count less than 350 cells/μl (AOR = 2.0; 95% CI: 1.8–4.2, tuberculosis (AOR = 2.3; 95% CI: 1.3–4.9, duration on antiretroviral therapy (AOR = 1.8; 95% CI: 1.2–2.9, and household food insecurity (AOR = 5.3; 95% CI: 2.5–8.3. Conclusions. The findings revealed high prevalence of malnutrition and household food insecurity among HIV/AIDS patients attended ART. The negative interactive effects of undernutrition, inadequate food

  7. Geological literature on the San Joaquin Valley of California

    Science.gov (United States)

    Maher, J.C.; Trollman, W.M.; Denman, J.M.

    1973-01-01

    The following list of references includes most of the geological literature on the San Joaquin Valley and vicinity in central California (see figure 1) published prior to January 1, 1973. The San Joaquin Valley comprises all or parts of 11 counties -- Alameda, Calaveras, Contra Costa, Fresno, Kern, Kings, Madera, Merced, San Joaquin, Stanislaus, and Tulare (figure 2). As a matter of convenient geographical classification the boundaries of the report area have been drawn along county lines, and to include San Benito and Santa Clara Counties on the west and Mariposa and Tuolumne Counties on the east. Therefore, this list of geological literature includes some publications on the Diablo and Temblor Ranges on the west, the Tehachapi Mountains and Mojave Desert on the south, and the Sierra Nevada Foothills and Mountains on the east.

  8. Breathing Valley Fever

    Centers for Disease Control (CDC) Podcasts

    2014-02-04

    Dr. Duc Vugia, chief of the Infectious Diseases Branch in the California Department of Public Health, discusses Valley Fever.  Created: 2/4/2014 by National Center for Emerging and Zoonotic Infectious Diseases (NCEZID).   Date Released: 2/5/2014.

  9. Urinary Incontinence, Its Risk Factors, and Quality of Life: A Study among Women Aged 50 Years and above in a Rural Health Facility of West Bengal.

    Science.gov (United States)

    Biswas, Bijit; Bhattacharyya, Aritra; Dasgupta, Aparajita; Karmakar, Anubrata; Mallick, Nazrul; Sembiah, Sembagamuthu

    2017-01-01

    Urinary incontinence (UI) is a chronic debilitating disease which is often under reported, but laid significant impact on one's quality of life (QoL) thus is of public health importance. The aim of this study is to find out proportion of rural women have UI, its associated risk factors and treatment-seeking behavior, QoL of affected women. This was a cross-sectional clinic-based study conducted from October 2016 to January 2017 among 177 women aged 50 years or above attending a rural health facility with a structured schedule. Data were analyzed using appropriate statistical methods by SPSS (version 16). Forty-nine (27.7%) out of 177 women were found having UI. The most prevalent type of UI was stress UI (51.0%), followed by mixed UI (32.7%) and urge UI (16.3%). In bivariate analysis, study participants who were illiterate, having a history of prolonged labor, having a history of gynecological operation, normal vaginal deliveries (NVDs) (>3), diabetic, having chronic cough, having constipation, and having lower urinary tract symptoms (LUTS) had shown significantly greater odds of having UI. In multivariable illiteracy (adjusted odds ratio [AOR] - 2.41 [1.02-5.69]), NVDs (AOR - 3.37 [1.54-7.37]), a history of gynecological operation (AOR - 3.84 [1.16-12.66]), chronic cough (AOR - 2.69 [1.21-5.99]), LUTS (AOR - 2.63 [1.15-6.00]) remained significant adjusted with other significant variable in bivariate analysis. Those with mixed UI had 5.33 times higher odds having unfavorable QoL. Only 30.6% sought medical help. Treatment-seeking behavior shown negative correlation with QoL while fecal incontinence and LUTS shown possitive correlation. The study revealed that rural women are indeed at high risk of developing UI. Majority of them did not sought treatment for UI which is matter of concern. Generating awareness regarding UI may help to improve health-seeking behavior and QoL.

  10. Urinary incontinence, its risk factors, and quality of life: A study among women aged 50 years and above in a rural health facility of West Bengal

    Directory of Open Access Journals (Sweden)

