WorldWideScience

Sample records for off-gas performance test

  1. Off gas condenser performance modelling

    International Nuclear Information System (INIS)

    A suite of three programmes has been developed to model the ruthenium decontamination performance of a vitrification plant off-gas condenser. The stages of the model are: condensation of water vapour, NOx absorption in the condensate, RuO4 absorption in the condensate. Juxtaposition of these stages gives a package that may be run on an IBM-compatible desktop PC. Experimental work indicates that the criterion [HNO2] > 10 [RuO4] used to determine RuO4 destruction in solution is probably realistic under condenser conditions. Vapour pressures of RuO4 over aqueous solutions at 70o-90oC are slightly lower than the values given by extrapolating the ln Kp vs. T-1 relation derived from lower temperature data. (author)

  2. HC-21C off-gas test procedure. Revision 1

    International Nuclear Information System (INIS)

    Stabilization of plutonium bearing scrap material occurs in furnaces, FUR-21C-1 and FUR-21C-2, located in glovebox HC-21C. During previous testing and processing operations, water has been observed forming in the off-gas rotameters, FI-21C-1 and FI-21C-2. The off-gas is filtered through a 2 micron ceramic filter, F-21C-1 or F-21C-2, before discharge into the 26 inch vacuum system. The goal of this test plan is to determine the cause and location of water formation in the sludge stabilization off-gas system. The results should help determine what design improvements or processing steps will be implemented to prevent this phenomena from occurring in the future

  3. Development of off-gas filters for reprocessing plants. Development and construction of an off-gas filter system for large reprocessing plants. Off-gas section of the resolver test stand of the IHCh

    International Nuclear Information System (INIS)

    The test of the highly impregnated iodine sorption material AC 6,120 was continued in the laboratory under simulated conditions of a 1,500 t/a uranium reprocessing plant. The influence of NO in nitrogen as the carrier gas on the removal efficiency of the sorption material has been especially examined. Several experiments on the removal efficiency of iodine sorption by the material AC 6,120 were carried out in the original off-gas of the French processing plant SAP Marcoule while the filter system was installed on the one side directly behind the dissolver and on the other side behind the iodine desorption columm. The first iodine filter developed at LAF II was installed in the off-gas line of the dissolver in the Karlsruhe reprocessing plant. The filter system for the dissolver off-gas handling test rig of the IHCh was specified and ordered with an engineering firm. The conception of the prototype off-gas filter system was selected and a lock and transport system allowing to replace filters was designed and subjected for testing. Five alternative solutions were set up in order to find the appropriate filter concept. The method of selection based on the evaluation of performance criteria. According to the selected solution a filter drum was designed and constructed. The lock of the filter system has been designed and realized. Preliminary tests have been made. (orig.)

  4. Materials performance in off-gas systems containing iodine

    International Nuclear Information System (INIS)

    During the reprocessing of spent reactor fuel elements, iodine is released to gas streams from which it is ultimately removed by conversion to nonvolatile iodic acid. Under some conditions iodine can produce severe corrosion in off-gas lines; in this study these conditions were established. Iron- and nickel-based alloys containing more than 6% molybdenum, such as Hastelloy G (7%), Inconel 625 (9%), and Hastelloy C-276 (16%), as well as titanium and zirconium, remained free of attack under all conditions tested. When the other materials, notably the austenitic stainless steels, were exposed to gas streams containing even only low concentrations of iodine and water vapors at 25 and 400C, a highly corrosive, brownish-green liquid formed on their surfaces. In the complete absence of water vapor, the iodine-containing liquid did not form and all materials remained unaffected. The liquid that formed had a low pH (usually 2 inhibited attack

  5. ART CCIM Phase II-A Off-Gas System Evaluation Test Plan

    Energy Technology Data Exchange (ETDEWEB)

    Nick Soelberg; Jay Roach

    2009-01-01

    This test plan defines testing to be performed using the Idaho National Laboratory (INL) engineering-scale cold crucible induction melter (CCIM) test system for Phase II-A of the Advanced Remediation Technologies (ART) CCIM Project. The multi-phase ART-CCIM Project is developing a conceptual design for replacing the joule-heated melter (JHM) used to treat high level waste (HLW) in the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) with a cold crucible induction melter. The INL CCIM test system includes all feed, melter off-gas control, and process control subsystems needed for fully integrated operation and testing. Testing will include operation of the melter system while feeding a non-radioactive slurry mixture prepared to simulate the same type of waste feed presently being processed in the DWPF. Process monitoring and sample collection and analysis will be used to characterize the off-gas composition and properties, and to show the fate of feed constituents, to provide data that shows how the CCIM retrofit conceptual design can operate with the existing DWPF off-gas control system.

  6. Test results from the GA Technologies engineering-scale off-gas treatment system

    International Nuclear Information System (INIS)

    Test results are available from the GA Technologies (GA) off-gas treatment facilities using gas streams from both the graphite fuel element burner system and from the spent fuel dissolver. The off-gas system is part of a pilot plant for development of processes for treating spent fuel from high temperature gas-cooled reactors (HTGRs). One method for reducing the volume of HTGR fuel prior to reprocessing or spent fuel storage is to crush and burn the graphite fuel elements. The burner off-gas (BOG) contains radioactive components, principally H-3, C-14, Kr-85, I-129, and Rn-220, as well as chemical forms such as CO2, CO, O2, and SO2. The BOG system employs components designed to remove these constituents. Test results are reported for the iodine and SO2 adsorbers and the CO/HT oxidizer. Integrated testing of major BOG system components confirmed the performance of units evaluated in individual tests. Design decontamination and conversion factors were maintained for up to 72 h. In a reprocessing flowsheet, the solid product from the burners is dissolved in nitric or Thorex acid. The dissolver off-gas (DOG) contains radioactive components H-3, Kr-85, I-129, Rn-220 plus chemical forms such as nitrogen oxides (NO/sub x/). In the pilot-scale system iodine is removed from the DOG by adsorption. Tests of iodine removal have been conducted using either silver-exchanged mordenite (AgZ) or AgNO3-impregnated silica gel (AC-613-impregnated silica gel (AC-6120). Although each sorbent performed well in the presence of NO/sub x/, the silica gel adsorbent proved more efficient in silver utilization and, thus, more cost effective

  7. Development of high performance catalyst for off-gas treatment system in BWR

    International Nuclear Information System (INIS)

    A high performance catalyst for off-gas treatment system in boiling water reactor (BWR) has been developed. The hydrogen concentration in the outlets of off-gas recombiners increased at several BWR plants in Japan. These phenomena were caused by deactivation of catalysts for the recombiners, and we assumed two types of deactivation mechanisms. The first cause was an increase of the amount of boehmite in the catalyst support due to alternation of the manufacturing process. The other cause was catalysts being poisoned by cyclic siloxanes that were introduced from the silicone sealant used in the upstream of the off-gas recombiners. The catalysts were manufactured by Pt adhering on alumina support. The conventional catalyst (CAT-A) used the aqueous solution of the chloroplatinic acid for adhesion of Pt. A dechlorination process by autoclave was applied to prevent the equipment at the downstream of the recombiners from stress corrosion cracking, but this process caused the support material to transform into boehmite. The boehmite-rich catalysts were deactivated more easily by organic silicon than gamma alumina-rich catalysts. Therefore, the CAT-A was replaced at many Japanese BWR plants by the improved catalyst (CAT-B), and their support was transformed into more stable gamma alumina by heating at 500degC. However, the siloxanes keep being detected in the off-gas though the source of siloxane had been removed and there still remain possibilities to deactivate the catalystn possibilities to deactivate the catalysts. Therefore, we have been developing high performance catalyst (CAT-C) that has higher activity and durability against poisoning. We investigated the properties of CAT-C by performance tests and instrumental analyses. The dependency of thermal output of nuclear reactor, and durability against siloxane poisoning were investigated. We found that CAT-C showed higher performance and better properties than CAT-B did. Moreover, we have been developing a modeling method to evaluate the hydrogen recombination reaction and deactivation by siloxanes. A simple Arrhenius equation was applied for the model and the poisoning behavior was represented using several parameters determined by experiments. We reproduced the experimental poisoning behavior as the outlet hydrogen concentration with the developed model. (author)

  8. ART CCIM PHASE II-A OFF-GAS SYSTEM EVALUATION TEST REPORT

    Energy Technology Data Exchange (ETDEWEB)

    Nick Soelberg

    2009-04-01

    AREVA Federal Services (AFS) is performing a multi-year, multi-phase Advanced Remediation Technologies (ART) project, sponsored by the U.S. Department of Energy (DOE), to evaluate the feasibility and benefits of replacing the existing joule-heated melter (JHM) used to treat high level waste (HLW) in the Defense Waste Processing Facility (DWPF) at the Savannah River Site with a cold crucible induction melter (CCIM). The AFS ART CCIM project includes several collaborators from AREVA subsidiaries, French companies, and DOE national laboratories. The Savannah River National Laboratory and the Commissariat a l’Energie Atomique (CEA) have performed laboratory-scale studies and testing to determine a suitable, high-waste-loading glass matrix. The Idaho National Laboratory (INL) and CEA are performing CCIM demonstrations at two different pilot scales to assess CCIM design and operation for treating SRS sludge wastes that are currently being treated in the DWPF. SGN is performing engineering studies to validate the feasibility of retrofitting CCIM technology into the DWPF Melter Cell. The long-term project plan includes more lab-testing, pilot- and large-scale demonstrations, and engineering activities to be performed during subsequent project phases. A simulant of the DWPF SB4 feed was successfully fed and melted in a small pilot-scale CCIM system during two test series. The OGSE tests provide initial results that (a) provide melter operating conditions while feeding a DWPF SB4 simulant feed, (b) determine the fate of feed organic and metal feed constituents and metals partitioning, and (c) characterize the melter off-gas source term to a downstream off-gas system. The INL CCIM test system was operated continuously for about 30 hours during the parametric test series, and for about 58 hours during the OGSE test. As the DWPF simulant feed was continuously fed to the melter, the glass level gradually increased until a portion of the molten glass was drained from the melter. The glass drain was operated periodically on-demand. A cold cap of unmelted feed was controlled by adjusting the feedrate and melter power levels to obtain the target molten glass temperatures with varying cold cap levels. Three test conditions were performed per the test plan, during which the melter was operated with a target melt temperature of either 1,250oC or 1,300oC, and with either a partial or complete cold cap of unmelted feed on top of the molten glass. Samples of all input and output streams including the starting glass, the simulant feed, the off-gas particulate matter, product glass, and deposits removed from the crucible and off-gas pipe after the test were collected for analysis.

  9. ART CCIM PHASE II-A OFF-GAS SYSTEM EVALUATION TEST REPORT

    International Nuclear Information System (INIS)

    AREVA Federal Services (AFS) is performing a multi-year, multi-phase Advanced Remediation Technologies (ART) project, sponsored by the U.S. Department of Energy (DOE), to evaluate the feasibility and benefits of replacing the existing joule-heated melter (JHM) used to treat high level waste (HLW) in the Defense Waste Processing Facility (DWPF) at the Savannah River Site with a cold crucible induction melter (CCIM). The AFS ART CCIM project includes several collaborators from AREVA subsidiaries, French companies, and DOE national laboratories. The Savannah River National Laboratory and the Commissariat Energie Atomique (CEA) have performed laboratory-scale studies and testing to determine a suitable, high-waste-loading glass matrix. The Idaho National Laboratory (INL) and CEA are performing CCIM demonstrations at two different pilot scales to assess CCIM design and operation for treating SRS sludge wastes that are currently being treated in the DWPF. SGN is performing engineering studies to validate the feasibility of retrofitting CCIM technology into the DWPF Melter Cell. The long-term project plan includes more lab-testing, pilot- and large-scale demonstrations, and engineering activities to be performed during subsequent project phases. A simulant of the DWPF SB4 feed was successfully fed and melted in a small pilot-scale CCIM system during two test series. The OGSE tests provide initial results that (a) provide melter operating conditions while feeding a DWPF SB4 sting conditions while feeding a DWPF SB4 simulant feed, (b) determine the fate of feed organic and metal feed constituents and metals partitioning, and (c) characterize the melter off-gas source term to a downstream off-gas system. The INL CCIM test system was operated continuously for about 30 hours during the parametric test series, and for about 58 hours during the OGSE test. As the DWPF simulant feed was continuously fed to the melter, the glass level gradually increased until a portion of the molten glass was drained from the melter. The glass drain was operated periodically on-demand. A cold cap of unmelted feed was controlled by adjusting the feedrate and melter power levels to obtain the target molten glass temperatures with varying cold cap levels. Three test conditions were performed per the test plan, during which the melter was operated with a target melt temperature of either 1,250 C or 1,300 C, and with either a partial or complete cold cap of unmelted feed on top of the molten glass. Samples of all input and output streams including the starting glass, the simulant feed, the off-gas particulate matter, product glass, and deposits removed from the crucible and off-gas pipe after the test were collected for analysis

  10. Test results from the GA technologies engineering-scale off-gas treatment system

    International Nuclear Information System (INIS)

    One method for reducing the volume of HTGR fuel prior to reprocessing or spent fuel storage is to crush and burn the graphite fuel elements. The burner off-gas (BOG) contains radioactive components, principally H-3, C-14, Kr-85, I-129, and Rn-220, as well as chemical forms such as CO2, CO, O2, and SO2. The BOG system employs components designed to remove these constitutents. Test results are reported for the iodine and SO2 adsorbers and the CO/HT oxidizer. Silver-based iodine adsorbents were found to catalyze the premature conversion of CO to CO2. Subsequent tests showed that iodine removal could not be performed downstream of the CO/HT oxidizer since iodine in the BOG system rapidly deactivated the Pt-coated alumina CO catalyst. Lead-exchanged zeolite (PbX) was found to be an acceptable alternative for removing iodine from BOG without CO conversion. Intermittent and steady-state tests of the pilot-plant SO2 removal unit containing sodium-exchanged zeolite (NaX) demonstrated that decontamination factors greater than or equal to 100 could be maintained for up to 50 h. In a reprocessing flowsheet, the solid product from the burners is dissolved in nitric or Thorex acid. The dissolver off-gas (DOG) contains radioactive components H-3, Kr-85, I-129, Rn-220 plus chemical forms such as nitrogen oxides (NO/sub x/). In the pilot-scale system at GA, iodine is removed from the DOG by adsorption. Tests of iodine removal have been conducted using either silver-exchanged mordenite (AgZ) or AgNO3-impregnated silica gel (AC-6120). Although each sorbent performed well in the presence of NO/sub x/, the silica gel adsorbent proved more efficient in silver utilization and, thus, more cost effective

  11. Laboratory Evaporation Testing Of Hanford Waste Treatment Plant Low Activity Waste Off-Gas Condensate Simulant

    International Nuclear Information System (INIS)

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream, LAW Off-Gas Condensate, from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of canistered glass waste forms. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to be within acceptable concentration ranges in the LAW glass. Diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task examines the impact of potential future disposition of this stream in the Hanford tank farms, and investigates auxiliary evaporation to enable another disposition path. Unless an auxiliary evaporator is used, returning the stream to the tank farms would require evaporation in the 242-A evaporator. This stream is expected to be unusual because it will be very high in corrosive species that are volatile in the melter (chloride, fluoride, sulfur), will have high ammonia, and will contain carryover particulates of glass-former chemicals. These species have potential to cause corrosion of tanks and equipment, precipitation of solids, release of ammonia gas vapors, and scale in the tank farm evaporator. Routing this stream to the tank farms does not permanently divert it from recycling into the WTP, only temporarily stores it prior to reprocessing. Testing is normally performed to demonstrate acceptable conditions and limits for these compounds in wastes sent to the tank farms. The primary parameter of this phase of the test program was measuring the formation of solids during evaporation in order to assess the compatibility of the stream with the evaporator and transfer and storage equipment. The origin of this LAW Off-Gas Condensate stream will be the liquids from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW facility melter offgas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover. The soluble components are expected to be mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet, and, thus, the composition will not be available until the WTP begins operation, but a simulant has been produced based on models, calculations, and comparison with pilot-scale tests. This report discusses results of evaporation testing of the simulant. Two conditions were tested, one with the simulant at near neutral pH, and a second at alkaline pH. The neutral pH test is comparable to the conditions in the Hanford Effluent Treatment Facility (ETF) evaporator, although that evaporator operates at near atmospheric pressure and tests were done under vacuum. For the alkaline test, the target pH was based on the tank farm corrosion control program requirements, and the test protocol and equipment was comparable to that used for routine evaluation of feed compatibility studies for the 242-A evaporator. One of the

  12. Laboratory Evaporation Testing Of Hanford Waste Treatment Plant Low Activity Waste Off-Gas Condensate Simulant

    Energy Technology Data Exchange (ETDEWEB)

    Adamson, Duane J.; Nash, Charles A.; McCabe, Daniel J.; Crawford, Charles L.; Wilmarth, William R.

    2014-01-27

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream, LAW Off-Gas Condensate, from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of canistered glass waste forms. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to be within acceptable concentration ranges in the LAW glass. Diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task examines the impact of potential future disposition of this stream in the Hanford tank farms, and investigates auxiliary evaporation to enable another disposition path. Unless an auxiliary evaporator is used, returning the stream to the tank farms would require evaporation in the 242-A evaporator. This stream is expected to be unusual because it will be very high in corrosive species that are volatile in the melter (chloride, fluoride, sulfur), will have high ammonia, and will contain carryover particulates of glass-former chemicals. These species have potential to cause corrosion of tanks and equipment, precipitation of solids, release of ammonia gas vapors, and scale in the tank farm evaporator. Routing this stream to the tank farms does not permanently divert it from recycling into the WTP, only temporarily stores it prior to reprocessing. Testing is normally performed to demonstrate acceptable conditions and limits for these compounds in wastes sent to the tank farms. The primary parameter of this phase of the test program was measuring the formation of solids during evaporation in order to assess the compatibility of the stream with the evaporator and transfer and storage equipment. The origin of this LAW Off-Gas Condensate stream will be the liquids from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW facility melter offgas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover. The soluble components are expected to be mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet, and, thus, the composition will not be available until the WTP begins operation, but a simulant has been produced based on models, calculations, and comparison with pilot-scale tests. This report discusses results of evaporation testing of the simulant. Two conditions were tested, one with the simulant at near neutral pH, and a second at alkaline pH. The neutral pH test is comparable to the conditions in the Hanford Effluent Treatment Facility (ETF) evaporator, although that evaporator operates at near atmospheric pressure and tests were done under vacuum. For the alkaline test, the target pH was based on the tank farm corrosion control program requirements, and the test protocol and equipment was comparable to that used for routine evaluation of feed compatibility studies for the 242-A evaporator. One of the

  13. Test results in the treatment of HTR reprocessing off-gas

    International Nuclear Information System (INIS)

    The AKUT II-facility (throughput 10 m3/h, STP) for the clean up of the burner off-gas has been tested with synthetic off-gas and with off-gas from cold burner tests. The results are reported. During dissolution of the burner ash in nitric acid an off-gas is formed whose main component is air and which, besides the gaseous fission products, contains NO/sub x/. Before the separation of the gaseous fission products NO/sub x/ and/or O2 are removed by reaction with H2 or NH3. For these reactions catalysts were used. Because of the known disadvantages of catalytic systems, like reduction in efficiency by poisoning or thermal influence, the alternative method of thermal, flameless reduction was tested. The reactions were carried out in a stainless steel and a quartz reactor. Throughput, reaction temperature, O2-, NO/sub x/-, H2-, and NH3-concentrations respectively were varied. The goal of these tests was to remove O2 and NO/sub x/ to below 1 ppM behind the reactor and NH3 to below the detection limit of 50 ppM. It was found that at a reaction temperature of 7500C in the stainless steel reactor these goals can be reached for both H2 and NH3 as reducing agents. In the quartz reactor only the O2-H2-reaction takes place. Obviously stainless steel acts as a catalyst for all other reactionsons

  14. Evaluation of the HEPA filter in-place test method in a corrosive off-gas environment

    International Nuclear Information System (INIS)

    Experiments were performed to determine if the combined effects of temperature, humidity, and oxides of nitrogen (NO/sub x/) hinder the in-place testing of high-efficiency particulate air (HEPA) filters used for cleaning the off-gas from a nuclear waste solidification facility. The laboratory system that was designed to simulate the process off-gas contained two HEPA filters in series with sample ports before each filter and after the filter bank. The system also included a reaction bomb for partial conversion of NO to NO2. Instrumentation measured stream flow, humidity, NO/sub x/ concentration, and temperature. Comparison measurements of the DOP concentrations were made by a forward light-scattering photometer and a single particle intra-cavity laser particle spectrometer. Experimental conditions could be varied, but maximum system capabilities were 95% relative humidity, 900C, and 10,000 ppM of NO/sub x/. A 23 factorial experimental design was used for the test program. This design determined the main effects of each factor plus the interactions of the factors in combination. The results indicated that water vapor and NO/sub x/ interfere with the conventional photometer measurements. Suggested modifications that include a unique sample dryer are described to correct the interferences. The laser particle spectrometer appears to be an acceptable instrument for measurements under adverse off-gas conditions

  15. Interim report on testing of off-gas treatment technologies for abatement of atmospheric emissions of chlorinated volatile organic compounds

    International Nuclear Information System (INIS)

    The purpose of this report is to briefly summarize the results to date of the off-gas treatment program for atmospheric emissions of chlorinated volatile organic compounds (CVOCs), in particular trichloroethylene (TCE) and perchloroethylene (PCE). This program is part of the Department of Energy's Office of Technology Development's Integrated Demonstration for Treatment of Organics in Soil and Water at a Non-Arid Site. The off-gas treatment program was initiated after testing of in-situ air stripping with horizontal wells was completed. That successful test expectedly produced atmospheric emissions of CVOCs that were unabated. It was decided after that test that an off-gas treatment program would complement the Integrated Demonstration not only because off-gas treatment is an integral portion of remediation of CVOC contamination in groundwater and soil but also because several technologies were being developed across the US to mitigate CVOC emissions. A single platform for testing off-gas treatment technologies would facilitate systematic and unbiased evaluation of the emerging technologies

  16. Final Report on Testing of Off-Gas Treatment Technologies for Abatement of Atmospheric Emissions of Chlorinated Volatile Organic Compounds

    International Nuclear Information System (INIS)

    The purpose of this report is to summarize the results of the program for off-gas treatment of atmospheric emissions of chlorinated volatile organic compounds (CVOCs), in particular trichloroethylene (TCE) and perchloroethylene (PCE). This program was funded through the Department of Energy Office of Technology Development's VOC's in Non-Arid Soils Integrated Demonstration (VNID). The off-gas treatment program was initiated after testing of in-situ air stripping with horizontal wells was completed (Looney et al., 1991). That successful test expectedly produced atmospheric emissions of CVOCs that were unabated. It was decided after that test that an off-gas treatment is an integral portion of remediation of CVOC contamination in groundwater and soil but also because several technologies were being developed across the United States to mitigate CVOC emissions. A single platform for testing off-gas treatment technologies would facilitate cost effective evaluation of the emerging technologies. Another motivation for the program is that many CVOCs will be regulated under the Clean Air Act Amendments of 1990 and are already regulated by many state regulatory programs. Additionally, compounds such as TCE and PCE are pervasive subsurface environmental contaminants, and, as a result, a small improvement in terms of abatement efficiency or cost will significantly reduce CVOC discharges to the environment as well as costs to United States government and industry

  17. LABORATORY OPTIMIZATION TESTS OF TECHNETIUM DECONTAMINATION OF HANFORD WASTE TREATMENT PLANT LOW ACTIVITY WASTE OFF-GAS CONDENSATE SIMULANT

    Energy Technology Data Exchange (ETDEWEB)

    Taylor-Pashow, K.; Nash, C.; McCabe, D.

    2014-09-29

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of glass waste. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task examines the potential treatment of this stream to remove radionuclides and subsequently disposition the decontaminated stream elsewhere, such as the Effluent Treatment Facility (ETF), for example. The treatment process envisioned is very similar to that used for the Actinide Removal Process (ARP) that has been operating for years at the Savannah River Site (SRS), and focuses on using mature radionuclide removal technologies that are also compatible with longterm tank storage and immobilization methods. For this new application, testing is needed to demonstrate acceptable treatment sorbents and precipitating agents and measure decontamination factors for additional radionuclides in this unique waste stream. The origin of this LAW Off-Gas Condensate stream will be the liquids from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover. The soluble components are expected to be mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet and will not be available until the WTP begins operation, but a simulant has been produced based on models, calculations, and comparison with pilot-scale tests. One of the radionuclides that is volatile and expected to be in greatest abundance in this LAW Off-Gas Condensate stream is Technetium-99 ({sup 99}Tc). Technetium will not be removed from the aqueous waste in the Hanford WTP, and will primarily end up immobilized in the LAW glass by repeated recycle of the off-gas condensate into the LAW melter. Other radionuclides that are low but are also expected to be in measurable concentration in the LAW Off-Gas Condensate are {sup 129}I, {sup 90}Sr, {sup 137}Cs, {sup 241}Pu, and {sup 241}Am. These are present due to their partial volatility and some entrainment in the off-gas system. This report discusses results of optimized {sup 99}Tc decontamination testing of the simulant. Testing examined use of inorganic reducing agents for {sup 99}Tc. Testing focused on minimizing the quantity of sorbents/reactants added, and minimizing mixing time to reach the decontamination targets in this simulant formulation. Stannous chloride and ferrous sulfate were tested as reducing agents to determine the minimum needed to convert soluble pertechnetate to the insoluble technetium dioxide. The reducing agents were tried with and without sorbents.

  18. Iodine and NOx behavior in the dissolver off-gas and IODOX [Iodine Oxidation] systems in the Oak Ridge National Laboratory Integrated Equipment Test facility

    International Nuclear Information System (INIS)

    This paper describes the most recent in a series of experiments evaluating the behavior of iodine and NOx in the Integrated Equipment Test (IET) Dissolver Off-Gas (DOG) System. This work was performed as part of a joint collaborative program between the US Department of Energy and the Power and Nuclear Fuel Development Corporation of Japan. The DOG system consists of two shell-and-tube heat exchangers in which water and nitric acid are removed from the dissolver off-gas by condensation, followed by a packed tower in which NOx is removed by absorption into a dilute nitric acid solution. The paper also describes the results of the operation of the Iodine Oxidation (IODOX) System. This system serves to remove iodine from the DOG system effluent by absorption into hyperazeotropic nitric acid. 7 refs., 11 figs., 10 tabs

  19. 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.

  20. Laboratory Scoping Tests Of Decontamination Of Hanford Waste Treatment Plant Low Activity Waste Off-Gas Condensate Simulant

    Energy Technology Data Exchange (ETDEWEB)

    Taylor-Pashow, Kathryn M.; Nash, Charles A.; Crawford, Charles L.; McCabe, Daniel J.; Wilmarth, William R.

    2014-01-21

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of glass waste. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task seeks to examine the potential treatment of this stream to remove radionuclides and subsequently disposition the decontaminated stream elsewhere, such as the Effluent Treatment Facility (ETF), for example. The treatment process envisioned is very similar to that used for the Actinide Removal Process (ARP) that has been operating for years at the Savannah River Site (SRS), and focuses on using mature radionuclide removal technologies that are also compatible with longterm tank storage and immobilization methods. For this new application, testing is needed to demonstrate acceptable treatment sorbents and precipitating agents and measure decontamination factors for additional radionuclides in this unique waste stream. The origin of this LAW Off-Gas Condensate stream will be the liquids from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover. The soluble components are expected to be mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet and will not be available until the WTP begins operation, but a simulant has been produced based on models, calculations, and comparison with pilot-scale tests. One of the radionuclides that is volatile and expected to be in high concentration in this LAW Off-Gas Condensate stream is Technetium-99 ({sup 99}Tc). Technetium will not be removed from the aqueous waste in the Hanford WTP, and will primarily end up immobilized in the LAW glass by repeated recycle of the off-gas condensate into the LAW melter. Other radionuclides that are also expected to be in appreciable concentration in the LAW Off-Gas Condensate are {sup 129}I, {sup 90}Sr, {sup 137}Cs, and {sup 241}Am. This report discusses results of preliminary radionuclide decontamination testing of the simulant. Testing examined use of Monosodium Titanate (MST) to remove {sup 90}Sr and actinides, inorganic reducing agents for {sup 99}Tc, and zeolites for {sup 137}Cs. Test results indicate that excellent removal of {sup 99}Tc was achieved using Sn(II)Cl{sub 2} as a reductant, coupled with sorption onto hydroxyapatite, even in the presence of air and at room temperature. This process was very effective at neutral pH, with a Decontamination Factor (DF) >577 in two hours. It was less effective at alkaline pH. Conversely, removal of the cesium was more effective at alka

  1. Development And Initial Testing Of Off-Gas Recycle Liquid From The WTP Low Activity Waste Vitrification Process - 14333

    International Nuclear Information System (INIS)

    The Waste Treatment and Immobilization Plant (WTP) process flow was designed to pre-treat feed from the Hanford tank farms, separate it into a High Level Waste (HLW) and Low Activity Waste (LAW) fraction and vitrify each fraction in separate facilities. Vitrification of the waste generates an aqueous condensate stream from the off-gas processes. This stream originates from two off-gas treatment unit operations, the Submerged Bed Scrubber (SBS) and the Wet Electrospray Precipitator (WESP). Currently, the baseline plan for disposition of the stream from the LAW melter is to recycle it to the Pretreatment facility where it gets evaporated and processed into the LAW melter again. If the Pretreatment facility is not available, the baseline disposition pathway is not viable. Additionally, some components in the stream are volatile at melter temperatures, thereby accumulating to high concentrations in the scrubbed stream. It would be highly beneficial to divert this stream to an alternate disposition path to alleviate the close-coupled operation of the LAW vitrification and Pretreatment facilities, and to improve long-term throughput and efficiency of the WTP system. In order to determine an alternate disposition path for the LAW SBS/WESP Recycle stream, a range of options are being studied. A simulant of the LAW Off-Gas Condensate was developed, based on the projected composition of this stream, and comparison with pilot-scale testing. The primary radionuclide that vaporizes and accumulates in the stream is Tc-99, but small amounts of several other radionuclides are also projected to be present in this stream. The processes being investigated for managing this stream includes evaporation and radionuclide removal via precipitation and adsorption. During evaporation, it is of interest to investigate the formation of insoluble solids to avoid scaling and plugging of equipment. Key parameters for radionuclide removal include identifying effective precipitation or ion adsorption chemicals, solid-liquid separation methods, and achievable decontamination factors. Results of the radionuclide removal testing indicate that the radionuclides, including Tc-99, can be removed with inorganic sorbents and precipitating agents. Evaporation test results indicate that the simulant can be evaporated to fairly high concentration prior to formation of appreciable solids, but corrosion has not yet been examined

  2. Development And Initial Testing Of Off-Gas Recycle Liquid From The WTP Low Activity Waste Vitrification Process - 14333

    Energy Technology Data Exchange (ETDEWEB)

    McCabe, Daniel J.; Wilmarth, William R.; Nash, Charles A.; Taylor-Pashow, Kathryn M.; Adamson, Duane J.; Crawford, Charles L.; Morse, Megan M.

    2014-01-07

    The Waste Treatment and Immobilization Plant (WTP) process flow was designed to pre-treat feed from the Hanford tank farms, separate it into a High Level Waste (HLW) and Low Activity Waste (LAW) fraction and vitrify each fraction in separate facilities. Vitrification of the waste generates an aqueous condensate stream from the off-gas processes. This stream originates from two off-gas treatment unit operations, the Submerged Bed Scrubber (SBS) and the Wet Electrospray Precipitator (WESP). Currently, the baseline plan for disposition of the stream from the LAW melter is to recycle it to the Pretreatment facility where it gets evaporated and processed into the LAW melter again. If the Pretreatment facility is not available, the baseline disposition pathway is not viable. Additionally, some components in the stream are volatile at melter temperatures, thereby accumulating to high concentrations in the scrubbed stream. It would be highly beneficial to divert this stream to an alternate disposition path to alleviate the close-coupled operation of the LAW vitrification and Pretreatment facilities, and to improve long-term throughput and efficiency of the WTP system. In order to determine an alternate disposition path for the LAW SBS/WESP Recycle stream, a range of options are being studied. A simulant of the LAW Off-Gas Condensate was developed, based on the projected composition of this stream, and comparison with pilot-scale testing. The primary radionuclide that vaporizes and accumulates in the stream is Tc-99, but small amounts of several other radionuclides are also projected to be present in this stream. The processes being investigated for managing this stream includes evaporation and radionuclide removal via precipitation and adsorption. During evaporation, it is of interest to investigate the formation of insoluble solids to avoid scaling and plugging of equipment. Key parameters for radionuclide removal include identifying effective precipitation or ion adsorption chemicals, solid-liquid separation methods, and achievable decontamination factors. Results of the radionuclide removal testing indicate that the radionuclides, including Tc-99, can be removed with inorganic sorbents and precipitating agents. Evaporation test results indicate that the simulant can be evaporated to fairly high concentration prior to formation of appreciable solids, but corrosion has not yet been examined.

  3. FINAL REPORT REGULATORY OFF GAS EMISSIONS TESTING ON THE DM1200 MELTER SYSTEM USING HLW AND LAW SIMULANTS VSL-05R5830-1 REV 0 10/31/05

    Energy Technology Data Exchange (ETDEWEB)

    KRUGER AA; MATLACK KS; GONG W; BARDAKCI T; D' ANGELO NA; BRANDYS M; KOT WK; PEGG IL

    2011-12-29

    The operational requirements for the River Protection Project - Waste Treatment Plant (RPP-WTP) Low Activity Waste (LAW) and High Level Waste (HLW) melter systems, together with the feed constituents, impose a number of challenges to the off-gas treatment system. The system must be robust from the standpoints of operational reliability and minimization of maintenance. The system must effectively control and remove a wide range of solid particulate matter, acid mists and gases, and organic constituents (including those arising from products of incomplete combustion of sugar and organics in the feed) to concentration levels below those imposed by regulatory requirements. The baseline design for the RPP-WTP LAW primary off-gas system includes a submerged bed scrubber (SBS), a wet electrostatic precipitator (WESP), and a high efficiency particulate air (HEPA) filter. The secondary off-gas system includes a sulfur-impregnated activated carbon bed (AC-S), a thermal catalytic oxidizer (TCO), a single-stage selective catalytic reduction NOx treatment system (SCR), and a packed-bed caustic scrubber (PBS). The baseline design for the RPP-WTP HLW primary off-gas system includes an SBS, a WESP, a high efficiency mist eliminator (HEME), and a HEPA filter. The HLW secondary off-gas system includes a sulfur-impregnated activated carbon bed, a silver mordenite bed, a TCO, and a single-stage SCR. The one-third scale HLW DM1200 Pilot Melter installed at the Vitreous State Laboratory (VSL) was equipped with a prototypical off-gas train to meet the needs for testing and confirmation of the performance of the baseline off-gas system design. Various modifications have been made to the DM1200 system as the details of the WTP design have evolved, including the installation of a silver mordenite column and an AC-S column for testing on a slipstream of the off-gas flow; the installation of a full-flow AC-S bed for the present tests was completed prior to initiation of testing. The DM1200 system was reconfigured to enable testing of the baseline HLW or LAW off-gas trains to perform off-gas emissions testing with both LAW and HLW simulants in the present work. During 2002 and 2003, many of these off-gas components were tested individually and in an integrated manner with the DM1200 Pilot Melter. Data from these tests are being used to support engineering design confirmation and to provide data to support air permitting activities. In fiscal year 2004, the WTP Project was directed by the Office of River Protection (ORP) to comply with Environmental Protection Agency (EPA) Maximum Achievable Control Technology (MACT) requirements for organics. This requires that the combined melter and off-gas system have destruction and removal efficiency (DRE) of >99.99% for principal organic dangerous constituents (PODCs). In order to provide confidence that the melter and off-gas system are able to achieve the required DRE, testing has been directed with both LAW and HLW feeds. The tests included both 'normal' and 'challenge' WTP melter conditions in order to obtain data for the potential range of operating conditions for the WTP melters and off-gas components. The WTP Project, Washington State Department of Ecology, and ORP have agreed that naphthalene will be used for testing to represent semi-volatile organics and allyl alcohol will be used to represent volatile organics. Testing was also performed to determine emissions of halides, metals, products of incomplete combustion (PICs), dioxins, furans, coplanar PCBs, total hydrocarbons, and COX and NOX, as well as the particle size distribution (PSD) of particulate matter discharged at the end of the off-gas train. A description of the melter test requirements and analytical methods used is provided in the Test Plan for this work. Test Exceptions were subsequently issued which changed the TCO catalyst, added total organic emissions (TOE) to exhaust sampling schedule, and allowing modification of the test conditions in response to attainable plenum temperatures as well as temperature increase

  4. Low-Level waste phase 1 melter testing off gas and mass balance evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, C.N.

    1996-06-28

    Commercially available melter technologies were tested during 1994-95 as part of a multiphase program to test candidate technologies for vitrification of the low-level waste (LLW) stream to be derived from retrieval and pretreatment of Hanford Site tank wastes. Seven vendors were selected for Phase 1 testing to demonstrate vitrification of a high sodium content liquid LLW simulant. The tested melter technologies included four Joule-heated melters, a carbon electrode melter, a combustion melter, and a plasma melter. Various dry and slurry melter feed preparation processes were also tested. Various feed material samples, product glass samples, and process offgas streams were characterized to provide data for evaluation of process decontamination factors and material mass balances for each vitrification technology. This report describes the melter mass balance evaluations and results for six of the Phase 1 LLW melter vendor demonstration tests.

