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Sample records for htgr reprocessing interim

  1. Gas-Cooled Reactor Programs annual progress report for period ending December 31, 1973. [HTGR fuel reprocessing, fuel fabrication, fuel irradiation, core materials, and fission product distribution; GCFR fuel irradiation and steam generator modeling

    Energy Technology Data Exchange (ETDEWEB)

    Kasten, P.R.; Coobs, J.H.; Lotts, A.L.

    1976-04-01

    Progress is summarized in studies relating to HTGR fuel reprocessing, refabrication, and recycle; HTGR fuel materials development and performance testing; HTGR PCRV development; HTGR materials investigations; HTGR fuel chemistry; HTGR safety studies; and GCFR irradiation experiments and steam generator modeling.

  2. HTGR fuel reprocessing pilot plant: results of the sequential equipment operation

    Energy Technology Data Exchange (ETDEWEB)

    Strand, J.B.; Fields, D.E.; Kergis, C.A.

    1979-05-01

    The second sequential operation of the HTGR fuel reprocessing cold-dry head-end pilot plant equipment has been successfully completed. Twenty standard LHGTR fuel elements were crushed to a size suitable for combustion in a fluid bed burner. The graphite was combusted leaving a product of fissile and fertile fuel particles. These particles were separated in a pneumatic classifier. The fissile particles were fractured and reburned in a fluid bed to remove the inner carbon coatings. The remaining products are ready for dissolution and solvent extraction fuel recovery.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-09-08

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

  4. Thorium utilization program quarterly progress report for the period ending February 29, 1976. [HTGR Fuel Recycle

    Energy Technology Data Exchange (ETDEWEB)

    1976-03-31

    This publication presents results of work performed under the National HTGR Fuel Recycle Program Thorium Utilization Program. The work reported includes the development of unit processes and equipment for reprocessing of HTGR fuel and the design and development of an integrated line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials. Work is also described on the development of the conceptual design of recycle facilities to identify the requirements of large-scale recycle of HTGR fuels and to incorporate the results of these studies in guidance of development activities for HTGR fuel recycle.

  5. HTGR fuel recycle development program. Quarterly progress report for the period ending August 31, 1978

    Energy Technology Data Exchange (ETDEWEB)

    1978-09-01

    The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel, the design and development of an integrated pilot line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials, and design work in support of Hot Engineering Tests (HET). Work is also described on tradeoff studies concerning the required design of facilities and equipment for the large-scale recycle of HTGR fuels in order to guide the development activities for HTGR fuel recycle.

  6. Noble gas isotope measurements for spent nuclear fuel reprocessing. IAEA Task 90/0A211 interim report

    Energy Technology Data Exchange (ETDEWEB)

    Hudson, G.B.

    1993-02-17

    The nuclear fission of actinides in reactor fuel produces large quantities of Kr and Xe as fission products. Because of the high levels of fission Kr and Xe, sample collection and analysis of noble gases for spent fuel diagnostic measurements is a simple, straight-forward technique. In modern reprocessing plants with continuous dissolvers, it will not be possible to use traditional methods for isolating input batches of fuel. This study investigates the feasibility of using noble gas isotope abundance measurements (isotope correlation techniques - ICT) to solve safeguards requirements. Noble gas measurements might be able to provide an independent analysis of Pu contained within dissolves fuel, on an individual fuel assembly basis. The isotopic composition of Kr and Xe in spent fuel reflects both the composition (isotope abundance ratios) of the fission products and the effects of neutron capture on those fission products. We have reviewed the available literature for noble gas analyses of spent reactor fuel. While references are made to noble gas isotope correlations over the last 20 years, we have found little if any detailed analysis of large data sets. The literature search did find several useful reports. Of these papers, one is particularly useful for evaluating noble gas isotopic compositions. The ``Benchmark-paper`` (1) contains 54 Kr and 56 Xe isotopic composition analyses for 4 different reactors with a variety of fuel enrichment factors. Burnup ranges from 8000 to 37000 MWd/tU. Besides the noble gas measurements, a variety of other measurements are reported (actinides and fission products).

  7. HTGR Fuel performance basis

    Energy Technology Data Exchange (ETDEWEB)

    Shamasundar, B.I.; Stansfield, O.M.; Jensen, D.D.

    1982-05-01

    The safety characteristics of the high-temperature gas-cooled reactor (HTGR) during normal and accident conditions are determined in part by HTGR fuel performance. During normal operation, less than 0.1% fuel failure occurs, primarily from defective particles. This low fuel failure fraction limits circulating activity to acceptable levels. During severe accidents, the radiological consequence is influenced by high-temperature fuel particle behavior. An empirical fuel failure model, supported by recent experimental data, is presented. The onset of significant fuel particle failure occurs at temperatures in excess of 1600/sup 0/C, and complete fuel failure occurs at 2660/sup 0/C. This indicates that the fuel is more retentive at higher temperatures than previously assumed. The more retentive nature of the fuel coupled with the high thermal capacitance of the core results in slow release of fission products from the core during severe accidents.

  8. Thorium utilization program progress report for January 1, 1974--June 30, 1975. [Reprocessing; refabrication; recycle fuel irradiations

    Energy Technology Data Exchange (ETDEWEB)

    Lotts, A.L.; Kasten, P.R.

    1976-05-01

    Work was carried out on the following: HTGR reprocessing development and pilot plant, refabrication development and pilot plant, recycle fuel irradiations, engineering and economic studies, and conceptual design of a commercial recycle plant. (DLC)

  9. Development of a procedure for evaluating the economics of process options in commercial HTGR fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, W.E.

    1976-05-01

    The report presented describes the status of and calculational procedures used in a machine code being developed for calculating costs of fresh fuel fabrication, chemical reprocessing, and refabrication of HTGR fuel. In its present state of development, the capability is confined principally to calculating annual mainstream and scrap recovery process throughputs in fresh fuel fabrication, chemical reprocessing, and refabrication. The code works from user-supplied reactor build schedules and fuel specifications to approximate changing fuel fabrication requirements over a 20-year (maximum) projection. The availability of a reprocessing facility may be delayed to some specified date beyond the first year of a projection. Some of the cost routines have also been programmed and are described.

  10. Probabilistic risk assessment of the modular HTGR plant. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Everline, C.J.; Bellis, E.A.; Vasquez, J.

    1986-06-01

    A preliminary probabilistic risk assessment (PRA) has been performed for the modular HTGR (MHTGR). This PRA is preliminary in the context that although it updates the PRA issued earlier to include a wider spectrum of events for Licensing Basis Events (LBE) selection, the final version will not be issued until later. The primary function of the assessment was to assure compliance with the NRC interim safety goals imposed by the top-level regulatory criteria, and utility/user requirements regarding public evacuation or sheltering. In addition, the assessment provides a basis for designer feedback regarding reliability allocations and barrier retention requirements as well as providing a basis for the selection of licensing basis events (LBEs) and the safety classification of structures, systems, and components. The assessment demonstrates that both the NRC interim safety goals and utility/user imposed sheltering/evacuation requirements are satisfied. Moreover, it is not anticipated that design changes introduced will jeopardize compliance with the interim safety goals or utility/user requirements. 61 refs., 48 figs., 24 tabs.

  11. HTGR Cost Model Users' Manual

    Energy Technology Data Exchange (ETDEWEB)

    A.M. Gandrik

    2012-01-01

    The High Temperature Gas-Cooler Reactor (HTGR) Cost Model was developed at the Idaho National Laboratory for the Next Generation Nuclear Plant Project. The HTGR Cost Model calculates an estimate of the capital costs, annual operating and maintenance costs, and decommissioning costs for a high-temperature gas-cooled reactor. The user can generate these costs for multiple reactor outlet temperatures; with and without power cycles, including either a Brayton or Rankine cycle; for the demonstration plant, first of a kind, or nth of a kind project phases; for a single or four-pack configuration; and for a reactor size of 350 or 600 MWt. This users manual contains the mathematical models and operating instructions for the HTGR Cost Model. Instructions, screenshots, and examples are provided to guide the user through the HTGR Cost Model. This model was design for users who are familiar with the HTGR design and Excel. Modification of the HTGR Cost Model should only be performed by users familiar with Excel and Visual Basic.

  12. HTGR generic technology program plan (FY 80)

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    Purpose of the program is to develop base technology and to perform design and development common to the HTGR Steam Cycle, Gas Turbine, and Process Heat Plants. The generic technology program breaks into the base technology, generic component, pebble-bed study, technology transfer, and fresh fuel programs. (DLC)

  13. Modular HTGR Safety Basis and Approach

    Energy Technology Data Exchange (ETDEWEB)

    Thomas Hicks

    2011-08-01

    The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) capable of producing electricity and/or high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) process, as recommended in the NGNP Licensing Strategy - A Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy [DOE/NRC 2008]. Nuclear Regulatory Commission (NRC) licensing of the NGNP plant utilizing this process will demonstrate the efficacy for licensing future HTGRs for commercial industrial applications. This information paper is one in a series of submittals that address key generic issues of the priority licensing topics as part of the process for establishing HTGR regulatory requirements. This information paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach with the NRC staff and public stakeholders. The NGNP project does not expect to receive comments on this information paper because other white papers are addressing key generic issues of the priority licensing topics in greater detail.

  14. Improving ATLAS reprocessing software

    CERN Document Server

    Novak, Tadej

    2014-01-01

    For my CERN Summer Student programme I have been working with ATLAS reprocessing group. Data taken at ATLAS experiment is not only processed after being taken, but is also reprocessed multiple times afterwards. This allows applying new alignments, calibration of detector and using improved or faster algorithms. Reprocessing is usually done in campaigns for different periods of data or for different interest groups. The idea of my project was to simplify the definition of tasks and monitoring of their progress. I created a LIST configuration files generator script in Python and a monitoring webpage for tracking current reprocessing tasks.

  15. HTGR generic technology program. Semiannual report ending March 31, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-05-01

    This document reports the technical accomplishments on the HTGR Generic Technology Program at General Atomic during the first half of FY-80. It covers a period when the design direction of the National HTGR Program is in the process of an overall review. The HTGR Generic Technology Program activities have continued so as to provide the basic technology required for all HTGR applications. The activities include the need to develop an MEU fuel and the need to qualify materials and components for the higher temperatures of the gas turbine and process heat plants.

  16. Status of HTGR development program in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Sanokawa, Konomo; Fujishiro, Toshio; Tanaka, Toshiyuki; Miyamoto, Yoshiaki; Shiozawa, Shusaku; Okubo, Minoru [Japan Atomic Energy Research Institute JAERI, Ibaraki-ken (Japan)

    1998-09-01

    Considering global warming due to emission of greenhouse gases it is essentially important to make efforts to obtain a more reliable and stable energy supply by extending use of nuclear energy which includes high temperature heat generated by nuclear power plants. Hence, efforts should be made continuously to establish and upgrade technologies of High Temperature Gas-cooled Reactor (HTGR), which can supply high temperature heat with high thermal efficiency and high heat-utilizing rate. It is also expected that making basic research at high temperature using HTGR will contribute to innovative basic research in the future. The construction of the High Temperature engineering Test Reactor (HTTR), which is an HTGR with the maximum helium gas coolant temperature of 9500C at the reactor outlet, was decided by the Atomic Energy Commission of Japan (JAEC) in 1987 and successfully completed by the Japan Atomic Energy Research Institute (JAERI). Functional tests of the HTTR have been carried out since May 1996. First criticality will be attained in the near future. The project is intended to establish and upgrade the technology basis necessary for HTGR developments. Heat utilization system is planned to be connected to the HTTR and demonstrated at the initial stage of the second core. Steam reforming of methane for hydrogen production is adopted as an HTTR heat utilization system. The JAERI also plans to conduct material and fuel irradiation tests as innovative basic research as well as safety demonstration tests after attaining coolant gas temperature of 950C. Preliminary tests on selected research subjects such as new semiconductors, superconductors and composite material development, have been carried out at high temperature and under irradiation. This paper describes major features of the HTTR, present status of its construction and prospects on test programs using the HTTR, and the other activity on HTGRs in Japan. 2 refs.

  17. HTGR Mechanistic Source Terms White Paper

    Energy Technology Data Exchange (ETDEWEB)

    Wayne Moe

    2010-07-01

    The primary purposes of this white paper are: (1) to describe the proposed approach for developing event specific mechanistic source terms for HTGR design and licensing, (2) to describe the technology development programs required to validate the design methods used to predict these mechanistic source terms and (3) to obtain agreement from the NRC that, subject to appropriate validation through the technology development program, the approach for developing event specific mechanistic source terms is acceptable

  18. Nuclear Fuel Reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Michael F. Simpson; Jack D. Law

    2010-02-01

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

  19. Processes for the control of /sup 14/CO/sub 2/ during reprocessing

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-01-01

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

  20. Processes for the control of /sup 14/CO/sub 2/ during reprocessing

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-07-01

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

  1. HTGR Application Economic Model Users' Manual

    Energy Technology Data Exchange (ETDEWEB)

    A.M. Gandrik

    2012-01-01

    The High Temperature Gas-Cooled Reactor (HTGR) Application Economic Model was developed at the Idaho National Laboratory for the Next Generation Nuclear Plant Project. The HTGR Application Economic Model calculates either the required selling price of power and/or heat for a given internal rate of return (IRR) or the IRR for power and/or heat being sold at the market price. The user can generate these economic results for a range of reactor outlet temperatures; with and without power cycles, including either a Brayton or Rankine cycle; for the demonstration plant, first of a kind, or nth of a kind project phases; for up to 16 reactor modules; and for module ratings of 200, 350, or 600 MWt. This users manual contains the mathematical models and operating instructions for the HTGR Application Economic Model. Instructions, screenshots, and examples are provided to guide the user through the HTGR Application Economic Model. This model was designed for users who are familiar with the HTGR design and Excel and engineering economics. Modification of the HTGR Application Economic Model should only be performed by users familiar with the HTGR and its applications, Excel, and Visual Basic.

  2. Safety status of HTGR structural ceramics

    Energy Technology Data Exchange (ETDEWEB)

    Wei, G.C.; DiStefano, J.R.

    1977-10-01

    The objective of this study is to assess the safety status of structural ceramics proposed for use in an HTGR. In this report the mechanical and physical properties of the proposed structural ceramics are reviewed, and the current design and material specifications are discussed. Potential safety problem areas are identified. Analytical models for creep deformation, devitrification, compatibility, fatigue, and thermal insulation stability are based on published work in the literature. The predictions made are generally based upon extrapolations to HTGR conditions. The data indicate that creep deformation in silicon nitride and alumina ceramics is acceptable if the purity and composition are properly controlled. Devitrification and creep in fused silica used in the core support structure and the thermal barrier system could be excessive. Thermodynamic data indicate that silicon nitride will be incompatible with the graphite seat used in the design. Under normal reactor operating conditions, or during start-up and shutdown, static fatigue and thermal shock effects in all three members of the core support structural ceramics could cause reductions in safety factors.

  3. HTGR Economic / Business Analysis and Trade Studies Market Analysis for HTGR Technologies and Applications

    Energy Technology Data Exchange (ETDEWEB)

    Richards, Matt [Ultra Safe Nuclear Corporation, Los Alamos, NM (United States); Hamilton, Chris [Ultra Safe Nuclear Corporation, Los Alamos, NM (United States)

    2013-11-01

    This report provides supplemental information to the assessment of target markets provided in Appendix A of the 2012 Next Generation Nuclear Plant (NGNP) Industry Alliance (NIA) business plan [NIA 2012] for deployment of High Temperature Gas-Cooled Reactors (HTGRs) in the 2025 – 2050 time frame. This report largely reiterates the [NIA 2012] assessment for potential deployment of 400 to 800 HTGR modules (100 to 200 HTGR plants with 4 reactor modules) in the 600-MWt class in North America by 2050 for electricity generation, co-generation of steam and electricity, oil sands operations, hydrogen production, and synthetic fuels production (e.g., coal to liquids). As the result of increased natural gas supply from hydraulic fracturing, the current and historically low prices of natural gas remain a significant barrier to deployment of HTGRs and other nuclear reactor concepts in the U.S. However, based on U.S. Department of Energy (DOE) Energy Information Agency (EIA) data, U.S. natural gas prices are expected to increase by the 2030 – 2040 timeframe when a significant number of HTGR modules could be deployed. An evaluation of more recent EIA 2013 data confirms the assumptions in [NIA 2012] of future natural gas prices in the range of approximately $7/MMBtu to $10/MMBtu during the 2030 – 2040 timeframe. Natural gas prices in this range will make HTGR energy prices competitive with natural gas, even in the absence of carbon-emissions penalties. Exhibit ES-1 presents the North American projections in each market segment including a characterization of the market penetration logic. Adjustments made to the 2012 data (and reflected in Exhibit ES-1) include normalization to the slightly larger 625MWt reactor module, segregation between steam cycle and more advanced (higher outlet temperature) modules, and characterization of U.S. synthetic fuel process applications as a separate market segment.

  4. Using SA508/533 for the HTGR Vessel Material

    Energy Technology Data Exchange (ETDEWEB)

    Larry Demick

    2012-06-01

    This paper examines the influence of High Temperature Gas-cooled Reactor (HTGR) module power rating and normal operating temperatures on the use of SA508/533 material for the HTGR vessel system with emphasis on the calculated times at elevated temperatures approaching or exceeding ASME Code Service Limits (Levels B&C) to which the reactor pressure vessel could be exposed during postulated pressurized and depressurized conduction cooldown events over its design lifetime.

  5. HTGR Generic Technology Program. Semiannual report for the period ending March 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    This document reports the technical accomplishments on the HTGR Generic Technology Program at General Atomic during the first half of FY-79. It covers a period when the major design direction of the National HTGR Program is in the process of changing from the HTGR-SC emphasis to an HTGR-GT emphasis in the near term. The HTGR Generic Technology Program activities have been redirected to ensure that the tasks covered are supportive of this changing emphasis in HTGR applications. The activities include the need to develop a medium enriched uranium (MEU) fuel, and the need to qualify materials and components for the higher temperatures of the gas turbine plant.

  6. HTGR Generic Technology Program. Semiannual report for the period ending September 30, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-11-01

    The technical accomplishments on the HTGR Generic Technology Program at General Atomic during the second half of FY-79 are reported. The report covers a period when the major design direction of the National HTGR Program is in the process of changing from the HTGR-SC emphasis to an HTGR-GT emphasis in the near term. The HTGR Generic Technology Program activities have been redirected to ensure that the tasks covered are supportive of this changing emphasis in HTGR applications. The activities include the need to develop an MEU fuel, and the need to qualify materials and components for the higher temperatures of the gas turbine plant.

  7. Reprocessing weld and method

    Energy Technology Data Exchange (ETDEWEB)

    Killian, M.L.; Lewis, H.E.

    1993-08-03

    A process is described for improving the fatigue resistance of a small primary structural weld at a joint between structural members of a weldment, the weld having been made with the welding energy input of E[sub 1], the process comprising: applying a reprocessing weld on at least a portion of either one or both toes of the primary structural weld, thereby covering said toe portion, the reprocessing weld containing a filler metal and having a cross-sectional area which is less than the corresponding cross-sectional area of the primary structural weld, the reprocessing weld extending onto the face of the primary structural weld at one side of the toe portion covered and onto the structural member at the other side of the toe portion covered, and the total welding energy input, E[sub 2], used in said reprocessing the primary structural weld being less than the welding energy input E[sub 1] of the primary structural weld.

  8. Gas Reactor International Cooperative Program. Interim report: assessment of gas-cooled reactor economics

    Energy Technology Data Exchange (ETDEWEB)

    1979-08-01

    The merits of introducing Pebble Bed Gas Reactors (PBRs) into the existing US electric generating sector are discussed. Information is presented concerning an economic model; nuclear fuel costs; capital cost targets; time comparison of nuclear power costs; introduction scenarios; domestic economic incentives; the selection of a discount rate for national energy supply studies; nuclear fuel cycle cost calculation code RAMMER; and PBR and HTGR fabrication and reprocessing costs.

  9. Case outsourcing medical device reprocessing.

    Science.gov (United States)

    Haley, Deborah

    2004-04-01

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

  10. HTGR-GT and electrical load integrated control

    Energy Technology Data Exchange (ETDEWEB)

    Chan, T.; Openshaw, F.; Pfremmer, D.

    1980-05-01

    A discussion of the control and operation of the HTGR-GT power plant is presented in terms of its closely coupled electrical load and core cooling functions. The system and its controls are briefly described and comparisons are made with more conventional plants. The results of analyses of selected transients are presented to illustrate the operation and control of the HTGR-GT. The events presented were specifically chosen to show the controllability of the plant and to highlight some of the unique characteristics inherent in this multiloop closed-cycle plant.

  11. Estimation and control in HTGR fuel rod fabrication

    Energy Technology Data Exchange (ETDEWEB)

    Downing, D J; Bailey, M J

    1980-01-01

    A control algorithm has been derived for a HTGR Fuel Rod Fabrication Process utilizing the method of Box and Jenkins. The estimator is a Kalman filter and is compared with a Least Square estimator and a standard control chart. The effects of system delays are presented.

  12. Status of HTGR-related activities in Germany

    Energy Technology Data Exchange (ETDEWEB)

    Von Lensa, W.; Kugeler, K. [Institut fuer Sicherheitsforschung und Reaktortechnik, Forschungszentrum Juelich GmbH, Juelich (Germany)

    1998-09-01

    The industrial activities towards the market introduction of High-Temperature Gas-Cooled Reactors as well as the related R and D programmes in Germany were stopped at the beginning of this decade in conjunction with the decision not to continue the commissioning of the 300 MWel demonstration reactor THTR 300 in Hamm-Uentrop. The 15 MWel test reactor AVR at the site of the research centre in Juelich was already shut down before, in the expectation of a further successful operation of the THTR 300. The HTGR-related activities in Germany are mainly oriented now to the decommissioning or safe closure of both plants and to the disposal of the irradiated fuel elements. Complementary to the commercial projects on evolutionary Light-Water Reactor Concepts, additional generic R and D is being performed in Germany with the aim to identify the fundamentals of an approach towards `catastrophy-free` innovative nuclear reactor technologies as being requested by the new German Atomic Act of 1994 even for beyond design basis accidents formerly assumed. The proven safety characteristics and principles of HTGRs form a sound start-up point for such considerations aiming to self-acting (passive) nuclear, thermal, chemical and mechanical stability of the primary circuit and an independence of the fission product barriers. Basic Technologies and safety principles originating from HTGR-related R and D are partially also relevant for the prevention and mitigation of severe accidents of other reactor types and vice versa as those scenarios are also characterised by high temperatures and highly corrosive conditions offering new application potentials e.g., for high-tech ceramic materials. The technology of coated-particles might offer significant advantages for safety and operational aspects as well as for an effective burning of plutonium and for direct disposal even beyond the HTGR frame. The use of thorium is being re-discussed as an effective tool to burn plutonium and reduce the

  13. Occupational hazard during hemodialyzers reprocessing

    OpenAIRE

    Heloisa Helena Karnas Hoefel; Liana Lautert

    2014-01-01

    Backgound and Objectives: The observation of hazards during processing of hemodialyzers showed the need to study these events. The aim of the study was to identify occupational accidents and hazards recognized by nursing professionals in the reprocessing of hemodialyzers. Methods: It was performed an exploratory-descriptive study in a haemodialysis unit of a university hospital using recall. Six nurses and fifteen nursing technicians answered the questions about risks in re-processing dialyze...

  14. HTGR Generic Technology Program. Semiannual report for the period ending September 30, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-11-01

    This document reports the technical accomplishments on the HTGR Generic Technology Program at General Atomic during the second half of FY-80. It covers a period when the design direction of the National HTGR Program is in the process of an overall review. The HTGR Generic Technology Program activities have continued so as to provide the basic technology required for all HTGR applications. The activities include the need to develop an LEU fuel and the need to qualify materials and components for the higher temperatures of the gas turbines and process heat plants.

  15. One-fifth-scale dowel force test report. [HTGR

    Energy Technology Data Exchange (ETDEWEB)

    Rakowski, J.E.

    1979-05-01

    The report presents the results of the second seismic test program conducted on the 1/5-scale, full-array model of the 3000 MW(t) high-temperature gas-cooled reactor (HTGR) core. The test conditions consisted of uniaxial horizontal sine sweeps at 0.5 g fixture acceleration, sine dwells at various g-levels and frequencies, and time history excitations at several g-levels conforming to NRC seismic response spectra for seismic category 1 components. The main objective of the program was to measure fuel element and reflector block dowel forces. In addition, measurements were taken for core damping, fuel element collision, and fuel element and reflector block rocking angles. These data were required to provide a broader base for validating analytical computer models used to calculate HTGR core design loads.

  16. HTGR core model response to simultaneous horizontal and vertical excitations

    Energy Technology Data Exchange (ETDEWEB)

    Bezler, P.; Curreri, J.R.

    1978-01-01

    An experimental program was undertaken to investigate the effects of simultaneous horizontal and vertical excitation on the response of the HTGR core. The tests were conducted with block array models of the core excited with both fixed frequency and sweeping frequency harmonic forcing functions. The effects on both free standing block arrays and on block arrays preloaded in the vertical direction were investigated. The results of the tests as well as their importance as regards to the full core response, are presented.

  17. Evaluation of EPRI nuclear power division research topics supportive of HTGR technology

    Energy Technology Data Exchange (ETDEWEB)

    1978-10-06

    For HTGR commercialization studies, an LWR/HTGR Technology Transfer program was devised. Candidate programs were identified out of a total of 208 EPRI NPD (Nuclear Power Division) projects. Of these, 26 project areas presented the highest probability for technology transfer. (DLC)

  18. HTGR Fuel Technology Program. Semiannual report for the period ending March 31, 1983

    Energy Technology Data Exchange (ETDEWEB)

    1983-07-01

    This document reports the technical accomplishments of the HTGR Fuel Technology Program at GA Technologies Inc. during the first half of FY 83. The activities include the fuel process, fuel materials, fuel cycle, fission product transport, core component verification, and core technology transfer tasks necessary to support the design and development of a steam cycle/cogeneration (SC/C) version of the HTGR.

  19. Interim design status and operational report for remote handling fixtures: primary and secondary burners

    Energy Technology Data Exchange (ETDEWEB)

    Burgoyne, R.M.

    1976-12-01

    The HTGR reprocessing flowsheet consists of two basic process elements: (1) spent fuel crushing and burning and (2) solvent extraction. Fundamental to these elements is the design and development of specialized process equipment and support facilities. A major consideration of this design and development program is equipment maintenance: specifically, the design and demonstration of selected remote maintenance capabilities and the integration of these into process equipment design. This report documents the current status of the development of remote handling and maintenance fixtures for the primary and secondary burners.

  20. HTGR-INTEGRATED COAL TO LIQUIDS PRODUCTION ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    Anastasia M Gandrik; Rick A Wood

    2010-10-01

    As part of the DOE’s Idaho National Laboratory (INL) nuclear energy development mission, the INL is leading a program to develop and design a high temperature gas-cooled reactor (HTGR), which has been selected as the base design for the Next Generation Nuclear Plant. Because an HTGR operates at a higher temperature, it can provide higher temperature process heat, more closely matched to chemical process temperatures, than a conventional light water reactor. Integrating HTGRs into conventional industrial processes would increase U.S. energy security and potentially reduce greenhouse gas emissions (GHG), particularly CO2. This paper focuses on the integration of HTGRs into a coal to liquids (CTL) process, for the production of synthetic diesel fuel, naphtha, and liquefied petroleum gas (LPG). The plant models for the CTL processes were developed using Aspen Plus. The models were constructed with plant production capacity set at 50,000 barrels per day of liquid products. Analysis of the conventional CTL case indicated a potential need for hydrogen supplementation from high temperature steam electrolysis (HTSE), with heat and power supplied by the HTGR. By supplementing the process with an external hydrogen source, the need to “shift” the syngas using conventional water-gas shift reactors was eliminated. HTGR electrical power generation efficiency was set at 40%, a reactor size of 600 MWth was specified, and it was assumed that heat in the form of hot helium could be delivered at a maximum temperature of 700°C to the processes. Results from the Aspen Plus model were used to perform a preliminary economic analysis and a life cycle emissions assessment. The following conclusions were drawn when evaluating the nuclear assisted CTL process against the conventional process: • 11 HTGRs (600 MWth each) are required to support production of a 50,000 barrel per day CTL facility. When compared to conventional CTL production, nuclear integration decreases coal

  1. Recent developments in graphite. [Use in HTGR and aerospace

    Energy Technology Data Exchange (ETDEWEB)

    Cunningham, J.E.

    1983-01-01

    Overall, the HTGR graphite situation is in excellent shape. In both of the critical requirements, fuel blocks and support structures, adequate graphites are at hand and improved grades are sufficiently far along in truncation. In the aerospace field, GraphNOL N3M permits vehicle performance with confidence in trajectories unobtainable with any other existing material. For fusion energy applications, no other graphite can simultaneously withstand both extreme thermal shock and neutron damage. Hence, the material promises to create new markets as well as to offer a better candidate material for existing applications.

  2. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-06-01

    This Interim Report summarizes the research and development activities of the Superconducting Super Collider project carried out from the completion of the Reference Designs Study (May 1984) to June 1985. It was prepared by the SSC Central Design Group in draft form on the occasion of the DOE Annual Review, June 19--21, 1985. Now largely organized by CDG Divisions, the bulk of each chapter documents the progress and accomplishments to date, while the final section(s) describe plans for future work. Chapter 1, Introduction, provides a basic brief description of the SSC, its physics justification, its origins, and the R&D organization set up to carry out the work. Chapter 2 gives a summary of the main results of the R&D program, the tasks assigned to the four magnet R&D centers, and an overview of the future plans. The reader wishing a quick look at the SSC Phase I effort can skim Chapter 1 and read Chapter 2. Subsequent chapters discuss in more detail the activities on accelerator physics, accelerator systems, magnets and cryostats, injector, detector R&D, conventional facilities, and project planning and management. The magnet chapter (5) documents in text and photographs the impressive progress in successful construction of many model magnets, the development of cryostats with low heat leaks, and the improvement in current-carrying capacity of superconducting strand. Chapter 9 contains the budgets and schedules of the COG Divisions, the overall R&D program, including the laboratories, and also preliminary projections for construction. Appendices provide information on the various panels, task forces and workshops held by the CDG in FY 1985, a bibliography of COG and Laboratory reports on SSC and SSC-related work, and on private industrial involvement in the project.

  3. Containment atmosphere response (CAR) program. Second status report. [HTGR

    Energy Technology Data Exchange (ETDEWEB)

    Landoni, J.A.

    1980-03-01

    This report contains a summary of the work performed under the Containment Atmosphere Response (CAR) Program of the High-Temperature Gas-Cooled Reactor (HTGR) Safety Research Task since the publication of the previous status report (February 1978). The work concentrated on development of models describing containment phenomena during core heatup in support of probabilistic risk assessment studies. Models were completed for fission product iodine sorption on coated surfaces, diffusivity and retentivity of untreated concrete, iodine interaction with condensing steam on the containment atmosphere boundaries, and the cleanup filter system. These models were incorporated into a new computer program called CARCAS, a substantial extension of the CNTB computer program, and applied to Accident Initiation and Progression Analysis for Phase II core heatup sequences. Development was begun on models describing the postulated behavior of particulate fission products or aerosols within and leaking out of the containment.

  4. Optimum power generation from an HTGR heat source

    Energy Technology Data Exchange (ETDEWEB)

    Op het Veld, R.P.; Van Buijtenen, J.P. [Section Thermal Power Engineering - Gas Turbines, Delft University of Technology, Delft (Netherlands)

    1998-09-01

    A preliminary design study on the thermal conversion system for an HTGR of 40 MWth has been carried out. As the fluid in a Helium cooled HTR cycle is gaseous, the conversion of heat to power is a closed Brayton Cycle. The design process of the energy conversion system and the rotating components can be divided in two phases: (1) a thermodynamic design study. The gas turbine design conditions for optimal energy conversion have to be defined. These are pressure ratio and mass flow of the gas turbine; and (2) preliminary design of the turbomachinery. The optimal architecture of the gas turbine is defined. Assumptions made in phase 1 for turbomachinery efficiencies can be verified

  5. Distribution and transport of tritium in the Peach Bottom HTGR

    Energy Technology Data Exchange (ETDEWEB)

    Wichner, R.P.; Dyer, F.F.

    1979-08-01

    This report completes the first phase of a two-phase effort to describe and understand tritium production and movement in an operating high-temperature gas-cooled reactor (HTGR) system. The principal objective of phase 1 is to report the findings on tritium concentrations in core components acquired during the Peach Bottom Surveillance Program, which dealt with fission product migration in general, and a follow-on task devoted specifically to tritium. Administrative procedures are being developed for the second phase of the work to be performed in the Federal Republic of Germany under the auspices of the international umbrella agreement on gas-cooled reactor (GCR) development. In this effort, computer model predictions of tritium transport in the reactor system will be compared with observed concentration levels.

  6. Commercial Nuclear Reprocessing in the United States

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-09-09

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

  7. Occupational hazard during hemodialyzers reprocessing

    Directory of Open Access Journals (Sweden)

    Heloisa Helena Karnas Hoefel

    2014-04-01

    Full Text Available Backgound and Objectives: The observation of hazards during processing of hemodialyzers showed the need to study these events. The aim of the study was to identify occupational accidents and hazards recognized by nursing professionals in the reprocessing of hemodialyzers. Methods: It was performed an exploratory-descriptive study in a haemodialysis unit of a university hospital using recall. Six nurses and fifteen nursing technicians answered the questions about risks in re-processing dialyzers. Results: 44 occupational hazards were reported: 30 (70% with the participant and 14 (30% with colleagues. Eleven (25% were touching clean surfaces with blood visible on gloves and ten (23% direct contact with blood. Disinfectants appeared in fifteen (34% cases: five contacts with the skin and mucous membranes, six to toxic fumes and three unspecified. Two reports about touching surfaces possibly contaminated but no visible blood. Conclusion: The risks reported were those that could be seen or felt, such as blood spatter and germicides, strong odors. Risks not visible were rare. KEYWORDS: Occupational risks. Occupational health. Renal Dialysi. Nursing.

  8. Reprocessing of PLA/Graphene Nanoplatelets Nanocomposites

    Directory of Open Access Journals (Sweden)

    Luigi Botta

    2017-12-01

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

  9. Preliminary experiment design of graphite dust emission measurement under accident conditions for HTGR

    Energy Technology Data Exchange (ETDEWEB)

    Peng, Wei, E-mail: pengwei@tsinghua.edu.cn [Institute of Nuclear and New Energy Technology of Tsinghua University, Advanced Nuclear Energy Technology Cooperation Innovation Center, The Key Laboratory of Advanced Nuclear Engineering and Safety, Ministry of Education, Beijing 100084 (China); Chen, Tao; Sun, Qi; Wang, Jie [Institute of Nuclear and New Energy Technology of Tsinghua University, Advanced Nuclear Energy Technology Cooperation Innovation Center, The Key Laboratory of Advanced Nuclear Engineering and Safety, Ministry of Education, Beijing 100084 (China); Yu, Suyuan, E-mail: suyuan@tsinghua.edu.cn [Center for Combustion Energy, The Key Laboratory for Thermal Science and Power Engineering, Ministry of Education, Tsinghua University, Beijing 100084 (China)

    2017-05-15

    Highlights: • A theoretical analysis is used to predict the total graphite dust release for an AVR LOCA. • Similarity criteria must be satisfied between the experiment and the actual HTGR system. • Model experiments should be conducted to predict the graphite dust resuspension rate. - Abstract: The graphite dust movement behavior is significant for the safety analyses of high-temperature gas cooled reactor (HTGR). The graphite dust release for accident conditions is an important source term for HTGR safety analyses. Depressurization release tests are not practical in HTGR because of a radioactivity release to the environment. Thus, a theoretical analysis and similarity principles were used to design a group of modeling experiments. Modeling experiments for fan start-up and depressurization process and actual experiments of helium circulator start-up in an HTGR were used to predict the rate of graphite dust resuspension and the graphite dust concentration, which can be used to predict the graphite dust release during accidents. The modeling experiments are easy to realize and the helium circulator start-up test does not harm the reactor system or the environment, so this experiment program is easily achieved. The revised Rock’n’Roll model was then used to calculate the AVR reactor release. The calculation results indicate that the total graphite dust releases during a LOCA will be about 0.65 g in AVR.

  10. HTGR Technology Family Assessment for a Range of Fuel Cycle Missions

    Energy Technology Data Exchange (ETDEWEB)

    Steven J. Piet; Samuel E. Bays; Nick Soelberg

    2010-08-01

    This report examines how the HTGR technology family can provide options for the once through, modified open cycle (MOC), or full recycle fuel cycle strategies. The HTGR can serve all the fuel cycle missions that an LWR can; both are thermal reactors. Additional analyses are warranted to determine if HTGR “full recycle” service could provide improved consumption of transuranic (TRU) material than LWRs (as expected), to analyze the unique proliferation resistance issues associated with the “pebble bed” approach, and to further test and analyze methods to separate TRISO-coated fuel particles from graphite and/or to separate used HTGR fuel meat from its TRISO coating. The feasibility of these two separation issues is not in doubt, but further R&D could clarify and reduce the cost and enable options not adequately explored at present. The analyses here and the now-demonstrated higher fuel burnup tests (after the illustrative designs studied here) should enable future MOC and full recycle HTGR concepts to more rapidly consume TRU, thereby offering waste management advantages. Interest in “limited separation” or “minimum fuel treatment” separation approaches motivates study of impurity-tolerant fuel fabrication. Several issues are outside the scope of this report, including the following: thorium fuel cycles, gas-cooled fast reactors, the reliability of TRISO-coated particles (billions in a reactor), and how soon any new reactor or fuel type could be licensed and then deployed and therefore impact fuel cycle performance measures.

  11. HTGR Technology Family Assessment for a Range of Fuel Cycle Missions

    Energy Technology Data Exchange (ETDEWEB)

    Steven J. Piet; Samuel E. Bays; Nick R. Soelberg

    2010-11-01

    This report examines how the HTGR technology family can provide options for the once through, modified open cycle (MOC), or full recycle fuel cycle strategies. The HTGR can serve all the fuel cycle missions that an LWR can; both are thermal reactors. Additional analyses are warranted to determine if HTGR “full recycle” service could provide improved consumption of transuranic (TRU) material than LWRs (as expected), to analyze the unique proliferation resistance issues associated with the “pebble bed” approach, and to further test and analyze methods to separate TRISO-coated fuel particles from graphite and/or to separate used HTGR fuel meat from its TRISO coating. The feasibility of these two separation issues is not in doubt, but further R&D could clarify and reduce the cost and enable options not adequately explored at present. The analyses here and the now-demonstrated higher fuel burnup tests (after the illustrative designs studied here) should enable future MOC and full recycle HTGR concepts to more rapidly consume TRU, thereby offering waste management advantages. Interest in “limited separation” or “minimum fuel treatment” separation approaches motivates study of impurity-tolerant fuel fabrication.

  12. Present status of research on hydrogen energy and perspective of HTGR hydrogen production system

    Energy Technology Data Exchange (ETDEWEB)

    Miyamoto, Yoshiaki; Ogawa, Masuro; Akino, Norio [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment] [and others

    2001-03-01

    A study was performed to make a clear positioning of research and development on hydrogen production systems with a High Temperature Gas-cooled Reactor (HTGR) under currently promoting at the Japan Atomic Energy Research Institute through a grasp of the present status of hydrogen energy, focussing on its production and utilization as an energy in future. The study made clear that introduction of safe distance concept for hydrogen fire and explosion was practicable for a HTGR hydrogen production system, including hydrogen properties and need to provide regulations applying to handle hydrogen. And also generalization of hydrogen production processes showed technical issues of the HTGR system. Hydrogen with HTGR was competitive to one with fossil fired system due to evaluation of production cost. Hydrogen is expected to be used as promising fuel of fuel cell cars in future. In addition, the study indicated that there were a large amount of energy demand alternative to high efficiency power generation and fossil fuel with nuclear energy through the structure of energy demand and supply in Japan. Assuming that hydrogen with HTGR meets all demand of fuel cell cars, an estimation would show introduction of the maximum number of about 30 HTGRs with capacity of 100 MWt from 2020 to 2030. (author)

  13. The Intentional Interim

    Science.gov (United States)

    Nugent, Patricia A.

    2011-01-01

    The author spent years in central-office administration, most recently in an interim position. Some interim administrators simply see themselves as placeholders until the real deal is hired, giving the organization the opportunity to coast. There are others who see themselves as change agents and cannot wait to undo or redo what their predecessor…

  14. Comparison of Damage Formation and Crack Propagation Behavior of Selected Nuclear Graphite for HTGR

    Energy Technology Data Exchange (ETDEWEB)

    Chi, Se-Hwan; Kim, Hyun-Ju; Kim, Eung-Seon; Kim, Min-Hwan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Undoubtedly, these changes are attributed to the irradiation-induced changes in the microstructure of graphite components and finally result in an increase in the probability of fracture of graphite core components menacing the safety of reactor. Due to the nature of HTGR whose core components are made of quasi-brittle graphite, the graphite core components operating for 40-60 years without failure require knowledge and understanding on the characteristics of graphite fracture. In this study, two results on the fracture of nuclear graphite, i.e., fracture under cyclic compressive loading unloading and fracture under static loading, were reevaluated to understand the fracture characteristics of selected nuclear graphite grade for HTGR. Present observation may need to be considered in the graphite selection as well as in the design and safety evaluation of the graphite core components in HTGR.

  15. Storage and Reprocessing of Spent Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-02-02

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

  16. Analysis of long time series of GPS precipitable water vapour from IGS reprocessing

    Science.gov (United States)

    Bock, O.; Willis, P.; Bar-Sever, Y.; Wang, J.; Garayt, B.

    2012-12-01

    Humidity is an essential climate variable, which needs to be monitored continuously and accurately. Few observational datasets are available, and most of them suffer from biases, uncertainties and discontinuities (e.g. radiosonde data records or satellite products). To date, precipitable water vapour (PWV) estimates from the International GNSS Service (IGS) network have not been used extensively in the climate monitoring. A reprocessed version of zenith tropospheric delays (ZTDs) has been made available recently for the International GNSS Service (IGS) network. It covers period 1995-2007 and has been updated until 2011 using the same data processing software. This work aims at evaluating the quality of these ZTD solutions and corresponding PWV estimates and assessing their potential for climate monitoring and atmospheric model validation. As a first step, the continuity of IGS reprocessed (repro1) and operational (trop-new) ZTD solution is assessed. Both segments before and after 2007 are compared to a third GPS solution for 160 common stations and to a DORIS solution for more than 50 stations. Both these GPS and DORIS solutions were homogenously reprocessed over the study period. The comparison did not show any significant discontinuity between the two IGS segments. However, the differences are found between the three independent datasets which are explained by the differences in data processing procedures (e.g. antenna models, mapping functions) and techniques (GPS vs. DORIS). But the magnitude of the differences is less than a few millimeters. The reprocessed GPS ZTD estimates were converted into PWV and analysed globally and for different regions. The PWV time series reveal significant variability on inter-annual, seasonal, intra-seasonal and synoptic timescales. The GPS results are overall fairly consistent with ECMWF reanalysis (ERA-Interim). The impact of changes in GPS equipment on PWV trend estimates needs further investigation. Reprocessed GPS PWV

  17. Heat exchanger design considerations for high temperature gas-cooled reactor (HTGR) plants

    Energy Technology Data Exchange (ETDEWEB)

    McDonald, C.F.; Vrable, D.L.; Van Hagan, T.H.; King, J.H.; Spring, A.H.

    1980-02-01

    Various aspects of the high-temperature heat exchanger conceptual designs for the gas turbine (HTGR-GT) and process heat (HTGR-PH) plants are discussed. Topics include technology background, heat exchanger types, surface geometry, thermal sizing, performance, material selection, mechanical design, fabrication, and the systems-related impact of installation and integration of the units in the prestressed concrete reactor vessel. The impact of future technology developments, such as the utilization of nonmetallic materials and advanced heat exchanger surface geometries and methods of construction, is also discussed.

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

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-03-08

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

  19. HTGR Gas Turbine Program. Semiannual progress report for the period ending September 30, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1980-05-01

    Information on the HTGR-GT program is presented concerning systems design methods; systems dynamics methods; alternate design; miscellaneous controls and auxiliary systems; structural mechanics; shielding analysis; licensing; safety; availability; reactor turbine system integration with plant; PCRV liners, penetrations, and closures; PCRV structures; thermal barrier; reactor internals; turbomachinery; turbomachine remote maintenance; control valve; heat exchangers; plant protection system; and plant control system.

  20. Proceedings of the Japan - U.S. Seminar on HTGR Safety Technology - Seismic Research. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    1977-09-15

    These volumes constitute the proceedings of the f i r s t Japan-United States HTGR Safety Technology Seminar sponsored by the U. S. Nuclear Regulatory Commission, which was held at Brookhaven National Laboratory, Upton, New York, on September 15 and 16, 1977. This Seminar was held within the framework of the technical information exchange agreement in the area of HTGR safety research between the United States Nuclear Regulatory Commission and the Japan Atomic Energy Bureau. The agreement covers many aspects of HTGR safety res'earch, including: accident delineation, fuel cycle safety, primary coolant impurities, seismic effects, 'material properties, fission product release and transport and graphite oxidation. This f i r s t Seminar covered the safety research being carried out i n the areas of seismic effects and helium technology. in Japan and the United States. The Seminar was divided into two parallel sessions, one for Seismic Research and the second for Helium Technology. The papers presented i n the Seismic Research.session constitute Volume I of the proceedings, and the papers of the Helium Technology session constitute Volume 11. I t is hoped that these papers will form the basis for future cooperation between the Japanese and American scientific and engineering community in 'HTGR safety research.

  1. Formation of actinides in irradiated HTGR fuel elements

    Energy Technology Data Exchange (ETDEWEB)

    dos Santos, A. M.

    1976-03-15

    Actinide nuclide concentrations of 11 spent AVR fuel elements were determined experimentally. The burnup of the spheres varied in the range between 10% and 100% fifa, the Th : U ratio was 5 : 1. The separation procedures for an actinide isolation were tested with highly irradiated ThO/sub 2/. Separation and decontamination factors are presented. Build-up of /sup 232/U was discussed. The AVR breeding rate was ascertained to be 0.5. The hazard potential of high activity waste was calculated. Actinide recovery factors were proposed in order to reduce the hazard potential of the waste by an actinide removal under consideration of the reprocessing technology which is available presently.

  2. Transition to reprocessing: one OR's success.

    Science.gov (United States)

    Boone, Penny K

    2010-01-01

    This article tells the story of an OR staff that achieved a successful implementation of reprocessing 6 years ago, ultimately resulting in a culture change. The transition to the use of reprocessed Food and Drug Administration-approved single-use surgical devices is described as it occurred. Consideration of the human factors, change management, and culture change are included in this tale of transition. This change occurred organically within the team, rather than being forced by organizational hierarchy. The telling of this experience speaks to the effectiveness of change initiated at the bedside by motivated staff, which then evolved into a culture change for this OR.

  3. Process Description and Operating History for the CPP-601/-640/-627 Fuel Reprocessing Complex at the Idaho National Engineering and Environmental Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    E. P. Wagner

    1999-06-01

    The Fuel Reprocessing Complex (FRC) at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory was used for reprocessing spent nuclear fuel from the early 1950's until 1992. The reprocessing facilities are now scheduled to be deactivated. As part of the deactivation process, three Resource Conservation and Recovery Act (RCRA) interim status units located in the complex must be closed. This document gathers the historical information necessary to provide a rational basis for the preparation of a comprehensive closure plan. Included are descriptions of process operations and the operating history of the FRC. A set of detailed tables record the service history and present status of the process vessels and transfer lines.

  4. 76 FR 45268 - Reprocessing of Reusable Medical Devices

    Science.gov (United States)

    2011-07-28

    ... patient exposure to inadequately reprocessed medical devices and subsequent health care- associated infections (HAIs). A definitive causal relationship between reusable device reprocessing and any patient... methodologies, validation methodologies, and health care facility best practices. This is part of an ongoing...

  5. Summary of nuclear fuel reprocessing activities around the world

    Energy Technology Data Exchange (ETDEWEB)

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

    1984-11-01

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

  6. 21 CFR 211.115 - Reprocessing.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 4 2010-04-01 2010-04-01 false Reprocessing. 211.115 Section 211.115 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) DRUGS: GENERAL CURRENT GOOD MANUFACTURING PRACTICE FOR FINISHED PHARMACEUTICALS Production and Process Controls § 211.115...

  7. Effects of reprocessing on nanoalumina polymer composites

    Science.gov (United States)

    Huang, Chunchia

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

  8. Radioactive Semivolatiles in Nuclear Fuel Reprocessing

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-09-01

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

  9. Creep-Rupture Properties and Corrosion Behaviour of 21/4 Cr-1 Mo Steel and Hastelloy X-Alloys in Simulated HTGR Environment

    DEFF Research Database (Denmark)

    Lystrup, Aage; Rittenhouse, P. L.; DiStefano, J. R.

    Hastelloy X and 2/sup 1///sub 4/ Cr-1 Mo steel are being considered as structural alloys for components of a High-Temperature Gas-Cooled Reactor (HTGR) system. Among other mechanical properties, the creep behavior of these materials in HTGR primary coolant helium must be established to form part...... of the design criteria. This report describes the simulated HTGR-helium environmental creep facilities, summarizes preliminary creep properties of 2/sup 1///sub 4/ Cr-1 Mo steel and Hastelloy X generated in HTGR helium and compares these with data obtained by testing in air. Some corrosion characteristics...

  10. Turbomachinery design considerations for the nuclear HTGR-GT power plant

    Energy Technology Data Exchange (ETDEWEB)

    McDonald, C.F.; Smith, M.J.

    1979-11-01

    For several years, design studies have been under way in the USA on a nuclear closed-cycle gas turbine plant (HTGR-GT). Design aspects of the helium turbomachine portion of these studies are presented. Gas dynamic and mechanical design considerations are presented for helium turbomachines in the 400-MW(e) (non-intercooled) and 600-MW(e) (intercooled) power range. Design of the turbomachine is a key element in the overall power plant program effort, which is currently directed toward the selection of a reference HTGR-GT commercial plant configuration for the US utility market. A conservative design approach has been emphasized to provide maximum safety and durability. The studies presented for the integrated plant concept outline the necessary close working relationship between the reactor primary system and turbomachine designers.

  11. Sensitivity and Uncertainty Analysis of IAEA CRP HTGR Benchmark Using McCARD

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Sang Hoon; Shim, Hyung Jin [Seoul National University, Seoul (Korea, Republic of)

    2016-05-15

    The benchmark consists of 4 phases starting from the local standalone modeling (Phase I) to the safety calculation of coupled system with transient situation (Phase IV). As a preliminary study of UAM on HTGR, this paper covers the exercise 1 and 2 of Phase I which defines the unit cell and lattice geometry of MHTGR-350 (General Atomics). The objective of these exercises is to quantify the uncertainty of the multiplication factor induced by perturbing nuclear data as well as to analyze the specific features of HTGR such as double heterogeneity and self-shielding treatment. The uncertainty quantification of IAEA CRP HTGR UAM benchmarks were conducted using first-order AWP method in McCARD. Uncertainty of the multiplication factor was estimated only for the microscopic cross section perturbation. To reduce the computation time and memory shortage, recently implemented uncertainty analysis module in MC wielandt calculation was adjusted. The covariance data of cross section was generated by NJOY/ERRORR module with ENDF/B-VII.1. The numerical result was compared with evaluation result of DeCART/MUSAD code system developed by KAERI. IAEA CRP HTGR UAM benchmark problems were analyzed using McCARD. The numerical results were compared with Serpent for eigenvalue calculation and DeCART/MUSAD for S/U analysis. In eigenvalue calculation, inconsistencies were found in the result with ENDF/B-VII.1 cross section library and it was found to be the effect of thermal scattering data of graphite. As to S/U analysis, McCARD results matched well with DeCART/MUSAD, but showed some discrepancy in 238U capture regarding implicit uncertainty.

  12. HTGR high temperature process heat design and cost status report. Volume II. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-12-01

    Information is presented concerning the 850/sup 0/C IDC reactor vessel; primary cooling system; secondary helium system; steam generator; heat cycle evaluations for the 850/sup 0/C IDC plant; 950/sup 0/C DC reactor vessel; 950/sup 0/C DC steam generator; direct and indirect cycle reformers; methanation plant; thermochemical pipeline; methodology for screening candidate synfuel processes; ECCG process; project technical requirements; process gas explosion assessment; HTGR program economic guidelines; and vendor respones.

  13. Irradiation performance of HTGR fuel rods in HFIR experiments HRB-11 and -12

    Energy Technology Data Exchange (ETDEWEB)

    Homan, F.J.; Tiegs, T.N.; Kania, M.J.; Long, E.L. Jr.; Thoms, K.R.; Robbins, J.M.; Wagner, P.

    1980-06-01

    Capsules HRB-11 and -12 were irradiated in support of development of weak-acid-resin-derived recycle fuel for the high-enriched uranium (HEU) fuel cycle for the HTGR. Fissil fuel particles with initial oxygen-to-metal ratios between 1.0 and 1.7 performed acceptably to full burnup for HEU fuel. Particles with ratios below 1.0 showed excessive chemical interaction between rare earth fission products and the SiC layer.