    Bijit Biswas

    2017-01-01

    Full Text Available Context: Urinary incontinence (UI is a chronic debilitating disease which is often under reported, but laid significant impact on one's quality of life (QoL thus is of public health importance. Aims: The aim of this study is to find out proportion of rural women have UI, its associated risk factors and treatment-seeking behavior, QoL of affected women. Methods: This was a cross-sectional clinic-based study conducted from October 2016 to January 2017 among 177 women aged 50 years or above attending a rural health facility with a structured schedule. Data were analyzed using appropriate statistical methods by SPSS (version 16. Results: Forty-nine (27.7% out of 177 women were found having UI. The most prevalent type of UI was stress UI (51.0%, followed by mixed UI (32.7% and urge UI (16.3%. In bivariate analysis, study participants who were illiterate, having a history of prolonged labor, having a history of gynecological operation, normal vaginal deliveries (NVDs (>3, diabetic, having chronic cough, having constipation, and having lower urinary tract symptoms (LUTS had shown significantly greater odds of having UI. In multivariable illiteracy (adjusted odds ratio [AOR] - 2.41 [1.02–5.69], NVDs (AOR - 3.37 [1.54–7.37], a history of gynecological operation (AOR - 3.84 [1.16–12.66], chronic cough (AOR - 2.69 [1.21–5.99], LUTS (AOR - 2.63 [1.15–6.00] remained significant adjusted with other significant variable in bivariate analysis. Those with mixed UI had 5.33 times higher odds having unfavorable QoL. Only 30.6% sought medical help. Treatment-seeking behavior shown negative correlation with QoL while fecal incontinence and LUTS shown possitive correlation. Conclusions: The study revealed that rural women are indeed at high risk of developing UI. Majority of them did not sought treatment for UI which is matter of concern. Generating awareness regarding UI may help to improve health-seeking behavior and QoL.

  11. Landform-Sediment Assemblages Units of the Upper Mississippi River Valley

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — Wisconsinan and Holocene Landform-Sediment Assemblages of the Upper Mississippi River Valley. Knowledge of the spatial distribution of natural and cultural resources...

  12. Construction of mixed waste storage RCRA facilities, Buildings 7668 and 7669: Environmental assessment

    International Nuclear Information System (INIS)

    1994-04-01

    The Department of Energy has prepared an environmental assessment, DOE/EA-0820, to assess the potential environmental impacts of constructing and operating two mixed waste Resource Conservation and Recovery Act (RCRA) storage facilities. The new facilities would be located inside and immediately west of the security-fenced area of the Oak Ridge National Laboratory Hazardous Waste Management Area in Melton Valley, Tennessee. Based on the analyses in the environmental assessment, the Department has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969. Therefore, the preparation of an environmental impact statement is not required, and the Department is issuing this finding of no significant impact

  13. BPA/Lower Valley transmission project. Final environmental impact statement

    International Nuclear Information System (INIS)

    1998-06-01

    Bonneville Power Administration and Lower Valley Power and Light, Inc. propose to solve a voltage stability problem in the Jackson and Afton, Wyoming areas. Lower Valley buys electricity from BPA and then supplies it to the residences and businesses of the Jackson and Afton, Wyoming areas. BPA is considering five alternatives. For the Agency Proposed Action, BPA and Lower Valley would construct a new 115-kV line from BPA's Swan Valley Substation near Swan Valley in Bonneville County, Idaho about 58 km (36 miles) east to BPA's Teton Substation near Jackson in Teton County, Wyoming. The new line would be next to an existing 115-kV line. The Single-Circuit Line Alternative has all the components of the Agency Proposed Action except that the entire line would be supported by single-circuit wood pole H-frame structures. the Short Line Alternative has all the components of the Single-Circuit Line Alternative except it would only be half as long. BPA would also construct a new switching station near the existing right-of-way, west or north of Targhee Tap. Targhee Tap would then be removed. For the Static Var Compensation Alternative, BPA would install a Static Var Compensator (SVC) at Teton or Jackson Substation. An SVC is a group of electrical equipment placed at a substation to help control voltage on a transmission system. The No Action Alternative assumes that no new transmission line is built, and no other equipment is added to the transmission system

  14. DIOXINS AND ENDOMETRIOSIS: COHORT STUDY OF WOMEN IN WEST VIRGINIA

    Science.gov (United States)

    Kanawha Valley of West Virginia has a history of 2,3,7,8-tetrachlorodibenzo-p-dioxin contamination (dioxin, TCDD). The bulk of the dioxin found in this area appears to be derived from the production of 2,4,5-trichlorophenoxyacetic acid (2,4,5-T) and the disposal of associated wa...

  15. Processing the THOREX waste at the West Valley demonstration project

    International Nuclear Information System (INIS)

    Barnes, S.M.; Schiffhauer, M.A.