  5. Long-Term Performance of Sulfer-Impregnated Granulated Activated Carbon (GAC) for Mercury Removal from NWCF Off-Gas

    International Nuclear Information System (INIS)

    Radioactive, Sodium-Bearing Waste (SBW) from past nuclear fuel reprocessing is currently being stored at the Idaho Nuclear Technology and Engineering Center (INTEC). Calcination of the SBW in the New Waste Calcining Facility (NWCF), upgraded with off-gas treatment technology to comply with the Environmental Protection Agency (EPA) Maximum Achievable Control Technology (MACT) rules is being considered as a waste treatment option. Mercury is a volatile component of the SBW. Current flow sheets and off-gas monitoring results from past NWCF operations have indicated that future mercury emissions may exceed the proposed (MACT) limit of 45 ug/dscm (micrograms/dry standard cubic meter) normalized to 7% O2 for existing Hazardous Waste Combustors (HWC) if modifications are not made

  6. FY'99 final report for the expedited technology demonstration project: demonstration test results for the MSO/off-gas and salt recycle system

    International Nuclear Information System (INIS)

    Molten Salt Oxidation (MSO) is a promising alternative to incineration for the treatment of a variety of organic wastes. Lawrence Livermore National Laboratory (LLNL) has prepared a facility in which an integrated pilot-scale MSO treatment system is being tested and demonstrated. The system consists of a MSO vessel with a dedicated off-gas treatment system, a salt recycle system, feed preparation equipment, and a ceramic final waste forms immobilization system. This integrated system was designed and engineered based on operational experience with an engineering-scale reactor unit and extensive laboratory development on salt recycle and final forms preparation. The MSO/off-gas system has been operational since December 1997. The salt recycle system and the ceramic final forms immobilization became operational in May 1998. In FY98, we have tested the MSO facility with various organic feeds, including chlorinated solvents, tributyl phosphate/kerosene, PCB-contaminated waste oils and solvents, booties, plastic pellets, ion exchange resins, activated carbon, radioactive-spiked organics, and well-characterized low-level liquid mixed wastes. MSO is shown to be a versatile technology for hazardous waste treatment and may be a solution to many waste disposal problems in DOE sites. The results of the demonstration conducted in FY98 has been reported [1]. In FY99 (October 1998 to April 1999) we conducted further testing in the MSO/off-gas system with ion exchange resins, two reas system with ion exchange resins, two real waste specimens, activated carbon, and TNT-loaded activated carbon, both at regular feed rates and higher feed rates up to a superficial gas velocity of 1.75 ft/s. We also drained the salt three times (SR7, SR8, SR9) in FY99 and sent the spent salts to the salt recycle system for further processing. This report presents the results obtained from the demonstration of the MSO/off-gas system and the salt recycle system from October 1998 to April 1999. We then shut down the operation and cleaned the equipment and the facility in May 1999

  7. Method for freezing out xenon from the dissolver off-gas from fuel reprocessing plants

    International Nuclear Information System (INIS)

    A laboratory arrangement on the basis of an evaporator-type cryostatic temperature regulator with LN2 cooling has been developed to separate radioactive xenon impurities by freezing out from the dissolver off-gas from fuel reprocessing plants. This simple cryotrapping principle enables freezing out of xenon controlled only by temperature. This is confirmed by the results of extensive test performed with simulated dissolver off-gas mixes (having a xenon content <= 2 vol%). (orig./HP)

  8. Off-gas considerations for a vitrification plant in the republic of Korea

    International Nuclear Information System (INIS)

    The Republic of Korea is in the process of preparing for its first ever vitrification plant to handle low and intermediate-level radioactive waste from her pressurized water reactors (PWRs). KEPRI, in coordination with her partners, will design, construct, and erect a pilot plant using data from the orientation tests. The pilot plant will be the basis for the development of the final objective, the establishment of an industrial scale vitrification installation in the Republic of Korea. Throughout these projects, the major goal is to minimize the harmful effects of the final waste form to the environment. The gaseous effluents emissions from the facility will need to be managed to meet the environmental regulations concerning gaseous releases into the environment of the Republic of Korea. The focus of this paper is on the considerations for the treatment of the off-gas for a low and intermediate-level radioactive waste treatment vitrification installation in the Republic of Korea. Off-gas considerations will span a wide-range of areas such as waste characteristics, thermal treatment systems, off-gas regulations, off-gas characteristics, assessment of air pollution control devices, systems assessments, numerical modelling, economics etc. Off-gas regulations in Korea are becoming tighter and will likely change from year to year. In terms of both off-gas treatment equipment performance and public protection, the amount and nature (e.g. chemical behavior and morphology) o (e.g. chemical behavior and morphology) of the species are important. The emissions may be classified as toxic metals, radionuclides, hydrocarbons, particulate matter, and acid gases. Air pollution control technologies are generally classified as wet or dry technologies covering over 40 different air pollution control devices (APCDs) with varying removal efficiencies for the different types of off-gas. In general, the state of the art systems for vitrification technologies incorporate the basic functions such as further oxidation of products of incomplete combustion (PICs), particle scrubbing, acid gas scrubbing, particle filtering, and continuous emissions monitoring that would also be utilized for other thermal treatment systems such as incinerators. Although, it is still not possible to use only computer simulation for the design of an off-gas treatment system, numerical modelling may be utilized to help speed design, examine situations difficult to model experimentally, help optimize system processes, etc. These considerations should help provide for an optimal off-gas treatment system for the managing of toxic emissions

  9. Electron beam processing of industrial off gas

    International Nuclear Information System (INIS)

    Full text: Emissions of chlorinated aromatic compounds e.g. polychlorinated dioxins and furans (PCDD/F) have been reported recently from a large number of industrial processes such as waste incineration and metal smelters. Due to the toxicity of PCDD/F, stringent emission limits have been imposed. State of the art for emission control are adsorption processes, which have removal efficiencies, but produced PCDD contaminated wastes. The incineration or disposal of these material is rather costly. Therefore, new technologies are being developed, which do not yield secondary wastes, such as catalysts, hydrogen peroxide injection or electron beam irradiation. Here the results on the electron beam induced decomposition of PCDD/F in incinerator off gas are reported. We used a mobile off gas cleaning plant (AGATE-M), which is equipped with 200 keV electron accelerator (EB). The off gas was sampled in the upstream and downstream of the irradiation zone by a condensation method. Subsequent clean-up and GC-MS analyses were performed using standard analytical methods. The analyses show that very high decompositions for PCDD and PCDF are achieved depending on the experimental parameters and the German emission standards are surpassed. In addition, chlorinated phenols and benzenes are destroyed. A computer model (AGATE-code) was developed to analyse the gas phase chemistry of the process. The experimental and the theoretical results are reported and compared. The energy consumptionorted and compared. The energy consumption of the process is of the order of 3-5 kWh per 100 m3 of treated off gas. The process has a very low pressure difference. The industrial application of the technology will be evaluated in comparison to competing methods with respect to costs and technical aspects

  10. Nuclear off-gas treatment...the cryogenic distillation method

    International Nuclear Information System (INIS)

    Instrumentation for the cryogenic distillation method of treating off-gas from a BWR nuclear power plant is described. A review of control valve reliability and leakage tests is presented. The design and testing of monitor and control analyzers to ensure process safety are considered, along with the seismic requirements applicable to all the instrumentation

  11. Hanford Low-Activity Waste Processing: Demonstration of the Off-Gas Recycle Flowsheet - 13443

    International Nuclear Information System (INIS)

    Vitrification of Hanford Low-Activity Waste (LAW) is nominally the thermal conversion and incorporation of sodium salts and radionuclides into borosilicate glass. One key radionuclide present in LAW is technetium-99. Technetium-99 is a low energy, long-lived beta emitting radionuclide present in the waste feed in concentrations on the order of 1-10 ppm. The long half-life combined with a high solubility in groundwater results in technetium-99 having considerable impact on performance modeling (as potential release to the environment) of both the waste glass and associated secondary waste products. The current Hanford Tank Waste Treatment and Immobilization Plant (WTP) process flowsheet calls for the recycle of vitrification process off-gas condensates to maximize the portion of technetium ultimately immobilized in the waste glass. This is required as technetium acts as a semi-volatile specie, i.e. considerable loss of the radionuclide to the process off-gas stream can occur during the vitrification process. To test the process flowsheet assumptions, a prototypic off-gas system with recycle capability was added to a laboratory melter (on the order of 1/200 scale) and testing performed. Key test goals included determination of the process mass balance for technetium, a non-radioactive surrogate (rhenium), and other soluble species (sulfate, halides, etc.) which are concentrated by recycling off-gas condensates. The studies performed are the initial demonstrations of process recycle for this type of liquid-fed melter system. This paper describes the process recycle system, the waste feeds processed, and experimental results. Comparisons between data gathered using process recycle and previous single pass melter testing as well as mathematical modeling simulations are also provided. (authors)

  12. Development and Testing of the Advanced CHP System Utilizing the Off-Gas from the Innovative Green Coke Calcining Process in Fluidized Bed

    Energy Technology Data Exchange (ETDEWEB)

    Chudnovsky, Yaroslav; Kozlov, Aleksandr

    2013-08-15

    Green petroleum coke (GPC) is an oil refining byproduct that can be used directly as a solid fuel or as a feedstock for the production of calcined petroleum coke. GPC contains a high amount of volatiles and sulfur. During the calcination process, the GPC is heated to remove the volatiles and sulfur to produce purified calcined coke, which is used in the production of graphite, electrodes, metal carburizers, and other carbon products. Currently, more than 80% of calcined coke is produced in rotary kilns or rotary hearth furnaces. These technologies provide partial heat utilization of the calcined coke to increase efficiency of the calcination process, but they also share some operating disadvantages. However, coke calcination in an electrothermal fluidized bed (EFB) opens up a number of potential benefits for the production enhancement, while reducing the capital and operating costs. The increased usage of heavy crude oil in recent years has resulted in higher sulfur content in green coke produced by oil refinery process, which requires a significant increase in the calcinations temperature and in residence time. The calorific value of the process off-gas is quite substantial and can be effectively utilized as an “opportunity fuel” for combined heat and power (CHP) production to complement the energy demand. Heat recovered from the product cooling can also contribute to the overall economics of the calcination process. Preliminary estimates indicated the decrease in energy consumption by 35-50% as well as a proportional decrease in greenhouse gas emissions. As such, the efficiency improvement of the coke calcinations systems is attracting close attention of the researchers and engineers throughout the world. The developed technology is intended to accomplish the following objectives: - Reduce the energy and carbon intensity of the calcined coke production process. - Increase utilization of opportunity fuels such as industrial waste off-gas from the novel petroleum coke calcination process. - Increase the opportunity of heat (chemical and physical) utilization from process off-gases and solid product. - Develop a design of advanced CHP system utilizing off-gases as an “opportunity fuel” for petroleum coke calcinations and sensible heat of calcined coke. A successful accomplishment of the aforementioned objectives will contribute toward the following U.S. DOE programmatic goals: - Drive a 25% reduction in U. S. industrial energy intensity by 2017 in support of EPAct 2005; - Contribute to an 18% reduction in U.S. carbon intensity by 2012 as established by the Administration’s “National Goal to Reduce Emissions Intensity.” 8

  13. Literature search for offsite data to improve the DWPF melter off-gas model

    Energy Technology Data Exchange (ETDEWEB)

    Daniel, W.E.

    2000-05-04

    This report documents the literature search performed and any relevant data that may help relax some of the constraints on the DWPF melter off-gas model. The objective of this task was to look for outside sources of technical data to help reduce some of the conservatism built in the DWPF melter off-gas model.

  14. FY-12 INL KR CAPTURE ACTIVITIES SUPPORTING THE OFF-GAS SIGMA TEAM

    Energy Technology Data Exchange (ETDEWEB)

    Troy G. Garn; Mitchell R. Greenhalgh; Jack D Law

    2012-08-01

    Tasks performed this year by INL Kr capture off-gas team members can be segregated into three separate task sub-sections which include: 1) The development and testing of a new engineered form sorbent, 2) An initial NDA gamma scan effort performed on the drum containing the Legacy Kr-85 sample materials, and 3) Collaborative research efforts with PNNL involving the testing of the Ni-DOBDC MOF and an initial attempt to make powdered chalcogel material into an engineered form using our binding process. This document describes the routes to success for the three task sub-sections.

  15. Waste Feed Evaporator Off-Gas Emissions Modeling

    International Nuclear Information System (INIS)

    The objectives of this task given in the test specification were to expand the waste feed evaporator OLI model by including all the major components of the evaporator off-gas treatment system. Also as part of this task, two test cases were developed that defined the baseline untreated waste feed composition, target organic components to be tracked, and the waste-to-recycle blend ratio. The goal of this task was to develop air emissions projections for two test cases using the expanded waste feed evaporator OLI model. The organic partitioning predictions and air emission projections are ultimately to be validated against experimental data obtained during pilot evaporator tests. The Environmental Simulation Program (ESP) software, licensed by OLI Systems, Inc., was used to build the current as well as earlier models for the FEP 7. The steady state simulation package performs vapor/liquid/solid equilibrium for electrochemical streams and processes. All vapor/liquid/solid equilibrium is determined by the OLI simulation engine. This task partially satisfied the test conditions and requirements described in the Research and Technology Plan (PL-W375-TE00007, Rev. 0) prepared by Bechtel National, Inc. (BNI). Specifically, BNI will use the information obtained during this task to support environmental regulatory permitting efforts for the waste feed evaporator and further to provide the operating data and correlations for the RPP-WTP flowsheet modellowsheet model

  16. Technology of off-gas treatment for liquid-fed ceramic melters

    Energy Technology Data Exchange (ETDEWEB)

    Scott, P.A.; Goles, R.W.; Peters, R.D.

    1985-05-01

    The technology for treating off gas from liquid-fed ceramic melters (LFCMs) has been under development at the Pacific Northwest Laboratory since 1977. This report presents the off-gas technology as developed at PNL and by others to establish a benchmark of development and to identify technical issues. Tests conducted on simulated (nonradioactive) wastes have provided data that allow estimation of melter off-gas composition for a given waste. Mechanisms controlling volatilization of radionuclides and noxious gases are postulated, and correlations between melter operation and emissions are presented. This report is directed to those familiar with LFCM operation. Off-gas treatment systems always require primary quench scrubbers, aerosol scrubbers, and final particulate filters. Depending on the composition of the off gas, equipment for removal of ruthenium, iodine, tritium, and noxious gases may also be needed. Nitrogen oxides are the most common noxious gases requiring treatment, and can be controlled by aqueous absorption or catalytic conversion with ammonia. High efficiency particulate air (HEPA) filters should be used for final filtration. The design criteria needed for an off-gas system can be derived from emission regulations and composition of the melter feed. Conservative values for melter off-gas composition can be specified by statistical treatment of reported off-gas data. Statistical evaluation can also be used to predict the frequency and magnitude of normal surge events that occur in the melter. 44 refs., 28 figs., 17 tabs.

  17. Technology of off-gas treatment for liquid-fed ceramic melters

    International Nuclear Information System (INIS)

    The technology for treating off gas from liquid-fed ceramic melters (LFCMs) has been under development at the Pacific Northwest Laboratory since 1977. This report presents the off-gas technology as developed at PNL and by others to establish a benchmark of development and to identify technical issues. Tests conducted on simulated (nonradioactive) wastes have provided data that allow estimation of melter off-gas composition for a given waste. Mechanisms controlling volatilization of radionuclides and noxious gases are postulated, and correlations between melter operation and emissions are presented. This report is directed to those familiar with LFCM operation. Off-gas treatment systems always require primary quench scrubbers, aerosol scrubbers, and final particulate filters. Depending on the composition of the off gas, equipment for removal of ruthenium, iodine, tritium, and noxious gases may also be needed. Nitrogen oxides are the most common noxious gases requiring treatment, and can be controlled by aqueous absorption or catalytic conversion with ammonia. High efficiency particulate air (HEPA) filters should be used for final filtration. The design criteria needed for an off-gas system can be derived from emission regulations and composition of the melter feed. Conservative values for melter off-gas composition can be specified by statistical treatment of reported off-gas data. Statistical evaluation can also be used to predict the frequency and magnitude of normal surge events that occur in the melter. 44 refs., 28 figs., 17 tabs

  18. Development of off-gas filters for reprocessing plants

    International Nuclear Information System (INIS)

    At the high linear air velocity of 63 cm/s of the dissolver off-gas found in the iodine sorption material AC 6120/H1 for the newly fixed volume flow and at the iodine concentrations corresponding to a large-scale reprocessing plant disturbances in the removal profile occurred in laboratory tests, which are presently investigated in more detail and might result in excluding gas velocities > 60 cm/s. The gas-chromatographic measurements of the organic iodine components contained in the WAK dissolver off-gas yielded low concentrations of methyl-, ethyl- and butyl-iodide. At the aerosol and iodine measuring console decontamination factors for aerosols of 120 - 160 were measured downstream of the WAK aerosol filter, using the activities of individual isotopes. The decontamination factors for I-129 were found to be > 103 for a residence time of 1.4 s. (orig.)

  19. Off-gas treatment in HTR fuel reprocessing

    International Nuclear Information System (INIS)

    In the reprocessing of HTR fuel essentially all of the gaseous fission products are released during the head-end treatment, which includes burning of the graphite matrix and dissolving of the heavy metallic residues in THOREX reagent. Test facilities for off-gas cleaning have been developed. The burner off-gas consists mainly of CO2 and with 0.5 ppm Kr and 10-3 ppm T in the form of tritiated water. After a caralytic burning step to remove the CO, the off-gas is liquified and distilled. The Kr-rich distillate is transferred to gas cylinders for storage. The Kr-free bottom product contains the tritiated water which is absorbed on a molecular sieve before the CO2 is released to the atmosphere. The dissolver off-gas consists mainly of air with 90 ppm Kr, 500 ppm Xe, 5 x 10-2 ppm T as tritiated water and 1,500 ppm NOsub(x). The gas is dried and filtered before oxygen and NOsub(x) are reacted with H2 in the presence of a catalyst to form N2 and H2O. The gas (N2, Ar, Xe, Kr) then enters the cryogenic separation unit where Xe freezes out in cold traps and the remaining gas is liquified and distilled. The Kr-free distillate (N2, Ar) is released to the atmosphere, the Kr-rich bottom product is stored in gas cylinders. The frozen out Xe contains about 1% Kr. To gain pure Xe this mixture is also distilled. The status of the facility development and test results will be reported. (orig.)

  20. Sorption Modeling and verification for Off-Gas Treatment

    Energy Technology Data Exchange (ETDEWEB)

    Tavlarides, Lawrence L.; Yiacoumi, Sotira; Tsouris, Costas; Gabitto, Jorge; DePaoli, David

    2015-04-29

    The project has made progress toward developing a comprehensive modeling capability for the capture of target species in off gas evolved during the reprocessing of nuclear fuel. The effort has integrated experimentation, model development, and computer code development for adsorption and absorption processes. For adsorption, a modeling library has been initiated to include (a) equilibrium models for uptake of off-gas components by adsorbents, (b) mass transfer models to describe mass transfer to a particle, diffusion through the pores of the particle and adsorption on the active sites of the particle, and (c) interconnection of these models to fixed bed adsorption modeling which includes advection through the bed. For single-component equilibria, a Generalized Statistical Thermodynamic Adsorption (GSTA) code was developed to represent experimental data from a broad range of isotherm types; this is equivalent to a Langmuir isotherm in the two-parameter case, and was demonstrated for Kr on INL engineered sorbent HZ PAN, water sorption on molecular sieve 3A sorbent material (MS3A), and Kr and Xe capture on metal-organic framework (MOF) materials. The GSTA isotherm was extended to multicomponent systems through application of a modified spreading pressure surface activity model and generalized predictive adsorbed solution theory; the result is the capability to estimate multicomponent adsorption equilibria from single-component isotherms. This advance, which enhances the capability to simulate systems related to off-gas treatment, has been demonstrated for a range of real-gas systems in the literature and is ready for testing with data currently being collected for multicomponent systems of interest, including iodine and water on MS3A. A diffusion kinetic model for sorbent pellets involving pore and surface diffusion as well as external mass transfer has been established, and a methodology was developed for determining unknown diffusivity parameters from transient uptake data. Two parallel approaches have been explored for integrating the kernels described above into a mass-transport model for adsorption in fixed beds. In one, the GSTA isotherm kernel has been incorporated into the MOOSE framework; in the other approach, a focused finite-difference framework and PDE kernels have been developed. Issues, including oscillatory behavior in MOOSE solutions to advection-diffusion problems, and opportunities have been identified for each approach, and a path forward has been identified toward developing a stronger modeling platform. Experimental systems were established for collection of microscopic kinetics and equilibria data for single and multicomponent uptake of gaseous species on solid sorbents. The systems, which can operate at ambient temperature to 250°C and dew points from -69 to l7°C, are useful for collecting data needed for modeling performance of sorbents of interest. Experiments were conducted to determine applicable models and parameters for isotherms and mass transfer for water and/or iodine adsorption on MS3A. Validation experiments were also conducted for water adsorption on fixed beds ofMS3A. For absorption, work involved modeling with supportive experimentation. A dynamic model was developed to simulate C02 absorption with chemical reaction using high alkaline content water solutions. A computer code was developed to implement the model based upon transient mass and energy balances. Experiments were conducted in a laboratory-scale column to determine model parameters. The influence of geometric parameters and operating variables on C02 absorption was studied over a wide range of conditions. This project has resulted in 7 publications, with 3 manuscripts in preparation. Also, 15 presentations were given at national meetings of ANS and AIChE and at Material Recovery and Waste Forms Campaign Working Group meetings.

  1. Characterization Of DWPF Melter Off-Gas Quencher Sample

    International Nuclear Information System (INIS)

    The Savannah River National Laboratory (SRNL) recently received a deposit sample from the Melter Primary Off Gas System (POG) of the Defense Waste Processing Facility (DWPF). This sample was composed of material that had been collected while the quencher was in operation January 27, 2011 through March 31, 2011. DWPF requested, through a technical assistance request, characterization of the melter off-gas deposits by x-ray diffraction (XRD), scanning electron microscopy (SEM), and chemical analysis. The purpose of the Melter Off-Gas System is to reduce the amount of radioactive particles and mercury in the gases vented to the atmosphere. Gases emitted from the melter pass through the primary film cooler, quencher, Off-Gas Condensate Tank (OGCT), Steam Atomized Scrubbers (SAS), a condenser, a high efficiency mist eliminator, and a high efficiency particulate air filter, before being vented to the Process Vessel Vent System. The film coolers cool the gases leaving the melter vapor space from ?750 C to ?375 C, by introducing air and steam to the flow. In the next step, the quencher cools the gas to about 60 C by bringing the condensate from the OGCT in contact with the effluent (Figure 1). Most of the steam in the effluent is then condensed and the melter vapor space pressure is reduced. The purpose of the OGCT is to collect and store the condensate formed during the melter operation. Condensate from the OGCT is circulated to the SAS and atomized with steam. This atomSAS and atomized with steam. This atomized condensate is mixed with the off-gas to wet and join the particulate which is then removed in the cyclone. The next stage incorporates a chilled water condenser which separates the vapors and elemental mercury from the off-gas steam. Primary off-gas deposit samples from the DWPF melter have previously been analyzed. In 2003, samples from just past the film cooler, from the inlet of the quencher and inside the quencher were analyzed at SRNL. It was determined that the samples were a mixture of sludge and glass frit. The major component was Si along with Fe, Al, and other elements in the radioactive waste being processed. The deposits analyzed also contained U-235 fission products and actinide elements. Prior to that, deposits in the off-gas system in the DWPF nonradioactive half scale melter and the one-tenth scale integrated DWPF melter system were analyzed and determined to be mixtures of alkali rich chlorides, sulfates, borates, and fluorides entrained with iron oxides, spinels and frit particles formed by vapor-phase transport and condensation. Additional work was performed in 2007 in which researchers similarly found the deposits to be a combination of sludge and frit particles.

  2. Exergetic Optimization of a Refrigeration Cycle for Re-Liquefaction of LNG Boil-Off Gas

    OpenAIRE

    Sayyaadi, Hoseyn; Babaelahi, Mojtaba

    2010-01-01

    The development of liquefaction process for liquefied natural gas boil-off re-liquefaction plants will be addressed to provide an environmentally friendly and cost effective solution for gas transport. Onboard boil-off gas (BOG) re-liquefaction is a new technology that liquefies BOG and returns it to the cargo tanks instead of burning it. Exergetic efficiency optimization for cryogenic refrigeration cycle for re-liquefaction of LNG boil-off gas is performed. Thermodynamic modeling has been pe...

  3. Adsorption Model for Off-Gas Separation

    Energy Technology Data Exchange (ETDEWEB)

    Veronica J. Rutledge

    2011-03-01

    The absence of 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 countries. Thus, it is essential to model complex series of unit operations to simulate, understand, and predict inherent transient behavior and feedback loops. A capability of accurately simulating the dynamic behavior of advanced fuel cycle separation processes will provide substantial cost savings and many technical benefits. The specific fuel cycle separation process discussed in this report is the off-gas treatment system. The off-gas separation consists of a series of scrubbers and adsorption beds to capture constituents of interest. Dynamic models are being developed to simulate each unit operation involved so each unit operation can be used as a stand-alone model and in series with multiple others. Currently, an adsorption model has been developed in gPROMS software. Inputs include gas stream constituents, sorbent, and column properties, equilibrium and kinetic data, and inlet conditions. It models dispersed plug flow in a packed bed under non-isothermal and non-isobaric conditions for a multiple component gas stream. The simulation outputs component concentrations along the column length as a function of time from which the breakthrough data is obtained. It also outputs temperature along the column length as a function of time and pressure drop along the column length. Experimental data will be input into the adsorption model to develop a model specific for iodine adsorption on silver mordenite as well as model(s) specific for krypton and xenon adsorption. The model will be validated with experimental breakthrough curves. Another future off-gas modeling goal is to develop a model for the unit operation absorption. The off-gas models will be made available via the server or web for evaluation by customers.

  4. Off-gas system data summary for the ninth run of the large slurry fed melter

    International Nuclear Information System (INIS)

    The ninth melter campaign successfully demonstrated extended operation of both melter and off-gas systems. Two critical problem areas associated with the handling of melter off-gases were resolved leading to firm definition of the DWPF Off-Gas Treatment System. These two concerns, wet scrubber decontamination efficiency and the reduction of solids deposition at the off-gas line entrance, were the primary focus of off-gas system studies during the 63-day run (LSFM-9). The Hydro-Sonic Scrubber was confirmed to be the superior candidate for wet scrubbing by outperforming all other scrubbers tested at the Equipment Test Facility (ETF). The two stage, steam-driven scrubber achieved consistent decontamination factors for cesium exceeding the required DWPF flowsheet DF of 50. As a result, the device was selected as the reference wet scrubber for the DWPF. The Off-Gas Film Cooling device continued to show promising results for reducing three accumulation of solid deposits at the entrance to the off-gas line. In addition, a rotating wire brush cleaning device provided easy and efficient removal of deposits which had accumulated. The combination of the two has adequately resolved the deposit accumulation problem and both devices have been incorporated in the DWPF design

  5. Safety evaluation of BWR off-gas treatment systems

    International Nuclear Information System (INIS)

    Some of the results of a safety evaluation performed on current generic types of BWR off-gas treatment systems including cooled and ambient temperature adsorber beds and cryogenics are presented. The evaluation covered the four generic types of off-gas systems and the systems of five major vendors. This study was part of original work performed under AEC contract for the Directorate of Regulatory Standards. The analysis techniques employed for the safety evaluation of these systems include: Fault Tree Analysis; FMECA (Failure Mode Effects and Criticality Analysis); general system comparisons, contaminant, system control, and design adequacy evaluations; and resultant Off-Site Dose Calculations. The salient areas presented are some of the potential problem areas, the approach that industry has taken to mitigate or design against potential upset conditions, and areas where possible deficiencies still exist. Potential problem areas discussed include hydrogen detonation, hydrogen release to equipment areas, operator/automatic control interface, and needed engineering evaluation to insure safe system operation. Of the systems reviewed, most were in the category of advanced or improved over that commonly in use today, and a conclusion from the study was that these systems offer excellent potential for noble gas control for BWR power plants where more stringent controls may be specified -- now or in the future. (U.S.)

  6. Method and apparatus for off-gas composition sensing

    Science.gov (United States)

    Ottesen, David Keith (Livermore, CA); Allendorf, Sarah Williams (Fremont, CA); Hubbard, Gary Lee (Richmond, CA); Rosenberg, David Ezechiel (Columbia, MD)

    1999-01-01

    An apparatus and method for non-intrusive collection of off-gas data in a steelmaking furnace includes structure and steps for transmitting a laser beam through the off-gas produced by a steelmaking furnace, for controlling the transmitting to repeatedly scan the laser beam through a plurality of wavelengths in its tuning range, and for detecting the laser beam transmitted through the off-gas and converting the detected laser beam to an electrical signal. The electrical signal is processed to determine characteristics of the off-gas that are used to analyze and/or control the steelmaking process.

  7. Development of membrane moisture separator for BWR off-gas system

    International Nuclear Information System (INIS)

    In BWR plant off-gas treatment systems, dehumidifiers are used to maintain noble gas adsorption efficiency in the first half of the charcoal hold-up units. From the perspective of simplifying and reducing the cost of such a dehumidification system, Japanese BWR utilities and plant fabricators have been developing a dehumidification system employing moisture separation membrane of the type already proven in fields such as medical instrumentation and precision measuring apparatus. The first part of this development involved laboratory testing to simulate the conditions found in an actual off-gas system, the results of which demonstrated satisfactory results in terms of moisture separation capability and membrane durability, and suggested favorable prospects for application in actual off-gas systems. Further, in-plant testing to verify moisture separation capability and membrane durability in the presence of actual gases is currently underway, with results so far suggesting that the system is capable of obtaining good moisture separation capability. (author)

  8. INTEGRATED DM 1200 MELTER TESTING OF HLW C-106/AY-102 COMPOSITION USING BUBBLERS VSL-03R3800-1 REV 0 9/15/03

    Energy Technology Data Exchange (ETDEWEB)

    KRUGER AA; MATLACK KS; GONG W; BARDAKCI T; D' ANGELO NA; KOT WK; PEGG IL

    2011-12-29

    This report documents melter and off-gas performance results obtained on the DM1200 HLW Pilot Melter during processing of simulated HLW C-106/AY-102 feed. The principal objectives of the DM1200 melter testing were to determine the achievable glass production rates for simulated HLW C-106/AY-102 feed; determine the effect of bubbling rate on production rate; characterize melter off-gas emissions; characterize the performance of the prototypical off-gas system components as well as their integrated performance; characterize the feed, glass product, and off-gas effluents; and to perform pre- and post test inspections of system components.

  9. Integrated DM 1200 Melter Testing Of HLW C-106/AY-102 Composition Using Bubblers VSL-03R3800-1, Rev. 0, 9/15/03

    International Nuclear Information System (INIS)

    This report documents melter and off-gas performance results obtained on the DM1200 HLW Pilot Melter during processing of simulated HLW C-106/AY-102 feed. The principal objectives of the DM1200 melter testing were to determine the achievable glass production rates for simulated HLW C-106/AY-102 feed; determine the effect of bubbling rate on production rate; characterize melter off-gas emissions; characterize the performance of the prototypical off-gas system components as well as their integrated performance; characterize the feed, glass product, and off-gas effluents; and to perform pre- and post test inspections of system components.

  10. Heat exchangers and thermal energy storage concepts for the off-gas heat of steelmaking devices

    International Nuclear Information System (INIS)

    The fluctuating thermal emissions of electric arc furnaces require energy storage systems to provide downstream consumers with a continuous amount of thermal energy or electricity. Heat recovery systems based on thermal energy storage are presented. A comparison of different thermal energy storage systems has been performed. For the purpose, suitable heat exchangers for the off-gas heat have been developed. Dynamic process simulations of the heat recovery plants were necessary to check the feasibility of the systems and consider the non-steady-state off-gas emissions of the steelmaking devices. The implementation of a pilot plant into an existing off-gas duct of an electric arc furnace was required to check the real behavior of the heat exchanger and determine suitable materials in view of corrosion issues. The pilot plant is presented in this paper.

  11. Heat exchangers and thermal energy storage concepts for the off-gas heat of steelmaking devices

    Science.gov (United States)

    Steinparzer, T.; Haider, M.; Fleischanderl, A.; Hampel, A.; Enickl, G.; Zauner, F.

    2012-11-01

    The fluctuating thermal emissions of electric arc furnaces require energy storage systems to provide downstream consumers with a continuous amount of thermal energy or electricity. Heat recovery systems based on thermal energy storage are presented. A comparison of different thermal energy storage systems has been performed. For the purpose, suitable heat exchangers for the off-gas heat have been developed. Dynamic process simulations of the heat recovery plants were necessary to check the feasibility of the systems and consider the non-steady-state off-gas emissions of the steelmaking devices. The implementation of a pilot plant into an existing off-gas duct of an electric arc furnace was required to check the real behavior of the heat exchanger and determine suitable materials in view of corrosion issues. The pilot plant is presented in this paper.

  12. Dynamic simulation aids DWPF off-gas and ventilation design

    International Nuclear Information System (INIS)

    Dynamic simulation is an effective engineering tool for the evaluation of dynamic systems during the design phase of a project. The primary objective is to gain understanding about all aspects of the dynamic behavior during upset conditions and to use such knowledge to arrive at a design that satisfies all control and performance criteria. On the Defense Waste Processing Facility (DWPF), it was used for the design of the melter off-gas processing system and the vitrification building control system for the air supply and exhaust to ensure a definite air flow pattern during upset conditions. For these applications, the simulation models were prepared using Bechtel's proprietary language, DAP and executed on Bechtel's Dynamic Simulation Facility. 9 figs

  13. Treatment of off-gas from radioactive waste incinerators

    International Nuclear Information System (INIS)

    An effective process reducing volume of radioactive wastes is incineration of combustible wastes. Appropriate design of the off-gas treatment system is necessary to ensure that any releases of airborne radionuclides into the environment are kept below acceptable limits. In many cases, the off-gas system must be designed to accommodate chemical constituents in the gas stream. The purpose of this publication is to provide the most up-to-date information regarding off-gas treatment as well as an account of some of the developments so as to aid users in the selection of an integrated system for a particular application. The choice of incinerator/off-gas system combination depends on the wastes to be treated, as well as other factors, such as regulatory requirements. Current problems and development needs are discussed. Following comprehensive discussions of the various factors affecting a choice, various incinerator and off-gas treatment systems are recommended for the various types of wastes that may be treated: low PVC content solid, high PVC content solid, organic liquid and resins. The economics or costs of the off-gas system and an evaluation of the overall cost effectiveness of incineration or direct burial is not discussed in detail. This publication is specifically directed toward technical aspects and addresses: incineration types and origin, sources and characteristics of off-gas streams; descriptions of available technologies for off-gas treatment; basic componlogies for off-gas treatment; basic component design requirements and component description; operational experience of plants in active operation and their current practices; legal aspects and safety requirements; remaining problems to be solved and development trends in plant design and component structure. This report seeks to broaden and enhance the understanding of the developed technology and to indicate areas where improvements can be made by further research and development. 110 refs

  14. Investigation of sulfur-impregnated activated carbon for removal of mercury vapor from a thermal desorption off-gas

    International Nuclear Information System (INIS)

    Sulfur-impregnated activated carbon is being studied for use as a final mercury emission control device for a thermal desorption unit. Bench-scale tests are being conducted to demonstrate the performance of the sulfur-impregnated activated carbon for mercury vapor recovery and to determine design parameters needed to implement this control technology in a pilot-scale thermal desorption process. These experiments are designed to analyze break-through time, adsorption capacity, and rate of adsorption. The performance of the sulfur-impregnated activated carbon will be compared with the base-activated carbon. A bench-scale experiment has been constructed to simulate the conditions of a mercury off-gas stream from a thermal desorption unit to collect the required data. Because a high concentration of water vapor is expected in the thermal desorption offgas, the experiments will be conducted both with and without water vapor present in the experimental off-gas to verify the impact of water vapor on performance of the carbon and to determine if preventive measures should be taken in the pilot-scale system

  15. Boiling water reactor off-gas systems evaluation

    International Nuclear Information System (INIS)

    An evaluation of the off-gas systems for all 25 operating Boiling Water Reactors (BWR) was made to determine the adequacy of their design and operating procedures to reduce the probability of off-gas detonations. The results of the evaluations are that, of the 25 operable units, 13 meet all the acceptance criteria. The other 12 units do not have the features needed to meet the criteria, but have been judged to have, or are committed to provide, features which give reasonable assurance that the potential for external off-gas detonations is minimized. The 12 units which did not originally meet the criteria are aware of the potential hazards associated with off-gas detonations and have agreed to take action to minimize the probability of future detonations

  16. Methods of Off-Gas Flammability Control for DWPF Melter Off-Gas System at Savannah River Site

    International Nuclear Information System (INIS)

    Several key operating variables affecting off-gas flammability in a slurry-fed radioactive waste glass melter are discussed, and the methods used to prevent potential off-gas flammability are presented. Two models have played a central role in developing such methods. The first model attempts to describe the chemical events occurring during the calcining and melting steps using a multistage thermodynamic equilibrium approach, and it calculates the compositions of glass and calcine gases. Volatile feed components and calcine gases are fed to the second model which then predicts the process dynamics of the entire melter off-gas system including off-gas flammability under both steady state and various transient operating conditions. Results of recent simulation runs are also compared with available data

  17. Treatment of nitrous off-gas from dissolution of sludges

    International Nuclear Information System (INIS)

    Several configurations have been reviewed for the NOx removal of dissolver off-gas. A predesign has been performed and operating conditions have been optimized. Simple absorption columns seems to be sufficient. NHC is in charge of the treatment of sludges containing mainly uranium dioxide and metallic uranium. The process is based on the following processing steps a dissolution step to oxidize the pyrophoric materials and to dissolve radionuclides (uranium, plutonium, americium and fission products), a solid/liquid separation to get rid of the insoluble solids (to be disposed at ERDF), an adjustment of the acid liquor with neutronic poisons, and neutralization of the acid liquor with caustic soda. The dissolution step generates a flow of nitrous fumes which was evaluated in a previous study. This NOx flow has to be treated. The purpose of this report is to study the treatment process of the nitrous vapors and to 0482 perform a preliminary design. Several treatment configurations are studied and the most effective process option with respect to the authorized level of discharge into atmosphere is discussed. As a conclusion, recommendations concerning the unit preliminary design are given

  18. Remotely replaceable and testable off-gas filter system for the NWCF

    International Nuclear Information System (INIS)

    The process off-gas filter system designed for use in the New Waste Calcining Facility (NWCF) requires remote filter removal, replacement and in-place DOP testing. A series of full-scale mockup tests, modifications and retesting at the Remote Maintenance Development Facility (RMDF) resulted in a system in which a commercial High Efficiency Particulate Air (HEPA) filter can be installed, tested for leaks, operated and removed from a sealed filter housing using remote handling methods. This paper describes the development, testing and results of this effort

  19. Advanced Off-Gas Control System Design For Radioactive And Mixed Waste Treatment

    Energy Technology Data Exchange (ETDEWEB)

    Nick Soelberg

    2005-09-01

    Treatment of radioactive and mixed wastes is often required to destroy or immobilize hazardous constituents, reduce waste volume, and convert the waste to a form suitable for final disposal. These kinds of treatments usually evolve off-gas. Air emission regulations have become increasingly stringent in recent years. Mixed waste thermal treatment in the United States is now generally regulated under the Hazardous Waste Combustor (HWC) Maximum Achievable Control Technology (MACT) standards. These standards impose unprecedented requirements for operation, monitoring and control, and emissions control. Off-gas control technologies and system designs that were satisfactorily proven in mixed waste operation prior to the implementation of new regulatory standards are in some cases no longer suitable in new mixed waste treatment system designs. Some mixed waste treatment facilities have been shut down rather than have excessively restrictive feed rate limits or facility upgrades to comply with the new standards. New mixed waste treatment facilities in the U. S. are being designed to operate in compliance with the HWC MACT standards. Activities have been underway for the past 10 years at the INL and elsewhere to identify, develop, demonstrate, and design technologies for enabling HWC MACT compliance for mixed waste treatment facilities. Some specific off-gas control technologies and system designs have been identified and tested to show that even the stringent HWC MACT standards can be met, while minimizing treatment facility size and cost.

  20. Test planning and performance

    International Nuclear Information System (INIS)

    Testing plan should include Safety guide Q4 - Inspection and testing - A testing plan should be prepared including following information: General information (facility name, item or system reference, procurement document reference, document reference number and status, associated procedures and drawings); A sequential listing of all testing activities; Procedure, work instruction, specification or standard to be followed in respect of each operation and test; Acceptance criteria; Identification of who is performing tests; Identification of hold points; Type of records to be prepared for each test; Persons and organizations having authority for final acceptance. Proposed activities sequence is: visual, electrical and mechanical checks; environmental tests (thermal aging, vibrations aging, radioactive aging); performance evaluation in extreme conditions; dynamic tests with functional checks; final electrical and mechanical checks The planning of the tests should always be performed taking into account an interpretative model: a very tight cooperation is advisable between experimental people and numerical people dealing with the analysis of more or less complex models for the seismic assessment of structures and components. Preparatory phase should include the choice of the following items should be agreed upon with the final user of the tests: Excitation points, Excitation types, Excitation amplitude with respect to frequency, Measuring points. Data acquisition, recording and storage, should take into account the characteristics of the successive data processing: to much data can be cumbersome to be processed, but to few data can make unusable the experimental results. The parameters for time history acquisition should be chosen taking into account data processing: for Shock Response Spectrum calculation some special requirements should be met: frequency bounded signal, high frequency sampling, shock noise. For stationary random-like excitation, the sample length should be chosen taking into account errors tolerances. Test procedures should be prepared and issued. Management of unexpected behaviours includes: Non linear behaviour; shocks among mechanical parts in presence of clearances; on line control, alarm limits, abort limits, and interlocks

  1. Dissolver Off-gas Hot Operations Authorization (AFCI CETE Milestone Report)

    Energy Technology Data Exchange (ETDEWEB)

    Jubin, Robert Thomas [ORNL

    2009-06-01

    The head-end processing of the Coupled-End-to-End (CETE) Demonstration includes fuel receipt, fuel disassembly, exposure of fuel (e.g., by segmenting the fuel pins), voloxidation of the fuel to separate tritium, and fuel dissolution. All of these processing steps with the exception of the dissolution step will be accomplished in the Irradiated Fuels Examination Laboratory (IFEL) (Building 3525). The final headend step will be performed in the Radiochemical Engineering Development Center (Building 7920). The primary purpose of the fuel dissolution step is to prepare the solid fuel for subsequent liquid separations steps. This is accomplished by dissolving the fuel solids using nitric acid. During the dissolution process gases are evolved. Oxides of nitrogen are the primary off-gas components generated by the reactions of nitric acid and the fuel oxides however, during the dissolution and sparging of the resulting solution, iodine, C-14 as carbon dioxide, xenon, and krypton gasses are also released to the off-gas stream. The Dissolver Off-gas treatment rack provides a means of trapping these volatile fission products and other gases via various trapping media. Specifically the rack will recover iodine on a solid sorbent bed, scrub NOx in a water/acid column, scrub CO{sub 2} in a caustic scrubber column, remove moisture with solid sorbent drier beds and recover Xe and Kr using solid absorbent beds. The primary purpose of this experimental rack and the off-gas rack associated with the voloxidation equipment located at IFEL is to close the material balances around the volatile gases and to provide an understanding of the impacts of specific processing conditions on the fractions of the volatile components released from the various head-end processing steps.