  14. A Small-Sized HTGR System Design for Multiple Heat Applications for Developing Countries

    Directory of Open Access Journals (Sweden)

    Hirofumi Ohashi

    2013-01-01

    Full Text Available Japan Atomic Energy Agency has conducted a conceptual design of a 50 MWt small-sized high temperature gas cooled reactor (HTGR for multiple heat applications, named HTR50S, with the reactor outlet coolant temperature of 750°C and 900°C. It is first-of-a-kind of the commercial plant or a demonstration plant of a small-sized HTGR system to be deployed in developing countries in the 2020s. The design concept of HTR50S is to satisfy the user requirements for multipurpose heat applications such as the district heating and process heat supply based on the steam turbine system and the demonstration of the power generation by helium gas turbine and the hydrogen production using the water splitting iodine-sulfur process, to upgrade its performance compared to that of HTTR without significant R&D utilizing the knowledge obtained by the HTTR design and operation, and to fulfill the high level of safety by utilizing the inherent features of HTGR and a passive decay heat removal system. The evaluation of technical feasibility shows that all design targets were satisfied by the design of each system and the preliminary safety analysis. This paper describes the conceptual design and the preliminary safety analysis of HTR50S.

  15. Integrity Surveillance Test for HTGR Graphite Core Components by Small Specimens

    Energy Technology Data Exchange (ETDEWEB)

    Chi, Sehwan; Sung, Jiyong; Kim, Minhwan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    For a graphite moderate high-temperature gas-cooled reactor (HTGR), a reliable monitoring of the mechanical property changes of graphite core components owing to a possible oxidation or neutron-irradiation is a critical issue for safe operation of a reactor. For safety, an increase in the failure probability of the components owing to the degradation of mechanical properties should be analysed and reflected during the operating condition renewal process. In monitoring the degradation of the mechanical properties of graphite core components, however, since the reactor environment has limits in the number, shape, and volume of the pre-installed specimens for integrity evaluation, small specimen test techniques are required. In the present study, specimen size effects on the flexural strength and fracture toughness were discussed based on the data obtained in KAERI for nuclear application. The present study on the specimen size effects on flexural strength and fracture toughness measurements of nuclear graphite grades for HTGR shows that the small graphite specimens examined in this study may be applied to an integrity surveillance test of HTGR graphite core components.

  16. Integrated international safeguards concepts for fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

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

    1981-12-01

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

  17. International safeguards for reprocessing plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

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

    1981-04-01

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

  18. Results for Phase I of the IAEA Coordinated Research Program on HTGR Uncertainties

    Energy Technology Data Exchange (ETDEWEB)

    Strydom, Gerhard [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bostelmann, Friederike [Idaho National Lab. (INL), Idaho Falls, ID (United States); Yoon, Su Jong [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-01-01

    The quantification of uncertainties in design and safety analysis of reactors is today not only broadly accepted, but in many cases became the preferred way to replace traditional conservative analysis for safety and licensing analysis. The use of a more fundamental methodology is also consistent with the reliable high fidelity physics models and robust, efficient, and accurate codes available today. To facilitate uncertainty analysis applications a comprehensive approach and methodology must be developed and applied. High Temperature Gas-cooled Reactors (HTGR) has its own peculiarities, coated particle design, large graphite quantities, different materials and high temperatures that also require other simulation requirements. The IAEA has therefore launched a Coordinated Research Project (CRP) on the HTGR Uncertainty Analysis in Modeling (UAM) in 2013 to study uncertainty propagation specifically in the HTGR analysis chain. Two benchmark problems are defined, with the prismatic design represented by the General Atomics (GA) MHTGR-350 and a 250 MW modular pebble bed design similar to the HTR-PM (INET, China). This report summarizes the contributions of the HTGR Methods Simulation group at Idaho National Laboratory (INL) up to this point of the CRP. The activities at INL have been focused so far on creating the problem specifications for the prismatic design, as well as providing reference solutions for the exercises defined for Phase I. An overview is provided of the HTGR UAM objectives and scope, and the detailed specifications for Exercises I-1, I-2, I-3 and I-4 are also included here for completeness. The main focus of the report is the compilation and discussion of reference results for Phase I (i.e. for input parameters at their nominal or best-estimate values), which is defined as the first step of the uncertainty quantification process. These reference results can be used by other CRP participants for comparison with other codes or their own reference

  19. The IAEA Coordinated Research Program on HTGR Uncertainty Analysis: Phase I Status and Initial Results

    Energy Technology Data Exchange (ETDEWEB)

    Strydom, Gerhard; Bostelmann, Friederike; Ivanov, Kostadin

    2014-10-01

    The continued development of High Temperature Gas Cooled Reactors (HTGRs) requires verification of HTGR design and safety features with reliable high fidelity physics models and robust, efficient, and accurate codes. One way to address the uncertainties in the HTGR analysis tools is to assess the sensitivity of critical parameters (such as the calculated maximum fuel temperature during loss of coolant accidents) to a few important input uncertainties. The input parameters were identified by engineering judgement in the past but are today typically based on a Phenomena Identification Ranking Table (PIRT) process. The input parameters can also be derived from sensitivity studies and are then varied in the analysis to find a spread in the parameter of importance. However, there is often no easy way to compensate for these uncertainties. In engineering system design, a common approach for addressing performance uncertainties is to add compensating margins to the system, but with passive properties credited it is not so clear how to apply it in the case of modular HTGR heat removal path. Other more sophisticated uncertainty modelling approaches, including Monte Carlo analysis, have also been proposed and applied. Ideally one wishes to apply a more fundamental approach to determine the predictive capability and accuracies of coupled neutronics/thermal-hydraulics and depletion simulations used for reactor design and safety assessment. Today there is a broader acceptance of the use of uncertainty analysis even in safety studies, and it has been accepted by regulators in some cases to replace the traditional conservative analysis. Therefore some safety analysis calculations may use a mixture of these approaches for different parameters depending upon the particular requirements of the analysis problem involved. Sensitivity analysis can for example be used to provide information as part of an uncertainty analysis to determine best estimate plus uncertainty results to the

  20. CMM Interim Check (U)

    Energy Technology Data Exchange (ETDEWEB)

    Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-03-23

    Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length. Unfortunately, several nonconformance reports have been generated to document the discovery of a certified machine found out of tolerance during a calibration closeout. In an effort to reduce risk to product quality two solutions were proposed – shorten the calibration cycle which could be costly, or perform an interim check to monitor the machine’s performance between cycles. The CMM interim check discussed makes use of Renishaw’s Machine Checking Gauge. This off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. Data was gathered, analyzed, and simulated from seven machines in seventeen different configurations to create statistical process control run charts for on-the-floor monitoring.

  1. Handbook on process and chemistry on nuclear fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-12-01

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

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

    OpenAIRE

    Nick R. Soelberg; Troy G. Garn; Mitchell R. Greenhalgh; Jack D. Law; Robert Jubin; Denis M. Strachan; Praveen K. Thallapally

    2013-01-01

    The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessing facility in the US. Various control technologies have been developed, tested, or used over the past 50 years for control of volatile radionuclide emissions from used fuel reprocessing plants. The US DOE has sponsored, since 2009, an Off-gas Sigma Team to perform research and development focused on the most pressing volatile radio...

  3. An Online Non-Invasive Condition Monitoring Method for Stepping Motor CRDM in HTGR

    Directory of Open Access Journals (Sweden)

    S. Bakhri

    2016-12-01

    Full Text Available Control Rod Drive Mechanism (CRDM based on stepping motor is one of the components applied in High Temperature Gas Coold Reactor (HTGR to control the reactivity as well as to maintain the safety of reactor. The stepping motor requires a unique condition monitoring to avoid any failures especially due to the specific environments of CRDM in HTGR such as the allowable of high temperature, high radiation and the location of stepper motor inside a pressure shell. This research aims to demonstrate an online non-invasive condition monitoring method without direct access to the CRDM of HTGR based on voltage and stator current measurements. A simple stepping motor CRDM simulator is employed. The online condition monitoring is carried out by direct pattern matching of the output signals of logic generator block and the output signals of motor driver. The online method utilizes signature patterns of voltage and stator current signals of the healthy motor as a baseline for healthy motor. In addition, the method is applied to detect high-resistance problem on the connector between the motor driver block and the stepper motor to show the effectiveness and the applicability of this method. The online condition monitoring system demonstrates a capability to identify a minimum detectable simulated high-resistance for about 2.9% which decreases the measured stator current and motor’s torque for around 5.1% and 3.3%, respectively. The paper also points out signatures of healthy motor, including mutual inductions of the motor’s winding in voltage and current measurement which can be used as the fault symptom indicators for online monitoring purposes.

  4. Tropospheric products of the second GOP European GNSS reprocessing (1996–2014

    Directory of Open Access Journals (Sweden)

    J. Dousa

    2017-09-01

    Full Text Available In this paper, we present results of the second reprocessing of all data from 1996 to 2014 from all stations in International Association of Geodesy (IAG Reference Frame Sub-Commission for Europe (EUREF Permanent Network (EPN as performed at the Geodetic Observatory Pecný (GOP. While the original goal of this research was to ultimately contribute to the realization of a new European Terrestrial Reference System (ETRS, we also aim to provide a new set of GNSS (Global Navigation Satellite System tropospheric parameter time series with possible applications to climate research. To achieve these goals, we improved a strategy to guarantee the continuity of these tropospheric parameters and we prepared several variants of troposphere modelling. We then assessed all solutions in terms of the repeatability of coordinates as an internal evaluation of applied models and strategies and in terms of zenith tropospheric delays (ZTDs and horizontal gradients with those of the ERA-Interim numerical weather model (NWM reanalysis. When compared to the GOP Repro1 (first EUREF reprocessing solution, the results of the GOP Repro2 (second EUREF reprocessing yielded improvements of approximately 50 and 25 % in the repeatability of the horizontal and vertical components, respectively, and of approximately 9 % in tropospheric parameters. Vertical repeatability was reduced from 4.14 to 3.73 mm when using the VMF1 mapping function, a priori ZHD (zenith hydrostatic delay, and non-tidal atmospheric loading corrections from actual weather data. Raising the elevation cut-off angle from 3 to 7° and then to 10° increased RMS from coordinates' repeatability, which was then confirmed by independently comparing GNSS tropospheric parameters with the NWM reanalysis. The assessment of tropospheric horizontal gradients with respect to the ERA-Interim revealed a strong sensitivity of estimated gradients to the quality of GNSS antenna tracking performance. This impact was

  5. Tropospheric products of the second GOP European GNSS reprocessing (1996-2014)

    Science.gov (United States)

    Dousa, Jan; Vaclavovic, Pavel; Elias, Michal

    2017-09-01

    In this paper, we present results of the second reprocessing of all data from 1996 to 2014 from all stations in International Association of Geodesy (IAG) Reference Frame Sub-Commission for Europe (EUREF) Permanent Network (EPN) as performed at the Geodetic Observatory Pecný (GOP). While the original goal of this research was to ultimately contribute to the realization of a new European Terrestrial Reference System (ETRS), we also aim to provide a new set of GNSS (Global Navigation Satellite System) tropospheric parameter time series with possible applications to climate research. To achieve these goals, we improved a strategy to guarantee the continuity of these tropospheric parameters and we prepared several variants of troposphere modelling. We then assessed all solutions in terms of the repeatability of coordinates as an internal evaluation of applied models and strategies and in terms of zenith tropospheric delays (ZTDs) and horizontal gradients with those of the ERA-Interim numerical weather model (NWM) reanalysis. When compared to the GOP Repro1 (first EUREF reprocessing) solution, the results of the GOP Repro2 (second EUREF reprocessing) yielded improvements of approximately 50 and 25 % in the repeatability of the horizontal and vertical components, respectively, and of approximately 9 % in tropospheric parameters. Vertical repeatability was reduced from 4.14 to 3.73 mm when using the VMF1 mapping function, a priori ZHD (zenith hydrostatic delay), and non-tidal atmospheric loading corrections from actual weather data. Raising the elevation cut-off angle from 3 to 7° and then to 10° increased RMS from coordinates' repeatability, which was then confirmed by independently comparing GNSS tropospheric parameters with the NWM reanalysis. The assessment of tropospheric horizontal gradients with respect to the ERA-Interim revealed a strong sensitivity of estimated gradients to the quality of GNSS antenna tracking performance. This impact was demonstrated at the

  6. Interim storage study report

    Energy Technology Data Exchange (ETDEWEB)

    Rawlins, J.K.

    1998-02-01

    High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration.

  7. Data validation and security for reprocessing.

    Energy Technology Data Exchange (ETDEWEB)

    Tolk, Keith Michael; Merkle, Peter Benedict; DurÔan, Felicia Angelica; Cipiti, Benjamin B.

    2008-10-01

    Next generation nuclear fuel cycle facilities will face strict requirements on security and safeguards of nuclear material. These requirements can result in expensive facilities. The purpose of this project was to investigate how to incorporate safeguards and security into one plant monitoring system early in the design process to take better advantage of all plant process data, to improve confidence in the operation of the plant, and to optimize costs. An existing reprocessing plant materials accountancy model was examined for use in evaluating integration of safeguards (both domestic and international) and security. International safeguards require independent, secure, and authenticated measurements for materials accountability--it may be best to design stand-alone systems in addition to domestic safeguards instrumentation to minimize impact on operations. In some cases, joint-use equipment may be appropriate. Existing domestic materials accountancy instrumentation can be used in conjunction with other monitoring equipment for plant security as well as through the use of material assurance indicators, a new metric for material control that is under development. Future efforts will take the results of this work to demonstrate integration on the reprocessing plant model.

  8. High-temperature process heat. Interim design and cost status report, FY 1981

    Energy Technology Data Exchange (ETDEWEB)

    1981-10-01

    Studies conductd on HTGR systems in FY 1980 were concluded in Application Study Reports to describe the preconceptual system designs to that point and discuss possible applications for three variations of the systems; the steam cycle/cogeneration plant, the higher temperature reformer plant, and the gas turbine concept. The HTGR-Reformer Application Study was conceived and directed to evaluate the HTGR-R with a core outlet temperature of 850/sup 0/C as a near-term Lead Project and as a vehicle to long-term HTGR Program Objectives. The scope of this effort included evaluations of the HTGR-R technology, evaluation of potential HTGR-R markets, assesment of the economics of commercial HTGR-R plants, and the evaluation of the program scope and expenditures necessary to establish HTGR-R technology through the completion of the Lead Project.

  9. 9 CFR 114.18 - Reprocessing of biological products.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Reprocessing of biological products..., DEPARTMENT OF AGRICULTURE VIRUSES, SERUMS, TOXINS, AND ANALOGOUS PRODUCTS; ORGANISMS AND VECTORS PRODUCTION REQUIREMENTS FOR BIOLOGICAL PRODUCTS § 114.18 Reprocessing of biological products. The Administrator may...

  10. 76 FR 24495 - Reprocessing of Reusable Medical Devices; Public Workshop

    Science.gov (United States)

    2011-05-02

    ... HUMAN SERVICES Food and Drug Administration Reprocessing of Reusable Medical Devices; Public Workshop AGENCY: Food and Drug Administration, HHS. ACTION: Notice of public workshop; request for comments. The Food and Drug Administration (FDA) is announcing a public workshop entitled: ``Reprocessing of Reusable...

  11. Properties of endotracheal tubes reprocessed by two procedures

    Directory of Open Access Journals (Sweden)

    Elisa Elisa

    2011-04-01

    component. SEM analysis detected some large particles and fissures. EDX analysis on the large particles detected sodium and calcium signals. Altogether, signs of contamination and material damage were very strong. Conclusion Both reprocessing methods of reused EITs gave comparable results on sterility and mechanical behavior, but reprocessing may cause decreased surface and matrix quality.

  12. Present status of the feasibility study of HTGR-GT system

    Energy Technology Data Exchange (ETDEWEB)

    Muto, Yasushi; Miyamoto, Yoshiaki; Shiozawa, Shusaku [Department of Advanced Nuclear Heat Technology, Oarai Research Establishment, Japan Atomic Energy Research Institute JAERI, Ibaraki-ken (Japan)

    1998-09-01

    A feasibility study of the High Temperature Gas-cooled Reactor - Gas Turbine (HTGR-GT) system has been started in January 1997. The aim of the study is to obtain a concept of HTGR-GT system which has a high thermal efficiency and at the same time is economically competitive. Designs of direct cycle, indirect cycle and cogeneration cycle will be undertaken and their power generation costs will be evaluated. In parallel with design works, some experimental works such as a fabrication of plate-fin type heat exchanger core and material tests will be carried out. The study will be continued till the year 2000. In 1996 some preliminary works have been carried out. In 1997 a design of direct cycle and fabrication of a model of the plate-fin type recuperator core section have been started. In this paper some results of the preliminary works are described, as well as main design parameters of direct cycle design and a plan of the fabrication of the recuperator model. 3 refs.

  13. Design and operation of equipment used to develop remote coating capability for HTGR fuel particles

    Energy Technology Data Exchange (ETDEWEB)

    Suchomel, R.R.; Stinton, D.P.; Preston, M.K.; Heck, J.L.; Bolfing, B.J.; Lackey, W.J.

    1978-12-01

    Refabrication of HTGR fuels is a manufacturing process that consists of preparation of fuel kernels, application of multiple layers of pyrolytic carbon and silicon carbide, preparation of fuel rods, and assembly of fuel rods into fuel elements. All the equipment for refabrication of /sup 233/U-containing fuel must be designed for completely remote operation and maintenance in hot-cell facilities. Equipment to remotely coated HTGR fuel particles has been designed and operated. Although not all of the equipment development needed for a fully remote coating system has been completed, significant progress has been made. The most important component of the coating furnace is the gas distributor, which must be simple, reliable, and easily maintainable. Techniques for loading and unloading the coater and handling microspheres have been developed. An engineering-scale system, currently in operation, is being used to verify the workability of these concepts. Coating crucible handling components are used to remove the crucible from the furnace, remove coated particles, and exchange the crucible, if necessary. After the batch of particles has been unloaded, it is transferred, weighed, and sampled. The components used in these processes have been tested to ensure that no particle breakage or holdup occurs. Tests of the particle handling system have been very encouraging because no major problems have been encountered. Instrumentation that controls the equipment performed very smoothly and reliably and can be operated remotely.

  14. High temperature strength and inelastic behavior of plate-fin structures for HTGR

    Energy Technology Data Exchange (ETDEWEB)

    Kawashima, F. [Mitsubishi Heavy Industries, Ltd., Fukahori-machi 5-717-1, 851-0392 Nagasaki (Japan)]. E-mail: fumiko_kawashima@mhi.co.jp; Igari, T. [Mitsubishi Heavy Industries, Ltd., Fukahori-machi 5-717-1, 851-0392 Nagasaki (Japan); Miyoshi, Y. [Mitsubishi Heavy Industries, Ltd., Fukahori-machi 5-717-1, 851-0392 Nagasaki (Japan); Kamito, Y. [Mitsubishi Heavy Industries, Ltd., Fukahori-machi 5-717-1, 851-0392 Nagasaki (Japan); Tanihira, M. [Mitsubishi Heavy Industries, Ltd., Fukahori-machi 5-717-1, 851-0392 Nagasaki (Japan)

    2007-03-15

    In this paper, both high temperature strength and inelastic behavior of plate-fin structures were discussed for applying these structures to the compact heat exchangers such as recuperative and intermediate heat exchangers for high-temperature gas-cooled reactors (HTGR). Firstly tensile, creep and fatigue tests of the brazed plate-fin model of small size were carried out to obtain the rupture strength and inelastic behavior. The influence of the braze filler metal thickness on the tensile strength was experimentally studied and a possibility of predicting both the tensile and creep strength was discussed using the data of base material of plates and fins. Secondly, we demonstrated the fabrication of large-size core with a dimension of 1000 mm, and also demonstrated that the bonding ratio in this core was improved up to almost 100% by adopting the pressurized tank system in the brazing process. Finally, we proposed the stress analysis method of plate-fin structures on the basis of the equivalent-homogeneous-solid concept, and carried out the elastic-plastic analysis of recuperative heat exchanger for HTGR. Characteristics of stress-strain behavior were discussed together with a possibility of predicting the fatigue life of the structure.

  15. Research on PARC process for future reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Asakura, T.; Hotoku, S.; Ban, Y.; Matsumura, M.; Kim, S.Y.; Mineo, H.; Morita, Y

    2004-07-01

    In JAERI, PARC process based on Purex technique has been studied to as the basis of future reprocessing. The key of concept is to obtain the products, U and Pu, within only a single extraction cycle by separating Np and Tc from U and Pu before U/Pu partition. Two flow-sheet tests on the process were performed with 44 GWd/t PWR spent-fuel solutions. It was demonstrated that remaining Np in raffinate from co-extraction could be decreased to 13 % compared to the dissolver solution with increased solvent flow rate and with increased nitric acid concentration of FP scrubbing solution. It was demonstrated that Np separation (selective reduction by n-butyr-aldehyde) efficiency could be improved from 36 % to 78 % by flow-sheet modification; increasing reductant concentration and scrubbing solution flow rate. The feasibility of the Tc separation technique by high acid scrubbing was demonstrated. (authors)

  16. Glass packages in interim storage; Les verres dans les stockages

    Energy Technology Data Exchange (ETDEWEB)

    Jacquet-Francillon, N.

    1994-10-01

    This report summarize the current state of knowledge concerning the behavior of type C waste packages consisting of vitrified high-level solutions produced by reprocessing spent fuel. The composition and the physical and chemical properties of the feed solutions are reviewed, and the vitrification process is described. Sodium alumino-borosilicate glass compositions are generally employed - the glass used at la Hague for LWR fuel solutions, for example, contains 45 % SiO{sub 2}. The major physical, chemical, mechanical and thermal properties of the glass are reviewed. In order to allow their thermal power to diminish, the 3630 glass packages produced (as of January 1993) in the vitrification facilities at Marcoule and La Hague are placed in interim storage for several decades. The actual interim storage period has not been defined, as it is closely related to the concept and organization selected for the final destination of the packages: a geological repository. The glass behavior under irradiation is described. Considerable basic and applied research has been conducted to assess the aqueous leaching behavior of nuclear containment glass. The effects of various repository parameters (temperature, flow rate, nature of the environmental materials) have been investigated. The experimental findings have been used to specify a model describing the kinetics of aqueous corrosion of the glass. More generally all the ``source term`` models developed in France by the CEA or by ANDRA are summarized. (author). 152 refs., 33 figs.

  17. Advantages on dry interim storage for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, L.S. [Centro Tecnologico da Marinha em Sao Paulo, Av. Professor Lineu Prestes 2468, 05508-900 Sao Paulo (Brazil); Rzyski, B.M. [IPEN/ CNEN-SP, 05508-000 Sao Paulo (Brazil)]. e-mail: romanato@ctmsp.mar.mil.br

    2006-07-01

    When the nuclear fuel lose its ability to efficiently create energy it is removed from the core reactor and moved to a storage unit waiting for a final destination. Generally, the spent nuclear fuel (SNF) remains inside concrete basins with water within the reactors facility for the radioactive activity decay. Water cools the generated heat and shields radioactivity emissions. After some period of time in water basins the SNF can be sent to a definitive deposition in a geological repository and handled as radioactive waste or to reprocessing installations, or still wait for a future solution. Meanwhile, SNF remains stored for a period of time in dry or wet installations, depending on the method adopted by the nuclear power plant or other plans of the country. In many SNF wet storage sites the capacity can be fulfilled very quickly. If so, additional area or other alternative storage system should be given. There are many options to provide capacity increase in the wet storage area, but dry storages are worldwide preferred since it reduces corrosion concerns. In the wet storage the temperature and water purity should be constantly controlled whereas in the dry storage the SNF stands protected in specially designed canisters. Dry interim storages are practical and approved in many countries especially that have the 'wait and see' philosophy (wait to see new technologies development). This paper shows the advantages of dry interim storages sites in comparison with the wet ones and the nowadays problems as terrorism. (Author)

  18. Preventive maintenance study : interim report.

    Science.gov (United States)

    2017-09-01

    This interim report details the performance of 69 test sites treated with various preventive maintenance treatments. The maintenance treatments applied included crack sealing, full lane chip sealing, wheel path chip sealing, dig outs (mill and fill),...

  19. Reprocessing of research reactor fuel the Dounreay option

    Energy Technology Data Exchange (ETDEWEB)

    Cartwright, P.

    1997-08-01

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

  20. IAEA Coordinated Research Project on HTGR Reactor Physics, Thermal-hydraulics and Depletion Uncertainty Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Strydom, Gerhard [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bostelmann, F. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    The continued development of High Temperature Gas Cooled Reactors (HTGRs) requires verification of HTGR design and safety features with reliable high fidelity physics models and robust, efficient, and accurate codes. The predictive capability of coupled neutronics/thermal-hydraulics and depletion simulations for reactor design and safety analysis can be assessed with sensitivity analysis (SA) and uncertainty analysis (UA) methods. Uncertainty originates from errors in physical data, manufacturing uncertainties, modelling and computational algorithms. (The interested reader is referred to the large body of published SA and UA literature for a more complete overview of the various types of uncertainties, methodologies and results obtained). SA is helpful for ranking the various sources of uncertainty and error in the results of core analyses. SA and UA are required to address cost, safety, and licensing needs and should be applied to all aspects of reactor multi-physics simulation. SA and UA can guide experimental, modelling, and algorithm research and development. Current SA and UA rely either on derivative-based methods such as stochastic sampling methods or on generalized perturbation theory to obtain sensitivity coefficients. Neither approach addresses all needs. In order to benefit from recent advances in modelling and simulation and the availability of new covariance data (nuclear data uncertainties) extensive sensitivity and uncertainty studies are needed for quantification of the impact of different sources of uncertainties on the design and safety parameters of HTGRs. Only a parallel effort in advanced simulation and in nuclear data improvement will be able to provide designers with more robust and well validated calculation tools to meet design target accuracies. In February 2009, the Technical Working Group on Gas-Cooled Reactors (TWG-GCR) of the International Atomic Energy Agency (IAEA) recommended that the proposed Coordinated Research Program (CRP) on

  1. Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

    Energy Technology Data Exchange (ETDEWEB)

    L.E. Demick

    2011-10-01

    This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

  2. OVERVIEW OF MODULAR HTGR SAFETY CHARACTERIZATION AND POSTULATED ACCIDENT BEHAVIOR LICENSING STRATEGY

    Energy Technology Data Exchange (ETDEWEB)

    Ball, Sydney J [ORNL

    2014-06-01

    This report provides an update on modular high-temperature gas-cooled reactor (HTGR) accident analyses and risk assessments. One objective of this report is to improve the characterization of the safety case to better meet current regulatory practice, which is commonly geared to address features of today s light water reactors (LWRs). The approach makes use of surrogates for accident prevention and mitigation to make comparisons with LWRs. The safety related design features of modular HTGRs are described, along with the means for rigorously characterizing accident selection and progression methodologies. Approaches commonly used in the United States and elsewhere are described, along with detailed descriptions and comments on design basis (and beyond) postulated accident sequences.

  3. LABORATORY-SCALE PRODUCTION OF ADU GELS BY EXTERNAL GELATION FOR AN INTERMEDIATE HTGR NUCLEAR

    Directory of Open Access Journals (Sweden)

    S Simbolon

    2015-03-01

    Full Text Available LABORATORY-SCALE PRODUCTION OF ADU GELS BY EXTERNAL GELATION FOR AN INTERMEDIATE HTGR NUCLEAR. The The aim of this research is to produce thousands of microsphere ADU (Ammonium Diuranate gels by using external gelation for an intermediate HTGR (High Temperature Gas-cooled Reactor nuclear fuel in laboratory-scale. Microsphere ADU gels were based on sol-solution which was made from a homogeneous mixture of ADUN (Acid Deficient Uranyl Nitrate which was containing uranyl ion in high concentration, a water soluble organic compound PVA (Polyvinyl Alcohol and THFA (Tetrahydrofurfuryl Alcohol. The simple unified home made laboratory experimental machine was developed to replace test tube experiment method which was once used due to a tiny amount of microsphere ADU gels produced. It consists of four main parts: tank filled sol-solution connecting to peristaltic pump and vibrating nozzle, preliminary gelation and gelation column. The machine has successfully converted 150 mL sol-solution into thousands of drops which produced 120 - 130 drops in each minute in steady state in ammonia gas free sector. Preliminary gelation reaction was carried out in ammonia gas sector where drops react with ammonia gas in a bat an eye followed by gelation reaction in column containing ammonia solution 7 M. In ageing process, ADU gels were collected and submerged into a vessel containing ammonia solution which was shaken for 1 hour in a shaker device. Isopropyl alcohol (90% solution was used to wash ADU gels and a digital camera was used to measured spherical form of ADU gels. Diameters in spherical spheroid form were found between 1.8 mm until 2.2 mm. The spherical purity of ADU gels were 10% - 20% others were oblate, prolate spheroid and microsphere which have hugetiny of dimples on the surface.   PRODUKSI GEL ADU SKALA LABORATORIUM DENGAN MENGGUNAKAN GELASI EKSTERNAL UNTUK BAHAN BAKAR ANTARA HTGR. Penelitian ini bertujuan untuk membuat ribuan gel bulat ADU (Ammonium

  4. Performance of HTGR biso- and triso-coated fertile particles irradiated in capsule HT-34

    Energy Technology Data Exchange (ETDEWEB)

    Long, E.L. Jr.; Tiegs, T.N.; Robbins, J.M.; Kania, M.J.

    1981-08-01

    Experiment HT-34, irradiated in the target region of the High Flux Isotope Reactor (HFIR), was designed to correlate HTGR Biso- and Triso-coated particle performance with fabrication parameters. Gamma analysis of the irradiated Triso-coated ThO/sub 2/ particles showed that the SiC deposited at the highest coating rate apparently had the best cesium-retention properties. Results of a similar analysis of the irradiated Biso-coated ThO/sub 2/ particles showed no differences in performance that could be related to coating conditions, but all the particles showed a significant loss of cesium (> 50%) at the higher temperatures. Pressure-vessel failures occurred with a significant number of particles; however, fission-gas-content measurements made at room temperature showed that the intact Biso particles from all batches except one became permeable during irradiation.

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

    Lifescience Database Archive (English)

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

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

    Lifescience Database Archive (English)

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

  7. Reliability Engineering Analysis of ATLAS Data Reprocessing Campaigns

    CERN Document Server

    Vaniachine, A; The ATLAS collaboration; Karpenko, D

    2013-01-01

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

  8. Reliability Engineering Analysis of ATLAS Data Reprocessing Campaigns

    CERN Document Server

    Vaniachine, A; The ATLAS collaboration; Karpenko, D

    2014-01-01

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

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

    Data.gov (United States)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Klepper, O.H.

    1985-06-01

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

  11. Advanced Safeguards Approaches for New Reprocessing Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Richard; Ehinger, Michael H.; Kovacic, Don N.; Tolk, K.

    2007-06-24

    U.S. efforts to promote the international expansion of nuclear energy through the Global Nuclear Energy Partnership (GNEP) will result in a dramatic expansion of nuclear fuel cycle facilities in the United States. New demonstration facilities, such as the Advanced Fuel Cycle Facility (AFCF), the Advanced Burner Reactor (ABR), and the Consolidated Fuel Treatment Center (CFTC) will use advanced nuclear and chemical process technologies that must incorporate increased proliferation resistance to enhance nuclear safeguards. The ASA-100 Project, “Advanced Safeguards Approaches for New Nuclear Fuel Cycle Facilities,” commissioned by the NA-243 Office of NNSA, has been tasked with reviewing and developing advanced safeguards approaches for these demonstration facilities. Because one goal of GNEP is developing and sharing proliferation-resistant nuclear technology and services with partner nations, the safeguards approaches considered are consistent with international safeguards as currently implemented by the International Atomic Energy Agency (IAEA). This first report reviews possible safeguards approaches for the new fuel reprocessing processes to be deployed at the AFCF and CFTC facilities. Similar analyses addressing the ABR and transuranic (TRU) fuel fabrication lines at AFCF and CFTC will be presented in subsequent reports.

  12. Environmental Impacts on Nuclear Reprocessing Solvents

    Science.gov (United States)

    Gillens, A. R.; Fessenden, J. E.

    2009-12-01

    Nuclear tests have been employed ever since the first nuclear explosion in Alamogordo, NM during the mid-1940s. Nuclear weapons pose a threat to civil society and result in extensive biological (medical) damages. For this reason, treaties banning nuclear tests and weapons have been employed since the 1960s to cease proliferation of weapons. However, as nuclear tests continue in secrecy and actinides, such as plutonium and uranium, are eligible for theft, nuclear forensics is needed to prevent weapons proliferation. In this study, solvents [tributyl phosphate (TBP), dodecane, decanol] used in reprocessing spent nuclear fuel are analyzed using an isotope ratio mass spectrometer, which provides indisputable evidence in identifying the operation in which solvents were used. Solvent samples are observed under variable conditions in the laboratory for different time periods. It is assumed that their carbon isotope values (δ13C) will become more positive (shift heavy) with time. It is found that the solvents are hygroscopic. TBP leaves the most robust signature compared to the other solvents studied and the isotope values for all solvents under all conditions become more positive with time. This study serves as primary research in understanding how solvents behave under variable conditions in the laboratory and how this could be translated to the environment in fate and transport studies.

  13. Interim Design Report

    CERN Document Server

    Choubey, S.; Goswami, S.; Berg, J.S.; Fernow, R.; Gallardo, J.C.; Gupta, R.; Kirk, H.; Simos, N.; Souchlas, N.; Ellis, M.; Kyberd, P.; Benedetto, E.; Fernandez-Martinez, E.; Efthymiopoulos, I.; Garoby, R.; Gilardoni, S.; Martini, M.; Prior, G.; Ballett, P.; Pascoli, S.; Bross, A.; Geer, S.; Johnstone, C.; Kopp, J.; Mokhov, N.; Morfin, J.; Neuffer, D.; Parke, S.; Popovic, M.; Strait, J.; Striganov, S.; Blondel, A.; Dufour, F.; Laing, A.; Soler, F.J.P; Lindner, M.; Schwetz, T.; Alekou, A.; Apollonio, M.; Aslaninejad, M.; Bontoiu, C.; Dornan, P.; Eccleston, R.; Kurup, A.; Long, K.; Pasternak, J.; Pozimski, J.; Bogacz, A.; Morozov, V.; Roblin, Y.; Bhattacharya, S.; Majumdar, D.; Mori, Y.; Planche, T.; Zisman, M.; Cline, D.; Stratakis, D.; Ding, X.; Coloma, P.; Donini, A.; Gavela, B.; Lopez Pavon, J.; Maltoni, M.; Bromberg, C.; Bonesini, M.; Hart, T.; Kudenko, Y.; Mondal, N.; Antusch, S.; Blennow, M.; Ota, T.; Abrams, R.J.; Ankenbrandt, C.M.; Beard, K.B.; Cummings, M.A.C.; Flanagan, G.; Johnson, R.P.; Roberts, T.J.; Yoshikawa, C.Y.; Migliozzi, P.; Palladino, V.; de Gouvea, A.; Graves, V.B.; Kuno, Y.; Peltoniemi, J.; Blackmore, V.; Cobb, J.; Witte, H.; Mezzetto, M.; Rigolin, S.; McDonald, K.T.; Coney, L.; Hanson, G.; Snopok, P.; Tortora, L.; Andreopoulos, C.; Bennett, J.R.J.; Brooks, S.; Caretta, O.; Davenne, T.; Densham, C.; Edgecock, R.; Kelliher, D.; Loveridge, P.; McFarland, A.; Machida, S.; Prior, C.; Rees, G.; Rogers, C.; Thomason, J.W.G.; Booth, C.; Skoro, G.; Karadzhov, Y.; Matev, R.; Tsenov, R.; Samulyak, R.; Mishra, S.R.; Petti, R.; Dracos, M.; Yasuda, O.; Agarwalla, S.K.; Cervera-Villanueva, A.; Gomez-Cadenas, J.J.; Hernandez, P.; Li, T.; Martin-Albo, J.; Huber, P.; Back, J.; Barker, G.; Harrison, P.; Meloni, D.; Tang, J.; Winter, W.

    2011-01-01

    The International Design Study for the Neutrino Factory (the IDS-NF) was established by the community at the ninth "International Workshop on Neutrino Factories, super-beams, and beta- beams" which was held in Okayama in August 2007. The IDS-NF mandate is to deliver the Reference Design Report (RDR) for the facility on the timescale of 2012/13. In addition, the mandate for the study [3] requires an Interim Design Report to be delivered midway through the project as a step on the way to the RDR. This document, the IDR, has two functions: it marks the point in the IDS-NF at which the emphasis turns to the engineering studies required to deliver the RDR and it documents baseline concepts for the accelerator complex, the neutrino detectors, and the instrumentation systems. The IDS-NF is, in essence, a site-independent study. Example sites, CERN, FNAL, and RAL, have been identified to allow site-specific issues to be addressed in the cost analysis that will be presented in the RDR. The choice of example sites shou...

  14. Suomi NPP VIIRS Reflective Solar Bands Operational Calibration Reprocessing

    Directory of Open Access Journals (Sweden)

    Slawomir Blonski

    2015-12-01

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

  15. 32 CFR 776.82 - Interim suspension.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 5 2010-07-01 2010-07-01 false Interim suspension. 776.82 Section 776.82... Complaint Processing Procedures § 776.82 Interim suspension. (a) Where the Rules Counsel determines there is... interim suspension, pending completion of a professional responsibility investigation. The covered...

  16. 22 CFR 127.8 - Interim suspension.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Interim suspension. 127.8 Section 127.8 Foreign... Interim suspension. (a) The Managing Director of the Directorate of Defense Trade Controls or the Director of the Office of Defense Trade Controls Compliance is authorized to order the interim suspension of...

  17. Pyrochemical reprocessing research activities in India

    Energy Technology Data Exchange (ETDEWEB)

    Nagarajan, K.; Subramanian, T.; Reddy, B. P.; Mohandas, K. S.; Mudali, U. K.; Kutty, K. V. G.; Rao, P. R. V.; Raj, B. [Indira Gandhi Centre for Atomic Research, Tamilnadu (India)

    2008-08-15

    It is planned to introduce metallic fuels in the Indian Fast Breeder Reactors beyond 2020 to meet the increasing energy demands of the country. A well-defined road map for the development of all aspects of the metal fuel cycle has been drawn up and the activities have been taken up. Development of pyrochemical reprocessing for metallic fuels started with the commissioning of a laboratory scale argon atmosphere glove box facility. The status of pyroprocess development studies was described in the first IPRC 2006. An engineering scale demonstration facility for gaining experience with bulk processing is being set up which will be commissioned soon. Development of compatible materials, fabrication technology and coatings for use in various unit operations like salt preparation, electrorefining, cathode processing etc. is anther activity being pursued. Components made of type 316L SS, Ni-base alloys, Cr-Mo steels and high density graphite will be utilized for the molten chloride and cadmium environment. Attempts have been made to study the corrosion behaviour of type 316L SS in molten chloride (LiCl+KCl) for considering its application for salt preparation and other containers. For better service and life, zirconia based ceramic coatings with a bond coat of MCrAlY has been proposed over the components employed towards this purpose. The studies indicated that the partially stabilized zirconia coating on 316L SS worked without significant degradation up to 1000 h. An attempt was also made to study the consolidation of such coatings on type 316L SS through laser surface treatment.

  18. UNIFRAME interim design report. [Fuel element size reduction plant

    Energy Technology Data Exchange (ETDEWEB)

    Strand, J.B.; Baer, J.W.; Cook, E.J.

    1977-12-01

    A fuel element size reduction system has been designed for the ''cold'' pilot-scale plant for an HTGR Fuel Reference Recycle Facility. This report describes in detail the present design.

  19. IAEA CRP on HTGR Uncertainties in Modeling: Assessment of Phase I Lattice to Core Model Uncertainties

    Energy Technology Data Exchange (ETDEWEB)

    Rouxelin, Pascal Nicolas [Idaho National Lab. (INL), Idaho Falls, ID (United States); Strydom, Gerhard [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-09-01

    Best-estimate plus uncertainty analysis of reactors is replacing the traditional conservative (stacked uncertainty) method for safety and licensing analysis. To facilitate uncertainty analysis applications, a comprehensive approach and methodology must be developed and applied. High temperature gas cooled reactors (HTGRs) have several features that require techniques not used in light-water reactor analysis (e.g., coated-particle design and large graphite quantities at high temperatures). The International Atomic Energy Agency has therefore launched the Coordinated Research Project on HTGR Uncertainty Analysis in Modeling to study uncertainty propagation in the HTGR analysis chain. The benchmark problem defined for the prismatic design is represented by the General Atomics Modular HTGR 350. The main focus of this report is the compilation and discussion of the results obtained for various permutations of Exercise I 2c and the use of the cross section data in Exercise II 1a of the prismatic benchmark, which is defined as the last and first steps of the lattice and core simulation phases, respectively. The report summarizes the Idaho National Laboratory (INL) best estimate results obtained for Exercise I 2a (fresh single-fuel block), Exercise I 2b (depleted single-fuel block), and Exercise I 2c (super cell) in addition to the first results of an investigation into the cross section generation effects for the super-cell problem. The two dimensional deterministic code known as the New ESC based Weighting Transport (NEWT) included in the Standardized Computer Analyses for Licensing Evaluation (SCALE) 6.1.2 package was used for the cross section evaluation, and the results obtained were compared to the three dimensional stochastic SCALE module KENO VI. The NEWT cross section libraries were generated for several permutations of the current benchmark super-cell geometry and were then provided as input to the Phase II core calculation of the stand alone neutronics Exercise

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

    Energy Technology Data Exchange (ETDEWEB)

    Soelberg, Nicolas R.; Garn, Troy; Greenhalgh, Mitchell; Law, Jack; Jubin, Robert T.; Strachan, Denis M.; Thallapally, Praveen K.

    2013-07-22

    Nuclear fission results in the production of fission products and activation products, some of which tend to be volatile during used fuel reprocessing. These can evolve in volatile species in the reprocessing facility off-gas streams, depending on the separations and reprocessing technologies that are used. Radionuclides that have been identified as “volatile radionuclides” are noble gases (most notably isotopes of Kr and Xe); 3H; 14C; and 129I. Radionuclides that tend to form volatile species that evolve into reprocessing facility off-gas systems are more challenging to efficiently control compared to radionuclides that tend to stay in solid or liquid phases. Future used fuel reprocessing facilities in the United States can require efficient capture of some volatile radionuclides in their off-gas streams to meet regulatory emission requirements. In aqueous reprocessing, these radionuclides are most commonly expected to evolve into off-gas streams in tritiated water [3H2O (T2O) and 3HHO (THO)], radioactive CO2, noble gases, and gaseous HI, I2, or volatile organic iodides. The fate and speciation of these radionuclides from a non-aqueous fuel reprocessing facility is less well known at this time, but active investigations are in progress. An Off-Gas Sigma Team was formed in late FY 2009 to integrate and coordinate the Fuel Cycle Research and Development (FCR&D) activities directed towards the capture and sequestration of the these volatile radionuclides (Jubin 2012a). The Sigma Team concept was envisioned to bring together multidisciplinary teams from across the DOE complex that would work collaboratively to solve the technical challenges and to develop the scientific basis for the capture and immobilization technologies such that the sum of the efforts was greater than the individual parts. The Laboratories currently participating in this effort are Argonne National Laboratory (ANL), Idaho National Laboratory (INL), Oak Ridge National Laboratory (ORNL), Pacific

  1. INVESTIGATION ON THERMAL-FLOW CHARACTERISTICS OF HTGR CORE USING THERMIX-KONVEK MODULE AND VSOP'94 CODE

    Directory of Open Access Journals (Sweden)

    Sudarmono Sudarmono

    2015-03-01

    Full Text Available The failure of heat removal system of water-cooled reactor such as PWR in Three Mile Islands and Fukushima Daiichi BWR makes nuclear society starting to consider the use of high temperature gas-cooled reactor (HTGR. Reactor Physics and Technology Division – Center for Nuclear Reactor Safety and Technology  (PTRKN has tasks to perform research and development on the conceptual design of cogeneration gas cooled reactor with medium power level of 200 MWt. HTGR is one of nuclear energy generation system, which has high energy efficiency, and has high and clean inherent safety level. The geometry and structure of the HTGR200 core are designed to produce the output of helium gas coolant temperature as high as 950 °C to be used for hydrogen production and other industrial processes in co-generative way. The output of very high temperature helium gas will cause thermal stress on the fuel pebble that threats the integrity of fission product confinement. Therefore, it is necessary to perform thermal-flow evaluation to determine the temperature distribution in the graphite and fuel pebble in the HTGR core. The evaluation was carried out by Thermix-Konvek module code that has been already integrated into VSOP'94 code. The HTGR core geometry was done using BIRGIT module code for 2-D model (RZ model with 5 channels of pebble flow in active core in the radial direction. The evaluation results showed that the highest and lowest temperatures in the reactor core are 999.3 °C and 886.5 °C, while the highest temperature of TRISO UO2 is 1510.20 °C in the position (z= 335.51 cm; r=0 cm. The analysis done based on reactor condition of 120 kg/s of coolant mass flow rate, 7 MPa of pressure and 200 MWth of power. Compared to the temperature distribution resulted between VSOP’94 code and fuel temperature limitation as high as 1600 oC, there is enough safety margin from melting or disintegrating. Keywords: Thermal-Flow, VSOP’94, Thermix-Konvek, HTGR, temperature

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

    Lifescience Database Archive (English)

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

  3. Equipment specifications for an electrochemical fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Hemphill, Kevin P [Los Alamos National Laboratory

    2010-01-01

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

  4. Fort Saint Vrain HTGR (Th/U carbide) Fuel Characteristics for Disposal Criticality Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, Larry Lorin

    2001-01-01

    DOE-owned spent nuclear fuels encompass many fuel types. In an effort to facilitate criticality analysis for these various fuel types, they were categorized into eight characteristic fuel groups with emphasis on fuel matrix composition. Out of each fuel group, a representative fuel type was chosen for analysis as a bounding case within that fuel group. Generally, burnup data, fissile enrichments and total fuel mass govern the selection of the representative or candidate fuel within that group. For the HTGR group, the Fort Saint Vrain (FSV) reactor fuel has been chosen for the evaluation of viability for waste co-disposal. The FSV reactor was operated by Public Service of Colorado as a licensed power reactor. The FSV fuel employs a U/Th carbide matrix in individually pyrolytic carbon-coated particles. These individual particles are in turn coated with silicon carbide (SiC) and contained within fuel compacts, that are in turn embedded in graphite blocks that comprised the structural core of the reactor.

  5. Sodemme: natural circulation thermal-hydraulics code for HTGR transient analysis

    Energy Technology Data Exchange (ETDEWEB)

    Epel, L.G.

    1977-07-01

    The SODEMME code provides a Solution to the One Dimensional Energy, Mass and Momentum Equations for a system of ''volumes'' and ''segments'' that comprise a circulating system containing a gaseous coolant. Input consists of a description of the system's geometry, the user's choice of some control variables, specification of the initial and time-dependent boundary conditions and setting various options for items such as pumping head, heat transfer and frictional effects. The program automatically finds the steady state solution corresponding to the initial conditions and then proceeds to compute the transient solution corresponding to the input boundary conditions. The present code is designed to operate with helium as the coolant but can very easily be altered to function with any gas by changing a few program statements. It is somewhat unique in that it is particularly suitable for solving natural circulation problems. The program has been written in modular form so that applications to diverse systems can be accommodated in the future by rewriting the subroutine that computes the heat transfer in particular components of the system being studied. The version described in this report is applicable to the 3000 MWth HTGR design.

  6. Thermophoretic and turbulent deposition of graphite dust in HTGR steam generators

    Energy Technology Data Exchange (ETDEWEB)

    Peng, Wei, E-mail: pengwei@tsinghua.edu.cn [Institute of Nuclear and New Energy Technology of Tsinghua University, Advanced Nuclear Energy Technology Cooperation Innovation Center, The Key Laboratory of Advanced Nuclear Engineering and Safety, Ministry of Education, Beijing 100084 (China); Zhang, Tianqi; Sun, Xiaokai [Institute of Nuclear and New Energy Technology of Tsinghua University, Advanced Nuclear Energy Technology Cooperation Innovation Center, The Key Laboratory of Advanced Nuclear Engineering and Safety, Ministry of Education, Beijing 100084 (China); Yu, Suyuan, E-mail: suyuan@tsinghua.edu.cn [Center for Combustion Energy, The Key Laboratory for Thermal Science and Power Engineering, Ministry of Education, Tsinghua University, Beijing 100084 (China)

    2016-04-15

    Graphical abstract: Most of small graphite dust particles are deposited in steam generators at low reactor power levels, mostly small and large particles are deposited with few medium-size particles at high reactor power levels. - Highlights: • Thermophoretic deposition is the main mechanism for small particles. • Turbulent deposition is dominant for large particles. • Mostly small particles were deposited at low reactor power. • Both small and large particles are deposited at high reactor power. - Abstract: The present study calculated the graphite dust deposition in the steam generator of HTGR by using a thermophoretic deposition model and a turbulent deposition model based on the temperature and flow field distributions calculated by a computational fluid dynamics (CFD) model. The results showed that the heat flux along the heat transfer surface was not evenly distributed which affect the particle deposition. Thermophoretic deposition is the main factor causing small graphite dust particles to deposit on the surface while turbulent deposition plays the dominant role for large particle deposition. The results also indicate that the deposited particles are mainly small graphite dust particles in steam generator when the reactor is running at low power, with both small and large graphite dust particles at high reactor power levels with fewer medium size particles.

  7. Analysis of fission product behavior in the Saclay Spitfire Loop Test SSL-1. [HTGR

    Energy Technology Data Exchange (ETDEWEB)

    Jensen, D.D.; Haire, M.J.; Ballagny, A.

    1978-02-01

    The behavior of the fission metal cesium and the fission gases krypton and xenon in the Saclay Spitfire Loop SSL-1 test has been compared to that predicted using General Atomic reference data and computer code models. This is the first in a series of analyses planned in order to provide quantitative validation of HTGR fission product design methods. In this analysis, the first attempt to rigorously verify fission product design methods, the FIPERQ code was used to model the diffusion of cesium graphite and release to the coolant stream. The comparisons showed that the cesium profile shape in the graphite web and the partition coefficient between fuel rod matrix material and fuel element graphite were correctly modeled, although the overall release was significantly underpredicted. Uncertainties in the source term (fissile particle failure fraction) and total release to the coolant precluded an accurate appraisal of the validity of FIPERQ. However, several recommendations are presented to improve the applicability of future in-pile test data for the validation of fission metal release codes. The half-life dependence of fission gas release during irradiation was found to be in good agreement with the model used in the reference design materials, providing assurance that this aspect of the fission gas release predictions is properly modeled.

  8. The challenges facing the long term interim storage

    Energy Technology Data Exchange (ETDEWEB)

    Iracane, D. [CEA Sacaly, Dir. de la Simulation et des Outils Experimentaux-DSOE, 91 - Gif sur Yvette (France); Marvy, A. [CEA Saclay, Dir. du Developpement et de l' Innovation Nucleares-DDIN, 91 - Gif Sur Yvette (France)

    2001-07-01

    In France electricity generation by means of commercial nuclear power plants has come to a point where it contributes to the national demand at a level of 80%. The safety performance of the production system has also reached a high level of both maturity and reliability taking advantage of the cumulative effect of a 30 years long learning experience and ever more stringent safety requirements. The policy to reprocess spent fuel has been overriding but no final decision has yet been made regarding the ultimate disposition of the waste streams. Although studies on deep geological disposal are ongoing, France is also looking at whether and under which conditions a long-term interim storage may provide an effective flexibility to the fuel cycle back-end. We discuss thereafter the needs and the paramount objectives of this latter R and D program. Results are being framed as potential guiding criteria for decision makers and various stakeholders. In first part, we propose a general analysis which emphasises that a long term interim storage is more than a classical nuclear facility because it explicitly requires long-lasting control and creates a burden for Society during many generations. Then, in second part, we offer an overview of the technical results from the R and D program as they stand at the time of writing. As an answer to the Government request, a strong emphasis has been put on this research for three years. Conclusion is an attempt to outline the societal context in which future decisions will have to be made. (author)

  9. Study on interim storage system to utilize waste heat from spent fuels

    Energy Technology Data Exchange (ETDEWEB)

    Aritomi, Masanori [Tokyo Inst. of Tech. (Japan); Kurokawa, Hideaki; Kamiyama, Yoshinori; Yamanaka, Tsuneyasu

    1997-12-31

    Spent fuels amounting to about 30 tons a year are generated by a 1,000MWe-class light water reactor (LWR). However, the whole amount of spent fuels generated by LWRs cannot be reprocessed. From the viewpoint of energy resources, it is believed in Japan that fast breeder reactors will be introduced as commercial power reactors in the future. In that time, it admits of no doubt that the spent fuel will be a valuable energy resource. It is, therefore, an urgent problem in Japan to establish interim storage systems of spent fuels for LWRs to continue smoothly in operation. In this work, the spent fuel is treated not as unwanted waste but as a heat source. At first, various kinds of interim storage systems of spent fuel are examined from the viewpoint of the utilization of the waste heat, and a pool storage system is dealt with. Next, the possibility of the utilization of the waste heat are examined. Finally, a concept of the interim storage plant, which supplies the heat to a green house where flowers with high value added such as orchids are cultivated, is proposed as a demonstration plant. (author)

  10. Design study on advanced reprocessing systems for FR fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Tanaka, H.; Kawamura, F.; Nishimura, T.; Kamiya, M. [Japan Nuclear Cycle Development Institute, Ibaraki (Japan)

    2001-07-01

    A design study has been carried out for four advanced reprocessing technologies for the future fast rector (FR) recycle systems (advanced aqueous, and three non-aqueous systems based on oxide electrowinning, metal electrorefining, and fluoride volatility methods). The systems were evaluated mainly from the viewpoint of economics. It has been shown that, for MOX fuel reprocessing, all the systems with a capacity of 200 t/y attains the economical target, whereas for such a small capacity as 50 t/y, only the non-aqueous systems have potential to attain the target. For metallic and nitride fuel, a metal electrorefining system has been shown to be advantageous. (author)

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

    African Journals Online (AJOL)

    Effect of Reprocessing and Excipient Characteristics on. Ibuprofen Tablet Properties. John Rojas*, Carlos Zuluaga and Andrés Cadavid. Department of Pharmacy, School of Pharmaceutical Chemistry, The University of Antioquia, Medellin, Colombia. *For correspondence: Email: jrojasca@gmail.com; Tel: 574 219 5472.