    1994-01-01

    This paper focuses on several options for neutralizing the THOREX and combining it with the PUREX wastes. Neutralization testing with simulated wastes (nonradioactive chemicals) was performed to evaluate the neutralization reactions and the reaction product generation. Various methods for neutralizing the THOREX solution were examined to determine their advantages and disadvantages relative to the overall project objectives and compatibility with the existing process. The primary neutralization process selection criteria were safety and minimizing the potential delays prior to vitrification. The THOREX neutralization method selected was direct addition to the high pH PUREX wastes within Tank 8D-2. Laboratory testing with simulated waste has demonstrated rapid neutralization of the THOREX waste acid. Test results for various direct addition scenarios has established the optimum process operating conditions which provide the largest safety margins

  16. Christmas Valley Renewable Energy Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Del Mar, Robert [Oregon Department of Energy, Salem, OR (United States)

    2017-05-22

    In partnership with the Oregon Military Department, the Department of Energy used the award to assess and evaluate renewable resources in a 2,622-acre location in Lake County, central Oregon, leading to future development of up to 200 MW of solar electricity. In partnership with the Oregon Military Department, the Department of Energy used the award to assess and evaluate renewable resources in a 2,622-acre location in Lake County, central Oregon, leading to future development of up to 200 MW of solar electricity. The Oregon Military Department (Military) acquired a large parcel of land located in south central Oregon. The land was previously owned by the US Air Force and developed for an Over-the-Horizon Backscatter Radar Transmitter Facility, located about 10 miles east of the town of Christmas Valley. The Military is investigating a number of uses for the site, including Research and Development (R&D) laboratory, emergency response, military operations, developing renewable energy and related educational programs. One of the key potential uses would be for a large scale solar photovoltaic power plant. This is an attractive use because the site has excellent solar exposure; an existing strong electrical interconnection to the power grid; and a secure location at a moderate cost per acre. The project objectives include: 1. Site evaluation 2. Research and Development (R&D) facility analysis 3. Utility interconnection studies and agreements 4. Additional on-site renewable energy resources analysis 5. Community education, outreach and mitigation 6. Renewable energy and emergency readiness training program for veterans

  17. 77 FR 33237 - Saline Valley Warm Springs Management Plan/Environmental Impact Statement, Death Valley National...

    Science.gov (United States)

    2012-06-05

    ... Valley Warm Springs Management Plan/Environmental Impact Statement, Death Valley National Park, Inyo... an Environmental Impact Statement for the Saline Valley Warm Springs Management Plan, Death Valley... analysis process for the Saline Valley Warm Springs Management Plan for Death Valley [[Page 33238...

  18. Landform Evolution of the Zanskar Valley, Ladakh Himalaya.

    Science.gov (United States)

    Chahal, P.; Kumar, A.; Sharma, P.; Sundriyal, Y.; Srivastava, P.

    2017-12-01

    Zanskar River flow from south-west to north-east, perpendicularly through Higher Himalayan crystalline sequences, Tethyan sedimentary sequences, and Indus Molasses; and finally merge with the Indus River at Nimu. Geologically, the Indus valley is bounded by Ladakh Batholith in the north and highly folded and thrusted Zanskar mountain ranges in the south. Sedimentary sequences of Zanskar ranges are largely of continental origin, which were uplifted and deformed via several north verging thrusts, where Zanskar counter thrust, Choksti and Indus-Bazgo thrusts are important thrust zone, and there is atleast 36 km of crustal shortening in the Zanskar section which continued from middle Miocene to the late Pleistocene. This shortening is accommodated mainly by north or north-east directed Zanskar backthrusts. Two major tributaries of Zanskar: Tsrapchu and Doda, flow in the headwaters, along the strike of South Tibetan Detachment System (STDs), an east-west trending regional fault. The present study incorporate field sedimentology, geomorphology and chronology of landform associated with Zanskar valley. In the upper Zanskar, alluvial fan, valley fill and strath terraces configured the major landforms with paleo-lake deposits­­­ in the area between the fans. The lower catchment, at the confluence of Zanskar and Indus rivers, exhibit mainly valley fill terraces and strath terraces. Chronology suggests diachronous aggradation in the upper and lower Zanskar catchments. In the upper Zanskar large scale valley aggradation took place with simultaneously fan progradation and flooding events from 45-15 ka. Luminescence chronology of the lower Zanskar indicates aggradation from 145-55 ka and 18-12 ka. The two aggradation basins are separated by a deep V-shaped gorge which is approximately 60 km long. The longitudinal profile of the Zanskar River shows several local convexities marking knick point zone, which suggests tectonically controlled topography.

  19. Preliminary hydrogeologic assessment near the boundary of the Antelope Valley and El Mirage Valley groundwater basins, California

    Science.gov (United States)