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

    International Nuclear Information System (INIS)

    General Atomic Company (GA) is conducting pilot-plant-scale tests that simulate the treatment of radioactive and other noxious volatile and gaseous constituents of off-gas streams from nuclear reprocessing plants. This paper reports the results of engineering-scale tests performed on the CO2/krypton separation and radon holdup/decay subsystems of the GA integrated off-gas treatment system. Separation of CO2 from krypton-containing gas streams is necessary to facilitate subsequent waste processing and krypton storage. Molecular sieve 5A achieved this separation in dissolver off-gas streams containing relatively low krypton and CO2 concentrations and in krypton-rich product streams from processes such as the krypton absorption in liquid carbon dioxide (KALC) process. The CO2/krypton separation unit is a 30.5-cm-diameter x 1.8-m-long column containing molecular sieve 5A. The loading capacity for CO2 was determined for gas mixtures containing 250 ppM to 2.2% CO2 and 170 to 750 ppM krypton in either N2 or air. Gas streams rich in CO2 were diluted with N2 to reduce the temperature rise from the heat of adsorption, which would otherwise affect loading capacity. The effluent CO2 concentration prior to breakthrough was less than 10 ppM, and the adsorption capacity for krypton was negligible. Krypton was monitored on-line with a time-of-flight mass spectrometer and its concentration determined quantitatively by a method of continuous analysis, i.e., selected-ion monitoring. Radon-220 was treated by holdup and decay on a column of synthetic H-mordenite. The Rn-220 concentration was monitored on-line with flow-through diffused-junction alpha detectors. Single-channel analyzers were utilized to isolate the 6.287-MeV alpha energy band characteristic of Rn-220 decay from energy bands due to daughter products

  3. FY-2001 Accomplishments in Off-gas Treatment Technology Development

    International Nuclear Information System (INIS)

    This report summarizes the efforts funded by the Tank Focus Area to investigate nitrogen oxide (NOx) destruction (a.k.a. deNOx) technologies and off-gas scrubber system designs. The primary deNOx technologies that were considered are staged combustion (a.k.a. NOx reburning), selective catalytic reduction, selective non-catalytic reduction, and steam reformation. After engineering studies and a team evaluation were completed, selective catalytic reduction and staged combustion were considered the most likely candidate technologies to be deployed in a sodium-bearing waste vitrification facility. The outcome of the team evaluation factored heavily in the establishing a baseline configuration for off-gas and secondary waste treatment systems

  4. Treatment of the off-gas stream from the HTR reprocessing head-end

    International Nuclear Information System (INIS)

    The AKUT II-facility (nominal throughput 10 m3/h, STP) for the clean-up of the burner off-gas has been operated for 20 cold runs in parallel to the JUPITER reprocessing head-end. Two of these runs were continuous operation tests with a duration of 50 and 80 hours, respectively. The facility met or exceeded all design specifications. In a further test series the distillation column alone was run with pure CO2 and two- and three-component gas mixtures to determine the flooding curves and the stage height (HETP)

  5. Burner and dissolver off-gas treatment in HTR fuel reprocessing

    International Nuclear Information System (INIS)

    In the reprocessing of HTR fuel, essentially all of the gaseous fission products are released during the heat-end tratment, which includes burning of the graphite matrix and dissolving of the heavy metallic residues in THOREX reagent. Three facilities for off-gas cleaning are described, the status of the facility development and test results are reported. Hot tests with a continuous dissolver for HTR-type fuel (throughput 2 kg HM/d) with a closed helium purge loop have been carried out. Preliminary results of these experiments are reported

  6. Dynamic Absorption Model for Off-Gas Separation

    International Nuclear Information System (INIS)

    Modeling and simulations will aid in the future design of U.S. advanced reprocessing plants for the recovery and recycle of actinides in used nuclear fuel. The specific fuel cycle separation process discussed in this report is the off-gas treatment system. The off-gas separation consists of a series of scrubbers and adsorption beds to capture constituents of interest. Dynamic models are being developed to simulate each unit operation involved so each unit operation can be used as a stand-alone model and in series with multiple others. Currently, a rate based, dynamic absorption model is being developed in gPROMS software. Inputs include liquid and gas stream constituents, column properties, liquid and gas phase reactions, number of stages, and inlet conditions. It simulates multiple component absorption with countercurrent flow and accounts for absorption by mass transfer and chemical reaction. The assumption of each stage being a discrete well-mixed entity was made. Therefore, the model is solved stagewise. The simulation outputs component concentrations in both phases as a function of time from which the rate of absorption is determined. Temperature of both phases is output as a function of time also. The model will be used able to be used as a standalone model in addition to in series with other off-gas separation unit operations. The current model is being generated based on NOx absorption; however, a future goal is to develop a CO2 specific model. The model will elop a CO2 specific model. The model will have the capability to be modified for additional absorption systems. The off-gas models, both adsorption and absorption, will be made available via the server or web for evaluation by customers.

  7. Dynamic Absorption Model for Off-Gas Separation

    Energy Technology Data Exchange (ETDEWEB)

    Veronica J. Rutledge

    2011-07-01

    Modeling and simulations will aid in the future design of U.S. advanced reprocessing plants for the recovery and recycle of actinides in used nuclear fuel. The specific fuel cycle separation process discussed in this report is the off-gas treatment system. The off-gas separation consists of a series of scrubbers and adsorption beds to capture constituents of interest. Dynamic models are being developed to simulate each unit operation involved so each unit operation can be used as a stand-alone model and in series with multiple others. Currently, a rate based, dynamic absorption model is being developed in gPROMS software. Inputs include liquid and gas stream constituents, column properties, liquid and gas phase reactions, number of stages, and inlet conditions. It simulates multiple component absorption with countercurrent flow and accounts for absorption by mass transfer and chemical reaction. The assumption of each stage being a discrete well-mixed entity was made. Therefore, the model is solved stagewise. The simulation outputs component concentrations in both phases as a function of time from which the rate of absorption is determined. Temperature of both phases is output as a function of time also. The model will be used able to be used as a standalone model in addition to in series with other off-gas separation unit operations. The current model is being generated based on NOx absorption; however, a future goal is to develop a CO2 specific model. The model will have the capability to be modified for additional absorption systems. The off-gas models, both adsorption and absorption, will be made available via the server or web for evaluation by customers.

  8. R and D for an off-gas treatment system for a slagging pyrolysis radioactive waste incinerator. Final report for Phase III

    International Nuclear Information System (INIS)

    Results of engineering-scale tests to obtain sintered metal filter particulate removal performance data with fly ash to simulate the expected incinerator particulate are reported. Efficiencies of greater than 99.9999% were obtained at the conditions of the tests. An evaluation of expected spray dryer performance indicated that a commercial unit should provide the desired removal for HCL and SO2. An off-gas treatment system safety analysis was performed, and no credible postulated accident could be identified that would result in a significant radioactivity exposure to the public. An updated cost estimate for the OGTS is also provided. Several areas were identified in which additional technical data are considered desirable to ensure efficient operation of the proposed OGTS, but nothing was identified that would indicate that the OGTS would not perform satisfactorily as designed

  9. Method for treating a nuclear process off-gas stream

    Science.gov (United States)

    Pence, Dallas T. (San Diego, CA); Chou, Chun-Chao (San Diego, CA)

    1984-01-01

    Disclosed is a method for selectively removing and recovering the noble gas and other gaseous components typically emitted during nuclear process operations. The method is adaptable and useful for treating dissolver off-gas effluents released during reprocessing of spent nuclear fuels whereby to permit radioactive contaminant recovery prior to releasing the remaining off-gases to the atmosphere. Briefly, the method sequentially comprises treating the off-gas stream to preliminarily remove NO.sub.x, hydrogen and carbon-containing organic compounds, and semivolatile fission product metal oxide components therefrom; adsorbing iodine components on silver-exchanged mordenite; removing water vapor carried by said stream by means of a molecular sieve; selectively removing the carbon dioxide components of said off-gas stream by means of a molecular sieve; selectively removing xenon in gas phase by passing said stream through a molecular sieve comprising silver-exchanged mordenite; selectively separating krypton from oxygen by means of a molecular sieve comprising silver-exchanged mordenite; selectively separating krypton from the bulk nitrogen stream using a molecular sieve comprising silver-exchanged mordenite cooled to about -140.degree. to -160.degree. C.; concentrating the desorbed krypton upon a molecular sieve comprising silver-exchange mordenite cooled to about -140.degree. to -160.degree. C.; and further cryogenically concentrating, and the recovering for storage, the desorbed krypton.

  10. Off-gas adsorption model and simulation - OSPREY

    International Nuclear Information System (INIS)

    A capability of accurately simulating the dynamic behavior of advanced fuel cycle separation processes is expected to provide substantial cost savings and many technical benefits. To support this capability, a modeling effort focused on the off-gas treatment system of a used nuclear fuel recycling facility is in progress. The off-gas separation consists of a series of scrubbers and adsorption beds to capture constituents of interest. Dynamic models are being developed to simulate each unit operation involved so each unit operation can be used as a stand-alone model and in series with multiple others. Currently, an adsorption model has been developed within Multi-physics Object Oriented Simulation Environment (MOOSE) developed at the Idaho National Laboratory (INL). Off-gas Separation and Recovery (OSPREY) models the adsorption of offgas constituents for dispersed plug flow in a packed bed under non-isothermal and non-isobaric conditions. Inputs to the model include gas composition, sorbent and column properties, equilibrium and kinetic data, and inlet conditions. The simulation outputs component concentrations along the column length as a function of time from which breakthrough data can be obtained. The breakthrough data can be used to determine bed capacity, which in turn can be used to size columns. In addition to concentration data, the model predicts temperature along the column length as a function of time and pressure drop along the column length. A description of the OSPREY model, results from krypton adsorption modeling and plans for modeling the behavior of iodine, xenon, and tritium will be discussed. (author)

  11. Off-gas Adsorption Model and Simulation - OSPREY

    Energy Technology Data Exchange (ETDEWEB)

    Veronica J Rutledge

    2013-10-01

    The absence of 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 countries. Thus, it is essential to model complex series of unit operations to simulate, understand, and predict inherent transient behavior. A capability of accurately simulating the dynamic behavior of advanced fuel cycle separation processes is expected to provide substantial cost savings and many technical benefits. To support this capability, a modeling effort focused on the off-gas treatment system of a used nuclear fuel recycling facility is in progress. The off-gas separation consists of a series of scrubbers and adsorption beds to capture constituents of interest. Dynamic models are being developed to simulate each unit operation involved so each unit operation can be used as a stand-alone model and in series with multiple others. Currently, an adsorption model has been developed within Multi-physics Object Oriented Simulation Environment (MOOSE) developed at the Idaho National Laboratory (INL). Off-gas Separation and REcoverY (OSPREY) models the adsorption of offgas constituents for dispersed plug flow in a packed bed under non-isothermal and non-isobaric conditions. Inputs to the model include gas composition, sorbent and column properties, equilibrium and kinetic data, and inlet conditions. The simulation outputs component concentrations along the column length as a function of time from which breakthrough data can be obtained. The breakthrough data can be used to determine bed capacity, which in turn can be used to size columns. In addition to concentration data, the model predicts temperature along the column length as a function of time and pressure drop along the column length. A description of the OSPREY model, results from krypton adsorption modeling and plans for modeling the behavior of iodine, xenon, and tritium will be discussed.

  12. FINAL REPORT DM1200 TESTS WITH AZ 101 HLW SIMULANTS VSL-03R3800-4 REV 0 2/17/04

    Energy Technology Data Exchange (ETDEWEB)

    KRUGER AA; MATLACK KS; BARDAKCI T; D' ANGELO NA; GONG W; KOT WK; PEGG IL

    2011-12-29

    This report documents melter and off-gas performance results obtained on the DM 1200 HLW Pilot Melter during processing of simulated HLW AZ-101 feed. The principal objectives of the DM1200 melter testing were to determine the achievable glass production rates for simulated HLW AZ-101 feed; determine the effect of bubbling rate and feed solids content on production rate; characterize melter off-gas emissions; characterize the performance of the prototypical off-gas system components as well as their integrated performance; characterize the feed, glass product, and off-gas effluents; and to perform pre- and post-test inspections of system components. The test objectives (including test success criteria), along with how they were met, are outlined in a table.

  13. Final Report DM1200 Tests With AZ 101 HLW Simulants VSL-03R3800-4, Rev. 0, 2/17/04

    International Nuclear Information System (INIS)

    This report documents melter and off-gas performance results obtained on the DM 1200 HLW Pilot Melter during processing of simulated HLW AZ-101 feed. The principal objectives of the DM1200 melter testing were to determine the achievable glass production rates for simulated HLW AZ-101 feed; determine the effect of bubbling rate and feed solids content on production rate; characterize melter off-gas emissions; characterize the performance of the prototypical off-gas system components as well as their integrated performance; characterize the feed, glass product, and off-gas effluents; and to perform pre- and post-test inspections of system components. The test objectives (including test success criteria), along with how they were met, are outlined in a table.

  14. Experimental determination of the solubilities of dissolver off-gas constituents in a Kr-85 recovery solvent (CCl2F2). Final report

    International Nuclear Information System (INIS)

    The experimental determination of the solubility of the major off-gas constituent-Nitrogen was performed with a new solubility measurement apparatus. The new apparatus was designed, built and tested; an algorithm for thermodynamic consistency testing of P-T-x-y data for solubility systems was developed, and thermodynamically consistent Nitrogen-R-12 solubility data were taken. The Henry's Law constant for the Nitrogen-R-12 system can be represented by the equation ln H/sub N2-R-12/ (atm) = 0.44 + 1.0708 lnT (0K). The solubility data extend the range of known equilibrium data into a region where process equipment operate and are consistent with both other data at lower temperatures by other researchers and with regular solution theory

  15. Removal of volatile organic compounds (VOC) from off-gas by electron beam

    International Nuclear Information System (INIS)

    The electron beam (EB) process is well suited to remove small concentrations of pollutants from large volume flows. Previously, the process was tested successfully for the simultaneous removal of NOx and SO2 from fossile fuelled power plants. The removal of VOC from industrial off-gas and the removal of NOx, SO2 and hydrocarbons from automobile tunnels are important new applications. The irradiation of these systems with energetic (300-800 keV) electrons produces excited state and ionized species which generate high radical concentrations by reaction with the matrix gas. The radicals (especially the OH radical) then react with the pollutants and remove them by oxidation. In this work, the VOC removal from simulated industrial off-gas was measured as function of inlet concentration and irradiation dose. The removal efficiency was found to be about 40 g C/kWh at low removal yields and around 15-20 g C/kWh at removal yields close to 70%. Besides CO and CO2, aerosol formation is observed due to irradiation. According to the carbon balance, 35% of the input carbon are found in the aerosol. Some inorganic by-products were found (O3, NO2, N2O, HNO2, HNO3) and measured quantitatively. From these by-products only N2O cannot be degraded heterogeneously across the filter surface. (orig.)

  16. 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.

  17. Design report: An off gas trapping system for a voloxidizer in INL of US

    International Nuclear Information System (INIS)

    This reports on the 'Development of Voloxidation Process for Treatment of LWR Spent Fuel', and it is the second year since it has started from June 2004 as a tripartite cooperation project among KAERI(Korea Atomic Energy Research Institute), INL(Idaho National Laboratory) and ORNL(Oak Ridge National Laboratory). This report is described mainly for the Task B2 accomplished during the second project year. The Task B2 in proposal contains two sub-tasks. The first one is design of an off-gas treatment system for a voloxidizer to be used in HFEF of INL. For this, KAERI team developed the design of INL OTS (Off-gas Treatment System) for hot experiment in the HFEF. INL team modified and completed the design of the INL OTS. The second task is manufacturing and test operation of the INL OTS for a voloxidizer in the INL. Manufacturing of the OTS is accomplished by INL team with co-work of KAERI. KAERI provided four sets of trapping filters needed for conducting hot experiment in the INL HFEF

  18. Peer review panel summary report for technical determination of mixed waste incineration off-gas systems for Rocky Flats

    International Nuclear Information System (INIS)

    A Peer Review Panel was convened on September 15-17, 1992 in Boulder, Co. The members of this panel included representatives from DOE, EPA, and DOE contractors along with invited experts in the fields of air pollution control and waste incineration. The primary purpose of this review panel was to make a technical determination of a hold, test and release off gas capture system should be implemented in the proposed RF Pland mixed waste incineration system; or if a state of the art continuous air pollution control and monitoring system should be utilized as the sole off-gas control system. All of the evaluations by the panel were based upon the use of the fluidized bed unit proposed by Rocky Flats and cannot be generalized to other systems

  19. CALCULATION OF DEMONSTRATION BULK VITRIFICATION SYSTEM MELTER INLEAKAGE AND OFF-GAS GENERATION RATE

    International Nuclear Information System (INIS)

    The River Protection Project (RPP) mission is to safely store, retrieve, treat, immobilize, and dispose of the Hanford Site tank waste. The Demonstration Bulk Vitrification System (DBVS) is a research and development project whose objective is to demonstrate the suitability of Bulk Vitrification treatment technology waste form for disposing of low-activity waste from the Tank Farms. The objective of this calculation is to determine the DBVS melter inleakage and off-gas generation rate based on full scale testing data from 38D. This calculation estimates the DBVS melter in leakage and gas generation rate based on test data. Inleakage is estimated before the melt was initiated, at one point during the melt, and at the end of the melt. Maximum gas generation rate is also estimated

  20. Infiniband Performance Testing

    Energy Technology Data Exchange (ETDEWEB)

    Minich, M

    2005-10-13

    A look at the performance of the infiniband interconnect using the Voltaire host stack. This will attempt to compare not only infiniband to other high-performance interconnects, but will also take a look at comparing some of the different hardware choices available at the time of writing (e.g. Opteron, EM64T, pci-express and pci-x).

  1. Performance Assessment in Language Testing

    Science.gov (United States)

    Salmani Nodoushan, Mohammad Ali

    2008-01-01

    Over the past few decades, educators in general, and language teachers in specific, were more inclined towards using testing techniques that resembled real-life language performance. Unlike traditional paper-and-pencil language tests that required test-takers to attempt tests that were based on artificial and contrived language content,…

  2. Computer model for the KALC process studies in the ORGDP Off-Gas Decontamination Pilot Plant

    International Nuclear Information System (INIS)

    A computer model of the KALC process is presented for the equipment configuration in use during HTGR off-gas studies at the ORGDP Off-Gas Decontamination Pilot Plant. The model is tailored to require input routinely available during such experimental studies. A program is included to provide McCabe-Thiele plots as an additional convenience

  3. Treatment Of Mercury Target Off-Gas At SNS

    International Nuclear Information System (INIS)

    The Spallation Neutron Source (SNS) is the first operational spallation source to use liquid Mercury as a target material. This paper describes the treatment system to remove volatile spallation products from a Helium purge stream that emanates from the Mercury target and adjustments made to achieve design goals in response to phenomena experienced during initial operations. The Helium stream is treated to remove volatile spallation products prior to environmental release because of its activity level as these accumulate in the gas space in the Mercury Loop. Unanticipated local dose rates were noted in treatment system components during low power startup. Gamma scanning of these components identified the presence of nineteen noble gas isotopes and their daughters, indicating that the doses resulted from noble gas sorption. Treatment of this equipment with stable Xenon greatly reduced but did not eliminate these. Significant moisture was also encountered in the system, resulting in the plugging of the system cold trap. Changes to some of the system equipment were required together with moisture elimination from components to which moisture was sorbed. Necessary re-configuration of Mercury pump components presented additional requirements and system control changes to accommodate system operation at reduced pressure. The Off-Gas Treatment System has been successfully operated since April, 2006. System availability and removal effectiveness have been high. Operational isfectiveness have been high. Operational issues occurring during the first year of operation have been resolved.

  4. Processes for decontaminating nuclear process off-gas streams

    International Nuclear Information System (INIS)

    In a process for decontaminating a nuclear process off-gas stream, oxygen and oxides of nitrogen are removed by catalytic reaction with hydrogen. The feed gas stream is then passed serially through a drier, a carbon dioxide adsorber and a xenon adsorber to sequentially remove water, CO2 and Xenon therefrom. The feed gas exiting the xenon adsorber is passed to a krypton recovery process wherein krypton is concentrated to a first level in a primary distillation column, partially evaporated to increase concentration thereof and is brought to a concentration of approximately 90 mol% or greater in a second distillation column thereby enabling efficient storage of a radioactive krypton product. The xenon gas removed from the main feed stream in the xenon adsorber is passed to a freezeout heat exchange device to concentrate xenon to approximately 99% or greater, balance krypton. The minor fraction of krypton may then be removed from such xenon-rich product in a distillation tower with the xenon product being stored in gas cylinders or the like

  5. MELTER OFF-GAS FLAMMABILITY ASSESSMENT FOR DWPF ALTERNATE REDUCTANT FLOWSHEET OPTIONS

    Energy Technology Data Exchange (ETDEWEB)

    Choi, A.

    2011-07-08

    Glycolic acid and sugar are being considered as potential candidates to substitute for much of the formic acid currently being added to the Defense Waste Processing Facility (DWPF) melter feed as a reductant. A series of small-scale melter tests were conducted at the Vitreous State Laboratory (VSL) in January 2011 to collect necessary data for the assessment of the impact of these alternate reductants on the melter off-gas flammability. The DM10 melter with a 0.021 m{sup 2} melt surface area was run with three different feeds which were prepared at SRNL based on; (1) the baseline formic/nitric acid flowsheet, (2) glycolic/formic/nitric acid flowsheet, and (3) sugar/formic/nitric acid flowsheet - these feeds will be called the baseline, glycolic, and sugar flowsheet feeds, respectively, hereafter. The actual addition of sugar to the sugar flowsheet feed was made at VSL before it was fed to the melter. For each feed, the DM10 was run under both bubbled (with argon) and non-bubbled conditions at varying melter vapor space temperatures. The goal was to lower its vapor space temperature from nominal 500 C to less than 300 C at 50 C increments and maintain steady state at each temperature at least for one hour, preferentially for two hours, while collecting off-gas data including CO, CO{sub 2}, and H{sub 2} concentrations. Just a few hours into the first test with the baseline feed, it was discovered that the DM10 vapor space temperature would not readily fall below 350 C simply by ramping up the feed rate as the test plan called for. To overcome this, ambient air was introduced directly into the vapor space through a dilution air damper in addition to the natural air inleakage occurring at the operating melter pressure of -1 inch H{sub 2}O. A detailed description of the DM10 run along with all the data taken is given in the report issued by VSL. The SRNL personnel have analyzed the DM10 data and identified 25 steady state periods lasting from 32 to 92 minutes for all six melter runs (bubbled and non-bubbled runs for each of the three feeds). The steady state selection was made by limiting the standard deviation of the average vapor space temperature readings from two bare thermocouples (TT-03 and TT-05) to less than 5 C in most cases at a constant feed rate. The steady state data thus selected were mass and heat balanced and the off-gas data were re-baselined to assess the flammability potential of each feed under the DWPF melter operating conditions. Efforts were made to extract as much information out of the data as possible necessary to extend the applicability of the existing baseline cold cap and off-gas combustion models to the glycolic and sugar flowsheet feeds. This report details the outcome of these activities.

  6. Inspection system performance test procedure

    International Nuclear Information System (INIS)

    This procedure establishes requirements to administer a performance demonstration test. The test is to demonstrate that the double-shell tank inspection system (DSTIS) supplied by the contractor performs in accordance with the WHC-S-4108, Double-Shell Tank Ultrasonic Inspection Performance Specification, Rev. 2-A, January, 1995. The inspection system is intended to provide ultrasonic (UT) and visual data to determine integrity of the Westinghouse Hanford Company (WHC) site underground waste tanks. The robotic inspection system consists of the following major sub-systems (modules) and components: Mobile control center; Deployment module; Cable management assembly; Robot mechanism; Ultrasonic testing system; Visual testing system; Pneumatic system; Electrical system; and Control system

  7. Airborne waste management technology applicable for use in reprocessing plants for control of iodine and other off-gas constituents

    International Nuclear Information System (INIS)

    Extensive work in the area of iodine removal from reprocessing plant off-gas streams using various types of solid sorbent materials has been conducted worldwide over the past two decades. This work has focused on the use of carbon filters, primarily for power plant applications. More recently, the use of silver-containing sorbents has been the subject of considerable research. The most recent work in the United States has addressed the use of silver-exchanged faujasites and mordenites. The chemical reactions of iodine with silver on the sorbent are not well defined, but it is generally believed that chemisorbed iodides and iodates are formed. The process for iodine recovery generally involves passage of the iodine-laden gas stream through a packed bed of the adsorbent material preheated to a temperature of about 150/degree/C. Most iodine removal system designs utilizing silver-containing solid sorbents assume only a 30 to 50% silver utilization. Based on laboratory tests, potentially 60 to 70% of the silver contained in the sorbents can be reacted with iodine. To overcome the high cost of silver associated with these materials, various approaches have been explored. Among these are the regeneration of the silver-containing sorbent by stripping the iodine and trapping the iodine on a sorbent that has undergone only partial silver exchange and is capable of attaining a much higher silver utilization. This summary report describes the US work in regeneration of iodine-loaded solid sorbent material. In addition, the report discusses the broader subject of plant off-gas treatment including system design. The off-gas technologies to recovery No/sub x/ and to recover and dispose of Kr, 14C, and I are described as to their impacts on the design of an integrated off-gas system. The effect of ventilation philosophy for the reprocessing plant is discussed as an integral part of the overall treatment philosophy of the plant off-gas. 103 refs., 5 figs., 8 tabs

  8. Remediation on off-gas system deposits in a radioactive waste glass melter

    International Nuclear Information System (INIS)

    Since the early 1980's, research glass melters have been used at the Savannah River Laboratory (SRL) to develop the reference vitrification process for immobilization of high level radioactive waste. One of the operating concerns for these melters has been the pluggage of the off-gas system with solid deposits. Samples of these deposits were analyzed to be mixture of alkali-rich chlorides, sulfates, borates, and fluorides with entrained Fe2O3 spinel, and frit particles. The spatial distribution of these deposits throughout the off-gas system indicates that they form by vapor-phase transport and subsequently condensation. Condensation of the alkali-rich phases cements entrained particulates causing the off-gas line to plug. It is concluded that off-gas system pluggage can be effectively controlled by maintaining the off-gas velocity above 16 m/s, while maintaining the off-gas temperature as high as practical below the glass softening point. This paper summarizes the results of chemical and physical analyses of off-gas deposit samples from various melters at SRL. Recent design changes made to the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) to alleviate the pluggage problem are also discussed

  9. Performance testing With JMeter 29

    CERN Document Server

    Erinle, Bayo

    2013-01-01

    Performance Testing With JMeter 2.9 is a standard tutorial that will help you polish your fundamentals, guide you through various advanced topics, and along the process help you learn new tools and skills.This book is for developers, quality assurance engineers, testers, and test managers new to Apache JMeter, or those who are looking to get a good grounding in how to effectively use and become proficient with it. No prior testing experience is required.

  10. Design and optimization of a combined fuel reforming and solid oxide fuel cell system with anode off-gas recycling

    International Nuclear Information System (INIS)

    Highlights: ? In this work, an analytical, parametric study is performed to evaluate the feasibility and performance of a combined fuel reforming and SOFC system. ? Specifically the effects of adding the anode off-gas recycling and recirculation components and the CO2 absorbent unit are investigated. ? The AOG recycle ratio increases with increasing S/C ratio and the addition of AOG recycle eliminates the need for external water consumption. ? The key finding is that for the SOFC operating at 900 deg. C with the steam to carbon ratio at 5 and no AOG recirculation, the system efficiency peaks. - Abstract: An energy conversion and management concept for a combined system of a solid oxide fuel cell coupled with a fuel reforming device is developed and analyzed by a thermodynamic and electrochemical model. The model is verified by an experiment and then used to evaluate the overall system performance and to further suggest an optimal design strategy. The unique feature of the system is the inclusion of the anode off-gas recycle that eliminates the need of external water consumption for practical applications. The system performance is evaluated as a function of the steam to carbon ratio, fuel cell temperature, anode off gas recycle ratio and CO2 adsorption percentage. For most of the operating conditions investigated, the system efficiency starts at around 70% and then monotonically decreases to the average of 50% at the peak power density bef 50% at the peak power density before dropping down to zero at the limiting current density point. From an engineering application point of view, the proposed combined fuel reforming and SOFC system with a range of efficiency between 50% and 70% is considered very attractive. It is suggested that the optimal system is the one where the SOFC operates around 900 deg. C with S/C ratio higher than 3, maximum CO2 capture, and minimum AOG recirculation.

  11. Team Performance with Test Scores

    OpenAIRE

    Kleinberg, Jon; Raghu, Maithra

    2015-01-01

    Team performance is a ubiquitous area of inquiry in the social sciences, and it motivates the problem of team selection -- choosing the members of a team for maximum performance. Influential work of Hong and Page has argued that testing individuals in isolation and then assembling the highest-scoring ones into a team is not an effective method for team selection. For a broad class of performance measures, based on the expected maximum of random variables representing individ...

  12. Performance Testing of Cutting Fluids

    DEFF Research Database (Denmark)

    Belluco, Walter

    2001-01-01

    The importance of cutting fluid performance testing has increased with documentation requirements of new cutting fluid formulations based on more sustainable products, as well as cutting with minimum quantity of lubrication and dry cutting. Two sub-problems have to be solved: i) which machining tests feature repeatability, reproducibility and sensitivity to cutting fluids, and ii) to what extent results of one test ensure relevance to a wider set of machining situations. The present work is aimed at assessing the range of validity of the different testing methods, investigating correlation within the whole range of operations, materials, cutting fluids, operating conditions, etc. Cutting fluid performance was evaluated in turning, drilling, reaming and tapping, and with respect to tool life, cutting forces, chip formation and product quality (dimensional accuracy and surface integrity). A number of different work materials were considered, with emphasis on austenitic stainless steel. Cutting fluids from two main groups were investigated, water miscible (reviewed from previous work) and straight oils. Results show that correlation of cutting fluid performance in different operations exists within the same group of cutting fluids, for stainless steel. A possible rationalisation of cutting fluid performance tests is suggested. In order to select a set of basic tests and optimise them for use as general and standardised testing methods, an original approach to the evaluation of cutting force and tool life uncertainty is proposed.

  13. Anode shroud for off-gas capture and removal from electrolytic oxide reduction system

    Science.gov (United States)

    Bailey, James L.; Barnes, Laurel A.; Wiedmeyer, Stanley G.; Williamson, Mark A.; Willit, James L.

    2014-07-08

    An electrolytic oxide reduction system according to a non-limiting embodiment of the present invention may include a plurality of anode assemblies and an anode shroud for each of the anode assemblies. The anode shroud may be used to dilute, cool, and/or remove off-gas from the electrolytic oxide reduction system. The anode shroud may include a body portion having a tapered upper section that includes an apex. The body portion may have an inner wall that defines an off-gas collection cavity. A chimney structure may extend from the apex of the upper section and be connected to the off-gas collection cavity of the body portion. The chimney structure may include an inner tube within an outer tube. Accordingly, a sweep gas/cooling gas may be supplied down the annular space between the inner and outer tubes, while the off-gas may be removed through an exit path defined by the inner tube.

  14. Off-Gas Analysis During the Vitrification of Hanford Radioactive Waste Samples

    International Nuclear Information System (INIS)

    This paper describes the off-gas analysis of samples collected during the radioactive vitrification experiments. Production and characterization of the Hanford waste-containing LAW and HAW glasses are presented in related reports from this conference

  15. Modular design of a reprocessing plant dissolver off-gas system. Variations, flexibility and stage of development

    International Nuclear Information System (INIS)

    Simple and economic control of the volatile radionuclides in a reprocessing plant requires two equally important prerequisites: suitable processing in the plant head-end and reliable operation of the dissolver off-gas (DOG) purification system. A small number of DOG purification modules was selected from various alternatives. The major selection criteria are removal efficiency, simplicity, convenient operating conditions and flexibility that provide compatibility with other off-gas treatment steps, subsequent waste treatment and different processing modes in the head-end. The behaviour of noxious materials was investigated in nitric acid off-gas scrubbers of different design and for a wide range of operating modes and conditions. A concentration range of nitric acid from very dilute to hyperazeotropic concentrations and a temperature range from -55 deg. C to above room temperature as well as the use of hydrogen peroxide were studied on an engineering scale. Nitrous gases and iodine can be removed to the trace level at special operating modes. Aerosol and iodine filters are discussed briefly. A selective absorption process using CF2Cl2 solvent for noble gas and 14C removal was developed on a laboratory scale. It operates at low temperatures and atmospheric pressure. Xe and Kr were separated using two absorption columns. Pilot-plant scale noble gas scrubbers are under construction and are being integrated into the existing test facility.ntegrated into the existing test facility. A series of process steps has been chosen for integrated process demonstration runs on an engineering scale. The integrated DOG system consists of several scrubbers and filters operating at atmospheric pressure. The temperature decreases stepwise, without producing large changes in the opposite direction, providing compatibility within the process train

  16. Exergetic Optimization of a Refrigeration Cycle for Re-Liquefaction of LNG Boil-Off Gas

    Directory of Open Access Journals (Sweden)

    Mojtaba Babaelahi

    2010-11-01

    Full Text Available The development of liquefaction process for liquefied natural gas boil-off re-liquefaction plants will be addressed to provide an environmentally friendly and cost effective solution for gas transport. Onboard boil-off gas (BOG re-liquefaction is a new technology that liquefies BOG and returns it to the cargo tanks instead of burning it. Exergetic efficiency optimization for cryogenic refrigeration cycle for re-liquefaction of LNG boil-off gas is performed. Thermodynamic modeling has been performed based on the energy and exergy analyses. Objective problem is developed based on maximization of the plant exergetic efficiency and selected decision variables and constraints. Optimization process is performed using MATLAB genetic algorithm optimization toolbox. The results of exergetic efficiency optimization are compared with the corresponding results of the base case system obtained in the previous study. Finally, effects of some operating parameters on the exergetic efficiency are discussed by sensitivity analysis.

  17. LFK, FORTRAN Application Performance Test

    International Nuclear Information System (INIS)

    1 - Description of program or function: LFK, the Livermore FORTRAN Kernels, is a computer performance test that measures a realistic floating-point performance range for FORTRAN applications. Informally known as the Livermore Loops test, the LFK test may be used as a computer performance test, as a test of compiler accuracy (via checksums) and efficiency, or as a hardware endurance test. The LFK test, which focuses on FORTRAN as used in computational physics, measures the joint performance of the computer CPU, the compiler, and the computational structures in units of Mega-flops/sec or Mflops. A C language version of subroutine KERNEL is also included which executes 24 samples of C numerical computation. The 24 kernels are a hydrodynamics code fragment, a fragment from an incomplete Cholesky conjugate gradient code, the standard inner product function of linear algebra, a fragment from a banded linear equations routine, a segment of a tridiagonal elimination routine, an example of a general linear recurrence equation, an equation of state fragment, part of an alternating direction implicit integration code, an integrate predictor code, a difference predictor code, a first sum, a first difference, a fragment from a two-dimensional particle-in-cell code, a part of a one-dimensional particle-in-cell code, an example of how casually FORTRAN can be written, a Monte Carlo search loop, an example of an implicit conditional computation, a fragment of a two-dimensional explicin, a fragment of a two-dimensional explicit hydrodynamics code, a general linear recurrence equation, part of a discrete ordinates transport program, a simple matrix calculation, a segment of a Planck distribution procedure, a two-dimensional implicit hydrodynamics fragment, and determination of the location of the first minimum in an array. 2 - Method of solution: CPU performance rates depend strongly on the maturity of FORTRAN compiler machine code optimization. The LFK test-bed executes the set of 24 kernels three times, resetting the DO-loop controls so that short, medium, and long vector performance is sampled and can be compared. Following these three executions, the 72 timings are combined for statistical analysis and printed. The entire LFK test is executed seven times to measure experimental timing errors. An analysis of these timing errors for each kernel is provided to confirm the accuracy of the test. The LFK test also computes a sensitivity analysis of the weighted harmonic mean rate by assigning 49 sets of weights to the kernels. This analysis may be used for risk analysis to understand the variation in net performance that different workloads would cause. The LFK test report concludes with an analysis of the sensitivity of the net FORTRAN rate to optimization using the SISD/SIMD model, a two-component form of the weighted harmonic mean (harmonic Mflops) model. This analysis may be used to gauge the performance of applications from a knowledge of their vectorizability. 3 - Restrictions on the complexity of the problem: Although the LFK test evaluates the performance of a broad sampling of FORTRAN computations, it is not an application program; neither is it a complete benchmark test nor a substitute for one

  18. Radioactive material packaging performance testing

    International Nuclear Information System (INIS)

    To provide uniform packaging of hazardous materials on an international level, the United Nations has developed packaging recommendations that have been implemented worldwide. The United Nations packaging recommendations are performance oriented, allowing for a wide variety of package materials and systems. As a result of this international standard, efforts in the United States are being directed toward use of performance-oriented packaging and elimination of specification (designed) packaging. This presentation will focus on trends, design evaluation, and performance testing of radioactive material packaging. The impacts of US Department of Transportation Dockets HM-181 and HM-169A on specification and low-specific activity radioactive material packaging requirements are briefly discussed. The US Department of Energy's program for evaluating radioactive material packings per US Department of Transportation Specification 7A Type A requirements, is used as the basis for discussing low-activity packaging performance test requirements. High-activity package testing requirements are presented with examples of testing performed at the Hanford Site that is operated by Westinghouse Hanford Company for the US Department of Energy. 5 refs., 2 tabs

  19. Design and cost estimate for the SRL integrated hot off gas facility using selective adsorption

    International Nuclear Information System (INIS)

    Based on the results of an engineering-scale demonstration program, a design and cost estimate were performed for a 25-m3/h (15-ft3/min) capacity pilot plant demonstration system using selective adsorption technology for installation at the Integrated Hot Off Gas Facility at the Savannah River Plant. The design includes provisions for the destruction of NO/sub x/ and the concentration and removal of radioisotopes of ruthenium, iodine-129, tritiated water vapor, carbon-14 contaminated carbon dioxide, and krypton-85. The nobel gases are separated by the use of selective adsorption on mordenite-type zeolites. The theory of noble gas adsorption on zeolites is essentially the same as that for the adsorption of noble gases on activated charcoals. Considerable detail is provided regarding the application of the theory to adsorbent bed designs and operation. The design is based on a comprehensive material balance and appropriate heat transfer calculations. Details are provided on techniques and procedures used for heating, cooling, and desorbing the adsorbent columns. Analyses are also given regarding component and arrangement selection and includes discussions on alternative arrangements. The estimated equipment costs for the described treatment system is about $1,400,000. The cost estimate includes a detailed equipment list of all the major component items in the design. Related technical issues and estimated system performance are also discussedystem performance are also discussed

  20. Design and operation of off-gas cleaning systems at high level liquid waste conditioning facilities

    International Nuclear Information System (INIS)

    The immobilization of high level liquid wastes from the reprocessing of irradiated nuclear fuels is of great interest and serious efforts are being undertaken to find a satisfactory technical solution. Volatilization of fission product elements during immobilization poses the potential for the release of radioactive substances to the environment and necessitates effective off-gas cleaning systems. This report describes typical off-gas cleaning systems used in the most advanced high level liquid waste immobilization plants and considers most of the equipment and components which can be used for the efficient retention of the aerosols and volatile contaminants. In the case of a nuclear facility consisting of several different facilities, release limits are generally prescribed for the nuclear facility as a whole. Since high level liquid waste conditioning (calcination, vitrification, etc.) facilities are usually located at fuel reprocessing sites (where the majority of the high level liquid wastes originates), the off-gas cleaning system should be designed so that the airborne radioactivity discharge of the whole site, including the emission of the waste conditioning facility, can be kept below the permitted limits. This report deals with the sources and composition of different kinds of high level liquid wastes and describes briefly the main high level liquid waste solidification processes examining the sources and characteristics of the off-gas contaminants to be retained by the off-gas cleaning system. The equipment and components of typical off-gas systems used in the most advanced (large pilot or industrial scale) high level liquid waste solidification plants are described. Safety considerations for the design and safe operation of the off-gas systems are discussed. 60 refs, 31 figs, 17 tabs

  1. Startup and initial operation of a DFGD and pulse jet fabric filter system on Cokenergy's Indiana Harbor coke oven off gas system

    Energy Technology Data Exchange (ETDEWEB)

    Morris, W.J.; Gansley, R.R.; Schaddell, J.G.

    1999-07-01

    This paper describes the design, initial operation and performance testing of a Dry Flue Gas Desulfurization (DFGD) and Modular Pulse Jet Fabric Filter (MPJFF) system installed at Cokenergy's site in East Chicago, Indiana. The combined flue gas from the sixteen (16) waste heat recovery boilers is processed by the system to control emissions of sulfur dioxide and particulates. These boilers recover energy from coke oven off gas from Indiana Harbor Coke Company's coke batteries. The DFGD system consists of two 100% capacity absorbers. Each absorber vessel uses a single direct drive rotary atomizer to disperse the lime slurry for SO{sub 2} control. The MPJFF consists of thirty two (32) modules arranged in twin sixteen-compartment (16) units. The initial start up of the DFGD/MPJFF posed special operational issues due to the low initial gas flows through the system as the four coke oven batteries were cured and put in service for the first time. This occurred at approximately monthly intervals beginning in March 1998. A plan was implemented to perform a staged startup of the DFGD and MPJFF to coincide with the staged start up of the coke batteries and waste heat boilers. Operational issues that are currently being addressed include reliability of byproduct removal. Performance testing was conducted in August and September 1998 at the inlet of the system and the outlet stack. During these tests, particulate, SO{sub 2}, SO{sub 3}, and HCI emissions were measured simultaneously at the common DFGD inlet duct and the outlet stack. Measurements were also taken for average lime, water, and power consumption during the tests as well as system pressure losses. These results showed that all guarantee parameters were achieved during the test periods. The initial operation and performance testing are described in this paper.

  2. Development of the krypton absorption in liquid carbon dioxide (KALC) process for HTGR off-gas reprocessing

    International Nuclear Information System (INIS)

    Reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel involves burning of the graphite-matrix elements to release the fuel for recovery purposes. The resulting off-gas is primarily CO2 with residual amounts of N2, O2, and CO, together with fission products. Trace quantities of krypton-85 must be recovered in a concentrated form from the gas stream, but processes commonly employed for rare gas removal and concentration are not suitable for use with off-gas from graphite burning. The KALC (Krypton Absorption in Liquid CO2) process employs liquid CO2 as a volatile solvent for the krypton and is, therefore, uniquely suited to the task. Engineering development of the KALC process is currently under way at the Oak Ridge National Laboratory (ORNL) and the Oak Ridge Gaseous Diffusion Plant (ORGDP). The ORNL system is designed for close study of the individual separation operations involved in the KALC process, while the ORGDP system provides a complete pilot facility for demonstrating combined operations on a somewhat larger scale. Packed column performance and process control procedures have been of prime importance in the initial studies. Computer programs have been prepared to analyze and model operational performance of the KALC studies, and special sampling and in-line monitoring systems have been developed for use in the experimental facilities. (U.S.)