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

    African Journals Online (AJOL)

    Methods: The effect of excipient type, technology and reprocessing on flow, compressibility and compactibility was assessed using and 8x2x2 factorial design. Design Expert® v.8.01 software was employed for data analysis. Pure excipients were processed by direct compression, while the ibuprofen:excipient mixtures were ...

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

    Science.gov (United States)

    Erwin, Terry McVannel

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

  14. Technical specifications on the welding in fuel reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-04-01

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

  15. Are interim management statements redundant?

    OpenAIRE

    Schleicher, T.; Walker, Martin

    2015-01-01

    In 2004 the Transparency Directive increased the reporting frequency by mandating the Interim Management Statement (IMS). However, only nine years later, the EU announced that it was making quarterly reporting voluntary again arguing that IMSs are redundant as they are unlikely to contain any additional information not already required by the Market Abuse Directive (MAD). The current paper tests this argument empirically. For that it collects data on trading statements from a post-MAD pre-IMS...

  16. Burn site groundwater interim measures work plan.

    Energy Technology Data Exchange (ETDEWEB)

    Witt, Jonathan L. (North Wind, Inc., Idaho Falls, ID); Hall, Kevin A. (North Wind, Inc., Idaho Falls, ID)

    2005-05-01

    This Work Plan identifies and outlines interim measures to address nitrate contamination in groundwater at the Burn Site, Sandia National Laboratories/New Mexico. The New Mexico Environment Department has required implementation of interim measures for nitrate-contaminated groundwater at the Burn Site. The purpose of interim measures is to prevent human or environmental exposure to nitrate-contaminated groundwater originating from the Burn Site. This Work Plan details a summary of current information about the Burn Site, interim measures activities for stabilization, and project management responsibilities to accomplish this purpose.

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

    Science.gov (United States)

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

    2010-05-01

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

  18. Control and simulation of a HTGR-GT combined heat and power plant

    Energy Technology Data Exchange (ETDEWEB)

    Kikstra, J.F. [ECN Nuclear Research, Petten (Netherlands)

    1998-09-01

    In the Dutch INCOGEN research program, a small modular High Temperature Gas-cooled Reactor - Gas Turbine (HTGR-GT) system for Combined Heat and Power (CHP) generation was studied. In a CHP plant off-design operation is of high importance, since the heat demand can vary considerably (in particular for district heating)and at the same time has to be fulfilled at every moment. In this study two typical CHP-systems are considered: (1) coproduction of electricity and industrial steam (10 bar 220C) and (2) coproduction of electricity and hot water for district heating (supply temperature 125C). For these two systems the layout and off-design conditions giving optimum efficiency have been established. It can be concluded that the conditions in the reactor core can be held fairly constant, although optimum temperatures and flows in the system vary strongly with the heat to power ratio. For the design of a control system, the process conditions which have to be controlled and possible control input variables have been identified. Subsequently, a control structure is proposed in which both electrical and heat demand can be followed. The control system uses mainly inventory control and control of compressor inlet temperature, while during fast transients bypass-control can be used to prevent thermal stresses. In order to test different control structures, a dynamic, first principles model is under construction. The model is based on one-dimensional heat-, mass- and momentum balances, thermodynamic fluid properties and semi-empirical correlations for e.g. heat transfer and compressor performance. Principles of the system modelling are described and an example of a model of a sub-unit is given. 12 refs.

  19. 3D Nondestructive Visualization and Evaluation of TRISO Particles Distribution in HTGR Fuel Pebbles Using Cone-Beam Computed Tomography

    Directory of Open Access Journals (Sweden)

    Gongyi Yu

    2017-01-01

    Full Text Available A nonuniform distribution of tristructural isotropic (TRISO particles within a high-temperature gas-cooled reactor (HTGR pebble may lead to excessive thermal gradients and nonuniform thermal expansion during operation. If the particles are closely clustered, local hotspots may form, leading to excessive stresses on particle layers and an increased probability of particle failure. Although X-ray digital radiography (DR is currently used to evaluate the TRISO distributions in pebbles, X-ray DR projection images are two-dimensional in nature, which would potentially miss some details for 3D evaluation. This paper proposes a method of 3D visualization and evaluation of the TRISO distribution in HTGR pebbles using cone-beam computed tomography (CBCT: first, a pebble is scanned on our high-resolution CBCT, and 2D cross-sectional images are reconstructed; secondly, all cross-sectional images are restructured to form the 3D model of the pebble; then, volume rendering is applied to segment and display the TRISO particles in 3D for visualization and distribution evaluation. For method validation, several pebbles were scanned and the 3D distributions of the TRISO particles within the pebbles were produced. Experiment results show that the proposed method provides more 3D than DR, which will facilitate pebble fabrication research and production quality control.

  20. 19 CFR 356.18 - Interim sanctions.

    Science.gov (United States)

    2010-04-01

    ... ARTICLE 1904 OF THE NORTH AMERICAN FREE TRADE AGREEMENT Violation of a Protective Order or a Disclosure... administrative law judge to impose such sanctions. (b) The administrative law judge may impose interim sanctions... interim sanctions are a reasonable means for protecting the rights of the Department, authorized agency of...

  1. Solid waste burial grounds interim safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Saito, G.H.

    1994-10-01

    This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment.

  2. Vet Centers. Interim final rule.

    Science.gov (United States)

    2015-08-04

    The Department of Veterans Affairs (VA) is amending its medical regulation that governs Vet Center services. The National Defense Authorization Act for Fiscal Year 2013 (the 2013 Act) requires Vet Centers to provide readjustment counseling services to broader groups of veterans, members of the Armed Forces, including a member of a reserve component of the Armed Forces, and family members of such veterans and members. This interim final rule amends regulatory criteria to conform to the 2013 Act, to include new and revised definitions.

  3. Inspiration fra New York - udforskende læreprocesser

    DEFF Research Database (Denmark)

    Jørgensen, Lone Tang

    2017-01-01

    Udforskende læreprocesser er inspireret af John Deweys filosofi og pædagogik og bygger på en didaktisk tilrettelæggelse, der vægter den demokratiske dannelse og børnenes medindflydelse på det, der arbejdes med i klasserummet. Børnenes erfaringer, interesser og engagement er selve afsættet...... for tilrettelæggelse af læreprocesserne. Med udgangspunkt i Deweys ideer om skolen, baseret på den eksperimentelle metode, præsenteres Paula Rogovins arbejde på Manhattan New School i New York som et eksempel på, hvordan arbejdet med udforskende læreprocesser kan tilrettelægges....

  4. Reprocessing seismic data: better results below diabase sills

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

    The effect of the diabase sills in the seismic data processing has been studied in the last twenty years. These rocks strongly influence the exploratory activities in a basin, because the diabase disturbs the sign and generates multiple and spherical divergence, increasing the exploratory risk in these areas. In the present work a method of 2D seismic reprocessing will be presented using Prestack Kirchhoff Time Migration in an older seismic data of Solimoes basin. The objective of this paper is to show the high results on the reprocessing seismic data below the diabase sills. The 2D lines processed give relevant improvement of the quality of signal, showing better the faults zones and preserving the geological structures than the older data. (author)

  5. The sterilization efficacy of reprocessed single use diathermy pencils.

    Science.gov (United States)

    Batista Neto, Simone; Graziano, Kazuko Uchikawa; Padoveze, Maria Clara; Kawagoe, Júlia Yaeko

    2010-01-01

    In Brazil, single use diathermy pencils (SUDP) are among the most common reused devices. This study assesses the sterilization efficacy of reprocessing SUDP using two cleansing methods (manual or automated), followed by one of three of the low-temperature sterilization methods: Hydrogen Peroxide Plasma (HPP), Ethylene Oxide (ETO) or Low-Temperature Steam Formaldehyde (LTSF). The sample was composed of 360 SUDP after their first use. The probability of sterilization failure was estimated considering the number of positive microbiological results obtained by cultures of the studied devices. The overall sterilization failure probability for SUDP was 0.26. The sterilization method, which presented the lowest failure probability was the LTSF (0.01), followed by ETO (0.21) and HPP (0.56). Automated cleansing obtained a better result than manual cleansing. This trial demonstrated that the probability of sterilization in reprocessed SUDP is highly dependent on both the type of cleansing and the sterilization method applied.

  6. Noble Gas Measurement and Analysis Technique for Monitoring Reprocessing Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Charlton, William S [Univ. of California, Berkeley, CA (United States)

    1999-09-01

    An environmental monitoring technique using analysis of stable noble gas isotopic ratios on-stack at a reprocessing facility was developed. This technique integrates existing technologies to strengthen safeguards at reprocessing facilities. The isotopic ratios are measured using a mass spectrometry system and are compared to a database of calculated isotopic ratios using a Bayesian data analysis method to determine specific fuel parameters (e.g., burnup, fuel type, fuel age, etc.). These inferred parameters can be used by investigators to verify operator declarations. A user-friendly software application (named NOVA) was developed for the application of this technique. NOVA included a Visual Basic user interface coupling a Bayesian data analysis procedure to a reactor physics database (calculated using the Monteburns 3.01 code system). The integrated system (mass spectrometry, reactor modeling, and data analysis) was validated using on-stack measurements during the reprocessing of target fuel from a U.S. production reactor and gas samples from the processing of EBR-II fast breeder reactor driver fuel. These measurements led to an inferred burnup that matched the declared burnup with sufficient accuracy and consistency for most safeguards applications. The NOVA code was also tested using numerous light water reactor measurements from the literature. NOVA was capable of accurately determining spent fuel type, burnup, and fuel age for these experimental results. Work should continue to demonstrate the robustness of this system for production, power, and research reactor fuels.

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

    Energy Technology Data Exchange (ETDEWEB)

    Soelberg, Nick R. [Idaho National Laboratory, Idaho Falls, ID 83415, USA; Garn, Troy G. [Idaho National Laboratory, Idaho Falls, ID 83415, USA; Greenhalgh, Mitchell R. [Idaho National Laboratory, Idaho Falls, ID 83415, USA; Law, Jack D. [Idaho National Laboratory, Idaho Falls, ID 83415, USA; Jubin, Robert [Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA; Strachan, Denis M. [Pacific Northwest National Laboratory, Richland, WA 99252, USA; Thallapally, Praveen K. [Pacific Northwest National Laboratory, Richland, WA 99252, USA

    2013-01-01

    The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessing facility in the US. Various control technologies have been developed, tested, or used over the past 50 years for control of volatile radionuclide emissions from used fuel reprocessing plants. The US DOE has sponsored, since 2009, an Off-gas Sigma Team to perform research and development focused on the most pressing volatile radionuclide control and immobilization problems. In this paper, we focus on the control requirements and methodologies for85Kr and129I. Numerous candidate technologies have been studied and developed at laboratory and pilot-plant scales in an effort to meet the need for high iodine control efficiency and to advance alternatives to cryogenic separations for krypton control. Several of these show promising results. Iodine decontamination factors as high as 105, iodine loading capacities, and other adsorption parameters including adsorption rates have been demonstrated under some conditions for both silver zeolite (AgZ) and Ag-functionalized aerogel. Sorbents, including an engineered form of AgZ and selected metal organic framework materials (MOFs), have been successfully demonstrated to capture Kr and Xe without the need for separations at cryogenic temperatures.

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

    Directory of Open Access Journals (Sweden)

    Nick R. Soelberg

    2013-01-01

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

  9. Succesvol interim-management : Meesterschap in een tijdelijke context

    NARCIS (Netherlands)

    Schaveling, J.

    2010-01-01

    Als flexibele optie om het management van organisaties aan te vullen, past interim-management helemaal in deze tijd. Maar wat maakt een interim-managementopdracht succesvol? ‘Succesvol interim-management’ is een studie naar de succesfactoren van interim-management. In de literatuur worden

  10. Scoren met interim-management : De weg naar tevreden opdrachtgevers

    NARCIS (Netherlands)

    Schaveling, J.

    2010-01-01

    Tegenwoordig kijkt niemand in organisaties meer op van de aanwezigheid van interim-managers. Interim-management biedt dé flexibiliteit om het management van organisaties aan te vullen. Maar wat maakt interim-managementopdrachten succesvol? Daarover gaat 'Scoren met interim-management: de weg naar

  11. 46 CFR 309.101 - Amendment of interim binders.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 8 2010-10-01 2010-10-01 false Amendment of interim binders. 309.101 Section 309.101... INSURANCE § 309.101 Amendment of interim binders. The interim binder for a vessel whose stated valuation is... after the attachment of the insurance under the interim binder to which such valuation applies...

  12. Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: reprocessing of high-temperature gas-cooled reactor fuel containing U-233 and thorium

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-05-01

    A cost/benefit study was made to determine the cost and effectiveness of various radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from a model high-temperature gas-cooled reactor (HTGR) fuel reprocessing plant and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist the U. S. Nuclear Regulatory Commission in defining the term as low as reasonably achievable as it applies to this nuclear facility. The base case is representative of conceptual, developing technology of head-end graphite-burning operations and of extensions of solvent-extraction technology of current designs for light-water-reactor (LWR) fuel reprocessing plants. The model plant has an annual capacity of 450 metric tons of heavy metal (MTHM, where heavy metal is uranium plus thorium), as charged to about fifty 1000-MW(e) HTGRs. 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 capital and annual costs for the added waste treatment operations and the corresponding reductions in dose commitments are calculated for each case. In the final analysis, the cost/benefit of each case, calculated as additional cost of radwaste system divided by the reduction in dose commitment, is tabulated or the dose commitment is plotted with cost as the variable. The status of each of the radwaste treatment methods used in the case studies is discussed.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-12-01

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

  14. Effects of surface condition on the corrosion of candidate structural materials in a simulated HTGR-GT environment

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, L.D.

    1980-02-01

    A simulated high-temperature gas-cooled reactor (HTGR) helium environment was used to study the effects of surface finish conditions on the subsequent elevated-temperature corrosion behavior of key candidate structural materials. The environment contained helium with 500 ..mu..atm H/sub 2//50 ..mu..atm CO/50 ..mu..atm CH/sub 4//<0.5 ..mu..atm H/sub 2/O at 900/sup 0/C with total test exposure durations of 3000 hours. Specimens with lapped, grit-blasted, pickled, and preoxidized surface conditions were studied. Materials tested included two cast superalloys, IN 100 and IN 713LC; one centrifugally cast high-temperature alloy, HK 40 one oxice-dispersion-strengthened alloy, Inconel MA 754; and three wrought high-temperature alloys, Hastelloy Alloy X, Inconel Alloy 617, and Alloy 800H.

  15. In-line monitoring of effluents from HTGR fuel particle preparation processes using a time-of-flight mass spectrometer

    Energy Technology Data Exchange (ETDEWEB)

    Lee, D.A.; Costanzo, D.A.; Stinton, D.P.; Carpenter, J.A.; Rainey, W.T. Jr.; Canada, D.C.; Carter, J.A.

    1976-08-01

    The carbonization, conversion, and coating processes in the manufacture of HTGR fuel particles have been studied with the use of a time-of-flight mass spectrometer. Non-condensable effluents from these fluidized-bed processes have been monitored continuously from the beginning to the end of the process. The processes which have been monitored are these: uranium-loaded ion exchange resin carbonization, the carbothermic reduction of UO/sub 2/ to UC/sub 2/, buffer and low temperature isotropic pyrocarbon coatings of fuel kernels, SiC coating of the kernels, and high-temperature particle annealing. Changes in concentrations of significant molecules with time and temperature have been useful in the interpretation of reaction mechanisms and optimization of process procedures.

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

    Directory of Open Access Journals (Sweden)

    Ramage Gordon

    2011-01-01

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

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

    Science.gov (United States)

    Posmontier, Bobbie; Dovydaitis, Tiffany; Lipman, Kenneth

    2010-08-01

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

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

    Science.gov (United States)

    Menon, Sukanya B; Jayan, C

    2010-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-09-01

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

  20. Materials management in an internationally safeguarded fuels reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-04-01

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

  1. Development of high-strength concrete mix designs in support of the prestressed concrete reactor vessel design for a HTGR steam cycle/cogeneration plant

    Energy Technology Data Exchange (ETDEWEB)

    Naus, D.J.; Oland, C.B.

    1985-01-01

    Design optimization studies indicate that a significant reduction in the size of the PCRV for a 2240 MW(t) HTGR plant can be effected through utilization of high-strength concrete in conjunction with large capacity prestressing systems. A three-phase test program to develop and evaluate high-strength concretes (>63.4 MPa) is described. Results obtained under Phase I of the investigation related to materials selection-evaluation and mix design development are presented. 3 refs., 4 figs.

  2. HTGR Generic Technology Program: safety, systems and component design and development. Quarterly progress report for the period ending March 31, 1978

    Energy Technology Data Exchange (ETDEWEB)

    1978-04-01

    The work documented includes HTGR safety and safety-related studies to better understand and more accurately define safety characteristics and safety margins of GCRs under postulated accident conditions. Also included are the design, analysis, and testing of th PCRV, liner, penetrations, thermal barrier, reactor internals, steam generator, CAHE, and rotating machinery. Design studies and analysis plus experimental procedures and results are discussed and, where appropriate, the data are presented in tables, graphs, and photographs.

  3. Results of Koo measurements of HTGR lattice by oscillated zero reactivity technique using the AGIP-NUCLEARE RB-2 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Benedetti, F; Brighenti, G.; Chiodi, P.L.; Ghilardotti, G.; Giuliani, C.

    1974-10-15

    This paper describes k-infinity measurements conducted using an assembly of loose HTGR coated particles in the BR-2 reactor by means of null reactivity oscillating method comparing the effect of poisoned and unpoisoned lattices like tests performed in the Physical Constants Test Reactor (PCTR) at Hanford. The RB-2 reactor was the property of the Italian firm AGIP NUCLEARE and operated at the Montecuccolino Center in Bologna.

  4. General Atomic reprocessing pilot plant: description and results of initial testing

    Energy Technology Data Exchange (ETDEWEB)

    1977-12-01

    In June 1976 General Atomic completed the construction of a reprocessing head-end cold pilot plant. In the year since then, each system within the head end has been used for experiments which have qualified the designs. This report describes the equipment in the plant and summarizes the results of the initial phase of reprocessing testing.

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

    Science.gov (United States)

    2011-01-01

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

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

    Science.gov (United States)

    Protinsky, Howard; Sparks, Jennifer; Flemke, Kimberly

    2001-01-01

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

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

    Science.gov (United States)

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

    2011-01-10

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

  8. Methods Data Qualification Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    R. Sam Alessi; Tami Grimmett; Leng Vang; Dave McGrath

    2010-09-01

    The overall goal of the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) is to maintain data provenance for all NGNP data including the Methods component of NGNP data. Multiple means are available to access data stored in NDMAS. A web portal environment allows users to access data, view the results of qualification tests and view graphs and charts of various attributes of the data. NDMAS also has methods for the management of the data output from VHTR simulation models and data generated from experiments designed to verify and validate the simulation codes. These simulation models represent the outcome of mathematical representation of VHTR components and systems. The methods data management approaches described herein will handle data that arise from experiment, simulation, and external sources for the main purpose of facilitating parameter estimation and model verification and validation (V&V). A model integration environment entitled ModelCenter is used to automate the storing of data from simulation model runs to the NDMAS repository. This approach does not adversely change the why computational scientists conduct their work. The method is to be used mainly to store the results of model runs that need to be preserved for auditing purposes or for display to the NDMAS web portal. This interim report demonstrates the currently development of NDMAS for Methods data and discusses data and its qualification that is currently part of NDMAS.

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

    Science.gov (United States)

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

    2017-10-01

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

  10. Interim-Management: A paradox for leadership research?

    OpenAIRE

    Bruns, Jürgen; Kabst, Rüdiger

    2005-01-01

    The study focuses on Interim-Management as a so far rarely discussed phenomenon of the flexible firm. Contradicting popular leadership perception, the authors argue that Interim-Management does not constitute a leadership paradox but can be explained by established organization theory. In particular, transaction cost economics as well as resource-based view help explain the utilization of Interim-Management. Furthermore, the authors show that Interim-Management constitutes a response to reduc...

  11. Evaluation of single-use reprocessed laparoscopic instrument sterilization.

    Science.gov (United States)

    Lopes, Cristiane de Lion Botero Couto; Graziano, Kazuko Uchikawa; Pinto, Terezinha de Jesus Andreoli

    2011-01-01

    This experimental, comparative, laboratory study evaluated the effectiveness of the sterilization of single-use laparoscopic instruments--SULIs (grasper, dissector, scissors, Veress needle and electrosurgical probe system), after contamination-challenge with bacterial spores and sheep blood, and compared the results of the sterilization tests with those of the equivalent reusable instruments. The cleaning methods used were; ultrasonic washer with pulsatile water jet and enzymatic detergent, manual cleaning, cleaning with pressurized water and rinsing. The SULIs were sterilized with ethylene oxide and the reusable instruments in an autoclave. Sterility tests showed 100% negative results for recovery of contaminate microorganisms in both groups. It was concluded that, regarding the sterilization, that it is possible to reprocess SULIs.

  12. Engineering study: Fast Flux Test Facility fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Beary, M.M.; Raab, G.J.; Reynolds, W.R. Jr.; Yoder, R.A.

    1974-01-07

    Several alternatives were studied for reprocessing FFTF fuels at Hanford. Alternative I would be to decontaminate and trim the fuel at T Plant and electrolytically dissolve the fuel at Purex. Alternative II would be to decontaminate and shear leach the fuels in a new facility near Purex. Alternative III would be to decontaminate and store fuel elements indefinitely at T Plant for subsequent offsite shipment. Alternative I, 8 to 10 M$ and 13 quarter-years; for Alternative II, 24 to 28 M$ and 20 quarter-years; for Alternative III, 3 to 4 M$ and 8 quarter-years. Unless there is considerable slippage in the FFTF shipping schedule, it would not be possible to build a new facility as described in Alternative II in time without building temporary storage facilities at T Plant, as described in Alternative III. (auth)

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

    Energy Technology Data Exchange (ETDEWEB)

    FRANCIS,A.J.

    2006-10-18

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

  14. Survey of Dynamic Simulation Programs for Nuclear Fuel Reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Troy J. Tranter; Daryl R. Haefner

    2008-06-01

    The absence of any industrial scale nuclear fuel reprocessing in the U.S. has precluded the necessary driver for developing the advanced simulation capability now prevalent in so many other industries. Modeling programs to simulate the dynamic behavior of nuclear fuel separations and processing were originally developed to support the US government’s mission of weapons production and defense fuel recovery. Consequently there has been little effort is the US devoted towards improving this specific process simulation capability during the last two or three decades. More recent work has been focused on elucidating chemical thermodynamics and developing better models of predicting equilibrium in actinide solvent extraction systems. These equilibrium models have been used to augment flowsheet development and testing primarily at laboratory scales. The development of more robust and complete process models has not kept pace with the vast improvements in computational power and user interface and is significantly behind simulation capability in other chemical processing and separation fields.

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

    Directory of Open Access Journals (Sweden)

    Carolina Marín

    2016-12-01

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

  16. Transuranic storage and assay facility interim safety basis

    Energy Technology Data Exchange (ETDEWEB)

    Porten, D.R., Fluor Daniel Hanford

    1997-02-12

    The Transuranic Waste Storage and Assay Facility (TRUSAF) Interim Safety Basis document provides the authorization basis for the interim operation and restriction on interim operations for the TRUSAF. The TRUSAF ISB demonstrates that the TRUSAF can be operated safely, protecting the workers, the public, and the environment. The previous safety analysis document TRUSAF Hazards Identification and Evaluation (WHC 1987) is superseded by this document.

  17. Analysis of nuclear proliferation resistance reprocessing and recycling technologies

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-05-01

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

  18. EMCS Retrofit Analysis - Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Diamond, R.C.; Salsbury, T.I.; Bell, G.C.; Huang, Y.J.; Sezgen, A.O.; Mazzucchi, R.; Romberger, J.

    1999-03-01

    This report presents the interim results of analyses carried out in the Phillip Burton Federal Building in San Francisco from 1996 to 1998. The building is the site of a major demonstration of the BACnet communication protocol. The energy management and control systems (EMCS) in the building were retrofitted with BACnet compatible controllers in order to integrate certain existing systems on one common network. In this respect, the project has been a success. Interoperability of control equipment from different manufacturers has been demonstrated in a real world environment. Besides demonstrating interoperability, the retrofits carried out in the building were also intended to enhance control strategies and capabilities, and to produce energy savings. This report presents analyses of the energy usage of HVAC systems in the building, control performance, and the reaction of the building operators. The report does not present an evaluation of the performance capabilities of the BACnet protocol. A monitoring system was installed in the building that parallels many of the EMCS sensors and data were archived over a three-year period. The authors defined pre-retrofit and post-retrofit periods and analyzed the corresponding data to establish the changes in building performance resulting from the retrofit activities. The authors also used whole-building energy simulation (DOE-2) as a tool for evaluating the effect of the retrofit changes. The results of the simulation were compared with the monitored data. Changes in operator behavior were assessed qualitatively with questionnaires. The report summarizes the findings of the analyses and makes several recommendations as to how to achieve better performance. They maintain that the full potential of the EMCS and associated systems is not being realized. The reasons for this are discussed along with possible ways of addressing this problem. They also describe a number of new technologies that could benefit systems of the type

  19. CMM Interim Check Design of Experiments (U)

    Energy Technology Data Exchange (ETDEWEB)

    Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-07-29

    Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length and include a weekly interim check to reduce risk. The CMM interim check makes use of Renishaw’s Machine Checking Gauge which is an off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. As verification on the interim check process a design of experiments investigation was proposed to test a couple of key factors (location and inspector). The results from the two-factor factorial experiment proved that location influenced results more than the inspector or interaction.

  20. Design review report FFTF interim storage cask

    Energy Technology Data Exchange (ETDEWEB)

    Scott, P.L.

    1995-01-03

    Final Design Review Report for the FFTF Interim Storage Cask. The Interim Storage Cask (ISC) will be used for long term above ground dry storage of FFTF irradiated fuel in Core Component Containers (CCC)s. The CCC has been designed and will house assemblies that have been sodium washed in the IEM Cell. The Solid Waste Cask (SWC) will transfer a full CCC from the IEM Cell to the RSB Cask Loading Station where the ISC will be located to receive it. Once the loaded ISC has been sealed at the RSB Cask Loading Station, it will be transferred by facility crane to the DSWC Transporter. After the ISC has been transferred to the Interim Storage Area (ISA), which is yet to be designed, a mobile crane will be used to place the ISC in its final storage location.

  1. When Should We Change Drill Bits? A Mechanical Comparison of New, Reprocessed, and Damaged Bits.

    Science.gov (United States)

    Myers, Richard; Kim, Hyunchul; Hsieh, Adam H; OʼToole, Robert V; Sciadini, Marcus F

    2017-05-01

    We assessed how reprocessed and damaged drill bits perform relative-to-new drill bits in terms of drilling force required, heat generated at near and far cortices, and number of usable passes. Nine pairs of nonosteoporotic human cadaveric femora were tested using 3 types of 3.2-mm drill bits (new, reprocessed, and damaged) in 3 investigations (force, temperature, and multiple usable passes). Operating room conditions were simulated. Force and temperature data were collected for each type. The multiple pass investigation measured only force. New and reprocessed drill bits performed similarly regarding force required and heat generated; both outperformed damaged bits. New and reprocessed bits had a similar number of usable passes in ideal conditions. Damaged bits required nearly 2.6 times as much force to maintain drilling rate. Reprocessed drill bits seem to be a viable alternative to new drill bits for fracture treatment surgery in terms of force required, heat generated, and number of usable passes. Drill bits that are damaged intraoperatively should be replaced. In ideal conditions, new and reprocessed drill bits can be used for multiple consecutive cases. Reprocessed drill bits may be as effective as new drill bits, representing potential cost savings for institutions. Both types can be considered for reuse.

  2. The R&D of HTGR high temperature helium sampling loop: From HTR-10 to HTR-PM

    Energy Technology Data Exchange (ETDEWEB)

    Fang, Chao, E-mail: fangchao@tsinghua.edu.cn [Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084 (China); Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing 100084 (China); The Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Beijing 100084 (China); Bao, Xuyin; Yang, Chen; Yang, Yanran; Cao, Jianzhu [Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084 (China); Collaborative Innovation Center of Advanced Nuclear Energy Technology, Tsinghua University, Beijing 100084 (China); The Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Beijing 100084 (China)

    2016-09-15

    A High Temperature Helium Sampling Loop (HTHSL) for studying the transportation (deposition) behavior and total amount of solid fission products in high-temperature helium coming from the steam generator (SG) in the 10 MW High Temperature Gas-cooled Test Reactor (HTR-10) and High Temperature Reactor-Pebble bed Modules (HTR-PM) are researched and designed, respectively. Through the optimal design and simulation based on thermohydraulics analysis, the three-sleeve structure of deposition sampling device (DSD) could realize full-length temperature control evenly so that it could be used to study fission products in the primary circuit of HTR-10. On the other hand, an improved DSD is also designed for HTR-PM based on corresponding simulations, which could be used to sample the important nuclei in the high temperature helium from SG. These schemes offer two different methods to obtain the original source term in the high temperature helium, which will provide deeper understanding for the analysis of source terms of HTGR.

  3. A hybrid HTGR system producing electricity, hydrogen and such other products as water demanded in the Middle East

    Energy Technology Data Exchange (ETDEWEB)

    Yan, X., E-mail: yan.xing@jaea.go.jp; Noguchi, H.; Sato, H.; Tachibana, Y.; Kunitomi, K.; Hino, R.

    2014-05-01

    Alternative energy products are being considered by the Middle East countries for both consumption and export. Electricity, water, and hydrogen produced not from oil and gas are amongst those desirable. A hybrid nuclear production system, GTHTR300C, under development in JAEA can achieve this regional strategic goal. The system is based on a 600 MWt HTGR and equipped to cogenerate electricity by gas turbine and seawater desalination by using only the nuclear plant waste heat. Hydrogen is produced via a thermochemical water-splitting process driven by the reactor's 950 °C heat. Additionally process steam may be produced for industrial uses. An example is shown of manufacturing soda ash, an internationally traded commodity, from using the steam produced and the brine discharged from desalination. The nuclear reactor satisfies nearly all energy requirements for the hybrid generations without emitting CO{sub 2}. The passive safety of the reactor as described in the paper permits proximity of siting the reactor with the production facilities to enhance energy transmission. Production flowsheet of the GTHTR300C is given for up to 300 MWe electricity, 58 t/day hydrogen, 56,000 m{sup 3}/day potable water, 3500 t/day steam, and 1000 t/day soda ash. The production thermal efficiency reaches 88%.

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

    Energy Technology Data Exchange (ETDEWEB)

    None

    1976-06-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Simon, Nicole; Gastaldi, Olivier; Penit, Thomas; Cohin, Olivier; Campion, Pierre-Yves [DEN/CADDTN/STPA/LPC-CEA Cadarache, 13108 Saint Paul lez Durance (France)

    2008-07-01

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

  6. Van interim-management naar tijdelijk leiderschap

    NARCIS (Netherlands)

    Schaveling, J.

    2008-01-01

    Het fenomeen interim-management, maar ook het tijdelijk inzetten van interne mensen op managementposities, neemt de laatste tijd een hoge vlucht. Welke voorwaarden zijn nodig om dit tot een succes te laten worden? En wat is de stand van zaken ervan in de praktijk?

  7. Interim Report - Grant AFOSR-85-0065.

    Science.gov (United States)

    1985-06-30

    Option 065 Drafting Plotter 1 7475A 6 Pen Graphics Plotter Vendor: Imagen Corporation $ 11,266 1 Model 8/300 Laser Printer System, 512Kbytes memory 1... Imagen 8/300 Laser Printer 3 Interim Report Grant No. AFOSR-85-0065 was equivalent to the Versatec plotter for small plots and better for text output

  8. 24 CFR 7.44 - Interim relief.

    Science.gov (United States)

    2010-04-01

    ... will result in the dismissal of the Department's appeal. (e) The Department may, by notice to the... conditional restoration of the employee to duty status in the position specified in the decision, pending the outcome of the Department appeal. The employee may decline the offer of interim relief. (b) Service under...

  9. Interim Guidelines Growing Longleaf Seedlings in Containers

    Science.gov (United States)

    James P. Barnett; Mark J. Hainds; George A. Hernandez

    2002-01-01

    These interim guidelines are designed for producers and users of longleaf pine container stock. They are not meant to exclude any container product. The seedling specifications listed in the preferred category are attainable by the grower and will result in excellent field sur vival and early height growth.

  10. LANDFILL BIOREACTOR PERFORMANCE, SECOND INTERIM REPORT

    Science.gov (United States)

    A bioreactor landfill is a landfill that is operated in a manner that is expected to increase the rate and extent of waste decomposition, gas generation, and settlement compared to a traditional landfill. This Second Interim Report was prepared to provide an interpretation of fie...

  11. A Non-Traditional Interim Project.

    Science.gov (United States)

    Brown, Diane; Ward, Dorothy

    1980-01-01

    Describes a project initiated by the Foreign Language Department of Birmingham-Southern College for their Interim term and discusses an interdisciplinary course focusing on Medieval Europe. The course included presentations on German and French language and literature, as well as lectures on the arts, philosophy, and family life of the period.…

  12. Highly Active Liquid Waste concentration using the formaldehyde de-nitration process in the French reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

    Bretault, P.; Schneider, J. [AREVA-SGN, 1 Rue des Herons, Montigny le Bretonneux Cedex, 78182 (France); Huel, C.; Bosse, E. [AREVA-NC (France); Juvenelle, A.; Masson, M. [Commissariat a l' Energie Atomique - CEA (France)

    2009-06-15

    The Highly Active Liquid Waste generated by a spent nuclear fuel reprocessing plant is mainly composed of the raffinate from the first stage of the uranium/plutonium extraction process. This stream contains the vast majority of the fission products and minor actinides which are finally vitrified. The HALW stream is concentrated in order to limit the volume of the interim storage between the extraction process and the vitrification and also to reduce the required evaporation duty of the vitrification process itself. The potential difficulties of this concentration step are the corrosion risk associated to the handling of acidic solution and the possible troubles linked to the formation and precipitation of solid particles. In addition, a highly robust design is a key demand for such high active processes since absolutely no direct maintenance operation will ever be possible after the active commissioning. In La Hague plant operated by AREVA NC the HALW are concentrated using the formaldehyde de-nitration process that was first used at the end of the 50's in the former Marcoule plant. The principle of the process is as follows: - The HALW are concentrated in a kettle type evaporator operated at constant level in a semi-continuous mode, - All along the evaporation sequence, the nitric acid contained in the waste is reduced into nitrous fumes by reaction with formaldehyde. This maintains the free acidity of the concentrate close to 2.5 N, a sufficiently low value to reduce the corrosion risk while minimizing the precipitation of solid compounds, - The nitrous fumes are recombined into nitric which is further purified, concentrated and eventually recycled into the highly active part of the main process. This paper describes with more details the chemical reactions involved, the equipment used and the operating mode of the de-nitration process. It also gives an overview of the 50-years-long operating experience in terms of equipment lifetime, process efficiency and

  13. Coastal Bend Texas Benthic Habitat Mapping Reprocessed DOQQ Aerial Imagery (NODC Accession 0086051)

    Data.gov (United States)

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

  14. Aplikasi eye moving desensitization dan reprocessing dalam konseling post-traumatic stress disorder

    OpenAIRE

    Hengki Satrianta

    2017-01-01

    Akhir-akhir ini banyak peristiwa yang berpotensi memunculkan efek traumatik yang jika tidak ditangani akan menimbulkan gangguan stres pascatrauma. Olehnya itu, dibutuhkan upaya-upaya untu menangani masalah ini. Salah satu upaya yang dimaksud adalah penggunaan eye moving desensitization and reprocessing. Artikel ini ditulis dengan fokus pada penanganan gangguan stres pascatrauma melalui eye moving desensitization and reprocessing. Tujuan penulisan artikel ini adalah untuk mengetahui gambaran u...

  15. Reprocessability of molybdenum and magnesia based inert matrix fuels

    Directory of Open Access Journals (Sweden)

    Ebert Elena L.

    2015-12-01

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

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

    Directory of Open Access Journals (Sweden)

    Afsaneh Zarghi

    2013-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-07-01

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

  18. High-quality endoscope reprocessing decreases endoscope contamination.

    Science.gov (United States)

    Decristoforo, Petra; Kaltseis, Josef; Fritz, Andreas; Edlinger, Michael; Posch, Wilfried; Wilflingseder, Doris; Lass-Flörl, Cornelia; Orth-Höller, Dorothea

    2018-02-02

    Several outbreaks of severe infections due to contamination of gastrointestinal (GI) endoscopes, mainly duodenoscopes have been described previously. The rate of microbial endoscope contamination is varying dramatically in literature. Thus, the aim of this multicentre prospective study was to evaluate the hygiene quality of endoscopes and automated endoscope reprocessors (AERs) in Tyrol/Austria. In 2015 and 2016, a total of 463 GI endoscopes and 105 AERs from 29 endoscopy centres were analysed by a routine (R) and a combined routine and advanced (CRA) sampling procedure and investigated for microbial contamination by culture- and molecular-based analyses. The contamination rate of GI endoscopes was 1.3-4.6% according to national guideline, suggesting that 1.3-4.6 patients out of 100 could have had contacts with hygiene relevant microorganisms through an endoscopic intervention. Comparison of R and CRA sampling showed 1.8% of R versus 4.6% of CRA failing the acceptance criteria in phase I and 1.3% of R versus 3.0% of CRA samples in phase II. The most commonly identified indicator organism was Pseudomonas spp., mainly P. oleovorans. None of the tested viruses were detected in 40 samples. While AERs in phase I failed (n=9, 17.6%) mainly due to technical faults, phase II revealed lapses (n=6, 11.5%) only on account to microbial contamination of the last rinsing water, mainly with Pseudomonas spp. In the present study the contamination rate of endoscopes was low compared to results from other European countries, possibly due to high quality of endoscope reprocessing, drying and storage. Copyright © 2018 European Society of Clinical Microbiology and Infectious Diseases. Published by Elsevier Ltd. All rights reserved.

  19. Analytical Chemistry Department annual report, 1975

    Energy Technology Data Exchange (ETDEWEB)

    Mosen, A.W. (ed.)

    1976-10-26

    The analytical methods developed or adopted for use in support of radiochemistry and gamma ray spectroscopy, HTGR fuel reprocessing, HTGR fuel development, TRIGA fuel fabrication, and miscellaneous projects are reported. (JSR)

  20. Changes to GPM Core Data Products as a Result of the V05 Reprocessing

    Science.gov (United States)

    Stocker, Erich Franz; Chou, Joyce; Ji, Yimin; Kelley, Owen; Kwiatkowski, John; Stout, John; Woltz, Lawrence

    2017-04-01

    Ongoing reprocessing is key to the improvement of GPM mission data products and is part of the mission requirements. The Global Precipitation Measurement (GPM) mission will be undertaking its second major reprocessing of mission data in Spring of 2017. The initial processing (V03) started in February 2014 with the launch of the GPM core satellite. This first processing required the use of pre-launch measurement and databases constructed from non-GPM measurements. In Spring of 2016, the first major reprocessed (V04) mission data suite was released. The calibrations, changes and improvements during this reprocessing cycle were based on on-orbit measurements and databases built using actual GPM measurements. The past year has provided the opportunity to study the impact of these V04 changes and determine what calibration changes were still necessary and how the retrievals were to be improved based on analysis of the new reprocessed datasets. The second major reprocessing (V05) is the result of additional analysis of the V04 calibrations and retrievals. The V04 step was vital as it ensured that data products analyzed for improvements were those that were actually based on GPM observations. This paper will present an early assessment of anticipated V05 changes. The paper will provide a summary of the following categories of V05 data products: 1) GPM Microwave Imager (GMI) level 1 calibration 2) Ku/Ka radar level 1 calibration 3) GPROF GMI and GPROF constellation [??] precipitation retrievals and format changes 4) High level radar Level 2 precipitation retrieval changes 5) Combined GMI+Radar product modifications 6) Level 3 gridded product changes The paper will also provide comparisons between V04 and V05 products. Additionally it will provide a high level discussion of the plans for the V05 reprocessing of the merged radiometer gridded products (IMERG) The presentation an effective summary for potential users of what they can expect from the GPM V05 products especially

  1. STAT, GAPS, STRAIN, DRWDIM: a system of computer codes for analyzing HTGR fuel test element metrology data. User's manual

    Energy Technology Data Exchange (ETDEWEB)

    Saurwein, J.J.

    1977-08-01

    A system of computer codes has been developed to statistically reduce Peach Bottom fuel test element metrology data and to compare the material strains and fuel rod-fuel hole gaps computed from these data with HTGR design code predictions. The codes included in this system are STAT, STRAIN, GAPS, and DRWDIM. STAT statistically evaluates test element metrology data yielding fuel rod, fuel body, and sleeve irradiation-induced strains; fuel rod anisotropy; and additional data characterizing each analyzed fuel element. STRAIN compares test element fuel rod and fuel body irradiation-induced strains computed from metrology data with the corresponding design code predictions. GAPS compares test element fuel rod, fuel hole heat transfer gaps computed from metrology data with the corresponding design code predictions. DRWDIM plots the measured and predicted gaps and strains. Although specifically developed to expedite the analysis of Peach Bottom fuel test elements, this system can be applied, without extensive modification, to the analysis of Fort St. Vrain or other HTGR-type fuel test elements.

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

    Lifescience Database Archive (English)

    Full Text Available List Contact us FANTOM5 (reprocessed)HeliscopeCAGE sequencing, Delve mapping and CAGE TSS aggregation Data d...etail Data name (reprocessed)HeliscopeCAGE sequencing, Delve mapping and CAGE TSS aggregation DOI 10.18908/l...m5_rp_exp_details#en Data acquisition method HeliScopeCAGE ( http://fantom.gsc.riken.jp/protocols/heliscop...icy | Contact Us (reprocessed)HeliscopeCAGE sequencing, Delve mapping and CAGE TSS aggregation - FANTOM5 | LSDB Archive ...

  3. Consolidated fuel-reprocessing program. Quarterly progress report for the period ending November 30, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Carney, H. C.; Pierce, V. H.; Rickman, W. S.; Strand, J. B.; Holder, N. D.; Brimhall, W. L.; Fields, D. E.; Callahan, S. F.; Higuchi, K.; Benedict, G. E.; Abraham, L.; Hirsch, P. M.; Engler, D. R.; Stock, W. C.; Wilbourn, R. G.; Dunlap, S. A.; Hostbjor, G. J.; Olquin, L. J.; Swieda, D. E.; Field, R. E.; Newman, P. W.; Rode, J. S.; Brown, L. C.; Haldy, B. B.

    1980-12-01

    Large-scale crushing and burning tests of fuel received from the Federal Republic of Germany (FRG) have identified differences in processing characteristics. The NO/sub x/ converter experimental tests continued this quarter in the GA off-gas system. The dependence of nitric oxide conversion efficiency on ammonia and oxygen concentrations has been determined. An optimum ratio of ammonia to nitric oxide was identified in terms of the conversion factor for nitrix oxide. No residual ammonia was detected downstream of the NO/sub x/ converter. Design of the radon source subsystem and fabrication of the radon source assembly and shielded radon source containment were completed. Second-thorium-cycle column tests confirm the feasibility of producing thorium product having acceptably low uranium contents. Two axial mixing tests were completed on the thorium extraction section. The Mott inertial filter tests continued. The dissolution rate of HTGR fuel spheres is speeded by a factor of three by using an airlift acid recirculator to improve ThO/sub 2/-dissolvent contact. The FRG HTGR fuel spheres dissolve a factor of three more slowly than the sol-gel derived ThO/sub 2/ spheres. The task group completed a thorium transfer kinetics comparison of alternative solvents. Hydrolysis studies were started on alternative solvents.

  4. First results of the 2nd IGS Data Reprocessing Campaign at GFZ

    Science.gov (United States)

    Deng, Zhiguo; Uhlemann, Maik; Nischan, Thomas; Gendt, Gerd

    2013-04-01

    The Analysis Centers (ACs) of the International GNSS Service (IGS) are preparing for the 2nd eprocessing campaign of the full history of GPS data collected by the IGS global network since 1994 in a fully consistent way using the latest models and methodology. The first IGS reprocessing was successful finished in 2010, the homogeneous products contributed to ITRF2008. The German Research Centre for Geosciences (GFZ) will contribute as to the first also to the 2nd IGS Reprocessing Campaign. Some improvements were implemented into the latest GFZ software version EPOS.P8 : reference frame IGb08 based on ITRF2008, antenna calibration igs08.atx, geopotential model (IERS2010), higher-order ionospheric effects, new a priori meteorological model (GPT2) and VMF mapping function etc. GPS data of the globally distributed IGS tracking network of 281 stations for the time span from 1994 until 2012 were reprocessed. Since the Repro2 combination solutions are not available, this poster shows some selected results from our 2nd IGS Reprocessing efforts. The data from 1994 until 2012 were twice reprocessed to study the effect of the improvements and models . In addition the internal consistency is checked, e.g. orbit overlap, station residuals.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-01

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

  6. 47 CFR 51.715 - Interim transport and termination pricing.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 3 2010-10-01 2010-10-01 false Interim transport and termination pricing. 51.715 Section 51.715 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER... Telecommunications Traffic § 51.715 Interim transport and termination pricing. (a) Upon request from a...

  7. 50 CFR 660.720 - Interim protection for sea turtles.

    Science.gov (United States)

    2010-10-01

    ... 50 Wildlife and Fisheries 9 2010-10-01 2010-10-01 false Interim protection for sea turtles. 660... Migratory Fisheries § 660.720 Interim protection for sea turtles. (a) Until the effective date of §§ 660.707... harvest of swordfish (Xiphias gladius) using longline gear deployed on the high seas of the Pacific Ocean...

  8. Decision on performing interim analysis for comparative clinical trials

    Directory of Open Access Journals (Sweden)

    Kyongsun Pak

    2017-09-01

    Full Text Available In randomized-controlled trials, interim analyses are often planned for possible early trial termination to claim superiority or futility of a new therapy. While unblinding is necessary to conduct the formal interim analysis in blinded studies, blinded data also have information about the potential treatment difference between the groups. We developed a blinded data monitoring tool that enables investigators to predict whether they observe such an unblinded interim analysis results that supports early termination of the trial. Investigators may skip some of the planned interim analyses if an early termination is unlikely. We specifically focused on blinded, randomized-controlled studies to compare binary endpoints of a new treatment with a control. Assuming one interim analysis is planned for early termination for superiority or futility, we conducted extensive simulation studies to assess the impact of the implementation of our tool on the size, power, expected number of interim analyses, and bias in the treatment effect. The numerical study showed the proposed monitoring tool does not affect size or power, but dramatically reduces the expected number of interim analyses when the effect of the treatment difference is small. The tool serves as a useful reference when interpreting the summary of the blinded data throughout the course of the trial, without losing integrity of the study. This tool could potentially save the study resources and budget by avoiding unnecessary interim analyses.

  9. General certification procedure of enterprises and interim job enterprises

    CERN Document Server

    Int. At. Energy Agency, Wien

    2002-01-01

    This procedure defines the certification global process of enterprises employing workers of A or B category for nuclear facilities and interim job enterprises proposing workers of A or B category for nuclear facilities. This certification proves the enterprises ability to satisfy the specification ''E'' of the CEFRI and the interim job enterprises to satisfy the specification ''I'' of the CEFRI. (A.L.B.)

  10. 40 CFR 80.141 - Interim detergent gasoline program.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Interim detergent gasoline program. 80... (CONTINUED) REGULATION OF FUELS AND FUEL ADDITIVES Detergent Gasoline § 80.141 Interim detergent gasoline... apply to: (i) All gasoline sold or transferred to a party who sells or transfers gasoline to the...

  11. 46 CFR 308.203 - Amount insured under interim binder.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 8 2010-10-01 2010-10-01 false Amount insured under interim binder. 308.203 Section 308.203 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE War Risk Protection and Indemnity Insurance § 308.203 Amount insured under interim binder. The...

  12. 46 CFR 308.303 - Amounts insured under interim binder.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 8 2010-10-01 2010-10-01 false Amounts insured under interim binder. 308.303 Section... INSURANCE Second Seamen's War Risk Insurance § 308.303 Amounts insured under interim binder. The amounts... of the date of a casualty involving the subject vessel. Upon the attachment of this binder, the...

  13. 46 CFR 308.103 - Insured amounts under interim binder.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 8 2010-10-01 2010-10-01 false Insured amounts under interim binder. 308.103 Section 308.103 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE War Risk Hull and Disbursements Insurance § 308.103 Insured amounts under interim binder. (a...

  14. Monitoring of endoscope reprocessing with an adenosine triphosphate (ATP bioluminescence method

    Directory of Open Access Journals (Sweden)

    Parohl, Nina

    2017-03-01

    Full Text Available Background: The arising challenges over endoscope reprocessing quality proposes to look for possibilities to measure and control the process of endoscope reprocessing.Aim: The goal of this study was to evaluate the feasibility of monitoring endoscope reprocessing with an adenosine triphosphate (ATP based bioluminescence system.Methods: 60 samples of eight gastroscopes have been assessed from routine clinical use in a major university hospital in Germany. Endoscopes have been assessed with an ATP system and microbial cultures at different timepoints during the reprocessing. Findings: After the bedside flush the mean ATP level in relative light units (RLU was 19,437 RLU, after the manual cleaning 667 RLU and after the automated endoscope reprocessor (AER 227 RLU. After the manual cleaning the mean total viable count (TVC per endoscope was 15.3 CFU/10 ml, and after the AER 5.7 CFU/10 ml. Our results show that there are reprocessing cycles which are not able to clean a patient used endoscope.Conclusion: Our data suggest that monitoring of flexible endoscope with ATP can identify a number of different influence factors, like the endoscope condition and the endoscopic procedure, or especially the quality of the bedside flush and manual cleaning before the AER. More process control is one option to identify and improve influence factors to finally increase the overall reprocessing quality, best of all by different methods. ATP measurement seems to be a valid technique that allows an immediate repeat of the manual cleaning if the ATP results after manual cleaning exceed the established cutoff of 200 RLU.

  15. Radon measurements in schools: an interim report

    Energy Technology Data Exchange (ETDEWEB)

    1989-03-01

    The report provides school officials, groups such as Parent-Teacher Associations, and other interested person with interim information on how to measure radon in schools and what to do if elevated levels are found. The first sections of the document contain facts about radon and the health risks associated with radon exposure. The next sections summarize what is known about radon in schools and provide guidance for conducting radon measurements. The last sections describe how to interpret the measurement results and suggest techniques that can be used to reduce radon concentrations if elevated levels are found.

  16. National NIF Diagnostic Program Interim Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    Warner, B

    2002-04-25

    The National Ignition Facility (NIF) has the mission of supporting Stockpile Stewardship and Basic Science research in high-energy-density plasmas. To execute those missions, the facility must provide diagnostic instrumentation capable of observing and resolving in time events and radiation emissions characteristic of the plasmas of interest. The diagnostic instrumentation must conform to high standards of operability and reliability within the NIF environment. These exacting standards, together with the facility mission of supporting a diverse user base, has led to the need for a central organization charged with delivering diagnostic capability to the NIF. The National NIF Diagnostics Program (NNDP) has been set up under the aegis of the NIF Director to provide that organization authority and accountability to the wide user community for NIF. The funds necessary to perform the work of developing diagnostics for NIF will be allocated from the National NIF Diagnostics Program to the participating laboratories and organizations. The participating laboratories and organizations will design, build, and commission the diagnostics for NIF. Restricted availability of funding has had an adverse impact, unforeseen at the time of the original decision to projectize NIF Core Diagnostics Systems and Cryogenic Target Handing Systems, on the planning and initiation of these efforts. The purpose of this document is to provide an interim project management plan describing the organizational structure and management processes currently in place for NIF Core Diagnostics Systems. Preparation of a Program Execution Plan for NIF Core Diagnostics Systems has been initiated and a current draft is provided as Attachment 1 to this document. The National NIF Diagnostics Program Interim Management Plan provides a summary of primary design criteria and functional requirements, current organizational structure, tracking and reporting procedures, and current planning estimates of project scope

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

    Energy Technology Data Exchange (ETDEWEB)

    Durant, W.S.; Perkins, W.C.; Lee, R.; Stoddard, D.H.

    1982-05-20

    The Safety Technology Group is developing methodology that can be used to assess the risk of operating a plant to reprocess spent nuclear fuel. As an early step in the methodology, a preliminary hazards analysis identifies safety-related incidents. In the absence of appropriate safety features, these incidents could lead to significant consequences and risk to onsite personnel or to the public. This report is a compilation of potential safety-related incidents that have been identified in studies at SRL and in safety analyses of various commercially designed reprocessing plants. It is an expanded revision of the version originally published as DP-1558, Published December 1980.

  18. 50 CFR 259.30 - Application for Interim Capital Construction Fund Agreement (“Interim CCF Agreement”).