    Stamos, Christina L.; Christensen, Allen H.; Langenheim, Victoria

    2017-07-19

    The increasing demands on groundwater for water supply in desert areas in California and the western United States have resulted in the need to better understand groundwater sources, availability, and sustainability. This is true for a 650-square-mile area that encompasses the Antelope Valley, El Mirage Valley, and Upper Mojave River Valley groundwater basins, about 50 miles northeast of Los Angeles, California, in the western part of the Mojave Desert. These basins have been adjudicated to ensure that groundwater rights are allocated according to legal judgments. In an effort to assess if the boundary between the Antelope Valley and El Mirage Valley groundwater basins could be better defined, the U.S. Geological Survey began a cooperative study in 2014 with the Mojave Water Agency to better understand the hydrogeology in the area and investigate potential controls on groundwater flow and availability, including basement topography.Recharge is sporadic and primarily from small ephemeral washes and streams that originate in the San Gabriel Mountains to the south; estimates range from about 400 to 1,940 acre-feet per year. Lateral underflow from adjacent basins has been considered minor in previous studies; underflow from the Antelope Valley to the El Mirage Valley groundwater basin has been estimated to be between 100 and 1,900 acre-feet per year. Groundwater discharge is primarily from pumping, mostly by municipal supply wells. Between October 2013 and September 2014, the municipal pumpage in the Antelope Valley and El Mirage Valley groundwater basins was reported to be about 800 and 2,080 acre-feet, respectively.This study was motivated by the results from a previously completed regional gravity study, which suggested a northeast-trending subsurface basement ridge and saddle approximately 3.5 miles west of the boundary between the Antelope Valley and El Mirage Valley groundwater basins that might influence groundwater flow. To better define potential basement

  20. The California Valley grassland

    Science.gov (United States)

    Keeley, J.E.; Schoenherr, Allan A.

    1990-01-01

    Grasslands are distributed throughout California from Oregon to Baja California Norte and from the coast to the desert (Brown 1982) (Figure 1). This review will focus on the dominant formation in cismontane California, a community referred to as Valley Grassland (Munz 1959). Today, Valley Grassland is dominated by non-native annual grasses in genera such as Avena (wild oat), Bromus (brome grass), and Hordeum (barley), and is often referred to as the California annual grassland. On localized sites, native perennial bunchgrasses such as Stipa pultra (purple needle grass) may dominate and such sites are interpreted to be remnants of the pristine valley grassland. In northwestern California a floristically distinct formation of the Valley Grassland, known as Coast Prairie (Munz 1959) or Northern Coastal Grassland (Holland and Keil 1989) is recognized. The dominant grasses include many native perennial bunchgrasses in genera such as Agrostis, Calamagrostis, Danthonia, Deschampsia, Festuca, Koeleria and Poa (Heady et al. 1977). Non-native annuals do not dominate, but on some sites non-native perennials like Anthoxanthum odoratum may colonize the native grassland (Foin and Hektner 1986). Elevationally, California's grasslands extend from sea level to at leas 1500 m. The upper boundary is vague because montane grassland formations are commonly referred to as meadows; a community which Munz (1959) does not recognize. Holland and Keil (1989) describe the montane meadow as an azonal community; that is, a community restricted not so much to a particular climatic zone but rather controlled by substrate characteristics. They consider poor soil-drainage an over-riding factor in the development of montane meadows and, in contrast to grasslands, meadows often remain green through the summer drought. Floristically, meadows are composed of graminoids; Cyperaceae, Juncaceae, and rhizomatous grasses such as Agropyron (wheat grass). Some bunchgrasses, such as Muhlenbergia rigens, are

  1. Confirming competence of operators - A regulatory approach to fuel cycle facilities

    International Nuclear Information System (INIS)

    Vesely, M.; Sigetich, J.

    2013-01-01

    For the past 40 years the Canadian Nuclear Safety Commission (CNSC), formerly the Atomic Energy Control Board, has certified workers in nuclear facilities. The requirement for certified personnel has ensured that workers assigned to positions that have a direct impact on the safe operation of the facility are fully qualified to perform their duties. This certification regime is defined in the regulatory framework under which the CNSC operates. Traditionally, this certification regime has been applied to Reactor Operators, Shift Supervisors and Health Physicists in Nuclear Power Plants and research reactors as well as to Exposure Device Operators who use nuclear substances for the purposes of industrial radiography. Stemming from progress made in implementing risk-informed regulatory oversight activities as well as a formal suggestion from the International Atomic Energy Agency - International Regulatory Review Service (IRRS) conducted on the CNSC in 2009, a regulatory approach to confirming the competence of Operators at Fuel Cycle Facilities has been initiated by CNSC staff. In the first stage of the implementation of this new regulatory approach, the CNSC had Cameco Corporation implement a formal internal qualification programme for the UF6 Operators at its Port Hope Conversion Facility (PHCF) in Port Hope, Ontario. In the future, following a review of the results of the qualification programme at the PHCF, the CNSC staff will evaluate the need for the application of a similar regulatory approach to confirm the competence of the Operators at other Fuel Cycle Facilities in Canada. (authors)

  2. Methods for nondestructive assay holdup measurements in shutdown uranium enrichment facilities

    International Nuclear Information System (INIS)

    Hagenauer, R.C.; Mayer, R.L. II.