  3. Present status and problems of conventional off-gas cleaning system

    International Nuclear Information System (INIS)

    The off-gas from reprocessing dissolution process contains volatile radioactive nuclides such as H-3, Kr-85, I-129 and C-14. The establishment of the method for removing or fixing them in order to prevent the release into environment is a social concern. The study group investigated the present status of the research and development on the volatile nuclides from the generation to the disposal, and attempted to set up the off-gas cleaning system which is considered to be more rational. It is important that the dissolution off-gas cleaning system is composed of the processes which are highly safe and reliable, economical and simple. It is necessary to pay attention to use the techniques of high reliability, to remove strongly corrosive nuclides such as iodine at the first step, to make the system into a continuous type or close to it to prevent the accumulation of radioactive substances, to avoid high temperature, high pressure operation as far as possible, to avoid the use of toxic and highly explosive chemical substances and to make the process flexible so as to be able to cope with the variation of operational condition. From these viewpoints, the existing off-gas cleaning system was examined, and the plan of its improvement was proposed as a total off-gas cleaning system. (Kako, I.)

  4. Parametric studies of off-gas release during in situ vitrification

    International Nuclear Information System (INIS)

    Off-gases are released from underground sources during the In Situ Vitrification (ISV) process. Most of these gases will be generated beyond the melt front where advancing high temperatures will cause pyrolysis and vaporization of organic and volatile materials. Some of these gases will enter the bottom of the melt pool and propagate upwards to the surface where they will enter the ISV confinement hood. A computer code called OGRE (Off-Gas RElease) has been written to model bubble-rise physics in the melt pool for given volumetric gas flux rates into the bottom of the pool. The models incorporated into OGRE have previously been reported. The purpose of the present document is to report the results of a series of parametric studies performed with OGRE. The numerical studies involve the variation of seventeen parameters for each of the two different inlet bubble-size models. Results indicate that while predictions appear qualitatively reasonable, additional development of the agglomeration and drift flux models is needed. This development will require experimental data for bubble formation and terminal velocity. 5 refs., 36 figs., 2 tabs

  5. Off-gas chemistry study of melter feed by Springborn Laboratories

    International Nuclear Information System (INIS)

    The purpose of the off-gas chemistry study of melter feed samples was to support and help substantiate glass melter thermochemistry models developed for the DWPF. Both sludge-only and sludge-precipitate feed samples were analyzed. Each slurry sample was pyrolyzed at temperatures from 150 to 10000C in air and inert atmospheres, and the head space products were analyzed by chromatographic and mass spectrometric methods. Thermogravimetric, differential scanning calorimetric and Fourier transform infrared analyses were also performed on each sample. There were no unusually high exothermic reactions that would be cause for concern in the DWPF melter. Results for two types of sludge-precipitate feed were compared. One type contained simulated precipitate hydrolysis aqueous (PHA) product as fed to the SCM-2 melter. The second type contained PHA from the lab-scale acid hydrolysis reactor in 677-T. A major difference between the two types was a small, but distinct, presence of higher aromatics in gas from feed with reactor-produced PHA. This feed also evolved more CO and CO2 than feed with simulated PHA at high pyrolytic temperatures (>7500C). Recent analyses have identified the higher boiling aromatics in reactor-produced PHA as primarily diphenylamine and p-terphenyl. These compounds will be included in future PHA simulations that are fed to research melters. Under an inert atmosphere, benzene and phenol were the two most abundant organics evnol were the two most abundant organics evolved during pyrolysis of sludge-precipitate feed

  6. Reflectors for SAR performance testing.

    Energy Technology Data Exchange (ETDEWEB)

    Doerry, Armin Walter

    2008-01-01

    Synthetic Aperture Radar (SAR) performance testing and estimation is facilitated by observing the system response to known target scene elements. Trihedral corner reflectors and other canonical targets play an important role because their Radar Cross Section (RCS) can be calculated analytically. However, reflector orientation and the proximity of the ground and mounting structures can significantly impact the accuracy and precision with which measurements can be made. These issues are examined in this report.

  7. Design and calibration of a test facility for MLI thermal performance measurements below 80K

    International Nuclear Information System (INIS)

    The design geometry of the SSC dipole cryostat includes active thermal radiation shields operating at 80K and 20K respectively. Extensive measurements conducted in a Heat Leak Test Facility (HLTF) have been used to evaluate the thermal performance of candidate multilayer insulation (MLI) systems for the 80K thermal shield, with the present system design based upon those measurement results. With the 80K MLI geometry established, efforts have focused on measuring the performance of MLI systems near 20K. A redesign of the HLTF has produced a measurement facility capable of conducting measurements with the warm boundary fixed at 80K and the cold boundary variable from 10K to 50K. Removing the 80K shield permits measurements with a warm boundary at 300K. The 80K boundary consists of a copper shield thermally anchored to a liquid nitrogen reservoir. The cold boundary consists of a copper anchor plate whose temperature is varied through boil-off gas from a 500 liter helium supply dewar. A transfer line heat exchanger supplies the boil-off gas to the anchor plate at a constant and controlled rate. The gas, which serves as cooling gas, is routed through a copper cooling tube soldered into the anchor plate. Varying the cooling gas flow rate varies the amount of refrigeration supplied to the anchor plate, thereby determining the plate temperature. A resistance heater installed on the anchor plate is regulated by a cryogenic temperature controller to provide final temperature control. Heat leak values are measured using a heatmeter which senses heat flow as a temperature gradient across a fixed thermal impedance. Since the thermal conductivity of the thermal impedance changes with temperature, the heatmeter is calibrated at key cold boundary temperatures. Thus, the system is capable of obtaining measurement data under a variety of system conditions. 7 refs

  8. Trends in the design and operation of off-gas cleaning systems in nuclear facilities

    International Nuclear Information System (INIS)

    Trends in the design and operation of off-gas cleaning systems in nuclear facilities reflect the normal development by manufacturers of new and improved equipment and the demand for more safety, greater reliability, and higher collection efficiency as an aftermath of the well publicized accident at Three Mile Island. The latter event has to be viewed as a watershed in the history of off-gas treatment requirements for nuclear facilities. It is too soon to predict what these will be with any degree of assurance but it seems reasonable to expect greatly increased interest in containment venting systems for light water and LMFBR nuclear power reactors and more stringent regulatory requirements for auxiliary off-gas cleaning systems. Although chemical and waste handling plants share few characteristics with reactors other than the presence of radioactive materials, often in large amounts, tighter requirements for handling reactor off-gases will surely be transferred to other kinds of nuclear facilities without delay. Currently employed nuclear off-gas cleaning technology was largely developed and applied during the decade of the 1950s. It is regrettable that the most efficient and most economical off-gas treatment systems do not always yield the best waste forms for storage or disposal. It is even more regrettable that waste management has ceased to be solely a technical matter but has been transformed instead into a highly charged political posture of major importance in many western nations. Little reinforcement has been provided by detailed studies of off-gas treatment equipment failures that show that approximately 13% of over 9000 licensee event reports to the United States Nuclear Regulatory Commission pertained to failures in ventilating and cleaning systems and their monitoring instruments

  9. Removal of CO2 in closed loop off-gas treatment systems

    International Nuclear Information System (INIS)

    A closed loop test system has been installed at Argonne National Laboratory (ANL) to demonstrate off-gas treatment, absorption, and purification systems to be used for incineration and vitrification of hazardous and mixed waste. Closed loop systems can virtually eliminate the potential for release of hazardous or toxic materials to the atmosphere during both normal and upset conditions. In initial tests, a 250,000 Btu/h (75 kW thermal) combustor was operated in an open loop to produce a combustion product gas. The CO2 in these tests was removed by reaction with a fluidized bed of time to produce CaCO3. Subsequently, recirculation system was installed to allow closed loop operation with the addition of oxygen to the recycle stream to support combustion. Commercially marketed technologies for removal of CO2 can be adapted for use on closed loop incineration systems. The paper also describes the Absorbent Solution Treatment (AST) process, based on modifications to commercially demonstrated gas purification technologies. In this process, a side loop system is added to the main loop for removing CO2 in scrubbing towers using aqueous-based CO2 absorbents. The remaining gas is returned to the incinerator with oxygen addition. The absorbent is regenerated by driving off the CO2 and water vapor, which are released to the atmosphere. Contaminants are either recycled for further treatment or form precipitates which are removed during the purification and regeneration process. There are no direct releases of gases or particulates to the environment. The CO2 and water vapor go through two changes of state before release, effectively separating these combustion products from contaminants released during incineration. The AST process can accept a wide range of waste streams. The system may be retrofitted to existing Facilities or included in the designs for new installations

  10. Removal of Mercury from the Off-Gas from Thermal Treatment of Radioactive Liquid Waste

    Energy Technology Data Exchange (ETDEWEB)

    Deldebbio, John Anthony; Olson, Lonnie Gene

    2001-05-01

    Acidic, radioactive wastes with a high nitrate concentration, and containing mercury are currently being stored at the Idaho Nuclear Technology and Engineering Center (INTEC). In the past, these wastes were converted into a dry, granular solid by a high temperature fluidized-bed calcination process. In the future, the calcined solids may be immobilized by a vitrification process prior to disposal. It has been proposed that a vitrification facility be built to treat the acidic wastes, as well as the calcined solids. As was the case with the calcination process, NOx levels in the vitrification off-gas are expected to be high, and mercury emissions are expected to exceed the Maximum Control Technology (MACT) limits. Mitigation of mercury emissions by wet scrubbing, followed by adsorption onto activated carbon is being investigated. Scoping tests with sulfur-impregnated activated carbon, KCl-impregnated activated carbon and non-impregnated activated carbon were conducted with a test gas containing1% NO2, 28% H2O, 4% O2 and 67% N2. Average removal efficiencies for Hgo and HgCl2 were 100 ± 2.5% and 99 ± 3.6% respectively, for sulfur-impregnated carbon. The KCl-impregnated carbon removed 99 ± 4.6% HgCl2. The removal efficiency of the non-impregnated carbon was 99 ± 3.6% for HgCl2. No short-term detrimental effects due to NO2 and H2O were observed. These results indicate that, placed downstream of a wet scrubber, an activated carbon adsorption bed has the potential of reducing mercury levels sufficiently to enable compliance with the MACT limit. Long-term exposure tests, and bed size optimization studies are planned for the future.

  11. Development of off-gas recombiner using catalyst with honeycomb ceramics carrier

    International Nuclear Information System (INIS)

    The off-gas recombiners in BWR nuclear plants have been using the beads type catalyst. Recently, a catalyst with the new carrier 'honeycomb ceramic' was commercialized in some fields of industries. It has some features indicating a high conversion ratio, low differential pressure, and high durability. We have examined it to confirm its applicability to BWR plant. As a result, it has been confirmed that the honeycomb-type carrier is more suitable for an off-gas recombiner catalyst compared with the conventional beads-type. In this paper, we introduce the outline of our development. (author)

  12. Reprocessing off-gas treatment research in Belgium

    International Nuclear Information System (INIS)

    The research project at the Belgian Nuclear Research Center (S.C.K./C.E.N.) is technologically oriented and aims at the development of industrially applicable techniques for capture of in the perspective of increasingly severe discharge authorizations at the stack of reprocessing plants. Attention was focussed on the I problem particularly, the long lived I129 isotope. Among the many capture techniques, scrubbing by HgNO3-HNO3 solutions, followed by adsorption on silver impregnated zeolites was chosen. Pilot installations with a throughput of 25 m3h-1 have been constructed and operated with simulated gases resulting fram a mock-up dissolver and traced with molecular I131 and CH3 I131 at up to several hundred mCi. The second nuclide of interest to the environment is Kr85 which has to be retained within the limits imposed by the new US regulations. Cryogenic absorption-distillation was chosen as reference technique. A pilot installation of 15 m3h-1 has been installed and operated on a continuous basis. Capture of T gas and tritiated water vapour was studied parametrically in simulated conditions. A new pilot equipment of 15 m3h-1 combining catalytic oxidation and adsorption on molecular sieves has been constructed. All the selected techniques will be integrated into a mock-up gas loop of 25 m3h-1 in order to test the mutual influence of the different unit steps on each other and on the ultimate decontamination factor. Finally a pilot facility for studying head-end processing (HERMES) has been designed in which the most appropriate gas purification techniques will be tested in hot cell conditions. (orig./HP)

  13. Development of a hydrogen mordenite sorbent for the capture of krypton from used nuclear fuel reprocessing off-gas streams

    International Nuclear Information System (INIS)

    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. (author)

  14. Characterization of magnesium phosphate ceramics incorporating off-gas filters

    International Nuclear Information System (INIS)

    Radioactive cesium (Cs-137) and technetium (Tc-99) are discharged from the spent fuel as gaseous forms during the head-end process in pyroprocess. These off-gases are safely trapped via porous ceramic filters made of fly ash and calcium based material. Spent filters have to be treated, converted into proper waste forms in order to be disposed safely at a repository. Conventional technology used to make waste forms such as vitrification requires high temperature and complex process. In this study, we report a promising method to stabilize spent filters containing cesium and technetium using magnesium phosphate ceramics. Simulated spent filters were fabricated by vaporizing nonradioactive cesium and rhenium (a surrogate of Tc) through the voloxidizer. The crushed filters were mixed with raw materials of magnesium phosphate ceramics, to be stabilized in the phosphate ceramic matrix. Characterization of the waste forms was made by the compressive strength test, apparent porosity, XRD analysis, and SEM analysis. The sample containing filters showed the excellent mechanical property, with the highest compressive strength of 38.1 MPa in the sample with 30 wt% of Cs-filter. Microstructural analysis suggests that wastes are embedded in the crystalline phase formed by an acid-base reaction. (author)

  15. Analysis of fire and smoke threat to off-gas HEPA filters in a transuranium processing plant

    International Nuclear Information System (INIS)

    The author performed an analysis of fire risk to the high-efficiency particulate air (HEPA) filters that provide ventilation containment for a transuranium processing plant at the Oak Ridge National Laboratory. A fire-safety survey by an independent fire-protection consulting company had identified the HEPA filters in the facility's off-gas containment ventilation system as being at risk from fire effects. Independently studied were the ventilation networks and flow dynamics, and typical fuel loads were analyzed. It was found that virtually no condition for fire initiation exists and that, even if a fire started, its consequences would be minimal as a result of standard shut-down procedures. Moreover, the installed fire-protection system would limit any fire and thus would further reduce smoke or heat exposure to the ventilation components. 4 references, 4 figures, 5 tables

  16. Operator performance in non-destructive testing: A study of operator performance in a performance test

    International Nuclear Information System (INIS)

    In the process industries there is a need of inspecting the integrity of critical components without disrupting the process. Such in-service inspections are typically performed with non-destructive testing (NDT). In NDT the task of the operator is to (based on diagnostic information) decide if the component can remain in service or not. The present study looks at the performance in NDT. The aim is to improve performance, in the long run, by exploring the operators' decision strategies and other underlying factors and to this way find out what makes some operators more successful than others. Sixteen operators performed manual ultrasonic inspections of four test pieces with the aim to detect (implanted) cracks. In addition to these performance demonstration tests (PDT), the operators performed independent ability tests and filled out questionnaires. The results show that operators who trust their gut feeling more than the procedure (when the two come to different results) and that at the same time have a positive attitude towards the procedure have a higher PDT performance. These results indicate the need for operators to be motivated and confident when performing NDT. It was also found that the operators who performed better rated more decision criteria higher in the detection phase than the operators who performed worse. For characterizing it was the other way around. Also, the operators who performed better used more time, both detecting and characterizing, than the operators who performed worse

  17. Operator performance in non-destructive testing: A study of operator performance in a performance test

    Energy Technology Data Exchange (ETDEWEB)

    Enkvist, J.; Edland, A.; Svenson, Ola [Stockholm Univ. (Sweden). Dept. of Psychology

    2000-05-15

    In the process industries there is a need of inspecting the integrity of critical components without disrupting the process. Such in-service inspections are typically performed with non-destructive testing (NDT). In NDT the task of the operator is to (based on diagnostic information) decide if the component can remain in service or not. The present study looks at the performance in NDT. The aim is to improve performance, in the long run, by exploring the operators' decision strategies and other underlying factors and to this way find out what makes some operators more successful than others. Sixteen operators performed manual ultrasonic inspections of four test pieces with the aim to detect (implanted) cracks. In addition to these performance demonstration tests (PDT), the operators performed independent ability tests and filled out questionnaires. The results show that operators who trust their gut feeling more than the procedure (when the two come to different results) and that at the same time have a positive attitude towards the procedure have a higher PDT performance. These results indicate the need for operators to be motivated and confident when performing NDT. It was also found that the operators who performed better rated more decision criteria higher in the detection phase than the operators who performed worse. For characterizing it was the other way around. Also, the operators who performed better used more time, both detecting and characterizing, than the operators who performed worse.

  18. Removal of carbon dioxide in reprocessing spent nuclear fuel off gas by adsorption

    International Nuclear Information System (INIS)

    Off gases produced in the reprocessing of spent nuclear fuel contain various radioactive components and emission of these components to the environment must be prevented as low as possible. Carbon-14 with a long half-life, which is mainly released as the form of carbon dioxide, is one of such gaseous radioactive materials. One of the measures to capture radioactive gases from the off-gas is the utilization of adsorption technique. In this work, the adsorption behavior of carbon dioxide on synthetic zeolites and natural mordenites was studied at lower partial pressure ranges. Moreover, the authors quantitatively investigated the influence of coexistent water vapor, which is also contained in the off-gas, on the adsorption behavior of carbon dioxide. (author)

  19. The art of application performance testing

    CERN Document Server

    Molyneaux, Ian

    2009-01-01

    The Art of Application Performance Testing provides a step-by-step approach to testing mission-critical applications for scalability and performance before they're deployed -- a critical topic to which other books devote, at most, one chapter. With it, you'll learn the complete life cycle of the testing process, along with best practices to help you plan, gain approval for, coordinate, and conduct performance tests on your applications

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

    International Nuclear Information System (INIS)

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

  1. Electron beam processing of industrial off gas by the mobile irradiation plant AGATE-M

    International Nuclear Information System (INIS)

    A mobile irradiation plant (AGATE-M) has been constructed for on-site demonstration of off-gas treatment by electron beam. AGATE-M has been designed for flow rates up to 1000 Nm3/h and is equipped with a pre-filter, a reaction chamber connected to a low energy (200 kV) accelerator, a product filter and measurement systems. (author)

  2. Confidence and Cognitive Test Performance

    Science.gov (United States)

    Stankov, Lazar; Lee, Jihyun

    2008-01-01

    This article examines the nature of confidence in relation to abilities, personality, and metacognition. Confidence scores were collected during the administration of Reading and Listening sections of the Test of English as a Foreign Language Internet-Based Test (TOEFL iBT) to 824 native speakers of English. Those confidence scores were correlated…

  3. Treatment of off-gas evolved from thermal decomposition of sludge waste

    International Nuclear Information System (INIS)

    Korea Atomic Energy Research Institute (KAERI) started a decommissioning program of a uranium conversion plant. The treatment of the sludge waste, which was generated during the operation of the plant, is one of the most important tasks in the decommissioning program of the plant. The major compounds of sludge waste are nitrate salts and uranium. The sludge waste is denitrated by thermal decomposition. The treatment of off-gas evolved from the thermal decomposition of nitrate salts in the sludge waste is investigated. The nitrate salts in the sludge were decomposed in two steps: the first decomposition is due to the ammonium nitrate, and the second is due to the sodium and calcium nitrate and calcium carbonate. The components of off-gas from the decomposition of ammonium nitrate at low temperature are NH3, N2O, NO2, and NO. In addition, the components from the decomposition of sodium and calcium nitrate at high temperature are NO2 and NO. Off-gas from the thermal decomposition is treated by the catalytic oxidation of ammonia and selective catalytic reduction (SCR). Ammonia is converted into nitrogen oxides through the oxidation catalyst and all nitrogen oxides are removed by SCR treatment besides nitrous oxide, which is greenhouse gas. An additional process is needed to remove nitrous oxide, and the feeding rate of ammonia in SCR should be controlled properly for evolved nitrogen oxides. (author)des. (author)

  4. Removal of Mercury from SBW Vitrification Off-Gas by Activated Carbon

    International Nuclear Information System (INIS)

    Radioactive, acidic waste stored at the Idaho Nuclear Technology and Engineering Center (INTEC) have been previously converted into a dry, granular solid at the New Waste Calcining Facility (NWCF). As an alternative to calcination, direct vitrification of the waste, as well as the calcined solids in an Idaho Waste Vitrification Facility (IWVF) is being considered to prepare the waste for final disposal in a federal repository. The remaining waste to be processed is Sodium-Bearing Waste (SBW). Off-gas monitoring during NWCF operations have indicated that future mercury emissions may exceed the proposed Maximum Achievable Control Technology (MACT) limit of 130 ug/dscm (micrograms/dry standard cubic meter) (at) 7% O2 for existing Hazardous Waste Combustors (HWC) if modifications are not made. Carbon monoxide and hydrocarbon emissions may also exceed the MACT limits. Off-gas models have predicted that mercury levels in the off-gas from SBW vitrification will exceed the proposed MACT limit of 45 ug/dscm (at) 7% O2 for new HWCs. NO2/44% H2O

  5. NOx Abatement Pilot Plant 90-day test results report

    International Nuclear Information System (INIS)

    High-level radioactive liquid wastes produced during nuclear fuel reprocessing at the Idaho Chemical Processing Plant are calcined in the New Waste Calcining Facility (NWCF) to provide both volume reduction and a more stable waste form. Because a large component of the HLW is nitric acid, high levels of oxides of nitrogen (NOx) are produced in the process and discharged to the environment via the calciner off-gas. The NOx abatement program is required by the new Fuel Processing Restoration (FPR) project permit to construct to reduce NOx emissions from the NWCF. Extensive research and development has indicated that the selective catalytic reduction (SCR) process is the most promising technology for treating the NWCF off-gas. Pilot plant tests were performed to determine the compatibility of the SCR process with actual NWCF off-gas. Test results indicate that the SCR process is a viable method for abating the NOx from the NWCF off-gas. Reduction efficiencies over 95% can be obtained, with minimal amounts of ammonia slip, provided favorable operating conditions exist. Two reactors operated with series flow will provide optimum reduction capabilities. Typical operation should be performed with a first reactor stage gas space velocity of 20,000 hr-1 and an inlet temperature of 320 degrees C. The first stage exhaust NOx concentration will then dictate the parameter settings for the second stage. Operation should always strive for a peak reactor temperature of 520 degrees C in both reactors, with minimal NH3 slip from the second reactor. Frequent fluctuations in the NWCF off-gas NOx concentration will require a full-scale reduction facility that is versatile and quick-responding. Sudden changes in NWCF off-gas NOx concentrations will require quick detection and immediate response to avoid reactor bed over-heating and/or excessive ammonia slip

  6. Formation rate of ammonium nitrate in the off-gas line of SRAT and SME in DWPF

    International Nuclear Information System (INIS)

    A mathematical model for the formation rate of ammonium nitrate in the off-gas line of the Sludge Receipt and Adjustment Tank (SRAT) and the Slurry Mixed Evaporator (SME) in DWPF has been developed. The formation rate of ammonium nitrate in the off-gas line depends on pH, temperature, volume and total concentration of ammonia and ammonium ion. Based on a typical SRAT and SME cycle in DWPF, this model predicts the SRAT contributes about 50 lbs of ammonium nitrate while SME contributes about 60 lbs of ammonium nitrate to the off-gas line

  7. The performance tests used the water scrubber for ruthenium rejection

    International Nuclear Information System (INIS)

    LEDF (Large Equipment Dismantling Facility) will be constructed for the purpose of decontaminating the high level ? solid waste generated in oarai engineering center of JNC. And, main processing process of LEDF is incineration and melting system. LEDF will be intended to reduce the secondary waste that occurs along with the operation of the off gas processing equipment of incineration and melting system. It assumed that we are able to eliminate the adsorption tower using silica gel, if the decontamination factor to volatile ruthenium is able to expect in the packed scrubber that is established to remove harmful gas. Thereupon, we carried out this tests that eliminates the adsorption tower and reduces the secondary waste. The decontamination factor (DF) to the volatile ruthenium by the water scrubber is confirmed in the established institution which is in Tokai Works. However, decontamination factor differs and depends on the ruthenium concentration, harmful gas concentration, washing method and also washing condition. Also, the DF value to the volatile ruthenium in the off gas that occurs from incineration and melting system is obtained, does not exist under the same condition as LEDF. Therefore, the decontamination factor to the volatile ruthenium of the packed scrubber under the operating condition of LEDF is confirmed by this test. The main result of this study is as follows. (1) In the examination of the test device specification, the packed scrubber design methoication, the packed scrubber design method was investigated. And, the test device the maintained the resemblance nature with a real machine was produced on the basis of this result. (2) In the result of the ruthenium occurrence condition confirmation test, it was confirmed that the test condition such as the kind of the oxidizer, hold temperature of the oxidization reaction container that produce volatile ruthenium continuously. (3) In the result of the occurrence temperature influence confirmation test, it was confirmed that the ruthenium that occurred with the test device is not particle from aerosol and be gas form volatile ruthenium. (4) In the result of the decontamination factor measuring test and small size hot test, it was confirmed that the DF of the packed scrubber is 10?50. (5) On the basis of the result of each test, we summarized the design condition of the packed scrubber of LEDF and clarified the examination subject in LEDF. (author)

  8. Structure-property relationship of metal-organic frameworks (MOFs) and physisorbed off-gas radionuclides

    International Nuclear Information System (INIS)

    We report on the host-guest interactions between metal-organic frameworks (MOFs) with various profiles and highly polarizable molecules (iodine), with emphasis on identifying preferential sorption sites in these systems. Radioactive iodine 129I, along with other volatile radionuclides (3H, 14C, Xe and Kr), represents a relevant component in the off-gas resulted during nuclear fuel reprocessing. Due to its very long half-life, 15.7 x 106 years, and potential health risks in humans, its efficient capture and long-term storage is of great importance. The leading iodine capture technology to date is based on trapping iodine in silver-exchanged mordenite. Our interests are directed towards improving existent capturing technologies, along with developing novel materials and alternative waste forms. Herein we report the first study that systematically monitors iodine loading onto MOFs, an emerging new class of porous solid-state materials. In this context, MOFs are of particular interest as: (i) they serve as ideal high capacity storage media, (ii) they hold potential for the selective adsorption from complex streams, due to their high versatility and tunability. This work highlights studies on both newly developed in our lab, and known highly porous MOFs that all possess distinct characteristics (specific surface area, pore volume, pore size, and dimension of the window access to the pore). The materials were loaded to saturation, where elemental iodine was introduced from here elemental iodine was introduced from solution, as well as from vapor phase. Uptakes in the range of ?125-150 wt% I2 sorbed were achieved, indicating that these materials outperform all other solid adsorbents to date in terms of overall capacity. Additionally, the loaded materials can be efficiently encapsulated in stable waste forms, including as low temperature sintering glasses. Ongoing studies are focused on gathering qualitative information with respect to localizing the physisorbed iodine molecules within the frameworks: X-ray single-crystal analyses, in conjunction with high pressure differential pair distribution function (d-PDF) studies aimed to identify preferential sites in the pores, and improve MOFs robustness. Furthermore, durability studies on the iodine loaded MOFs and subsequent waste forms include thermal analyses, SEM/EDS elemental mapping, and leach-durability testing. We anticipate for this in-depth analysis to further aid the design of advanced materials, capable to address major hallmarks: safe capture, stability and durability over extended timeframes.

  9. Ecotoxicological testing of performance fluids

    International Nuclear Information System (INIS)

    The report deals with a project comprising the testing of drilling fluids concerning ecotoxicology, biological degradation, and toxicity. Two types of drilling fluids were tested for toxic effects on marine algae and biological degradability. A fluid based on mineral oil was readily degradable (98% DOC removal in 28 days) while an ether based oil degraded more slowly (56% DOC removal in 28 days). The toxicity of both fluids was tested after emulsification of the oils in water and separating the oil and water phase after equilibration. The EC50 values obtained with this approach were 8.15 g/l for the oil based fluid and 116 g/l for the ether fluid. 9 figs., 8 tabs

  10. Integrated Performance Testing Workshop, Modules 6 - 11

    Energy Technology Data Exchange (ETDEWEB)

    Leach, Janice; Torres, Teresa M.

    2012-10-01

    These modules cover performance testing of: Interior Detection Systems; Access Controls; Exterior Detection Systems; Video Assessment Systems; SNM / Contraband Detection Systems; Access Delay Elements

  11. 40 CFR 610.63 - Performance tests.

    Science.gov (United States)

    2010-07-01

    40 Protection of Environment 29 2010-07-01 2010-07-01 false ...vehicle's performance will be determined by performing wide-open-throttle 0 to 60 mph acceleration tests (at normal ambient temperatures) on the baseline vehicle...

  12. A PERFORMANCE TEST OF TEACHING EFFECTIVENESS.

    Science.gov (United States)

    BAKER, EVA L.; POPHAM, V. JAMES

    THIS REPORT DESCRIBES THE INITIAL VALIDATION OF PERFORMANCE TESTS OF TEACHER EFFECTIVENESS--USING PUPIL GAINS AS THE CRITERION OF EFFECTIVENESS--AND THE STEPS TAKEN IN RECOGNITION OF THE PROPRIETY OF SUCH MEASURES ONLY IF ALL TEACHERS ARE TEACHING FOR THE SAME OBJECTIVES. AS A FIRST STEP, IT WAS HYPOTHESIZED THAT A VALID PERFORMANCE TEST OF…

  13. Performance test of laser trackers of FARO

    International Nuclear Information System (INIS)

    Results on performance test of laser trackers of FARO are reported. Test was performed on the following items: (1) drift of output after power on, (2) long term variation of output, (3) reproducibility of point measurement, and (4) comparison between measurement with a laser tracker and the one with WPS (Wire Positioning Sensor). (author)

  14. Performance test for a solar water heater

    Science.gov (United States)

    1979-01-01

    Two reports describe procedures and results of performance tests on domestic solar powered hot water system. Performance tests determine amount of energy collected by system, amount of energy delivered to solar source, power required to operate system and maintain proper tank temperature, overall system efficiency, and temperature distribution in tank.

  15. 2009 Ford Mustang Performance Test

    Directory of Open Access Journals (Sweden)

    Daniel Fernandes

    2009-01-01

    Full Text Available Our goal is to find the time required for a 2009 Ford Mustang to accelerate from rest to 88 feet per second. We begin with three equations involving force, velocity, and force inverse, which is a value derived from Newton's Law, F=ma. The Mustang has three gears with three different gear ratios that must be used as the car accelerates. We found results from 2000 to 6000 RPMs for all three gears. Once the force inverse was found, we plotted the force inverse vs. velocity graph. The area beneath this curve from 0 to 88 feet per second is the time it takes to reach that speed. Using a Riemann sum approximation, we found that the time to be 4.109 seconds. This is a very brief time and is comparable to 5.2 seconds, the time found in a real test by RSPORTSCARS.com.

  16. Off-gas treatment system Process Experimental Pilot Plant (PREPP) k-t evaluation

    International Nuclear Information System (INIS)

    The scope of work for this task involves a systems' evaluation, using the Kepner-Tregoe (K-T) decision analysis methodology, of off-gas treatment alternatives for a Process Experimental Pilot Plant (PREPP). Two basic systems were evaluated: (1) a wet treatment system using a quencher and scrubber system; and (2) a dry treatment system using a spray dryer and baghouse arrangement. Both systems would neutralize acidic off-gases (HCL and SO2) and remove radioactive particulates prior to release to the environment. The K-T analysis results provided a numerical comparison of the two basic off-gas treatments systems for PREPP. The overall ratings for the two systems differ by only 7%. The closeness of the evaluation indicates that either system is capable of treating the off-gases from PREPP. Based on the analysis, the wet treatment system design is slightly more favorable for PREPP. Technology development, expected operability, total costs, and safety aspects were determined to be more advantageous for the wet system design. Support technology was the only major category that appears less favorable for using the wet off-gas system for PREPP. When considering the two criteria considered most important for PREPP (capital cost and major accident prevention - both rated 10), the wet treatment system received maximum ratings. Space constraints placed on the design by the existing TAN-607 building configuration also are more easily met by the wet system design. Lastlyasily met by the wet system design. Lastly, the level of development for the wet system indicates more applicable experience for nuclear waste processing

  17. Steam Pressurizer test and water level measurement performance test

    International Nuclear Information System (INIS)

    The reports discuss steam high pressure chamber test and water level measurement system performance test. In the report, the necessity and the methodology of test is described. The test loop and small scale steam chamber are designed. The validation for the design is conducted. Muliti-channel(200 or more) high-speed data acquisition system is required and chosen. The achievement of 1st year and 2nd year plan are presented

  18. Critique of Hanford Waste Vitrification Plant off-gas sampling requirements

    International Nuclear Information System (INIS)

    Off-gas sampling and monitoring activities needed to support operations safety, process control, waste form qualification, and environmental protection requirements of the Hanford Waste Vitrification Plant (HWVP) have been evaluated. The locations of necessary sampling sites have been identified on the basis of plant requirements, and the applicability of Defense Waste Processing Facility (DWPF) reference sampling equipment to these HWVP requirements has been assessed for all sampling sites. Equipment deficiencies, if present, have been described and the bases for modifications and/or alternative approaches have been developed

  19. Development and validation of a combustion model for a fuel cell off-gas burner

    OpenAIRE

    Collins, William Tristan

    2008-01-01

    A low-emissions power generator comprising a solid oxide fuel cell coupled to a gas turbine has been developed by Rolls-Royce Fuel Cell Systems. As part of the cycle, a fraction of the unreacted fuel (the off-gas) and oxidizer streams is reacted in a burner, which is the main source of pollutant formation. In this thesis a computational model of the burner has been developed which captures the formation of NOx and the oxidation of CO. This model gives accurate predictions at lo...

  20. Modelling of Boil-Off Gas in LNG Tanks: A Case Study

    OpenAIRE

    Sheikh Zahidul Islam; Ebenezer Adom; Xianda Ji

    2010-01-01

    This paper focuses on the effect of pressure and heat leakages on Boil-off Gas (BOG) in Liquefied Natural Gas (LNG) tanks. The Lee-Kesler-Plocker (LKP) and the Starling modified Benedict-Webb-Rubin (BWRS) empirical models were used to simulate the compressibility factor, enthalpy and hence heat leakage at various pressures to determine the factors that affect the BOG in typical LNG tanks of different capacities. Using a case study data the heat leakage of 140,000kl, 160,00kl, 180,000kl and 20...

  1. Performance Test of the Salt transfer and Pellet fabrication of UCl3 Making Equipment for Electrorefining

    International Nuclear Information System (INIS)

    The process to produce a uranium chloride salt includes two steps: a reaction process of gaseous chlorine with liquid cadmium to form the CdCl2 occurring in a Cd layer, followed by a process to produce UCl3 by the reaction of U in the LiCl-KCl eutectic salt and CdCl2. Chemical reaction is next chlorination reaction; - Cd chlorination : Cd + Cl2 ? CdCl2 - U chlorination : 3CdCl2 + 2U ? 3Cd + 2UCl3 The apparatus for producing UCl3 consists of a chlorine gas generator, a uranium chlorinator, a Cd distiller, the pelletizer, a off-gas wet scrubber and a dry scrubber. Salt transfer system set among reactors to transfer salt at 500 .deg. C. The temperature of the reactants is maintained at about 600 .deg. C. After the reaction is completed in the uranium chlorinator, The Salt product is transferred to the Cd distiller to decrease residual Cd concentration in the salts, and then salt is transferred to the mould of pelletizer by a transfer system to fabricate pellet type salt. Performance test of the salt transfer and pellet fabrication of its equipment was tested in this work. Performance test of the salt transfer and pellet fabrication of UCl3 making equipment for Electrorefining carried out in this work. The result of equipment test is that melted salt at 600 .deg. C was easy transferred by salt transfer equipment heated at 500 .deg. C. In this time, salt transfer was carried out by argon gas pressurization at 3bar. When velocity of salt transfer was controlled under reduce pressure, velocity of salt transfer was difficult to control. And when salt pellet was fabricated by the mold of pelletizer heated at 90 .deg. C better than mold of pelletizer heated at 200 .deg. C because salt melted prevent leakage from mold of pelletizer

  2. Isoinertial tests to predict lifting performance.

    Science.gov (United States)

    Stevenson, J M; Andrew, G M; Bryant, J T; Greenhorn, D R; Thomson, J M

    1989-02-01

    Previous research has found isoinertial strength testing to be superior to isometric and isokinetic strength testing for prediction of task performance. The purpose of this study was to investigate tests on an isoinertial lifting machine (ILM) and their ability to predict performance on actual lifting tasks. Sixteen male subjects performed two lifting tasks: maximum box lift to truck-bed height of 1.35 m; and 'speed lifts' of 60 concrete blocks (each 22.7 kg) to the same height. These performance tests were compared to three ILM tests: a maximal lift to 1.83 m, a second maximal lift to 1.52 m, and an endurance test that entailed 60 timed ILM lifts of 22.7 kg to 1.83 m. Pearson product-moment correlations between ILM tests and performance tasks varied from r = 0.55 to 0.71. Therefore, the isoinertial test protocols employed in this study were able to account for only 30% to 50% of the variance in the performance of maximal lifting and endurance tasks. In was concluded that prediction of maximal lifting ability or endurance ability using an ILM might be enhanced by closer approximation of specific task variables, or by inclusion of dynamic parameters to measure technique. PMID:2714247

  3. Vitrification Facility integrated system performance testing report

    International Nuclear Information System (INIS)

    This report provides a summary of component and system performance testing associated with the Vitrification Facility (VF) following construction turnover. The VF at the West Valley Demonstration Project (WVDP) was designed to convert stored radioactive waste into a stable glass form for eventual disposal in a federal repository. Following an initial Functional and Checkout Testing of Systems (FACTS) Program and subsequent conversion of test stand equipment into the final VF, a testing program was executed to demonstrate successful performance of the components, subsystems, and systems that make up the vitrification process. Systems were started up and brought on line as construction was completed, until integrated system operation could be demonstrated to produce borosilicate glass using nonradioactive waste simulant. Integrated system testing and operation culminated with a successful Operational Readiness Review (ORR) and Department of Energy (DOE) approval to initiate vitrification of high-level waste (HLW) on June 19, 1996. Performance and integrated operational test runs conducted during the test program provided a means for critical examination, observation, and evaluation of the vitrification system. Test data taken for each Test Instruction Procedure (TIP) was used to evaluate component performance against system design and acceptance criteria, while test observations were used to correct, modify, or improve system operation. This process was critical in establishing operating conditions for the entire vitrification process

  4. Canadian national internal dosimetry performance testing programme

    International Nuclear Information System (INIS)

    This paper describes the design and construction of new Performance Testing programme that was implemented in Canada in 2008. The Canadian Regulator (Canadian Nuclear Safety Commission - CNSC) had determined that their licensees, in addition to the existing In Vivo and In Vitro performance tests, needed to demonstrate their ability in interpreting bioassay results. The program is administered by the Canadian National Calibration Reference Centre for Bioassay and In Vivo Monitoring (NCRC). Currently the NCRC carries out the performance testing for the In Vitro and In Vivo. At time of writing, the first round has not been completed and the pass/fail criteria have not been determined. (author)

  5. Canadian development program for off-gas management in nuclear facilities

    International Nuclear Information System (INIS)

    The Canadian program for the development and evaluation of processes and technology for the separation and containment of radioactive species in off-gases is directed towards the following specific aspects: 1) assessment of available treatment technology and evaluation of future clean-up requirements; 2) development and engineering evaluation, under realistic conditions, of promising new processes that would be inherently simpler and safer; and 3) specification of off-gas emission control systems for future nuclear facilities based on the most favourable technology. The program is being carried out by Atomic Energy of Canada Limited in collaboration with the electrical utility, Ontario Hydro, and selected Canadian universities. A brief description is presented of methods for removing tritium and carbon-14 from the moderator systems of CANDU power reactors, methods for removing iodine from the off-gases of a molybdenum-99 production facility at the Chalk River Nuclear Laboratories, and procedures for monitoring the off-gas effluent composition in the Thorium Fuel Reprocessing Experiment (TFRE) facility at the Whiteshell Nuclear Research Establishment

  6. HTGR-reprocessing off-gas cleaning by the AKUT-process

    International Nuclear Information System (INIS)

    During reprocessing of HTGR-fuel the graphite matrix has to be removed in order to gain the heavy metal, which is accomplished by burning the crushed fuel elements. During the burning part of the krypton and tritium is released from the fuel. Since the combustion gas is a mixture of CO2 and O2, the burner off-gas consists mainly of CO2 with a small amount of CO and fission products, mainly in gaseous form but also aerosols. A facility, called AKUT II, which consists of the following process steps: aerosol removal by electrostatic precipitators followed by HEPA-filters, catalytic conversion of CO and O2 to CO2, compression and liquefaction, separation of krypton by distillation, and adsorption of tritiated water on molecular sieve is now being installed in the KFA hot cells. The facility will be ready for cold operation early in 1977. After start-up of the HTGR-reprocessing pilot plant JUPITER the off-gas from the head-end will be treated in the AKUT facility

  7. Integrated Performance Testing for Nonproliferation Support Project

    Energy Technology Data Exchange (ETDEWEB)

    Johns, Russell; Bultz, Garl Alan; Byers, Kenneth R.; Yaegle, William

    2013-08-20

    The objective of this workshop is to provide participants with training in testing techniques and methodologies for assessment of the performance of: Physical Protection system elements; Material Control and Accounting (MC&A) system elements.