    Science.gov (United States)

    2010-10-01

    ...) Date of construction, acquisition, or reconstruction, (vii) Fishery of operation (which in this section... 50 Wildlife and Fisheries 7 2010-10-01 2010-10-01 false Application for Interim Capital Construction Fund Agreement (âInterim CCF Agreementâ). 259.30 Section 259.30 Wildlife and Fisheries NATIONAL...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  20. Conclusions from V and V studies on the German codes PANAMA and FRESCO for HTGR fuel performance and fission product release

    Energy Technology Data Exchange (ETDEWEB)

    Verfondern, K., E-mail: k.verfondern@fz-juelich.de [Research Center Jülich, 52425, Jülich (Germany); Cao, J.; Liu, T. [Tsinghua University, Beijing (China); Allelein, H.-J. [Research Center Jülich, 52425, Jülich (Germany); RWTH Aachen, 52072, Aachen (Germany)

    2014-05-01

    In modern HTGR reactors, the fuel element represents the principal barrier against release of the fission products generated during reactor operation. Both the acquired experience from HTGR operation and experimental data from accident simulation testing of the fuel have always been accompanied by intensive efforts of mathematical fuel performance modeling taking into consideration as far as possible the physical phenomena that may occur. The computer codes FRESCO and PANAMA both developed at the Research Center Jülich in Germany in the early 1980s have become essential tools to predict the fission product release from spherical fuel elements and the TRISO fuel performance, respectively, under given normal or accidental conditions. These two codes are also presently being used for a conservative estimation of the source term, i.e., quantity and duration of radionuclide release, for the Chinese demonstration project HTR-PM. A description of the comprehensive efforts in the past on code verification and validation (V and V) including the most recent studies of code-to-code benchmarking studies and code-to-experiment comparisons as part of the IAEA directed CRP-6 project will be given. The conclusions drawn from those activities will be given with regard to the codes’ ability to allow for a conservative quantification of the source term as part of safety and risk analyses for pebble-bed HTGRs. Recommendations for further model improvement have been taken into account in the new code development, STACY, combining the PANAMA and FRESCO model approach and other features, as a module of the HTR Code Package (HCP)

  1. Reprocessing the Southern Hemisphere ADditional OZonesondes (SHADOZ) Database for Long-Term Trend Analyses

    Science.gov (United States)

    Witte, J. C.; Thompson, A. M.; Coetzee, G.; Fujiwara, M.; Johnson, B. J.; Sterling, C. W.; Cullis, P.; Ashburn, C. E.; Jordan, A. F.

    2015-12-01

    SHADOZ is a large archive of tropical balloon-bone ozonesonde data at NASA/Goddard Space Flight Center with data from 14 tropical and subtropical stations provided by collaborators in Europe, Asia, Latin America and Africa . The SHADOZ time series began in 1998, using electrochemical concentration cell (ECC) ozonesondes. Like many long-term sounding stations, SHADOZ is characterized by variations in operating procedures, launch protocols, and data processing such that biases within a data record and among sites appear. In addition, over time, the radiosonde and ozonesonde instruments and data processing protocols have changed, adding to the measurement uncertainties at individual stations and limiting the reliability of ozone profile trends and continuous satellite validation. Currently, the ozonesonde community is engaged in reprocessing ECC data, with an emphasis on homogenization of the records to compensate for the variations in instrumentation and technique. The goals are to improve the information and integrity of each measurement record and to support calculation of more reliable trends. We illustrate the reprocessing activity of SHADOZ with selected stations. We will (1) show reprocessing steps based on the recent WMO report that provides post-processing guidelines for ozonesondes; (2) characterize uncertainties in various parts of the ECC conditioning process; and (3) compare original and reprocessed data to co-located ground and satellite measurements of column ozone.

  2. Development of robot arm for automatic analytical operation in nuclear reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Shibayama, S.; Ohnishi, K. [Mitsubishi Heavy Industries Ltd., Kobe (Japan); Hayashibara, H. [Mitsubishi Heavy Industries Ltd., Takasago Research and Development Center, Takasago-shi, Hyogo-Ken (Japan)

    1998-07-01

    The analytical work in the nuclear reprocessing plant is very important role to operate the plant in normal and safety. The new compact robot arm has been developed for the automatic analytical system installed in the analytical box with the heavy shielding and confirmed the availability for this system by results of several validation tests. (author)

  3. Hydrometallurgical reprocessing of BREST-OD-300 mixed uranium-plutonium nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Shadrin, A.Y.; Dvoeglazov, K.N.; Kascheyev, V.A.; Vidanov, V.L. [Institution Innovation and Technology Center by ' PRORYV' Project, 2/8 Malaya Krasnoselskaya, 107140 Moscow (Russian Federation); Volk, V.I.; Veselo, S.N. [JSC A.A. Bochvar VNIINM, 5a Rogova, 123060 Moscow (Russian Federation); Zilberman, B.Y.; Ryabkov, D.V. [JSC ' VG Khlopin Radium Institute' , 28 2-oy Michurinskiy proezd, 194021, St. Petersburg (Russian Federation)

    2016-07-01

    The duration of external fuel cycle of BREST-OD-300 reactor with mixed U-Pu nitride fuel (MNIT) including hydrometallurgical reprocessing should not exceed 3 years. An average burnup of the fuel should be 6% of heavy metal (HM) with the potential increase up to 10% HM. Therefore, the technology should provide the reprocessing of spent nuclear fuel (SNF) after less than 2 years cooling time and with fissile materials content of 10 - 15%. Pellets technology has been chosen for the MNIT fuel production. That means necessity to receive the recycled actinides oxides of high purification coefficient (∼ 10{sup 6}). Currently on a laboratory scale, the following process stages have been tested on the real products: actinide oxides production and rare-earth and trans-plutonium elements separation. Moreover, on a pilot scale the process of high level radioactive waste and intermediate level radioactive waste concentration by evaporation has been tested, as well as the Am-Cm separation. In 2015, the design of the MNIT SNF reprocessing facility has been started, placed at the JSC Siberian Chemical Plant site as a part of the pilot demonstration power complex with BREST-OD-300 reactor. MNIT SNF reprocessing plant should be put in operation after 2020. (authors)

  4. Component failure-rate data with potential applicability to a nuclear fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

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

    1982-07-01

    Approximately 1223 pieces of component failure-rate data, under 136 subject categories, have been compiled from published literature and computer searches of a number of data bases. Component selections were based on potential applicability to facilities for reprocessing spent nuclear fuels. The data will be useful in quantifying fault trees for probabilistic safety analyses and risk assessments.

  5. Mechanical, Thermomechanical and Reprocessing Behavior of Green Composites from Biodegradable Polymer and Wood Flour.

    Science.gov (United States)

    Morreale, Marco; Liga, Antonio; Mistretta, Maria Chiara; Ascione, Laura; Mantia, Francesco Paolo La

    2015-11-11

    The rising concerns in terms of environmental protection and the search for more versatile polymer-based materials have led to an increasing interest in the use of polymer composites filled with natural organic fillers (biodegradable and/or coming from renewable resources) as a replacement for traditional mineral inorganic fillers. At the same time, the recycling of polymers is still of fundamental importance in order to optimize the utilization of available resources, reducing the environmental impact related to the life cycle of polymer-based items. Green composites from biopolymer matrix and wood flour were prepared and the investigation focused on several issues, such as the effect of reprocessing on the matrix properties, wood flour loading effects on virgin and reprocessed biopolymer, and wood flour effects on material reprocessability. Tensile, Dynamic-mechanical thermal (DMTA), differential scanning calorimetry (DSC) and creep tests were performed, pointing out that wood flour leads to an improvement of rigidity and creep resistance in comparison to the pristine polymer, without compromising other properties such as the tensile strength. The biopolymer also showed a good resistance to multiple reprocessing; the latter even allowed for improving some properties of the obtained green composites.

  6. A study of visual and blood contamination on reprocessed endodontic files from general dental practice.

    Science.gov (United States)

    Letters, S; Smith, A J; McHugh, S; Bagg, J

    2005-10-22

    This study examined methods used for reprocessing endodontic instruments in general dental practice and determined the degree of residual visual contamination and blood contamination on 250 reprocessed files collected from 25 general dental practices. A questionnaire was administered to 25 general dental practitioners to obtain information on the re-processing of used endodontic files. Ten files which had been used and reprocessed were also collected from each practice. These were examined visually under a dissecting light microscope for residual contamination and then tested for blood deposits using the Kastle-Meyer test. Nineteen of the 25 practices used stainless steel hand files. No practitioners used endodontic files as single use devices. Ninety-two per cent of the practitioners discarded and replaced files when they were bent or damaged. Several decontamination methods were reported. The two combinations employed most frequently were manual cleaning and autoclaving or manual cleaning, followed by ultrasonic cleaning and autoclaving. Of the 250 files, 75% showed some degree of visual contamination and seven percent tested positive for residual blood. Blood contaminated files were significantly more heavily contaminated when examined visually. Large variations were found in residual contamination of files collected from practices using the same methods of decontamination. While all practitioners re-used endodontic files, the variations in decontamination methods reported indicate a lack of clarity on best practice. This study demonstrates that endodontic files are not reliably decontaminated by methods currently employed in dental practice.

  7. Reprocessing of spent nuclear fuels. Status and trends; Upparbetning av anvaent kaernbraensle. Laege och trender

    Energy Technology Data Exchange (ETDEWEB)

    Hultgren, Aa.

    1993-01-01

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

  8. A Review of Eye Movement Desensitization and Reprocessing (EMDR): Research Findings and Implications for Counsellors.

    Science.gov (United States)

    MacCluskie, Kathryn C.

    1998-01-01

    States that within the last six years a new therapeutic technique for the treatment of posttraumatic stress disorder, Eye Movement Desensitization and Reprocessing (EMDR), has emerged. Examines the strengths and weaknesses of published studies concerning EMDR, describes the nature of the debate about the efficacy of EMDR, and reviews implications…

  9. Eye Movement Desensitization and Reprocessing (EMDR) Treatment for Psychologically Traumatized Individuals.

    Science.gov (United States)

    Wilson, Sandra A.; And Others

    1995-01-01

    Studies the effects of 3 90-minute Eye Movement Desensitization and Reprocessing (EMDR) treatment sessions on traumatic memories of 80 participants. Participants receiving EMDR showed decreases in complaints and anxiety, and increases in positive cognition. Participants in the delayed-treatment condition showed no improvement in any measures in…

  10. Effects of reprocessing on chemical and morphological properties of guide wires used in angioplasty

    Directory of Open Access Journals (Sweden)

    Rogério Valentim Gelamo

    2013-09-01

    Full Text Available OBJECTIVE: To investigate the influence of the reprocessing technique of enzymatic bath with ultrasonic cleaning and ethylene oxide sterilization on the chemical properties and morphological structure of polymeric coatings of guide wire for regular guiding catheter. METHODS: These techniques simulated the routine of guide wire reprocessing in many hemodynamic services in Brazil and other countries. Samples from three different manufacturers were verified by scanning electron microscopy and X-ray photoelectron spectroscopy. RESULTS: A single or double sterilization of the catheters with ethylene oxide was not associated with morphological or chemical changes. However, scanning electron microscopy images showed that the washing method was associated with rough morphological changes, including superficial holes and bubbles, in addition to chemical changes of external atomic layers of polymeric coating surfaces, as detected by the X-ray photoelectron spectroscopy method, which is compatible with extended chemical changes on catheter surfaces. CONCLUSION: The reprocessing of the catheters with ethylene oxide was not associated with morphological or chemical changes, and it seemed appropriate to maintain guide wire coating integrity. However, the method combining chemical cleaning with mechanical vibration resulted in rough anatomical and chemical surface deterioration, suggesting that this reprocessing method should be discouraged.

  11. 77 FR 38789 - Notice of Availability of Draft Waste Incidental to Reprocessing Evaluation for the Concentrator...

    Science.gov (United States)

    2012-06-29

    ... of Availability of Draft Waste Incidental to Reprocessing Evaluation for the Concentrator Feed Makeup... concentrator feed makeup tank and melter feed hold tank (the vessels) which were used in conjunction with... waste packages in accordance with applicable waste acceptance criteria using specific waste profile...

  12. Mechanical, Thermomechanical and Reprocessing Behavior of Green Composites from Biodegradable Polymer and Wood Flour

    Directory of Open Access Journals (Sweden)

    Marco Morreale

    2015-11-01

    Full Text Available The rising concerns in terms of environmental protection and the search for more versatile polymer-based materials have led to an increasing interest in the use of polymer composites filled with natural organic fillers (biodegradable and/or coming from renewable resources as a replacement for traditional mineral inorganic fillers. At the same time, the recycling of polymers is still of fundamental importance in order to optimize the utilization of available resources, reducing the environmental impact related to the life cycle of polymer-based items. Green composites from biopolymer matrix and wood flour were prepared and the investigation focused on several issues, such as the effect of reprocessing on the matrix properties, wood flour loading effects on virgin and reprocessed biopolymer, and wood flour effects on material reprocessability. Tensile, Dynamic-mechanical thermal (DMTA, differential scanning calorimetry (DSC and creep tests were performed, pointing out that wood flour leads to an improvement of rigidity and creep resistance in comparison to the pristine polymer, without compromising other properties such as the tensile strength. The biopolymer also showed a good resistance to multiple reprocessing; the latter even allowed for improving some properties of the obtained green composites.

  13. Advances in Endoscope Reprocessing Technology and Its Impact on Pathogen Transmission.

    Science.gov (United States)

    Shellnutt, Cathleen

    Pathogen transmissions via flexible endoscopes have been documented in the literature and have been historically related to human error or omission of steps in the reprocessing cycle. The 2008 Centers for Disease Control and Prevention report challenged manufacturers of automated endoscope reprocessors to improve and advance technology to automate more of the reprocessing steps. A review and synthesis of the literature following the 2008 Centers for Disease Control and Prevention report was performed to evaluate whether advances in reprocessing technology have occurred and whether these have had an impact on pathogen transmission via flexible endoscopes. The Iowa Model of Evidence-Based Practice to Promote Quality Care was used to guide the project. The literature search regarding pathogen transmission related to flexible endoscopes yielded 10 documents citing infections from 2008 to 2015. A total of 353 patients were identified as having been infected with a contaminated gastroscope, bronchoscope, or duodenoscope. An evaluation of reprocessing technology identified 3 automated endoscope reprocessors with enhanced capabilities and flushing devices intended to automate portions of the manual cleaning step.

  14. Assessment of the NOAA S-NPP VIIRS Geolocation Reprocessing Improvements

    Directory of Open Access Journals (Sweden)

    Wenhui Wang

    2017-09-01

    Full Text Available Long-term time series analysis requires consistent data records from satellites. The Visible Infrared Imaging Radiometer Suite (VIIRS onboard the Suomi National Polar orbiting Partner (S-NPP satellite launched in 2011 requires a major effort to produce consistently calibrated sensor data records (SDR. Accurate VIIRS geolocation products are critical to other VIIRS products and products from other instruments on the S-NPP satellite. This paper presents methods for assessing major improvements to the VIIRS geolocation products in the ongoing National Oceanic and Atmospheric Administration (NOAA/Center for Satellite Applications and Research (STAR reprocessing that incorporates all corrections in calibration parameters and SDR algorithms since launch to present. In this study, we analyzed the history of VIIRS geometric calibration parameter updates to identify optimal parameters to account for geolocation errors in the early days of the mission. A sample area located in North Western Africa was selected for validation purposes after analyzing global VIIRS and Landsat control point matching results. Geolocation products over the study region were reprocessed and I-bands/M-bands geolocation improvements were characterized by comparing geolocation errors before and after the reprocessing. Our results indicate that all short-term geolocation anomalies before the latest operational geometric calibration parameter update on 22 August 2013 were effectively minimized after reprocessing, with geolocation errors reduced from −47.1 ± 83.8 m to −23.3 ± 51.1 m (along scan and from −15.6 ± 43.6 m to −5.9 ± 37.7 m (along track. Terrain correction for the VIIRS Day-Night-Band (DNB was not implemented in the NOAA operational processing until 22 May 2015. In the reprocessing, it will be implemented to the entire DNB geolocation data record. DNB reprocessing improvement due to this implementation was evaluated using nighttime observations over point

  15. Retention of long-term interim restorations with sodium fluoride enriched interim cement

    Science.gov (United States)

    Strash, Carolyn

    Purpose: Interim fixed dental prostheses, or "provisional restorations", are fabricated to restore teeth when definitive prostheses are made indirectly. Patients undergoing extensive prosthodontic treatment frequently require provisionalization for several months or years. The ideal interim cement would retain the restoration for as long as needed and still allow for ease of removal. It would also avoid recurrent caries by preventing demineralization of tooth structure. This study aims to determine if adding sodium fluoride varnish to interim cement may assist in the retention of interim restorations. Materials and methods: stainless steel dies representing a crown preparation were fabricated. Provisional crowns were milled for the dies using CAD/CAM technology. Crowns were provisionally cemented onto the dies using TempBond NE and NexTemp provisional cements as well as a mixture of TempBond NE and Duraphat fluoride varnish. Samples were stored for 24h then tested or thermocycled for 2500 or 5000 cycles before being tested. Retentive strength of each cement was recorded using a universal testing machine. Results: TempBond NE and NexTemp cements performed similarly when tested after 24h. The addition of Duraphat significantly decreased the retention when added to TempBond NE. NexTemp cement had high variability in retention over all tested time periods. Thermocycling for 2500 and 5000 cycles significantly decreased the retention of all cements. Conclusions: The addition of Duraphat fluoride varnish significantly decreased the retention of TempBond NE and is therefore not recommended for clinical use. Thermocycling significantly reduced the retention of TempBond NE and NexTemp. This may suggest that use of these cements for three months, as simulated in this study, is not recommended.

  16. PROJECT W-551 INTERIM PRETREATMENT SYSTEM PRECONCEPTUAL CANDIDATE TECHNOLOGY DESCRIPTIONS

    Energy Technology Data Exchange (ETDEWEB)

    MAY TH

    2008-08-12

    The Office of River Protection (ORP) has authorized a study to recommend and select options for interim pretreatment of tank waste and support Waste Treatment Plant (WTP) low activity waste (LAW) operations prior to startup of all the WTP facilities. The Interim Pretreatment System (IPS) is to be a moderately sized system which separates entrained solids and 137Cs from tank waste for an interim time period while WTP high level waste vitrification and pretreatment facilities are completed. This study's objective is to prepare pre-conceptual technology descriptions that expand the technical detail for selected solid and cesium separation technologies. This revision includes information on additional feed tanks.

  17. Possible toxic effects from the nuclear reprocessing at Sellafield and Cap de la Hague

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, M.; Coeytaux, X.; Faid, Y.B.; Marignac, Y.; Rouy, E. [Wise, 75 - Paris (France); Thompson, G. [IRSS, Cambridge (United States); Fairlie, I.; Lowry, D.; Sumner, D

    2001-11-15

    The principal aim of this report is to assist the Committee of Petitions of the European Parliament in its consideration of Petition 393/95 brought by Dr. W. Nachtwey. The Petition expresses concerns about radioactive discharges from nuclear reprocessing plants at Sellafield in the UK and La Hague in France, and their possible adverse health effects. Six years after the Petition was introduced, the Petitioner main concerns remain relevant. This report concludes that reprocessing discharges are a valid matter for the Committee consideration. It also concludes that, on balance, the Petitioner's concerns over radioactive discharges from Sellafield and La Hague are justified. The report presents evidence and data on: 1) radioactive discharges from the Sellafield and La Hague sites; 2) resulting nuclide concentrations in environmental media including foodstuffs; 3) radiation doses from nuclide discharges to critical groups near the sites; 4) adverse health effects near the two sites; and 5) resulting collective doses from nuclide discharges. The report also examines a number of current issues in radiobiology concerning health effects from exposure to ionising radiation, in particular genetic and in utero effects. In addition, in accordance with contract specifications, the report examines other major factors that might influence future decision-making on reprocessing. It provides information on the legal framework, the operational history of the plants and the economic case for reprocessing compared with available alternatives for spent nuclear fuel management. The report also makes policy-related recommendations that take into account current knowledge and uncertainties in risk assessment and the availability of alternatives to reprocessing in spent fuel management. (authors)

  18. Duodenoscope reprocessing surveillance with adenosine triphosphate testing and terminal cultures: a clinical pilot study.

    Science.gov (United States)

    Visrodia, Kavel; Hanada, Yuri; Pennington, Kelly M; Tosh, Pritish K; Topazian, Mark D; Petersen, Bret T

    2017-07-01

    Recent reports of infectious outbreaks linked to duodenoscopes have led to proposals for duodenoscope surveillance culturing, which has inherent limitations. We aimed to assess the feasibility of real-time adenosine triphosphate (ATP) testing after manual cleaning and its ability to predict reprocessing adequacy, as determined by terminal duodenoscope cultures. Clinically used duodenoscopes underwent reprocessing per current guidelines. After manual cleaning, ATP samples were obtained from the elevator, within the proximal biopsy port, and by flushing of the biopsy channel. After high-level disinfection (HLD), aerobic cultures of the elevator and biopsy channel were obtained using sterile technique. Duodenoscopes with any ATP sample ≥200 relative light units underwent repeated cycles of cleaning, ATP testing, HLD, and terminal culturing. Twenty clinically used duodenoscopes were included; 18 underwent a second reprocessing cycle, and 6 underwent a third reprocessing cycle because of detection of high ATP. After the initial reprocessing cycle, 12 of 20 (60%) duodenoscopes had positive culture results, most commonly yielding gram-negative bacilli (GNB, n = 11 from 9 duodenoscopes), and catalase-positive gram-positive cocci (CP-GPC, n = 7 from 7 duodenoscopes), suggesting staphylococcal organisms. Ambient environmental controls also showed GNB and CP-GPC growth. The overall sensitivity and specificity of ATP testing compared with terminal cultures were 30% and 53%, respectively. ATP sampling appears to correlate poorly with terminal culture results and cannot be recommended as a surrogate for terminal cultures. The performance and interpretation of cultures remains complicated by the potential recovery of environmental contaminants. Copyright © 2017 American Society for Gastrointestinal Endoscopy. Published by Elsevier Inc. All rights reserved.

  19. OSI SAF Sea Surface Temperature reprocessing of MSG/SEVIRI archive.

    Science.gov (United States)

    Saux Picart, Stéphane; Legendre, Gerard; Marsouin, Anne; Péré, Sonia; Roquet, Hervé

    2017-04-01

    The Ocean and Sea-Ice Satellite Application Facility (OSI-SAF) of the European Organisation for the Exploitation of Meteorological Satellites (EUMETSAT) is planning to deliver a reprocessing of Sea Surface Temperature (SST) from Spinning Enhanced Visible and Infrared Imager/Meteosat Second Generation (SEVIRI/MSG) archive (2004-2012) by the end of 2016. This reprocessing is drawing from experiences of the OSI SAF team in near real time processing of MSG/SEVIRI data. The retrieval method consist in a non-linear split-window algorithm including the algorithm correction scheme developed by Le Borgne et al. (2011). The bias correction relies on simulations of infrared brightness temperatures performed using Numerical Weather Prediction model atmospheric profiles of water vapour and temperature, and RTTOV radiative transfer model. The cloud mask used is the Climate SAF reprocessing of the MSG/SEVIRI archive. It is consistent over the period in consideration. Atmospheric Saharan dusts have a strong impact on the retrieved SST, they are taken into consideration through the computation of the Saharan Dust Index (Merchant et al., 2006) which is then used to determine an empirical correction applied to SST. The MSG/SEVIRI SST reprocessing dataset consist in hourly level 3 composite of sub-skin temperature projected onto a regular 0.05° grid over the region delimited by 60N,60S and 60W,60E. This presentation gives an overview of the data and methods used for the reprocessing, the products and validation results against drifting buoys measurements extracted from the ERA Clim dataset.

  20. Nuclear fuel reprocessing deactivation plan for the Idaho Chemical Processing Plant, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Patterson, M.W.

    1994-10-01

    The decision was announced on April 28, 1992 to cease all United States Department of Energy (DOE) reprocessing of nuclear fuels. This decision leads to the deactivation of all fuels dissolution, solvent extraction, krypton gas recovery operations, and product denitration at the Idaho Chemical Processing Plant (ICPP). The reprocessing facilities will be converted to a safe and stable shutdown condition awaiting future alternate uses or decontamination and decommissioning (D&D). This ICPP Deactivation Plan includes the scope of work, schedule, costs, and associated staffing levels necessary to achieve a safe and orderly deactivation of reprocessing activities and the Waste Calcining Facility (WCF). Deactivation activities primarily involve shutdown of operating systems and buildings, fissile and hazardous material removal, and related activities. A minimum required level of continued surveillance and maintenance is planned for each facility/process system to ensure necessary environmental, health, and safety margins are maintained and to support ongoing operations for ICPP facilities that are not being deactivated. Management of the ICPP was transferred from Westinghouse Idaho Nuclear Company, Inc. (WINCO) to Lockheed Idaho Technologies Company (LITCO) on October 1, 1994 as part of the INEL consolidated contract. This revision of the deactivation plan (formerly the Nuclear Fuel Reprocessing Phaseout Plan for the ICPP) is being published during the consolidation of the INEL site-wide contract and the information presented here is current as of October 31, 1994. LITCO has adopted the existing plans for the deactivation of ICPP reprocessing facilities and the plans developed under WINCO are still being actively pursued, although the change in management may result in changes which have not yet been identified. Accordingly, the contents of this plan are subject to revision.

  1. Does the radiation from the interim storage in Gorleben affect the sex ratio of newborn children?; Beeinflusst die Strahlung aus dem Zwischenlager in Gorleben das Geschlechterverhaeltnis von Neugeborenen?

    Energy Technology Data Exchange (ETDEWEB)

    Engelmann, H.W.; Schulze, H.; Wede, S. [GNS Gesellschaft fuer Nuklear-Service mbH, Gorleben (Germany); Mueller, S. [Studsvik GmbH, Pforzheim (Germany)

    2015-07-01

    In the professional world but especially in public, the question is discussed whether ionizing radiation from nuclear facilities has a significant impact on the secondary sex ratio of newborn children in the vicinity of the plants. This issue is of exceptional importance in the region around Gorleben, where the opposition to nuclear facilities and activities for decades is particularly strong. At the site borders of the interim storage facility (TBL-G) of GNS the effective individual dose is about 0.2 mSv per year, mainly caused by neutron irradiation from 108 casks with high-level radioactive waste from reprocessing. In the surrounding villages there is no radiation measurable. Statistical studies allegedly have shown evidence that in some villages in the area and during certain periods, proportionately fewer girls were born in comparison to the average for the Federal Republic of Germany. Based on these purely statistical results henceforward was also alleged that neutron-induced secondary effects such as activation or secondary gamma radiation would be responsible for it. Monte Carlo calculations and special measurements yielded values of the dose at the plant border for activation products less than E-04 mSv/a and for secondary gamma radiation of about E-03 mSv/a. These results indicate that the ionizing radiation from the Gorleben interim storage facility cannot be held accountable for shifts of the secondary sex ratio.

  2. ORNL fusion power demonstration study: interim report

    Energy Technology Data Exchange (ETDEWEB)

    STeiner, D.; Bettis, E. S.; Huxford, T. J.

    1977-03-01

    The purpose of the ORNL Fusion Power Demonstration Study (Demo study) is to develop a plan for demonstrating, in this century, the commercial feasibility of fusion power based on the tokamak concept. The two-year study was initiated in FY 1976, and this interim report summarizes the results for FY 1976. Major results include: (1) the outline of a three-phase plan for demonstrating the commercial feasibility of tokamak fusion power in this century; (2) a parametric analysis of tokamak costs which provides the economic basis for the demonstration plan; and (3) a critical evaluation of the technological directions, design approaches, and plasma characteristics which serve as the technical basis for the demonstration plan.

  3. Natural tooth as an interim prosthesis.

    Science.gov (United States)

    Dhariwal, Neha S; Gokhale, Niraj S; Patel, Punit; Hugar, Shivayogi M

    2016-01-01

    A traumatic injury to primary maxillary anterior tooth is one of the common causes for problems with the succedaneous tooth leading to it noneruption. A missing anterior tooth can be psychologically and socially damaging to the patient. Despite a wide range of treatment options available, sometimes, it is inevitable to save the natural tooth. This paper describes the immediate replacement of a right central incisor using a fiber-composite resin splint with the natural tooth crown as a pontic following surgical extraction of the dilacerated impacted permanent maxillary central incisor. The abutment teeth can be conserved with minimal or no preparation, thus keeping the technique reversible and can be completed at chair side thereby avoiding laboratory costs. It can be used as an interim measure until a definitive prosthesis can be fabricated as the growth is still incomplete.

  4. Interim Feed The Future Population Based Assessment of Cambodia

    Data.gov (United States)

    US Agency for International Development — This is the interim population based survey of Feed the Future in Cambodia for 2015. The data is split into survey modules. Modules A through C includes location...

  5. 13 CFR 120.890 - Source of interim financing.

    Science.gov (United States)

    2010-01-01

    ... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Source of interim financing. 120.890 Section 120.890 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION BUSINESS LOANS... or professional construction manager.) ...

  6. TANK FARM INTERIM SURFACE BARRIER MATERIALS AND RUNOFF ALTERNATIVES STUDY

    Energy Technology Data Exchange (ETDEWEB)

    HOLM MJ

    2009-06-25

    This report identifies candidate materials and concepts for interim surface barriers in the single-shell tank farms. An analysis of these materials for application to the TY tank farm is also provided.

  7. Big Oaks National Wildlife Refuge : Interim Public Access Plan : 2000

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This interim plan covers public access for Big Oaks National Wildlife Refuge. Sections include introduction, safety briefing protocols, entry procedure, types of...

  8. Interim research assessment 2003-2005 - Computer Science

    NARCIS (Netherlands)

    Mouthaan, A.J.; Hartel, Pieter H.

    This report primarily serves as a source of information for the 2007 Interim Research Assessment Committee for Computer Science at the three technical universities in the Netherlands. The report also provides information for others interested in our research activities.

  9. Students' interim literacies as a dynamic resource for teaching and ...

    African Journals Online (AJOL)

    . ... This article explores the notion of 'interim literacies'by drawing on data from a research project which used linguistic and intertextual analysis of first year student writing in economics to investigate the intersection of academic discourse and ...

  10. Intelligent cruise control field operational test : interim report

    Science.gov (United States)

    1997-03-01

    This interim document reports on a cooperative agreement between NHTSA and UMTRI entitled Intelligent Cruise Control (ICC) Field Operational Test (FOT). The overarching goal of the work is to characterize safety and comfort issues that are fundamenta...

  11. Environmental survey of the reprocessing and waste management portions of the LWR fuel cycle: a task force report

    Energy Technology Data Exchange (ETDEWEB)

    Bishop, W.P.; Miraglia, F.J. Jr. (eds.)

    1976-10-01

    This Supplement deals with the reprocessing and waste management portions of the nuclear fuel cycle for uranium-fueled reactors. The scope of the report is limited to the illumination of fuel reprocessing and waste management activities, and examination of the environmental impacts caused by these activities on a per-reactor basis. The approach is to select one realistic reprocessing and waste management system and to treat it in enough depth to illuminate the issues involved, the technology available, and the relationships of these to the nuclear fuel cycle in general and its environmental impacts.

  12. Interim Safety Basis for Fuel Supply Shutdown Facility

    Energy Technology Data Exchange (ETDEWEB)

    BENECKE, M.W.

    2000-09-07

    This ISB, in conjunction with the IOSR, provides the required basis for interim operation or restrictions on interim operations and administrative controls for the facility until a SAR is prepared in accordance with the new requirements or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines.

  13. K basins interim remedial action health and safety plan

    Energy Technology Data Exchange (ETDEWEB)

    DAY, P.T.

    1999-09-14

    The K Basins Interim Remedial Action Health and Safety Plan addresses the requirements of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as they apply to the CERCLA work that will take place at the K East and K West Basins. The provisions of this plan become effective on the date the US Environmental Protection Agency issues the Record of Decision for the K Basins Interim Remedial Action, currently planned in late August 1999.

  14. Application of laser induced fluorescence analysis to nuclear fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Hayashibara, Hirofumi; Miyake, Takafumi; Izumi, Jyun [Mitsubishi Heavy Industries Ltd., Takasago, Hyogo (Japan). Takasago Research and Development Center; Taguchi, Syouzou; Watanabe, Ryuuichi

    1996-09-01

    In nuclear fuel reprocessing plants, to maintain the system integrity, many kinds of chemical analysis must be done. However, with chemical analysis performed under a high radiation field, to reduce the occupational radiation exposure, a new type of trace analysis technique is desirable, concerning the technique of trace analysis, a laser ray method enables us to achieve higher sensitivity and selectivity than the conventional methods, due to its higher energy and narrow spectral width. Then, we developed a laser induced fluorescence (LIF) method and performed an application study for fuel reprocessing plants by using the simulated samples. Main investigated analyzed elements are an impurities of uranium in nitric acid solution. As a result of this investigation, a pretreatment procedure of analysis was found to be simple compared with the conventional analysis method. (author)

  15. Available reprocessing and recycling services for research reactor spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Tozser, Sandor; Marshall, Frances M.; Adelfang, Pablo; Bradley, Edward [International Atomic Energy Agency, Vienna (Austria); Budu, Madalina Elena [SOSNY Research and Development Company, Moscow (Russian Federation); Chiguer, Mustapha [AREVA, Paris La Defense (France)

    2016-03-15

    International activities in the back end of the research reactor (RR) fuel cycle have so far been dominated by the programmes of acceptance of highly-enriched uranium (HEU) spent nuclear fuel (SNF) by the country where it was originally enriched. In the future inventories of LEU SNF will continue to be created and the back end solution of RR SNF remains a critical issue. The IAEA, based on the experience gained during the decade of international cooperation in supporting the objectives of the HEU take-back programmes, drew up a report presenting available reprocessing and recycling services for RR SNF. This paper gives an overview of the report, which will address all aspects of reprocessing and recycling services for RR SNF.

  16. Eye movement desensitization and reprocessing (EMDR) in the treatment of war veterans.

    Science.gov (United States)

    Silver, Steven M; Rogers, Susan; Russell, Mark

    2008-08-01

    Recent practice guidelines and meta-analyses have designated eye movement desensitization and reprocessing (EMDR) as a first-line treatment for trauma. Eye movement desensitization and reprocessing is an eight-phase therapeutic approach guided by an information-processing model that addresses the combat veteran's critical incidents, current triggers, and behaviors likely to prove useful in his or her future. Two case examples of combat veterans illustrate the ability of EMDR to achieve symptom reduction in a variety of clinical domains (e.g., anxiety, depression, anger, physical pain) simultaneously without requiring the patient to carry out homework assignments or discuss the details of the event. The treatment of phantom limb pain and other somatic presentations is also reviewed. The ability of EMDR to achieve positive effects without homework indicates that it can be effectively employed on consecutive days, making it especially useful during combat situations. (c) 2008 Wiley Periodicals, Inc.

  17. Designing and Operating for Safeguards: Lessons Learned From the Rokkasho Reprocessing Plant (RRP)

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, Shirley J.; Ehinger, Michael

    2010-08-07

    This paper will address the lessons learned during the implementation of International Atomic Energy Agency (IAEA) safeguards at the Rokkasho Reprocessing Plant (RRP) which are relevant to the issue of ‘safeguards by design’. However, those lessons are a result of a cumulative history of international safeguards experiences starting with the West Valley reprocessing plant in 1969, continuing with the Barnwell plant, and then with the implementation of international safeguards at WAK in Germany and TRP in Japan. The design and implementation of safeguards at RRP in Japan is the latest and most challenging that the IAEA has faced. This paper will discuss the work leading up to the development of a safeguards approach, the design and operating features that were introduced to improve or aid in implementing the safeguards approach, and the resulting recommendations for future facilities. It will provide an overview of how ‘safeguardability’ was introduced into RRP.

  18. The Patient Observer : Eye-Movement Desensitization and Reprocessing for the Treatment of Posttraumatic Stress following Childbirth

    NARCIS (Netherlands)

    Stramrood, Claire A. I.; van der Velde, Janneke; Doornbos, Bennard; Paarlberg, K. Marieke; Weijmar Schultz, Willibrord C. M.; van Pampus, Maria G.

    Background: No standard intervention with proved effectiveness is available for women with posttraumatic stress following childbirth because of insufficient research. The objective of this paper was to evaluate the possibility of using eye-movement desensitization and reprocessing treatment for

  19. Evaluation of ERA-Interim precipitation data in complex terrain

    Science.gov (United States)

    Gao, Lu; Bernhardt, Matthias; Schulz, Karsten

    2013-04-01

    Precipitation controls a large variety of environmental processes, which is an essential input parameter for land surface models e.g. in hydrology, ecology and climatology. However, rain gauge networks provides the necessary information, are commonly sparse in complex terrains, especially in high mountainous regions. Reanalysis products (e.g. ERA-40 and NCEP-NCAR) as surrogate data are increasing applied in the past years. Although they are improving forward, previous studies showed that these products should be objectively evaluated due to their various uncertainties. In this study, we evaluated the precipitation data from ERA-Interim, which is a latest reanalysis product developed by ECMWF. ERA-Interim daily total precipitation are compared with high resolution gridded observation dataset (E-OBS) at 0.25°×0.25° grids for the period 1979-2010 over central Alps (45.5-48°N, 6.25-11.5°E). Wet or dry day is defined using different threshold values (0.5mm, 1mm, 5mm, 10mm and 20mm). The correspondence ratio (CR) is applied for frequency comparison, which is the ratio of days when precipitation occurs in both ERA-Interim and E-OBS dataset. The result shows that ERA-Interim captures precipitation occurrence very well with a range of CR from 0.80 to 0.97 for 0.5mm to 20mm thresholds. However, the bias of intensity increases with rising thresholds. Mean absolute error (MAE) varies between 4.5 mm day-1 and 9.5 mm day-1 in wet days for whole area. In term of mean annual cycle, ERA-Interim almost has the same standard deviation of the interannual variability of daily precipitation with E-OBS, 1.0 mm day-1. Significant wet biases happened in ERA-Interim throughout warm season (May to August) and dry biases in cold season (November to February). The spatial distribution of mean annual daily precipitation shows that ERA-Interim significant underestimates precipitation intensity in high mountains and northern flank of Alpine chain from November to March while pronounced

  20. Lanthanides extraction processes in molten fluoride media. Application to nuclear spent fuel reprocessing

    OpenAIRE

    Taxil, Pierre; Massot, Laurent; Nourry, Christophe; Gibilaro, Mathieu; Chamelot, Pierre; Cassayre, Laurent

    2009-01-01

    This paper describes four techniques of extraction of lanthanides elements (Ln) from molten salts in the general frame of reprocessing nuclear wastes; One of them is chemical: the precipitation of Ln ions in insoluble compounds (oxides or oxifluorides); the others use electrochemical methodology in molten fluorides for extraction and measurement of the progress of the processes: first electrodeposition of pure Ln metals on an inert cathode material was proved to be incomplete and cause probl...

  1. Krypton-85 health risk assessment for a nuclear fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Mellinger, P.J.; Brackenbush, L.W.; Tanner, J.E.; Gilbert, E.S.

    1984-08-01

    The risks involved in the routine release of /sup 85/Kr from nuclear fuel reprocessing operations to the environment were compared to those resulting from the capture and storage of /sup 85/Kr. Instead of releasing the /sup 85/Kr to the environment when fuel is reprocessed, it can be captured, immobilized and stored. Two alternative methods of capturing /sup 85/Kr (cryogenic distillation and fluorocarbon absorption) and one method of immobilizing the captured gas (ion implantation/sputtering) were theoretically incorporated into a representative fuel reprocessing plant, the Barnwell Nuclear Fuel Plant, even though there are no known plans to start up this facility. Given the uncertainties in the models used to generate lifetime risk numbers (0.02 to 0.027 radiation induced fatal cancers expected in the occupational workforce and 0.017 fatal cancers in the general population), the differences in total risks for the three situations, (i.e., no-capture and two-capture alternatives) cannot be considered meaningful. It is possible that no risks would occur from any of the three situations. There is certainly no reason to conclude that risks from /sup 85/Kr routinely released to the environment are greater than those that would result from the other two situations considered. Present regulations mandate recovery and disposal of /sup 85/Kr from the off gases of a facility reprocessing spent fuel from commercial sources. Because of the lack of a clear-cut indication that recovery woud be beneficial, it does not seem prudent to burden the facilities with a requirement for /sup 85/Kr recovery, at least until operating experience demonstrates the incentive. The probable high aging of the early fuel to be processed and the higher dose resulting from the release of the unregulated /sup 3/H and /sup 14/C also encourage delaying implementation of the /sup 85/Kr recovery in the early plants.

  2. 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)

  3. Post-traumatic stress disorder: neurobiology and effects of eye movement desensitization and reprocessing

    OpenAIRE

    Högberg, Göran

    2008-01-01

    The aim of this study was to evaluate a new psychotherapy method, eye movement desensitization and reprocessing (EMDR) in the treatment of post-traumatic stress disorder (PTSD) and to study the biological reactions in PTSD during a script-driven symptom provocation. PTSD is a disorder that may occur after a major psychological trauma. It is characterised by the phenomenon of reliving, bringing the person back to the sensations and reactions that prevailed during the traumat...

  4. An Integrative Model for the Neural Mechanism of Eye Movement Desensitization and Reprocessing (EMDR)

    OpenAIRE

    Coubard, Olivier A.

    2016-01-01

    Since the seminal report by Shapiro that bilateral stimulation induces cognitive and emotional changes, twenty-six years of basic and clinical research have examined the effects of Eye Movement Desensitization and Reprocessing (EMDR) in anxiety disorders, particularly in Post-Traumatic Stress Disorder (PTSD). The present article aims at better understanding EMDR neural mechanism. I first review procedural aspects of EMDR protocol and theoretical hypothesis about EMDR effects, and develop the ...

  5. Treatment of dysfunctionally stored experiences with the method Eye Movement Desensitization and Reprocessing – EMDR

    Directory of Open Access Journals (Sweden)

    Robert Cvetek

    2002-09-01

    Full Text Available In this paper a new therapeutic method called EMDR (Eye Movement Desensitization and Reprocessing is described. The method was formed mainly for treatment of posttraumatic stress disorder, but there are also some reports about success with other mental disorders. The theoretical base of EMDR and especially the accelerated information processing model, the concept of memory networks and the explanations of effects of eye movements are presented. The process of EMDR is also described.

  6. The reclamation and reprocessing of cotton wastes produced during yarn preparation

    CSIR Research Space (South Africa)

    Bathie, LA

    1984-11-01

    Full Text Available reprocessing such as: - waste from cotton gins; - blowroom waste; - carding waste (licker-in, grids), and - card flat strips and filter waste. (i) Clean waste: waste which requires no further cleaning, e.g. - comber waste; - card, drawframe and combed... waste slivers; - opened rovings, and - filter waste from drawframes, speed frames, ring spinning frames and rotor spinning machines. (i) Hard waste: waste which requires opening on special machines, such as: - twisted rovings; - yams...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-07-01

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

  8. Effect of reprocessing cycles on the degradation of polypropylene copolymer filled with talc or montmorillonite during injection molding process

    Energy Technology Data Exchange (ETDEWEB)

    Demori, R.; Mauler, R. S., E-mail: raquel.mauler@ufrgs.br [Chemistry Institute, Federal University of Rio Grande do Sul, UFRGS, Av. Bento Gonçalves, 9500, Porto Alegre, 91501-970 (Brazil); Ashton, E.; Weschenfelder, V. F.; Cândido, L. H. A.; Kindlein, W. [Laboratory of Design LDSM, Federal University of Rio Grande do Sul, UFRGS (Brazil)

    2015-05-22

    Mechanical recycling of polymeric materials is a favorable technique resulting in economic and environmental benefits, especially in the case of polymers with a high production volume as the polypropylene copolymer (PP). However, recycling by reprocessing techniques can lead to thermal, mechanical or thermo-oxidative degradation that can affect the structure of the polymer and subsequently the material properties. PP filled with montmorillonite (MMT) or talc are widely produced and studied, however, its degradation reactions by reprocessing cycles are poorly studied so far. In this study, the effects of reprocessing cycles in the structure and in the properties of the PP/MMT and PP/Talc were evaluated. The samples were mixed with 5% talc or MMT Cloisite C15A in a twin-screw extrusion. After extrusion, this filled material was submitted to five reprocessing cycles through an injection molding process. In order to evaluate the changes induced by reprocessing techniques, the samples were characterized by DSC, FT-IR, Izod impact and tensile strength tests. The study showed that Young modulus, elongation at brake and Izod impact were not affected by reprocessing cycles, except when using talc. In this case, the elongation at brake reduced until the fourth cycle, showing rigidity increase. The DSC results showed that melting and crystallization temperature were not affected. A comparison of FT-IR spectra of the reprocessed indicated that in both samples, between the first and the fifth cycle, no noticeable change has occurred. Thus, there is no evidence of thermo oxidative degradation. In general, these results suggest that PP reprocessing cycles using MMT or talc does not change the material properties until the fifth cycle.

  9. Safety-related Innovative Nuclear Reactor Technology Elements R and D (SINTER) Network and Global HTGR R and D Network (GHTRN). Strategic benefits of international networking

    Energy Technology Data Exchange (ETDEWEB)

    Von Lensa, W. [Institut fuer Sicherheitsforschung und Reaktortechnik ISR, Forschungszentrum Juelich, Juelich (Germany)

    1998-09-01

    Action on `Safety-related Innovative Nuclear Reactor Technology Elements - R and D - (SINTER) Network` both aim at the identification of priority items for sustainable innovations of nuclear technologies and work-shared European collaboration structures. Such an approach can also be realised for future R and D on HTGR-related R and D under the umbrella of the IAEA as already proposed by the `International Working Group on Gas-Cooled Reactors (IWGGCR)` in 1996 and illustrated in this paper for the construction of a `Global HTGR R and D Network (GHTRN)`. 3 refs.

  10. Effect of compatibilization and reprocessing on the isothermal crystallization kinetics of polypropylene/wood flour composites

    Directory of Open Access Journals (Sweden)

    Arieny Rodrigues

    2013-01-01

    Full Text Available Numerous studies have focused on polymer mixtures aimed at the potential applications of these materials. This work analyzed the effect of polymer reprocessing and the type and concentration of compatibilizer on the isothermal crystallization kinetics of polypropylene/wood flour composites. The composites, which were polypropylene grafted with acrylic acid (PP-g-AA and maleic anhydride (PP-g-MA, were processed in a twin screw extruder with and without compatibilizer. Reprocessed polypropylene reached complete crystallization in less time than the composites with virgin polypropylene. The addition of wood flour to the composites did not change the kinetics significantly compared to that of the pure polymers, but the compatibilizers did, particularly PP-g-AA. The nucleation exponent (n and crystallization rate (K were calculated from Avrami plots. The values of n ranged from 2 to 3, indicating instantaneous to sporadic nucleation. The crystallization half-time of reprocessed polypropylene was shorter than that of virgin polypropylene and of the compositions containing PP-g-AA compatibilizer. The activation energy of crystallization and the equilibrium melting temperature were calculated, respectively, from Arrhenius and Hoffman-Weeks plots. Both of these parameters showed lower values in the composites, particularly in the ones containing compatibilizers.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-01-01

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

  12. Influence of Reprocessing in the formation of functional groups during low density polyethylene aging

    Directory of Open Access Journals (Sweden)

    Maurício M. Selonke

    2012-01-01

    Full Text Available In recent years, the interest in polymer recycling has increased. However, in every reprocessing step the material undergoes shear stress and is affected by temperature and oxygen. The aim of this paper is to investigate the influence of multiple extrusion in the generation of functional groups, namely hydroperoxide, carbonyl, and transvinylene. Low density polyethylene was reprocessed three times in a single screw extruder. In each recycling step hot pressed films were prepared. These films were submitted to a heat treatment in an oven with air circulation and renovation to proceed with aging tests at different times and temperatures. The results obtained showed that all functional groups had their concentration increased with the increase in number of reprocessing, the aging time and temperature of the heat treatment. The factorial design was applied to verify the influence of these parameters. All the parameters had significant effects, since their regression coefficients had the same order of magnitude, with the most influential parameter being the aging temperature, followed by the aging time and number of extrusions. Most of the interactions were influential, indicating that the formation of functional groups depends upon their interaction, and not only on their isolated effects.

  13. Estimation of heavy metal concentration in FBR reprocessing solvent streams by density measurement

    Energy Technology Data Exchange (ETDEWEB)

    Brown, M.L.; Savage, D.J.

    1986-04-15

    The application of density measurement to heavy metal monitoring in the solvent phase is described, including practical experience gained during three fast reactor fuel reprocessing campaigns. An experimental algorithm relating heavy metal concentration and sample density was generated from laboratory-measured density data, for uranyl nitrate dissolved in nitric acid loaded tri-butyl phosphate in odorless kerosene. Differences in odorless kerosene batch densities are mathematically interpolated, and the algorithm can be used to estimate heavy metal concentrations from the density to within +1.5 g/l. An Anton Paar calculating digital densimeter with remote cell operation was used for all density measurements, but the algorithm will give similar accuracy with any density measuring device capable of a precision of better than 0.0005 g/cm/sup 3/. For plant control purposes, the algorithm was simplified using a density referencing system, whereby the density of solvent not yet loaded with heavy metal is subtracted from the sample density. This simplified algorithm compares very favorably with empirical algorithms, derived from numerical analysis of density data and chemically measured uranium and plutonium data obtained during fuel reprocessing campaigns, particularly when differences in the acidity of the solvent are considered before and after loading with heavy metal. This simplified algorithm has been successfully used for plant control of heavy metal loaded solvent during four fast reactor fuel reprocessing campaigns.

  14. Effectiveness of Eye Movement Desensitization and Reprocessing Therapy on Public Speaking Anxiety of University Students

    Directory of Open Access Journals (Sweden)

    Jalil Aslani

    2014-08-01

    Full Text Available Background: Public speaking anxiety is a prominent problem in the college student population. The purpose of this study was to determine the effectiveness of eye movement desensitization and reprocessing on public speaking anxiety of college students. Materials and Methods: The design of research was quasi-experimental with pre-post test type, and control group. The sample consistent of 30 students with speech anxiety that selected base on available sampling and assigned randomly in experimental (N=15 and control (N=15 groups. The experimental group was treated with EMDR therapy for 7 sessions. In order to collect the data, Paul’s personal report of confidence as a speaker, S-R inventory of anxiousness was used. To analyze the data, SPSS-19 software and covariance analysis were used. Results: The multivariate analysis of covariance showed that the eye movement desensitization and reprocessing reducing public speaking anxiety. The one-way analysis of covariance for each variable shows there are significant differences in confidence of speaker (p=0.001 and physiological symptoms of speech anxiety (p=0.001 at the two groups. Conclusion: These results suggest that treatment of eye movement desensitization and reprocessing is effective on reducing physiological symptoms of speech anxiety and increasing the speaker’s confidence.

  15. Lessons Learned in International Safeguards - Implementation of Safeguards at the Rokkasho Reprocessing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Ehinger, Michael H [ORNL; Johnson, Shirley [Tucker Creek Consulting

    2010-02-01

    The focus of this report is lessons learned at the Rokkasho Reprocessing Plant (RRP). However, the subject of lessons learned for application of international safeguards at reprocessing plants includes a cumulative history of inspections starting at the West Valley (New York, U.S.A.) reprocessing plant in 1969 and proceeding through all of the efforts over the years. The RRP is the latest and most challenging application the International Atomic Energy Agency has faced. In many ways the challenges have remained the same, timely inspection and evaluation with limited inspector resources, with the continuing realization that planning and preparations can never start early enough in the life cycle of a facility. Lessons learned over the years have involved the challenges of using ongoing advances in technology and dealing with facilities with increased throughput and continuous operation. This report will begin with a review of historical developments and lessons learned. This will provide a basis for a discussion of the experiences and lessons learned from the implementation of international safeguards at RRP.

  16. An assessment of the methods for determining defect or failure fractions in HTGR coated particle fuels and their relationship to particle microstructure

    Energy Technology Data Exchange (ETDEWEB)

    Meyers, B.F.

    1989-04-01

    The methods for determining the fraction of defective or failed coatings in high-temperature gas-cooled reactor (HTGR) fuel particles, the burn-leach and acid leach methods, are critically analyzed. Evaluation of the method reveals that (1) the efficacy of the methods is limited by access, for leaching and oxidizing fluids, to the interior of defective or failed coatings; (2) the coating defects can be characterized in terms of pores by a distribution of effective pore radii; (3) effective pore radii significantly less than several, hundred nanometers cannot be detected; and (4) pore radii less than the latter limit may contribute significantly to fission product release from the defective or failed particles. The currently used methods are thus inadequate for detecting defective or failed fuel particle coatings. The development of better methods is recommended; the intrusion method, by which a portion of the distribution of effective pore radii was determined in the analysis from limited previous measurements, is suggested as one suitable basis for the development. 32 refs., 10 figs., 11 tabs.

  17. Gas turbine and advanced HTGR materials screening test program: 10,000-hour results and semiannual progress report for the period ending March 31, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Rosenwasser, S.N.; Johnson, W.R.

    1977-07-01

    Work on the Gas-Turbine and Advanced High-Temperature Gas-Cooled Reactor (HTGR) Materials Screening Test Program is documented. Emphasis is on the results and analyses of creep data to 11,000 hr and the detailed metallurgical evaluations performed on candidate alloy specimens tested for up to 10,000 hr. Long-term creep and unstressed aging data in controlled-impurity helium and in air at 650, 800, and 900/sup 0/C are reported for the original alloys in the program, including the vacuum-cast Ni-base superalloys, IN 100, Rene 100, IN 713, MM 004, M 21, and IN 738; the wrought solid-solution-strengthened Ni--Cr alloys, Hastelloy X and Inconel 617; the centrifugally-cast austenitic Fe--Ni--Cr alloy, IN 519; the oxide-dispersion-strengthened (ODS) Ni--Cr alloys, MA 753 and MA 754; and the wrought Mo-base alloy, MoTZM. Results at 650/sup 0/C and 10,000 hr for the precipitation-strengthened alloys Inconel 718, Inconel 706, and A 286 are also included. Similar, but much shorter term data at 800, 900, and 1000/sup 0/C for the recently added wrought alloys Hastelloy X (second heat), Hastelloy S, RA 333, and HD 556, and the additional centrifugally-cast alloys HK 40, Supertherm, Manaurite 36X, Manaurige 36XS, and Manaurite 900, are also reported.