    1991-09-01

    Measurement surveys of uranium holdup using nondestructive assay (NDA) techniques are being conducted for shutdown gaseous diffusion facilities at the Oak Ridge K-25 Site (formerly the Oak Ridge Gaseous Diffusion Plant). When in operation, these facilities processed UF 6 with enrichments ranging from 0.2 to 93 wt % 235 U. Following final shutdown of all process facilities, NDA surveys were initiated to provide process holdup data for the planning and implementation of decontamination and decommissioning activities. A three-step process is used to locate and quantify deposits: (1) high-resolution gamma-ray measurements are performed to generally define the relative abundances of radioisotopes present, (2) sizable deposits are identified using gamma-ray scanning methods, and (3) the deposits are quantified using neutron measurement methods. Following initial quantitative measurements, deposit sizes are calculated; high-resolution gamma-ray measurements are then performed on the items containing large deposits. The quantitative estimates for the large deposits are refined on the basis of these measurements. Facility management is using the results of the survey to support a variety of activities including isolation and removal of large deposits; performing health, safety, and environmental analyses; and improving facility nuclear material control and accountability records. 3 refs., 1 tab

  3. Rift Valley Fever.

    Science.gov (United States)

    Hartman, Amy

    2017-06-01

    Rift Valley fever (RVF) is a severe veterinary disease of livestock that also causes moderate to severe illness in people. The life cycle of RVF is complex and involves mosquitoes, livestock, people, and the environment. RVF virus is transmitted from either mosquitoes or farm animals to humans, but is generally not transmitted from person to person. People can develop different diseases after infection, including febrile illness, ocular disease, hemorrhagic fever, or encephalitis. There is a significant risk for emergence of RVF into new locations, which would affect human health and livestock industries. Copyright © 2017 Elsevier Inc. All rights reserved.

  4. Design/Installation and Structural Integrity Assessment of Bethel Valley Low-Level Waste collection and transfer system upgrade for Building 3092 (central off-gas scrubber facility) at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1994-10-01

    This document describes and assesses planned modifications to be made to the Building 3092 Central Off-Gas Scrubber Facility of the Oak Ridge National Laboratory, Oak Ridge, Tennessee. The modifications are made in response to the requirements of 40CFR264 Subpart J, relating to environmental protection requirements for buried tank systems. The modifications include the provision of a new scrubber recirculation tank in a new, below ground, lined concrete vault, replacing an existing recirculation sump that does not provide double containment. A new buried, double contained pipeline is provided to permit discharge of spent scrubber recirculation fluid to the Central Waste Collection Header. The new vault, tank, and discharge line are provided with leak detection and provisions to remove accumulated liquid. Ne scrubber recirculation pumps, piping, and accessories are also provided. This assessment concludes that the planned modifications comply with applicable requirements of 40CFR264 Subpart J, as set forth in Appendix F to the Federal Facility Agreement, Docket No. 89-04-FF, covering the Oak Ridge Reservation. A formal design certification statement is included herein on Page 53, a certification covering the installation shall be executed prior to placing the modified facility into service

  5. The behavior of a container for UF6 under accident conditions

    International Nuclear Information System (INIS)

    Andreuccetti, P.; Aquaro, D.; Forasassi, G.

    1987-01-01

    Transport of uranium hexafluoride during the different phases of the fuel cycle is carried out using containers of various types that must meet the safety requirements provided for in the specific international regulations for this area. Qualification of the behavior of the 30B cylinder and its respective overpack under reference accident conditions for the purpose of design and utilization of such containers is currently a subject of interest on an international level, since it is being widely used in a number of countries. To contribute to this qualification process, a relatively complex research program was defined and developed, including, among other things, drop tests from 9 m on to an unyielding target, drop tests from a height of 1 m on to a cylindrical bar, and thermal tests in a furnace, all of which were carried out on two complete specimens of the same container with a simulated load. For analysis of the damage a series of leak tests and a water immersion test were developed to analyze the damage to the two specimens mentioned above and to a container of reduced dimensions designed for this purpose and equipped to reproduce conditions similar to the real conditions inside the container under investigation. Evaluation of the heat exchange conditions that could exist in the container given real contents of uranium hexafluoride was also conducted using a series of calculations carried out with the computer code TRUMP. The results of the different types of experiments and calculations performed and presented in detail in the present study have made it possible to draw useful conclusions for practical evaluation of the reliability of the container under investigation, also in view of the intended goal of container qualification as per the existing regulations for transport of radioactive material. 21 refs., 44 figs., 3 tabs

  6. Effect of separation factors on product assay of an ideal cascade composed of UF6 centrifuges

    International Nuclear Information System (INIS)

    Yamashita, S.; Okamoto, T.

    1975-01-01

    Kinetics equations using two assumptions describe an ideal cascade with accuracy. Using the kinetics equations, it is found that if the decrease of the separation factor in a selected stage is small, the product can be withdrawn at the product assay allowed for shipment without stopping the operation of the ideal cascade composed of the model centrifuges (approximately 4 kg SWU/yr, α = 1.135). Moreover, the fraction of centrifuges permissible to stop in case of an accident is found to be 4 to 5 percent of the model centrifuges in each stage in the enriching section of the ideal cascade. (U.S.)