  8. Numerical study on NOx/CO emissions in the diffusion flames of high-temperature off-gas of steelmaking converter

    International Nuclear Information System (INIS)

    The combustion of high-temperature off-gas of steelmaking converter with periodical change of temperature and CO concentration always leads to CO and NOx over-standard emissions. In the paper, high-temperature off-gas combustion is simulated by adopting counterflow diffusion flame model, and some influencing factors of CO and NOx emissions are investigated by adopting a detailed chemistry GRI 3.0 mechanism. The emission index of NOx (EINOx) decreases 1.7-4.6% when air stoichiometric ratio (SR) increase from 0.6 to 1.4, and it dramatically increases with off-gas temperature at a given SR when the off-gas temperature is above 1500 K. High-concentration CO in off-gas can result in high NOx emissions, and NOx levels increase dramatically with CO concentration when off-gas temperature is above 1700 K. Both SR and off-gas temperature are important for the increase of CO burnout index (BICO) when SR is less than 1.0, but BICO increase about 1% when off-gas temperature increases from 1100 K to 1900 K at SR > 1.0. BICO increases with CO concentration in off-gas, and the influence of off-gas temperature on BICO is marginal. BICO increases with the relative humidity (RH) in air supplied, but it increases about 0.5% when RH is larger than 30%. (author)

  9. Performance testing of ultrasound Doppler equipment

    OpenAIRE

    Walker, Andrew

    2003-01-01

    Blood and tissue velocities are measured and analysed in cardiac, vascular and other applications of diagnostic ultrasound. Errors in system performance might give invalid measurements. We developed two moving string test targets (“Doppler phantoms”) to characterise ultrasound Doppler systems. These phantoms were initially used to measure such variables as sample volume dimensions, location of the sample volume, and the performance of the spectral analysis. Specific tests were done to det...

  10. Effect of encouragement on walking test performance.

    OpenAIRE

    Guyatt, G. H.; Pugsley, S O; Sullivan, M J; Thompson, P.J.; Berman, L.; Jones, N. L.; Fallen, E. L.; Taylor, D. W.

    1984-01-01

    Walking tests, frequently used to document effects of treatment on exercise capacity, have never been standardised. We studied the effects of encouragement on walking test performance in a randomised study that controlled for the nature of the underlying disease, time of day, and order effects. We randomised 43 patients with chronic airflow limitation or chronic heart failure or both to receive or not receive encouragement as they performed serial two and six minute walks every fortnight for ...

  11. Severe Pain Confounds Neuropsychological Test Performance*

    OpenAIRE

    Heyer, Eric J; Sharma, Ruchey; Winfree, Christopher J.; Mocco, J.; Donald J. McMahon; McCormick, Paul A.; Quest, Donald O.; McMurtry, James G.; Riedel, Charles J.; Lazar, Ronald M; Stern, Yaakov; Connolly, E Sander

    2000-01-01

    There is little information on the effect of pain on neuropsychological test performance. We have undertaken this study to explore which tests are affected by pain, the magnitude of these changes, and other confounders of neuropsychological performance in a population of patients having spine surgery. Twenty-four elderly English speaking Caucasian patients (age > 60 years) were enrolled pre-operatively in this Institutional Review Board approved study. Pain scores using an 11-point Numeric Pa...

  12. Novel sorbent development and evaluation for the capture of krypton and xenon from nuclear fuel reprocessing off-gas stream

    International Nuclear Information System (INIS)

    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, Idaho National Laboratory 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. (authors)

  13. 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.

  14. 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.

  15. Predicting edge seal performance from accelerated testing

    Science.gov (United States)

    Hardikar, Kedar; Vitkavage, Dan; Saproo, Ajay; Krajewski, Todd

    2014-10-01

    Degradation in performance of a PV module attributable to moisture ingress has received significant attention in PV reliability research. Assessment of field performance of PV modules against moisture ingress through product-level testing in temperature-humidity control chambers poses challenges. Development of a meaningful acceleration factor model is challenging due to different rates of degradation of components embedded in a PV module, when exposed to moisture. Test results are typically a convolution of moisture barrier performance of the edge seal and degradation of laminated components when exposed to moisture. It is desirable to have an alternate method by which moisture barrier performance of the edge seal in its end product form can be assessed in any given field conditions, independent of particular cell design. In this work, a relatively inexpensive test technique was developed to test the edge seal in its end product form in a manner that is decoupled from other components of the PV module. A theoretical framework was developed to assess moisture barrier performance of edge seal with desiccants subjected to different conditions. This framework enables the analysis of test results from accelerated tests and prediction of the field performance of the edge seal. Results from this study lead to the conclusion that the edge seal on certain Miasole glass-glass modules studied is effective for the most aggressive weather conditions examined, beyond the intended service.

  16. RHIC sextant test: Accelerator systems and performance

    International Nuclear Information System (INIS)

    One sextant of the RHIC Collider was commissioned in early 1997 with beam. We describe here the performance of the accelerator systems, instrumentation subsystems and application software. We also describe a ramping test without beam that took place after the commissioning with beam. Finally, we analyze the implications of accelerator systems performance and their impact on the planning for RHIC installation and commissioning

  17. Performance testing of distributed components architecture

    OpenAIRE

    Denaro, Giovanni; Polini, Andrea; Emmerich, Wolfgang

    2004-01-01

    Performance characteristics, such as response time, throughput, and scalability, are key quality attributes of distributed applications. Current practice,however, rarely applies systematic techniques to evaluate performance characteristics. We argue that evaluation of performance is particularly crucial in early development stages, when important architectural choices are made. At first glance, this contradicts the use of testing techniques, which are usually applied toward the end of a proje...

  18. In situ vitrification pilot-scale radioactive test

    International Nuclear Information System (INIS)

    Pacific Northwest Laboratory (PNL) is developing in situ vitrification (ISV) as an in-place stabilization technique for selected liquid radioactive waste disposal sites. The process melts the wastes and surrounding soil to produce a durable glass and crystalline waste form. These ISV process development testing and evaluation studies are being conducted for the US Department of Energy. The results of an ISV pilot-scale test conducted in June of 1983 in which soils contaminated with actual radioactive transuranic and mixed fission product elements were vitrified are discussed. The primary objectives of the radioactive test were to: demonstrate containment and confinement of the radioactive material; verify equipment performance of the power and off-gas systems; identify losses to the off-gas system; and characterize the behavior of the radioactive material in the vitrified soil. The test successfully demonstrated the processing containment of radionuclides both within the vitrified mass and in the off-gas system. No environmental release of radioactive material was measured during testing operations. The vitrified soil had a greater than 99% retention of all radionuclides. Losses to the off-gas system varied from less than or equal to 0.03% for particulate materials (plutonium and strontium) to 0.8% for cesium which is a more volatile element. The off-gas system effectively contained both volatile and entrained radioactive materials. Analysis of the vitrified soil revealed that all radionuclides were distributed throughout the vitrified zone, some more uniformly than others. No migration of radionuclides outside the vitrification zone occurred, as indicated by analysis of soil samples from around the block. Previous waste form leaching studies indicate an acceptable durability of the ISV product. 8 references, 34 figures, 8 tables

  19. AMTEC RC-10 Performance Evaluation Test Program

    Science.gov (United States)

    Schuller, Michael; Reiners, Elinor; Lemire, Robert; Sievers, Robert

    1994-07-01

    The Phillips Laboratory Power and Thermal Management Division (PL/VTP), in conjunction with ORION International Technologies, initiated the Alkali Metal Thermal to Electric Conversion (AMTEC), Remote Condensed-10% efficient (RC-10) Performance Evaluation Test Program to investigate cell design variations intended to increase efficiency in AMTEC cells. The RC-10 cell, fabricated by Advanced Modular Power Systems, uses a remote condensing region to reduce radiative heat losses from the electrode. The cell has operated at 10% efficiency. PL/VTP tested the RC-10 to evaluate its performance and efficiency. The impact of temperature variations along the length of the cell wall on performance were evaluated. Testing was performed in air, with a `` guard heater'' surrounding the cell to simulate the system environment of the cell.

  20. Development of turbopump cavitation performance test facility and the test of inducer performance

    International Nuclear Information System (INIS)

    A performance test facility for turbopump inducer cavitation was developed and the inducer cavitation performance tests were performed. Major components of the performance test facility are driving unit, test section, piping, water tank, and data acquisition and control system. The maximum of testing capability of this facility are as follows: flow rate - 30kg/s; pressure - 13 bar, rotational speed - 10,000rpm. This cavitation test facility is characterized by the booster pump installed at the outlet of the pump that extends the flow rate range, and by the pressure control system that makes the line pressure down to vapor pressure. The vacuum pump is used for removing the dissolved air in the water as well as the line pressure. Performance tests were carried out and preliminary data of test model inducer were obtained. The cavitation performance test and cavitation bubble flow visualization were also made. This facility is originally designed for turbopump inducer performance test and cavitation test. However it can be applied to the pump impeller performance test in the future with little modification

  1. Performance tests of the ITER model pump

    International Nuclear Information System (INIS)

    To study the pump performance of a sorption cryopump intended for use within the ITER fuel cycle, the test facility TIMO 'Test facility for the ITER Model pump' was built at the Forschungszentrum Karlsruhe. After the successful acceptance tests of the model pump in 2000, new components were installed to improve the cooling performance. At the end of the reconstruction activities, the tests with the model pump were continued. During these new test series, all important aspects regarding the changed requirements of the new ITER design were to be checked, such as the pump behavior at high throughputs, the capacities achievable at temperatures higher than 5 K, and the possibility of using the torus cryopumps for the examination of small helium leaks

  2. NNWSI waste form performance test development

    International Nuclear Information System (INIS)

    A test method has been developed to measure the release of radionuclides from the waste package under simulated NNWSI repository conditions, and to provide information concerning materials interactions that may occur in the repository. Data from 13 weeks of unsaturated testing are discussed and compared to that from a 13-week analog test. The data indicate that the waste form test is capable of producing consistent, reproducible results that will be useful in evaluating the role of the waste in the long-term performance of the repository. 6 references, 3 figures

  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. Decomposition of volatile organic compounds and polycyclic aromatic hydrocarbons in industrial off-gas by electron beams: A review

    International Nuclear Information System (INIS)

    The electron beam induced decomposition of volatile organic compounds (e.g. aromatic compounds, esters, chlorinated hydrocarbons) and polycyclic aromatic hydrocarbons (e.g. chlorinated dibenzo-dioxins) in industrial off gas has been investigated by several research groups in Germany and Japan. The method was shown to be effective for cleaning the waste gas of a paint factory, the waste air discharged from an automobile tunnel, the off gas cleaning from a groundwater remediation plant and the flue gas of a waste incinerator. The electron beam process achieves high removal efficiencies for volatile organic compounds. Reaction models have been developed, which suggest that the organic compounds are oxidized by hydroxyl radicals. The electron beam process may treat very large off-gas volumes at ambient temperatures and has a low energy consumption. The production of secondary wastes can be avoided or minimized. Compared to conventional methods the investment and operation costs of the process seem to be attractive for selected applications

  5. Preliminary test conditions for KNGR SBLOCA DVI ECCS performance test

    International Nuclear Information System (INIS)

    The Korean Next Generation Reactor (KNGR) adopts 4-train Direct Vessel Injection (DVI) configuration and injects the safety injection water directly into the downcomer through the 8.5'' DVI nozzle. Thus, the thermal hydraulic phenomena such as ECCS mixing and bypass are expected to be different from those observed in the cold leg injection. In order to investigate the realistic injection phenomena and modify the analysis code developed in the basis of cold leg injection, thermal hydraulic test with the performance evaluation is required. Preliminarily, the sequence of events and major thermal hydraulic phenomena during the small break LOCA for KNGR are identified from the analysis results calculated by the CEFLASH-4AS/REM. It is shown from the analysis results that the major transient behaviors including the core mixture level are largely affected by the downcomer modeling. Therefore, to investigate the proper thermal hydraulic phenomena occurring in the downcomer with limited budget and time, the separate effects test focusing on this region is considered to be effective and the conceptual test facility based on this recommended. For this test facility the test initial and boundary conditions are developed using the CEFLASH-4AS/REM analysis results that will be used as input for the preliminary test requirements. The final test requirements will be developed through the further discussions with the test performance group. (Author). 10 refs., 18 tabs., 4 figs

  6. Data quality objectives summary report for the 105-N monolith off-gas issue

    International Nuclear Information System (INIS)

    The 105-N Basin hardware waste with radiation exposure rates high enough to make above-water handling and packaging impractical has been designated high exposure rate hardware (HERH) waste. This material, consisting primarily of irradiated reactor components, is packaged underwater for subsequent disposal as a grout-encapsulated solid monolith. The third HERH waste package that was created (Monolith No. 3) was not immediately removed from the basin because of administrative delays. During a routine facility walkdown, Monolith No. 3 was observed to be emitting bubbles. Mass spectroscopic analysis of a gas sample from Monolith No. 3 indicated that the gas was 85.2% hydrogen along with a trace of fission gases (stable isotopes of xenon). Gamma energy analysis of a gas sample from Monolith No. 3 also identified trace quantities of 85Kr. The monolith off-gas Data Quality Objective (DQO) process concluded the following: Monolith No. 3 and similar monoliths can be safely transported following installation of spacers between the lids of the L3-181 transport cask to vent the hydrogen gas; The 85Kr does not challenge personnel or environmental safety; Fumaroles in the surface of gassing monoliths renders them incompatible with Hanford Site Solid Waste Acceptance Criteria requirements unless placed in a qualified high integrity container overpack; and Gassing monoliths do meet Environmental Restoration Disposal Facility Waste Acceptance Criteria requirements. This DQO Summary Report is both an account of the Monolith Off-Gas DQO Process and a means of documenting the concurrence of each of the stakeholder organizations

  7. Performance of a large-scale melter off-gas system utilizing simulated SRP DWPF waste

    International Nuclear Information System (INIS)

    The Department of Energy and the DuPont Company have begun construction of a Defense Waste Processing Facility to immobilize radioactive waste now stored as liquids at the Department of Energy's Savannah River Plant. The immobilization process solidifies waste sludge by vitrification into a leach-resistant borosilicate glass. Development of the process has been the responsibility of the Savannah River Laboratory. As part of the development, two large-scale glass melter systems have been designed and operated with simulated waste. Experimental data from these operations show that process requirements will be met. 6 references, 8 figures, 4 tables

  8. Thermal Performance Testing of Cryogenic Insulation Systems

    Science.gov (United States)

    Fesmire, James E.; Augustynowicz, Stan D.; Scholtens, Brekke E.

    2007-01-01

    Efficient methods for characterizing thermal performance of materials under cryogenic and vacuum conditions have been developed. These methods provide thermal conductivity data on materials under actual-use conditions and are complementary to established methods. The actual-use environment of full temperature difference in combination with vacuum-pressure is essential for understanding insulation system performance. Test articles include solids, foams, powders, layered blankets, composite panels, and other materials. Test methodology and apparatus design for several insulation test cryostats are discussed. The measurement principle is liquid nitrogen boil-off calorimetry. Heat flux capability ranges from approximately 0.5 to 500 watts per square meter; corresponding apparent thermal conductivity values range from below 0.01 up to about 60 mW/m- K. Example data for different insulation materials are also presented. Upon further standardization work, these patented insulation test cryostats can be available to industry for a wide range of practical applications.

  9. Estimating skimmer performance using controlled test data

    International Nuclear Information System (INIS)

    In the early 1990s the ASTM F20 Committee on Hazardous Substances and Oil Spill Response began a major effort to upgrade existing standards on oil spill response and to develop new ones that would support the Oil Pollution Act of 1990. More than 20 new standards were developed and many existing standards were revised. One of the most significant revisions was the requirement to estimate the potential performance level of various kinds of skimmers used in the event of oil spills. The ASTM F20 Committee authorized the preparation of the 200 page guide entitled 'Oil Spill Response Performance Review of Skimmers'. The guide reviews all available test reports for any skimmer type based on test results. Data in the review indicates where more research and development is needed to estimate the performance of skimmer types in certain environments. The factors affecting skimmer performance include: (1) oil type, condition and viscosity, (2) effects of waves and currents, and (3) slick thickness

  10. Testing prospect theory in students’ performance

    OpenAIRE

    Pérez Galdón, Patricia; Nicolau Gonzálbez, Juan Luis

    2013-01-01

    This paper tests the existence of ‘reference dependence’ and ‘loss aversion’ in students’ academic performance. Accordingly, achieving a worse than expected academic performance would have a much stronger effect on students’ (dis)satisfaction than obtaining a better than expected grade. Although loss aversion is a well-established finding, some authors have demonstrated that it can be moderated – diminished, to be precise–. Within this line of research, we also examine whether the students’ e...

  11. Load responsive multilayer insulation performance testing

    Science.gov (United States)

    Dye, S.; Kopelove, A.; Mills, G. L.

    2014-01-01

    Cryogenic insulation designed to operate at various pressures from one atmosphere to vacuum, with high thermal performance and light weight, is needed for cryogenically fueled space launch vehicles and aircraft. Multilayer insulation (MLI) performs well in a high vacuum, but the required vacuum shell for use in the atmosphere is heavy. Spray-on foam insulation (SOFI) is often used in these systems because of its light weight, but can have a higher heat flux than desired. We report on the continued development of Load Responsive Multilayer Insulation (LRMLI), an advanced thermal insulation system that uses dynamic beam discrete spacers that provide high thermal performance both in atmosphere and vacuum. LRMLI consists of layers of thermal radiation barriers separated and supported by micromolded polymer spacers. The spacers have low thermal conductance, and self-support a thin, lightweight vacuum shell that provides internal high vacuum in the insulation. The dynamic load responsive spacers compress to support the external load of a vacuum shell in one atmosphere, and decompress under reduced atmospheric pressure for lower heat leak. Structural load testing was performed on the spacers with various configurations. LRMLI was installed on a 400 liter tank and boil off testing with liquid nitrogen performed at various chamber pressures from one atmosphere to high vacuum. Testing was also performed with an MLI blanket on the outside of the LRMLI.

  12. Load responsive multilayer insulation performance testing

    International Nuclear Information System (INIS)

    Cryogenic insulation designed to operate at various pressures from one atmosphere to vacuum, with high thermal performance and light weight, is needed for cryogenically fueled space launch vehicles and aircraft. Multilayer insulation (MLI) performs well in a high vacuum, but the required vacuum shell for use in the atmosphere is heavy. Spray-on foam insulation (SOFI) is often used in these systems because of its light weight, but can have a higher heat flux than desired. We report on the continued development of Load Responsive Multilayer Insulation (LRMLI), an advanced thermal insulation system that uses dynamic beam discrete spacers that provide high thermal performance both in atmosphere and vacuum. LRMLI consists of layers of thermal radiation barriers separated and supported by micromolded polymer spacers. The spacers have low thermal conductance, and self-support a thin, lightweight vacuum shell that provides internal high vacuum in the insulation. The dynamic load responsive spacers compress to support the external load of a vacuum shell in one atmosphere, and decompress under reduced atmospheric pressure for lower heat leak. Structural load testing was performed on the spacers with various configurations. LRMLI was installed on a 400 liter tank and boil off testing with liquid nitrogen performed at various chamber pressures from one atmosphere to high vacuum. Testing was also performed with an MLI blanket on the outside of the LRMLI

  13. Testing stemming performance, possible or not?

    Scientific Electronic Library Online (English)

    D., Boshoff; R.C.W., Webber-Youngman.

    2011-12-01

    Full Text Available The ability of an explosive to break rock is influenced considerably by the extent of confinement in the blasthole. It is believed that confinement is improved by the use of adequate stemming. The aim of this paper is to present the results of the first and second stages of developing a stemming per [...] formance testing rig for small diameter boreholes. The rig was used to compare and contrast the performance of different designs of products. The results showed that different stemming products have differences in terms of their functionality, which can have a major impact on the efficiency of rock breaking. Two test procedures were used, one through the exclusive use of compressed air and the second using a purposebuilt high pressure test rig with small quantities of explosives. Both tests were used to identify and evaluate the ability of various stemming products to resist the escape of explosive gas through the collar of a blasthole. An investigation was done to determine the types of stemming products most commonly used in South African underground hard rock mines, and these products were used during the tests. The first stage of tests using compressed air only did not prove adequate to predict with certainty the pressure behaviour in the borehole of a particular product under high pressure conditions. The purpose-built high pressure test rig also did not prove to be a very effective tool to test stemming products under high pressure conditions. The test rig incorporated only the effect of gas pressure on the stemming product, and excluded the effect of the shock wave. This study therefore proved that to take into account only the gas pressure generated in the blasthole is not sufficient to effectively test stemming product performance.

  14. TESTING AND REPORTING SOLAR COOKER PERFORMANCE

    Science.gov (United States)

    This Standard for quantifying solar cooker performance specifies that test results be presented as cooking power, in Watts, normalized for ambient conditions, relative to the temperature difference betweeen cooker contents and ambient air, both as a plot and as a regression equation for no less than...

  15. Performance tests for integral reactor nuclear fuel

    International Nuclear Information System (INIS)

    An integral type reactor SMART plans to utilize metallic Zr-U fuel which is Zr-based alloy with 34?38 wt% U. In order to verify the technologies for the design and manufacturing of the fuel and get a license, performance tests were carried out. Experimental Fuel Assembly (EFA) manufactured in KAERI is being successfully irradiated in the MIR reactor of RIAR from September 4 2004, and it has achieved burnup of 0.21 g/cc as of January 25 2006. Thermal properties of irradiated Zr-U fuel were measured. Up to the phase transformation temperature, thermal diffusivity increased linearly in proportion to temperature. However its dependence on the burnup was not significant. RIA tests with 4 unirradiated Zr-U fuel rods were performed in Kurchatov Institute to establish a safety criterion. In the case of the un-irradiated Zr-U fuel, the energy deposition during the control rod ejection accident should be less than 172 cal/g to prevent the failure accompanying fuel fragmentation and dispersal. Finally the irradiation tests of fuel rods have been performed at HANARO. The HITE-2 test was successfully completed up to a burnup of 0.31 g/cc. The HITE-3 test began in February 2004 and will be continued up to a target burnup of 0.6 g/cc

  16. Performance testing rotating gamma camera SPECT systems

    International Nuclear Information System (INIS)

    A reasonably simple protocol for testing the performance of rotating gamma camera SPECT systems has been established, which could be performed in about 10 hours. This protocol has been used to test almost all currently available systems, including GE, Siemens, Technicare, Elscint, Phillips, CGR, etc. In general, several models of a given system were tested in order to give an indication of the range of results that might be obtained. Reconstructions were performed in a standard manner (Uniformity correction, Ramp filter, no attenuation correction) in order to try to eliminate the effect of differences in software. In addition to using the Jaszczak phantom as an overall test pattern, measurements were made of spatial resolution, energy resolution, contrast, variations of sensitivity and uniformity with angle, etc. Results indicated that some systems, with a high resolution collimator and after very careful setting up, could achieve a spatial resolution of the order of 11mm, with good image quality. Not all commercially available systems performed as well. Strong indication was given of the need to improve spatial resolution, even at the expense of sensitivity, confirming the results from simulated tomographic data for various design compromises. Tests were also performed varying the energy window used. It was found that only very few system were capable of producing artefact free images with other than a symmetric photopeak window. However, very significant improvementdow. However, very significant improvement of image quality of current systems with respect to older systems were noted. This protocol has been used, in addition, to establish a routine quality assurance program for such SPECT systems

  17. Off-gas characteristics of defense waste vitrification using liquid-fed Joule-heated ceramic melters

    International Nuclear Information System (INIS)

    Off-gas and effluent characterization studies have been established as part of a PNL Liquid-Fed Ceramic Melter development program supporting the Savannah River Laboratory Defense Waste Processing Facility (SRL-DWPF). The objectives of these studies were to characterize the gaseous and airborne emission properties of liquid-fed joule-heated melters as a function of melter operational parameters and feed composition. All areas of off-gas interest and concern including effluent characterization, emission control, flow rate behavior and corrosion effects have been studied using alkaline and formic-acid based feed compositions. In addition, the behavioral patterns of gaseous emissions, the characteristics of melter-generated aerosols and the nature and magnitude of melter effluent losses have been established under a variety of feeding conditions with and without the use of auxiliary plenum heaters. The results of these studies have shown that particulate emissions are responsible for most radiologically important melter effluent losses. Melter-generated gases have been found to be potentially flammable as well as corrosive. Hydrogen and carbon monoxide present the greatest flammability hazard of the combustibles produced. Melter emissions of acidic volatile compounds of sulfur and the halogens have been responsible for extensive corrosion observed in melter plenums and in associated off-gas lines and processing equipment. The use of auxiliary plenum heating has had little effect upon melter off-gas characteristics other than reducing the concentrations of combustibles

  18. MFTF test coil construction and performance

    International Nuclear Information System (INIS)

    A solenoid coil, 105 cm inside the 167 cm outside diameter, has been constructed and tested to study the performance of the stabilized Nb--Ti conductor to be used in the Mirror Fusion Test Facility (MFTF) being built at Lawrence Livermore Laboratory. The insulation system of the test coil is identical to that envisioned for MFTF. Cold-weld joints were made in the conductor at the start and finish of each layer; heaters were fitted to some of these joints and also to the conductor at various locations in the winding. This paper gives details of the construction of the coil and the results of the tests carried out to determine its propagation and recovery characteristics

  19. Leaching of the residue from the dry off-gas de-dusting and desulfurization process of an iron ore sinter plant

    Science.gov (United States)

    Lanzerstorfer, Christof; Xu, Qi; Neuhold, Robert

    2015-02-01

    The residue from a second-stage dry sinter plant off-gas cleaning process contains both the fine dust from the sinter plant and the sorbent used. Recycling of the material that is usually handled by landfills to the sinter plant feed is not possible because of its chloride content. Leaching of the chlorides allow the recycling of remaining solids. The saline leachate produced contains some heavy metals and must be treated before it is discharged into the sea. In laboratory experiments, leaching tests with the subsequent treatment of the leachate were conducted. After the process was optimized, all heavy-metal concentrations were below the permissible values. The optimum treatment conditions for heavy-metal precipitation were observed to be the filtration of the suspended solids followed by the dosing of liquid with lime milk (pH 10) and the subsequent precipitation using sodium sulfide.

  20. Performance Test of CCTV in a Test Field

    International Nuclear Information System (INIS)

    On April 12-13, 2010, US President Obama hosted a Nuclear Security Summit in Washington, DC, to enhance international cooperation to prevent nuclear terrorism, an issue which he has identified as the most immediate and extreme threat to global security. The Summit focused on the security of nuclear materials, nonproliferation, disarmament, and peaceful nuclear energy. At the summit, the Republic of Korea was chosen as the host of the next Summit in 2012. This series of events reflects the growing global interest on 'Nuclear Security' and as the host country of the next Nuclear Summit it is the time for Korea to strengthen the physical protection regime for nuclear facilities as a first step of securing its nuclear security capability. KINAC has been operating Test field as a mean of preparing solid backup data for reviewing and revising DBT (Design Basis Threat) and to test components of the conventional physical protection system. CCTV is a key component which is used worldwide for the assessment measure of alarms. In terms of performance test of CCTV, there are several elements such as image quality, coverage and mechanical features (speed of zoom-in-out, capture, angle shift etc.). Speaking of image quality acquired by the CCTV, the quality is subject to resolution, monitor specification, camera housing, camera mounting and lightening. Thus it is clear that performance tests on image quality should consider those factors and vary the factors respectively in order td vary the factors respectively in order to verify the influence and the interaction among those. Nevertheless due to the restrictions of the current Test field, this paper focuses on the image quality through resolution test under the various lightening conditions

  1. Performance Test of CCTV in a Test Field

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Hyung Min [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2011-10-15

    On April 12-13, 2010, US President Obama hosted a Nuclear Security Summit in Washington, DC, to enhance international cooperation to prevent nuclear terrorism, an issue which he has identified as the most immediate and extreme threat to global security. The Summit focused on the security of nuclear materials, nonproliferation, disarmament, and peaceful nuclear energy. At the summit, the Republic of Korea was chosen as the host of the next Summit in 2012. This series of events reflects the growing global interest on 'Nuclear Security' and as the host country of the next Nuclear Summit it is the time for Korea to strengthen the physical protection regime for nuclear facilities as a first step of securing its nuclear security capability. KINAC has been operating Test field as a mean of preparing solid backup data for reviewing and revising DBT (Design Basis Threat) and to test components of the conventional physical protection system. CCTV is a key component which is used worldwide for the assessment measure of alarms. In terms of performance test of CCTV, there are several elements such as image quality, coverage and mechanical features (speed of zoom-in-out, capture, angle shift etc.). Speaking of image quality acquired by the CCTV, the quality is subject to resolution, monitor specification, camera housing, camera mounting and lightening. Thus it is clear that performance tests on image quality should consider those factors and vary the factors respectively in order to verify the influence and the interaction among those. Nevertheless due to the restrictions of the current Test field, this paper focuses on the image quality through resolution test under the various lightening conditions

  2. HSE performance tests for dosimetry services

    International Nuclear Information System (INIS)

    In the United Kingdom a dosimetry service that measures and assesses whole-body or part-body doses arising from external radiation must successfully complete a performance test. Results of the performance tests for routine whole-body, routine extremity/skin and special accident dosimetry, carried out over the past six years by the AEA Technology Calibration Service at Winfrith, and DRaStaC, the AWE Calibration Service at Aldermaston, are presented. The test involves irradiating groups of dosemeters to known doses of gamma radiation and determining the bias and relative standard deviations for each dose group. The results are compared with the pass criteria specified by the UK Health and Safety Executive. For routine whole-body dosimetry, both the film badge and thermoluminescent dosemeter (TLD) perform adequately for irradiations between 0.6 and 30 mSv. For higher doses up to 250 mSv, where the slow emulsion of the film is used, the film badge shows poorer performance with a tendency to overestimate the dose. For routine extremity/skin dosimetry there is a wider spread of relative standard deviation results than is seen for routine whole-body dosimetry. This is to be expected since the results will include dosemeters that are based on 'disposable' TLDs and ones based on lithium fluoride powder in sachets. For special accident dosimetry the dosemeters are tested between 0.26 and 6 Gy. For the highest dose group the film badge invariably underestimates the true dose, whnvariably underestimates the true dose, whereas the TLD has a tendency to overestimate it. (author)

  3. Performance testing of large metallic seals

    International Nuclear Information System (INIS)

    Containment of radioactive material in spent fuel shipping casks can be achieved if the internal cavity pressure boundary is kept intact under both normal and accident conditions. The major potential boundary weakness is the seal used for cask closure. In an effort to evaluate parameters which influence closure seal performance, an experimental program has been undertaken. This paper describes the program, early results, and test hardware

  4. Testing Devices Garner Data on Insulation Performance

    Science.gov (United States)

    2014-01-01

    To develop a test instrument that could garner measurements of the thermal performance of insulation under extreme conditions, researchers at Kennedy Space Center devised the Cryostat 1 and then Cryostat 2. McLean, Virginia-based QinetiQ North America licensed the technology and plans to market it to organizations developing materials for things like piping and storage tank insulation, refrigeration, appliances, and consumer goods.

  5. Performance tests on the NRPB thermoluminescent dosemeter

    CERN Document Server

    Shaw, K B

    1977-01-01

    Performance tests on the thermoluminescent dosemeter, designed at NRPB for use in the automated personal dosimetry system, are described. An ultra-thin lithium borate dosemeter has been developed for skin absorbed dose measurement. The X-ray, gamma-ray and beta-ray energy response of the dosemeter has been investigated and the angular response for the dosemeter has been examined. The annealing, read-out and stabilisation procedures for the dosemeter are described.

  6. Flow rate measuring method for radioactive off gas in local exhaustion facility

    International Nuclear Information System (INIS)

    In the inside of an exhaustion duct extending horizontally for flowing radioactive off-gas, a baffle plate having a size substantially covering the cross section of the duct is pivoted at the upper end thereof by means of a rotational shaft. The baffle plate is thus pivoted to the duct in a state where in can incline in the radial direction of the cross section of the duct around the rotational shaft. An indication pointer is secured to the upper end of the baffle plate penetrating a duct wall, and the pointer is tiltable together with the baffle plate around the rotational axis as a fulcrum. A display plate having gradients showing a relation between the inclination of the indication pointer and the flow rate in the duct is disposed at the back of the display pointer. When gas flows in the duct, buoyancy is caused to the baffle plate in accordance with the flow rate of the gas, whereby the baffle plate is inclined to display the flow rate corresponding to the indication pointer. (I.N.)

  7. Retrofit design of a boil-off gas handling process in liquefied natural gas receiving terminals

    International Nuclear Information System (INIS)

    Generation of Boil-off gas (BOG) in liquefied natural gas (LNG) receiving terminals considerably affects operating costs and the safety of the facility. For the above reasons, a proper BOG handling process is a major determinant in the design of a LNG receiving terminal. This study proposes the concept of a retrofit design for a BOG the handling process using a fundamental analysis. A base design was determined for a minimum send-out case in which the BOG handling becomes the most difficult. In the proposed design, the cryogenic energy of the LNG stream is used to cool other streams inside the process. It leads to a reduction in the operating costs of the compressors in the BOG handling process. Design variables of the retrofit design were optimized with non-linear programming to maximize profitability. Optimization results were compared with the base design to show the effect of the proposed design. The proposed design provides a 22.7% energy saving ratio and a 0.176 year payback period. -- Highlights: ? A retrofit design of the BOG handling process was proposed to maximize energy savings. ? The superstructure of the proposed design was developed based on a thermodynamic analysis. ? In the proposed design, the cryogenic energy of the LNG stream was utilized to directly cool down the BOG streams. ? The payback period of the proposed design is sufficiently short for investment in industry.

  8. Excess-air incineration with high temperature filtering for efficient off-gas cleaning

    International Nuclear Information System (INIS)

    When SGN started work on volume reduction of low-level and intermediate-level radioactive wastes in the early 1960s, in collaboration with the French Atomic Energy Commission (CEA), incineration was relatively undeveloped but its potential efficiency was immediately recognized. The incinerators then available divided more or less into proven designs used in municipal refuse incineration and so-called advanced systems: SGN's initial impression was that systems for municipal refuse incineration could be readily adapted to handle combustible nuclear wastes. These systems mainly employed excess-air fixed-bed combustion, rotary furnaces or fluidized-bed combustion, sometimes with partial or total pyrolysis. The ''advanced'' systems proposed by various inventors were far more sophisticated but, due to a lack of industrial experience, were often designed with inadequate regard to human safety. The result was a number of serious accidents, including some deaths. Nuclear-grade incineration was a rather esoteric subject at the time. Standard incinerators were not designed to handle radioactive wastes. They lacked essential safety features (e.g. leaktightness) and did not provide for repair and maintenance after contamination nor for affordable dismantling at end of life. Off-gas cleaning had neither the efficiency nor safety required in the nuclear industry. Extensive automation of control and monitoring was not envisaged, because unnecessary in traditional applicationsessary in traditional applications

  9. Multi-level computational chemistry study on hydrogen recombination catalyst of off-gas treatment system

    International Nuclear Information System (INIS)

    In order to reveal the deactivation mechanism of the hydrogen recombination catalyst of off-gas treatment system, we investigate by using multi-level computational chemistry simulation methods. The recombiner apparatus is modeled by the numerical mesh system in the axial coordinates, and unsteady, advection and reaction rate equations are solved by using a finite difference method. The chemical reactions are formulated to represent adsorption-desorption of hydrogen and oxygen on Pt catalyst, and time developments of the coverage factors of Pt are solved numerically. The computational simulations successfully reproduce the very similar behaviors observed by experiments, such as increasing of the inversion rates of H2 to H2O, the temperatures distributions along the flow direction, dependencies of experimental condition, and so on. Thus Pt poisoning is considered to cause the deactivation of the hydrogen recombination catalyst. To clarify the poisoning mechanism, the molecular level simulation is applied to the system of Pt on boehmite attacked by a cyclic siloxane which has been detected by experiments and considered as one of poisoning spices. The simulation shows ring-opening reaction of the cyclic siloxane on Pt, then attachment of two ends of the chain-like siloxane to Pt and boehmite, respectively, and that finally the recombination reaction is prevented. This may be the first study to find out the detailed dynamical mechanism of hydrogen rectailed dynamical mechanism of hydrogen recombination catalyst poisoning with cyclic siloxane. (author)

  10. Modeling The Impact Of Elevated Mercury In Defense Waste Processing Facility Melter Feed On The Melter Off-Gas System - Preliminary Report

    International Nuclear Information System (INIS)

    The Defense Waste Processing Facility (DWPF) is currently evaluating an alternative Chemical Process Cell (CPC) flowsheet to increase throughput. It includes removal of the steam-stripping step, which would significantly reduce the CPC processing time and lessen the sampling needs. However, its downside would be to send 100% of the mercury that come in with the sludge straight to the melter. For example, the new mercury content in the Sludge Batch 5 (SB5) melter feed is projected to be 25 times higher than that in the SB4 with nominal steam stripping of mercury. This task was initiated to study the impact of the worst-case scenario of zero-mercury-removal in the CPC on the DWPF melter off-gas system. It is stressed that this study is intended to be scoping in nature, so the results presented in this report are preliminary. In order to study the impact of elevated mercury levels in the feed, it is necessary to be able to predict how mercury would speciate in the melter exhaust under varying melter operating conditions. A homogeneous gas-phase oxidation model of mercury by chloride was developed to do just that. The model contains two critical parameters pertaining to the partitioning of chloride among HCl, Cl, Cl2, and chloride salts in the melter vapor space. The values for these parameters were determined at two different melter vapor space temperatures by matching the calculated molar ratio of HgCl (or Hg2Cl2) to HgCl2 witub>Cl2) to HgCl2 with those measured during the Experimental-Scale Ceramic Melter (ESCM) tests run at the Pacific Northwest National Laboratory (PNNL). The calibrated model was then applied to the SB5 simulant used in the earlier flowsheet study with an assumed mercury stripping efficiency of zero; the molar ratio of Cl-to-Hg in the resulting melter feed was only 0.4, compared to 12 for the ESCM feeds. The results of the model run at the indicated melter vapor space temperature of 650 C (TI4085D) showed that due to excessive shortage of chloride, only 6% of the mercury fed is expected to get oxidized, mostly as HgCl, while the remaining mercury would exist either as elemental mercury vapor (90%) or HgO (4%). Noting that the measured chloride level in the SB5 qualification sample was an order of magnitude lower than that used in the SB5 simulant, the degree of chloride shortage will be even greater. As a result, the projected level of HgCl in the actual SB5 melter exhaust will be even lower than 6% of the total mercury fed, while that of elemental mercury is likely to be greater than 90%. The homogeneous oxidation of mercury in the off-gas was deemed to be of primary importance based on the postulation that mercury and other volatile salts form submicron sized aerosols upon condensation and thus remain largely in the gas stream downstream of the quencher where they can deposit in the off-gas lines, Steam-Atomized Scrubbers (SAS), and High-Efficiency Mist Eliminator (HEME). Formation of these submicron semi-volatile salts in the condensate liquid is considered to be unlikely, so the liquid phase reactions were considered to be less important. However, subsequent oxidation of mercury in the liquid phase in the off-gas system was examined in a simplified model of the off-gas condensate. It was found that the condensate chemistry was consistent with further oxidation of elemental mercury to Hg2Cl2 and conversion of HgO to chlorides. The results were consistent with the available experimental data. It should also be noted that the model predictions presented in this report do not include any physically entrained solids, which typically account for much of the off-gas carryover on a mass basis. The high elemental mercury vapor content predicted at the DWPF Quencher inlet means that physically entrained solids could provide the necessary surface onto which elemental mercury vapor could condense, thereby coating the solids as well as the internal surfaces of the off-gas system with mercury. Clearly, there are many process benefits to be gained by removing the steam-stripping step from the CPC cycle. The goal o

  11. Heating facility for blanket and performance test

    International Nuclear Information System (INIS)

    A design and a fabrication of heating test facility for a mock-up of the blanket module to be installed in International Thermonuclear Experimental Reactor (ITER) have been conducted to evaluate/demonstrate its heat removal performance and structural soundness under cyclic heat loads. To simulate surface heat flux to the blanket module, infrared heating method is adopted so as to heat large surface area uniformly. The infrared heater is used in vacuum environment (10-4 Torr?), and the lamps are cooled by air flowing through an annulus between the lamp and a cover tube made of quartz glass. Elastomer O rings (available to be used up to ?300degC) and used for vacuum seal at outer surface of the cover tube. To prevent excessive heating of the O ring, the end part of the cover tube is specially designed including the tube shape, flow path of air and gold coating on the surface of the cover tube to protect the O ring against thermal radiation from glowing tungsten filament. To examine the performance of the facility, steady state and cyclic operation of the infrared heater were conducted using a small-scaled shielding blanket mock-up as a test specimen. The important results are as follows: (1) Heat flux at the surface of the small-scaled mock-up measured by a calorimeter was ?0.2 MW/m2. (2) A comparison of thermal analysis results and measured temperature responses showed that the small-scaled mock-up had good heat removal performance. (3) Steady state operation and cyclic operation with step response between the rated and zero powers of the infrared heater were successfully performed, and it was confirmed that this heating facility was well-prepared and available for the thermal cyclic test of a blanket module. (author)

  12. Performance Tests for Bubble Blockage Device

    International Nuclear Information System (INIS)

    Postulated severe core damage accidents have a high threat risk for the safety of human health and jeopardize the environment. Versatile measures have been suggested and applied to mitigate severe accidents in nuclear power plants. To improve the thermal margin for the severe accident measures in high-power reactors, engineered corium cooling systems involving boiling-induced two-phase natural circulation have been proposed for decay heat removal. A boiling-induced natural circulation flow is generated in a coolant path between a hot vessel wall and cold coolant reservoir. In general, it is possible for some bubbles to be entrained in the natural circulation loop. If some bubbles entrain in the liquid phase flow passage, flow instability may occur, that is, the natural circulation mass flow rate may be oscillated. A new device to block the entraining bubbles is proposed and verified using air-water test loop. To avoid bubbles entrained in the natural circulation flow loop, a new device was proposed and verified using an air-water test loop. The air injection and liquid circulation loop was prepared, and the tests for the bubble blockage devices were performed by varying the geometry and shape of the devices. The performance of the bubble blockage device was more effective as the area ratio of the inlet to the down-comer increased, and the device height decreased. If the device has a rim to generate a vortex zone, the bubbles will be most effectively blocked

  13. DPM PERFORMANCE TESTING USING RASPBERRY PIS

    CERN Document Server

    Regala, M

    2013-01-01

    This is the final report from attending CERN’s Summer Student Programme. The project goal was to do performance testing on the Disk Pool Manager (DPM), a lightweight, reliable, grid-aware storage software used to store and retrieve data produced by CERN’s LHC experiments using the small, low-end ARM powered devices named Raspberry Pis. The idea behind it was to reason if it’s possible to use a cluster of lower-end, under-capable devices to run DPM, and to conclude if it would be more energy efficient than running it on oversized machines, with the same or comparable performance. If this hypothesis was true, the power-hungry machines could be ditched in favour of these small devices, leading to an enormous saving in overall power consumption and hence, overall cost. In this report, I describe what was the initial project goal and intended outcomes, proceeding to explain the underlying technologies used. Afterwards, I’ll explain the setup used, the tests performed, and the conclusions reached. iii

  14. Performance testing of a hydrogen heat pipe

    International Nuclear Information System (INIS)

    Test results are presented for a reentrant groove heat pipe with hydrogen working fluid. The heat pipe became operational between 20 and 30 K after a cooldown from 77 K without any difficulty. Steady-state performance data taken over a 19 to 23 K temperature range indicated the following: (1) maximum heat transport capacity 5.4 W-m (2) static wicking height 1.42 cm and (3) overall heat pipe conductance 1.7 W/C. These data agreed remarkably well with extrapolations made from comparable ammonia test results. The maximum heat transport capacity is 9.5% larger than the extrapolated value, but the static wicking height is the same. The overall conductance is 29% of the ammonia value, which is close to the ratio of liquid thermal conductivities (24%). Also, recovery from a completely frozen condition was accomplished within 5 min by simply applying an evaporater heat load of 1.8 W

  15. Eurados trial performance test for photon dosimetry

    DEFF Research Database (Denmark)

    Stadtmann, H.; Bordy, J.M.