  18. A digital technique for fabricating implant-supported interim restorations in the esthetic zone.

    Science.gov (United States)

    Liu, Xiaoqiang; Tan, Yao; Liu, Jianzhang; Tan, Jianguo

    2017-07-11

    A digital technique for fabricating an implant-supported interim restoration is presented. The labial cervical architecture of the natural tooth is captured before extraction and registered to form the emergence profile of the interim restoration. A well-contoured interim restoration is fabricated before surgery and connected to the immediately placed implant with a customized interim abutment. Copyright © 2017 Editorial Council for the Journal of Prosthetic Dentistry. Published by Elsevier Inc. All rights reserved.

  19. 75 FR 35510 - License Renewal Interim Staff Guidance Process, Revision 2 Notice of Availability

    Science.gov (United States)

    2010-06-22

    ... COMMISSION License Renewal Interim Staff Guidance Process, Revision 2 Notice of Availability AGENCY: Nuclear... license renewal interim staff guidance (LR-ISG) process. This revision is entitled, ``License Renewal... Renewal Interim Staff Guidance Process, Revision 1'' (ML091950069) (the previous LR-ISG process). FOR...

  20. 78 FR 56750 - Interim Staff Guidance on Environmental Issues Associated With New Reactors

    Science.gov (United States)

    2013-09-13

    ... COMMISSION Interim Staff Guidance on Environmental Issues Associated With New Reactors AGENCY: Nuclear... Staff Guidance (ISG) ESP/COL-ISG-026, ``Interim Staff Guidance on Environmental Issues ] Associated with... Notice: Draft Interim Staff Guidance on Environmental Issues Associated with New Reactors. ML12326A742...

  1. 46 CFR 308.302 - Issuance of interim binder; terms and conditions.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 8 2010-10-01 2010-10-01 false Issuance of interim binder; terms and conditions. 308... OPERATIONS WAR RISK INSURANCE Second Seamen's War Risk Insurance § 308.302 Issuance of interim binder; terms and conditions. Upon acceptance of an application, an interim binder in form as set forth in § 308.3...

  2. 46 CFR 308.102 - Issuance of interim binder; terms and conditions; fees.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 8 2010-10-01 2010-10-01 false Issuance of interim binder; terms and conditions; fees... OPERATIONS WAR RISK INSURANCE War Risk Hull and Disbursements Insurance § 308.102 Issuance of interim binder; terms and conditions; fees. Upon acceptance of an application, an interim binder in the form set forth...

  3. A review of proposed Glen Canyon Dam interim operating criteria

    Energy Technology Data Exchange (ETDEWEB)

    LaGory, K.; Hlohowskyj, I.; Tomasko, D.; Hayse, J.; Durham, L.

    1992-04-01

    Three sets of interim operating criteria for Glen Canyon Dam on the Colorado River have been proposed for the period of November 1991, to the completion of the record of decision for the Glen Canyon Dam environmental impact statement (about 1993). These criteria set specific limits on dam releases, including maximum and minimum flows, up-ramp and down-ramp rates, and maximum daily fluctuation. Under the proposed interim criteria, all of these parameters would be reduced relative to historical operating criteria to protect downstream natural resources, including sediment deposits, threatened and endangered fishes, trout, the aquatic food base, and riparian plant communities. The scientific bases of the three sets of proposed operating criteria are evaluated in the present report:(1) criteria proposed by the Research/Scientific Group, associated with the Glen Canyon Environmental Studies (GCES); (2) criteria proposed state and federal officials charged with managing downstream resources; and (3) test criteria imposed from July 1991, to November 1991. Data from Phase 1 of the GCES and other sources established that the targeted natural resources are affected by dam operations, but the specific interim criteria chosen were not supported by any existing studies. It is unlikely that irreversible changes to any of the resources would occur over the interim period if historical operating criteria remained in place. It is likely that adoption of any of the sets of proposed interim operating criteria would reduce the levels of sediment transport and erosion below Glen Canyon Dam; however, these interim criteria could result in some adverse effects, including the accumulation of debris at tributary mouths, a shift of new high-water-zone vegetation into more flood-prone areas, and further declines in vegetation in the old high water zone.

  4. Interim process report for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Sellin, Patrick (ed.)

    2004-08-01

    This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses.

  5. Numerical simulations of waste forms from the reprocessing of nuclear fuel; Numerische Simulationen von Abfallgebinden aus der Wiederaufarbeitung von Kernbrennstoffen

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, Stephan

    2014-07-01

    The usage of fissile material for nuclear fuel causes that alongside radioactive wastes are produced. These waste materials are created during all handling or usage operations within the nuclear fuel cycle. The main source of radiotoxicity is produced during the usage of nuclear fuel within the reactor. Energy is released by neutron induced fission reactions in heavy isotopes. Parts of the created fission products have large radiotoxicities. Due to neutron capture within the nuclear fuel the radiotoxicity is furthermore increased. These waste streams from the nuclear fuel cycle must be stored in a safe way to prevent any contamination of the biosphere and any harm to the civilization or the environment. The waste packages must be treated and conditioned for the final disposal. These created packages are subject to an independent product control to ensure there acceptability for transport, interim and final storage. The independent product control is a significant component of an effective waste management system. The aim of this work is the development of a software system used for the assessment of radioactive waste packages. The software shall permit the auditor to perform scenario analysis to forecast the product properties of a certain waste stream and therefore optimize the needed inspection scope in preparation of a new campaign. The software is designed as a modular library this permits the most flexible use of the software components and a high reusability of written analysis software. The software system is used for coupling of established and well-known simulation programs used for nuclear systems. The results of Monte-Carlo simulations and burn-up calculations are automatically imported and prepared for user interaction. The usage of simulation programs cause different challenges to the computing infrastructure. The scenario analyses need a large number of parameter variations which are bound to the computing time. For this reason additional to the

  6. The reprocessing of advanced mixed lithium orthosilicate/metatitanate tritium breeder pebbles

    Energy Technology Data Exchange (ETDEWEB)

    Leys, Oliver, E-mail: oliver.leys@kit.edu [Karlsruhe Institute of Technology, Institute for Applied Materials, Eggenstein-Leopoldshafen, 76344 (Germany); Bergfeldt, Thomas; Kolb, Matthias H.H.; Knitter, Regina [Karlsruhe Institute of Technology, Institute for Applied Materials, Eggenstein-Leopoldshafen, 76344 (Germany); Goraieb, Aniceto A. [Karlsruhe Beryllium Handling Facility, Eggenstein-Leopoldshafen, 76344 (Germany)

    2016-06-15

    Highlights: • The recycling of advanced breeder pebbles without a deterioration of the material properties is possible using a melt-based process. • The only accumulation of impurities upon reprocessing, results from the platinum crucible alloy used for processing. • It is possible to replenish burnt-up lithium by additions of LiOH·H{sub 2}O to the melt during reprocessing. - Abstract: The recycling of tritium breeding materials will be necessary for any future use of nuclear fusion energy due to economical as well as ecological considerations. In the case of the solid breeder blanket concept, the ceramic pebble beds that are intended for the generation of tritium will eventually need to be restored due to depleted lithium levels as well as due to fractured pebbles, which will cause a deterioration of the pebble bed properties. It is proposed that the pebbles, which are fabricated using a melt-based process, are recycled using the same initial process, by replenishing the lithium levels and reforming the pebbles at the same time. To prove this recycling scheme, advanced ceramic pebbles were fabricated and then re-melted multiple times to prove that the reprocessing did not have any negative effect on the pebble properties and secondly, pebbles were produced with a simulated lithium burn-up and subsequently replenished by additions of LiOH to the melt. It was shown that the re-melting and lithium re-enrichment had no effect on the pebble properties, demonstrating that a melt-based process is suitable for recycling used breeder pebbles.

  7. Review of NRC Commission Papers on Regulatory Basis for Licensing and Regulating Reprocessing Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jae Yeong; Shin, Hyeong Ki [KINS, Daejeon (Korea, Republic of)

    2016-05-15

    Spent nuclear fuel (SNF) accumulated in nuclear power plant has been a serious issue in most countries with operating nuclear power plants. Direct disposal of SNF could be a solution of the problem but many countries including the Republic of Korea have had a hard time selecting a site for high level waste repository because of low public acceptance. SNF recycling technologies consisting of reprocessing and transmutation have been developed so as to reduce the final volume of the disposed radioactive waste and to diminish the radiotoxicity of the waste. The Republic of Korea is now developing pyroprocessing and sodium-cooled fast reactor (SFR) technology to be used for the recycling of the wastes. KAERI has a plan to construct a pyroprocessing facility with a capacity of 30 tHM/y and a facility manufacturing TRU fuel for SFR by 2025. However, to license these facility and secure the safety, the current regulatory system related to SNF treatment needs to be improved and amended since the system has been developed focusing on facilities to examine irradiated nuclear materials. Status of reprocessing facility regulations developed by U.S.NRC was reviewed based on SECY papers. U.S.NRC has approved the development of a new rule referred to nationally as '10CFR Part 7x'. Existing 10CFR 50 and 70 has been evolved mainly for nuclear power plants and fuel cycle facilities whose radiological hazard is much lower than reprocessing plants respectively. U.S.NRC also derived many regulatory gaps including safety assessment methods, technical specification, general design criteria and waste classification and continue to develop the regulatory framework limited in scope to the resolution of Gap 5.

  8. Usefulness of Adenosinetriphosphate Bioluminescence Assay (ATPmetry) for Monitoring the Reprocessing of Endoscopes.

    Science.gov (United States)

    Batailler, Pierre; Saviuc, Philippe; Picot-Gueraud, Romain; Bosson, Jean-Luc; Mallaret, Marie-Reine

    2015-12-01

    To assess the diagnostic value of an adenosinetriphosphate bioluminescence assay (ATPmetry) to monitor the effectiveness of the reprocessing of endoscopes compared with microbiologic sampling. Diagnostic study. A 2,200-bed teaching hospital performing 5,000 to 6,000 endoscopic procedures annually. All samples from bronchial or gastrointestinal endoscopes whatever the context. Samples for microbiologic analysis and ATPmetry measurements were taken when each endoscope was inspected following reprocessing. Sampling was performed by flushing each endoscope with 300 mL Neutralizing Pharmacopeia Diluent thiosulfate rinsing solution divided equally between the endoscope channels. For each endoscope a series of 3 ATPmetry measurements were made on a vial containing the first jet from each channel and a second series on the whole sample. Of 165 samples from endoscopes, 11 exceeded the acceptability threshold of 25 colony-forming units/endoscope. In the first jet collected, the median (interquartile range) level of ATPmetry was 30.5 (15.3-37.7) relative light units (RLU) for samples with 25 or fewer colony-forming units compared with 37.0 (34.7-39.3) RLU for samples with more than 25 colony-forming units (P=.008). For the whole sample, the median (interquartile range) level of ATPmetry was 24.8 (14.3-36.3) RLU and 36.3 (36.0-38.3) RLU (P=.006), respectively. After adjusting on the batch of cleansing solution used, no difference in ATPmetry values was found between microbiologically acceptable and unacceptable samples. ATPmetry cannot be used as an alternative or complementary approach to microbiologic tests for monitoring the reprocessing of endoscopes in France.

  9. Container for reprocessing and permanent storage of spent nuclear fuel assemblies

    Science.gov (United States)

    Forsberg, Charles W.

    1992-01-01

    A single canister process container for reprocessing and permanent storage of spent nuclear fuel assemblies comprising zirconium-based cladding and fuel, which process container comprises a collapsible container, having side walls that are made of a high temperature alloy and an array of collapsible support means wherein the container is capable of withstanding temperature necessary to oxidize the zirconium-based cladding and having sufficient ductility to maintain integrity when collapsed under pressure. The support means is also capable of maintaining their integrity at temperature necessary to oxide the zirconium-based cladding. The process container also has means to introduce and remove fluids to and from the container.

  10. Report on dynamic analysis of seismic isolated building of utility facility in Tokai Reprocessing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Uryu, Mitsuru; Shinohara, Takaharu; Yamazaki, Toshihiko; Nakayama, Kazuhiko; Sakaguchi, Shinobu; Kondo, Toshinari; Hosoya, Hisashi

    1998-03-01

    Building of utility facility in Tokai Reprocessing Plant is planned to adopt a seismic isolated structure using seismic isolators comprising of laminated rubber and lead damper. In this report, in addition to a reference earthquake motion for the conventional earthquake resistant structure (Osaki`s method) adapted to nuclear facilities with high importance in earthquake resistance, a dynamic analysis method of building for the reference earthquake motion (various long period earthquake motion estimation methods) for seismic isolated structure containing its own period (about 3 sec. by equalized own period) of the building was described. (G.K.)

  11. Prolonged Exposure versus Eye Movement Desensitization and Reprocessing (EMDR) for PTSD rape victims.

    Science.gov (United States)

    Rothbaum, Barbara Olasov; Astin, Millie C; Marsteller, Fred

    2005-12-01

    This controlled study evaluated the relative efficacy of Prolonged Exposure (PE) and Eye Movement Desensitization and Reprocessing (EMDR) compared to a no-treatment wait-list control (WAIT) in the treatment of PTSD in adult female rape victims (n = 74). Improvement in PTSD as assessed by blind independent assessors, depression, dissociation, and state anxiety was significantly greater in both the PE and EMDR group than the WAIT group (n = 20 completers per group). PE and EMDR did not differ significantly for change from baseline to either posttreatment or 6-month follow-up measurement for any quantitative scale.

  12. Report on the NGS3 Working Group on Safeguards by Design For Aqueous Reprocessing Plants

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, Shirley J.; Ehinger, Michael; Schanfein, Mark

    2011-02-01

    The objective of the Working Group on SBD for Aqueous Reprocessing Facilities was to provide recommendations, for facility operators and designers, which would aid in the coordination and integration of nuclear material accountancy and the safeguards requirements of all concerned parties - operators, state/regional authorities, and the IAEA. The recommendations, which are to be provided to the IAEA, are intended to assist in optimizing facility design and operating parameters to ensure the safeguardability of the facility while minimizing impact on the operations. The one day Working Group session addressed a wide range of design and operating topics.

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

    Energy Technology Data Exchange (ETDEWEB)

    Van Hecke, K.; Goethals, P.

    2006-07-15

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

  14. The Development of a Quality Management Framework for Evaluating Medical Device Reprocessing Practice in Healthcare Facilities.

    Science.gov (United States)

    Lorv, Bailey; Horodyski, Robin; Welton, Cynthia; Vail, John; Simonetto, Luca; Jokanovic, Danilo; Sharma, Richa; Mahoney, Angela Rea; Savoy-Bird, Shay; Bains, Shalu

    2017-01-01

    There is increasing awareness of the importance of medical device reprocessing (MDR) for the provision of safe patient care. Although industry service standards are available to guide MDR practices, there remains a lack of published key performance indicators (KPIs) and targets that are necessary to evaluate MDR quality for feedback and improvement. This article outlines the development of an initial framework that builds on established guidelines and includes service standards, KPIs and targets for evaluating MDR operations. This framework can support healthcare facilities in strengthening existing practices and enables a platform for collaboration towards better MDR performance management.

  15. XMM-Newton On-demand Reprocessing Using SaaS Technology

    Science.gov (United States)

    Ibarra, A.; Fajersztejn, N.; Loiseau, N.; Gabriel, C.

    2014-05-01

    We present here the architectural design of the new on-the-fly reprocessing capabilities that will be soon developed and implemented in the new XMM-Newton Science Operation Centre. The inclusion of processing capabilities into the archive, as we plan, will be possible thanks to the recent refurbishment of the XMM-Newton science archive, its alignment with the latest web technologies and the XMM-Newton Remote Interface for Science Analysis (RISA), a revolutionary idea of providing processing capabilities through internet services.

  16. Oil condition sensor. Interim report; Oelzustandssensor. Zwischenbericht

    Energy Technology Data Exchange (ETDEWEB)

    Hartwig, S.; Jaegle, M. [Fraunhofer-Inst. fuer Physikalische Messtechnik, Freiburg (Germany); Rademacher, S.; Schultheis, W. [BEDIA, Leinburg (Germany)

    2003-07-01

    In the summer of 2000 the Fraunhofer Institute for physical measuring technology was tasked by the FW with a study to evaluate various measurement principles for the development of oil condition sensors. In the frame of this study, four new sensor principles were proposed for the use in engine oil. Apart from an optical measurement method (online-ATR -spectroscopy) the measurement of sensitive material - in particular metal oxides and zeolites - within the engine oil as well as a method for the determination of electrode transition resistances, which falsify the measure values, were tested. The last method has been adapted from the field of microelectronics (TLM approach, transmission line model). In the frame of the current project ''Oil condition sensor'' the feasibility of these approaches is supposed to be tested. The plan is to construct sensors for these four measurement principles, to manufacture them and to carry out the measurements. A measurement stand was especially set-up to for the last purpose of this project, which allows adjusting the operating conditions within the engine in terms of pressure, flow and temperature course as realistic as possible. This interim report provides an overview of the results, which have been obtained so far. (orig.) [German] In einer von der FW in Auftrag gegebenen Studie wurde das Fraunhofer-Institut fuer Physikalische Messtechnik im Sommer 2000 beauftragt, verschiedene Messprinzipien fuer die Entwicklung eines Oelzustandssensors zu evaluieren. Als Ergebnis wurden im Rahmen dieser Studie vier fuer den Einsatz im Motoroel neuartige Sensorprinzipien vorgeschlagen. Neben einem optischen Messverfahren (online-ATR-Spektroskopie) waren dies die Vermessung sensitiver Materialien - insbesondere Metalloxide und Zeolithe - im Motoroel, sowie ein aus der Mikroelektronik adaptiertes Verfahren zur Bestimmung von messwertverfaelschenden Elektrodenuebergangswiderstaenden (TLM-Ansatz, Transmission-Line Model). Im

  17. Interim Project Financing in the Nigerian Construction Industry ...

    African Journals Online (AJOL)

    Out of the 47 variables identified through a structured survey, that can adversely affect the construction industry in Nigeria, “the difficulties in securing credit for interim construction finance on reasonable terms”, is ranked as the 6th most important factor, while “client's unwillingness to pay for advance for mobilization and ...

  18. Single-shell tank interim stabilization project plan

    Energy Technology Data Exchange (ETDEWEB)

    Ross, W.E.

    1998-05-11

    This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline.

  19. Rosiglitazone evaluated for cardiovascular outcomes--an interim analysis

    DEFF Research Database (Denmark)

    Home, Philip D; Pocock, Stuart J; Beck-Nielsen, Henning

    2007-01-01

    BACKGROUND: A recent meta-analysis raised concern regarding an increased risk of myocardial infarction and death from cardiovascular causes associated with rosiglitazone treatment of type 2 diabetes. METHODS: We conducted an unplanned interim analysis of a randomized, multicenter, open-label, non......BACKGROUND: A recent meta-analysis raised concern regarding an increased risk of myocardial infarction and death from cardiovascular causes associated with rosiglitazone treatment of type 2 diabetes. METHODS: We conducted an unplanned interim analysis of a randomized, multicenter, open...... group). The primary end point was hospitalization or death from cardiovascular causes. RESULTS: Because the mean follow-up was only 3.75 years, our interim analysis had limited statistical power to detect treatment differences. A total of 217 patients in the rosiglitazone group and 202 patients...... group and the control group regarding myocardial infarction and death from cardiovascular causes or any cause. There were more patients with heart failure in the rosiglitazone group than in the control group (hazard ratio, 2.15; 95% CI, 1.30 to 3.57). CONCLUSIONS: Our interim findings from this ongoing...

  20. Effectiveness Monitoring Report, MWMF Tritium Phytoremediation Interim Measures.

    Energy Technology Data Exchange (ETDEWEB)

    Hitchcock, Dan; Blake, John, I.

    2003-02-10

    This report describes and presents the results of monitoring activities during irrigation operations for the calendar year 2001 of the MWMF Interim Measures Tritium Phytoremediation Project. The purpose of this effectiveness monitoring report is to provide the information on instrument performance, analysis of CY2001 measurements, and critical relationships needed to manage irrigation operations, estimate efficiency and validate the water and tritium balance model.

  1. Evaluation of hardness and wear resistance of interim restorative materials.

    Science.gov (United States)

    Savabi, Omid; Nejatidanesh, Farahnaz; Fathi, Mohamad Hossein; Navabi, Amir Arsalan; Savabi, Ghazal

    2013-03-01

    The interim restorative materials should have certain mechanical properties to withstand in oral cavity. The aim of this study was to evaluate the hardness and wear resistance of interim restorative materials. Fifteen identical rectangular shape specimens with dimensions of 2 mm × 10 mm × 30 mm were made from 7 interim materials (TempSpan, Protemp 3 Garant, Revotek, Unifast LC, Tempron, Duralay, and Acropars). The Vickers hardness and abrasive wear of specimens were tested in dry conditions and after 1 week storage in artificial saliva. The depth of wear was measured using surface roughness inspection device. Data were subjected to Kruskal-Wallis and Mann-Whitney tests. The Pearson correlation coefficient was used to determine the relationship between hardness and wear (α =0.05). TempSpan had the highest hardness. The wear resistance of TempSpan (in dry condition) and Revotek (after conditioning in artificial saliva) was significantly higher (P materials (P = 0.281, r = -0.31). Hardness and wear resistance of interim resins are material related rather than category specified.

  2. Single Shell Tank (SST) Interim Stabilization Project Plan

    Energy Technology Data Exchange (ETDEWEB)

    VLADIMIROFF, D.T.; BOYLES, V.C.

    2000-05-22

    This project plan establishes the management framework for the conduct of the CHG Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organization structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline.

  3. Iodine Pathways and Off-Gas Stream Characteristics for Aqueous Reprocessing Plants – A Literature Survey and Assessment

    Energy Technology Data Exchange (ETDEWEB)

    R. T. Jubin; D. M. Strachan; N. R. Soelberg

    2013-09-01

    Used nuclear fuel is currently being reprocessed in only a few countries, notably France, England, Japan, and Russia. The need to control emissions of the gaseous radionuclides to the air during nuclear fuel reprocessing has already been reported for the entire plant. But since the gaseous radionuclides can partition to various different reprocessing off-gas streams, for example, from the head end, dissolver, vessel, cell, and melter, an understanding of each of these streams is critical. These off-gas streams have different flow rates and compositions and could have different gaseous radionuclide control requirements, depending on how the gaseous radionuclides partition. This report reviews the available literature to summarize specific engineering data on the flow rates, forms of the volatile radionuclides in off-gas streams, distributions of these radionuclides in these streams, and temperatures of these streams. This document contains an extensive bibliography of the information contained in the open literature.

  4. Selective absorption pilot plant for decontamination of fuel reprocessing plant off-gas

    Energy Technology Data Exchange (ETDEWEB)

    Stephenson, M.J.; Eby, R.S.; Huffstetler, V.C.

    1977-10-01

    A fluorocarbon-based selective absorption process for removing krypton-85, carbon-14, and radon-222 from the off-gas of conventional light water and advanced reactor fuel reprocessing plants is being developed at the Oak Ridge Gaseous Diffusion Plant in conjunction with fuel recycle work at the Oak Ridge National Laboratory and at the Savannah River Laboratory. The process is characterized by an especially high tolerance for many other reprocessing plant off-gas components. This report presents detailed drawings and descriptions of the second generation development pilot plant as it has evolved after three years of operation. The test facility is designed on the basis of removing 99% of the feed gas krypton and 99.9% of the carbon and radon, and can handle a nominal 15 scfm (425 slm) of contaminated gas at pressures from 100 to 600 psig (7.0 to 42.2 kg/cm/sup 2/) and temperatures from minus 45 to plus 25/sup 0/F (-43 to -4/sup 0/C). Part of the development program is devoted to identifying flowsheet options and simplifications that lead to an even more economical and reliable process. Two of these applicative flowsheets are discussed.

  5. Available reprocessing and recycling services for research reactor spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Tozser, Sandor Miklos; Adelfang, Pablo; Bradley, Ed [International Atomic Energy Agency, Vienna (Austria); Budu, Madalina [SOSNY Research and Development Company, Moscow (Russian Federation); Chiguer, Mustapha [AREVA, Paris (France)

    2015-05-15

    International activities in the back-end of the research reactor (RR) fuel cycle have so far been dominated by the programmes of acceptance of highly-enriched uranium (HEU) spent nuclear fuel (SNF) by the country where it was originally enriched. These programmes will soon have achieved their goals and the SNF take-back programmes will cease. However, the needs of the nuclear community dictate that the majority of the research reactors continue to operate using low enriched uranium (LEU) fuel in order to meet the varied mission objectives. As a result, inventories of LEU SNF will continue to be created and the back-end solution of RR SNF remains a critical issue. In view of this fact, the IAEA, based on the experience gained during the decade of international cooperation in supporting the objectives of the HEU take-back programmes, will draw up a report presenting available reprocessing and recycling services for research reactor spent nuclear fuel. This paper gives an overview of the guiding document which will address all aspects of Reprocessing and Recycling Services for RR SNF, including an overview of solutions, decision making support, service suppliers, conditions (prerequisites, options, etc.), services offered by the managerial and logistics support providers with a focus on available transport packages and applicable transport modes.

  6. Reassessment of protective design of Rokkasho reprocessing facility against aircraft crash

    Energy Technology Data Exchange (ETDEWEB)

    Matsuoka, S.; Fujinaga, H.; Takebe, K. [Japan Nuclear Fuel Co. Ltd., Aomori-shi, Aomori-ken (Japan); Shirasaka, Y.; Nukui, Y.; Endoh, M. [Japan Nuclear Fuel Co. Ltd., Tokyo (Japan)

    1998-07-01

    About 10 km south of the Rokkasho reprocessing site, there is a field where Japan Air Self-Defense Force and US Air Force fighters carry out gunnery and bombing practice around 40,000 times a year. Although an aircraft crash accident into the reprocessing facility seems extremely unlikely, the facility is designed to be protected by outermost walls and roofs. In the original protective design we took into account F-16 fighter's excessive weight of 20 tons and striking velocity of 150 m/s, anticipating a future change in the model of fighter. In fact last year the Self-Defense Force introduced F-4EJ as a substitute for overage F-1, which is heavier (and larger) than F-16. In response to the Science and Technology Agency's instructions, we conducted the reassessment to verify the safety of the original design with respect to a postulated F-4EJ crash. The total weight of 22 tons was used on the basis of our observation of outer equipment during practices, with best gliding velocity of 155 m/s. The reassessment confirmed that, even under the postulated F-4EJ crash conditions, safety is secured. A report of this reassessment was submitted to the Science and Technology Agency and the Agency accepted the appropriateness of the result. (author)

  7. Eye movement desensitisation and reprocessing therapy v. stabilisation as usual for refugees: randomised controlled trial.

    Science.gov (United States)

    Ter Heide, F Jackie June; Mooren, Trudy M; van de Schoot, Rens; de Jongh, Ad; Kleber, Rolf J

    2016-10-01

    Eye movement desensitisation and reprocessing (EMDR) therapy is a first-line treatment for adults with post-traumatic stress disorder (PTSD). Some clinicians argue that with refugees, directly targeting traumatic memories through EMDR may be harmful or ineffective. To determine the safety and efficacy of EMDR in adult refugees with PTSD (trial registration: ISRCTN20310201). In total, 72 refugees referred for specialised treatment were randomly assigned to 12 h of EMDR (3×60 min planning/preparation followed by 6×90 min desensitisation/reprocessing) or 12 h (12×60 min) of stabilisation. The Clinician-Administered PTSD Scale (CAPS) and Harvard Trauma Questionnaire (HTQ) were primary outcome measures. Intention-to-treat analyses found no differences in safety (one severe adverse event in the stabilisation condition only) or efficacy (effect sizes: CAPS -0.04 and HTQ 0.20) between the two conditions. Directly targeting traumatic memories through 12 h of EMDR in refugee patients needing specialised treatment is safe, but is only of limited efficacy. © The Royal College of Psychiatrists 2016.

  8. Contaminants of the bismuth phosphate process as signifiers of nuclear reprocessing history.

    Energy Technology Data Exchange (ETDEWEB)

    Schwantes, Jon M.; Sweet, Lucas E.

    2012-10-01

    Reagents used in spent nuclear fuel recycling impart unique contaminant patterns into the product stream of the process. Efforts are underway at Pacific Northwest National Laboratory to characterize and understand the relationship between these patterns and the process that created them. A main challenge to this effort, recycling processes that were employed at the Hanford site from 1944-1989 have been retired for decades. This precludes direct measurements of the contaminant patterns that propagate within product streams of these facilities. In the absence of any operating recycling facilities at Hanford, we have taken a multipronged approach to cataloging contaminants of U.S. reprocessing activities using: (1) historical records summarizing contaminants within the final Pu metal button product of these facilities; (2) samples of opportunity that represent intermediate products of these processes; and (3) lab-scale experiments and model simulations designed to replicate contaminant patterns at each stage of nuclear fuel reprocessing. This report provides a summary of the progress and results from Fiscal Year (April 1, 2010-September 30) 2011.

  9. Reprogrammable, Reprocessible, and Self-Healable Liquid Crystal Elastomer with Exchangeable Disulfide Bonds.

    Science.gov (United States)

    Wang, Zhijian; Tian, Hongmiao; He, Qiguang; Cai, Shengqiang

    2017-09-27

    A liquid crystal elastomer (LCE) can be regarded as an integration of mesogenic molecules into a polymer network. The LCE can generate large mechanical actuation when subjected to various external stimuli. Recently, it has been extensively explored to make artificial muscle and multifunctional devices. However, in the commonly adopted two-step crosslinking method for synthesizing monodomain LCEs, the LCE needs to be well-cross-linked in the first step before stretching, which increases the disorder of mesogenic molecules in the final state of the LCE and makes it very challenging to fabricate the LCE of complex shapes. In this article, we developed a new LCE with disulfide bonds, which can be reprogrammed from the polydomain state to the monodomain state either through heating or UV illumination, owing to the rearrangement of the polymer network induced by the metathesis reaction of disulfide bonds. In addition, the newly developed LCE can be easily reprocessed and self-healed by heating. Because of the excellent reprogrammability as well as reprocessability of the LCE, we further fabricated LCE-based active micropillar arrays through robust imprint lithography, which can be hardly achieved using the LCE prepared previously. Finally, we showed an excellent long-term durability of the newly developed LCE.

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

    Energy Technology Data Exchange (ETDEWEB)

    Susan Stacy; Julie Braun

    2006-12-01

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

  11. Aanbevelingen voor succesvol interim-management : Welke handelen van de interim-manager leidt tot tevredenheid van zijn opdrachtgever?

    NARCIS (Netherlands)

    Schaveling, J.; Muijen, van J.J.; Montfort, van K.

    2010-01-01

    Wat maakt de opdrachtgever van interim-managers tevreden? In de literatuur worden verschillende factoren genoemd en ook de betrokkenen zelf hebben er ideeën over, maar welk gedrag doet er nu werkelijk toe? Op basis van een empirisch onderzoek wordt deze vraag beantwoord. Een literatuurstudie vormt

  12. SLIGHTLY IRRADIATED FUEL (SIF) INTERIM DISPOSITION PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    NORTON SH

    2010-02-23

    CH2M HILL Plateau Remediation Company (CH2M HILL PRC) is proud to submit the Slightly Irradiated Fuel (SIF) Interim Disposition Project for consideration by the Project Management Institute as Project of the Year for 2010. The SIF Project was a set of six interrelated sub-projects that delivered unique stand-alone outcomes, which, when integrated, provided a comprehensive and compliant system for storing high risk special nuclear materials. The scope of the six sub-projects included the design, construction, testing, and turnover of the facilities and equipment, which would provide safe, secure, and compliant Special Nuclear Material (SNM) storage capabilities for the SIF material. The project encompassed a broad range of activities, including the following: Five buildings/structures removed, relocated, or built; Two buildings renovated; Structural barriers, fencing, and heavy gates installed; New roadways and parking lots built; Multiple detection and assessment systems installed; New and expanded communication systems developed; Multimedia recording devices added; and A new control room to monitor all materials and systems built. Project challenges were numerous and included the following: An aggressive 17-month schedule to support the high-profile Plutonium Finishing Plant (PFP) decommissioning; Company/contractor changeovers that affected each and every project team member; Project requirements that continually evolved during design and construction due to the performance- and outcome-based nature ofthe security objectives; and Restrictions imposed on all communications due to the sensitive nature of the projects In spite of the significant challenges, the project was delivered on schedule and $2 million under budget, which became a special source of pride that bonded the team. For years, the SIF had been stored at the central Hanford PFP. Because of the weapons-grade piutonium produced and stored there, the PFP had some of the tightest security on the Hanford

  13. Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 3. Alternatives for interim storage and transportation

    Energy Technology Data Exchange (ETDEWEB)

    1976-05-01

    Volume III of the five-volume report contains information on alternatives for interim storage and transportation. Section titles are: interim storage of spent fuel elements; interim storage of chop-leach fuel bundle residues; tank storage of high-level liquid waste; interim storage of solid non-high-level wastes; interim storage of solidified high-level waste; and, transportation alternatives. (JGB)

  14. 10 CFR Appendix B to Part 50 - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants B Appendix B to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC...: reactor physics, stress, thermal, hydraulic, and accident analyses; compatibility of materials...

  15. The Efficacy of Eye Movement Desensitization and Reprocessing Therapy Technique in the Treatment of Test Anxiety of College Students.

    Science.gov (United States)

    Enright, Matthew; Baldo, Tracy D.; Wykes, Scott D.

    2000-01-01

    Explores the efficacy of eye movement desensitization and reprocessing (EMDR) in the treatment of test anxiety. Thirty-five college students with test anxiety were assigned to either a treatment or delayed treatment control group. EMDR was shown to be effective in reducing overall test anxiety as well as "emotionality" and…

  16. Longitudinal assessment of reprocessing effectiveness for colonoscopes and gastroscopes: Results of visual inspections, biochemical markers, and microbial cultures.

    Science.gov (United States)

    Ofstead, Cori L; Wetzler, Harry P; Heymann, Otis L; Johnson, Ellen A; Eiland, John E; Shaw, Michael J

    2017-02-01

    Flexible endoscopes are currently reused following cleaning and high-level disinfection. Contamination has been found on endoscopes, and infections have been linked to gastrointestinal, respiratory, and urologic endoscopes. This longitudinal study involved visual inspections with a borescope, microbial cultures, and biochemical tests for protein and adenosine triphosphate to identify endoscopes in need of further cleaning or maintenance. Three assessments were conducted over a 7-month period. Control group endoscopes reprocessed using customary practices were compared with intervention group endoscopes subjected to more rigorous reprocessing. At final assessment, all endoscopes (N = 20) had visible irregularities. Researchers observed fluid (95%), discoloration, and debris in channels. Of 12 (60%) endoscopes with microbial growth, 4 had no growth until after 48 hours. There were no significant differences in culture results by study group, assessment period, or endoscope type. Similar proportions of control and intervention endoscopes (~20%) exceeded postcleaning biochemical test benchmarks. Adenosine triphosphate levels were higher for gastroscopes than colonoscopes (P = .014). Eighty-five percent of endoscopes required repair due to findings. More rigorous reprocessing was not consistently effective. Seven-day incubation allowed identification of slow-growing microbes. These findings bolster the need for routine visual inspection and cleaning verification tests recommended in new reprocessing guidelines. Copyright © 2017 Association for Professionals in Infection Control and Epidemiology, Inc. Published by Elsevier Inc. All rights reserved.

  17. Reprocessing of Shallow Seismic Reflection Data to Image Faults Near a Hazardous Waste Site on the Oak Ridge Reservation, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Doll, W.E.

    1997-12-31

    Shallow seismic reflection data from Bear Creek Valley on the Oak Ridge Reservation demonstrates that spectral balancing and tomographic refraction statics can be important processing tools for shallow seismic data. At this site, reprocessing of data which had previously yielded no usable CMP stacked sections was successful after application of these processing techniques.

  18. REPROCESSING OF SHALLOW SEISMIC REFLECTION DATA TO IMAGE FAULTS NEAR A HAZARDOUS WASTE SITE ON THE OAK RIDGE RESERVATION, TENNESSEE

    Energy Technology Data Exchange (ETDEWEB)

    DOLL, W.E.

    1997-12-30

    Shallow seismic reflection data from Bear Creek Valley on the Oak Ridge Reservation demonstrates that spectral balancing and tomographic refraction statics can be important processing tools for shallow seismic data. At this site, reprocessing of data which had previously yielded no useable CMP stacked sections was successful after application of these processing techniques.

  19. Brief eclectic psychotherapy v. eye movement desensitisation and reprocessing therapy for post-traumatic stress disorder: randomised controlled trial

    NARCIS (Netherlands)

    Nijdam, M.J.; Gersons, B.P.R.; Reitsma, J.B.; de Jongh, A.; Ollf, M.

    2012-01-01

    Background Trauma-focused cognitive-behavioural therapy (CBT) and eye movement desensitisation and reprocessing therapy (EMDR) are efficacious treatments for post-traumatic stress disorder (PTSD), but few studies have directly compared them using well-powered designs and few have investigated

  20. Reprocessing of Lunar occultations observations carried out in Uzbekistan during 1882-1996

    Science.gov (United States)

    Muminov, M. M.; Kazantseva, L. V.; Ehgamberdiev, Sh. A.; Kahhorov, B. B.; Andruk, V. M.

    A unified database of ILOC and Kyiv Observatory by selected locations on the territory of Uzbekistan was presented. Reprocessing of observations using the semi-analytical ephemeris of lunar motion VSOP87A with obtained correction for the relief of the marginal zone according to Watts’s map was carried out. Observation of ocultations was carried out by the staff of Tashkent Observatory in Uzbekistan from the end of the XIX century. The observations are planned to be continued with 48 cm telescope of Maidanak Observatory. Selected database (1145 results of observations) was obtained during a long period (1882-1993 AD), but distribution of observation over that period is not uniform. 4 periods of an active observation 1882-1890, 1927-1938, 1948-1972 and 1993 can be noted.

  1. Development of spent fuel reprocessing by super-critical fluid (Development of super DIREX method)

    Energy Technology Data Exchange (ETDEWEB)

    Shimada, Takashi; Ogumo, Shin-ya; Mori, Yukihide; Ishihara, Nobuo [Mitsubishi Heavy Industries Ltd., Tokyo (Japan); Kosaka, Yuji; Ito, Kunihiro [Nuclear Development Corp., Tokai, Ibaraki (Japan)

    2000-10-01

    Supercritical fluid DIRect EXtraction (Super-DIREX) Method has been developed, and it is the technique of extracting Uranium and Plutonium elements directly from spent fuel oxides by supercritical CO{sub 2} containing HNO{sub 3}-tributylphosphate (TBP) complex (at 313K-333K and 10-20MPa). From this study, it is concluded that the reprocessing system adopting Super-DIREX Method is more simple and unexpensive than PUREX system. The experiment was carried out by using test piece of unirradiated Uranium oxide included imitative fission product (FP) elements oxides, and the results showed that Uranium could be extracted in separating from FP elements at 313K and 12MPa and that one step extraction by Super DIREX Method could get more than 100 of decontamination factor (DE) of the FP elements. (author)

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

    Science.gov (United States)

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

    2013-11-05

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-10-01

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

  5. Experience with the custom-developed ATLAS Offline Trigger Monitoring Framework and Reprocessing Infrastructure

    CERN Document Server

    Bartsch, V

    2012-01-01

    After about two years of data taking with the ATLAS detector manifold experience with the custom-developed trigger monitoring and reprocessing infrastructure could be collected. The trigger monitoring can be roughly divided into online and offline monitoring. The online monitoring calculates and displays all rates at every level of the trigger and evaluates up to 3000 data quality histograms. The physics analysis relevant data quality information is being checked and recorded automatically. The offline trigger monitoring provides information depending of the physics motivated different trigger streams after a run has finished. Experts are checking the information being guided by the assessment of algorithms checking the current histograms with a reference. The experts are recording their assessment in a so-called data quality defects which are used to select data for physics analysis. In the first half of 2011 about three percent of all data had an intolerable defect resulting from the ATLAS trigger system. T...

  6. Assessment of lead tellurite glass for immobilizing electrochemical salt wastes from used nuclear fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Riley, Brian J.; Kroll, Jared O.; Peterson, Jacob A.; Pierce, David A.; Ebert, William L.; Williams, Benjamin D.; Snyder, Michelle M. V.; Frank, Steven M.; George, Jaime L.; Kruska, Karen

    2017-11-01

    This paper provides an overview of research evaluating the use of lead tellurite glass as a waste form for salt wastes from electrochemical reprocessing of used nuclear fuel. The efficacy of using lead tellurite glass to immobilize three different salt compositions was evaluated: a LiCl-Li2O oxide reduction salt containing fission products from oxide fuel, a LiCl-KCl eutectic salt containing fission products from metallic fuel, and SrCl2. Physical and chemical properties of glasses made with these salts were characterized with X-ray diffraction, bulk density measurements, differential thermal analysis, chemical durability tests, scanning and transmission electron microscopies, and energy-dispersive X-ray spectroscopy. These glasses were found to accommodate high salt concentrations and have high densities, but further development is needed to improve chemical durability. (C) 2017 Published by Elsevier B.V.

  7. Reprocessing of Soft X-ray Emission Lines in Black Hole Accretion Disks

    Energy Technology Data Exchange (ETDEWEB)

    Mauche, C W; Liedahl, D A; Mathiesen, B F; Jimenez-Garate, M A; Raymond, J C

    2003-10-17

    By means of a Monte Carlo code that accounts for Compton scattering and photoabsorption followed by recombination, we have investigated the radiation transfer of Ly{alpha}, He{alpha}, and recombination continua photons of H- and He-like C, N, O, and Ne produced in the photoionized atmosphere of a relativistic black hole accretion disk. We find that photoelectric opacity causes significant attenuation of photons with energies above the O VIII K-edge; that the conversion efficiencies of these photons into lower-energy lines and recombination continua are high; and that accounting for this reprocessing significantly (by factors of 21% to 105%) increases the flux of the Ly{alpha} and He{alpha} emission lines of H- and He-like C and O escaping the disk atmosphere.

  8. Eye movement desensitization and reprocessing therapy for personality disorders in older adults?

    Science.gov (United States)

    Gielkens, E M J; Sobczak, S; Van Alphen, S P J

    2016-10-01

    Eye Movement Desensitization and Reprocessing (EMDR) is a kind of psychotherapy, which is growing in popularity, particularly for treatment of post-traumatic stress disorder (PTSD). When Shapiro first introduced EMDR in 1989, it was approached as a controversial treatment because of lack of evidence. However, nowadays there is growing evidence for EMDR efficacy in PTSD (Mc Guire et al., 2014) and EMDR is recommended by international and national treatment guidelines for PTSD. Moreover, EMDR is also used for the treatment of other anxiety disorders, such as panic disorders (De Jongh et al., 2002). Furthermore, research continues on effects of EMDR in addiction, somatoform disorders and psychosis. So far, there is no empirical research on the efficacy of EMDR treatment in older adults.

  9. Thoria-based nuclear fuels thermophysical and thermodynamic properties, fabrication, reprocessing, and waste management

    CERN Document Server

    Bharadwaj, S R

    2013-01-01

    This book presents the state of the art on thermophysical and thermochemical properties, fabrication methodologies, irradiation behaviours, fuel reprocessing procedures, and aspects of waste management for oxide fuels in general and for thoria-based fuels in particular. The book covers all the essential features involved in the development of and working with nuclear technology. With the help of key databases, many of which were created by the authors, information is presented in the form of tables, figures, schematic diagrams and flow sheets, and photographs. This information will be useful for scientists and engineers working in the nuclear field, particularly for design and simulation, and for establishing the technology. One special feature is the inclusion of the latest information on thoria-based fuels, especially on the use of thorium in power generation, as it has less proliferation potential for nuclear weapons. Given its natural abundance, thorium offers a future alternative to uranium fuels in nuc...

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

    Science.gov (United States)

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

    2017-10-01

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

  11. Cognitive Behavioral Therapy and Eye Movement Desensitization and Reprocessing in Posttraumatic Stress Disorder

    Directory of Open Access Journals (Sweden)

    Filiz Ýzci

    2017-04-01

    Cognitive behavioral therapy (CBT and eye movement desensitization and reprocessing (EMDR are from the most common treatment methods that have begun to be used in trauma patients in recent years. With the increased applicability of these treatment models in Post Traumatic Stress Disorder (PTSD and on other trauma patients success of treatment rate in trauma patients is increasing steadily. In this article, it is tried to review the application forms and effects of EMDR and CBT methods among patients with PTSD which is a commonly seen trauma disorder. It is aimed in this article to emphasize the importance of CBT and a newly treatment EMDR in post-traumatic acute and chronic disorders with multiple psychiatric symptoms. [JCBPR 2017; 6(1.000: 31-38

  12. Eye Movement Desensitization Reprocessing as Treatment for Chronic Pain Syndromes: A Literature Review.

    Science.gov (United States)

    Tefft, Angela J; Jordan, Irma O

    2016-04-05

    Chronic pain is public health problem in the United States, costing upwards of $560 to $635 billion annually. Guidelines consistently recommend psychological treatment for chronic pain. Eye movement desensitization reprocessing (EMDR) psychotherapy may provide an alternate approach to treating chronic pain. Review of literature to evaluate the effectiveness of EMDR in the treatment of chronic pain. A literature search of seven databases was conducted to find relevant studies addressing the use of EMDR for chronic pain. Most studies reported improvement in pain and psychological indices with EMDR. Because most literature reported case studies, the results have limited generalizability. However, for clients who suffer from chronic pain, EMDR is a reasonable treatment alternative. © The Author(s) 2016.

  13. Symposium on the reprocessing of irradiated fuels. Book 3, Session V

    Energy Technology Data Exchange (ETDEWEB)

    None

    1958-12-31

    Book three of this conference has a single-focused session V entitled Engineering and Economics, with 16 papers. The session is concerned with several phases of chemical reprocessing of fuels which are of a general nature. Hot labs, radiochemical analytical facilities, and high level development cells are described. Dissolution equipment, contactors, flow generation, measurement, and control equipment, samplers, connectors, carriers, valves, filters, and hydroclones are described and discussed. Papers are included on: radiation safety, chemical safety, radiochemical plant operating experience in the U.S., and heavy element isotopic buildup. The general economics of solvent extraction processing is discussed, and capital and operating costs for several U. S. plants given. The Atomic Energy Commission's chemical processing programs and administration are evaluated and the services offered and charges therefore are listed.

  14. Science and pseudoscience in the development of eye movement desensitization and reprocessing: implications for clinical psychology.

    Science.gov (United States)

    Herbert, J D; Lilienfeld, S O; Lohr, J M; Montgomery, R W; O'Donohue, W T; Rosen, G M; Tolin, D F

    2000-11-01

    The enormous popularity recently achieved by Eye Movement Desensitization and Reprocessing (EMDR) as a treatment for anxiety disorders appears to have greatly outstripped the evidence for its efficacy from controlled research studies. The disparity raises disturbing questions concerning EMDR's aggressive commercial promotion and its rapid acceptance among practitioners. In this article, we: (1) summarize the evidence concerning EMDR's efficacy; (2) describe the dissemination and promotion of EMDR; (3) delineate the features of pseudoscience and explicate their relevance to EMDR; (4) describe the pseudoscientific marketing practices used to promote EMDR; (5) analyze factors contributing to the acceptance of EMDR by professional psychologists; and (6) discuss practical considerations for professional psychologists regarding the adoption of EMDR into professional practice. We argue that EMDR provides an excellent vehicle for illustrating the differences between scientific and pseudoscientific therapeutic techniques. Such distinctions are of critical importance for clinical psychologists who intend to base their practice on the best available research.

  15. Cleaning of outgoing air at companies reprocessing residual material; Abluftreinigung fuer Reststoffverwertungsbetriebe

    Energy Technology Data Exchange (ETDEWEB)

    Rafflenbeul, R. [Rafflenbeul und Partner, Frankfurt am Main (Germany)

    1996-05-01

    With the extension of the federal act for the protection against nuisances to companies reprocessing residual material and, concomitantly, their obligation from 1997 to obtain a licence, outgoing-air cleaning systems for the removal of odorous nuisances will become indispensable. Because of want of information on the part of many operators, scrubbers, and in part even air cleaning systems with after-burning, are still frequently used. The article gives an overview of the different techniques for cleaning outgoing air such as scrubbers, biological methods as well as plasma and bioplasma techniques. (orig./SR) [Deutsch] Mit der Neueingliederung der Reststoffverwertungsbetriebe in das Bundesimmissionschutz-Gesetz, und hiermit verknuepft der ab 1997 erforderlichen Genehmigungspflicht, werden Abluftreinigungsverfahren zur Geruchsbeseitigung unumgehbar. Aus Unkenntnis der Betreiber gelangen immer noch Waschverfahren, zum Teil sogar nachverbrennend wirkende Abluftreinigungssysteme, zur Anwendung. Es wird ein Ueberblick ueber die verschiedenen Abluftreinigungsverfahren wie Waescher, biologische Verfahren sowie Plasma- und Bioplasmaverfahren gegeben. (orig./SR)

  16. Plutonium Finishing Plant. Interim plutonium stabilization engineering study

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-08-01

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

  17. The Role and Reprocessing of Attitudes in Fostering Employee Work Happiness: An Intervention Study

    Science.gov (United States)

    Williams, Paige; Kern, Margaret L.; Waters, Lea

    2017-01-01

    This intervention study examines the iterative reprocessing of explicit and implicit attitudes as the process underlying associations between positive employee attitudes (PsyCap), perception of positive organization culture (organizational virtuousness, OV), and work happiness. Using a quasi-experimental design, a group of school staff (N = 69) completed surveys at three time points. After the first assessment, the treatment group (n = 51) completed a positive psychology training intervention. Results suggest that employee PsyCap, OV, and work happiness are associated with one another through both implicit and explicit attitudes. Further, the Iterative-Reprocessing Model of attitudes (IRM) provides some insights into the processes underlying these associations. By examining the role and processes through which explicit and implicit attitudes relate to wellbeing at work, the study integrates theories on attitudes, positive organizational scholarship, positive organizational behavior and positive education. It is one of the first studies to apply the theory of the IRM to explain associations amongst PsyCap, OV and work happiness, and to test the IRM theory in a field-based setting. In applying attitude theory to wellbeing research, this study provides insights to mechanisms underlying workplace wellbeing that have not been previously examined and in doing so responds to calls for researchers to learn more about the mechanisms underlying wellbeing interventions. Further, it highlights the need to understand subconscious processes in future wellbeing research and to include implicit measures in positive psychology interventions measurement programs. Practically, this research calls attention to the importance of developing both the positive attitudes of employees and the organizational culture in developing employee work happiness. PMID:28154546

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-06-15

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

  19. Analysis of the Reuse of Uranium Recovered from the Reprocessing of Commercial LWR Spent Fuel

    Energy Technology Data Exchange (ETDEWEB)

    DelCul, Guillermo Daniel [ORNL; Trowbridge, Lee D [ORNL; Renier, John-Paul [ORNL; Ellis, Ronald James [ORNL; Williams, Kent Alan [ORNL; Spencer, Barry B [ORNL; Collins, Emory D [ORNL

    2009-02-01

    This report provides an analysis of the factors involved in the reuse of uranium recovered from commercial light-water-reactor (LWR) spent fuels (1) by reenrichment and recycling as fuel to LWRs and/or (2) by recycling directly as fuel to heavy-water-reactors (HWRs), such as the CANDU (registered trade name for the Canadian Deuterium Uranium Reactor). Reuse is an attractive alternative to the current Advanced Fuel Cycle Initiative (AFCI) Global Nuclear Energy Partnership (GNEP) baseline plan, which stores the reprocessed uranium (RU) for an uncertain future or attempts to dispose of it as 'greater-than-Class C' waste. Considering that the open fuel cycle currently deployed in the United States already creates a huge excess quantity of depleted uranium, the closed fuel cycle should enable the recycle of the major components of spent fuel, such as the uranium and the hazardous, long-lived transuranic (TRU) actinides, as well as the managed disposal of fission product wastes. Compared with the GNEP baseline scenario, the reuse of RU in the uranium fuel cycle has a number of potential advantages: (1) avoidance of purchase costs of 11-20% of the natural uranium feed; (2) avoidance of disposal costs for a large majority of the volume of spent fuel that is reprocessed; (3) avoidance of disposal costs for a portion of the depleted uranium from the enrichment step; (4) depending on the {sup 235}U assay of the RU, possible avoidance of separative work costs; and (5) a significant increase in the production of {sup 238}Pu due to the presence of {sup 236}U, which benefits somewhat the transmutation value of the plutonium and also provides some proliferation resistance.

  20. The Role and Reprocessing of Attitudes in Fostering Employee Work Happiness: An Intervention Study.

    Science.gov (United States)

    Williams, Paige; Kern, Margaret L; Waters, Lea

    2017-01-01

    This intervention study examines the iterative reprocessing of explicit and implicit attitudes as the process underlying associations between positive employee attitudes (PsyCap), perception of positive organization culture (organizational virtuousness, OV), and work happiness. Using a quasi-experimental design, a group of school staff (N = 69) completed surveys at three time points. After the first assessment, the treatment group (n = 51) completed a positive psychology training intervention. Results suggest that employee PsyCap, OV, and work happiness are associated with one another through both implicit and explicit attitudes. Further, the Iterative-Reprocessing Model of attitudes (IRM) provides some insights into the processes underlying these associations. By examining the role and processes through which explicit and implicit attitudes relate to wellbeing at work, the study integrates theories on attitudes, positive organizational scholarship, positive organizational behavior and positive education. It is one of the first studies to apply the theory of the IRM to explain associations amongst PsyCap, OV and work happiness, and to test the IRM theory in a field-based setting. In applying attitude theory to wellbeing research, this study provides insights to mechanisms underlying workplace wellbeing that have not been previously examined and in doing so responds to calls for researchers to learn more about the mechanisms underlying wellbeing interventions. Further, it highlights the need to understand subconscious processes in future wellbeing research and to include implicit measures in positive psychology interventions measurement programs. Practically, this research calls attention to the importance of developing both the positive attitudes of employees and the organizational culture in developing employee work happiness.