  7. Ultra-low field NMR for detection and characterization of 235 UF6

    Energy Technology Data Exchange (ETDEWEB)

    Espy, Michelle A [Los Alamos National Laboratory; Magnelind, Per E [Los Alamos National Laboratory; Matlashov, Andrei N [Los Alamos National Laboratory; Urbaitis, Algis V [Los Alamos National Laboratory; Volegov, Petr L [Los Alamos National Laboratory

    2009-01-01

    We have demonstrated the first ultra-low field (ULF) nuclear magnetic resonance measurements of uranium hexafluoride (UF{sub 6}), both depleted and 70% enriched, which is used in the uranium enrichment process. A sensitive non-invasive detection system would have an important role in non-proliferation surveillance. A two-frequency technique was employed to remove the transients induced by rapidly switching off the 50 mT pre-polarization field. A mean transverse relaxation time T{sub 2} of 24 ms was estimated for the un-enriched UF{sub 6} sample measured at a mean temperature of 80 C. Nuclear magnetic resonance at ULF has several advantages including the ability to measure through metal, such as pipes, and simple magnetic field generation hardware. We present here recent data and discuss the potential for non-proliferation monitoring of enrichment and flow velocity.

  8. Monitoring the enrichment of the UF6 in the pipework of a gas centrifuge enrichment plant

    International Nuclear Information System (INIS)

    Packer, T.W.; Close, D.A.; Pratt, J.C.

    1987-01-01

    Research in the UK and the US has resulted in the development of a nondestructive assay instrument which can confirm the presence of low enriched uranium, on a rapid Go, No-Go basis, in cascade header pipework in the centrifuge enrichment plant at Capenhurst. The instrument is based on gamma-ray spectrometry and x-ray fluorescence analysis. It allows pipes, 120mm outer diameter, to be inspected in a total measurement time of approximately 30 minutes. This paper describes the techniques developed and includes the results obtained during a demonstration to, and preliminary in-plant measurements by, members of the IAEA and EURATOM Inspectorates at Capenhurst

  9. Field Trial of LANL On-Line Advanced Enrichment Monitor for UF6 GCEP

    Energy Technology Data Exchange (ETDEWEB)

    Ianakiev, Kiril D. [Los Alamos National Laboratory; Lombardi, Marcie [Los Alamos National Laboratory; MacArthur, Duncan W. [Los Alamos National Laboratory; Parker, Robert F. [Los Alamos National Laboratory; Smith, Morag K. [Los Alamos National Laboratory; Keller, Clifford [Los Alamos National Laboratory; Friend, Peter [URENCO; Dunford, Andrew [URENCO

    2012-07-13

    The outline of this presentation is: (1) Technology basis of on-line enrichment monitoring; (2) Timescale of trial; (3) Description of installed equipment; (4) Photographs; (5) Results; (6) Possible further development; and (7) Conclusions. Summary of the good things about the Advanced Enrichment Monitor (AEM) performance is: (1) High accuracy - normally better than 1% relative, (2) Active system as accurate as passive system, (3) Fast and accurate detection of enrichment changes, (4) Physics is well understood, (5) Elegant method for capturing pressure signal, and (6) Data capture is automatic, low cost and fast. A couple of negative things are: (1) Some jumps in measured passive enrichment - of around +2% relative (due to clock errors?); and (2) Data handling and evaluation is off-line, expensive and very slow. Conclusions are: (1) LANL AEM is being tested on E23 plant at Capenhurst; (2) The trial is going very well; (3) AEM could detect production of HEU at potentially much lower cost than existing CEMO; (4) AEM can measure {sup 235}U assay accurately; (5) Active system using X-Ray source would avoid need for pressure measurement; (6) Substantial work lies ahead to go from current prototype to a production instrument.

  10. Methods and results for stress analyses on 14-ton, thin-wall depleted UF6 cylinders

    International Nuclear Information System (INIS)

    Kirkpatrick, J.R.; Chung, C.K.; Frazier, J.L.; Kelley, D.K.