    2001-01-01

    Within the framework of the EURADOS Action entitled Harmonisation and Dosimetric Quality Assurance in Individual Monitoring for External Radiation, trial performance tests for whole-body and extremity personal dosemeters were carried out. Photon, beta and neutron dosemeters were considered. This paper summarises the results of the whole-body photon dosemeter test. Twenty-six dosimetry services from all EU Member States and Switzerland participated. Twelve different radiation fields were used to simulate various workplace irradiation fields. Dose values from 0.4 mSv to 80 mSv were chosen. From 312 single results, 26 fell outside the limits of the trumpet curve and 32 were outside the range 1/1.5 to 1.5. Most outliers resulted from high energy R-F irradiations without electronic equilibrium. These fields are not routinely encountered by many of the participating dosimetry services. If the results for this field are excluded, most participating services satisfied the evaluation criteria.

  16. Spent fuel metal storage cask performance testing and future spent fuel concrete module performance testing

    International Nuclear Information System (INIS)

    REA-2023 (currently marketed by Mitsubishi Heavy Metals of Japan as an MSF IV), Gesellshaft fur Nuklear Service (GNS) CASTOR-V/21, Transnuclear TN-24P, and Westinghouse MC-10 metal storage casks, have been performance tested under the guidance of the Pacific Northwest Laboratory to determine their thermal and shielding performance. The REA-2023 cask was tested under Department of Energy (DOE) sponsorship at General Electric's facilities in Morris, Illinois, using BWR spent fuel from the Cooper Reactor. The other three casks were tested under a cooperative agreement between Virginia Power Company and DOE at the Idaho National Engineering Laboratory (INEL) by EG and G Idaho, Inc. using intact spent PWR fuel from the Surry reactors. The Electric Power Research Institute (EPRI) made contributions to both programs. A summary of the various cask designs and the results of the performance tests is presented

  17. Krypton absorption in liquid CO2 (KALC): Campaign II in the Experimental Engineering Section Off-Gas Decontamination facility

    International Nuclear Information System (INIS)

    Results are presented for the second major campaign for quantifying krypton removal from simulated High-Temperature Gas-Cooled Reactor reprocessing off-gas by the KALC process. The Experimental Engineering Section Off-Gas Decontamination Facility used in the campaign provides engineering-scale experiments with nominal gas and liquid flows of 5 scfm and 0.5 gpm respectively. Equilibrium and nonequilibrium mass transfer experiments for the CO2--O2--Kr system are described, and a detailed discussion of the data analysis is included. The analysis, although not rigorous, is reasonable and indicates values of HTU for krypton on the order of 0.4 ft for decontamination factors from 100 to 10,000. Recent flooding information for the packed columns is combined with previous data and is shown to be well represented by an empirical flooding equation

  18. A laser-based sensor for measurement of off-gas composition and temperature in basic oxygen steelmaking

    International Nuclear Information System (INIS)

    We are developing an optical sensor for process control in basic oxygen steelmaking. The sensor measures gas temperature and relative CO/CO2 concentration ratios in the furnace off-gas by transmitting the laser probe beam directly above the furnace lip and below the exhaust hood during oxygen blowing. Dynamic off-gas information is being evaluated for optimizing variables such as lance height, oxygen flow, post-combustion control, and prediction of final melt-carbon content. The non-invasive nature of the optical sensor renders it robust and relatively maintenance-free. Additional potential applications of the method are process control for electric arc furnace and bottom-blown oxygen steelmaking processes. (author)

  19. Krypton absorption in liquid CO2 (KALC): Campaign III in the Experimental Engineering Section Off-Gas Decontamination Facility

    International Nuclear Information System (INIS)

    Results are presented for the third major campaign for quantifying krypton removal from simulated High-Temperature Gas-Cooled Reactor reprocessing off-gas by the KALC process. The Experimental Engineering Section Off-Gas Decontamination Facility used in the campaign provides engineering-scale experiments with nominal gas and liquid flows of 5 scfm and 0.5 gpm, respectively. Mass transfer experiments for the CO2--O2--Kr system are described for the absorption, fractionation, and stripping operations of the KALC process. A detailed discussion of the data analysis is included. The analysis indicates nominal HTU values for the absorber, fractionator, and stripper on the order of 0.4, 0.5, and 0.7 ft, respectively. Flooding data for the packed columns are combined with previous data and are shown to be well represented by an empirical flooding equation

  20. Systematic selection of off-gas treatment at the Savannah River Site

    International Nuclear Information System (INIS)

    At the Savannah River Site (SRS), from 1958--1985, effluent waste from the reactor fuel and target rod fabrication area (M-Area) was discharged to a settling basin. In 1981, monitoring wells detected groundwater contamination, specifically trichloroethylene and tetrachloroethylene, in the immediate vicinity of the basin. Under the auspices of Resource Conservation and Recovery Act (RCRA) the M-Area contamination must be addressed by a corrective action program until the volatile organic compound (VOC) concentrations reach Drinking Water Standards. This was initiated in 1985 with startup of a full-scale pump-and-treat air stripper system. Recently, remediation efforts have focused on vacuum extraction to treat vadose zone contamination not addressed by the original recovery wells, and additional pump-and-treat systems to achieve hydraulic control of the plume. Regulatory requirements allowed for discharge of VOCs to the atmosphere when the original remediation system was installed; however, 1990 amendments to the Clean Air Act will eventually require treatment of VOC contaminated air prior to discharge. This has ramifications to systems currently being design, as well as the existing systems. In response to the 1990 Clean Air Act amendments, SRS initiated a study to assess commercially available off-gas treatment technologies. These included carbon adsorption, thermal incineration, catalytic oxidation, absorption, condensation, and UV/peroxide destruction, and xenon flashlamp. Criteria used to evaluate the technologies were the thirty (30) year life cycle cost, permitting considerations, and manpower requirements. The study concluded that catalytic oxidation provided the most desirable combination of these elements

  1. Modelling of Boil-Off Gas in LNG Tanks: A Case Study

    Directory of Open Access Journals (Sweden)

    Sheikh Zahidul Islam

    2010-08-01

    Full Text Available This paper focuses on the effect of pressure and heat leakages on Boil-off Gas (BOG in Liquefied Natural Gas (LNG tanks. The Lee-Kesler-Plocker (LKP and the Starling modified Benedict-Webb-Rubin (BWRS empirical models were used to simulate the compressibility factor, enthalpy and hence heat leakage at various pressures to determine the factors that affect the BOG in typical LNG tanks of different capacities. Using a case study data the heat leakage of 140,000kl, 160,00kl, 180,000kl and 200,000kl LNG tanks were analyzed using the LKP and BWRS models. The heat leakage of LNG tanks depends on the structure of tanks, and the small tanks lose heatto the environment due to their large surface area to volume ratio. As the operation pressure was dropped to 200mbar, all four of the LNG tanks’ BOG levels reached 0.05vol%/day. In order to satisfy the BOG design requirement, the operating pressure of the four large LNG tanks in the case study was maintained above 200mbar. Thus, the operating pressure impacts BOG on LNG tanks, but this effect is limited under the extreme high operation pressure. An attempt was made to determine the relationship between the compositions of LNGand BOG; one been combustible and the other non-combustible gases. The main component of combustible gas was methane, and nitrogen was of non-combustible gases. The relationship between BOG and methane compositions was that, as the methane fraction increases in the LNG, the BOG volume also increases. In general, results showed a direct correlation between BOG and operating pressure. The study also found that larger LNG tanks have less BOG; however as the operation pressure is increased the differences in the quantity of BOGamong the four tanks decreased.

  2. Modeling of off-gas emissions from wood pellets during marine transportation.

    Science.gov (United States)

    Pa, Ann; Bi, Xiaotao T

    2010-10-01

    After a fatal accident during the discharge of wood pellets at Helsingborg, emissions from pellets during marine transportation became a concern for the safe handling and storage of wood pellets. In this paper, a two-compartment model has been developed for the first time to predict the concentrations of CO, CO?, CH?, and O? inside the cargo ship and the time and rate of forced ventilation required before the safe entry into the stairway adjacent to the storage hatch. The hatch and stairway are treated as two perfectly mixed tanks. The gas exchange rate between these two rooms and the gas exchange rate with the atmosphere are fitted to satisfy a measured tracer final concentration of 33 p.p.m.v. in the stairway and an average final hatch to stairway CO, CO?, and CH? concentration ratio of 1.62 based on measurement from five other hatch and stairway systems. The reaction kinetics obtained from a laboratory unit using a different batch of pellets, however, need to be scaled in order to bring the prediction to close agreement with onboard measured emission data at the end of voyage. Using the adjusted kinetic data, the model was able to predict the general trend of data recorded in the first 12.5 days of the voyage. Further validation, however, requires the data recorded over the whole journey. The model was applied to predict the effect of ocean temperature on the off-gas emissions and the buildup of concentrations in the hatch and stairway. For safe entry to the cargo ship, the current model predicted that a minimal ventilation rate of 4.4 hr?¹ is required for the stairway's CO concentration to lower to a safe concentration of 25 p.p.m.v. At 4.4 hr?¹, 10 min of ventilation time is required for the safe entry into the stairway studied. PMID:20603277

  3. Formation of the ZnFe2O4 phase in an electric arc furnace off-gas treatment system.

    Science.gov (United States)

    Suetens, T; Guo, M; Van Acker, K; Blanpain, B

    2015-04-28

    To better understand the phenomena of ZnFe2O4 spinel formation in electric arc furnace dust, the dust was characterized with particle size analysis, X-ray fluorescence (XRF), electron backscatter diffraction (EBSD), and electron probe micro-analysis (EPMA). Different ZnFe2O4 formation reaction extents were observed for iron oxide particles with different particle sizes. ZnO particles were present as both individual particles and aggregated on the surface of larger particles. Also, the slag particles found in the off-gas were shown not to react with the zinc vapor. After confirming the presence of a ZnFe2O4 formation reaction, the thermodynamic feasibility of in-process separation - a new electric arc furnace dust treatment technology - was reevaluated. The large air intake and the presence of iron oxide particles in the off-gas were included into the thermodynamic calculations. The formation of the stable ZnFe2O4 spinel phase was shown to be thermodynamically favorable in current electric arc furnace off-gas ducts conditions even before reaching the post combustion chamber. PMID:25646901

  4. Standard specification for agencies performing nondestructive testing

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This specification covers minimum requirements for agencies performing nondestructive testing (NDT). 1.2 When using this specification to assess the capability of, or to accredit NDT agencies, Guide E 1359 shall be used as a basis for the survey. It can be supplemented as necessary with more detail in order to meet the auditor's specific needs. 1.3 This specification can be used as a basis to evaluate testing or inspection agencies, or both, and is intended for use for the qualifying or accrediting, or both, of testing or inspection agencies, public or private. 1.4 The use of SI or inch-pound units, or combination thereof, will be the responsibility of the technical committee whose standards are referred to in this standard. 1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to...

  5. 42 CFR 493.1421 - Condition: Laboratories performing moderate complexity testing; testing personnel.

    Science.gov (United States)

    2010-10-01

    ...2010-10-01 false Condition: Laboratories performing moderate complexity testing...CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Personnel for Nonwaived Testing Laboratories Performing Moderate Complexity...

  6. MODELING THE IMPACT OF ELEVATED MERCURY IN DEFENSE WASTE PROCESSING FACILITY MELTER FEED ON THE MELTER OFF-GAS SYSTEM--PRELIMINARY REPORT

    International Nuclear Information System (INIS)

    The Defense Waste Processing Facility (DWPF) is currently evaluating an alternative Chemical Process Cell (CPC) flowsheet to increase throughput. It includes removal of the steam-stripping step, which would significantly reduce the CPC processing time and lessen the sampling needs. However, its downside would be to send 100% of the mercury that comes in with the sludge straight to the melter. For example, the new mercury content in the Sludge Batch 5 (SB5) melter feed is projected to be 25 times higher than that in the SB4 with nominal steam stripping of mercury. This task was initiated to study the impact of the worst-case scenario of zero-mercury-removal in the CPC on the DWPF melter offgas system. It is stressed that this study is intended to be scoping in nature, so the results presented in this report are preliminary. In order to study the impact of elevated mercury levels in the feed, it is necessary to be able to predict how mercury would speciate in the melter exhaust under varying melter operating conditions. A homogeneous gas-phase oxidation model of mercury by chloride was developed to do just that. The model contains two critical parameters pertaining to the partitioning of chloride among HCl, Cl, Cl2, and chloride salts in the melter vapor space. The values for these parameters were determined at two different melter vapor space temperatures by matching the calculated molar ratio of HgCl (or Hg2Cl2) to HgCl2 witub>Cl2) to HgCl2 with those measured during the Experimental-Scale Ceramic Melter (ESCM) tests run at the Pacific Northwest National Laboratory (PNNL). The calibrated model was then applied to the SB5 simulant used in the earlier flowsheet study with an assumed mercury stripping efficiency of zero; the molar ratio of Cl-to-Hg in the resulting melter feed was only 0.4, compared to 12 for the ESCM feeds. The results of the model run at the indicated melter vapor space temperature of 650 C (TI4085D) showed that due to excessive shortage of chloride, only 6% of the mercury fed is expected to get oxidized, mostly as HgCl, while the remaining mercury would exist either as elemental mercury vapor (90%) or HgO (4%). Noting that the measured chloride level in the SB5 qualification sample was an order of magnitude lower than that used in the SB5 simulant, the degree of chloride shortage will be even greater. As a result, the projected level of HgCl in the actual SB5 melter exhaust will be even lower than 6% of the total mercury fed, while that of elemental mercury is likely to be greater than 90%. The homogeneous oxidation of mercury in the off-gas was deemed to be of primary importance based on the postulation that mercury and other volatile salts form submicron sized aerosols upon condensation and thus remain largely in the gas stream downstream of the quencher where they can deposit in the off-gas lines, Steam-Atomized Scrubbers (SAS), and High-Efficiency Mist Eliminator (HEME). Formation of these submicron semi-volatile salts in the condensate liquid is considered to be unlikely, so the liquid phase reactions were considered to be less important. However, subsequent oxidation of mercury in the liquid phase in the off-gas system was examined in a simplified model of the off-gas condensate. It was found that the condensate chemistry was consistent with further oxidation of elemental mercury to Hg2Cl2 and conversion of HgO to chlorides. The results were consistent with the available experimental data. It should also be noted that the model predictions presented in this report do not include any physically entrained solids, which typically account for much of the off-gas carryover on a mass basis. The high elemental mercury vapor content predicted at the DWPF Quencher inlet means that physically entrained solids could provide the necessary surface onto which elemental mercury vapor could condense, thereby coating the solids as well as the internal surfaces of the off-gas system with mercury. Clearly, there are many process benefits to be gained by removing the steam-stripping step from the CPC cycle. The goal o

  7. Off-Gas Generation Rate during Chemical Cleaning Operations at the Savannah River Site - 12499

    International Nuclear Information System (INIS)

    The enhanced chemical cleaning process (ECC) is being developed at the Savannah River Site (SRS) to remove the residual radioactive sludge heel that remains in a liquid waste storage tank. Oxalic acid is the chemical agent utilized for this purpose. However, the acid also corrodes the carbon steel tank wall and cooling coils. If the oxalic acid has little interaction with the sludge, hydrogen gas could conceivably evolve at cathodic areas due to the corrosion of the carbon steel. Scenarios where hydrogen evolution could occur during ECC include the initial filling of the tank prior to agitation and near the end of the process when there is little or no sludge present. The purpose of this activity was to provide a bounding estimate for the hydrogen generation rate during the ECC process. Sealed vessel coupon tests were performed to estimate the hydrogen generation rate due to corrosion of carbon steel by oxalic acid. These tests determined the maximum instantaneous hydrogen generation rate, the rate at which the generation rate decays, and the total hydrogen generated. The tests were performed with polished ASTM A285 Grade C carbon steel coupons. This steel is representative of the Type I and II waste tanks at SRS. Bounding conditions were determined for the solution environment. The oxalic acid concentration was 2.5 wt.% and the test temperature was 75 deg. C. The test solution was agitated and contained no sludge simulant. Duplicate tests were performed and showed excellent reproducibility for the hydrogen generation rate and total hydrogen generated. The results showed that the hydrogen generation rate was initially high, but decayed rapidly within a couple of days. A statistical model was developed to predict the instantaneous hydrogen generation rate as a function of exposure time by combining both sets of data. An upper bound on the maximum hydrogen generation rate was determined from the upper 95% confidence limit. The upper bound limit on the maximum instantaneous generation rate at 5 hours was 6.1 x 10-5 m3/m2/minute. After two and five days the upper bound limit decayed to 7.9 x 10-6 and 1.3 x 10-6 m3/m2/minute, respectively. The total volume of hydrogen gas generated during the test was calculated from the model equation. An upper bound on the total gas generated was determined from the upper 95% confidence limit. The upper bound limit on the total hydrogen generated during the 163 hour test was 0.101 m3/m2. Corrosion rates were determined from the coupon tests and also calculated from the measured hydrogen generation rates. Excellent agreement was achieved between the time averaged corrosion rate calculated from the hydrogen generation rates and the corrosion rates determined from the coupon tests. The corrosion rates were on the order of 0.45 mmpy. Good agreement was also observed between the maximum instantaneous corrosion rate as calculated from the hydrogen generation rate and the corrosion rate determined by previous electrochemical tests. (authors)

  8. CFC and HFC recycling equipments: Test performances

    International Nuclear Information System (INIS)

    Actual regulatory conditions about ozone layer depleting chemicals set problems on their disposal and on the management of plants still using illegal CFCs. Anyway fluids that will replace CFCs (i.e. HFCs) will not be allowed to be spread into the atmosphere, due to their high costs and to the greenhouse effect. A viable solution would be the recovery, purification and recycle of contaminated fluids. ENEA (National Agency for New Technology, Energy and the Environment), in cooperation with ICF (Industria Componenti Frigoriferi) Company leader in the field of air refrigerating and conditioning, patented a device able to extract, to clean and to recycle CFC 12 and HFC 134a in the refrigerating systems. This paper presents experimental data from the qualification tests on a device performing the above mentioned operations regarding systems that use HFC 134a as process fluid

  9. Integrated Performance Testing Workshop - Supplemental Materials (Scripts and Procedures)

    Energy Technology Data Exchange (ETDEWEB)

    Baum, Gregory A.

    2014-02-01

    A variety of performance tests are described relating to: Material Transfers; Emergency Evacuation; Alarm Response Assessment; and an Enhanced Limited Scope Performance Test (ELSPT). Procedures are given for: nuclear material physical inventory and discrepancy; material transfers; and emergency evacuation.

  10. 42 CFR 493.15 - Laboratories performing waived tests.

    Science.gov (United States)

    2010-10-01

    ...2010-10-01 2010-10-01 false Laboratories performing waived tests. 493.15...CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS General Provisions § 493.15 Laboratories performing waived tests. (a)...

  11. Heat exchanger bypass test procedure

    International Nuclear Information System (INIS)

    The HC-21C Muffle Furnace Process has been experiencing problems with corrosion of the off-gas piping system. During the processing cycle, condensation is forming and corroding the off-gas piping. The corrosion products build up in the rotameters and cause them to be dysfunctional. The condensation is suspected to be occurring in the heat exchanger, so the test will bypass the heat exchanger to verify this. This process test will help to establish a temperature profile for the off-gas system near the rotameter. Also, this information will be used to help determine the location and cause of water condensation that is occurring in the off-gas equipment. The process test will include operating one of the two furnaces in Room 230A to stabilize Pu bearing material. During the test run, various temperature readings will be taken and visual inspections done

  12. Novel synthesis of bismuth-based adsorbents for the removal of 129I in off-gas

    Science.gov (United States)

    Yang, Jae Hwan; Shin, Jin Myeong; Park, Jang Jin; Park, Geun Il; Yim, Man Sung

    2015-02-01

    New adsorbents based on bismuth were investigated for the capture of iodine-129 (129I) in off-gas produced from spent fuel reprocessing. Porous bulky materials were synthesized with polyvinyl alcohol (PVA) as a sacrificial template. Our findings showed that the iodine trapping capacity of as-synthesized samples could reach 1.9-fold that of commercial silver-exchanged zeolite (AgX). The thermodynamic stability of the reaction products explains the high removal efficiency of iodine. We also found that the pore volume of each sample was closely related to the ratio of the reaction products.

  13. Technical and economic evaluation of processes for krypton-85 recovery from power fuel-reprocessing plant off-gas

    Energy Technology Data Exchange (ETDEWEB)

    Waggoner, R.C.

    1982-08-01

    A technical and economical analysis has been made of methods for collecting and concentrating krypton from the off-gas from a typical nuclear fuel reprocessing plant. The methods considered were cryogenic distillation, fluorocarbon absorption, mordenite adsorption, and selective permeation. The conclusions reached were: Cryogenic distillation is the only demonstrated route to date. Fluorocarbon absorption may offer economic and technical advantages if fully developed and demonstrated. Mordenite adsorption has been demonstrated only on a bench scale and is estimated to cost more than either cryogenic distillation or fluorocarbon absorption. Selective permeation through a silicone rubber membrane is not sufficiently selective for the route to be cost effective.

  14. Technical and economic evaluation of processes for krypton-85 recovery from power fuel-reprocessing plant off-gas

    International Nuclear Information System (INIS)

    A technical and economical analysis has been made of methods for collecting and concentrating krypton from the off-gas from a typical nuclear fuel reprocessing plant. The methods considered were cryogenic distillation, fluorocarbon absorption, mordenite adsorption, and selective permeation. The conclusions reached were: Cryogenic distillation is the only demonstrated route to date. Fluorocarbon absorption may offer economic and technical advantages if fully developed and demonstrated. Mordenite adsorption has been demonstrated only on a bench scale and is estimated to cost more than either cryogenic distillation or fluorocarbon absorption. Selective permeation through a silicone rubber membrane is not sufficiently selective for the route to be cost effective

  15. 49 CFR Appendix A to Part 665 - Tests To Be Performed at the Bus Testing Facility

    Science.gov (United States)

    2010-10-01

    ...should be obtained during the bus durability test at the test track...twenty-five percent of the bus life should be simulated...should be performed at the Bus Testing Center, and the structural durability test should be...

  16. New test methods for BIPV. Results from IP performance

    International Nuclear Information System (INIS)

    Within the Performance project new test procedures for PV building products and the building performance as a whole when PV is applied in buildings have been drafted. It has resulted in a first draft of new test procedures for PV building products and proposals for tests for novel BIPV technology like thin film. The test proposed are a module breakage test for BIPV products, a fire safety test for BIPV products and a dynamic load test for BIPV products. Furthermore first proposals of how flexible PV modules could be tested in an appropriate way to ensure long time quality and safety of these new products are presented.

  17. Earthquake early warning performance tests for Istanbul

    Science.gov (United States)

    Köhler, N.; Wenzel, F.; Erdik, M.; Alcik, H.; Mert, A.

    2009-04-01

    The Marmara Region is the most densily populated region in Turkey. The greater area of the mega-city Istanbul inhabits about 14 million people. The city is located in the direct vicinity of the Main Marmara Fault, a dextral strike-slip fault system intersecting the Sea of Marmara, which is the western continuation of the North Anatolian Fault [Le Pichon et al., 2001]. Its closest distance to the city of Istanbul ranges between 15 and 20 km. Recent estimates by Parsons [2004] give a probability of more than 40% of a M ? 7 earthquake that will affect Istanbul within the next 30 years. Due to this high seismic risk, earthquake early warning is an important task in disaster management and seismic risk reduction, increasing the safety of millions of people living in and around Istanbul and reducing economic losses. The Istanbul Earthquake Rapid Response and Early Warning System (IERREWS) includes a set of 10 strong-motion sensors used for early warning which are installed between Istanbul and the Main Marmara Fault. The system works on the exceedance of amplitude thresholds, whereas three alarm levels are defined at three different thresholds [Erdik et al., 2003]. In the context of the research project EDIM (Earthquake Disaster Information System for the Marmara Region, Turkey), the early warning network is planned to be extended by an additional set of 10 strong-motion sensors installed around the Sea of Marmara to include the greater Marmara Region into the early warning process. We present performance tests of both the existing and the planned extended early warning network using ground motion simulations for 280 synthetic earthquakes along the Main Marmara Fault with moment magnitudes between 4.5 and 7.5. We apply the amplitude thresholds of IERREWS, as well as, for comparison, an early warning algorithm based on artificial neural networks which estimates hypocentral location and magnitude of the occurring earthquake. The estimates are updated continuously with proceeding time. Applying the amplitude thresholds increase the number of alarms by 6.5% for alarm level 1, by 6% for alarm level 2, and by 4% for alarm level 3, mainly due to false alarms caused by earthquakes further away from Istanbul but closer to the additional stations. However, applying the neural network algorithm to the extended network increases the reliability of source parameter estimates by 8% already 2 seconds after the first station triggers, and by 19% after 5 seconds. We analyse the effects of the network extension to the greater region and discuss possible advantages as well as arising problems.

  18. Final Report Integrated DM1200 Melter Testing Using AZ-102 And C-106/AY-102 HLW Simulants: HLW Simulant Verification VSL-05R5800-1, Rev. 0, 6/27/05

    International Nuclear Information System (INIS)

    The principal objectives of the DM1200 melter tests were to determine the effects of feed rheology, feed solid content, and bubbler configuration on glass production rate and off-gas system performance while processing the HLW AZ-101 and C-106/AY-102 feed compositions; characterize melter off-gas emissions; characterize the performance of the prototypical off-gas system components, as well as their integrated performance; characterize the feed, glass product, and off-gas effluents; and perform pre- and post test inspections of system components. The specific objectives (including test success criteria) of this testing, along with how each objective was met, are outlined in a table. The data provided in this Final Report address the impacts of HLW melter feed rheology on melter throughput and validation of the simulated HLW melter feeds. The primary purpose of this testing is to further validate/verify the HLW melter simulants that have been used for previous melter testing and to support their continued use in developing melter and off-gas related processing information for the Project. The primary simulant property in question is rheology. Simulants and melter feeds used in all previous melter tests were produced by direct addition of chemicals; these feed tend to be less viscous than rheological the upper-bound feeds made from actual wastes. Data provided here compare melter processing for the melter feed used in all previous DM100 and DM1200 tests (nominal melter feed) with feed adjusted by the feed vendor (NOAH Technologies) to be more viscous, thereby simulating more closely the upperbounding feed produced from actual waste. This report provides results of tests that are described in the Test Plan for this work. The Test Plan is responsive to one of several test objectives covered in the WTP Test Specification for this work; consequently, only part of the scope described in the Test Specification was addressed in this particular Test Plan. For the purpose of comparison, the tests reported here were performed with AZ-102 and C-106/AY-102 HLW simulants and glass compositions that are essentially the same as those used for recent DM1200 tests. One exception was the use of an alternate, higher-waste-loading C-106/AY-102 glass composition that was used in previous DM100 tests to further evaluate the performance of the optimized bubbler configuration.

  19. FINAL REPORT INTEGRATED DM1200 MELTER TESTING USING AZ 102 AND C 106/AY-102 HLW SIMULANTS: HLW SIMULANT VERIFICATION VSL-05R5800-1 REV 0 6/27/05

    Energy Technology Data Exchange (ETDEWEB)

    KRUGER AA; MATLACK KS; GONG W; BARDAKCI T; D' ANGELO NA; BRANDYS M; KOT WK; PEGG IL

    2011-12-29

    The principal objectives of the DM1200 melter tests were to determine the effects of feed rheology, feed solid content, and bubbler configuration on glass production rate and off-gas system performance while processing the HLW AZ-101 and C-106/AY-102 feed compositions; characterize melter off-gas emissions; characterize the performance of the prototypical off-gas system components, as well as their integrated performance; characterize the feed, glass product, and off-gas effluents; and perform pre- and post test inspections of system components. The specific objectives (including test success criteria) of this testing, along with how each objective was met, are outlined in a table. The data provided in this Final Report address the impacts of HLW melter feed rheology on melter throughput and validation of the simulated HLW melter feeds. The primary purpose of this testing is to further validate/verify the HLW melter simulants that have been used for previous melter testing and to support their continued use in developing melter and off-gas related processing information for the Project. The primary simulant property in question is rheology. Simulants and melter feeds used in all previous melter tests were produced by direct addition of chemicals; these feed tend to be less viscous than rheological the upper-bound feeds made from actual wastes. Data provided here compare melter processing for the melter feed used in all previous DM100 and DM1200 tests (nominal melter feed) with feed adjusted by the feed vendor (NOAH Technologies) to be more viscous, thereby simulating more closely the upperbounding feed produced from actual waste. This report provides results of tests that are described in the Test Plan for this work. The Test Plan is responsive to one of several test objectives covered in the WTP Test Specification for this work; consequently, only part of the scope described in the Test Specification was addressed in this particular Test Plan. For the purpose of comparison, the tests reported here were performed with AZ-102 and C-106/AY-102 HLW simulants and glass compositions that are essentially the same as those used for recent DM1200 tests. One exception was the use of an alternate, higher-waste-loading C-106/AY-102 glass composition that was used in previous DM100 tests to further evaluate the performance of the optimized bubbler configuration.

  20. Testing performance criteria for radioactive shipping containers

    International Nuclear Information System (INIS)

    Considerable confusion exists concerning the use of testing as applied to the design and certification of radioactive material packaging. Many people would insist upon demonstration-testing of such items as shipping casks, in order to develop public confidence. While such demonstrations may be significant in a political sense, more important to the design of safe systems are benchmark tests to evaluate analytical codes and testing to evaluate the adequacy of the regulations. While in some situations demonstration-testing has some limited technical application, it is even then only part of a complete and balanced engineering approach and should not be looked upon as the ultimate solution to the problem of public confidence

  1. 40 CFR 63.1161 - Performance testing and test methods.

    Science.gov (United States)

    2010-07-01

    ...Pickling-HCl Process Facilities and Hydrochloric Acid Regeneration Plants § 63...concentration of HCl (and Cl2 for hydrochloric acid regeneration plants) in gases...tests. (c) Establishment of hydrochloric acid regeneration plant...

  2. DiPerF: an automated DIstributed PERformance testing Framework

    OpenAIRE

    Dumitrescu, Catalin; Raicu, Ioan; Ripeanu, Matei; Foster, Ian

    2004-01-01

    We present DiPerF, a distributed performance testing framework, aimed at simplifying and automating service performance evaluation. DiPerF coordinates a pool of machines that test a target service, collects and aggregates performance metrics, and generates performance statistics. The aggregate data collected provide information on service throughput, on service "fairness" when serving multiple clients concurrently, and on the impact of network latency on service performance....

  3. Catalytic O2- and NOsub(x)-removal: a process step for an off-gas cleaning system in reprocessing plants

    International Nuclear Information System (INIS)

    The last step of an off-gas purification system for future reprocessing plants of spent nuclear fuels is the retention of the radioactive krypton. If a cryogenic distillation process is chosen for this step, O2 and NOsub(x) must be removed prior to the cryogenic part in order to avoid radiolytic formation of ozone and crystallization problems, respectively. Simultaneous catalytic reduction with H2 was chosen using ruthenium on A12O3 as catalyst. The process step was tested in a semiscale unit with a gas throughput of 50 m3/h. The feed-gas was diluted by N2 in a gas loop by a factor of 10, to prevent formation of explosive gas mixtures. Residual O2- and NOsub(x)-concentrations 1 ppmv were attained routinely in the temperature range of the catalyst between 3500C and 5500C and at space velocities (GHVS) between 10000 and 15000 h-1. Formation of CH4 is very low (2O). H2 feed control is carried out by means of chemical analysis of O2 and NOsub(x) in the feed gas by calculating the necessary H2 amount and controlling the main H2-valve with a microcomputer. An additional small H2-valve is controlled by analysis of the H2 excess behind the catalyst bed. Even large concentration transients of O2 and NOsub(x) can thus be handled by the catalyst without breakthrough. (author)

  4. Test plan for dig-face characterization performance testing

    International Nuclear Information System (INIS)

    The dig-face characterization concept has been under development at the Idaho National Engineering Laboratory (INEL) since FY 1992 through the support of the Buried Waste Integrated Demonstration Program. A Dig-face Characterization System conducts continuous subsurface characterization simultaneously with retrieval of hazardous and radioactive waste from buried waste sites. The system deploys multiple sensors at the retrieval operation dig-face and collects data that provide a basis for detecting, locating, and identifying hazardous conditions before they are disturbed by the retrieval equipment. This test plan describes initial efforts to test the dig-face characterization concept at the INEL Cold Test Pit using a simplified prototype apparatus and off-the-shelf sensors. The Cold Test Pit is a simulated waste site containing hazardous and radioactive waste surrogates at known locations. Testing will be directed toward three generic characterization problems: metal detection, plume detection, and radioactive source detection. The prototype apparatus will gather data using magnetometers, a ground conductivity meter, a trace gas analyzer, and a gamma ray sensor during simulated retrieval of the surrogate waste materials. The data acquired by a dig-face characterization system are unique because of the high precision, high data density, and multiple viewpoints attainable through the dig-face deployment approach. The test plan establishes procedures for collecting and validating a representative dig-face characterization data set. Analysis of these data will focus on developing criteria for predicting the depth, location, composition, and other characteristics of the surrogate waste materials. If successful, this proof-of-concept exercise will provide a foundation for future development of a fully-operational system that is capable of operating on an actual waste site

  5. Reliability performance testing of totally encapsulating chemical protective suits

    International Nuclear Information System (INIS)

    The need to assure a high degree of reliability for totally encapsulating chemical protective (TECP) suits has been recognized by Lawrence Livermore National Laboratory's (LLNL) Hazards Control Department for some time. The following four tests were proposed as necessary to provide complete evaluation of TECP suit performance: 1. Quantitative leak test (ASTM draft), 2. Worst-case chemical exposure test (conceptual), 3. Pressure leak-rate test (complete, ASTM F1057-87), and 4. Chemical leak-rate test (ASTM draft). This paper reports on these tests which should be applied to measuring TECP suit performance in two stages: design qualification tests and field use tests. Test 1, 2, and 3 are used as design qualification tests, and tests 3 and 4 are used as field use tests

  6. Collaborative group testing benefits high- and low-performing students

    Science.gov (United States)

    Maurico J. Giuliodori (Univ Nacional De La Plata Dept Physiology)

    2008-12-01

    We used collaborative group testing in a veterinary physiology course (65 students) to test the hypothesis that all students (e.g., high-performing and low-performing students of each group) benefit from collaborative group testing. In this format, students answered questions in the traditional format as individuals. Immediately after completing the exam as individuals, students answered the same questions in groups of two, and, finally, the same questions were discussed by the instructor and students. We measured two learning outcomes for every student: individual and group test scores. Based on individual test scores, students were categorized as "high performing" (students with higher individual scores) or "low performing" (students with lower individual scores). Finally, student evaluations of the format were collected. Collaborative group testing enhanced student performance. Specifically, group scores were higher than individual scores (P testing effect was large for the population and for the low-performing students; however, the collaborative testing effect was small for the high-performing students. Finally, student evaluations of this testing format were very positive. In conclusion, collaborative group testing was beneficial for all students; however, collaborative testing was significantly more beneficial for low-performing students.

  7. Customized design of electronic noses placed on top of air-lift bioreactors for in situ monitoring the off-gas patterns.

    Science.gov (United States)

    Rosi, Pablo E; Miscoria, Silvia A; Bernik, Delia L; Martín Negri, R

    2012-06-01

    A specially designed electronic nose was coupled to an air-lift bioreactor in order to perform on-line monitoring of released vapors. The sensor array was placed at the top of the bioreactor sensing the headspace in equilibrium with the evolving liquor at any time without the need of aspiration and pumping of gases into a separated sensor chamber. The device was applied to follow the off-gas of a bioreactor with Acidithiobacillus thiooxidans grown on beds of elemental sulfur under aerobic conditions. Evolution was monitored by acid titration, pH and optical density measurements. The electronic nose was capable to differentiate each day of reactor evolution since inoculation within periods marked off culture medium replacements using multivariate data analysis. Excellent discrimination was obtained indicating the potentiality for on-line monitoring in non-perturbed bioreactors. The prospects for electronic nose/bioreactor merging are valuable for whatever the bacterial strain or consortium used in terms of scent markers to monitor biochemical processes. PMID:22212349

  8. TESTING GAME BASED PERFORMANCE IN TEAM-HANDBALL.

    Science.gov (United States)

    Wagner, Herbert; Orwat, Matthias; Hinz, Matthias; Pfusterschmied, Jürgen; Bacharach, David W; Petelin von Duvillard, Serge; Müller, Erich

    2014-06-17

    Team-handball is a fast paced game of defensive and offensive action that includes specific movements of jumping, passing, throwing, checking and screening. To date and to our knowledge, a game based performance test for team-handball does not exist. Therefore the aim of this study was to develop and validate such a test.Seventeen experienced team-handball players performed two game based performance tests separated by seven days between each test, an incremental treadmill-running test, and a team-handball test game (2×20min). Peak oxygen uptake (VO2-peak), blood lactate concentration (BLC), heart rate (HR), sprinting time, time of offensive and defensive actions as well as running intensities, ball velocity and jump height were measured in the game based test. Reliability of the tests was calculated utilizing an interclass correlation coefficient (ICC). Additionally, we measured VO2-peak in the incremental treadmill-running test and BLC, HR and running intensities in the team-handball test game to determine the validity of the game based performance test.For the test-retest reliability, we found an ICC>.70 for the peak BLC and HR, mean offense and defense time as well as ball velocity that yielded an ICC>.90 for the VO2-peak in the game based performance test. Percent walking and standing constituted 73% of total time. Moderate (18%) and high (9%) intensity running in the game based performance test was similar to the team-handball test game.Our results indicated that the game based performance test is a valid and reliable test to analyze team-handball performance (physiological and biomechanical variables) under conditions similar to competition. PMID:24942169

  9. Qualification Plus: Performance and Durability Tests Beyond IEC 61215 (Presentation)

    Energy Technology Data Exchange (ETDEWEB)

    Kurtz, S.; Jordan, J.; Kempe, M.; Miller, D.; Bosco, N.; Silverman, T.; Hacke, P.; Phillips, N.; Earnest, T.; Romero, R.

    2014-03-01

    Qualification Plus is an accelerated test protocol and quality management system that gives higher confidence in field performance of PV modules compared with conventional qualification testing. The test sequences are being developed as consensus standards, but the early publication of these tests enables the community to begin benefiting from them sooner.