  1. Evaluation of the Healthy Schools Program: Part I. Interim Progress

    OpenAIRE

    Beam, Margaret; Ehrlich, Ginny; Donze Black, Jessica; Block, Audrey; Leviton, Laura C.

    2012-01-01

    Introduction Federal and state policies identify schools as a setting to prevent childhood obesity, but schools need better health-promoting strategies. The objective of this study was to evaluate interim progress in schools receiving hands-on training from the Healthy Schools Program, the nation's largest school-based program aimed at preventing childhood obesity. The 4-year program targets schools with predominantly low-income, African American, or Hispanic students. Methods In 2010 we asse...

  2. Method of preparing nuclear wastes for tansportation and interim storage

    Science.gov (United States)

    Bandyopadhyay, Gautam; Galvin, Thomas M.

    1984-01-01

    Nuclear waste is formed into a substantially water-insoluble solid for temporary storage and transportation by mixing the calcined waste with at least 10 weight percent powdered anhydrous sodium silicate to form a mixture and subjecting the mixture to a high humidity environment for a period of time sufficient to form cementitious bonds by chemical reaction. The method is suitable for preparing an interim waste form from dried high level radioactive wastes.

  3. Waste Encapsulation and Storage Facility interim operational safety requirements

    CERN Document Server

    Covey, L I

    2000-01-01

    The Interim Operational Safety Requirements (IOSRs) for the Waste Encapsulation and Storage Facility (WESF) define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt and inspection of cesium and strontium capsules from private irradiators; decontamination of the capsules and equipment; surveillance of the stored capsules; and maintenance activities. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological consequences below risk evaluation guidelines (EGs) are included.

  4. Interim Sanitary Landfill Groundwater Monitoring Report. 1997 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

    Eight wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Interim Sanitary Landfill at the Savannah River Site (SRS). These wells are sampled semiannually to comply with the South Carolina Department of Health and Environmental Control Modified Municipal Solid Waste Permit 025500-1120 (formerly dWP-087A) and as part of the SRS Groundwater Monitoring Program.

  5. Interim data report for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Vahlund, Fredrik [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden)

    2004-08-01

    This document is the interim data report in the project SR-Can. The purpose of the data report is to present input data, with uncertainty estimates, for the SR-Can assessment calculations. Besides input data, the report also describes the standardised procedures used when deriving the input data and the corresponding uncertainty estimates. However, in the present interim version of the report (written in the initial stage of the project when site characterisation has yet not been completed) the standardised procedures have not been possible to apply for most of the data and, in order to present a compilation of the data used in the assessment, much of the input data is presented without following the standardised procedures. This will however be changed for the final version of the SR-Can data report, in order to show the methodology that will be used in the final version one example of how input data will be presented is included (migration data for buffer) . The recommended input data for the assessment calculations are, for the interim version, mainly based on SR 97 Beberg data, these are merely presented without any background or uncertainty discussion (this is presented in the SR 97 data report)

  6. International validation study for interim PET in ABVD-treated, advanced-stage hodgkin lymphoma

    DEFF Research Database (Denmark)

    Biggi, Alberto; Gallamini, Andrea; Chauvie, Stephane

    2013-01-01

    in lymphoma. Accordingly, an international validation study was undertaken with the primary aim of validating the prognostic role of interim PET using the Deauville 5-point score to evaluate images and with the secondary aim of measuring concordance rates among reviewers using the same 5-point score......At present, there are no standard criteria that have been validated for interim PET reporting in lymphoma. In 2009, an international workshop attended by hematologists and nuclear medicine experts in Deauville, France, proposed to develop simple and reproducible rules for interim PET reporting....... This paper focuses on the criteria for interpretation of interim PET and on concordance rates....

  7. Influence of reprocessing on fibre length distribution, tensile strength and impact strength of injection moulded cellulose fibre-reinforced polylactide (PLA composites

    Directory of Open Access Journals (Sweden)

    N. Graupner

    2016-08-01

    Full Text Available The present study focuses on the reprocessing behaviour of recycled injection moulded polylactide (PLA composites. The composites are reinforced with regenerated cellulose fibres (lyocell of variable fineness and a fibre mass content of 30%. They were reprocessed up to three times. The influence of reprocessing on the fibre length distribution and the resulting composite mechanical properties (tensile and impact strength was analysed. While the first reprocessing cycle does not affect the mechanical characteristics of the neat PLA matrix, the strength of the composites decreases significantly due to a decreasing fibre aspect ratio. It was shown that fibres having a larger cross-sectional area display a lower aspect ratio than finer fibres, after reprocessing. This phenomenon leads to a larger decrease in tensile strength of composites reinforced with coarser fibres when compared to composites reinforced with finer fibres. A comparison of virgin composites and threefold reprocessed composites with a similar fibre length distribution resulted in a significantly higher tensile strength compared to the virgin sample. This result leads to the conclusion that not only the fibre length is drastically reduced by reprocessing but also that the fibres and the matrix were damaged.

  8. Investigating the effect of Eye Movement Desensitization and Reprocessing (EMDR) on postoperative pain intensity in adolescents undergoing surgery: a randomized controlled trial.

    Science.gov (United States)

    Maroufi, Mohsen; Zamani, Shahla; Izadikhah, Zahra; Marofi, Maryam; O'Connor, Peter

    2016-09-01

    To investigate the efficacy of Eye Movement Desensitization and Reprocessing for postoperative pain management in adolescents. Eye Movement Desensitization and Reprocessing is an inexpensive, non-pharmacological intervention that has successfully been used to treat chronic pain. It holds promise in the treatment of acute, postsurgical pain based on its purported effects on the brain and nervous system. A randomized controlled trial was used. Fifty-six adolescent surgical patients aged between 12-18 years were allocated to gender-balanced Eye Movement Desensitization and Reprocessing (treatment) or non-Eye Movement Desensitization and Reprocessing (control) groups. Pain was measured using the Wong-Baker FACES(®) Pain Rating Scale (WBFS) before and after the intervention (or non-intervention for the control group). A Wilcoxon signed-rank test demonstrated that the Eye Movement Desensitization and Reprocessing group experienced a significant reduction in pain intensity after treatment intervention, whereas the control group did not. Additionally, a Mann-Whitney U-test showed that, while there was no significant difference between the two groups at time 1, there was a significant difference in pain intensity between the two groups at time 2, with the Eye Movement Desensitization and Reprocessing group experiencing lower levels of pain. These results suggest that Eye Movement Desensitization and Reprocessing may be an effective treatment modality for postoperative pain. © 2016 John Wiley & Sons Ltd.

  9. Environmental survey of two interim dumpsites, Middle Atlantic Bight from 05 November 1973 to 10 November 1973 (NODC Accession 7501280)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — A second oceanographic survey cruise was made to an interim municipal sludge dumpsite and initially to an interim dumpsite for the disposal of industrial acid waste...

  10. Fuel salt reprocessing influence on the MSFR behavior and on its associated reprocessing unit; Influence du retraitement physico-chimique du sel combustible sur le comportement du MSFR et sur le dimensionnement de son unite de retraitement

    Energy Technology Data Exchange (ETDEWEB)

    Doligez, X.

    2010-10-15

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

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

    Science.gov (United States)

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

    2009-12-01

    Since November 2006 an absolute phase center correction model for GNSS satellite and receiver antennas has been used within the International GNSS Service (IGS). This model, called igs05.atx, comprises consistent phase center offset (PCO) and variation (PCV) values given in ANTEX format. Generally, these correction values have not been changed in the meantime.For most of the receiver antenna types dominating the IGS network, absolute robot calibrations provided by Geo++ GmbH are available. Those comprise azimuth- and zenith-dependent PCVs down to the horizon. For the remaining antenna types converted field calibrations from the National Geodetic Survey are applied that are purely zenith-dependent. The impact of radomes is taken into account, if calibration results are available. So far, igs05.atx only contains calibrations for the GPS frequencies.The GPS satellite antenna corrections contained in igs05.atx were estimated by Deutsches GeoForschungsZentrum and by TUM by reprocessing more than ten years of IGS data. The corresponding GLONASS corrections were provided by the Center for Orbit Determination in Europe (CODE) after processing more than one year of data. Although azimuth-dependent PCVs are present, the igs05.atx model is limited to block-specific purely nadir-dependent PCVs. In contrast, satellite-specific z-offsets are given.At the time the satellite antenna corrections were estimated, the solutions could only be aligned to IGb00, the IGS realization of ITRF2000, that was based on relative receiver antenna corrections. Moreover, the impact of radomes had to be ignored, as calibration results were not available. So, the IGS reprocessing campaign is an excellent possibility to improve the consistency between both satellite and receiver antenna corrections and the terrestrial reference frame.Several analysis centers (ACs) of the IGS provide z-offset estimates within their weekly SINEX files. By back-solving those files with selected station coordinates fixed

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

    Energy Technology Data Exchange (ETDEWEB)

    Ross, Jens Ole

    2010-02-02

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

  13. Estimates of Zenith Total Delay trends from GPS reprocessing with autoregressive process

    Science.gov (United States)

    Klos, Anna; Hunegnaw, Addisu; Teferle, Felix Norman; Ebuy Abraha, Kibrom; Ahmed, Furqan; Bogusz, Janusz

    2017-04-01

    Nowadays, near real-time Zenith Total Delay (ZTD) estimates from Global Positioning System (GPS) observations are routinely assimilated into numerical weather prediction (NWP) models to improve the reliability of forecasts. On the other hand, ZTD time series derived from homogeneously re-processed GPS observations over long periods have the potential to improve our understanding of climate change on various temporal and spatial scales. With such time series only recently reaching somewhat adequate time spans, the application of GPS-derived ZTD estimates to climate monitoring is still to be developed further. In this research, we examine the character of noise in ZTD time series for 1995-2015 in order to estimate more realistic magnitudes of trend and its uncertainty than would be the case if the stochastic properties are not taken into account. Furthermore, the hourly sampled, homogeneously re-processed and carefully homogenized ZTD time series from over 700 globally distributed stations were classified into five major climate zones. We found that the amplitudes of annual signals reach values of 10-150 mm with minimum values for the polar and Alpine zones. The amplitudes of daily signals were estimated to be 0-12 mm with maximum values found for the dry zone. We examined seven different noise models for the residual ZTD time series after modelling all known periodicities. This identified a combination of white plus autoregressive process of fourth order to be optimal to match all changes in power of the ZTD data. When the stochastic properties are neglected, ie. a pure white noise model is employed, only 11 from 120 trends were insignificant. Using the optimum noise model more than half of the 120 examined trends became insignificant. We show that the uncertainty of ZTD trends is underestimated by a factor of 3-12 when the stochastic properties of the ZTD time series are ignored and we conclude that it is essential to properly model the noise characteristics of

  14. NASADEM Overview and First Results: Shuttle Radar Topography Mission (SRTM) Reprocessing and Improvements

    Science.gov (United States)

    Buckley, S.; Agram, P. S.; Belz, J. E.; Crippen, R. E.; Gurrola, E. M.; Hensley, S.; Kobrick, M.; Lavalle, M.; Martin, J. M.; Neumann, M.; Nguyen, Q.; Rosen, P. A.; Shimada, J.; Simard, M.; Tung, W.

    2015-12-01

    NASADEM is a significant modernization of SRTM digital elevation model (DEM) data supported by the NASA MEaSUREs program. We are reprocessing the raw radar signal data using improved algorithms and incorporating ICESat and ASTER-derived DEM data unavailable during the original processing. The NASADEM products will be freely-available through the Land Processes Distributed Active Archive Center (LPDAAC) at 1-arcsecond spacing. The most significant processing improvements involve void reduction through improved phase unwrapping and using ICESat data for control. The updated unwrapping strategy now includes the use of SNAPHU for data processing patches where the unwrapped coverage from the original residue-based unwrapper falls below a coverage threshold. In North America continental processing, first experiments show the strip void area is reduced by more than 50% and the number of strip void patches is reduced by 40%. Patch boundary voids are mitigated by reprocessing with a different starting burst and merging the unwrapping results. We also updated a low-resolution elevation database to aid with unwrapping bootstrapping, retaining isolated component of unwrapped phase, and assessing the quality of the strip DEMs. We introduce a height ripple error correction to reduce artifacts in the strip elevation data. These ripples are a few meters in size with along-track spatial scales of tens of kilometers and are due to uncompensated mast motion most pronounced after Shuttle roll angle adjustment maneuvers. We developed an along-track filter utilizing differences between the SRTM heights and ICESat lidar elevation data. For a test using all data over North America, the algorithm reduced the ICESat-SRTM bias from 80 cm to 3 cm and the RMS from 5m to 4m. After merging and regridding the SRTM strip DEMs into 1x1-degree tiles, remaining voids are primarily filled with the ASTER-derived Global DEM. We use a Delta Surface Fill method to rubbersheet fill data across the void for

  15. 78 FR 41125 - Interim Enforcement Policy for Permanent Implant Brachytherapy Medical Event Reporting

    Science.gov (United States)

    2013-07-09

    ... COMMISSION Interim Enforcement Policy for Permanent Implant Brachytherapy Medical Event Reporting AGENCY...'s permanent implant brachytherapy program. This interim policy affects NRC licensees that are authorized to perform permanent implant brachytherapy. DATES: This policy revision is effective July 9, 2013...

  16. 42 CFR 417.572 - Budget and enrollment forecast and interim reports.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 3 2010-10-01 2010-10-01 false Budget and enrollment forecast and interim reports... forecast and interim reports. (a) Annual submittal. The HMO or CMP must submit an annual operating budget and enrollment forecast, in the form and detail required by CMS, at least 90 days before the beginning...

  17. 78 FR 56752 - Interim Staff Guidance Specific Environmental Guidance for Integral Pressurized Water Reactors...

    Science.gov (United States)

    2013-09-13

    ... activities associated with review of applications for ESPs, design certifications, and COLs by the Office of... comment on, draft Interim Staff Guidance (ISG) ESP/COL-ISG-027, ``Interim Staff Guidance Specific..., early site permits (ESPs), and combined licenses (COLs). DATES: Submit comments by October 15, 2013...

  18. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    Energy Technology Data Exchange (ETDEWEB)

    Burgard, K.C.

    1998-04-09

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

  19. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    Energy Technology Data Exchange (ETDEWEB)

    Burgard, K.C.

    1998-06-02

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

  20. 32 CFR 643.36 - Policy-Interim leasing of excess properties to facilitate economic readjustment.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 4 2010-07-01 2010-07-01 true Policy-Interim leasing of excess properties to facilitate economic readjustment. 643.36 Section 643.36 National Defense Department of Defense (Continued) DEPARTMENT OF THE ARMY (CONTINUED) REAL PROPERTY REAL ESTATE Policy § 643.36 Policy—Interim leasing of excess...

  1. 76 FR 15028 - Airport Improvement Program (AIP): Interim Policy Regarding Access to Airports From Residential...

    Science.gov (United States)

    2011-03-18

    ... Federal Aviation Administration Airport Improvement Program (AIP): Interim Policy Regarding Access to Airports From Residential Property AGENCY: Federal Aviation Administration (FAA). ACTION: Interim policy... clarifying FAA policy concerning through-the-fence access to a federally-obligated airport from an adjacent...

  2. 46 CFR 308.202 - Issuance of interim binder; terms and conditions.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 8 2010-10-01 2010-10-01 false Issuance of interim binder; terms and conditions. 308... binder; terms and conditions. Upon acceptance of an application, an interim binder in form as set forth... forth in § 308.207) to the same extent as if such application and policy were made a part of the binder...

  3. PROJECT W-551 INTERIM PRETREATMENT SYSTEM TECHNOLOGY SELECTION SUMMARY DECISION REPORT AND RECOMMENDATION

    Energy Technology Data Exchange (ETDEWEB)

    CONRAD EA

    2008-08-12

    This report provides the conclusions of the tank farm interim pretreatment technology decision process. It documents the methodology, data, and results of the selection of cross-flow filtration and ion exchange technologies for implementation in project W-551, Interim Pretreatment System. This selection resulted from the evaluation of specific scope criteria using quantitative and qualitative analyses, group workshops, and technical expert personnel.

  4. 78 FR 72897 - Draft Guidance for Industry on Interim Product Reporting for Human Drug Compounding Outsourcing...

    Science.gov (United States)

    2013-12-04

    ... HUMAN SERVICES Food and Drug Administration Draft Guidance for Industry on Interim Product Reporting for Human Drug Compounding Outsourcing Facilities Under Section 503B of the Federal Food, Drug, and Cosmetic... entitled ``Interim Product Reporting for Human Drug Compounding Outsourcing Facilities Under Section 503B...

  5. An Interim Report on NASA's Draft Space Technology Roadmaps

    Science.gov (United States)

    2011-01-01

    NASA has developed a set of 14 draft roadmaps to guide the development of space technologies under the leadership of the NASA Office of the Chief Technologist (OCT). Each of these roadmaps focuses on a particular technology area (TA). The roadmaps are intended to foster the development of advanced technologies and concepts that address NASA's needs and contribute to other aerospace and national needs. OCT requested that the National Research Council conduct a study to review the draft roadmaps, gather and assess relevant community input, and make recommendations and suggest priorities to inform NASA's decisions as it finalizes its roadmaps. The statement of task states that "based on the results of the community input and its own deliberations, the steering committee will prepare a brief interim report that addresses high-level issues associated with the roadmaps, such as the advisability of modifying the number or technical focus of the draft NASA roadmaps." This interim report, which does not include formal recommendations, addresses that one element of the study charge. NASA requested this interim report so that it would have the opportunity to make an early start in modifying the draft roadmaps based on feedback from the panels and steering committee. The final report will address all other tasks in the statement of task. In particular, the final report will include a prioritization of technologies, will describe in detail the prioritization process and criteria, and will include specific recommendations on a variety of topics, including many of the topics mentioned in this interim report. In developing both this interim report and the final report to come, the steering committee draws on the work of six study panels organized by technical area, loosely following the organization of the 14 roadmaps, as follows: A Panel 1: Propulsion and Power TA01 Launch Propulsion Systems TA02 In-Space Propulsion Technologies TA03 Space Power and Energy Storage Systems TA13

  6. Costs of head-end incineration with respect to Kr separation in the reprocessing of HTR fuel elements

    Energy Technology Data Exchange (ETDEWEB)

    Barnert-Wiemer, H.; Boehnert, R.

    1976-07-15

    The C-incinerations and the Kr-separations during head-end incineration in the reprocessing of HTR fuel elements are described. The costs for constructing an operating a head-end incineration of reprocessing capacities with 5,000 to 50,000 MW(e)-HTR power have been determined. The cost estimates are divided into investment and operating costs, further after the fraction of the N/sub 2/-content in the incineration exhaust gas, which strongly affects costs. It appears that, in the case of Kr-separation from the incineration exhaust gas, the investment costs as well as the operating costs of the head-end for N/sub 2/-containing exhaust gas are considerably greater than those for gas without N/sub 2/. The C-incineration of the graphite of the HTR fuel elements should therefore only be performed with influx gas that is free of N/sub 2/.

  7. Global Daily Sea Ice Concentration Reprocessing Data Set for 1978-2007 from the EUMETSAT Ocean and Sea Ice Satellite Application Facility (NCEI Accession 0068294)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — These data constitute the reprocessed sea ice concentration data set from the EUMETSAT Ocean and Sea Ice Satellite Application Facility (OSI SAF), covering the...

  8. Protecting the confidentiality of interim data: addressing current challenges.

    Science.gov (United States)

    Fleming, Thomas R

    2015-02-01

    There is compelling evidence supporting the importance of maintaining confidentiality of interim data in clinical trials designed to reliably address the benefit-to-risk profile of interventions. While this is widely recognized, creative approaches are needed to achieve this in challenging settings where interim data are released for regulatory review and action, even though the trial would be continued to address its primary hypothesis. An illustration is the recently emerging setting of cardiovascular safety trials in type 2 diabetes mellitus. At the first stage of such trials, if large relative increases in cardiovascular major morbidity/mortality can be ruled out, data can be released solely for the purpose of allowing regulatory decision making about marketing approval. The trial is then continued in the post-marketing setting to address the primary hypothesis regarding whether smaller relative increases can be ruled out. Active rather than passive approaches are needed to protect the integrity of cardiovascular safety trials. Given the importance to trial integrity of maintaining confidentiality of interim data such as the estimated relative effect on cardiovascular risk, a Data Access Plan should be in place in these trials to ensure such data are not revealed to study participants and their caregivers, investigators involved in trial conduct, the sponsor's management team, and the public, until trial completion. A Performance Standards Document also should be developed to pre-specify targeted and minimally acceptable levels for recruitment rate, best real-world achievable adherence, avoidance of cross-ins, and retention rate. This document should specify creative approaches for achieving these targets, oversight procedures during trial conduct to monitor performance levels, and actions to be taken if emerging data indicate minimally acceptable levels are not being reached. In settings where meaningful breaches in confidentiality have occurred, such

  9. Tritium enrichment for process flow streams of a nuclear fuel reprocessing plant having a hot-cold system

    Energy Technology Data Exchange (ETDEWEB)

    Mangold, H.; Schindewolf, U.

    1988-07-01

    During the nuclear fuel reprocessing tritium is partially transferred into the aqueous process streams. At normal pressure, the most promising enrichment method appears to be an inverse current exchanger system using electrolysis at the bottom of the inverse current column apparatus and recombination in an oxyhydrogen gas flame at the top of the column apparatus. A hydrophobic catalyst is used which is made of a pulverized mix of platinized activated carbon and PTFE.

  10. HTGR Resilient Control System Strategy

    Energy Technology Data Exchange (ETDEWEB)

    Lynne M. Stevens

    2010-09-01

    A preeminent objective for corporate and government organizations is the protection of major investments, which is attained by achieving state awareness, a comprehensive understanding of security and safety, for critical infrastructures. Given the dependence of critical infrastructure on control systems for automation, the integrity of these systems and their ability to provide owner/operators a high degree of state awareness is essential in attaining a high degree of investment protection and public acceptance. Operators as well as government are therefore burdened to ensure they have a timely understanding of the status of their plant or all plants, respectively, to ensure efficient operations and investment and public protection. “This characterization is a significant objective that must consider many aspects of instrumentation, control, and intelligent systems in order to achieve the required result. These aspects include sensory, communication, analysis, decision, and human system interfaces necessary to achieve fusion of data and presentation of results that will provide an understanding of what issues are important and why.

  11. AN INTERIM THERMODYNAMIC PROPERTY FORMULATION FOR SUPERCRITICAL n-HEXANE

    Directory of Open Access Journals (Sweden)

    Azzedine Abbaci

    2010-07-01

    Full Text Available Accurate information on the thermodynamic properties of supercritical fluids is highly sought for the chemical technology, especially, supercritical extraction technology. The thermodynamic properties of fluids near the critical region are strongly affected by the presence of fluctuations and therefore, can not be described by conventional equation. We have investigated an interim formulation for the behavior of the thermodynamic properties of n-hexane in the vicinity of the critical region. For this reason we have used the so-called “crossover model” to describe the thermodynamic properties of n-hexane in a wide range of temperatures and densities around the critical point.

  12. Hospital clinicians' iPad use: an interim report.

    Science.gov (United States)

    Witman, Lydia

    2012-01-01

    An increasing number of hospital libraries are supporting the use of tablet computers such as iPads for access to information resources. To date, this adoption of tablets is not supported by high-quality research evidence. This article provides an interim report on a formal study of clinicians' use of iPads in the hospital setting, currently being conducted at Pennsylvania Hospital in Philadelphia. Other hospital librarians may wish to consider similar factors when beginning to support the use of tablet computers at their own institutions.

  13. Hanford low-level tank waste interim performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Mann, F.M.

    1996-09-16

    The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single- and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and its performance as early as possible in the project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives.

  14. The development of an interim generalized gate logic software simulator

    Science.gov (United States)

    Mcgough, J. G.; Nemeroff, S.

    1985-01-01

    A proof-of-concept computer program called IGGLOSS (Interim Generalized Gate Logic Software Simulator) was developed and is discussed. The simulator engine was designed to perform stochastic estimation of self test coverage (fault-detection latency times) of digital computers or systems. A major attribute of the IGGLOSS is its high-speed simulation: 9.5 x 1,000,000 gates/cpu sec for nonfaulted circuits and 4.4 x 1,000,000 gates/cpu sec for faulted circuits on a VAX 11/780 host computer.

  15. Hanford low-level tank waste interim performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Mann, F.M.

    1997-09-12

    The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and performance early in the disposal system project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives.

  16. The PDF4LHC Working Group Interim Report

    CERN Document Server

    Alekhin, Sergey; Ball, Richard D.; Bertone, Valerio; Blumlein, Johannes; Botje, Michiel; Butterworth, Jon; Cerutti, Francesco; Cooper-Sarkar, Amanda; de Roeck, Albert; Del Debbio, Luigi; Feltesse, Joel; Forte, Stefano; Glazov, Alexander; Guffanti, Alberto; Gwenlan, Claire; Huston, Joey; Jimenez-Delgado, Pedro; Lai, Hung-Liang; Latorre, Jose I.; McNulty, Ronan; Nadolsky, Pavel; Olaf Moch, Sven; Pumplin, Jon; Radescu, Voica; Rojo, Juan; Sjostrand, Torbjorn; Stirling, W.J.; Stump, Daniel; Thorne, Robert S.; Ubiali, Maria; Vicini, Alessandro; Watt, Graeme; Yuan, C.-P.

    2011-01-01

    This document is intended as a study of benchmark cross sections at the LHC (at 7 TeV) at NLO using modern parton distribution functions currently available from the 6 PDF fitting groups that have participated in this exercise. It also contains a succinct user guide to the computation of PDFs, uncertainties and correlations using available PDF sets. A companion note, also submitted to the archive, provides an interim summary of the current recommendations of the PDF4LHC working group for the use of parton distribution functions and of PDF uncertainties at the LHC, for cross section and cross section uncertainty calculations.

  17. Atmospheric tritium concentrations under influence of AREVA NC La Hague reprocessing plant (France) and background levels.

    Science.gov (United States)

    Connan, O; Hébert, D; Solier, L; Maro, D; Pellerin, G; Voiseux, C; Lamotte, M; Laguionie, P

    2017-10-01

    In-air tritium measurements were conducted around the AREVA NC La Hague reprocessing plant, as well as on other sites that are not impacted by the nuclear industry in northwest of France. The results indicate that the dominant tritium form around the AREVA site is HT (86%). HT and HTO levels are lower than 5 and 1 Bq. m-3 for hourly samples taken in the plume. No tritiated organic molecules (TOM) were detected. 26 measurement campaigns were performed and links were established between near-field 85Kr, HT and HTO activities. Environmental measurements are in line with those taken at the discharge stack, and tend to demonstrate that there are no rapid changes in the tritium forms released. Out of the influence of any nuclear activities, the levels measured were below 13 mBq.m-3 for HT and 5 mBq.m-3 for HTO (<0.5 Bq. L-1). HTO level in air seems to be influenced by HTO activities in surrounding seawater. Copyright © 2017 Elsevier Ltd. All rights reserved.

  18. Silica-based waste form for immobilization of iodine from reprocessing plant off-gas streams

    Energy Technology Data Exchange (ETDEWEB)

    Matyáš, Josef; Canfield, Nathan; Sulaiman, Sannoh; Zumhoff, Mac

    2016-08-01

    A high selectivity and sorption capacity for iodine and a feasible consolidation to a durable SiO2-based waste form makes silver-functionalized silica aerogel (Ag0-aerogel) an attractive choice for the removal and sequestration of iodine compounds from the off-gas of a nuclear fuel reprocessing plant. Hot uniaxial pressing of iodine-loaded Ag0-aerogel (20.2 mass% iodine) at 1200°C for 30 min under 29 MPa pressure provided a partially sintered product with residual open porosity of 16.9% that retained ~93% of sorbed iodine. Highly iodine-loaded Ag0-aerogel was successfully consolidated by hot isostatic pressing at 1200°C with a 30-min hold and under 207 MPa. The fully densified waste form had a bulk density of 3.3 g/cm3 and contained ~39 mass% iodine. The iodine was retained in the form of nano- and micro-particles of AgI that were uniformly distributed inside and along boundaries of fused silica grains.

  19. Consolidated fuel reprocessing program: Criticality experiments with fast test reactor fuel pins in an organic moderator

    Energy Technology Data Exchange (ETDEWEB)

    Bierman, S.R.

    1986-12-01

    The results obtained in a series of criticality experiments performed as part of a joint program on criticality data development between the United States Department of Energy and the Power Reactor and Nuclear Fuel Development Corporation of Japan are presented in this report along with a complete description of the experiments. The experiments involved lattices of Fast Test Reactor (FTR) fuel pins in an organic moderator mixture similar to that used in the solvent extraction stage of fuel reprocessing. The experiments are designed to provide data for direct comparison with previously performed experimental measurements with water moderated lattices of FTR fuel pins. The same lattice arrangements and FTR fuel pin types are used in these organic moderated experimental assemblies as were used in the water moderated experiments. The organic moderator is a mixture of 38 wt % tributylphosphate in a normal paraffin hydrocarbon mixture of C{sub 11}H{sub 24} to C{sub 15}H{sub 32} molecules. Critical sizes of 1054.8, 599.2, 301.8, 199.5 and 165.3 fuel pins were obtained respectively for organic moderated lattices having 0.761 cm, 0.968 cm, 1.242 cm, 1.537 cm and 1.935 cm square lattice pitches as compared to 1046.9, 571.9, 293.9, 199.7 and 165.1 fuel pins for the same lattices water moderated.

  20. Self-Healable and Reprocessable Polysulfide Sealants Prepared from Liquid Polysulfide Oligomer and Epoxy Resin.

    Science.gov (United States)

    Gao, Wentong; Bie, Mengyao; Liu, Fu; Chang, Pengshan; Quan, Yiwu

    2017-05-10

    Polysulfide sealants have been commercially applied in many industrial fields. In this article, we study the self-healing property of the epoxy resin-cured polysulfide sealants for the first time. The obtained sealants showed a flexible range of ultimate elongation of 157-478% and a tensile strength of 1.02-0.75 MPa corresponding to different polysulfide oligomers. By taking advantage of the dynamic reversible exchange of disulfide bonds, polysulfide sealants exhibited good self-healing ability under a moderate thermal stimulus. A higher molecular weight and a lower degree of cross-linking of polysulfide oligomer were helpful in improving the ultimate elongation and healing efficiency of the polysulfide sealants. After subjecting to a temperature of 75 °C for 60 min, both the tensile strength and ultimate elongation of a fully cut sample, LP55-F, were restored to 91% of the original values, without affecting the sealing property. Furthermore, the sample exhibited excellent reshaping and reprocessing abilities. These outcomes offer a paradigm toward sustainable industrial applications of the polysulfide-based sealants.

  1. Supercritical Water Oxidation: A Solution for the Elimination of Back-End Organic Reprocessing Wastes

    Energy Technology Data Exchange (ETDEWEB)

    Leybros, A.; Roubaud, A.; Turc, H.A.; Fournel, B. [Supercritical fluids and membranes Laboratory, CEA Valrho, BP 17171, 30207 Bagnols/Ceze Cedex (France)

    2008-07-01

    Supercritical water oxidation (SCWO) is a very efficient technique for total elimination of organic wastes from reprocessing activities on the way of 'zero wastes' facilities. This technology uses the properties of supercritical water (P > 221 bars and T > 647 K) to obtain a good mixing between oxygen (the oxidant) and the organic waste. Thereby, the oxidation reaction is fast and complete. Using the SCWO process, contamination contained in organic materials like spent solvents can be confined in a closed space, like a reactor in a glovebox. A new application is tested for the treatment of solid organic wastes like ion exchange resins (IER). Experiments are made with suspensions of IER in water and isopropyl-alcohol. A nuclear version of the process with the double shell reactor has been constructed and is being tested. The aim of this work is to obtain a treatment capacity of 1 kg/h for the nuclear version with the same global set-up, concept of process and security as well as contamination management as for a 200 g/h pilot. (authors)

  2. Reprocessing the Elliptical Orbiting Galileo Satellites E14 and E18: Preliminary Results

    Science.gov (United States)

    Männel, Benjamin

    2017-04-01

    In August 2014, the two Galileo satellites FOC-1 (E18) and FOC-2 (E14) were - due to a technical problem - launched into a wrong, elliptic orbit. In a recovery mission a series of orbit maneuvers were performed to raise the perigee to an altitude where both spacecrafts could be introduced to the Galileo navigation service. After this period of orbit maintenance both satellites started to transmit navigation signals at November 29, 2014 (E18) and March 17, 2015 (E14). However, as it was not possible to recover the nominal orbits due to propellant limitations, both spacecrafts orbit the Earth with a numerical eccentricity of 0.16 and an inclination of 50.2°. Very soon, it was assumed that both satellites could be highly useful for studies on general relativity, especially as the Galileo spacecrafts are equipped with very stable passive hydrogen masers. A prerequisite for dedicated studies in this field are highly accurate satellite orbits and clock corrections. Preliminary results for orbit and satellite clock determination will be presented based on an initial reprocessing over the past 2.5 years. The presentation focuses firstly on orbit modeling aspects with respect to the elliptically orbits. Secondly the derived clock corrections for the on-board passive clocks are assessed with respect to the reference clock at ground stations. The results will be discussed also with respect to the proposed Galileo-based studies on the gravitational redshift.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1986-09-01

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

  4. Methodological Aspects of Cognitive Rehabilitation with Eye Movement Desensitization and Reprocessing (EMDR

    Directory of Open Access Journals (Sweden)

    Afsaneh Zarghi

    2013-02-01

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

  5. Control of radio-iodine at the German reprocessing plant WAK during operation and after shutdown

    Energy Technology Data Exchange (ETDEWEB)

    Herrmann, F.J.; Herrmann, B.; Kuhn, K.D. [Wiederaufarbeitungsanlage Karlsruhe (Germany)] [and others

    1997-08-01

    During 20 years of operation 207 metric tons of oxide fuel from nuclear power reactors with 19 kg of iodine-129 had been reprocessed in the WAK plant near Karlsruhe. In January 1991 the WAK Plant was shut down. During operation iodine releases of the plant as well as the iodine distribution over the liquid and gaseous process streams had been determined. Most of the iodine is evolved into the dissolver off-gas in volatile form. The remainder is dispersed over many aqueous, organic and especially gaseous process and waste streams. After shut down of the plant in January 1991, iodine measurements in the off-gas streams have been continued up to now. Whereas the iodine-129 concentration in the dissolver off-gas dropped during six months after shutdown by three orders of magnitude, the iodine concentrations in the vessel ventilation system of the PUREX process and the cell vent system decreased only by a factor of 10 during the same period. Iodine-129 releases of the liquid high active waste storage tanks did not decrease distinctly. The removal efficiencies of the silver impregnated iodine filters in the different off-gas streams of the WAK plant depend on the iodine concentration in the off-gas. The reason of the observed dependence of the DF on the iodine-129 concentration might be due to the presence of organic iodine compounds which are difficult to remove. 13 refs., 3 figs.

  6. Hemodynamic responses of eye movement desensitization and reprocessing in posttraumatic stress disorder.

    Science.gov (United States)

    Ohtani, Toshiyuki; Ohta ni, Toshiyuki; Matsuo, Koji; Kasai, Kiyoto; Kato, Tadafumi; Kato, Nobumasa

    2009-12-01

    Eye movement desensitization and reprocessing (EMDR) is an effective psychological intervention for posttraumatic stress disorder (PTSD). Trauma-related recall (Recall) with eye movements (EMs) is thought to reduce distress. However, the neural mechanisms underlying this process remain unknown. Thirteen patients with PTSD received EMDR treatment over the course of 2-10 weeks. We assessed the change in hemoglobin concentration in the lateral prefrontal cortex (PFC) during Recall with and without EM using multi-channel near-infrared spectroscopy (NIRS). Clinical diagnosis and improvement were evaluated using the Clinician-Administered PTSD Scale. Recall with EM was associated with a significant decrease in oxygenated hemoglobin concentration ([oxy-Hb]) in the lateral PFC as compared with Recall without EM. Longitudinally, [oxy-Hb] during Recall significantly decreased and the amount of decrease was significantly correlated with clinical improvement when the post-treatment data was compared with that of the pre-treatment. Our results suggest that performing EM during Recall reduces the over-activity of the lateral PFC, which may be part of the biological basis for the efficacy of EMDR in PTSD. NIRS may be a useful tool for objective assessment of psychological intervention in PTSD.

  7. Methodological Aspects of Cognitive Rehabilitation with Eye Movement Desensitization and Reprocessing (EMDR).

    Science.gov (United States)

    Zarghi, Afsaneh; Zali, Alireza; Tehranidost, Mehdi

    2013-01-01

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

  8. Eye Movement Desensitization and Reprocessing and Slow Wave Sleep: A Putative Mechanism of Action.

    Science.gov (United States)

    Pagani, Marco; Amann, Benedikt L; Landin-Romero, Ramon; Carletto, Sara

    2017-01-01

    Eye Movement Desensitization and Reprocessing (EMDR) is considered highly efficacious for the treatment of Post-traumatic Stress Disorder and has proved to be a valid treatment approach with a wide range of applications. However, EMDR's mechanisms of action is not yet fully understood. This is an active area of clinical and neurophysiological research, and several different hypotheses have been proposed. This paper discusses a conjecture which focuses on the similarity between the delta waves recorded by electroencephalography during Slow Wave Sleep (SWS) and those registered upon typical EMDR bilateral stimulation (eye movements or alternate tapping) during recurrent distressing memories of an emotionally traumatic event. SWS appears to have a key role in memory consolidation and in the reorganization of distant functional networks, as well as Eye Movements seem to reduce traumatic episodic memory and favor the reconsolidation of new associated information. The SWS hypothesis may put forward an explanation of how EMDR works, and is discussed also in light of other theories and neurobiological findings.

  9. An Integrative Model for the Neural Mechanism of Eye Movement Desensitization and Reprocessing (EMDR).

    Science.gov (United States)

    Coubard, Olivier A

    2016-01-01

    Since the seminal report by Shapiro that bilateral stimulation induces cognitive and emotional changes, 26 years of basic and clinical research have examined the effects of Eye Movement Desensitization and Reprocessing (EMDR) in anxiety disorders, particularly in post-traumatic stress disorder (PTSD). The present article aims at better understanding EMDR neural mechanism. I first review procedural aspects of EMDR protocol and theoretical hypothesis about EMDR effects, and develop the reasons why the scientific community is still divided about EMDR. I then slide from psychology to physiology describing eye movements/emotion interaction from the physiological viewpoint, and introduce theoretical and technical tools used in movement research to re-examine EMDR neural mechanism. Using a recent physiological model for the neuropsychological architecture of motor and cognitive control, the Threshold Interval Modulation with Early Release-Rate of rIse Deviation with Early Release (TIMER-RIDER)-model, I explore how attentional control and bilateral stimulation may participate to EMDR effects. These effects may be obtained by two processes acting in parallel: (i) activity level enhancement of attentional control component; and (ii) bilateral stimulation in any sensorimotor modality, both resulting in lower inhibition enabling dysfunctional information to be processed and anxiety to be reduced. The TIMER-RIDER model offers quantitative predictions about EMDR effects for future research about its underlying physiological mechanisms.

  10. The eye movement desensitization and reprocessing procedure prevents defensive processing in health persuasion.

    Science.gov (United States)

    Dijkstra, Arie; van Asten, Regine

    2014-01-01

    In the present study, the method of eye movement desensitization and reprocessing (EMDR) is studied to understand and prevent defensive reactions with regard to a negatively framed message advocating fruit and vegetable consumption. EMDR has been shown to tax the working memory. Participants from a university sample (n = 124) listened to the persuasive message in a randomized laboratory experiment. In the EMDR condition, they were also instructed to follow with their eyes a dot on the computer screen. The dot constantly moved from one side of the screen to the other in 2 seconds. In addition, a self-affirmation procedure was applied in half of the participants. EMDR led to a significant increase in persuasion, only in recipients in whom the persuasive message could be expected to activate defensive self-regulation (in participants with a moderate health value and in participants with low self-esteem). In those with a moderate health value, EMDR increased persuasion, but only when recipients were not affirmed. In addition, EMDR increased persuasion only in recipients with low self-esteem, not in those with high self-esteem. These results showed that EMDR influenced persuasion and in some way lowered defensive reactions. The similarities and differences in effects of EMDR and self-affirmation further increased our insight into the psychology of defensiveness.

  11. Eye movement desensitization and reprocessing for treating psychological disturbances in Taiwanese adolescents who experienced Typhoon Morakot.

    Science.gov (United States)

    Tang, Tze-Chun; Yang, Pinchen; Yen, Cheng-Fang; Liu, Tai-Ling

    2015-07-01

    In this case-control study, we aimed to assess the intervention effects of four-session eye movement desensitization and reprocessing (EMDR) on reducing the severity of disaster-related anxiety, general anxiety, and depressive symptoms in Taiwanese adolescents who experienced Typhoon Morakot. A total of 83 adolescents with posttraumatic stress disorder related to Typhoon Morakot, major depressive disorder, or current moderate or high suicide risk after experiencing Typhoon Morakot were allocated to a four-session course of EMDR (N = 41) or to treatment as usual (TAU; N = 42). A multivariate analysis of covariance was performed to examine the effects of EMDR in reducing the severity of disaster-related anxiety, general anxiety, and depressive symptoms in adolescents by using preintervention severity values as covariates. The multivariate analysis of covariance results indicated that the EMDR group exhibited significantly lower preintervention severity values of general anxiety and depression than did the TAU group. In addition, the preintervention severity value of disaster-related anxiety in the EMDR group was lower than that in the TAU group (p = 0.05). The results of this study support that EMDR could alleviate general anxiety and depressive symptoms and reduce disaster-related anxiety in adolescents experiencing major traumatic disasters. Copyright © 2015. Published by Elsevier Taiwan.

  12. Comparison of eye movement desensitization and reprocessing with citalopram in treatment of obsessive-compulsive disorder.

    Science.gov (United States)

    Nazari, Hedayat; Momeni, Nahid; Jariani, Mojgan; Tarrahi, Mohammad Javad

    2011-11-01

    Obsessive-compulsive disorder (OCD) is one of the chronic anxiety disorders that interfere with routine individual life, occupational and social functions. There is controversy about the first choice of treatment for OCD between medication and psychotherapy. the aim was to investigate the efficacy of eye movement desensitization and reprocessing (EMDR) compared with medication by citalopram in treatment of OCD. This randomized controlled trial was carried out on 90 OCD patients that randomly were assigned into two groups. They either received therapeutic sessions of EMDR or citalopram during 12 weeks. Both groups blindly were evaluated by the Yale-Brown scale before and after the trial period. Pretreatment average Yale-Brown score of citalopram group was about 25.26 as well as 24.83 in EMDR group. The after treatment scores were 19.06 and 13.6, respectively. There was significant difference between the mean Yale-Brown scores of the two groups after treatment and EMDR was more effective than citalopram in improvement of OCD signs. It is concluded that although both therapeutic methods (EMDR and Citalopram) had significant effect in improving obsessive signs but it seems that in short term EMRD has better effect in improvement of final outcome of OCD.

  13. Dissociation predicts treatment response in eye-movement desensitization and reprocessing for posttraumatic stress disorder.

    Science.gov (United States)

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

    2016-01-01

    Using clinical data from a specialized trauma clinic, this study investigated pretreatment clinical factors predicting response to eye-movement desensitization and reprocessing (EMDR) among adult patients diagnosed with posttraumatic stress disorder (PTSD). Participants were evaluated using the Clinician-Administered PTSD Scale (CAPS), the Symptom Checklist-90-Revised, the Beck Depression Inventory, and the Dissociative Experiences Scale before treatment and were reassessed using the CAPS after treatment and at 6-month follow-up. A total of 69 patients underwent an average of 4 sessions of EMDR, and 60 (87%) completed the posttreatment evaluation, including 8 participants who terminated treatment prematurely. Intent-to-treat analysis revealed that 39 (65%) of the 60 patients were classified as responders and 21 (35%) as nonresponders when response was defined as more than a 30% decrease in total CAPS score. The nonresponders had higher levels of dissociation (depersonalization and derealization) and numbing symptoms, but other PTSD symptoms, such as avoidance, hyperarousal, and intrusion, were not significantly different. The number of psychiatric comorbidities was also associated with treatment nonresponse. The final logistic regression model yielded 2 significant variables: dissociation (p < .001) and more than 2 comorbidities compared to none (p < .05). These results indicate that complex symptom patterns in PTSD may predict treatment response and support the inclusion of the dissociative subtype of PTSD in the Diagnostic and Statistical Manual of Mental Disorders, Fifth Edition.

  14. An integrative model for the neural mechanism of Eye Movement Desensitization and Reprocessing (EMDR

    Directory of Open Access Journals (Sweden)

    Olivier A. Coubard

    2016-04-01

    Full Text Available Since the seminal report by Shapiro that bilateral stimulation induces cognitive and emotional changes, twenty-six years of basic and clinical research have examined the effects of Eye Movement Desensitization and Reprocessing (EMDR in anxiety disorders, particularly in Post-Traumatic Stress Disorder (PTSD. The present article aims at better understanding EMDR neural mechanism. I first review procedural aspects of EMDR protocol and theoretical hypothesis about EMDR effects, and develop the reasons why the scientific community is still divided about EMDR. I then slide from psychology to physiology describing eye movements/emotion interaction from the physiological viewpoint, and introduce theoretical and technical tools used in movement research to re-examine EMDR neural mechanism. Using a recent physiological model for the neuropsychological architecture of motor and cognitive control, the Threshold Interval Modulation with Early Release-Rate of rIse Deviation with Early Release – TIMER-RIDER – model, I explore how attentional control and bilateral stimulation may participate to EMDR effects. These effects may be obtained by two processes acting in parallel: (i activity level enhancement of attentional control component; and (ii bilateral stimulation in any sensorimotor modality, both resulting in lower inhibition enabling dysfunctional information to be processed and anxiety to be reduced. The TIMER-RIDER model offers quantitative predictions about EMDR effects for future research about its underlying physiological mechanisms.

  15. Eye movement desensitization and reprocessing in addiction continuing care: a phenomenological study of women in recovery.

    Science.gov (United States)

    Marich, Jamie

    2010-09-01

    Traditional models of addiction treatment and relapse prevention fail to consider the role that unresolved trauma plays in an addicted woman's recovery experience. Implementing Eye Movement Desensitization and Reprocessing (EMDR) into the treatment process offers a potential solution to this problem. Ten women (alumnae of an extended-care treatment facility) participated in a semistandardized interview to share their experiences with active addiction, treatment, EMDR therapy, and recovery. With the use of A. P. Giorgi's descriptive phenomenological psychological method for analysis, four major thematic areas emerged from the interview data: the existence of safety as an essential crucible of the EMDR experience, the importance of accessing the emotional core as vital to the recovery experience, the role of perspective shift in lifestyle change, and the use of a combination of factors for successful treatment. All 10 women, to some degree, credited EMDR treatment as a crucial component of their addiction continuing-care processes, especially in helping with emotional core access and perspective shift. Implications emerge from the data on how to best implement EMDR into a comprehensive addiction treatment program.

  16. Eye movement desensitization and reprocessing for treating psychological disturbances in Taiwanese adolescents who experienced Typhoon Morakot

    Directory of Open Access Journals (Sweden)

    Tze-Chun Tang

    2015-07-01

    Full Text Available In this case–control study, we aimed to assess the intervention effects of four-session eye movement desensitization and reprocessing (EMDR on reducing the severity of disaster-related anxiety, general anxiety, and depressive symptoms in Taiwanese adolescents who experienced Typhoon Morakot. A total of 83 adolescents with posttraumatic stress disorder related to Typhoon Morakot, major depressive disorder, or current moderate or high suicide risk after experiencing Typhoon Morakot were allocated to a four-session course of EMDR (N = 41 or to treatment as usual (TAU; N = 42. A multivariate analysis of covariance was performed to examine the effects of EMDR in reducing the severity of disaster-related anxiety, general anxiety, and depressive symptoms in adolescents by using preintervention severity values as covariates. The multivariate analysis of covariance results indicated that the EMDR group exhibited significantly lower preintervention severity values of general anxiety and depression than did the TAU group. In addition, the preintervention severity value of disaster-related anxiety in the EMDR group was lower than that in the TAU group (p = 0.05. The results of this study support that EMDR could alleviate general anxiety and depressive symptoms and reduce disaster-related anxiety in adolescents experiencing major traumatic disasters.

  17. LWR Fuel Reprocessing and Recycle Program quarterly report, April 1--June 30, 1976

    Energy Technology Data Exchange (ETDEWEB)

    1976-07-01

    This quarterly report is the second in a series to be issued on the LWR Fuel Reprocessing and Recycle Program at ORNL as part of the national program administered by Savannah River Operations-Savannah River Laboratory. Several more dissolutions were made using irradiated fuel from the H. B. Robinson II reactor. Characterization of the solids and the resulting solutions is in progress and will be reported in the next quarterly. Requests for bids have been issued for the design and fabrication of a model 1/2 ton-per-day voloxidizer. Two mixer-settler units have been installed in the laboratory, and reference flowsheet studies using synthetic solutions have been initiated. The Fluorocarbon Absorption Studies program was expanded during this quarter to include acceleration of the pilot-plant development, the initiation of plant engineering design criteria, continuance of a system reliability analysis, and a study of the chemical effects of impurities in the fluorocarbon solvent on the process and equipment. Calculations have been made to provide mass balance data for a three-region PWR through successive recycle of self-generated plutonium.

  18. Transmutation Strategy Using Thorium-Reprocessed Fuel ADS for Future Reactors in Vietnam

    Directory of Open Access Journals (Sweden)

    Thanh Mai Vu

    2013-01-01

    Full Text Available Nuclear power is believed to be a key to the energy security for a developing country like Vietnam where the power demanding increases rapidly every year. Nevertheless, spent nuclear fuel from nuclear power plants is the source of radiotoxic and proliferation risk. A conceptual design of ADS utilizing thorium fuel as a based fuel and reprocessed fuel as a seed for nuclear waste transmutation and energy production is proposed as one of the clean, safe, and economical solutions for the problem. In the design, 96 seed assemblies and 84 blanket assemblies were inserted into the core to make a heterogeneous subcritical core configuration. Introducing thorium fuel into the core offers an effective way to transmute plutonium and minor actinide (MA and gain energy from this process. Transmutation rate as a function of burnup is estimated using MCNPX 2.7.0 code. Results show that by using the seed-blanket designed ADS, at 40 GWd/t burnup, 192 kg of plutonium and 156 kg of MA can be eliminated. Equivalently, 1  ADS can be able to transmute the transuranic (TRU waste from 2  LWRs. 14 units of ADS would be required to eliminate TRUs from the future reactors to be constructed in Vietnam.

  19. Adjustments to the MODIS Terra Radiometric Calibration and Polarization Sensitivity in the 2010 Reprocessing

    Science.gov (United States)

    Meister, Gerhard; Franz, Bryan A.

    2011-01-01

    The Moderate-Resolution Imaging Spectroradiometer (MODIS) on NASA s Earth Observing System (EOS) satellite Terra provides global coverage of top-of-atmosphere (TOA) radiances that have been successfully used for terrestrial and atmospheric research. The MODIS Terra ocean color products, however, have been compromised by an inadequate radiometric calibration at the short wavelengths. The Ocean Biology Processing Group (OBPG) at NASA has derived radiometric corrections using ocean color products from the SeaWiFS sensor as truth fields. In the R2010.0 reprocessing, these corrections have been applied to the whole mission life span of 10 years. This paper presents the corrections to the radiometric gains and to the instrument polarization sensitivity, demonstrates the improvement to the Terra ocean color products, and discusses issues that need further investigation. Although the global averages of MODIS Terra ocean color products are now in excellent agreement with those of SeaWiFS and MODIS Aqua, and image quality has been significantly improved, the large corrections applied to the radiometric calibration and polarization sensitivity require additional caution when using the data.

  20. Motion-based equilibrium reprocessing therapy a novel treatment method for chronic peripheral vestibulopathies

    Science.gov (United States)

    Hondebrink, Mirke S.; Mert, Agali; van der Lint, Roos; de Ru, J. Alexander; van der Wurff, Peter

    2017-01-01

    Abstract Rehabilitation for vestibular disease is a safe method to partially alleviate symptoms of vertigo. It was hypothesized that principles of military aviation vestibular desensitization procedures that have a success rate of more than 80% can be extrapolated to chronic vestibular disease as well. The virtual reality motion base computer-assisted rehabilitation environment was used as treatment modality in 17 patients. They were exposed to sinusoidal vertical passive whole body motion in increasing intensity for a maximum of 12 sessions. The Dizziness Handicap Inventory (DHI) was used for assessment of the subjective complaints of vertigo. The median DHI scores of 50 points at baseline dropped to 22 points (P <.001) at follow-up. Post hoc analysis showed significant differences in outcome between measurements at baseline and at the end of the treatment, between baseline and follow-up, but not between end of treatment and follow-up. This pilot study concerning motion-based equilibrium reprocessing therapy (MERT) shows that it is a simple, quick, and well-tolerated treatment option to alleviate symptoms in patients with chronic peripheral vestibulopathies. PMID:28614234

  1. Eye Movement Desensitization and Reprocessing and Slow Wave Sleep: A Putative Mechanism of Action

    Directory of Open Access Journals (Sweden)

    Marco Pagani

    2017-11-01

    Full Text Available Eye Movement Desensitization and Reprocessing (EMDR is considered highly efficacious for the treatment of Post-traumatic Stress Disorder and has proved to be a valid treatment approach with a wide range of applications. However, EMDR’s mechanisms of action is not yet fully understood. This is an active area of clinical and neurophysiological research, and several different hypotheses have been proposed. This paper discusses a conjecture which focuses on the similarity between the delta waves recorded by electroencephalography during Slow Wave Sleep (SWS and those registered upon typical EMDR bilateral stimulation (eye movements or alternate tapping during recurrent distressing memories of an emotionally traumatic event. SWS appears to have a key role in memory consolidation and in the reorganization of distant functional networks, as well as Eye Movements seem to reduce traumatic episodic memory and favor the reconsolidation of new associated information. The SWS hypothesis may put forward an explanation of how EMDR works, and is discussed also in light of other theories and neurobiological findings.