    1996-10-01

    Uranium enrichment operations at the three US gaseous diffusion plants produce depleted uranium hexafluoride (DUF 6 ) as a residential product. At the present time, the inventory of DUF 6 in this country is more than half a million tons. The inventory of DUF 6 is contained in metal storage cylinders, most of which are located at the gaseous diffusion plants. The principal objective of the project is to ensure the integrity of the cylinders to prevent causing an environmental hazard by releasing the contents of the cylinders into the atmosphere. Another objective is to maintain the cylinders in such a manner that the DUF 6 may eventually be converted to a less hazardous material for final disposition. An important task in the DUF 6 cylinders management project is determining how much corrosion of the walls can be tolerated before the cylinders are in danger of being damaged during routine handling and shipping operations. Another task is determining how to handle cylinders that have already been damaged in a manner that will minimize the chance that a breach will occur or that the size of an existing breach will be significantly increased. A number of finite element stress analysis (FESA) calculations have been done to analyze the stresses for three conditions: (1) while the cylinder is being lifted, (2) when a cylinder is resting on two cylinders under it in the customary two-tier stacking array, and (3) when a cylinder is resting on tis chocks on the ground. Various documents describe some of the results and discuss some of the methods whereby they have been obtained. The objective of the present report is to document as many of the FESA cases done at Oak Ridge for 14-ton thin-wall cylinders as possible, giving results and a description of the calculations in some detail

  11. The development of thermal models for a UF6 transport container in a fully engulfing fire

    International Nuclear Information System (INIS)

    Lomas, J.; Clayton, D.G.

    1993-01-01

    This paper describes the recent development work on a lumped-parameter model known as BURST3 created by BNFL to examine the physics of the heating problem. The predictions of this model were compared with the results obtained by Mallett in 1965, in which small (3.5, 5 and 8 inch diameter) cylinders were exposed to a fire. In general, the comparison is good; however there are some differences - particularly on the speed of response of the wall temperature to the heating from the fire. The model was further modified to allow conditions of partial and full insulation to be investigated. The partially insulated condition simulates the Japanese proposal to insulate the ends of the container only, leaving the cylinder bare between the stiffening rings. The results obtained with our modified model support the predictions of Abe et al that the partially-insulated cylinder will survive the fire test. The analysis of a completely insulated container has indicated that a minimal thickness of insulation provides sufficient protection to allow survival in the fire test. A discussion of additional improvements to the lumped-parameter model are presented. (J.P.N.)

  12. Thermal tests on UF6 containers and valves modelisation and extrapolation on real fire situations

    International Nuclear Information System (INIS)

    Duret, B.; Warniez, P.

    1988-12-01

    From realistic tests on containers or on valves, we propose a modelisation which we apply to 3 particular problems: resistance of a 48 Y containers, during a fire situation. Influence of the presence of a valve. Evaluation of a leakage through a breach, mechanically created before a fire

  13. High temperature experiments on a 4 tons UF6 container TENERIFE program

    Energy Technology Data Exchange (ETDEWEB)

    Casselman, C.; Duret, B.; Seiler, J.M.; Ringot, C.; Warniez, P.

    1991-12-31

    The paper presents an experimental program (called TENERIFE) whose aim is to investigate the behaviour of a cylinder containing UF{sub 6} when exposed to a high temperature fire for model validation. Taking into account the experiments performed in the past, the modelization needs further information in order to be able to predict the behaviour of a real size cylinder when engulfed in a 800{degrees}C fire, as specified in the regulation. The main unknowns are related to (1) the UF{sub 6} behaviour beyond the critical point, (2) the relationship between temperature field and internal pressure and (3) the equivalent conductivity of the solid UF{sub 6}. In order to investigate these phenomena in a representative way it is foreseen to perform experiments with a cylinder of real diameter, but reduced length, containing 4 tons of UF{sub 6}. This cylinder will be placed in an electrically heated furnace. A confinement vessel prevents any dispersion of UF{sub 6}. The heat flux delivered by the furnace will be calibrated by specific tests. The cylinder will be changed for each test.

  14. The uncertainty evaluation of measurement for uranium in UF_6 hydrolysate by potentiometric titration

    International Nuclear Information System (INIS)

    Jiang Haiying; Cheng Ruoyu; Meng Xiujun

    2014-01-01

    Based on the building of mathematical model, this paper analyzed the origin of component of indeterminacy of which the measurement result for uranium in uranium hexafluoride hydrolysate by potentiometric titration, also each uncertainty was calculated and the expanded uncertainty was given. By evaluation the result of the uranium concentration is that: (158.88 + 1.22) mgU/mL, K = 2, P = 95%. (authors)

  15. Presentation and interpretation of field experiments of gaseous UF6 releases in the atmosphere

    Energy Technology Data Exchange (ETDEWEB)

    Crabol, B.; Boulaud, D.; Deville-Cavelin, G. [CEA Centre d`Etudes de Fontenay-aux-Roses, 92 (France). Dept. de Protection de l`Environnement et des Installations; Geisse, C.; Iacona, L. [EURODIF, 26 - Pierrelatte (France)

    1992-12-31

    An experimental programme concerning the behaviour of UF{sub 6} released in gaseous phase in the atmosphere has been conducted in the years 1986-1989 by the french Atomic Energy Commission and Eurodif. Three field tests have been performed on the CEA/CESTA experimental site. These experiments permitted to get informations about the kinetics of the hydrolysis reaction of the UF{sub 6}, the behaviour of the hydrolysis products in the atmosphere and the granulometry of the solid particles.