  10. Performance testing of thermoelectric generators at JPL

    International Nuclear Information System (INIS)

    Several thermoelectric generators, ranging in output power from 170 watts to microwatts, are undergoing testing at JPL. They represent a wide range of technologies using advanced PbTe, SiGe and cascaded PbTe and BiTe thermoelectric materials. Several of these generators are of an advanced concept while others are representative of the Nimbus, Transit, Viking and the Multi-Hundred Watt (MHW) technology. Of interest is the behavior of generators which have been tested for times in excess of 60,000 hours

  11. Component test procedure for the ground demonstration system turbine performance

    International Nuclear Information System (INIS)

    This test procedure provides a detailed description of the verification methods which shall be used in the development program to be conducted on the Dynamic Isotope Power System (DIPS) Turbine to fulfill the requirements of the Ground Demonstration System Test Plan. The test objectives are to characterize turbine performance so that data can be used for turbine configuration selection and system performance evaluation during Ground Demonstration System (GDS) testing

  12. Containment venting through the off-gas system: a way of upgrading the accident manageability of the plant

    International Nuclear Information System (INIS)

    The technical feasibility of the OGTS (Off-Gas Treatment System), installed in BWR's, as means to mitigate the consequences of severe accidents has been investigated in the past. The studies are still in progress. In particular are under investigation problems associated with the pressure drop through the off-gas line, the adoption and optimization of a water basin, useful to condense the first part of steam leaving the containment in case of an accident. Also fire problems on the charcoal beds were investigated as consequence of the heating induced on the charcoal by the decay power associated with the fission products collected on it. A short presentation of the main findings up to now is given in this paper for each item. Another point of interest is to quantify the benefits of using the removal capability, associated with the big mass of charcoal contained in the system, after determining the new margins of operability of the off-gas system. As generally understood the effectiveness of a mitigative system against radioactive contamination is ultimately connected with the delay allowed for the release of contamination into the environment. In a situation of continuous flow through the beds the delay can be of the order of ten hours (for the most volatiles components), but this activity get bottled in the charcoal almost indefinitely if it is assumed that the flow is stopped after a certain period. The venting of the containment can then be routed through an hardenement can then be routed through an hardened stand by gas treatment system, if still necessary. The residual, less volatile, activity still present in the containment is released after removal through the filter trains. Using this procedure a decontamination factor of more than 100 for the most volatiles radionuclides can be attained. In conclusion: The conditions under which the feasibility of a venting through the OGTS could be assured has been evidenced in the report. The demonstration of the benefit of this feature, as part of a containment venting system has been given in terms of further reduction in the noble gases releases (factors of 50 for Kr, 300 for Xe). In addition it is reduced the uncertainty connected with the effectiveness in removing the organic forms of iodine. Those benefits make possible a greater flexibility in the operation of the system, which otherwise should be limited with regard to the time of actuation

  13. CHROMagar Salmonella Detection Test Kit. Performance Tested Method 020502.

    Science.gov (United States)

    Webb, Katana; Ritter, Vicki

    2009-01-01

    BBL CHROMagar Salmonella was evaluated by an external food testing laboratory for the recovery of Salmonella in peanut butter using the U.S. Food and Drug Administration's Bacteriological Analytical Manual (FDA-BAM) procedure. The peanut butter was found to be negative for the presence of Salmonella and, therefore, was seeded with heat-stressed Salmonella at target concentrations of 0.2 and 2 CFU/25 g. The Salmonella-seeded samples remained at room temperature for 14 days before analysis to stabilize the Salmonella in the food environment. Twenty 25 g test portions from each seeded level and five 25 g samples of uninoculated control samples were processed using enrichment broths as outlined in the FDA-BAM procedure. BBL CHROMagar Salmonella-prepared plates were evaluated with the FDA reference method media (bismuth sulfite, xylose lysine desoxycholate, and Hektoen enteric agars). Fractionally positive results were obtained from the lower inoculum level of peanut butter samples. Five positive cultures were recovered from both the BBL CHROMagar Salmonella and reference methods. The two methods gave identical results for all cultures resulting in a method agreement of 100%. McNemar's chi2 test, which assesses the evidence for difference in marginal proportions between two methods, could not be evaluated because it requires one or more discrepant cultures. However, because there were no discrepant cultures, the marginal proportions for the two methods were identical; therefore, there is no evidence of a difference between the methods. This study demonstrates that the results from BBL CHROMagar Salmonella are comparable to the three reference method media for the detection of Salmonella in peanut butter using the FDA-BAM procedures. PMID:20166616

  14. Evaluation of spacer grid support performance by vibration test

    International Nuclear Information System (INIS)

    Four 5x5 spacer grids for a PWR fuel assembly were manufactured, and performed the spacer's support performance test that is one of the mechanical tests for the spacer grid. Among the specimen, two spacer grids have the traditional spring-to-dimple supporting configuration, and the others the spring-to-spring feature. The supporting performance test as an out-of-pile test is a kind of vibration test because it is the evaluation test for capability in restraining a fuel rod from vibrating. Since the nonlinear characteristic of the vibration behavior of the fuel rod was appreciated, input force from shaker was controlled to use the same force for every test. It was resulted that the maximum displacements were Obtained at the first resonant frequency in most cases while some at third resonance frequency, and the supporting performance of new spacer grids were as good as, or better than that of the reference spacer grid

  15. Comparison of thermochemically calculated and measured dioxin contents in the off-gas of a sinter plant

    Energy Technology Data Exchange (ETDEWEB)

    Spencer, P.; Eriksson, G.; Neuschuelz, D. [Lehrstuhl fuer Theoretische Huettenkunde, Aachen (Germany)

    1997-12-31

    Polychlorinated dibenzo-p-dioxins and dibenzo-furans form a family of more than 200 compounds which are relatively stable in the biosphere and tend to accumulate in the human body. The tetra- to hexa-chlorinated dioxins and furans are considered highly toxic. To facilitate the assessment of the total toxicity of dioxin and furan mixtures, the estimated toxic effects of the individual compounds relative to the 2,3,7,8-tetrachloro-dibenzo-p-dioxin (TCDD) were introduced as Toxic Equivalent Factors which yield, when multiplied with the respective concentrations, the Toxic Equivalent (TE) of the mixture. Toxic dioxins and furans are unintentionally formed in a number of industrial combustion processes such as waste incineration and iron ore sintering, in the chemical industry and in household heating. To keep the emissions as low as possible, off-gas clearing systems for the collection of dioxins and furans are increasingly prescribed by the authorities. In addition, it appears desirable to select process conditions that are unfavourable for the formation of these compounds. A simulation of the relevant processes on the basis of thermodynamic data may be helpful in defining such process conditions. To simulate dioxin formation in the sintering process, all major gas-solid reactions taking place in the sinter bed must also be simulated. A sufficiently accurate reproduction of the off-gas compositions along the length of the sinter strand requires detailed assumptions concerning the relative amounts of `active` O{sub 2} as well as the distribution of reacting carbon and water over the strand length. From this basis, an equilibrium calculation for the gas/solid reactions at the sintering temperature of 1150 deg C and an equilibrium calculation restricted to the gas phase at 700 deg C produced values for the concentrations of the major off-gas constituents in very good agreement with the measured values. The further assumption that below 700 deg C all reactions are frozen appears to be reasonable. The latter assumption has consequently been extended to the formation of dioxins from the off-gas. Making use of the calculated data for 700 deg C, it was found that for dioxins to form in the amounts observed in practice, three further assumptions must be made: The formation of solid carbon must be suppressed, the oxygen partial pressure must be set to very low values and the C/H ratio must be >2, which implies that a large part of the hydrogen present does not take part in the reaction. With these assumptions, the calculated dioxin concentrations are of the same order of magnitude as the measured values. Furthermore, the different dioxins appear with closely similar partial pressures. This is also in accordance with observation. The calculated TE concentrations increase along the length of the sinter strand in a similar manner to the observed values. Beyond Stage 10, the simulation reads to a further strong increase which is not found in reality. In the calculation, the oxygen and chlorine concentrations as well as the C/H ratio are kept constant along the length of the strand. What varies is the carbon content as given in the sum of CO{sub 2} + CO. It thus appears that the Cl/C ratio, which increases with strand length, strongly enhances the formation of dioxins. General conclusions which may be drawn from the present calculations with regard to restricting possible formation of dioxins are: increase the content of hydrogen-containing species in the system; decrease the chlorine content in the gas phase and if possible, avoid local extremely reducing conditions in the system. (author) 12 refs.

  16. Thermodynamic analysis-based improvement for the boil-off gas reliquefaction process of liquefied ethylene vessels

    Energy Technology Data Exchange (ETDEWEB)

    Li, Y.; Jin, G.; Zhong, Z. [South China University of Technology, School of Chemistry and Chemical Engineering, Key Lab of Heat Transfer Enhancement and Energy Conservation of the Ministry of Education, Guangzhou (China)

    2012-10-15

    A new optimization design of the boil-off gas (BOG) reliquefaction process for liquefied ethylene (LEG) vessels is proposed in order to reduce the reliquefaction process energy cost and improve its cold exergy efficiency. The exergy loss of each component is calculated and the efficiency of the available energy utilization is evaluated on the basis of a detailed thermodynamic analysis. The exergy analysis results indicate that the exergy efficiency of the improved BOG reliquefaction process is about 19.0 % higher than that of the existing process, and the amount of refrigerant used in the improved process is reduced by about 44.9 % per hour. The power consumption could be decreased by 16 %. The circulation volumes of the refrigerant and BOG are both significantly reduced, thus lowering the equipment and operation costs of the BOG reliquefaction process. (Copyright copyright 2012 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  17. Performance demonstration tests for detection of intergranular stress corrosion cracking

    International Nuclear Information System (INIS)

    This report evaluates detection tests of inservice inspectors (ISI), procedures and equipment that are employed to find intergranular stress corrosion cracks in nuclear power plant piping. Performance is described by two fundamental parameters: false call probability and probability of detection. Acceptable inspection performance and detection tests are therefore defined in terms of these two parameters. 14 refs., 25 figs

  18. Beam test performance of the SKIROC2 ASIC

    CERN Document Server

    Frisson, T; Anduze, M; Augustin, J.E; Bonis, J; Boudry, V; Bourgeois, C; Brient, J.C; Callier, S; Cerutti, M; Chen, S; Cornat, R; Cornebise, P; Cuisy, D; David, J; De la Taille, C; Dulucq, F; Frotin, M; Gastaldi, F; Ghislain, P; Giraud, J; Gonnin, A; Grondin, D; Guliyev, E; Hostachy, J.Y; Jeans, D; Kamiya, Y; Kawagoe, K; Kozakai, C; Lacour, D; Lavergne, L; Lee, S.H; Magniette, F; Ono, H; Poeschl, R; Rouëné, J; Seguin-Moreau, N; Song, H.S; Sudo, Y; Thiebault, A; Tran, H; Ueno, H; Van der Kolk, N; Yoshioka, T

    2015-01-01

    Beam tests of the first layers of CALICE silicon tungsten ECAL technological prototype were performed in April and July 2012 using 1–6 GeV electron beam at DESY. This paper presents an analysis of the SKIROC2 readout ASIC performance under test beam conditions.

  19. Performance of the test control system using Java/CORBA

    International Nuclear Information System (INIS)

    In order to research the control system for 'Super SOR', we have developed the test bench of the control system and evaluated its performance. We use Common Object Request Broker Architecture (CORBA) as the framework for the control system, and Java as the programming language for the graphical user interface. This paper describes the test bench and its performance. (author)

  20. Performance Testing Effort at the ATM Forum: An Overview

    OpenAIRE

    Jain, Raj; Babic, Gojko

    1998-01-01

    The testing group at ATM Forum is working on developing a specification for performance testing of ATM switches and networks. The emphasis is on the user perceived frame-level performance. This paper explains what is different about this new effort and gives its status.

  1. Performance test of PPAC in different gases

    CERN Document Server

    Wang Meng; Zhan Wen Long; Xiao Guo Qing; Xu Hu Shan; Mao Rui Shi; Hu Zheng Guo; Chen Zhi Qiang; Sun Zhi Yu; Li Jia Xing; Wang Wu Sheng; Chen Li Xin; Li Chen; Bai Jie; Zhang Xia; Zhang Jin Xia; Li Cun Fan

    2002-01-01

    A two-dimension position sensitive parallel-plate avalanche (PPAC) detector has been developed for RIBLL. The detector consists of one anode and two cathodes. In each cathode a resistance chain is used to readout position signals. The detector has been tested in different operating gases with an alpha source. When the detector is at 7 mb flowing rate of isobutane and + 500 V on anode, the position resolution of 0.76 mm is obtained. For 7 mb C sub 3 F sub 8 and +595 V on anode, the position resolution is 0.64 mm. The efficiencies are around 99.1% in the cases of C sub 3 F sub 8 and isobutane

  2. Performance testing framework for smart grid communication network

    International Nuclear Information System (INIS)

    Smart grid communication network is comprised of different communication mediums and technologies. Performance evaluation is one of the main concerns in smart grid communication system. In any smart grid communication implementation, to determine the performance factor of the network, a testing of an end-to-end process flow is required. Therefore, an effective and coordinated testing procedure plays a crucial role in evaluating the performance of smart grid communications. In this paper, a testing framework is proposed as a guideline to analyze and assess the performance of smart grid communication network.

  3. History and Performance of Chinese LSAT Test Takers.

    Science.gov (United States)

    Wang, Xiang Bo; Harris, Vincent

    Although the Law School Admission Test (LSAT) has been administered to Chinese test takers in Taiwan and Hong Kong for more than 22 years and in China for the past decade, there is very little documentation on the history, test taker volumes, performance, or law school admission rates of these candidates. The current study addresses the following…

  4. ASME performance test on TVA Sequoyah Unit 1

    International Nuclear Information System (INIS)

    In April 1983 an ASME Performance Test was conducted on the Sequoyah 1 nuclear turbine-generator unit. Test data was collected using a mobile computer-controlled data-acquisition system. Excellent and consistent test results were achieved which showed that the unit performed better than expected. Earlier calorimetric analysis had indicated that the unit was not generating the expected electrical output. These earlier results were based on final feedwater flow measurement using permanently-installed station venturis. The ASME tests, which employed calibrated ASME throat-tap nozzles to measure feedwater flow, showed that the permanently-installed venturis had been indicating high, thereby causing the unit to be operated at less than 100% thermal power prior to the ASME test. The causes of this discrepancy are discussed in the paper. This paper includes a description of the test program and testing procedures and the performance of the major components of the heat cycle

  5. Performance testing of CANDU MOX fuel

    International Nuclear Information System (INIS)

    CANDU fuel bundles containing 0.5 wt % plutonium in natural uranium were fabricated at Chalk River Laboratories and were successfully irradiated in the NRU reactor at powers up to 65 kW/m and to burnups ranging from 13 to 23 MW·d/kg HE. Two of the bundles experienced power histories that bound the normal powers and burnups of natural UO2 CANDU fuel (2 fuel. Significantly more grain growth was observed than that typically expected for UO2 fuel; however, this increase in grain growth had no apparent effect on the overall performance of the fuel. Pellet-centre columnar grain growth was accompanied by plutonium homogenization. Two other MOX bundles operated to extended burnups of 19 to 23 MW·d/kg HE. Burnup extension above 15 MW·d/kg HE had no apparent effect on sheath strain or grain growth, and only a small effect on FGR and the amount of oxide observed on the inner surface of the sheath. (author)

  6. Off-gas treatment for pressurized water reactors by absorption of xenon and krypton in fluorocarbons

    International Nuclear Information System (INIS)

    Pilot plant tests showed selective absorption of krypton and xenon in dichlorodifluoromethane produced concentrations as low as 40 ppb and 3 ppb, respectively. Satisfactory operation was demonstrated for a variety of carrier gases including hydrogen, nitrogen, air, helium, and argon. Charcoal absorption, cryogenic absorption, and cryogenic distillation techniques were compared disadvantageously to the fluorocarbon solvent method. (PCS)

  7. Fenestration System Performance Research, Testing, and Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Jim Benney

    2009-11-30

    The US DOE was and is instrumental to NFRC's beginning and its continued success. The 2005 to 2009 funding enables NFRC to continue expanding and create new, improved ratings procedures. Research funded by the US DOE enables increased fenestration energy rating accuracy. International harmonization efforts supported by the US DOE allow the US to be the global leader in fenestration energy ratings. Many other governments are working with the NFRC to share its experience and knowledge toward development of their own national fenestration rating process similar to the NFRC's. The broad and diverse membership composition of NFRC allows anyone with a fenestration interest to come forward with an idea or improvement to the entire fenestration community for consideration. The NFRC looks forward to the next several years of growth while remaining the nation's resource for fair, accurate, and credible fenestration product energy ratings. NFRC continues to improve its rating system by considering new research, methodologies, and expanding to include new fenestration products. Currently, NFRC is working towards attachment energy ratings. Attachments are blinds, shades, awnings, and overhangs. Attachments may enable a building to achieve significant energy savings. An NFRC rating will enable fair competition, a basis for code references, and a new ENERGY STAR product category. NFRC also is developing rating methods to consider non specular glazing such as fritted glass. Commercial applications frequently use fritted glazing, but no rating method exists. NFRC is testing new software that may enable this new rating and contribute further to energy conservation. Around the world, many nations are seeking new energy conservation methods and NFRC is poised to harmonize its rating system assisting these nations to better manage and conserve energy in buildings by using NFRC rated and labeled fenestration products. As this report has shown, much more work needs to be done to continues research to improve existing ratings and develop new ones. NFRC needs to continue the work it has begun in several nations to implement the NFRC rating system that has been introduced. Many nations are eager to accept the expertise NFRC can offer to achieve energy conservation goals. NFRC looks forward to a continues partnership with the US Department of Energy to cooperatively achieve both.

  8. Spacecraft Quasi-Static Test Performed on a Shaker

    Science.gov (United States)

    Sadkin, Y.

    2004-08-01

    The TECSAR S/C, a Synthetic Aperture Radar (SAR) technology demonstration satellite is being developed by Israel Aerospace Industries (IAI). The Structural Model (SM) has successfully completed its qualification program at the IAI-MBT testing center. The TECSAR Structural Model (SM) Quasi-Static (QS) test was performed as part of the structural qualification program that is comprised of sinusoidal vibration, acoustic and pyro-shock tests. The QS test was performed on a shaker by a controlled sinusoidal sweep vibration. This method was selected because of its simplicity and cost and time savings considerations. It also enabled using the same specimen for all tests, QS as well as sine vibration, acoustic and pyro-shock tests, with only slight modifications. Thus all the test objectives were fully achieved in a most cost- effective way. This paper discusses the rationale and advantages of quasi-static testing on a shaker. It provides detailed information about actual QS implementation and a summary of the QS test that was performed on TECSAR S/C. Following a brief description of the TECSAR S/C and a definition of the quasi-static qualification loads, the test objectives and the optional testing methods are detailed with a discussion of the considerations and decision to select the way to perform this test on a shaker. Test specimen descriptions including the TECSAR SM installation and test instrumentation (load cells, accelerometers, strain gages) are summarized. Photogrammetry technique was used to establish residual dimensional deviations. The quasi-static test is then described with test results validation, evaluation and comparison to FEM results. Finally, the main conclusions are given.

  9. Thermionic Fuel Element performance: TFE Verification Program. Final test report

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The program objective is to demonstrate the technology readiness of a Thermionic Fuel Element (TFE) suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full power life of 7 years. A TFE was designed that met the reliability and lifetime requirements for a 2 MW(e) conceptual reactor design. Analysis showed that this TFE could be used over the range of 0.5 to 5 megawatts. This was used as the basis for designing components for test and evaluation. The demonstration of a 7-year component lifetime capability was through the combined use of analytical models and accelerated, confirmatory tests in a fast test reactor. Iterative testing was performed in which the results of one test series led to evolutionary improvements in the next test specimens. The TFE components underwent screening and initial development testing in ex-reactor tests. Several design and materials options were considered for each component. As screening tests permitted, down selection occurred to very specific designs and materials. In parallel with ex-reactor testing, and fast reactor component testing, components were integrated into a TFE and tested in the TRIGA test reactor at GA. Realtime testing of partial length TFEs was used to test support, alignment and interconnective TFE components, and to verify TFE performance in-reactor with integral cesium reservoirs. Realtime testing was also used to verify the relation between TFE performance and fueled emitter swelling, to test the durability of intercell insulation, to check temperature distributions, and to verify the adequacy over time of the fission gas venting channels. Predictions of TFE lifetime rested primarily on the accelerated component testing results, as correlated and extended to realtime by the use of analytical models.

  10. The Impact of Test Anxiety on Test Performance among Iranian EFL Learners

    Directory of Open Access Journals (Sweden)

    Minoo Alemi

    2010-09-01

    Full Text Available As an affective factor, test-taking anxiety has been investigated in different contexts in the
    past two decades. However, the mixed results of the relationship between test-taking anxiety and
    L2 learners’ test performance show that the instrumentation for the assessment of test-taking
    anxiety and the factors comprising the construct of test-taking anxiety trait requires more
    investigation in order to shed more light on the issue. To this end, a test-taking anxiety
    questionnaire (Sarason, 1975 [27] and a general English test were administered to 164 ESP
    students of Engineering enrolled in a B.A. program to document (a the degree of their test taking
    anxiety, (b the relationship between test-taking anxiety and test performance, and (c the factor
    loadings of anxiety based on exploratory factor analysis. The results show that L2 learners’ test
    anxiety is rather low, with most of its components having no significant negative correlation with
    test performance. The results of exploratory factor analysis reveal the loading of test anxiety trait
    on the rather overlapping three factors of specific test anxiety, general test anxiety, and test preparation anxiety. However, out of these factors, general test anxiety, due to its functioning at the higher-order affective level, has a significant negative correlation with test performance. By contrast, test preparation anxiety, in view of facilitating test performance, manifests a positive, albeit non-significant, correlation with test performance. The results have two implications: (a as the correlations and loadings on test anxiety factors proved to be of both negative and positive types, the anxiety questionnaire is not monolithic and hence it is not a proper measure in case the linear relationship between test anxiety and test performance is the focus of the study; and (b test anxiety does not seem to much influence on test performance at the micro- test-specific level.

  11. Personal dosimetry performance testing in the United States

    International Nuclear Information System (INIS)

    The basis for personal dosimetry performance testing in the United States is ANSI/HPS N13.11. Now in it's fourth edition, this standard has been in place since 1983. Testing under this standard is administered by the National Voluntary Laboratory Accreditation Program (NVLAP), and accreditation of dosimetry processors under this program is required by U.S. Nuclear Regulatory Commission (NRC) regulations. The U.S. Department of Energy (DOE) also maintains a testing program for its laboratories and contractors, administered by the Department of Energy Laboratory Accreditation Program (DOELAP). One of the goals of this current revision was the modification of ANSI/HPS N13.11 to allow acceptance by both testing programs in order to bring harmonization to U.S. personal dosemeter performance testing. The testing philosophy of ANSI/HPS N13.11 has always combined elements of type testing and routine performance testing and is thus different from the testing philosophy used in the rest of the world. In this paper, the history of performance testing in the U.S. is briefly reviewed. Also described is the revision that produced the fourth edition of this standard, which has taken place over the last three years (2005-2008) by a working group representing national standards laboratories, government laboratories, the military, dosimetry vendors, universities and the nuclear power industry. (author)

  12. Personal dosimetry performance testing in the United States

    International Nuclear Information System (INIS)

    The basis for personal dosimetry performance testing in the United States is ANSI/HPS N13.11. Now in its fourth edition, this standard has been in place since 1983. Testing under this standard is administered by the National Voluntary Laboratory Accreditation Program (NVLAP), and accreditation of dosimetry processors under this program is required by U.S. Nuclear Regulatory Commission (NRC) regulations. The U.S. Department of Energy (DOE) also maintains a testing program for its laboratories and contractors, administered by the Department of Energy Laboratory Accreditation Program (DOELAP). One of the goals of this current revision was the modification of ANSI/HPS N13.11 to allow acceptance by both testing programs in order to bring harmonization to U.S. personal dosemeter performance testing. The testing philosophy of ANSI/HPS N13.11 has always combined elements of type testing and routine performance testing and is thus different from the testing philosophy used in the rest of the world. In this paper, the history of performance testing in the U.S. is briefly reviewed. Also described is the revision that produced the fourth edition of this standard, which has taken place over the last three years (2005-2008) by a working group representing national standards laboratories, government laboratories, the military, dosimetry vendors, universities and the nuclear power industry. (author)

  13. Performance Testing of the CMS Cathode Strip Chambers

    CERN Document Server

    Breedon, Richard; Andreev, M. Tripathi V; Arisaka, Katsushi; Cline, David; Hauser, Jay; Ignatenko, Mikhail; Lisowsky, B; Matthey, Christina; Rakness, Gregory; Wenman, Daniel

    2009-01-01

    The production, installation, and testing of 468 cathode strip chambers for the endcap muon system of the CMS experiment played a critical role in the preparation of the endcap muon system for the final commissioning. Common testing procedures and sets of standard equipment were used at 5 international assembly centers. The chambers were then thoroughly retested after shipment to CERN. Final testing was performed after chamber installation on the steel disks in the CMS detector assembly building. The structure of the detector quality control procedure is presented along with the results of chamber performance validation tests.

  14. Laboratory Test System Design for Star Sensor Performance Evaluation

    Directory of Open Access Journals (Sweden)

    JUN YANG

    2012-04-01

    Full Text Available A novel laboratory test system is designed to evaluate the performance of star sensors. Two evaluation methods are presented, the star images simulation test and the zenith observation experiments method. In star image simulation, the nebula and moon lights enter into the CCD field of view (FOV is considered. A new algorithm for fast access star catalog is also designed to enhance the speed of star image simulation. Zenith observation provides a new method to test accuracy of star sensor without telescope. The results demonstrate that the test system is effectively to evaluate the star pattern recognition rates and relatively accuracy performance of star sensors.

  15. DOE mixed waste metals partition in a rotary kiln wet off-gas system

    International Nuclear Information System (INIS)

    In 1996, the Savannah River Site plans to begin operation of the Consolidated Incineration Facility (CIF) to treat solid and liquid RCRA hazardous and mixed wastes. Test burns were conducted using surrogate CIF wastes spiked with hazardous metals and organics. The partition of metals between the kiln bottom ash, scrubber blowdown solution, and stack gas was measured as a function of kiln temperature, waste chloride content, and waste form (liquid or solid). Three waste simulants were used in these tests, a high and low chloride solid waste mix (paper, plastic, latex, PVC), and a liquid waste mix (benzene and chlorobenzene). An aqueous solution containing: antimony, arsenic, barium, cadmium, chromium, lead, mercury, nickel, silver, and thallium was added to the waste to determine metals fate under various combustion conditions. Test results were used to divide the metals into three general groups, volatile, semi-volatile, and nonvolatile metals. Mercury was the only volatile metal. No mercury remained in the kiln bottom ash under any incineration condition. Lead, cadmium, thallium, and silver exhibited semi-volatile behavior. The partition between the kiln ash, blowdown, and stack gas depended on incineration conditions. Chromium, nickel, barium, antimony, and arsenic exhibited nonvolatile behavior, with greater than 90 wt % of the metal remaining in the kiln bottom ash. Incineration temperature had a significant effect on the partition of volatile and semi-volatile metals, and no effect on nonvolatile metal partition. As incineration temperatures were increased, the fraction of metal leaving the kiln increased. Three metals, lead, cadmium, and mercury showed a relationship between chloride concentration in the waste and metals partition. Increasing the concentration of chlorides in the waste or burning liquid waste versus solid waste resulted in a larger fraction of metal exiting the kiln

  16. Development of refining technology of Xe recovered from reprocessing plant off gas for commercial use

    International Nuclear Information System (INIS)

    The present study is aiming to develop refining system of recovered Xe at Krypton Recovery Facility (KRF) by pressure swing adsorption with purge system for commercial use, such as to lighting and ion engine. Refined Xe with low radioactive Kr was prepared through three series of adsorption column packing synthetic Ca-X zeolite. And the computer simulation by molecular mechanics was practiced to obtain purification mechanism for Xe/Kr mixed gas. The simulation was fitted with the practical adsorption test. So the effects of pressure and cation were studied about adsorption. (author)

  17. Performances on Symbol Digit Modalities Test, Color Trails Test, and modified Stroop test in a healthy, elderly Danish sample.

    Science.gov (United States)

    Vogel, Asmus; Stokholm, Jette; Jørgensen, Kasper

    2013-01-01

    This study presents Danish data for the Symbol Digit Modalities Test (SDMT), Color Trails Test (CTT), and a modified Stroop test from 100 subjects aged 60-87 years. Among the included demographic variables, age had the highest impact on test performances. Thus, the study presents separate data for different age groups. For SDMT and CTT1, Danish Adult Reading Test (DART) score also had a significant impact on test performances. The incongruent version of the modified Stroop test was significantly correlated to education. Moderate and significant correlations were found between the three tests. Even though the three tests are commonly used, few normative data for elderly exists. SDMT and CTT performances from this study were in the same range as previously published international norms, but the validity of the result from the modified Stroop test could not be investigated. PMID:23013462

  18. Performances on Symbol Digit Modalities Test, Color Trails Test, and modified Stroop test in a healthy, elderly Danish sample

    DEFF Research Database (Denmark)

    Vogel, Asmus; Stokholm, Jette

    2013-01-01

    This study presents Danish data for the Symbol Digit Modalities Test (SDMT), Color Trails Test (CTT), and a modified Stroop test from 100 subjects aged 60-87 years. Among the included demographic variables, age had the highest impact on test performances. Thus, the study presents separate data for different age groups. For SDMT and CTT1, Danish Adult Reading Test (DART) score also had a significant impact on test performances. The incongruent version of the modified Stroop test was significantly correlated to education. Moderate and significant correlations were found between the three tests. Even though the three tests are commonly used, few normative data for elderly exists. SDMT and CTT performances from this study were in the same range as previously published international norms, but the validity of the result from the modified Stroop test could not be investigated.

  19. Performance of a large-scale melter and off-gas system utilizing simulated SRP DWPF waste

    International Nuclear Information System (INIS)

    The Department of Energy and the DuPont Company have begun construction of a Defense Waste Processing Facility to immobilize radioactive waste now stored as liquids at the Department of Energy's Savannah River Plant. The immobilization process solidifies waste sludge by vitrification into a leach resistant borosilicate glass. Development of the process has been the responsibility of the Savannah River Laboratory. As part of the development, two large-scale glass melter systems have been designed and operated with simulated waste. Experimental data from these operations show that process requirements will be met

  20. Achievement Test Performance of Intellectually Advanced Preschool Children.

    Science.gov (United States)

    Shorr, David N.; And Others

    1980-01-01

    The study assessed the feasibility of using the Peabody Individual Achievement Test (PIAT) with 24 intellectually precocious preschoolers. Ss' performances suggested that the PIAT is an appropriate instrument for assessing the academic skills of intellectually advanced preschoolers. (SBH)

  1. Index Tests Performed on a Francis Turbine from HPP Ruieni

    Directory of Open Access Journals (Sweden)

    Adrian Cuzmo?

    2008-10-01

    Full Text Available Index test are a set of measurements performed on hydro units in order to determine the relative flow and the relative efficiency. This method is usually used on refurbished hydro units, before and after rehabilitation.

  2. Legal consequences of not performing requisite pre-anaesthesia test

    Directory of Open Access Journals (Sweden)

    2008-01-01

    Full Text Available Suggested Precautions Perform sensitive test before giving anaesthesia and specifically record the said fact in pre-operative notes.Necessary precautions prescribed and followed in medicine must be strictly followed and duly recorded.

  3. 40 CFR 60.723 - Performance tests and compliance provisions.

    Science.gov (United States)

    2010-07-01

    ...Surface Coating: Surface Coating of Plastic Parts for Business Machines § 60.723 Performance tests and compliance provisions...Air-assistd airless spray .40 Prime and color coats. Electrostatic air spray .40 Do. where n is the number of...

  4. 40 CFR 63.1349 - Performance testing requirements.

    Science.gov (United States)

    2010-07-01

    ...source subject to limitations on emissions of THC shall demonstrate initial compliance with the THC limit by operating a continuous emission monitor...performance test shall be three hours, and the average THC concentration (as calculated from the...

  5. Index Tests Performed on a Francis Turbine from HPP Ruieni

    OpenAIRE

    Adrian Cuzmo?; Cosmin Dumbrav?; Constantin Viorel Câmpian; Dorian Nedelcu

    2008-01-01

    Index test are a set of measurements performed on hydro units in order to determine the relative flow and the relative efficiency. This method is usually used on refurbished hydro units, before and after rehabilitation.

  6. Predicting road test performance in drivers with stroke.

    Science.gov (United States)

    Barco, Peggy P; Wallendorf, Michael J; Snellgrove, Carol A; Ott, Brian R; Carr, David B

    2014-01-01

    OBJECTIVE. The aim of this study was to develop a brief screening battery to predict the on-road performance of drivers who had experienced a stroke. METHOD. We examined 72 people with stroke referred by community physicians to an academic rehabilitation center. The outcome variable was pass or fail on the modified Washington University Road Test. Predictor measures were tests of visual, motor, and cognitive functioning. RESULTS. The best predictive model for failure on the road test included Trail Making Test Part A and the Snellgrove Maze Task(®). CONCLUSION. A screening battery that can be performed in less than 5 min was able to assist in the prediction of road test performance in a sample of drivers with stroke. A probability of failure calculator may be useful for clinicians in their decision to refer clients with stroke for a comprehensive driving evaluation. PMID:24581409

  7. ATLAS SCT Endcap module and system test performance

    CERN Document Server

    Bates, R

    2003-01-01

    Silicon detector modules for the Endcap of the ATLAS semiconductor tracker have been designed and many devices have now been fabricated and tested. Results obtained from testing a module individually with electrical test pulses injected into the front-end are presented. These modules are shown to fulfill the electrical requirements demanded of the devices. The modules however, must operate in a large-scale system with many hundreds of modules in close proximity to each other. To validate the electrical performance of such a system, a "system test" has been established at CERN. The grounding and shielding of the Endcap is vital for the performance of the experiment. Therefore the electrical performance of the modules with various grounding schemes has been explored in detail at the system test and is presented here.

  8. ATLAS SCT Endcap module and system test performance

    CERN Document Server

    Bates, R

    2004-01-01

    Silicon detector modules for the Endcap of the ATLAS semiconductor tracker have been designed and many devices have now been fabricated and tested. Results obtained from testing a module individually with electrical test pulses injected into the front-end are presented. These modules are shown to fulfill the electrical requirements demanded of the devices. The modules however, must operate in a large-scale system with many hundreds of modules in close proximity to each other. To validate the electrical performance of such a system, a "system test" has been established at CERN. The grounding and shielding of the Endcap is vital for the performance of the experiment. Therefore the electrical performance of the modules with various grounding schemes has been explored in detail at the system test and is presented here. (10 refs).

  9. Current Status and Performance Tests of Korea Heat Load Test Facility KoHLT-EB

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sukkwon; Jin, Hyunggon; Shin, Kyuin; Choi, Boguen; Lee, Eohwak; Yoon, Jaesung; Lee, Dongwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Duckhoi; Cho, Seungyon [National Fusion Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    A commissioning test has been scheduled to establish the installation and preliminary performance experiments of the copper hypervapotron mockups. And a qualification test will be performed to evaluate the CuCrZr duct liner in the ITER neutral beam injection facility and the ITER first wall small-scale mockups of the semi-prototype, at up to 1.5 and 5 MW/m{sup 2} high heat flux. Also, this system will be used to test other PFCs for ITER and materials for tokamak reactors. Korean high heat flux test facility(KoHLT-EB; Korea Heat Load Test facility - Electron Beam) by using an electron beam system has been constructed in KAERI to perform the qualification test for ITER blanket FW semi-prototype mockups, hypervapotron cooling devices in fusion devices, and other ITER plasma facing components. The commissioning and performance tests with the supplier of e-gun system have been performed on November 2012. The high heat flux test for hypervapotron cooling device and calorimetry were performed to measure the surface heat flux, the temperature profile and cooling performance. Korean high heat flux test facility for the plasma facing components of nuclear fusion machines will be constructed to evaluate the performance of each component. This facility for the plasma facing materials will be equipped with an electron beam system with a 60 kV acceleration gun.

  10. Current Status and Performance Tests of Korea Heat Load Test Facility KoHLT-EB

    International Nuclear Information System (INIS)

    A commissioning test has been scheduled to establish the installation and preliminary performance experiments of the copper hypervapotron mockups. And a qualification test will be performed to evaluate the CuCrZr duct liner in the ITER neutral beam injection facility and the ITER first wall small-scale mockups of the semi-prototype, at up to 1.5 and 5 MW/m2 high heat flux. Also, this system will be used to test other PFCs for ITER and materials for tokamak reactors. Korean high heat flux test facility(KoHLT-EB; Korea Heat Load Test facility - Electron Beam) by using an electron beam system has been constructed in KAERI to perform the qualification test for ITER blanket FW semi-prototype mockups, hypervapotron cooling devices in fusion devices, and other ITER plasma facing components. The commissioning and performance tests with the supplier of e-gun system have been performed on November 2012. The high heat flux test for hypervapotron cooling device and calorimetry were performed to measure the surface heat flux, the temperature profile and cooling performance. Korean high heat flux test facility for the plasma facing components of nuclear fusion machines will be constructed to evaluate the performance of each component. This facility for the plasma facing materials will be equipped with an electron beam system with a 60 kV acceleration gun

  11. Verification Test of Hydraulic Performance for Reactor Coolant Pump

    International Nuclear Information System (INIS)

    According to this project, basic design for prototype pump and model pump of reactor coolant pump and test facilities has been completed. Basic design for prototype pump to establish structure, dimension and hydraulic performance has been completed and through primary flow analysis by computational fluid dynamics(CFD), flow characteristics and hydraulic performance have been established. This pump was designed with mixed flow pump having the following design requirements; specific velocity(Ns); 1080.9(rpm·m3/m·m), capacity; 3115m3/h, total head ; 26.3m, pump speed; 1710rpm, pump efficiency; 77.0%, Impeller out-diameter; 349mm, motor output; 360kw, design pressure; 17MPaG. The features of the pump are leakage free due to no mechanical seal on the pump shaft which insures reactor's safety and law noise level and low vibration due to no cooling fan on the motor which makes eco-friendly product. Model pump size was reduced to 44% of prototype pump for the verification test for hydraulic performance of reactor coolant pump and was designed with mixed flow pump and canned motor having the following design requirements; specific speed(NS); 1060.9(rpm·m3/m·m), capacity; 539.4m3/h, total head; 21.0m, pump speed; 3476rpm, pump efficiency; 72.9%, Impeller out-diameter; 154mm, motor output; 55kw, design pressure; 1.0MPaG. The test facilities were designed for verification test of hydraulic performance suitable for pump performance test, homologous test, NPSH test(cavitation), cost down test and pressure pulsation test of inlet and outlet ports. Test tank was designed with testing capacity enabling up to 2000m3/h and design pressure 1.0MPaG. Auxiliary pump was designed with centrifugal pump having capacity; 1100m3/h, total head; 42.0m, motor output; 190kw

  12. Fracture testing and performance of beryllium copper alloy C 17510

    International Nuclear Information System (INIS)

    A series of test programs was undertaken on copper beryllium alloy C 17510 for several variations in material process and chemistry. These variations in C 17510 were primarily optimized for combinations of strength and conductivity. While originally intended for use as cyclically loaded high-field, high-strength conductors in fusion energy research, material testing of C 17510 has indicated that it is an attractive and economical alternative for a host of other structural, mechanical and electrical applications. ASTM tests performed on three variations of C 17510 alloys included both J-integral and plane strain fracture toughness testing (E813, E399) and fatigue crack growth rate tests (E647), as well as verifying tensile, hardness, Charpy, and other well defined mechanical properties. Fracture testing was performed at both room and liquid nitrogen temperatures, which bound the thermal environment anticipated for the fusion components being designed. Fatigue crack propagation stress ratios ranged from nominal zero to minus one at each temperature

  13. 40 CFR 63.805 - Performance test methods.

    Science.gov (United States)

    2010-07-01

    ...STANDARDS FOR HAZARDOUS AIR POLLUTANTS FOR SOURCE CATEGORIES (CONTINUED...determine the HAP concentration of gaseous air streams. The test shall...f)(6) shall perform a gaseous emission test using the following...area with other nonaffected gaseous emission sources from all...

  14. Performing Identities in Speaking Tests: Co-Construction Revisited

    Science.gov (United States)

    Norton, Julie

    2013-01-01

    Poststructuralist perspectives on the discursive construction of identity and critical approaches to linguistics, discourse analysis, and language testing have contributed to a growing awareness of the complex social nature of performance in speaking tests. In this article, I explore how the concept of co-construction is useful to understand how…

  15. Thermal Performance Testing of EMU and OSS Liquid Cooling Garments

    Science.gov (United States)

    Rhodes, Richard; Bue, Grant; Hakam, Mary

    2012-01-01

    A test was conducted to evaluate three factors influencing the thermal performance of liquid cooling garments (LCG): (1) the comparable thermal performance of an Oceaneering developed engineering evaluation unit (EEU) prototype LDG, (2) the effect of the thermal comfort undergarment (TCU), and (3) the performance of a torso or upper body only LCG configuration. To evaluate the thermal performance of each configuration a metabolic test was conducted, utilizing suited subjects to generate the metabolic heat. For this study three (3) test subjects of similar health and weight produced a metabolic load on the LDG configuration by either resting (300-600 BTU/hr), walking at a slow pace (1200 BRU/hr), and walking at a brisk pace (2200 BTU/hr), as outlined in Figure 1, the metabolic profile. During the test, oxygen consumption, heart rate, relative humidity, air flow, inlet and outlet air pressure, inlet and outlet air temperature, delta air temperature, water flow (100 lb/hr), inlet water temperature (64 F), delta water temperature, water pressure, core body temperature, skin temperature, and sweat loss data was recorded. Four different test configurations were tested, with one configuration tested twice, as outlined in Table 1. The test was conducted with the suit subjects wearing the Demonstrator Suit, pressurized to vent pressure (approximately 0.5 psig). The demonstrator suit has an integrated ventilation duct system and was used to create a relevant environment with a captured ventilation return, an integrated vent tree, and thermal insulation from the environment.