  2. Evaluation of the effect of reprocessing on the structure and properties of low density polyethylene/thermoplastic starch blends.

    Science.gov (United States)

    Peres, Anderson M; Pires, Ruthe R; Oréfice, Rodrigo L

    2016-01-20

    The great quantity of synthetic plastic discarded inappropriately in the environment is forcing the search for materials that can be reprocessable and biodegradable. Blends between synthetic polymers and natural and biodegradable polymers can be good candidates of such novel materials because they can combine processability with biodegradation and the use of renewable raw materials. However, traditional polymers usually present high levels of recyclability and use the well-established recycling infrastructure that can eventually be affected by the introduction of systems containing natural polymers. Thus, this work aims to evaluate the effect of reprocessing (simulated here by multiple extrusions) on the structure and properties of a low density polyethylene/thermoplastic starch (LDPE/TPS) blend compared to LDPE. The results indicated that multiple extrusion steps led to a reduction in the average size of the starch-rich phases of LDPE/TPS blends and minor changes in the mechanical and rheological properties of the materials. Such results suggest that the LDPE/TPS blend presents similar reprocessability to the LDPE for the experimental conditions used. Copyright © 2015 Elsevier Ltd. All rights reserved.

  3. The Effectiveness of Eye Movement Desensitization and Reprocessing Therapy on the Emotion Regulation and Emotion Recognition of Addicted Individuals

    Directory of Open Access Journals (Sweden)

    Soheyla Meysami-Bonab

    2012-10-01

    Full Text Available Background: The purpose of this study is to assess the effectiveness of eye movement desensitization and reprocessing therapy on the emotion regulation and emotion recognition of addicts with traumatic experience. Materials and Methods: This research is an experimental study with pre and post-test design and a control group. The subjects of this study were selected using random sampling method on drug addicts of Ardebil Addiction Treatment Camp who have successfully completed the detoxification period and they were evaluated in two different experimental (15 individuals and control (15 individuals groups. The experimental group was treated with EMDR therapy for 8 sessions (each one for 60 minutes and the control group received no special treatment. All participants filled a questionnaire of Emotion Regulation and Emotion Recognition at the onset of the research and 2 months after termination of treatment. For the data analysis, SPSS-17 software and covariance analysis were used.Results: The results of covariance analysis test indicated that the eye movement desensitization and reprocessing therapy intervention increased the average of positive emotion regulation and emotion recognition scores in the post-test phase and significantly reduced the average of negative emotion regulation scores.Conclusion: These results suggest that the treatment of eye movement desensitization and reprocessing is effective in improving regulation and recognition of emotions in addicts with traumatic experience.

  4. REPROCESSING CLOSE RANGE TERRESTRIAL AND UAV PHOTOGRAMMETRIC PROJECTS WITH THE DBAT TOOLBOX FOR INDEPENDENT VERIFICATION AND QUALITY CONTROL

    Directory of Open Access Journals (Sweden)

    A. Murtiyoso

    2017-11-01

    Full Text Available Photogrammetry has recently seen a rapid increase in many applications, thanks to developments in computing power and algorithms. Furthermore with the democratisation of UAVs (Unmanned Aerial Vehicles, close range photogrammetry has seen more and more use due to the easier capability to acquire aerial close range images. In terms of photogrammetric processing, many commercial software solutions exist in the market that offer results from user-friendly environments. However, in most commercial solutions, a black-box approach to photogrammetric calculations is often used. This is understandable in light of the proprietary nature of the algorithms, but it may pose a problem if the results need to be validated in an independent manner. In this paper, the Damped Bundle Adjustment Toolbox (DBAT developed for Matlab was used to reprocess some photogrammetric projects that were processed using the commercial software Agisoft Photoscan. Several scenarios were experimented on in order to see the performance of DBAT in reprocessing terrestrial and UAV close range photogrammetric projects in several configurations of self-calibration setting. Results show that DBAT managed to reprocess PS projects and generate metrics which can be useful for project verification.

  5. Reprocessing Close Range Terrestrial and Uav Photogrammetric Projects with the Dbat Toolbox for Independent Verification and Quality Control

    Science.gov (United States)

    Murtiyoso, A.; Grussenmeyer, P.; Börlin, N.

    2017-11-01

    Photogrammetry has recently seen a rapid increase in many applications, thanks to developments in computing power and algorithms. Furthermore with the democratisation of UAVs (Unmanned Aerial Vehicles), close range photogrammetry has seen more and more use due to the easier capability to acquire aerial close range images. In terms of photogrammetric processing, many commercial software solutions exist in the market that offer results from user-friendly environments. However, in most commercial solutions, a black-box approach to photogrammetric calculations is often used. This is understandable in light of the proprietary nature of the algorithms, but it may pose a problem if the results need to be validated in an independent manner. In this paper, the Damped Bundle Adjustment Toolbox (DBAT) developed for Matlab was used to reprocess some photogrammetric projects that were processed using the commercial software Agisoft Photoscan. Several scenarios were experimented on in order to see the performance of DBAT in reprocessing terrestrial and UAV close range photogrammetric projects in several configurations of self-calibration setting. Results show that DBAT managed to reprocess PS projects and generate metrics which can be useful for project verification.

  6. Contributions to a shallow aquifer study by reprocessed seismic sections from petroleum exploration surveys, eastern Abu Dhabi, United Arab Emirates

    Science.gov (United States)

    Woodward, D.

    1994-01-01

    The US Geological Survey, in cooperation with the National Drilling Company of Abu Dhabi, is conducting a 4-year study of the fresh and slightly saline groundwater resources of the eastern Abu Dhabi Emirate. Most of this water occurs in a shallow aquifer, generally less than 150 m deep, in the Al Ain area. A critical part of the Al Ain area coincides with a former petroleum concession area where about 2780 km of vibroseis data were collected along 94 seismic lines during 1981-1983. Field methods, acquistion parameters, and section processing were originally designed to enhance reflections expected at depths ranging from 5000 to 6000 m, and subsurface features directly associated with the shallow aquifer system were deleted from the original seismic sections. The original field tapes from the vibroseis survey were reprocessed in an attempt to extract shallow subsurface information (depths less than 550 m) for investigating the shallow aquifer. A unique sequence of reproccessing parameters was established after reviewing the results from many experimental tests. Many enhancements to the resolution of shallow seismic reflections resulted from: (1) application of a 20-Hz, low-cut filter; (2) recomputation of static corrections to a datum nearer the land surface; (3) intensive velocity analyses; and (4) near-trace muting analyses. The number, resolution, and lateral continuity of shallow reflections were greatly enhanced on the reprocessed sections, as was the delineation of shallow, major faults. Reflections on a synthetic seismogram, created from a borehole drilled to a depth of 786 m on seismic line IQS-11, matcheddprecisely with shallow reflections on the reprocessed section. The 33 reprocessed sections were instrumental in preparing a map showing the major structural features that affect the shallow aquifer system. Analysis of the map provides a better understanding of the effect of these shallow features on the regional occurrence, movement, and quality of

  7. Climate change : we are at risk : interim report

    Energy Technology Data Exchange (ETDEWEB)

    Oliver, D.; Wiebe, J.

    2003-06-01

    Between November 2002 and May 2003 the Standing Senate Committee on Agriculture and Forestry travelled across Canada to hear the views of farmer organizations, rural associations, ecotourism groups and environmental organizations regarding concerns about climate change and the impact it may have on the agriculture and forestry sectors and rural communities. The Committee also examined potential adaptation strategies focusing on primary production, practices, technologies, ecosystems and other related areas. Farmers and forest operators are already facing changes in market conditions, domestic regulations, trade policies and technology. This interim report expressed the concerns of farmers and forest operators. It includes a review of the Saguenay flood of 1996, the Red River flood of 1997, the ice storm of 1998, and droughts since 1999. It also includes a discussion on climate change and its biophysical and economic effects on agriculture, forestry, water resources, rural communities, and Aboriginal communities. This interim report also briefly outlines the Kyoto Protocol, the emissions trading system, and the decarbonization of global energy systems. It emphasized the need for integrated research and government policies and programs that encourage adaptation to climate change. The final report will be released in October 2003 and will provide specific recommendations to ensure that Canada responds to the concerns of farmers and forest operators and to ensure continued prosperity in these sectors. refs., figs.

  8. Interim sanitary landfill groundwater monitoring report. 1996 Annual report

    Energy Technology Data Exchange (ETDEWEB)

    Bagwell, L.A.

    1997-01-01

    Eight wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Interim Sanitary Landfill at the Savannah River Site. These wells are sampled semiannually to comply with the South Carolina Department of Health and Environmental Control Modified Municipal Solid Waste Permit 025500-1120 and as part of the SRS Groundwater Monitoring Program. Trichlorofluoromethane and 1,1,1-trichloroethane were elevated in one sidegradient well and one downgradient well during 1996. Zinc was elevated in three downgradient wells and also was detected in the associated laboratory blanks for two of those wells. Specific conductance was elevated in one background well and one sidegradient well. Barium and copper exceeded standards in one sidegradient well, and dichloromethane (a common laboratory contaminant) was elevated in another sidegradient well. Barium, copper, and dichloromethane were detected in the associated blanks for these wells, also. The groundwater flow direction in the Steed Pond Acquifer (Water Table) beneath the Interim Sanitary Landfill was to the southeast (universal transverse Mercator coordinates). The flow rate in this unit was approximately 210 ft/year during first quarter 1996 and 180 ft/yr during third quarter 1996.

  9. Technology, safety, and costs of decommissioning a reference nuclear fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, K.J.; Jenkins, C.E.; Rhoads, R.E.

    1977-09-01

    Safety and cost information were developed for the conceptual decommissioning of a fuel reprocessing plant with characteristics similar to the Barnwell Nuclear Fuel Plant. The main process building, spent fuel receiving and storage station, liquid radioactive waste storage tank system, and a conceptual high-level waste-solidification facility were postulated to be decommissioned. The plant was conceptually decommissioned to three decommissioning states or modes; layaway, protective storage, and dismantlement. Assuming favorable work performance, the elapsed time required to perform the decommissioning work in each mode following plant shutdown was estimated to be 2.4 years for layaway, 2.7 years for protective storage, and 5.2 years for dismantlement. In addition to these times, approximately 2 years of planning and preparation are required before plant shutdown. Costs, in constant 1975 dollars, for decommissioning were estimated to be $18 million for layaway, $19 million for protective storage and $58 million for dismantlement. Maintenance and surveillance costs were estimated to be $680,000 per year after layaway and $140,000 per year after protective storage. The combination mode of protective storage followed by dismantlement deferred for 10, 30, and 100 years was estimated to cost $64 million, $67 million and $77 million, respectively, in nondiscounted total 1975 dollars. Present values of these costs give reduced costs as dismantlement is deferred. Safety analyses indicate that radiological and nonradiological safety impacts from decommissioning activities should be small. The 50-year radiation dose commitment to the members of the public from airborne releases from normal decommissioning activities were estimated to be less than 11 man-rem.

  10. Silica-based waste form for immobilization of iodine from reprocessing plant off-gas streams

    Energy Technology Data Exchange (ETDEWEB)

    Matyáš, Josef, E-mail: Josef.Matyas@pnnl.gov [Radiological Materials & Technology Development, Pacific Northwest National Laboratory, P.O. Box 999, Richland, WA 99352 (United States); Canfield, Nathan [Electrochemical Materials and Systems, Pacific Northwest National Laboratory, P.O. Box 999, Richland, WA 99352 (United States); Sulaiman, Sannoh; Zumhoff, Mac [Radiological Materials & Technology Development, Pacific Northwest National Laboratory, P.O. Box 999, Richland, WA 99352 (United States)

    2016-08-01

    A high selectivity and sorption capacity for iodine and a feasible consolidation to a durable SiO{sub 2}-based waste form makes silver-functionalized silica aerogel (Ag{sup 0}-aerogel) an attractive choice for the removal and sequestration of iodine compounds from the off-gas of a nuclear fuel reprocessing plant. Hot uniaxial pressing of iodine-loaded Ag{sup 0}-aerogel (20.2 mass% iodine) at 1200 °C for 30 min under 29 MPa pressure provided a partially sintered product with residual open porosity of 16.9% that retained ∼93% of sorbed iodine. Highly iodine-loaded Ag{sup 0}-aerogel was successfully consolidated by hot isostatic pressing at 1200 °C with a 30-min hold and under 207 MPa. The fully densified waste form had a bulk density of 3.3 × 10{sup 3} kg/m{sup 3} and contained ∼39 mass% iodine. The iodine was retained in the form of nano- and micro-particles of AgI that were uniformly distributed inside and along boundaries of fused silica grains. - Highlights: • Silver-functionalized silica aerogel is an effective sorbent and a viable waste form for iodine. • Simultaneous application of fast heating rates and high pressures produced a fully dense product. • HIPing produced a fully consolidated waste form with a bulk density of 3.3 × 10{sup 3} kg/m{sup 3} and containing ∼39 mass% of iodine.

  11. Assessment of Endoscope Reprocessing Using Peer-to-Peer Assessment Through a Clinical Community.

    Science.gov (United States)

    Teter, Jonathan; Zenilman, Michael E; Wachter, Patricia

    2016-06-01

    Cleaning, disinfection, and sterilization (CDS) of medical devices are intended to help prevent health care-associated infections (HAIs), a significant cause of mortality and morbidity. In February 2013 the Johns Hopkins Health System (JHHS; Baltimore) formed a clinical community of experts and stakeholders--physicians, nurses, administrators, infection control practitioners, risk managers, and regulatory staff--to assess CDS practices across facilities. A survey administered to leadership indicated endoscopy areas of risk. An endoscopy tracer tool with eight major performance areas was then created from best practices identified in the literature, regulatory requirements, and national guidelines for endoscope reprocessing. Peer-to-peer (P2P) assessments using the tracer tool were performed at five Johns Hopkins Medicine gastrointestinal endoscopy sites (three hospital-based; two freestanding ambulatory surgery centers) selected on the basis of their large procedural volumes and their operational ability to participate in further areas of the project. The P2P assessments revealed that 20 (42%) of the 48 possible criteria had a noted deficiency at one or more sites. Three of the eight major performance areas on the tracer tool had no deficiencies identified at any of the five sites. Deficiencies were mostly minor process improvements, and only one critical process required immediate alteration of practice. Because the assessments were nonpunitive, horizontal communication enabled feedback on process improvements, alternate methods to achieve outcomes, and solutions to common issues. A nonpunitive and collaborative peer methodology was successful in capturing and sharing best practices in endoscopy areas. Successful replication in other clinical areas can be an effective way to assess CDS processes and facilitate dialogue for improvements.

  12. Glass ceramics containment matrix for insoluble residues coming from spent fuel reprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Pinet, O., E-mail: olivier.pinet@cea.fr; Boën, R.

    2014-04-01

    Spent fuel reprocessing by hydrometallurgical process generates insoluble residues waste streams called fines solution. Considering their radioactivity, fines solution could be considered as Intermediate Level Waste. This waste stream is usually mixed with fission products stream before vitrification. Thus fines are incorporated in glass matrix designed for High Level Waste. The withdrawal of fines from high level glass could decrease the volume of high level waste after conditioning. It could also decrease the reaction time between high level waste and additives to obtain a homogeneous melt and then increase the vitrification process capacity. Separated conditioning of fines in glass matrices has been tested. The fines content targeted value is 16 wt%. To achieve this objective, two types of glass ceramic formulations have been tested. 700 g of the two selected glass ceramics have been prepared using simulated fines. Additives used were ground glass. Melting is achieved at 1100 °C. According to the type of glass ceramic, reducing or oxidizing conditions have been performed during melting. Due to their composition and the melting redox conditions, different phases have been observed. These crystalline phases are typically RuO{sub 2}, metallic Ru, metallic Pd, MoO{sub 2} and CaMoO{sub 4}. In view of melting these matrices in an in can process the corrosiveness of one of the most oxidizing borosilicate glass ceramic formulation has been tested. This one has been remelted at 1100 °C in inconel 601 pot for 3 days. The oxygen fugacity measurement performed in the remelted glass leads to an oxidizing value, indicating that no significant reaction occurred between the inconel pot and the glass melt had occurred.

  13. NASADEM Initial Production Processing Results: Shuttle Radar Topography Mission (SRTM) Reprocessing with Improvements

    Science.gov (United States)

    Buckley, S.; Agram, P. S.; Belz, J. E.; Crippen, R. E.; Gurrola, E. M.; Hensley, S.; Kobrick, M.; Lavalle, M.; Martin, J. M.; Neumann, M.; Nguyen, Q.; Rosen, P. A.; Shimada, J.; Simard, M.; Tung, W.

    2016-12-01

    NASADEM is a significant modernization of SRTM digital elevation model (DEM) data supported by the NASA MEaSUREs program. We are reprocessing the raw radar signal data using improved algorithms and incorporating ICESat and DEM data unavailable during the original processing. The NASADEM products will be freely-available through the Land Processes Distributed Active Archive Center (LPDAAC) at one-arcsecond spacing and delivered by continent: North America, South America, Australia, Eurasia, Africa, and Island Groups. We are in the production phase of the project. This involves radar interferometry (InSAR) processing on thousands of radar datatakes. New phase unwrapping and height ripple error correction (HREC) procedures are applied to the data. The resulting strip DEMs and ancillary information are passed to a back-end processor to create DEM mosaics and new geocoded single-swath products. Manual data quality assessment (QA) and fixes are performed at several steps in the processing chain. Post-production DEM void-filling is described in a companion AGU Fall Meeting presentation. The team completed the InSAR processing for all continents and the manual QA of the strip DEMs for more than half the world. North America strip DEM void areas are reduced by more than 50%. The ICESat data is used for height ripple error correction and as control for continent-scale adjustment of the strip DEMs. These ripples are due to uncompensated mast motion most pronounced after Shuttle roll angle adjustment maneuvers. After an initial assessment of the NASADEM production processing for the Americas, we further refined the selection of ICESat data for control by excluded data over glaciers, snow cover, forest clear cuts, and sloped areas. The HREC algorithm reduces the North America ICESat-SRTM bias from 80 cm to 3 cm and the RMS from 5m to 4m.

  14. Application of the pyrochemical DOS, developed by the CEA, within reprocessing of CERCER transmutation fuel targets

    Energy Technology Data Exchange (ETDEWEB)

    Mendes, E.; Ducasse, T.; Bertrand, M. [CEA, Centre de Marcoule, Nuclear Energy Division, Radiochemistry and Processes Department, SMCS, LDPS, F-30207 Bagnols-sur-Ceze (France); Miguirditchian, M. [CEA, Centre de Marcoule, Nuclear Energy Division, Radiochemistry and Processes Department, SMCS, LCPE, F-30207 Bagnols-sur-Ceze (France)

    2016-07-01

    Pyrochemical technology using high-temperature molten salts and molten metal media presents a potential interest for an overall separation and transmutation strategy for long-lived radionuclides. Within the frame of the two French acts on radioactive waste management, a pyrochemical research/development program was launched at the CEA Marcoule in the late 90's. The second step is the actinides back-extraction, which consists in a liquid/liquid oxidative stripping of the An from aluminium matrix into molten chloride media. The DOS process has been successfully demonstrated for treatment of oxide type fuels within the last years: the core of the process has been already assessed and the studies have shown high selectivity and a quantitative recovery of actinides. Within the framework of the SACSESS European research program, the pyrochemical activities focused on applications of the DOS process to reprocess CERCER transmutation targets. These particular types of fuels consist of a mixture of minor actinides (MA) oxides diluted in an inert (oxide MgO) matrices. The behaviour of matrices material was first investigated regarding the solubility in the fluoride salt, starting from both oxide powders or sintered pellets. The saturation of Mg in the salt could be estimated at ∼ 3 wt%. Regarding the reductive extraction, as expected no Mg was reduced by the metallic phase. The present work also highlights that Mg has low impact on the extraction efficiency of U as long as the salt is not saturated. Once the saturation occurs, the efficiency starts to decrease. So we recommend recycling the salt when Mg saturation is reached.

  15. Neurophysiological correlates of eye movement desensitization and reprocessing sessions: preliminary evidence for traumatic memories integration.

    Science.gov (United States)

    Farina, Benedetto; Imperatori, Claudio; Quintiliani, Maria I; Castelli Gattinara, Paola; Onofri, Antonio; Lepore, Marta; Brunetti, Riccardo; Losurdo, Anna; Testani, Elisa; Della Marca, Giacomo

    2015-11-01

    We have investigated the potential role of eye movement desensitization and reprocessing (EMDR) in enhancing the integration of traumatic memories by measuring EEG coherence, power spectra and autonomic variables before (pre-EMDR) and after (post-EMDR) EMDR sessions during the recall of patient's traumatic memory. Thirteen EMDR sessions of six patients with post-traumatic stress disorder were recorded. EEG analyses were conducted by means of the standardized Low Resolution Electric Tomography (sLORETA) software. Power spectra, EEG coherence and heart rate variability (HRV) were compared between pre- and post-EMDR sessions. After EMDR, we observed a significant increase of alpha power in the left inferior temporal gyrus (T = 3.879; P = 0.041) and an increased EEG coherence in beta band between C3 and T5 electrodes (T = 6.358; P < 0.001). Furthermore, a significant increase of HRV in the post-EMDR sessions was also observed (pre-EMDR: 6.38 ± 6.83; post-EMDR: 2.46 ± 2.95; U-Test = 45, P = 0.043). Finally, the values of lagged coherence were negatively associated with subjective units of disturbance (r(24) = -0.44, P < 0.05) and positively associated with parasympathetic activity (r(24) = 0.40, P < 0.05). Our results suggest that EMDR leads to an integration of dissociated aspects of traumatic memories and, consequently, a decrease of hyperarousal symptoms [Correction made here after initial publication]. © 2014 Scandinavian Society of Clinical Physiology and Nuclear Medicine. Published by John Wiley & Sons Ltd.

  16. An X-Ray Reprocessing Model of Disk Thermal Emission in Type 1 Seyfert Galaxies

    Science.gov (United States)

    Chiang, James; White, Nicholas E. (Technical Monitor)

    2002-01-01

    Using a geometry consisting of a hot central Comptonizing plasma surrounded by a thin accretion disk, we model the optical through hard X-ray spectral energy distributions of the type 1 Seyfert. galaxies NGC 3516 and NGC 7469. As in the model proposed by Poutanen, Krolik, and Ryde for the X-ray binary Cygnus X-1 and later applied to Seyfert galaxies by Zdziarski, Lubifiski, and Smith, feedback between the radiation reprocessed by the disk and the thermal Comptonization emission from the hot central plasma plays a pivotal role in determining the X-ray spectrum, and as we show, the optical and ultraviolet spectra as well. Seemingly uncorrelated optical/UV and X-ray light curves, similar to those which have been observed from these objects can, in principle, be explained by variations in the size, shape, and temperature of the Comptonizing plasma. Furthermore, by positing a disk mass accretion rate which satisfies a condition for global energy balance between the thermal Comptonization luminosity and the power available from accretion, one can predict the spectral properties of the heretofore poorly measured hard X-ray continuum above approximately 50 keV in type 1 Seyfert galaxies. Conversely, forthcoming measurements of the hard X-ray continuum by more sensitive hard X-ray and soft gamma-ray telescopes, such as those aboard the International Gamma-Ray Astrophysics Laboratory (INTEGRAL) in conjunction with simultaneous optical, UV, and soft X-ray monitoring, will allow the mass accretion rates to be directly constrained for these sources in the context of this model.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-04-03

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

  18. Age of stratospheric air in the ERA-Interim

    Directory of Open Access Journals (Sweden)

    M. Diallo

    2012-12-01

    Full Text Available The Brewer-Dobson mean circulation and its variability are investigated in the ERA-Interim over the period 1989-2010 by using an off-line Lagrangian transport model driven by analysed winds and heating rates.

    At low and mid-latitudes, the mean age of air in the lower stratosphere is in good agreement with ages derived from aircraft, high altitude balloon and satellite observations of long-lived tracers. At high latitude and in the upper stratosphere, we find, however that the ERA-Interim ages exhibit an old bias, typically of one to two years.

    The age spectrum exhibits a long tail except in the low tropical stratosphere which is modulated by the annual cycle of the tropical upwelling. The distribution of ages and its variability is consistent with the existence of two separate branches, shallow and deep, of the Brewer-Dobson circulation. Both branches are modulated by the tropical upwelling and the shallow branch is also modulated by the subtropical barrier.

    The variability of the mean age is analysed through a decomposition in terms of annual cycle, QBO, ENSO and trend. The annual modulation is the dominating signal in the lower stratosphere and is maximum at latitudes greater than 50° in both hemispheres with oldest ages at the end of the winter. The phase of the annual modulation is also reversed between below and above 25 km. The maximum amplitude of the QBO modulation is of about 0.5 yr and is mostly concentrated within the tropics between 25 and 35 km. It lags the QBO wind at 30 unit{hPa} by about 8 months. The ENSO signal is small and limited to the lower northen stratosphere.

    The age trend over the 1989–2010 period, according to this ERA-Interim dataset, is significant and negative, of the order of −0.3 to −0.5 yr dec−1, within the lower stratosphere in the Southern Hemisphere and south of 40° N in the Northern Hemisphere below 25 km. The age trend is positive (of the order of 0

  19. Thorium utilization program. Quarterly progress report for the period ending May 31, 1977

    Energy Technology Data Exchange (ETDEWEB)

    1977-06-01

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

  20. Advanced nuclear reactor public opinion project. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    Benson, B.

    1991-07-25

    This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.

  1. Veterans Employment Pay for Success Grant Program. Interim final rule.

    Science.gov (United States)

    2016-08-10

    The Department of Veterans Affairs (VA) is establishing a grant program (Veterans Employment Pay for Success (VEPFS)) under the authority of the U.S.C. to award grants to eligible entities to fund projects that are successful in accomplishing employment rehabilitation for Veterans with service-connected disabilities. VA will award grants on the basis of an eligible entity's proposed use of a Pay for Success (PFS) strategy to achieve goals. This interim final rule establishes regulations for awarding a VEPFS grant, including the general process for awarding the grant, criteria and parameters for evaluating grant applications, priorities related to the award of a grant, and general requirements and guidance for administering a VEPFS grant program.

  2. SNF Interim Storage Canister Corrosion and Surface Environment Investigations

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, Charles R. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Enos, David G. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2015-09-01

    This progress report describes work being done at Sandia National Laboratories (SNL) to assess the localized corrosion performance of container/cask materials used in the interim storage of spent nuclear fuel (SNF). Of particular concern is stress corrosion cracking (SCC), by which a through-wall crack could potentially form in a canister outer wall over time intervals that are shorter than possible dry storage times. In order for SCC to occur, three criteria must be met. A corrosive environment must be present on the canister surface, the metal must susceptible to SCC, and sufficient tensile stress to support SCC must be present through the entire thickness of the canister wall. SNL is currently evaluating the potential for each of these criteria to be met.

  3. Health Resources Priority and Allocations System (HRPAS). Interim final rule.

    Science.gov (United States)

    2015-07-17

    This interim final rule establishes standards and procedures by which the U.S. Department of Health and Human Services (HHS) may require that certain contracts or orders that promote the national defense be given priority over other contracts or orders. This rule also sets new standards and procedures by which HHS may allocate materials, services, and facilities to promote the national defense. This rule will implement HHS's administration of priorities and allocations actions, and establish the Health Resources Priorities and Allocation System (HRPAS). The HRPAS will cover health resources pursuant to the authority under Section 101(c) of the Defense Production Act as delegated to HHS by Executive Order 13603. Priorities authorities (and other authorities delegated to the Secretary in E.O. 13603, but not covered by this regulation) may be re-delegated by the Secretary. The Secretary retains the authority for allocations.

  4. 1998 interim 242-A Evaporator tank system integrity assessment report

    Energy Technology Data Exchange (ETDEWEB)

    Jensen, C.E.

    1998-07-02

    This Integrity Assessment Report (IAR) is prepared by Fluor Daniel Northwest (FDNW) under contract to Lockheed-Martin Hanford Company (LMHC) for Waste Management Hanford (WMH), the 242-A Evaporator (facility) operations contractor for Fluor Daniel Hanford, and the US Department of Energy, the system owner. The contract specifies that FDNW perform an interim (5 year) integrity assessment of the facility and prepare a written IAR in accordance with Washington Administrative Code (WAC) 173-303-640. The WAC 173-303 defines a treatment, storage, or disposal (TSD) facility tank system as the ``dangerous waste storage or treatment tank and its ancillary equipment and containment.`` This integrity assessment evaluates the two tank systems at the facility: the evaporator vessel, C-A-1 (also called the vapor-liquid separator), and the condensate collection tank, TK-C-100. This IAR evaluates the 242-A facility tank systems up to, but not including, the last valve or flanged connection inside the facility perimeter. The initial integrity assessment performed on the facility evaluated certain subsystems not directly in contact with dangerous waste, such as the steam condensate and used raw water subsystems, to provide technical information. These subsystems were not evaluated in this IAR. The last major upgrade to the facility was project B-534. The facility modifications, as a result of project B-534, were evaluated in the 1993 facility interim integrity assessment. Since that time, the following upgrades have occurred in the facility: installation of a process condensate recycle system, and installation of a package steam boiler to provide steam for the facility. The package boiler is not within the scope of the facility TSD.

  5. Effectiveness of Eye Movement Desensitization and Reprocessing on Anxiety in Children with Thalassemia in a 12-month follow up

    Directory of Open Access Journals (Sweden)

    A Shahnavazi

    2016-02-01

    Full Text Available Background and  Objective: Thalassemia is the most common genetic diseases in the world and especially in our country. For many reasons, including chronic disease, health care costs, the expected mortality Ray disease states such as anxiety, psychological and social problems in thalassemia. The aim of the present study was to assess the efficacy of Eye Movement Desensitization and Reprocessing (EMDR on anxiety of children with thalassemia in a 12-month follow up..  Methods: It was a clinical trial study, which was performed on 60 patients with Thalassemia in 2013-2014. A total of 60 thalassemic patients based on Beck anxiety inventory, selected using sampling and were randomly divided into experimental and Control groups. in experimental group, eye movement desensitization and reprocessing therapy was perfomed in five sessions and The control group received no intervention. In order to collect information on demographic questionnaire and Beck Anxiety Inventory were used. data were gathered on anxiety symptoms at pretreatment, posttreatment and 12 month follow up and were analyzed using descriptive statistics, repeated measures and chi square. Results: The average age of the participants was 15.22±1.93  years old. This study shows that the mean or average level of anxiety children with thalassemia in the experimental group before and after intervention and in a 12-month follow up group 34.73 ± 5.62, 19.90 ± 2.48 and 19.23 ± 2.48 respectively; repeated measures ANOVA showed significant statistical difference (p.05 Conclusion: This study shows that Method of eye movement desensitization and reprocessing as an alternative method to treat or reduce anxiety, aggressive children with thalassemia .Trained Nurses can use this new method is effective in the treatment of anxiety.

  6. Treatment of PTSD by eye movement desensitization reprocessing (EMDR) improves sleep quality, quality of life, and perception of stress.

    Science.gov (United States)

    Raboni, Mara Regina; Tufik, Sergio; Suchecki, Deborah

    2006-07-01

    The impact of posttraumatic stress disorder (PTSD) on the sleep of patients is widely reported. However, the parameters that can be altered are not the same for all patients. Some studies report an impairment of sleep maintenance and recurrent nightmares, while others failed to find such alterations. Among the many treatments, the eye movement desensitization reprocessing (EMDR) is a therapy used specifically to treat PTSD and general trauma. The purpose of this study was to examine whether EMDR treatment can improve PTSD symptoms, such as sleep, depression, anxiety, and poor quality of life.

  7. DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

    Energy Technology Data Exchange (ETDEWEB)

    T. A. Lee

    2005-09-15

    The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

  8. Basis for Interim Operation for the K-Reactor in Cold Standby

    Energy Technology Data Exchange (ETDEWEB)

    Shedrow, B.

    1998-10-19

    The Basis for Interim Operation (BIO) document for K Reactor in Cold Standby and the L- and P-Reactor Disassembly Basins was prepared in accordance with the draft DOE standard for BIO preparation (dated October 26, 1993).

  9. Fabrication of an Implant-Supported Fixed Interim Prosthesis Using a Duplicate Denture: An Alternative Technique.

    Science.gov (United States)

    Al-Thobity, Ahmad M

    2016-06-22

    The fabrication of an implant-supported fixed complete denture prosthesis involves multiple clinical and laboratory steps. One of the main steps is to provide the patient with an interim fixed prosthesis to evaluate the patient's esthetic and functional needs as well as to enhance the patient's psychology before proceeding to the definitive prosthesis. Different techniques for fabricating interim prostheses have been described in the literature. This report describes an alternative technique that uses a duplicate denture made of self-curing acrylic resin to fabricate an implant-supported fixed interim prosthesis. The interim prosthesis was later used as a blueprint for the definitive implant-supported hybrid prosthesis. © 2016 by the American College of Prosthodontists.

  10. Sample results from the interim salt disposition program macrobatch 9 tank 21H qualification samples

    Energy Technology Data Exchange (ETDEWEB)

    Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-11-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 9 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H.

  11. U.S. Fish and Wildlife Service : Rocky Mountain Arsenal : Interim Plan for Weekend Visitor Access

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — This is an interim plan for weekend visitors designed to provide for the safety of visitors to the Rocky Mountain Arsenal during its remediation and transition to a...

  12. Interim report for defining brine and oil threats in the Patoka River National Wildlife Refuge [2002

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — The following interim report is a list of activities being performed in conjunction with the study of oil brine effects on crayfish in the Patoka River National...

  13. The Interim Implementation Plan Report in Support of the Information Sharing Environment

    National Research Council Canada - National Science Library

    2006-01-01

    ...). This interim report describes the 11 requirements stated in IRTPA and provides a road map for developing the comprehensive Implementation Plan for the ISE, which is expected to be submitted to the Congress in July 2006...

  14. LANDFILLS AS BIOREACTORS: RESEARH AT THE OUTER LOOP LANDFILL, LOUISVILLE, KENTUCKY; FIRST INTERIM REPORT

    Science.gov (United States)

    Interim report resulting from a cooperative research and development agreement (CRADA) between US EP A's Officeof Research and Development - National Risk Management Research Laboratory and a n ongoing field demonstrationof municipal waste landfills being operated as bioreact...

  15. Interim revision of the South African Mechanistic-Empirical pavement design method for flexible pavements

    CSIR Research Space (South Africa)

    Theyse, HL

    2011-09-01

    Full Text Available an interim revision of the SAMDM recommending increased contact stress values at the tyre-pavement interface; updated unbound material characterisation parameters; effective stress analysis for unbound material; and revised damage models for estimating...

  16. Reprocessing COCORP Seismic Reflection Data to Image Deep Crustal Structure in the Wind River Mountains, Wyoming

    Science.gov (United States)

    Bressers, C. A.; Plescia, S. M.; Sheehan, A. F.; Cook, S. W.; Whitney, M. D.

    2016-12-01

    Characterizing deformation in the basement-cored uplifts that occurred during rapid exhumation in the Laramide orogeny (65-50Ma) is critical to understanding the formation of the Cordilleran foreland thrust and fold belt of Wyoming and Colorado. The Wind River Thrust (WRT) fault in west-central Wyoming has been studied as a model for Laramide basement-cored uplifts. We reprocessed two lines of active source seismic reflection data that cross-cut the WRT to determine the shape of the thrust at depth and the shape of the Moho and midcrustal reflectors beneath the fault. The Vibroseis seismic survey, collected in 1976 and 1977 by the Consortium for Continental Reflection Profiling (COCORP), spans 106 km and runs perpendicular to the WRT, across the Wind River Mountains and flanking basins. The COCORP field gathers were recorded to 20-second two-way travel time with maximum offsets of 6.8 km for Line 1 and 9.9 km for Line 1A. The data was processed to 24-fold common-depth-point (CDP) correlated gathers. We used modern industry-standard processing software suites by Paradigm and XtremeGeo. The processing flow included: CDP stacking, normal moveout (NMO) correction with applied stretch mute, refraction velocity analysis and statics, multiple passes of reflection velocity analysis surface-consistent deconvolution and finite-difference post-stack time migration. We focused on generating statics to handle the effects of significant lateral heterogeneity in the velocity. We found that a tomographic solution for the refraction velocity model produced the best results for producing statics to remove the effects of the weathering layer. Additionally, careful selection of a reflection velocity model greatly improved the resolution, especially along the fault and the basin-fault boundary. Using a post-stack time migration at 80% of the reflection velocity model corrected an artefact of overcorrection in an earlier migration. Our migration has reconfirmed the shallow dip of the

  17. PRELIMINARY STUDY OF CERAMICS FOR IMMOBILIZATION OF ADVANCED FUEL CYCLE REPROCESSING WASTES

    Energy Technology Data Exchange (ETDEWEB)

    Fox, K.; Billings, A.; Brinkman, K.; Marra, J.

    2010-09-22

    The Savannah River National Laboratory (SRNL) developed a series of ceramic waste forms for the immobilization of Cesium/Lanthanide (CS/LN) and Cesium/Lanthanide/Transition Metal (CS/LN/TM) waste streams anticipated to result from nuclear fuel reprocessing. Simple raw materials, including Al{sub 2}O{sub 3}, CaO, and TiO{sub 2} were combined with simulated waste components to produce multiphase ceramics containing hollandite-type phases, perovskites (particularly BaTiO{sub 3}), pyrochlores, zirconolite, and other minor metal titanate phases. Identification of excess Al{sub 2}O{sub 3} via X-ray Diffraction (XRD) and Scanning Electron Microscopy with Energy Dispersive Spectroscopy (SEM/EDS) in the first series of compositions led to a Phase II study, with significantly reduced Al{sub 2}O{sub 3} concentrations and increased waste loadings. Three fabrication methodologies were used, including melting and crystallizing, pressing and sintering, and Spark Plasma Sintering (SPS), with the intent of studying phase evolution under various sintering conditions. XRD and SEM/EDS results showed that the partitioning of the waste elements in the sintered materials was very similar, despite varying stoichiometry of the phases formed. The Phase II compositions generally contained a reduced amount of unreacted Al{sub 2}O{sub 3} as identified by XRD, and had phase assemblages that were closer to the initial targets. Chemical composition measurements showed no significant issues with meeting the target compositions. However, volatilization of Cs and Mo was identified, particularly during melting, since sintering of the pressed pellets and SPS were performed at lower temperatures. Partitioning of some of the waste components was difficult to determine via XRD. SEM/EDS mapping showed that those elements, which were generally present in small concentrations, were well distributed throughout the waste forms. Initial studies of radiation damage tolerance using ion beam irradiation at Los

  18. Estimation of GPS satellite antenna z-offsets from reprocessed SINEX files

    Science.gov (United States)

    Schmid, Ralf; Collilieux, Xavier; Steigenberger, Peter; Hugentobler, Urs

    2010-05-01

    Since November 2006 an absolute phase center correction model for GNSS satellite and receiver antennas has been used within the International GNSS Service (IGS). This model, called igs05.atx, comprises consistent phase center offset and variation values given in ANTEX format. Generally, these correction values have not been changed in the meantime. Solely values for new receiver antenna types or newly launched satellites have been added. With view to the upcoming transition to ITRF2008, a general update of the IGS antenna phase center model is in progress that will be called igs08.atx. Therefore, reprocessed weekly SINEX files of several IGS analysis centers (ACs) will be analyzed to derive new GPS satellite antenna z-offsets. These values will be based on more data (16 instead of 11 years) and more ACs than the values currently used, and they will also cover the latest satellites launched in recent years. As selected station coordinates will be fixed to ITRF2008 when back-solving the SINEX files, the antenna model will be fully consistent with the corresponding terrestrial reference frame. For the z-offsets contained in igs05.atx this is not the case. At the time those were estimated, the solutions could only be aligned to IGb00, an IGS realization of ITRF2000, but not to ITRF2005. Whereas absolute receiver antenna corrections were applied for these computations, the underlying reference frame was based on relative corrections, and the effect of radomes could not be considered. Moreover, an error in the mean vertical velocity of IGb00 caused a significant trend in the z-offset time series of all satellites. Thus, they could only be given for a specific epoch. We will compare z-offset time series from the computations for igs05.atx and igs08.atx to demonstrate the reduction of trends and the improvement of the overall consistency. Resulting biases between individual ACs will highlight scale-related discrepancies, and the general agreement between the two phase

  19. Reprocessing and clearance as ways for reducing radioactive waste from fusion reactors

    Energy Technology Data Exchange (ETDEWEB)

    Rocco, P.; Zucchetti, M. [Energetics Dept., Polytechnic of Turin (Italy); Zucchetti, M. [European Commission, JRC, Institute for Advanced Material, Ispra, Vatican City State, Holy See (Italy)

    1998-07-01

    The irradiated material chosen to investigate this concept is V-4Cr-4Ti, used as in-vessel structural material of PM-1, one of the three reactor models of SEAFP-2 assessments. The analysis performed deserves the following comments: in general, the modified concentrations of the parent isotopes have been assumed equal to the actual detection limits of the concerned elements. The nuclides investigated are those having the higher activities in the irradiated alloy (dominant nuclides). The contribution to the clearance index of other nuclides, present in the irradiated alloy and not yet examined should also be assessed. Even having reduced the concentrations of the impurities to the very low levels hypothesized, the ratios (A/L{sub c}){sub m} of some nuclides are too great. Beside K-42 and Ar-42, deriving from titanium, this happens for nuclides deriving from niobium, silver, nickel, copper, strontium. Hence the clearance index of the modified alloy is greater than the unity and clearance conditions are not achieved. Additional purification process have to be envisaged after the irradiation, with an elemental dilution of the noxious nuclides and then performing a purification process. As an example, it is found from table 2 that the sum of the ratios (A/L{sub c}){sub m} of Nb-93m, Nb-91 and Nb-94, nuclides deriving from a concentration of 2 x 10{sup -2} ppm of niobium, is 7.75. An addition of 5/10 ppm of natural niobium to the molten irradiated material and a further purification of niobium to levels near to the initial one could achieve a 100-fold reduction of the ratios (A/L{sub c}){sub m}. 10000 t of V-4Cr4Ti, representing the total amount (maintenance + decommissioning) arising from the in vessel structures of a power reactor should be reprocessed with 100 kg of niobium, in the highly conservative hypothesis that all material is irradiated in first wall conditions. The secondary waste arising from the purification processes would not exceed a few ton which could be

  20. Effects of eye movement desensitization and reprocessing (EMDR) treatment in chronic pain patients: a systematic review.

    Science.gov (United States)

    Tesarz, Jonas; Leisner, Sabine; Gerhardt, Andreas; Janke, Susanne; Seidler, Günter H; Eich, Wolfgang; Hartmann, Mechthild

    2014-02-01

    This study systematically reviewed the evidence regarding the effects of eye movement desensitization and reprocessing (EMDR) therapy for treating chronic pain. Systematic review. We screened MEDLINE, EMBASE, the Cochrane Library, CINHAL Plus, Web of Science, PsycINFO, PSYNDEX, the Francine Shapiro Library, and citations of original studies and reviews. All studies using EMDR for treating chronic pain were eligible for inclusion in the present study. The main outcomes were pain intensity, disability, and negative mood (depression and anxiety). The effects were described as standardized mean differences. Two controlled trials with a total of 80 subjects and 10 observational studies with 116 subjects met the inclusion criteria. All of these studies assessed pain intensity. In addition, five studies measured disability, eight studies depression, and five studies anxiety. Controlled trials demonstrated significant improvements in pain intensity with high effect sizes (Hedges' g: -6.87 [95% confidence interval (CI95 ): -8.51, -5.23] and -1.12 [CI95 : -1.82, -0.42]). The pretreatment/posttreatment effect size calculations of the observational studies revealed that the effect sizes varied considerably, ranging from Hedges' g values of -0.24 (CI95 : -0.88, 0.40) to -5.86 (CI95 : -10.12, -1.60) for reductions in pain intensity, -0.34 (CI95 : -1.27, 0.59) to -3.69 (CI95 : -24.66, 17.28) for improvements in disability, -0.57 (CI95 : -1.47, 0.32) to -1.47 (CI95 : -3.18, 0.25) for improvements in depressive symptoms, and -0.59 (CI95 : -1.05, 0.13) to -1.10 (CI95 : -2.68, 0.48) for anxiety. Follow-up assessments showed maintained improvements. No adverse events were reported. Although the results of our study suggest that EMDR may be a safe and promising treatment option in chronic pain conditions, the small number of high-quality studies leads to insufficient evidence for definite treatment recommendations. Wiley Periodicals, Inc.

  1. Will interim storage sites become ultimate storage sites?; Werden aus Zwischenlager Endlager?

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, W.P. [ia GmbH - Wissensmanagement und Ingenieurleistungen, Muenchen (Germany)

    2007-07-01

    According to a Prognos study, the maximum interim storage capacity required in Germany in 2008 will be 4 - 5 million cubic metres. Interim storage is necessary because there are not sufficient options for disposal. The stored waste will be combusted, so that German incinerators will be capable of running at full capacity until 2013. From mere disposal systems, incinerators are rapidly becoming waste-to-energy systems that will make a contribution to power supply. (orig.)

  2. DATA MINING METHODOLOGY FOR DETERMINING THE OPTIMAL MODEL OF COST PREDICTION IN SHIP INTERIM PRODUCT ASSEMBLY

    Directory of Open Access Journals (Sweden)

    Damir Kolich

    2016-03-01

    Full Text Available In order to accurately predict costs of the thousands of interim products that are assembled in shipyards, it is necessary to use skilled engineers to develop detailed Gantt charts for each interim product separately which takes many hours. It is helpful to develop a prediction tool to estimate the cost of interim products accurately and quickly without the need for skilled engineers. This will drive down shipyard costs and improve competitiveness. Data mining is used extensively for developing prediction models in other industries. Since ships consist of thousands of interim products, it is logical to develop a data mining methodology for a shipyard or any other manufacturing industry where interim products are produced. The methodology involves analysis of existing interim products and data collection. Pre-processing and principal component analysis is done to make the data “user-friendly” for later prediction processing and the development of both accurate and robust models. The support vector machine is demonstrated as the better model when there are a lower number of tuples. However as the number of tuples is increased to over 10000, then the artificial neural network model is recommended.

  3. Controversies on the prognostic value of interim FDG-PET in advanced-stage Hodgkin lymphoma.

    Science.gov (United States)

    Adams, Hugo J A; Kwee, Thomas C

    2016-12-01

    Hodgkin lymphoma, even in advanced-stage, is a highly curable malignancy, but treatment is associated with short-term toxicity and long-term side effects. Early predictive markers are required to identify those patients who do not require the full-length standard therapy (and thus qualify for therapy de-escalation) and those patients who will not be cured by standard therapy (and thus qualify for therapy escalation). Multiple trials have assessed the value of (18) F-fluoro-2-deoxy-d-glucose positron emission tomography (FDG-PET) after a few cycles of chemotherapy (also known as 'interim FDG-PET') in predicting outcome in advanced-stage Hodgkin lymphoma. Furthermore, multiple interim FDG-PET-adapted trials, in which patients with positive interim FDG-PET scans are assigned to escalated therapies, and patients with negative interim FDG-PET scans are assigned to de-escalated therapies, have recently been published or are currently ongoing, with generally heterogeneous results. The present article reports the currently available evidence (and controversies) on the prognostic value of interim FDG-PET in advanced-stage Hodgkin lymphoma in patients with positive and negative interim FDG-PET findings following continuation of standard chemotherapy or escalated/de-escalated therapy. © 2016 John Wiley & Sons A/S. Published by John Wiley & Sons Ltd.

  4. Effect of Extrusion on the Mechanical and Rheological Properties of a Reinforced Poly(Lactic Acid): Reprocessing and Recycling of Biobased Materials

    Science.gov (United States)

    Peinado, Víctor; Castell, Pere; García, Lidia; Fernández, Ángel

    2015-01-01

    The aim of this research paper is to study the behaviour of a common used biopolymer (Poly(Lactic Acid) (PLA)) after several reprocesses and how two different types of additives (a melt strength enhancer and a nanoadditive) affect its mechanical and rheological properties. Systematic extraction of extrudate samples from a twin-screw compounder was done in order to study the effect in the properties of the reprocessed material. Detailed rheological tests on a capillary rheometer as well as mechanical studies on a universal tensile machine after preparation of injected specimens were carried out. Results evidenced that PLA and reinforced PLA materials can be reprocessed and recycled without a remarkable loss in their mechanical properties. Several processing restrictions and specific phenomena were identified and are explained in the present manuscript. PMID:28793622

  5. Study on the technique of spent fuel reprocessing with supercritical fluid direct extraction method (Super-DIREX method)

    Energy Technology Data Exchange (ETDEWEB)

    Shimada, Takashi; Ogumo, Shinya [Mitsubishi Heavy Industries Ltd., Kobe, Hyogo (Japan); Ishihara, Nobuo [Mitsubishi Heavy Industries Ltd., Takasago, Hyogo (Japan); Kosaka, Yuji [Nuclear Development Corp., Tokai, Ibaraki (Japan); Mori, Yukihide [Mitsubishi Heavy Industries Ltd., Yokohama, Kanagawa (Japan)

    2002-11-01

    The spent fuel reprocessing method with supercritical fluid has been developed. Uranium and plutonium elements can be extracted directly from spent fuel oxides by supercritical carbon dioxide (CO{sub 2}) containing nitric acid and tributylphosphate (HNO{sub 3}-TBP) complex at 313-333K and 10-20 MPa. It is called Super-DIREX method which stands for Supercritical fluid Direct Extraction method. In Super-DIREX method, the process from dissolution to extraction(co-decontamination) in PUREX is consolidated to one component of direct extraction column', so that the cost of the spent fuel reprocessing plant is expected to be reduced from purex process. In order to evaluate the ability of extraction, basic tests have been carried out using unirradiated uranium oxide with artificial fission products (FPs) oxide. The concentration of uranium extracted in supercritical fluid and the decontamination factor (DF) of the FPs were evaluated. The test results revealed that it would be possible to extract U selectively from the U-oxide. The DFs of almost all FPs were more than 10{sup 2}. The concentration of uranium extracted is approx. 4.5 g/L-scCO{sub 2} under 313K of temperature and 12 MPa of pressure. An increase of pressure may improve the concentration of uranium extracted. (author)

  6. Synthesis and properties of reprocessable sulfonated polyimides cross-linked via acid stimulation for use as proton exchange membranes

    Science.gov (United States)

    Zhang, Boping; Ni, Jiangpeng; Xiang, Xiongzhi; Wang, Lei; Chen, Yongming

    2017-01-01

    Cross-linked sulfonated polyimides are one of the most promising materials for proton exchange membrane (PEM) applications. However, these cross-linked membranes are difficult to reprocess because they are insoluble. In this study, a series of cross-linkable sulfonated polyimides with flexible pendant alkyl side chains containing trimethoxysilyl groups is successfully synthesized. The cross-linkable polymers are highly soluble in common solvents and can be used to prepare tough and smooth films. Before the cross-linking reaction is complete, the membranes can be reprocessed, and the recovery rate of the prepared films falls within an acceptable range. The cross-linked membranes are obtained rapidly when the cross-linkable membranes are immersed in an acid solution, yielding a cross-linking density of the gel fraction of greater than 90%. The cross-linked membranes exhibit high proton conductivities and tensile strengths under hydrous conditions. Compared with those of pristine membranes, the oxidative and hydrolytic stabilities of the cross-linked membranes are significantly higher. The CSPI-70 membrane shows considerable power density in a direct methanol fuel cell (DMFC) test. All of these results suggest that the prepared cross-linked membranes have great potential for applications in proton exchange membrane fuel cells.

  7. Eye movement desensitization and reprocessing (EMDR) therapy in the treatment of depression: a matched pairs study in an inpatient setting.

    Science.gov (United States)

    Hase, Michael; Balmaceda, Ute Mirian; Hase, Adrian; Lehnung, Maria; Tumani, Visal; Huchzermeier, Christian; Hofmann, Arne

    2015-06-01

    Depression is a severe mental disorder that challenges mental health systems worldwide as the success rates of all established treatments are limited. Eye Movement Desensitization and Reprocessing (EMDR) therapy is a scientifically acknowledged psychotherapeutic treatment for PTSD. Given the recent research indicating that trauma and other adverse life experiences can be the basis of depression, the aim of this study was to determine the effectiveness of EMDR therapy with this disorder. In this study, we recruited a group of 16 patients with depressive episodes in an inpatient setting. These 16 patients were treated with EMDR therapy by reprocessing of memories related to stressful life events in addition to treatment as usual (TAU). They were compared to a group of 16 controls matched regarding diagnosis, degree of depression, sex, age and time of admission to hospital, which were receiving TAU only. Sixty-eight percent of the patients in the EMDR group showed full remission at end of treatment. The EMDR group showed a greater reduction in depressive symptoms as measured by the SCL-90-R depression subscale. This difference was significant even when adjusted for duration of treatment. In a follow-up period of more than 1 year the EMDR group reported less problems related to depression and less relapses than the control group. EMDR therapy shows promise as an effective treatment for depressive disorders. Larger controlled studies are necessary to replicate our findings.