  16. Effects of fire exposure on integrity of UF6 shipping cylinders

    International Nuclear Information System (INIS)

    Barlow, C.R.; Ziehlke, K.T.; Pryor, W.A.

    1985-01-01

    Two 2-1/2-ton steel cylinders for the transport of uranium hexafluoride within the United States nuclear fuel enrichment cycle were involved in a warehouse fire where portions of the cylinders were estimated to have reached a temperature of 1600 0 F (870 0 C). The cylinders were empty at the time of the fire and therefore were not in protective overpacks in which full product cylinders are handled while in transit. Hydrostatic tests to failure showed that the integrity of the cylinders was not degraded by exposure to the temperatures generated by the fire. They withstood test pressures in excess of 10 times the design pressure, and showed a volume expansion of 30% above the original capacity before rupture in a completely ductile fashion. Reference CAPE-323. 9 figs

  17. Long term effects of climate on human adaptation in the middle Gila River Valley, Arizona, America

    NARCIS (Netherlands)

    Zhu, T.; Ertsen, M.W.; Van de Giesen, N.C.

    2015-01-01

    The Hohokam, an irrigation-based society in the American South West, used the river valleys of the Salt and Gila Rivers between 500 and 1500 AD to grow their crops. Such irrigated crops are linking human agency, water sources and the general natural environment. In order to grow crops, water

  18. San Luis Valley - Taos Plateau Landscape-Level Cultural Heritage Values and Risk Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Wescott, Konstance L. [Argonne National Lab. (ANL), Argonne, IL (United States); Abplanalp, Jennifer M. [Argonne National Lab. (ANL), Argonne, IL (United States); Brown, Jeff [Bureau of Land Management, Monte Vista, CO (United States); Cantwell, Brian [Argonne National Lab. (ANL), Argonne, IL (United States); Dicks, Merrill [Bureau of Land Management, Taos, NM (United States); Fredericks, Brian [Bureau of Land Management, Monte Vista, CO (United States); Krall, Angie [US Forest Service, Creede, CO (United States); Rollins, Katherine E. [Argonne National Lab. (ANL), Argonne, IL (United States); Sullivan, Robert [Argonne National Lab. (ANL), Argonne, IL (United States); Valdez, Arnie [Univ. of New Mexico, Albuquerque, NM (United States); Verhaaren, Bruce [Argonne National Lab. (ANL), Argonne, IL (United States); Vieira, Joseph [Bureau of Land Management, Monte Vista, CO (United States); Walston, Lee [Argonne National Lab. (ANL), Argonne, IL (United States); Zvolanek, Emily A. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-10-01

    The San Luis Valley – Taos Plateau Landscape-Level Cultural Heritage Values and Risk Assessment (hereafter referred to as cultural assessment) is a BLM pilot project designed to see whether the Rapid Ecoregional Assessment (REA) framework (already established and implemented throughout many ecoregions in the West) can be applied to the cultural environment.

  19. Aburra Valley: Quo vadis?

    International Nuclear Information System (INIS)

    Hermelin, Michel

    2008-01-01

    These paper intents a brief description of the evolution that characterised natural risk prevention in the area surrounding the city of Medellin, Colombia, called the Aburra Valley. Both the lithological and structural composition of the Valle and its topographic and climatic conditions contribute to the abundance of destructive natural phenomena as earthquakes, slope movements, flash floods and, in a lower proportion, to floods. The population increase, which reaches now 3.5 millions inhabitants and the frequent occupation of sites exposed to natural hazards have resulted in numerous disasters. At present two entities called SIMPAD and DAPARD work on risk prevention, on city and department scale respectively. The amount of knowledge about physical environment is considered to be insufficient, together with regulations which should direct land use in accordance to restrictions related to natural hazards. Several seminars on this topic have already been carried out and the organisers of the present one, destined to commemorate the twentieth anniversary of the Villatina disaster, should make the decision to meet each two years. Furthermore, the creation of a permanent commission dedicated to study past events, to foster information broadcasting and to seek a better knowledge of the Aburra Valley, should be considered

  20. Spent fuel treatment at ANL-West

    International Nuclear Information System (INIS)

    Goff, K.M.; Benedict, R.W.; Levinskas, D.

    1994-01-01

    At Argonne National Laboratory-West (ANL-West) there are several thousand kilograms of metallic spent nuclear fuel containing bond sodium. This fuel will be treated in the Fuel Cycle Facility at ANL-West to produce stable waste forms for storage and disposal. The treatment operations will employ a pyrochemical process that also has applications for treating most of the fuel types within the Department of Energy complex. The treatment equipment is in its last stage of readiness, and operations will begin in the Fall of 1994