  8. Improvement of mood and sleep alterations in posttraumatic stress disorder patients by eye movement desensitization and reprocessing.

    Science.gov (United States)

    Raboni, Mara R; Alonso, Fabiana F D; Tufik, Sergio; Suchecki, Deborah

    2014-01-01

    Posttraumatic stress disorder (PTSD) patients exhibit depressive and anxiety symptoms, in addition to nightmares, which interfere with sleep continuity. Pharmacologic treatment of these sleep problems improves PTSD symptoms, but very few studies have used psychotherapeutic interventions to treat PTSD and examined their effects on sleep quality. Therefore, in the present study, we sought to investigate the effects of Eye Movement Desensitization Reprocessing therapy on indices of mood, anxiety, subjective, and objective sleep. The sample was composed of 11 healthy controls and 13 PTSD patients that were victims of assault and/or kidnapping. All participants were assessed before, and 1 day after, the end of treatment for depressive and anxiety profile, general well-being and subjective sleep by filling out specific questionnaires. In addition, objective sleep patterns were evaluated by polysomnographic recording. Healthy volunteers were submitted to the therapy for three weekly sessions, whereas PTSD patients underwent five sessions, on average. Before treatment, PTSD patients exhibited high levels of anxiety and depression, poor quality of life and poor sleep, assessed both subjectively and objectively; the latter was reflected by increased time of waking after sleep onset. After completion of treatment, patients exhibited improvement in depression and anxiety symptoms, and in quality of life; with indices that were no longer different from control volunteers. Moreover, these patients showed more consolidated sleep, with reduction of time spent awake after sleep onset. In conclusion, Eye Movement Desensitization and Reprocessing was an effective treatment of PTSD patients and improved the associated sleep and psychological symptoms.

  9. Improvement of mood and sleep alterations in posttraumatic stress disorder patients by eye movement desensitization and reprocessing

    Directory of Open Access Journals (Sweden)

    Mara Regina Raboni

    2014-06-01

    Full Text Available Posttraumatic stress disorder (PTSD patients exhibit depressive and anxiety symptoms, in addition to nightmares, which interfere with sleep continuity. Pharmacologic treatment of these sleep problems improves PTSD symptoms, but very few studies have used psychotherapeutic interventions to treat PTSD and examined their effects on sleep quality. Therefore, in the present study, we sought to investigate the effects of Eye Movement Desensitization Reprocessing therapy on indices of mood, anxiety, subjective and objective sleep. The sample was composed of 11 healthy controls and 13 PTSD patients that were victims of assault and/or kidnapping. All participants were assessed before, and one day after, the end of treatment for depressive and anxiety profile, general well-being and subjective sleep by filling out specific questionnaires. In addition, objective sleep patterns were evaluated by polysomnographic recording. Healthy volunteers were submitted to the therapy for three weekly sessions, whereas PTSD patients underwent five sessions, on average. Before treatment, PTSD patients exhibited high levels of anxiety and depression, poor quality of life and poor sleep, assessed both subjectively and objectively; the latter was reflected by increased time of waking after sleep onset. After completion of treatment, patients exhibited improvement in depression and anxiety symptoms, and in quality of life; with indices that were no longer different from control volunteers. Moreover, these patients showed more consolidated sleep, with reduction of time spent awake after sleep onset. In conclusion, Eye Movement Desensitization and Reprocessing was an effective treatment of PTSD patients and improved the associated sleep and psychological symptoms.

  10. Development of the scientific concept of the phosphate methods for actinide-containing waste handling (pyrochemical fuel reprocessing)

    Energy Technology Data Exchange (ETDEWEB)

    Orlova, A.I.; Orlova, V.A. [Department of Chemistry, Nizhny Novgorod State University, 23, Gagarin Ave., Nizhny Novgorod, 603950 (Russian Federation); Skiba, O.V.; Bychkov, A.V.; Volkov, Yu.F.; Lukinykh, A.N.; Tomilin, S.V.; Lizin, A.A. [Federal State Unitary Enterprise State Scientific Center, Research Institute of Atomic Reactors, Dimitrovgrad, Ulyanovsk region, 433510 (Russian Federation)

    2008-07-01

    Full text of publication follows: The crystallochemical phosphate concept in question is developed successfully in the new pyro-electrochemical reprocessing technology of irradiated fuel in molten chlorides of alkaline elements at one of the leading scientific nuclear centers - Research Institute of Atomic Reactors. Irradiated fuel is dissolved in molten chlorides of alkaline elements by mean of treating by chlorine. Then uranium and plutonium dioxides are removed electrochemically. The melt, when used many times, is contaminated by the residual actinide and contains fission products and the so called 'process' elements. This melt is unacceptable for future use. Phosphate methods can be applied for the solution of the following tasks: a) reprocessing (purification) of molten chloride salt solvents; b) conversion of the spent chloride melts to the insoluble stable crystalline product for safe storage and disposal. Within the framework of task 'a' phosphate methods may be realized by the several ways: 1) phosphate concentrating of impurities and their extraction from molten chlorides into solid phase by mean of chemical precipitation, co-precipitation, ion exchange and other chemical interactions, 2) conversion of precipitated waste phosphates to stable crystalline phosphate powders or ceramics for safe storage and disposal. (authors)

  11. Novel Sorbent Development and Evaluation for the Capture of Krypton and Xenon from Nuclear Fuel Reprocessing Off-Gas Streams

    Energy Technology Data Exchange (ETDEWEB)

    Troy G. Garn; Mitchell R. Greenhalgh; Jack D. Law

    2013-10-01

    The release of volatile radionuclides generated during Used Nuclear Fuel reprocessing in the US will most certainly need to be controlled to meet US regulatory emission limits. A US DOE sponsored Off-Gas Sigma Team has been tasked with a multi-lab collaborative research and development effort to investigate and evaluate emissions and immobilization control technologies for the volatile radioactive species generated from commercial Used Nuclear Fuel (UNF) Reprocessing. Physical Adsorption technology is a simpler and potential economical alternative to cryogenic distillation processes that can be used for the capture of krypton and xenon and has resulted in a novel composite sorbent development procedure using synthesized mordenite as the active material. Utilizing the sorbent development procedure, INL sigma team members have developed two composite sorbents that have been evaluated for krypton and xenon capacities at ambient and 191 K temperature using numerous test gas compositions. Adsorption isotherms have been generated to predict equilibration and maximum capacities enabling modeling to support process equipment scale-up.

  12. Novel Sorbent Development and Evaluation for the Capture of Krypton and Xenon from Nuclear Fuel Reprocessing Off-Gas Streams

    Energy Technology Data Exchange (ETDEWEB)

    Troy G. Garn; Mitchell R. Greenhalgh; Jack D. Law

    2013-09-01

    The release of volatile radionuclides generated during Used Nuclear Fuel reprocessing in the US will most certainly need to be controlled to meet US regulatory emission limits. A US DOE sponsored Off-Gas Sigma Team has been tasked with a multi-lab collaborative research and development effort to investigate and evaluate emissions and immobilization control technologies for the volatile radioactive species generated from commercial Used Nuclear Fuel (UNF) Reprocessing. Physical Adsorption technology is a simpler and potential economical alternative to cryogenic distillation processes that can be used for the capture of krypton and xenon and has resulted in a novel composite sorbent development procedure using synthesized mordenite as the active material. Utilizing the sorbent development procedure, INL sigma team members have developed two composite sorbents that have been evaluated for krypton and xenon capacities at ambient and 191 K temperature using numerous test gas compositions. Adsorption isotherms have been generated to predict equilibration and maximum capacities enabling modeling to support process equipment scale-up.

  13. Thorium utilization program progress report, July 1, 1975--September 30, 1976

    Energy Technology Data Exchange (ETDEWEB)

    Lotts, A.L.; Kasten, P.R.

    1977-07-01

    Status of the following tasks is reported: program management and analysis; reprocessing development; refabrication development; waste treatment; fuels irradiation and examination; HTGR fuel recycle demonstration facility; hot engineering test project; and cold prototype refabrication development. (LK)

  14. Public comments and Task Force responses regarding the environmental survey of the reprocessing and waste management portions of the LWR fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    1977-03-01

    This document contains responses by the NRC Task Force to comments received on the report ''Environmental Survey of the Reprocessing and Waste Management Portions of the LWR Fuel Cycle'' (NUREG-0116). These responses are directed at all comments, inclding those received after the close of the comment period. Additional information on the environmental impacts of reprocessing and waste management which has either become available since the publication of NUREG-0116 or which adds requested clarification to the information in that document.

  15. Interim measure work plan/design for Agra, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2008-11-18

    This Interim Measure Work Plan/Design (IMWP/D) is supplemental to the Argonne document Interim Measure Conceptual Design for Remediation of Source Area Contamination at Agra, Kansas. The IMWP/D includes information required by Kansas Department of Health and Environment (KDHE) Policy BER-RS-029, Policy and Scope of Work for Interim Measures. Specific to Policy BER-RS-029 is the requirement for several documents that will ensure that an adequate amount and type of data are collected for implementation of the IMWP/D and that data quality and safe conditions are prevailed. Such information is included in the IMWP/D as follows: Appendix A: Data Acquisition Plan--Design Testing Requirements; Appendix B: Basis of Design; Appendix C: Permits; Appendix D: Quality Assurance Project Plan; Appendix E: Health and Safety Plan; and Appendix F: Operations, Maintenance, and Monitoring Schedule. The proposed remedial technology for this project is the installation of five large-diameter boreholes (LDBs) in a source area that has been identified on the property formerly used for grain storage by the Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA). The goal of the LDB technology is the remediation of the source area by removal of mass quantities of contaminated soil from the vadose zone and treatment of any remaining contaminated soils that are adjacent to the source area to achieve a carbon tetrachloride concentration below 200 {micro}g/kg. Secondary to the soil remediation is the remediation of groundwater at and adjacent to the source areas. The LDB technology serves the following purposes: (1) The physical removal of contaminated soil from the identified source area. (2) Replacement of less permeable native materials (silty clay, clayey silt, and silty sand) with more permeable materials to facilitate the capture of volatilized contaminants in the vertical borehole. (3) Removal of contaminants volatilized by air sparging (AS) and extracted from the

  16. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

  17. Interim main report of the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, Allan (ed.) [and others

    2004-08-01

    This document is an interim report on the safety assessment SR-Can (SR in the acronym stands for Safety Report and Can is short for canister). The final SR-Can report will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of the present interim report is to demonstrate the methodology for safety assessment so that it can be reviewed before it is used in a license application. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark site, presently being investigated by SKB as one of the candidate for a KBS-3 repository are used to some extent as examples. However, the collected data are yet too sparse to allow an evaluation of safety for this site. An important aim of this report is to demonstrate the proper handling of requirements on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Authority are duplicated in an Appendix. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10{sup -6} for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects. Following the introductory chapter 1, this report outlines the methodology for the SR-Can assessment in chapter 2, and presents in chapters 3, 4 and 5 the initial state of the system and the plans and methods for handling external influences and internal processes, respectively. Function indicators are introduced in chapter 6 and a preliminary evaluation of these is given in chapter 7. The material presented in the first seven chapters is utilised in the scenario selection

  18. SWSA 6 interim corrective measures environmental monitoring: FY 1990 results

    Energy Technology Data Exchange (ETDEWEB)

    Ashwood, T.L.; Spalding, B.P.

    1991-07-01

    This report presents the results and conclusions from a multifaceted monitoring effort associated with the high-density polyethylene caps installed in Solid Waste Storage Area (SWSA) 6 at Oak Ridge National Laboratory (ORNL) as an interim corrective measure (ICM). The caps were installed between November 1988 and June 1989 to meet Resource Conservation and Recovery Act (RCRA) requirements for closure of those areas of SWSA 6 that had received RCRA-regulated wastes after November 1980. Three separate activities were undertaken to evaluate the performance of the caps: (1) wells were installed in trenches to be covered by the caps, and water levels in these intratrench wells were monitored periodically; (2) samples were taken of the leachate in the intratrench wells and were analyzed for a broad range of radiological and chemical contaminants; and (3) water levels in wells outside the trenches were monitored periodically. With the exception of the trench leachate sampling, each of these activities spanned the preconstruction, construction, and postconstruction periods. Findings of this study have important implications for the ongoing remedial investigation in SWSA 6 and for the design of other ICMs. 51 figs., 2 tabs.

  19. Database and Interim Glass Property Models for Hanford HLW Glasses

    Energy Technology Data Exchange (ETDEWEB)

    Hrma, Pavel R.; Piepel, Gregory F.; Vienna, John D.; Cooley, Scott K.; Kim, Dong-Sang; Russell, Renee L.

    2001-07-24

    The purpose of this report is to provide a methodology for an increase in the efficiency and a decrease in the cost of vitrifying high-level waste (HLW) by optimizing HLW glass formulation. This methodology consists in collecting and generating a database of glass properties that determine HLW glass processability and acceptability and relating these properties to glass composition. The report explains how the property-composition models are developed, fitted to data, used for glass formulation optimization, and continuously updated in response to changes in HLW composition estimates and changes in glass processing technology. Further, the report reviews the glass property-composition literature data and presents their preliminary critical evaluation and screening. Finally the report provides interim property-composition models for melt viscosity, for liquidus temperature (with spinel and zircon primary crystalline phases), and for the product consistency test normalized releases of B, Na, and Li. Models were fitted to a subset of the screened database deemed most relevant for the current HLW composition region.

  20. DOUBLE TRACKS Test Site interim corrective action plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    The DOUBLE TRACKS site is located on Range 71 north of the Nellis Air Force Range, northwest of the Nevada Test Site (NTS). DOUBLE TRACKS was the first of four experiments that constituted Operation ROLLER COASTER. On May 15, 1963, weapons-grade plutonium and depleted uranium were dispersed using 54 kilograms of trinitrotoluene (TNT) explosive. The explosion occurred in the open, 0.3 m above the steel plate. No fission yield was detected from the test, and the total amount of plutonium deposited on the ground surface was estimated to be between 980 and 1,600 grams. The test device was composed primarily of uranium-238 and plutonium-239. The mass ratio of uranium to plutonium was 4.35. The objective of the corrective action is to reduce the potential risk to human health and the environment and to demonstrate technically viable and cost-effective excavation, transportation, and disposal. To achieve these objectives, Bechtel Nevada (BN) will remove soil with a total transuranic activity greater then 200 pCI/g, containerize the soil in ``supersacks,`` transport the filled ``supersacks`` to the NTS, and dispose of them in the Area 3 Radioactive Waste Management Site. During this interim corrective action, BN will also conduct a limited demonstration of an alternative method for excavation of radioactive near-surface soil contamination.

  1. International Programs and Agreements in Geothermal Energy. An Interim report

    Energy Technology Data Exchange (ETDEWEB)

    Oppenheimer, M.; Fein, E.; Bye, J.

    1978-06-01

    This report contains the interim results of a study for the Division of Geothermal Energy on the Division's international programs and activities. The complete research program, which is scheduled to be finished i November 1978, will have the following elements: (1) an assessment of objectives that have motivated the formulation of international programs and an explanation of any changes in the evolution of those programs. These objectives will be assessed for their internal consistency, degree of governmental consensus, their practicality, the current status of their accomplishments, and the implications of their accomplishments for the role of DGE. (2) An assessment of organizational structures and teams, including the identity of key decisionmakers, the nature of the interagency process, procedures for generating nongovernmental support for international programs and the success of these procedures, and the effectiveness of the interface with foreign partners. (3) Assessment of results of international cooperative programs, which involve the development of an overall balance sheet of benefits and disbenefits attributed to each international program. (4) The formulation of future international cooperative programs based on the assessments described. These programs may involve the development of new exchanges, alteration or elimination of existing exchanges, and revisions in the management of exchanges by US government agencies.

  2. Interim performance criteria for photovoltaic energy systems. [Glossary included

    Energy Technology Data Exchange (ETDEWEB)

    DeBlasio, R.; Forman, S.; Hogan, S.; Nuss, G.; Post, H.; Ross, R.; Schafft, H.

    1980-12-01

    This document is a response to the Photovoltaic Research, Development, and Demonstration Act of 1978 (P.L. 95-590) which required the generation of performance criteria for photovoltaic energy systems. Since the document is evolutionary and will be updated, the term interim is used. More than 50 experts in the photovoltaic field have contributed in the writing and review of the 179 performance criteria listed in this document. The performance criteria address characteristics of present-day photovoltaic systems that are of interest to manufacturers, government agencies, purchasers, and all others interested in various aspects of photovoltaic system performance and safety. The performance criteria apply to the system as a whole and to its possible subsystems: array, power conditioning, monitor and control, storage, cabling, and power distribution. They are further categorized according to the following performance attributes: electrical, thermal, mechanical/structural, safety, durability/reliability, installation/operation/maintenance, and building/site. Each criterion contains a statement of expected performance (nonprescriptive), a method of evaluation, and a commentary with further information or justification. Over 50 references for background information are also given. A glossary with definitions relevant to photovoltaic systems and a section on test methods are presented in the appendices. Twenty test methods are included to measure performance characteristics of the subsystem elements. These test methods and other parts of the document will be expanded or revised as future experience and needs dictate.

  3. Thorium utilization program. Quarterly progress report for the period ending February 28, 1977. [Fuel element crushing, burning; particle classification; solvent extraction; dry solids handling; plant management; HET fuel shipping; HTGR recycle demonstration facility

    Energy Technology Data Exchange (ETDEWEB)

    1977-03-01

    General Atomic Thorium Utilization Program activities progressed on schedule during the quarter, with continuation of the head-end reprocessing equipment testing program. Individual testing of the tertiary, oversize crushers and the screener was completed. Preparation of the equipment for testing as a system is under way. Tests on the tertiary crusher revealed no operating problems. No material holdup areas or bypass of the crushing cavity were detected. The initial issue of a functional level diagram for the Fuel Element Size Reduction System has been prepared for preliminary review. Heat transfer coefficients were calculated from data obtained in six 0.40-m primary burner heatup runs. Six runs were made on the 0.20-m primary burner. Other significant 0.20-m burner work included fabrication and initial testing of an electrical resistance probe bed level sensor and preliminary heat transfer design calculations for determining the cooling requirements to maintain the recycling fines cyclone exit temperature at approximately 500/sup 0/C. The conceptual design of the engineering-scale dissolver-centrifuge for incorporation into the head-end line was completed. Three solvent extraction feed adjustment runs were completed. Two of the runs were representative of the continuous intercycle concentration step. The other run was a continuous operation which utilized leacher product as feed. Progress with dry solids handling component and system testing continues. Efforts were focused on completion of the HET fuel shipping conceptual design report, development of detailed costs, and identification of all system interfaces. The Reprocessing Flowsheet Review and Materials Balance Study of reprocessing head-end and off-gas treatment systems is in technical review.

  4. Predictors of unsuccessful interim treatment outcomes of multidrug resistant tuberculosis patients.

    Science.gov (United States)

    Atif, Muhammad; Bashir, Arslan; Ahmad, Nafees; Fatima, Razia Kaneez; Saba, Sehar; Scahill, Shane

    2017-09-29

    Interim treatment outcomes at 6-months for multidrug-resistant tuberculosis (MDR-TB) treatment are among the most basic performance monitoring and key evaluation indicators in the Stop and End TB strategy of the World Health Organization (WHO). Therefore, this study was conducted to evaluate the interim treatment outcomes of MDR-TB patients in Pakistan. This study was conducted at the Programmatic Management Unit for Drug-resistance TB (PMDT) site of the National Tuberculosis Program (NTP), Pakistan. It is located in the Chest Disease Unit (CDU) of the Bahawal Victoria Hospital (BVH), Bahawalpur, Punjab, Pakistan. Data was collected between April 1, 2014 and December 31, 2015. The medical records, Electronic Nominal Recording Reporting System (ENRS) data and MRD-TB notification forms of the MDR-TB patients registered at the PMDT site were reviewed to obtain data. For reporting and calculation of interim treatment outcomes, standardized WHO methodology was adopted. Simple logistic regression analysis was used to examine the possible association between the dependent variable (i.e. unsuccessful interim treatment outcome) and selected socio-demographic and clinical variables. A total of 100 drug-resistant TB (DR-TB) patients (all types) were registered during the study period. Out of these, 80 were MDR-TB patients for whom interim results were available. Out of the 80 MDR-TB cases, 48 (60%) were classified under the successful interim treatment outcome category. The remaining 40% had unsuccessful 6-month treatment outcomes and 12 (15%) patients died, while nine (11.3%) were lost to follow-up by six months. The final predictors of unsuccessful interim treatment outcomes were; being resistant to ofloxacin (AOR 3.23, 95% CI 0.96-10.89; p-value = 0.04), having above normal baseline serum creatinine levels (AOR 6.49, 95% CI 1.39-30.27; p-value = 0.02), and being culture positive at the second month of treatment (AOR 6.94, 95% CI 2-24.12; p-value = 0.01). Despite free

  5. Eye movement desensitisation and reprocessing therapy for posttraumatic stress disorder in a child and an adolescent with mild to borderline intellectual disability: A multiple baseline across subjects study

    NARCIS (Netherlands)

    Mevissen, E.H.M.; Didden, H.C.M.; Korzilius, H.P.L.M.; Jongh, A. de

    2017-01-01

    BACKGROUND: This study explored the effectiveness of eye movement desensitisation and reprocessing (EMDR) therapy for post-traumatic stress disorder (PTSD) in persons with mild to borderline intellectual disability (MBID) using a multiple baseline across subjects design. METHODS: One child and one

  6. 10 CFR Appendix F to Part 50 - Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities

    Science.gov (United States)

    2010-01-01

    ... and Related Waste Management Facilities F Appendix F to Part 50 Energy NUCLEAR REGULATORY COMMISSION... Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities 1. Public health... facilities for the temporary storage of highlevel radioactive wastes, may be located on privately owned...

  7. A high quality reprocessed ground-based GPS dataset for atmospheric process studies, radiosonde and model evaluation, and reanalysis of HYMEX Special Observing Period

    Science.gov (United States)

    BOCK, Olivier; Bosser, Pierre; Pacione, Rosa; Nuret, Mathieu; Fourrié, Nadia

    2015-04-01

    Data from more than 1000 ground-based GPS receivers in the north-western Mediterranean area have been reprocessed in a consistent way using GIPSY-OASIS II software for the period from 1st September 2012 to 31 March 2013 which encompasses the Special Observation Periods (SOPs) 1 and 2 of the HYMEX project. The reprocessed GPS ZTD data were screened converted to IWV. The ZTD data were used to assess the accuracy of the near real time ZTD data assimilated for operational weather forecasting. The mean of delay differences between the operational and reprocessed solutions is about 0 +/- 3 mm (mean +/- standard deviation of bias over all stations) and the standard deviation of delay differences ranges between 4 and 8 mm. Significant bias reduction is thus expected from a reanalysis ingesting the reprocessed delay data. Various methods and auxiliary data (surface pressure and weighted mean temperature) are investigated for the conversion of ZTD data into IWV. The final IWV dataset is used to evaluate radiosonde humidity observations and operational analyses produced with the AROME model. The spatial and temporal distribution of IWV is also studied with a focus on heavy precipitation events in the north-western Mediterranean area during the HYMEX SOP1.

  8. Eye Movement Desensitisation and Reprocessing Therapy for Posttraumatic Stress Disorder in a Child and an Adolescent with Mild to Borderline Intellectual Disability: A Multiple Baseline across Subjects Study

    Science.gov (United States)

    Mevissen, Liesbeth; Didden, Robert; Korzilius, Hubert; de Jongh, Ad

    2017-01-01

    Background: This study explored the effectiveness of eye movement desensitisation and reprocessing (EMDR) therapy for post-traumatic stress disorder (PTSD) in persons with mild to borderline intellectual disability (MBID) using a multiple baseline across subjects design. Methods: One child and one adolescent with MBID, who met diagnostic criteria…

  9. Eye movement desensitization and reprocessing therapy in subsyndromal bipolar patients with a history of traumatic events: a randomized, controlled pilot-study.

    Science.gov (United States)

    Novo, Patricia; Landin-Romero, Ramon; Radua, Joaquim; Vicens, Victor; Fernandez, Isabel; Garcia, Francisca; Pomarol-Clotet, Edith; McKenna, Peter J; Shapiro, Francine; Amann, Benedikt L

    2014-09-30

    Traumatic events are frequent in bipolar patients and can worsen the course of the disease. Psychotherapeutic interventions for these events have not been studied so far. Twenty DSM-IV bipolar I and II patients with subsyndromal mood symptoms and a history of traumatic events were randomly assigned to Eye Movement Desensitization and Reprocessing therapy (n=10) or treatment as usual (n=10). The treatment group received between 14 and 18 Eye Movement Desensitization and Reprocessing sessions during 12 weeks. Evaluations of affective symptoms, symptoms of trauma and trauma impact were carried out by a blind rater at baseline, 2 weeks, 5 weeks, 8 weeks, 12 weeks and at 24 weeks follow-up. Patients in the treatment group showed a statistically significant improvement in depressive and hypomanic symptoms, symptoms of trauma and trauma impact compared to the treatment as usual group after intervention. This effect was only partly maintained in trauma impact at the 24 weeks follow-up visit. One patient dropped from Eye Movement Desensitization and Reprocessing group whereas four from the treatment as usual group. This pilot study suggests that Eye Movement Desensitization and Reprocessing therapy may be an effective and safe intervention to treat subsyndromal mood and trauma symptoms in traumatized bipolar patients. Copyright © 2014 Elsevier Ireland Ltd. All rights reserved.

  10. Self-esteem treatment in anxiety : A randomized controlled crossover trial of Eye Movement Desensitization and Reprocessing (EMDR) versus Competitive Memory Training (COMET) in patients with anxiety disorders

    NARCIS (Netherlands)

    Staring, A. B. P.; van den Berg, D. P. G.; Cath, D. C.; Schoorl, M.; Engelhard, I. M.; Korrelboom, C. W.

    2016-01-01

    Background and purpose Little is known about treating low self-esteem in anxiety disorders. This study evaluated two treatments targeting different mechanisms: (1) Eye Movement Desensitization and Reprocessing (EMDR), which aims to desensitize negative memory representations that are proposed to

  11. Self-esteem treatment in anxiety : A randomized controlled crossover trial of Eye Movement Desensitization and Reprocessing (EMDR) versus Competitive Memory Training (COMET) in patients with anxiety disorders

    NARCIS (Netherlands)

    Staring, A B P; van den Berg, D P G; Cath, D C; Schoorl, M; Engelhard, I M; Korrelboom, C W

    BACKGROUND AND PURPOSE: Little is known about treating low self-esteem in anxiety disorders. This study evaluated two treatments targeting different mechanisms: (1) Eye Movement Desensitization and Reprocessing (EMDR), which aims to desensitize negative memory representations that are proposed to

  12. Comparing the Efficacy of Eye Movement Desensitization and Reprocessing Therapy with Prolonged Exposure Therapy on the Trauma impact symptoms in Veterans Suffering from Chronic PTSD

    Directory of Open Access Journals (Sweden)

    A Maredpour

    2013-09-01

    Background and aim: Post-traumatic stress disorder is considered as set of symptoms developed afterward an individual witness, hear or involved. The current research was purposed to compare the efficacy of eye movement desensitization and reprocessing therapy with prolonged exposure therapy on the trauma impact symptoms in veterans suffering from chronic PTSD. Methods: in this clinical trail research randomly sampled 48 veterans diagnosed with PTSD who had psychiatric records in Salman City Hospital of Yasuj. The subjects devoted in three equal groups: two experimental and one control groups. As intervention procedures the two experimental groups were exposed to eye movement desensitization and reprocessing therapy (5 sessions and prolonged exposure therapy (10 sessions respectively. The control group received none. Subsequent to the treatment period the triple groups were post-tested by the prior pre test scales. The data were analyzed by implementing univariate analysis of covariance (ANCOVA and Bonferroni post hoc test. Results: Both treatment procedures significantly reduced the trauma impact symptoms (p ≤0/001.The results also indicated that prolonged exposure therapy was more effective concerning the trauma impact symptoms improvement. Conclusion: Intervention treatment procedures such as eye movement desensitization, reprocessing therapy, and prolonged exposure therapy sustain sufficient efficacy in trauma impact symptoms improvement while prolonged exposure therapy exceeded significantly. Key words: Post Traumatic Stress Disorder, Eye Movement, Desensitization, Reprocessing, Prolonged Exposure Therapy

  13. Fit of interim crowns fabricated using photopolymer-jetting 3D printing.

    Science.gov (United States)

    Mai, Hang-Nga; Lee, Kyu-Bok; Lee, Du-Hyeong

    2017-08-01

    The fit of interim crowns fabricated using 3-dimensional (3D) printing is unknown. The purpose of this in vitro study was to evaluate the fit of interim crowns fabricated using photopolymer-jetting 3D printing and to compare it with that of milling and compression molding methods. Twelve study models were fabricated by making an impression of a metal master model of the mandibular first molar. On each study model, interim crowns (N=36) were fabricated using compression molding (molding group, n=12), milling (milling group, n=12), and 3D polymer-jetting methods. The crowns were prepared as follows: molding group, overimpression technique; milling group, a 5-axis dental milling machine; and polymer-jetting group using a 3D printer. The fit of interim crowns was evaluated in the proximal, marginal, internal axial, and internal occlusal regions by using the image-superimposition and silicone-replica techniques. The Mann-Whitney U test and Kruskal-Wallis tests were used to compare the results among groups (α=.05). Compared with the molding group, the milling and polymer-jetting groups showed more accurate results in the proximal and marginal regions (P3D printing significantly enhanced the fit of interim crowns, particularly in the occlusal region. Copyright © 2016 Editorial Council for the Journal of Prosthetic Dentistry. Published by Elsevier Inc. All rights reserved.

  14. Wayne Interim Storage Site annual environmental report for calendar year 1991, Wayne, New Jersey. [Wayne Interim Storage Site

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-09-01

    This document describes the envirormental monitoring program at the Wayne Interim Storage Site (WISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of WISS and surrounding area began in 1984 when Congress added the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. WISS is a National Priorities List site. The environmental monitoring program at WISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Several nonradiological parameters are also measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides, dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment.

  15. Maywood Interim Storage Site annual environmental report for calendar year 1991, Maywood, New Jersey. [Maywood Interim Storage Site

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-09-01

    This document describes the environmental monitoring program at the Maywood Interim Storage Site (MISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of MISS began in 1984 when congress added the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at MISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation-exposure; and total uranium, radium-226, radium-228, thorium-232, and thorium-230 concentrations in surface water, sediment, and groundwater. Additionally, several nonradiological parameters are measured in surface water, sediment, and groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment.

  16. Treatment of specific phobias with Eye Movement Desensitization and Reprocessing (EMDR): protocol, empirical status, and conceptual issues.

    Science.gov (United States)

    De Jongh, A; Ten Broeke, E; Renssen, M R

    1999-01-01

    This paper considers the current empirical status of Eye Movement Desensitization and Reprocessing (EMDR) as a treatment method for specific phobias, along with some conceptual and practical issues in relation to its use. Both uncontrolled and controlled studies on the application of EMDR with specific phobias demonstrate that EMDR can produce significant improvements within a limited number of sessions. With regard to the treatment of childhood spider phobia, EMDR has been found to be more effective than a placebo control condition, but less effective than exposure in vivo. The empirical support for EMDR with specific phobias is still meagre, therefore, one should remain cautious. However, given that there is insufficient research to validate any method for complex or trauma related phobias, that EMDR is a time-limited procedure, and that it can be used in cases for which an exposure in vivo approach is difficult to administer, the application of EMDR with specific phobias merits further clinical and research attention.

  17. Corrosion resistance of ceramic materials in pyrochemical reprocessing condition by using molten salt for spent nuclear oxide fuel

    Science.gov (United States)

    Takeuchi, M.; Kato, T.; Hanada, K.; Koizumi, T.; Aose, S.

    2005-02-01

    The corrosion resistance of ceramic materials in pyrochemical reprocessing using molten salts was discussed through the thermodynamic calculation and corrosion test. The corrosion test was basically carried out in alkali molten salt under chlorine gas. In addition, the effects of oxygen, carbon and main fission product's chlorides on ceramics corrosion were evaluated in that condition. Most of ceramic oxides showed good chemical stability on chlorine, oxygen and uranyl chloride from thermodynamic calculation results. On the other hand, from corrosion test result, silicon nitride, mullite (Al6Si2O13) and cordierite (Mg2Al3(AlSi5O18)) have a good corrosion resistance which is corresponding to 0.1 mm/y or less. No cracks on the materials were observed and flexural strength did not drop remarkably after 480 h corrosion testing in molten salt under Cl2 O2 atmosphere.

  18. Potential of eye movement desensitization and reprocessing therapy in the treatment of post-traumatic stress disorder.

    Science.gov (United States)

    McGuire, Tracy M; Lee, Christopher W; Drummond, Peter D

    2014-01-01

    Post-traumatic stress disorder (PTSD) continues to attract both empirical and clinical interest due to its complex symptom profile and the underlying processes involved. Recently, research attention has been focused on the types of memory processes involved in PTSD and hypothesized neurobiological processes. Complicating this exploration, and the treatment of PTSD, are underlying comorbid disorders, such as depression, anxiety, and substance use disorders. Treatment of PTSD has undergone further reviews with the introduction of eye movement desensitization and reprocessing (EMDR). EMDR has been empirically demonstrated to be as efficacious as other specific PTSD treatments, such as trauma-focused cognitive behavioral therapy. There is emerging evidence that there are different processes underlying these two types of trauma treatment and some evidence that EMDR might have an efficiency advantage. Current research and understanding regarding the processes of EMDR and the future direction of EMDR is presented.

  19. DEVELOPMENT OF A HYDROGEN MORDENITE SORBENT FOR THE CAPTURE OF KRYPTON FROM USED NUCLEAR FUEL REPROCESSING OFF-GAS STREAMS

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell Greenhalgh; Troy G. Garn; Jack D. Law

    2014-04-01

    A novel new sorbent for the separation of krypton from off-gas streams resulting from the reprocessing of used nuclear fuel has been developed and evaluated. A hydrogen mordenite powder was successfully incorporated into a macroporous polymer binder and formed into spherical beads. The engineered form sorbent retained the characteristic surface area and microporosity indicative of mordenite powder. The sorbent was evaluated for krypton adsorption capacities utilizing thermal swing operations achieving capacities of 100 mmol of krypton per kilogram of sorbent at a temperature of 191 K. A krypton adsorption isotherm was also obtained at 191 K with varying krypton feed gas concentrations. Adsorption/desorption cycling effects were also evaluated with results indicating that the sorbent experienced no decrease in krypton capacity throughout testing.

  20. Spectroscopic On-Line Monitoring for Process Control and Safeguarding of Radiochemical Streams in Nuclear Fuel Reprocessing Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, Samuel A.; Levitskaia, Tatiana G.; Casella, Amanda J.; Peterson, James M.; Johnsen, Amanda M.; Lines, Amanda M.; Thomas, Elizabeth M.

    2011-03-01

    The current book chapter presents preliminary work toward the use of spectroscopic on-line monitoring for process control and safeguarding of radiochemical streams. Raman spectroscopy was demonstrated as a method for determining U(VI), nitrate, and nitric acid, while visible-near-infrared (vis-NIR) spectroscopy was demonstrated as a method for determining Pu(IV), Np(V), U(VI) and Nd(III). This method has been established using fuel reprocessing solution stimulants under dynamic flow conditions and on commercial spent nuclear fuel samples. Partial least squares (PLS) models for each analyte were prepared, and the fits of the data presented. A brief review of literature relevant to the use of vibrational spectroscopy and physicochemical measurements for process monitoring of nuclear fuel solutions is reported.

  1. Successful treatment of methotrexate intolerance in juvenile idiopathic arthritis using eye movement desensitization and reprocessing - treatment protocol and preliminary results.

    Science.gov (United States)

    Höfel, Lea; Eppler, Bruno; Storf, Magdalena; Schnöbel-Müller, Elizabeth; Haas, Johannes-Peter; Hügle, Boris

    2018-02-13

    Methotrexate (MTX), commonly used in juvenile idiopathic arthritis (JIA), frequently has to be discontinued due to intolerance with anticipatory and associative gastrointestinal adverse effects. Eye Movement Desensitization and Reprocessing (EMDR) is a psychological method where dysfunctional experiences and memories are reprocessed by recall combined with bilateral eye movements. The objective of this study was to assess efficacy of EMDR for treatment of MTX intolerance in JIA patients. We performed an open prospective study on consecutive JIA patients with MTX intolerance. Intolerance was determined using the Methotrexate Intolerance Severity Score (MISS) questionnaire prior to treatment, directly after treatment and after four months. Health-related quality of life was determined using the PedsQL prior to and four months after treatment. Patients were treated according to an institutional EMDR protocol with 8 sessions over two weeks. Changes in MISS and PedsQL were analyzed using non-parametric statistics. Eighteen patients with MTX intolerance (median MISS at inclusion 16.5, IQR = 11.75-20.25) were included. Directly after treatment, MTX intolerance symptoms were significantly improved (median MISS 1 (IQR = 0-2). After four months, median MISS score was at 6.5 (IQR = 2.75-12.25, p = 0.001), with 9/18 patients showing MISS scores ≥6. Median PedsQL after 4 months improved significantly from 77.6% to 85.3% (p = 0.008). MTX intolerance in children with JIA was effectively treated using an EMDR protocol, with lasting effect over a period of 4 months. EMDR treatment can potentially increase quality of life of affected patients and enable continued MTX treatment.

  2. Removal efficiency of silver impregnated filter materials and performance of iodie filters in the off-gas of the Karlsruhe reprocessing plant WAK

    Energy Technology Data Exchange (ETDEWEB)

    Herrmann, F.J.; Herrmann, B.; Hoeflich, V. [Wiederaufarbeitungsanlage Karlsruhe (Germany)] [and others

    1997-08-01

    An almost quantitative retention of iodine is required in reprocessing plants. For the iodine removal in the off-gas streams of a reprocessing plant various sorption materials had been tested under realistic conditions in the Karlsruhe reprocessing plant WAK in cooperation with the Karlsruhe research center FZK. The laboratory results achieved with different iodine sorption materials justified long time performance tests in the WAK Plant. Technical iodine filters and sorption materials for measurements of iodine had been tested from 1972 through 1992. This paper gives an overview over the most important results, Extended laboratory, pilot plant, hot cell and plant experiences have been performed concerning the behavior and the distribution of iodine-129 in chemical processing plants. In a conventional reprocessing plant for power reactor fuel, the bulk of iodine-129 and iodine-127 is evolved into the dissolver off-gas. The remainder is dispersed over many aqueous, organic and gaseous process and waste streams of the plant. Iodine filters with silver nitrate impregnated silica were installed in the dissolver off-gas of the Karlsruhe reprocessing plant WAK in 1975 and in two vessel vent systems in 1988. The aim of the Karlsruhe iodine research program was an almost quantitative evolution of the iodine during the dissolution process to remove as much iodine with the solid bed filters as possible. After shut down of the WAK plant in December 1990 the removal efficiency of the iodine filters at low iodine concentrations had been investigated during the following years. 12 refs., 2 figs., 2 tabs.

  3. 77 FR 75649 - Establishment of Interim Final Supplementary Rules for Public Lands Managed by the Carrizo Plain...

    Science.gov (United States)

    2012-12-21

    ... and rare flora and wildlife species, and world class archaeological sites. Protecting these values... upon the date of publication. III. Discussion of Interim Final Supplementary Rules These interim final... replica weapons (such as paintball, airsoft, or war game apparatus) is prohibited on the Monument. The use...

  4. 49 CFR 1152.29 - Prospective use of rights-of-way for interim trail use and rail banking.

    Science.gov (United States)

    2010-10-01

    ... use and rail banking. 1152.29 Section 1152.29 Transportation Other Regulations Relating to... Prospective use of rights-of-way for interim trail use and rail banking. (a) If any state, political... line proposed to be abandoned for interim trail use and rail banking pursuant to 16 U.S.C. 1247(d), it...

  5. 40 CFR 257.3-5 - Application to land used for the production of food-chain crops (interim final).

    Science.gov (United States)

    2010-07-01

    ... production of food-chain crops (interim final). 257.3-5 Section 257.3-5 Protection of Environment... Application to land used for the production of food-chain crops (interim final). (a) Cadmium. A facility or... for the production of food-chain crops shall not exist or occur, unless in compliance with all...

  6. Planning and monitoring of placebo-controlled survival trials : comparison of the triangular test with usual interim analyses methods

    NARCIS (Netherlands)

    Hulot, JS; Cucherat, M; Charlesworth, A; Van Veldhuisen, DJ; Corvol, JC; Mallet, A; Boissel, JP; Hampton, J; Lechat, P

    Aims For ethical and economic reasons, interim analysis of phase III clinical trials is essential. This study was conducted to compare the efficiency of two interim analysis procedures, which could be used to allow early termination of a clinical trial. Methods We made a post hoc application of two

  7. 75 FR 34537 - Interim Final Rules for Group Health Plans and Health Insurance Coverage Relating to Status as a...

    Science.gov (United States)

    2010-06-17

    ... Health Insurance Coverage Relating to Status as a Grandfathered Health Plan Under the Patient Protection...-AB68 Interim Final Rules for Group Health Plans and Health Insurance Coverage Relating to Status as a... Consumer Information and Insurance Oversight, Department of Health and Human Services. ACTION: Interim...

  8. 76 FR 60802 - Foreign-Trade Zone 77-Memphis, TN; Withdrawal of Request for Temporary/Interim Manufacturing...

    Science.gov (United States)

    2011-09-30

    ... Foreign-Trade Zones Board Foreign-Trade Zone 77--Memphis, TN; Withdrawal of Request for Temporary/Interim Manufacturing Authority; Flextronics Logistics USA, Inc., (Cell Phone/Mobile Handset Kitting). Memphis, TN..., requesting temporary/interim manufacturing authority on behalf of Flextronics Logistics USA, Inc. in Memphis...

  9. 78 FR 3039 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-06; Performing a...

    Science.gov (United States)

    2013-01-15

    ... COMMISSION Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-06; Performing a Tsunami, Surge, or Seiche Hazard Assessment AGENCY: Nuclear Regulatory Commission. ACTION: Japan Lessons... Commission (NRC) is issuing the Final Japan Lessons-Learned Project Directorate Interim Staff Guidance (JLD...

  10. 76 FR 8383 - Office of New Reactors; Interim Staff Guidance on Impacts of Construction of New Nuclear Power...

    Science.gov (United States)

    2011-02-14

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Office of New Reactors; Interim Staff Guidance on Impacts of Construction of New Nuclear Power...: Solicitation of public comment. SUMMARY: The NRC staff is soliciting public comment on its proposed Interim...

  11. 76 FR 17159 - Office of New Reactors; Final Interim Staff Guidance on Standard Review Plan, Section 17.4...

    Science.gov (United States)

    2011-03-28

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Office of New Reactors; Final Interim Staff Guidance on Standard Review Plan, Section 17.4.... SUMMARY: The NRC staff is issuing its Final Interim Staff Guidance (ISG) DC/COL-ISG-018 (Agencywide...

  12. 75 FR 8412 - Office of New Reactors: Interim Staff Guidance on Assessing Ground Water Flow and Transport of...

    Science.gov (United States)

    2010-02-24

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Office of New Reactors: Interim Staff Guidance on Assessing Ground Water Flow and Transport of... Interim Staff Guidance (ISG) DC/COL-ISG-014 (Agencywide Documents Access and Management System (ADAMS...

  13. Gas-turbine HTGR materials screening test program. Quarterly progress report, July 1, 1976--September 30, 1976. [IN 100; IN 713; MM004; M21; IN 738; RENE 100; MoTZM; Hastelloy X; Inconel 617; MA 753; IN 519, Inconel 706; Inconel 718; A286; 316 SS; Incoloy 800

    Energy Technology Data Exchange (ETDEWEB)

    Rosenwasser, S.N.; Johnson, W.R.

    1976-09-30

    The duration of controlled-impurity creep-screening tests and unstressed aging tests has reached 10,000 hr. Creep and weight change data from testing up to 9,000 hr and results from post-test metallurgical evaluations of several recently returned 3,000-hr specimens, including alloys IN519 and MoTZM, are presented. Preliminary materials requirements for key GT-HTGR 850/sup 0/C (1562/sup 0/F) reactor outlet temperature reference design components are documented.

  14. THE IMPORTANCE OF FINANCIAL INTERIM REPORTING FOR THE POSITION OF COMPANIES

    Directory of Open Access Journals (Sweden)

    Claudia‐Elena\tGRIGORAȘ‐ICHIM

    2015-12-01

    Full Text Available The importance that each company must grant to the strategic sources of information generates our concern for analysis of the interim financial reporting. In every enterprise, there are doubts on the usefulness of interim financial reports, given the following elements: the necessary time for their preparation (relatively long, their restricted character and the resources necessary to establish them. Finding a common solution to these problems and, implicitly, increasing the interest for interim financial reporting, can help to increase the economic performance of the company, either by reducing the unnecessary costs related to time, or by increasing communication and transparency with third parties. An appropriate management can act early in the direction of counteracting the negative effects in their company or prevention of any commercial or production failures, the overall economic trends in that field and increasing productivity. Starting from these premises, we propose a research in order to capture the main aspects related to the mentioned issues.

  15. Using ERA-Interim reanalysis for creating datasets of energy-relevant climate variables

    Science.gov (United States)

    Jones, Philip D.; Harpham, Colin; Troccoli, Alberto; Gschwind, Benoit; Ranchin, Thierry; Wald, Lucien; Goodess, Clare M.; Dorling, Stephen

    2017-07-01

    The construction of a bias-adjusted dataset of climate variables at the near surface using ERA-Interim reanalysis is presented. A number of different, variable-dependent, bias-adjustment approaches have been proposed. Here we modify the parameters of different distributions (depending on the variable), adjusting ERA-Interim based on gridded station or direct station observations. The variables are air temperature, dewpoint temperature, precipitation (daily only), solar radiation, wind speed, and relative humidity. These are available on either 3 or 6 h timescales over the period 1979-2016. The resulting bias-adjusted dataset is available through the Climate Data Store (CDS) of the Copernicus Climate Change Data Store (C3S) and can be accessed at present from ftp://ecem.climate.copernicus.eu. The benefit of performing bias adjustment is demonstrated by comparing initial and bias-adjusted ERA-Interim data against gridded observational fields.

  16. In vitro evaluation of the marginal integrity of CAD/CAM interim crowns.

    Science.gov (United States)

    Kelvin Khng, Kwang Yong; Ettinger, Ronald L; Armstrong, Steven R; Lindquist, Terry; Gratton, David G; Qian, Fang

    2016-05-01

    The accuracy of interim crowns made with computer-aided design and computer-aided manufacturing (CAD/CAM) systems has not been well investigated. The purpose of this in vitro study was to evaluate the marginal integrity of interim crowns made by CAD/CAM compared with that of conventional polymethylmethacrylate (PMMA) crowns. A dentoform mandibular left second premolar was prepared for a ceramic crown and scanned for the fabrication of 60 stereolithical resin dies, half of which were scanned to fabricate 15 Telio CAD-CEREC and 15 Paradigm MZ100-E4D-E4D crowns. Fifteen Caulk and 15 Jet interim crowns were made on the remaining resin dies. All crowns were cemented with Tempgrip under a 17.8-N load, thermocycled for 1000 cycles, placed in 0.5% acid fuschin for 24 hours, and embedded in epoxy resin before sectioning from the mid-buccal to mid-lingual surface. The marginal discrepancy was measured using a traveling microscope, and dye penetration was measured as a percentage of the overall length under the crown. The mean vertical marginal discrepancy of the conventionally made interim crowns was greater than for the CAD/CAM crowns (P=.006), while no difference was found for the horizontal component (P=.276). The mean vertical marginal discrepancy at the facial surface of the Caulk crowns was significantly greater than that of the other 3 types of interim crowns (Pcrowns was significantly larger than that of the other 3 types, with no difference at the lingual margins (P=.150). The mean percentage dye penetration for the Paradigm MZ100-E4D crowns was significantly greater and for Jet crowns significantly smaller than for the other 3 crowns (Pcrowns at the facial surface and with the horizontal marginal discrepancies of the Caulk interim crowns at the lingual surface (Pcrowns fabricated by CAD/CAM as compared with PMMA crowns; however, this difference was not observed for the horizontal component. The percentage dye penetration was correlated with vertical and horizontal

  17. 1988 Federal Interim Storage Fee study: A technical and economic analysis

    Energy Technology Data Exchange (ETDEWEB)

    1988-11-01

    This document is the latest in a series of reports that are published annually by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). The information in this report, which was prepared by E.R. Johnson Associates, Inc., under subcontract to PNL, will be used by the DOE to establish a payment schedule for interim storage of spent nuclear fuel under the Federal Interim Storage (FIS) Program. The FIS Program was mandated by the Nuclear Waste Policy Act of 1982. The information will be used to establish the schedule of charges for FIS services for the year commencing January 1, 1989. 13 refs.

  18. Early rehabilitation of facial defects using interim removable prostheses: A clinical case report

    Directory of Open Access Journals (Sweden)

    Vivekanandhan Ramkumar

    2013-01-01

    Full Text Available Surgical resection of neoplasms or malformations of the face may result in defects that are not amenable to immediate surgical reconstruction. Such defects can have a severe adverse effect on patient perceptions of body image and self-esteem. In these cases, the use of an interim removable facial prosthesis can offer a rapid alternative treatment solution. The patient may then resume social interactions more comfortably while permitting easy access to the facial defect to observe tissue healing while awaiting definitive rehabilitation. This article presents a case report describing the use of interim nasal prostheses to provide rapid patient rehabilitation of facial defects.

  19. On-site Interim Stores for Decommissioning Waste; Standort-Zwischenlager fuer Rueckbauabfaelle

    Energy Technology Data Exchange (ETDEWEB)

    Geiser, H. [Wissenschaftlich - Technische Ingenieurberatung GmbH (WTI), Juelich (Germany)

    2003-05-01

    Periods of interim storage of radioactive waste above ground perhaps up until 2040 must be bridged in case a repository will not be available in time. Ongoing operation of nuclear power plants and, especially, the increasing rate of decommissioning and demolition of power reactors add to the need to plan for the management of waste arising in operation and demolition. Most of the existing interim storage capacity has been earmarked for waste arising in plant operation. It will become necessary to create additional interim storage capacity in order to allow plants to be decommissioned and demolished speedily and, at the same time, make the necessary provisions for interim storage pending final storage. Government institutions and research centers (FZK, FZJ, VKTA, and EWN) created new storage capacity in recent years. The waste arising from decommissioning and demolition of the Hanau nuclear plants will also be emplaced in a new on-site interim store. At a number of sites where power reactors are going to be decommissioned and demolished, operators also are planning for new interim storage capacity for radioactive waste. An overview is given of the on-site interim stores newly built and the new interim stores currently in the planning phase on various sites where plants are to be dismantled. (orig.) [German] Fuer den Fall, dass ein Endlager nicht rechtzeitig zur Verfuegung steht, sind Zwischenlagerzeitraeume fuer die oberirdische Lagerung von radioaktiven Abfaellen u.U. bis 2040 zu ueberbruecken. Durch den laufenden Betrieb der Kernkraftwerke und insbesondere durch den jetzt verstaerkt einsetzenden Rueckbau der Leistungsreaktoren ergibt sich ein zusaetzlicher Planungszwang als Vorsorge fuer die Entsorgung der Betriebs- und Rueckbauabfaelle. Die bestehenden Zwischenlagerkapazitaeten sind weitgehend fuer die Aufnahme von Betriebsabfaellen verplant. Es wird zukuenftig notwendig werden, weitere Zwischenlagerkapazitaeten zu schaffen, damit ein zuegiger Rueckbau moeglich

  20. INCREASING OIL RECOVERY THROUGH ADVANCED REPROCESSING OF 3D SEISMIC, GRANT CANYON AND BACON FLAT FIELDS, NYE COUNTY, NEVADA

    Energy Technology Data Exchange (ETDEWEB)

    Eric H. Johnson; Don E. French

    2001-06-01

    Makoil, Inc., of Orange, California, with the support of the U.S. Department of Energy has reprocessed and reinterpreted the 3D seismic survey of the Grant Canyon area, Railroad Valley, Nye County, Nevada. The project was supported by Dept. of Energy Grant DE-FG26-00BC15257. The Grant Canyon survey covers an area of 11 square miles, and includes Grant Canyon and Bacon Flat oil fields. These fields have produced over 20 million barrels of oil since 1981, from debris slides of Devonian rocks that are beneath 3,500 to 5,000 ft of Tertiary syntectonic deposits that fill the basin of Railroad Valley. High-angle and low-angle normal faults complicate the trap geometry of the fields, and there is great variability in the acoustic characteristics of the overlying valley fill. These factors combine to create an area that is challenging to interpret from seismic reflection data. A 3D seismic survey acquired in 1992-93 by the operator of the fields has been used to identify development and wildcat locations with mixed success. Makoil believed that improved techniques of processing seismic data and additional well control could enhance the interpretation enough to improve the chances of success in the survey area. The project involved the acquisition of hardware and software for survey interpretation, survey reprocessing, and reinterpretation of the survey. SeisX, published by Paradigm Geophysical Ltd., was chosen as the interpretation software, and it was installed on a Dell Precision 610 computer work station with the Windows NT operating system. The hardware and software were selected based on cost, possible addition of compatible modeling software in the future, and the experience of consulting geophysicists in the Billings area. Installation of the software and integration of the hardware into the local office network was difficult at times but was accomplished with some technical support from Paradigm and Hewlett Packard, manufacturer of some of the network equipment. A