  16. High explosive corner turning performance and the LANL Mushroom test

    Energy Technology Data Exchange (ETDEWEB)

    Hill, L.G.; Seitz, W.L.; Forest, C.A.; Harry, H.H.

    1997-09-01

    The Mushroom test is designed to characterize the corner turning performance of a new generation of less insensitive booster explosives. The test is described in detail, and three corner turning figures-of-merit are examined using pure TATB (both Livermore`s Ultrafine and a Los Alamos research blend) and PBX9504 as examples.

  17. Laboratory Test System Design for Star Sensor Performance Evaluation

    OpenAIRE

    JUN YANG; Bin Liang; Tao Zhang; Jing-yan Song; Liang-liang Song

    2012-01-01

    A novel laboratory test system is designed to evaluate the performance of star sensors. Two evaluation methods are presented, the star images simulation test and the zenith observation experiments method. In star image simulation, the nebula and moon lights enter into the CCD field of view (FOV) is considered. A new algorithm for fast access star catalog is also designed to enhance the speed of star image simulation. Zenith observation provides a new method to test accuracy of star sensor wit...

  18. Laboratory Performance Testing of Residential Window Air Conditioners

    Energy Technology Data Exchange (ETDEWEB)

    Winkler, J.; Booten, C.; Christensen, D.; Tomerlin, J.

    2013-03-01

    Window air conditioners are the dominant cooling product for residences, in terms of annual unit sales. They are inexpensive, portable and can be installed by the owner. For this reason, they are an attractive solution for supplemental cooling, for retrofitting air conditioning into a home which lacks ductwork, and for renters. Window air conditioners for sale in the United States are required to meet very modest minimum efficiency standards. Four window air conditioners' performance were tested in the Advanced HVAC Systems Laboratory on NREL's campus in Golden, CO. In order to separate and study the refrigerant system's performance, the unit's internal leakage pathways, the unit's fanforced ventilation, and the leakage around the unit resulting from installation in a window, a series of tests were devised that focused on each aspect of the unit's performance. These tests were designed to develop a detailed performance map to determine whole-house performance in different climates. Even though the test regimen deviated thoroughly from the industry-standard ratings test, the results permit simple calculation of an estimated rating for both capacity and efficiency that would result from a standard ratings test. Using this calculation method, it was found that the three new air conditioners' measured performance was consistent with their ratings. This method also permits calculation of equivalent SEER for the test articles. Performance datasets were developed across a broad range of indoor and outdoor operating conditions, and used them to generate performance maps.

  19. Continuous nitrous oxide abatement in a novel denitrifying off-gas bioscrubber.

    Science.gov (United States)

    Frutos, Osvaldo D; Arvelo, Ilan A; Pérez, Rebeca; Quijano, Guillermo; Muñoz, Raúl

    2015-04-01

    The potential of a bioscrubber composed of a packed bed absorption column coupled to a stirred tank denitrification bioreactor (STR) was assessed for 95 days for the continuous abatement of a diluted air emission of N2O at different liquid recycling velocities. N2O removal efficiencies of up to 40?±?1 % were achieved at the highest recirculation velocity (8 m h(-1)) at an empty bed residence time of 3 min using a synthetic air emission containing N2O at 104?±?12 ppmv. N2O was absorbed in the packed bed column and further reduced in the STR at efficiencies >80 % using methanol as electron donor. The long-term operation of the bioscrubber suggested that the specialized N2O degrading community established was not able to use N2O as nitrogen source. Additional nitrification assays showed that the activated sludge used as inoculum was not capable of aerobically oxidizing N2O to nitrate or nitrite, regardless of the inorganic carbon concentration tested. Denitrification assays confirmed the ability of non-acclimated activated sludge to readily denitrify N2O at a specific rate of 3.9 mg N2O g VSS h(-1) using methanol as electron donor. This study constitutes, to the best of our knowledge, the first systematic assessment of the continuous abatement of N2O in air emission. A characterization of the structure of the microbial population in the absorption column by DGGE-sequencing revealed a high microbial diversity and the presence of heterotrophic denitrifying methylotrophs. PMID:25547842

  20. Dynamic Performance Characteristic Tests of Real Scale Lead Rubber Bearing for the Evaluation of Performance Criteria

    International Nuclear Information System (INIS)

    Dynamic characteristic tests of full scale lead rubber bearing were performed for the evaluation of performance criteria of isolation system for nuclear power plants. For the dynamic test for a full scale rubber bearing, two 1500mm diameter lead rubber bearings were manufactured. The viewpoints of this dynamic test are determination of an ultimate shear strain level of lead rubber bearing, behavior of rubber bearing according to static and dynamic input motion, sinusoidal and random (earthquake) motion, and 1-dimentional and 2-dimensional input motion. In this study, seismic isolation device tests were performed for the evaluation of performance criteria of isolation system. Through this test, it can be recognized that in the case of considering a mechanical property test, dynamic and multi degree of loading conditions should be determined. But these differences should be examined how much affect to the global structural behavior

  1. Cr(VI) Generation During Flaring of CO-Rich Off-Gas from Closed Ferrochromium Submerged Arc Furnaces

    Science.gov (United States)

    du Preez, S. P.; Beukes, J. P.; van Zyl, P. G.

    2015-04-01

    Ferrochromium (FeCr) is the only source of new Cr units used in stainless steel production, which is a vital modern day alloy, making FeCr equally important. Small amounts of Cr(VI) are unintentionally formed during several FeCr production steps. One such production step is the flaring of CO-rich off-gas from closed submerged arc furnaces (SAF), for which Cr(VI) formation is currently not quantified. In this study, the influence of flaring temperature, size of the particles passing through the flare, and retention time within the flame were investigated by simulating the process on laboratory scale with a vertical tube furnace. Multiple linear regression (MLR) analysis was conducted on the overall dataset obtained, which indicated that retention time had the greatest impact on pct Cr(VI) conversion, followed by particle size and temperature. The MLR analysis also yielded an optimum mathematical solution, which could be used to determine the overall impact of these parameters on pct Cr(VI) conversion. This equation was used to determine realistic and unrealistic worst-case scenario pct Cr(VI) conversions for actual FeCr SAFs, which yielded 2.7 × 10-2 and 3.5 × 10-1 pct, respectively. These values are significantly lower than the current unsubstantiated pct Cr(VI) conversion used in environmental impact assessments for FeCr smelters, i.e., 0.8 to 1 pct.

  2. Report on long range alpha detector (LRAD) performance tests

    CERN Document Server

    Kobayashi, H; Ishikawa, H; Unno, M; Yoshida, T

    2002-01-01

    At present, alpha contamination measurement on objects is conducted with ZnS scintillation survey meter (direct method) and smear test (indirect method). But it is difficult to measure large and complicated objects by direct method. Long Range Alpha Detector (LRAD) was produced as a solution for this problem. We carried out performance tests of this LRAD. As a result of the performance tests, we confirmed the linear relation between the measurement values of LRAD and alpha-radioactivity on the surface of objects.

  3. Spent nuclear fuel storage -- Performance tests and demonstrations

    International Nuclear Information System (INIS)

    This report summarizes the results of heat transfer and shielding performance tests and demonstrations conducted from 1983 through 1992 by or in cooperation with the US Department of Energy (DOE), Office of Commercial Radioactive Waste Management (OCRWM). The performance tests consisted of 6 to 14 runs involving one or two loadings, usually three backfill environments (helium, nitrogen, and vacuum backfills), and one or two storage system orientations. A description of the test plan, spent fuel load patterns, results from temperature and dose rate measurements, and fuel integrity evaluations are contained within the report

  4. Thermal performance testing of flat-plate collectors

    Energy Technology Data Exchange (ETDEWEB)

    Rojas, D.; Beermann, J.; Klein, S.A.; Reindl, D.T. [Solar Energy Laboratory, University of Wisconsin - Madison, Madison, WI (United States)

    2008-08-15

    Existing standards for testing the performance of flat-plate solar collectors are documented in ASHRAE 93 [ANSI/ASHRAE Standard 93-2003, 2003. Methods of Testing to Determine Thermal Performance of Solar Collectors, ISSN: 1041-2336, ASHRAE, Inc., 1791 Tullie Circle, Ne, Atlanta, GA30329], ISO 9806-1 [ISO Standard 9806-1:1994(E), 1994. Test Methods for Solar Collectors - Part 1: Thermal Performance of Glazed Liquid Heating Collectors Including Pressure Drop, ISO, Case Postale 56, CH-1211 Geneve 20, Switzerland] and EN12975-2 [European Standard EN12975-2:2001, 2001. Thermal Solar Systems and Components - Solar Collectors - Part 2: Test Methods, CEN, Rue de Stasart, 36, B-1050, Brussels]. The ASHRAE 93 standard requires an experimental determination of the steady-state collector efficiency under prescribed environmental conditions for a range of collector fluid temperatures. Each test requires a minimum of 20 min and 22 tests are required to fully characterize a collector's thermal performance. The ASHRAE 93 testing procedure is further complicated by the fact that the prescribed weather conditions do not often occur in some locations, which prolongs the time required to conduct the performance tests for a given collector. The EN12975-2 collector test procedure provides an alternative transient test method that can be conducted over a larger range of environmental conditions. This paper compares the results obtained by applying the EN12975-2 standard with results obtained from the ASHRAE 93 steady-state tests for a well-designed single-glazed selective surface flat-plate collector. The collector thermal parameters, F{sub R}({tau}{alpha}){sub e} and F{sub R}U{sub L} obtained by the two test methods show good agreement. The incident angle modifier coefficient determined in the ASHRAE method, which uses a separate test for this purpose, was found to be more accurate than that determined in the transient method according to the EN12975-2 standard, which obtains this value and all other collector parameters in the same step. This transient method, however, uses a refined collector model that includes specific terms for the wind speed dependence and the collector thermal capacitance, which are absent in the ASHRAE model. The long-term collector thermal performance as a part of a water heating system was simulated using the efficiency curves derived from each of the test methods. The solar fractions obtained by simulation are within 7% for both cases. (author)

  5. Stereotype threat and the intellectual test performance of African Americans.

    Science.gov (United States)

    Steele, C M; Aronson, J

    1995-11-01

    Stereotype threat is being at risk of confirming, as self-characteristic, a negative stereotype about one's group. Studies 1 and 2 varied the stereotype vulnerability of Black participants taking a difficult verbal test by varying whether or not their performance was ostensibly diagnostic of ability, and thus, whether or not they were at risk of fulfilling the racial stereotype about their intellectual ability. Reflecting the pressure of this vulnerability, Blacks underperformed in relation to Whites in the ability-diagnostic condition but not in the nondiagnostic condition (with Scholastic Aptitude Tests controlled). Study 3 validated that ability-diagnosticity cognitively activated the racial stereotype in these participants and motivated them not to conform to it, or to be judged by it. Study 4 showed that mere salience of the stereotype could impair Blacks' performance even when the test was not ability diagnostic. The role of stereotype vulnerability in the standardized test performance of ability-stigmatized groups is discussed. PMID:7473032

  6. A Study of the Relationships Between Test Order, Physiological Arousal, and Intelligence and Achievement Test Performance.

    Science.gov (United States)

    Nighswander, James K.; Beggs, Donald L.

    The relative predictive abilities of two indices of test anxiety were investigated. The galvanic skin response (GSR) and the Test Anxiety Scale for Children (TASC) were used as predictor variables for IQ and achievement test performance. The results of multiple linear regression analysis indicated that neither the TASC nor the GSR, combined over…

  7. Performance demonstration experience for reactor pressure vessel shell ultrasonic testing

    International Nuclear Information System (INIS)

    The most ultrasonic testing techniques used by many vendors for pressurized water reactor (PWR) examinations were based on American Society of Mechanical Engineers 'Boiler and Pressurized Vessel Code' (ASME B and PV Code) Sections XI and V. The Addenda of ASME B and PV Code Section XI, Edition 1989 introduced Appendix VIII - 'Performance Demonstration for Ultrasonic Examination Systems'. In an effort to increase confidence in performance of ultrasonic testing of the operating nuclear power plants in United States, the ultrasonic testing performance demonstration examination of reactor vessel welds is performed in accordance with Performance Demonstration Initiative (PDI) program which is based on ASME Code Section XI, Appendix VIII requirements. This article provides information regarding extensive qualification preparation works performed prior EPRI guided performance demonstration exam of reactor vessel shell welds accomplished in January 1997 for the scope of Appendix VIII, Supplements IV and VI. Additionally, an overview of the procedures based on requirements of ASME Code Section XI and V in comparison to procedure prepared for Appendix VIII examination is given and discussed. The samples of ultrasonic signals obtained from artificial flaws implanted in vessel material are presented and results of ultrasonic testing are compared to actual flaw sizes. (author)

  8. 42 CFR 493.1467 - Condition: Laboratories performing high complexity testing; cytology general supervisor.

    Science.gov (United States)

    2010-10-01

    ...2010-10-01 false Condition: Laboratories performing high complexity testing...CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Personnel for Nonwaived Testing Laboratories Performing High Complexity Testing...

  9. 42 CFR 493.1447 - Condition: Laboratories performing high complexity testing; technical supervisor.

    Science.gov (United States)

    2010-10-01

    ...2010-10-01 false Condition: Laboratories performing high complexity testing...CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Personnel for Nonwaived Testing Laboratories Performing High Complexity Testing...

  10. Type test of TLD badge reader: parameters and performance

    International Nuclear Information System (INIS)

    Reliable and accurate estimation of individual occupational radiation doses requires standardization of not only the procedures and practices but also the standardized dosimeters and the measurement systems with stable performance. It is therefore important to quantify the effect of various variables on the overall performance of any new type of systems and to ascertain that the prescribed performance criteria (RSG-1.3) are met in actual practice. lAEA, IEC etc. have recommended tests, referred to as Type Test to quantify these aspects and demonstrate that the overall uncertainty is within the allowed limit. In India, the CaSO4:Dy based TLD badge was introduced for personnel monitoring following a satisfactory performance using manual reader with contact heating system. Since then, the TLD reader has undergone major changes and presently PC based N2 gas heating based semi automatic reader is under use. Recently, a new version of the semi automatic reader along with new software developed by a private manufacturer was subjected to type testing at Quality Assurance (QA) lab of RPAD. The paper summaries the method of testing, parameters tested, the acceptance criteria and the performance of the system on different parameter

  11. Performance testing and dose verification for extremity ring dosimetry

    International Nuclear Information System (INIS)

    The paper describes the testing performed on an extremity dosimetry system to measure the personal dose equivalent Hp(0.07) in photon and beta reference fields. This research refers to the American National Standard Institute to organize the performance testing for the INER's TLD-100H extremity ring dosimeters. The results show that tolerance level (L), absolute of bias (|B|) and standard deviation (S) for all categories of performance testing meet the ANSI N13.32 performance testing criteria. The performance testing results were suggested to be an important step of an accreditation procedure for the extremity ring dosimetry system in Taiwan. Besides, the dose evaluation of extremity ring dosimeters to measure Hp(0.07) in realistic fields of nuclear medicine is also verified. The reference values of Hp(0.07) were calculated using the Monte Carlo method normalized by the measured activity of the radioactive solution. For nuclear medicine irradiations the relative response to 201Tl and 99mTc radionuclides produced by INER are also satisfactory.

  12. The Effects of Foreign Language Anxiety and Test Anxiety on Foreign Language Test Performance

    OpenAIRE

    Masoomeh Salehi; Fahimeh Marefat

    2014-01-01

    This study aimed at investigating the effects of foreign language anxiety and test anxiety on foreign language test performance. Another purpose of this study was to see whether there is any relationship between foreign language anxiety and test anxiety. Two hundred students of English as a foreign language at pre-intermediate (Pre 1) level participated in this study. In the present study, the Foreign Language Classroom Anxiety Scale and the Test Anxiety Scale were used to measure foreign lan...

  13. Fast Flux Test Facility core restraint system performance

    International Nuclear Information System (INIS)

    Characterizing Fast Flux Test Facility (FFTF) core restraint system performance has been ongoing since the first operating cycle. Characterization consists of prerun analysis for each core load, in-reactor and postirradiation measurements of subassembly withdrawal loads and deformations, and using measurement data to fine tune predictive models. Monitoring FFTF operations and performing trend analysis has made it possible to gain insight into core restraint system performance and head off refueling difficulties while maximizing component lifetimes. Additionally, valuable information for improved designs and operating methods has been obtained. Focus is on past operating experience, emphasizing performance improvements and avoidance of potential problems. 4 refs., 12 figs., 2 tabs

  14. Fracture testing and performance of beryllium copper alloy C17510

    International Nuclear Information System (INIS)

    When a literature search and discussion with manufacturers revealed that there was virtually no existing data related to the fracture properties and behavior of copper beryllium alloy C17510, a series of test programs was undertaken to ascertain this information for several variations in material processing and chemistry. These variations in C17510 were primarily optimized for combinations of strength and conductivity. While originally intended for use as cyclically loaded high-field, high-strength conductors in fusion energy research, material testing of C17510 has indicated that it is an attractive and economical alternative for a host of other structural, mechanical and electrical applications. ASTM tests performed on three variations of C17510 alloys included both J-integral and plane strain fracture toughness testing and fatigue crack growth rate tests, as well as verifying tensile, hardness, Charpy, and other well defined mechanical properties. Fracture testing was performed at both room and liquid nitrogen temperatures, which bound the thermal environment anticipated for the fusion components being designed. Fatigue crack propagation stress ratios ranged from nominal zero to minus one at each temperature. In order to confirm the test results, duplicate and independent test programs were awarded to separate facilities with appropriate test experience, whenever possible. The primary goal of the test program, to determine and bound the fracture toughness and Paris constants for C17510,was accomplished. In addition, a wealth of information was accumulated pertaining to crack growth characteristics, effects of directionality and potential testing pitfalls. The paper discusses the test program and its findings in detail

  15. Do precursor tests influence the performance of Oral Hygiene students in subsequent semester tests?

    Scientific Electronic Library Online (English)

    V, Bookhan; V, Warren; Hs, schoeman.

    2014-11-01

    Full Text Available INTRODUCTION: Precursor tests may be useful educational tools In dentistry to enhance learning among Oral Hygiene students, but their application and possible effect on the subsequent performance of these students have not been studied AIM: To determine whether precursor tests, used as dental educat [...] ional and formative assessment tools, influence the performance of undergraduate Oral Hygiene students in ensuing formal semester tests in the discipline of Basic Restorative Dentistry METHODS: This descriptive cross sectional study involved seventeen consenting Oral Hygiene students. An electronic Odontology Theory Test (OTT) and an electronic Objective Structured Practical Test (OSPT), were prepared and introduced as precursor tests prior to scheduled semester tests in the Division of Restorative Dentistry (Department of Odontology). Eleven (65%) of the seventeen students completed the precursor OTT, as well as the precursor OSPT, fourteen days prior to their scheduled semester OTT and semester OSPT and sixty two days prior to their final examinations. The results of the precursor and the semester tests were entered into a Microsoft Excel® database for comparative analysis, using a Student's t-test RESULTS: For both OTT and OSPT tests there were significant differences between the means of the scores of the students for precursor and semester tests (OTT: p = 0.0009; OSPT: p = 0.0180) DISCUSSION: The students performed significantly better in their precursor OTT, whilst their performance in the OSPT was significantly better in the semester test. : In the context of this investigation, the precursor OTT did not enhance the performance of the students in their semester OTT, whilst the precursor OSPT was associated with an enhanced performance of the students in their semester OSPT

  16. High Temperature Calcination - MACT Upgrade Equipment Pilot Plant Test

    Energy Technology Data Exchange (ETDEWEB)

    Richard D. Boardman; B. H. O& #39; Brien; N. R. Soelberg; S. O. Bates; R. A. Wood; C. St. Michel

    2004-02-01

    About one million gallons of acidic, hazardous, and radioactive sodium-bearing waste are stored in stainless steel tanks at the Idaho Nuclear Technology and Engineering Center (INTEC), which is a major operating facility of the Idaho National Engineering and Environmental Laboratory. Calcination at high-temperature conditions (600 C, with alumina nitrate and calcium nitrate chemical addition to the feed) is one of four options currently being considered by the Department of Energy for treatment of the remaining tank wastes. If calcination is selected for future processing of the sodium-bearing waste, it will be necessary to install new off-gas control equipment in the New Waste Calcining Facility (NWCF) to comply with the Maximum Achievable Control Technology (MACT) standards for hazardous waste combustors and incinerators. This will require, as a minimum, installing a carbon bed to reduce mercury emissions from their current level of up to 7,500 to <45 {micro}g/dscm, and a staged combustor to reduce unburned kerosene fuel in the off-gas discharge to <100 ppm CO and <10 ppm hydrocarbons. The staged combustor will also reduce NOx concentrations of about 35,000 ppm by 90-95%. A pilot-plant calcination test was completed in a newly constructed 15-cm diameter calciner vessel. The pilot-plant facility was equipped with a prototype MACT off-gas control system, including a highly efficient cyclone separator and off-gas quench/venturi scrubber for particulate removal, a staged combustor for unburned hydrocarbon and NOx destruction, and a packed activated carbon bed for mercury removal and residual chloride capture. Pilot-plant testing was performed during a 50-hour system operability test January 14-16, followed by a 100-hour high-temperature calcination pilot-plant calcination run January 19-23. Two flowsheet blends were tested: a 50-hour test with an aluminum-to-alkali metal molar ratio (AAR) of 2.25, and a 50-hour test with an AAR of 1.75. Results of the testing indicate that sodium-bearing waste can be successfully calcined at 600 C with an AAR of 1.75. Unburned hydrocarbons are reduced to less than 10 ppm (7% O2, dry basis), with >90% reduction of NOx emissions. Mercury removal by the carbon bed reached 99.99%, surpassing the control efficiency needed to meet MACT emissions standards. No deleterious impacts on the carbon bed were observed during the tests. The test results imply that upgrading the NWCF calciner with a more efficient cyclone separator and the proposed MACT equipment can process the remaining tanks wastes in 3 years or less, and comply with the MACT standards.

  17. Performance testing open source products for the TMT event service

    Science.gov (United States)

    Gillies, K.; Bhate, Yogesh

    2014-07-01

    The software system for TMT is a distributed system with many components on many computers. Each component integrates with the overall system using a set of software services. The Event Service is a publish-subscribe message system that allows the distribution of demands and other events. The performance requirements for the Event Service are demanding with a goal of over 60 thousand events/second. This service is critical to the success of the TMT software architecture; therefore, a project was started to survey the open source and commercial market for viable software products. A trade study led to the selection of five products for thorough testing using a specially constructed computer/network configuration and test suite. The best performing product was chosen as the basis of a prototype Event Service implementation. This paper describes the process and performance tests conducted by Persistent Systems that led to the selection of the product for the prototype Event Service.

  18. Performance testing of multi-metal continuous emissions monitors

    Energy Technology Data Exchange (ETDEWEB)

    Haas, W.J. [Ames Lab., IA (United States); French, N.B. [Sky+, Inc. (United States); Brown, C.H. [Oak Ridge National Lab., TN (United States); Burns, D.B. [Westinghouse Savannah River Co., Aiken, SC (United States); Lemieux, P.M.; Ryan, J.V. [National Risk Management Research Lab., Research Triangle Park, NC (United States); Priebe, S.J. [Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States); Waterland, L.R. [Acurex Environmental Corp. (United States)

    1997-11-17

    Three prototype multi-metals continuous emissions monitors (CEMs) were tested in April 1996 at the Rotary Kiln Incinerator Simulator facility at the US Environmental Protection Agency (EPA) National Risk Management Research Laboratory, Research Triangle Park, North Carolina. The CEM instruments were: Inductively Coupled Plasma-Atomic Emission Spectrometry (ICP-AES); Laser Induced Breakdown Spectrometry-Atomic Emission Spectroscopy (LIBS); and Laser Spark Spectrometry, another LIBS instrument. The three CEMs were tested simultaneously during test periods in which low, medium, and high concentration levels of seven toxic metals -- antimony, arsenic, beryllium, cadmium, chromium, lead, and mercury -- were maintained under carefully controlled conditions. Two methods were used to introduce the test metals into the flue gas: (1) solution atomization, introducing metal-containing aerosol directly into the secondary combustion burner, and (2) injection of fly ash particulates. The testing addressed four measures of CEM performance: relative accuracy (RA), calibration drift, zero drift, and response time. These were accomplished by comparing the toxic metal analyte concentrations reported by the CEMs to the concentrations measured using the EPA reference method (RM) for the same analytes. Overall, the test results showed the prototype nature of the test CEMs and the clear need for further development. None of the CEMs tested consistently achieved RA values of 20% or less as required by the EPA draft performance specification. Instrument size reduction and automation will also likely need additional attention before multi-metal CEMs systems become commercially available for service as envisioned by regulators and citizens.

  19. Sensitivity Analysis for DHRS Heat Exchanger Performance Tests of PGSFR

    International Nuclear Information System (INIS)

    The STELLA-1 facility has been constructed and separate effect tests of heat exchangers for DHRS are going to be conducted. Two kinds of heat exchangers including DHX (shell-and-tube sodium-to-sodium heat exchanger) and AHX (helical-tube sodium-to-air heat exchanger) will be tested for design codes V and V. Main test points are a design point and a plant normal operation point of each heat exchanger. Additionally, some plant transient conditions are taken into account for establishing a test condition set. To choose the plant transient test conditions, a sensitivity analysis has been conducted using the design codes for each heat exchanger. The sensitivity of the PGSFR DHRS heat exchanger tests (the DHX and AHX in the STELLA-1 facility) has been analyzed through a parametric study using the design codes SHXSA and AHXSA at the design point and the plant normal operation point. The DHX heat transfer performance was sensitive to the change in the inlet temperature of the shell-side and the AHX heat transfer performance was sensitive to the change in the inlet temperature of the tube side. The results of this work will contribute to an improvement of the test matrix for the separate effect test of each heat exchanger

  20. Light water reactor pressure isolation valve performance testing

    International Nuclear Information System (INIS)

    The Light Water Reactor Valve Performance Testing Program was initiated by the NRC to evaluate leakage as an indication of valve condition, provide input to Section XI of the ASME Code, evaluate emission monitoring for condition and degradation and in-service inspection techniques. Six typical check and gate valves were purchased for testing at typical plant conditions (550F at 2250 psig) for an assumed number of cycles for a 40-year plant lifetime. Tests revealed that there were variances between the test results and the present statement of the Code; however, the testing was not conclusive. The life cycle tests showed that high tech acoustic emission can be utilized to trend small leaks, that specific motor signature measurement on gate valves can trend and indicate potential failure, and that in-service inspection techniques for check valves was shown to be both feasible and an excellent preventive maintenance indicator. Life cycle testing performed here did not cause large valve leakage typical of some plant operation. Other testing is required to fully understand the implication of these results and the required program to fully implement them. (author)

  1. Gas-lift valve performance testing and data correlation

    International Nuclear Information System (INIS)

    In this paper a method of analyzing data from gas lift valve performance tests is presented. This method relies on the ability to determine the true dynamic stem position of the valve during flowing conditions. The types of tests required to obtain the data needed by the analysis technique are explained. The data analysis method is applicable to any pressure operated gas lift valve and yields predictions within 10% of actual flow rate

  2. Testing of Tactical Performance in Youth Elite Soccer

    OpenAIRE

    Daniel Memmert

    2010-01-01

    This is a twofold study with the goals of evaluating tactical oriented game test situations for 12-13-year old highly-talented soccer players and to analyze dynamic, intra-individual developments of the players. A cross-sectional design was carried in study 1, using game test situations to measure specific tactics and creative performance for 195 expert players. The results from five evaluation criteria show that both diagnostic instruments can be used for recording football-specific creativi...

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

    International Nuclear Information System (INIS)

    The AKUT process consists of the following process steps: (1) aerosol retention by an electrostatic separator followed by HEPA filters, (2) oxidation of CO with O2 or reaction of excess O2 with CO, respectively, (3) compression, (4) scrubbing and/or liquefaction, (5) separation of krypton by distillation, and (6) separation of tritiated water and iodine by adsorption or chemical reaction. Liquefied off-gas with low permanent gas content resulting from graphite burning with oxygen may be distilled at ambient temperature. Off-gas with higher permanent gas content from burning with oxygen enriched air must be processed at lower temperature. The ambient temperature flow sheet is preferable from an economic as well as safety point of view. (U.S.)

  4. Large scale and performance tests of the ATLAS online software

    International Nuclear Information System (INIS)

    One of the sub-systems of the Trigger/DAQ system of the future ATLAS experiment is the Online Software system. It encompasses the functionality needed to configure, control and monitor the DAQ. Its architecture is based on a component structure described in the ATLAS Trigger/DAQ technical proposal. Regular integration tests ensure its smooth operation in test beam setups during its evolutionary development towards the final ATLAS online system. Feedback is received and returned into the development process. Studies of the system behavior have been performed on a set of up to 111 PCs on a configuration which is getting closer to the final size. Large scale and performance test of the integrated system were performed on this setup with emphasis on investigating the aspects of the inter-dependence of the components and the performance of the communication software. Of particular interest were the run control state transitions in various configurations of the run control hierarchy. For the purpose of the tests, the software from other Trigger/DAQ sub-systems has been emulated. The author presents a brief overview of the online system structure, its components and the large scale integration tests and their results

  5. Power Performance Test Report for the SWIFT Wind Turbine

    Energy Technology Data Exchange (ETDEWEB)

    Mendoza, I.; Hur, J.

    2012-12-01

    This report summarizes the results of a power performance test that NREL conducted on the SWIFT wind turbine. This test was conducted in accordance with the International Electrotechnical Commission's (IEC) standard, Wind Turbine Generator Systems Part 12: Power Performance Measurements of Electricity Producing Wind Turbines, IEC 61400-12-1 Ed.1.0, 2005-12. However, because the SWIFT is a small turbine as defined by IEC, NREL also followed Annex H that applies to small wind turbines. In these summary results, wind speed is normalized to sea-level air density.

  6. TRAC analyses and GIRAFFE tests for PCCS performance prediction

    International Nuclear Information System (INIS)

    The passive containment cooling system (PCCS) would remove decay heat by steam condensation without any electric power supply or operator's action if an accident should occur in nuclear reactors. There is, however, concern that non-condensable gas might influence the PCCS performance in the event of an accident. This paper summarizes Toshiba's activities respecting PCCS development, in particular those activities relating to TRAC qualification for PCCS performance prediction and the GIRAFFE tests. TRAC is a best estimate thermal hydraulic analysis code. GIRAFFE is a full-height test facility simulating the SBWR containment with the PCCS, at Toshiba's Ukishima site. (author)

  7. Performance tests of haemodynamic and digital subtraction angiography equipment

    International Nuclear Information System (INIS)

    This work presents the results of quality control tests performed in hemodynamic and digital subtraction angiography, which have fundamental importance to the image quality guaranty and to control the doses ministered to patients and staff. These tests are based on national and international standards and they can evaluate the performance of these systems. The results showed that the equipment do not present problems in their digital subtraction systems. Nevertheless, one of the equipment presented patient entrance skin air kerma rates above the limit prescribed by the national standard. (author)

  8. Performance testing of the AC propulsion ELX electric vehicle

    Energy Technology Data Exchange (ETDEWEB)

    Kramer, W.E.; MacDowall, R.D.; Burke, A.F.

    1994-06-01

    Performance testing of the AC Propulsion ELX electric vehicle is described. Test data are presented and analyzed. The ELX vehicle is the first of a series of electric vehicles of interest to the California Air Resources Board. The test series is being conducted under a Cooperative Research and Development Agreement (CRADA) between the US Department of energy and the California Air Resources Board. The tests which were conducted showed that the AC Propulsion ELX electric vehicle has exceptional acceleration and range performance. when the vehicle`s battery was fully charged, the vehicle can accelerate from 0 to 96 km/h in about 10 seconds. Energy consumption and range tests using consecutive FUDS and HWFET Driving cycles (the all-electric cycle) indicate that the energy economy of the AC Propulsion ELX electric vehicle with regenerative braking is 97 W{center_dot}h/km, with a range of 153 km (95 miles). Computer simulations performed using the SIMPLEV Program indicate that the vehicle would have a range of 327 km (203 miles) on the all-electric cycle if the lead acid batteries were replaced with NiMH batteries having an energy density of 67 W{center_dot}h/kg. Comparisons of FUDS test data with and without regenerative braking indicated that regenerative braking reduced the energy consumption of the ELX vehicle by approximately 25%.

  9. Verification Test of Hydraulic Performance for Reactor Coolant Pump

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sang Jun; Kim, Jae Shin; Ryu, In Wan; Ko, Bok Seong; Song, Keun Myung [Samjin Ind. Co., Seoul (Korea, Republic of)

    2010-01-15

    According to this project, basic design for prototype pump and model pump of reactor coolant pump and test facilities has been completed. Basic design for prototype pump to establish structure, dimension and hydraulic performance has been completed and through primary flow analysis by computational fluid dynamics(CFD), flow characteristics and hydraulic performance have been established. This pump was designed with mixed flow pump having the following design requirements; specific velocity(Ns); 1080.9(rpm{center_dot}m{sup 3}/m{center_dot}m), capacity; 3115m{sup 3}/h, total head ; 26.3m, pump speed; 1710rpm, pump efficiency; 77.0%, Impeller out-diameter; 349mm, motor output; 360kw, design pressure; 17MPaG. The features of the pump are leakage free due to no mechanical seal on the pump shaft which insures reactor's safety and law noise level and low vibration due to no cooling fan on the motor which makes eco-friendly product. Model pump size was reduced to 44% of prototype pump for the verification test for hydraulic performance of reactor coolant pump and was designed with mixed flow pump and canned motor having the following design requirements; specific speed(NS); 1060.9(rpm{center_dot}m{sup 3}/m{center_dot}m), capacity; 539.4m{sup 3}/h, total head; 21.0m, pump speed; 3476rpm, pump efficiency; 72.9%, Impeller out-diameter; 154mm, motor output; 55kw, design pressure; 1.0MPaG. The test facilities were designed for verification test of hydraulic performance suitable for pump performance test, homologous test, NPSH test(cavitation), cost down test and pressure pulsation test of inlet and outlet ports. Test tank was designed with testing capacity enabling up to 2000m{sup 3}/h and design pressure 1.0MPaG. Auxiliary pump was designed with centrifugal pump having capacity; 1100m{sup 3}/h, total head; 42.0m, motor output; 190kw

  10. ?-alanine supplementation improves YoYo intermittent recovery test performance

    OpenAIRE

    Saunders Bryan; Sunderland Caroline; Harris Roger C; Sale Craig

    2012-01-01

    Abstract Background ?-alanine supplementation has been shown to improve high-intensity exercise performance and capacity. However, the effects on intermittent exercise are less clear, with no effect shown on repeated sprint activity. The aim of this study was to investigate the effects of ?-alanine supplementation on YoYo Intermittent Recovery Test Level 2 (YoYo IR2) performance. Methods Seventeen amateur footballers were allocated to either a placebo (PLA; N = 8) or ?-alanine (BA; N = 9) ...

  11. Performance test results for a cold helium compressor

    International Nuclear Information System (INIS)

    This paper presents performance test data for a generic pump/compressor designed for circulation of cryogenic fluids. The unit is designed to operate over a wide range of flow rate and pressure rise and can be used for the pumping of liquid and the compression of vapor at temperatures down to 4 K. Topics considered in this paper include cryogenic fluids, helium, pumps, data analysis, pumping, vapors, operation, cryogenics, compressors, performance, liquid flow, compression, and design

  12. Cardiopulmonary exercise testing – the gold standard in physical performance assesment

    Directory of Open Access Journals (Sweden)

    Claudiu Avram

    2008-12-01

    Full Text Available Background: Cardiopulmonary exercise testing (CPX is a modern procedure that allows us to evaluate the global performanceof a subject. Because CPX devices are expensive and less popular due to a less amount of specialists in this field, many oflaboratories uses the more common ECG stress tests for physical performance assessment. Aim: to demonstrate theimportance and accuracy of cardiopulmonary exercise testing comparing with traditional maximal electrocardiographic (ECGstress test without gas exchange analysis. Methods: 18th elite soccer players (age 22.7±6 years, body mass 74.6±9.5 kg,height 175.4±9.8 cm participated in the study. The subjects accomplished two treadmill effort tests with and without gasanalyses, in 2 consecutive days interval. Results: At the end of the study we noticed a highly significant statistical difference(p<0.0001 between the investigated testing methods. In gas exchange testing method we found a decreased level of all theparameters evaluated comparing to stress ECG: VO2 peak (ml*kg-1*min-1 = 55.4±5.2 vs. 67.8±5.7; AT (ml*kg-1*min-1 =41.2±7.6 vs. 47.4±6.9; VO2/HR (ml = 23.8±2.5 vs. 23.8±2.5. Conclusions: Asessment of exercise performance based solelyon a maximal stress ECG without gas analyzing is inaccurate. Furthermore, estimation of peak exercise responses based uponcalculation of VO2 peak from peak work rate are inappropriate in sportsman. The study demonstrate once again that CPXremain the most accurate and reliable test for detection of AT and for a comprehensive physical performance assessment andcannot be replace by other surrogate laboratory exercise tests like stress ECG.

  13. Distillation as a means of separating krypton from the off-gas of a reprocessing plant for graphite-coated HTR fuel elements

    International Nuclear Information System (INIS)

    The AKUT-II facility is described, which is designed for an off-gas throughput of 10 Nm3/h. The low-pressure section is for primary purification in several steps, whereas in the high-pressure CO2 section (70 bar, 200C) the separation of Kr-85 by means of distillation is achieved. The parameters for the design of the rectifying columns have been determined experimentally. (HP)

  14. Performance test of database server based on MySQL

    International Nuclear Information System (INIS)

    MySQL is preliminarily chosen as the archive toolkit of CSNS experimental control system. A performance test of a database server based on MySQL is introduced. Main characters including the relationship between query rate, insertion rate and the number of connection threads are carried out with the consideration of data size. The hardware setup, software environment, ways and means of the test, and the results analysis are introduced in detail. The test results will help a lot to the database system design of the CSNS experiment control system. (authors)

  15. Performance testing of West Valley Reference 6 glass

    International Nuclear Information System (INIS)

    The chemical durability of West Valley Reference 6 glass is being evaluated by using a suite of laboratory tests which highlight the early, interim, and long-term stages of corrosion. The test results are being used to describe the glass corrosion path and its long-term durability. The long-term durability of the SRL Environmental Assessment glass is being evaluated for comparison. Test results also provide parameter values for an analytical corrosion model that can be used in performance assessments of specific disposal sites

  16. Performance test on testing apparatus for radionuclide migration on ground surface

    International Nuclear Information System (INIS)

    Testing apparatus for radionuclide migration on ground surface was constructed to study the radionuclide migration on ground surface which is one of radionuclide migration paths in a natural barrier. The apparatus is composed of inflow section of solution, testing section of soil sample, outflow section of effluent solution, measurement section of water velocity, measurement section of water content et al., which can test the soil sample taken from natural field undestructively. As performance tests, four tests were carried out for each section and over all test was also carried out to confirm the linking of each section on the operation of the apparatus under actual test condition. From the performance test, it is confirmed that each section accomplishes the prescribed performance of the apparatus. As to water velocity on ground surface and water content in soil, which are important parameters to analyze the behavior of radionuclide migration, it is confirmed that sufficient information can be obtained about the distribution of surface water velocity and the infiltration of surface water, from the measurement test of each section and the overall test. (author)

  17. Post-test analysis for the APR1400 LBLOCA DVI performance test using MARS

    International Nuclear Information System (INIS)

    Post-test analyses using a multi-dimensional best-estimate analysis code, MARS, are performed for the APR1400 LBLOCA DVI (Direct Vessel Injection) performance tests. This report describes the code evaluation results for the test data of various void height tests and direct bypass tests that have been performed at MIDAS test facility. MIDAS is a scaled test facility of APR1400 with the objective of identifying multi-dimensional thermal-hydraulic phenomena in the downcomer during the reflood conditions of a large break LOCA. A modified linear scale ratio was applied in its construction and test conditions. The major thermal-hydraulic parameters such as ECC bypass fraction, steam condensation fraction, and temperature distributions in downcomer are compared and evaluated. The evaluation results of MARS code for the various test cases show that: (a) MARS code has an advanced modeling capability of well predicting major multi-dimensional thermal-hydraulic phenomena occurring in the downcomer, (b) MARS code under-predicts the steam condensation rates, which in turn causes to over-predict the ECC bypass rates. However, the trend of decrease in steam condensation rate and increase in ECC bypass rate in accordance with the increase in steam flow rate, and the calculation results of the ECC bypass rates under the EM analysis conditions generally agree with the test data

  18. Testing performance of Standards-based protocols in DPM

    International Nuclear Information System (INIS)

    In the interests of the promotion of the increased use of non-proprietary protocols in grid storage systems, we perform tests on the performance of WebDAV and pNFS transport with the DPM storage solution. We find that the standards-based protocols behave similarly to the proprietary standards currently in use, despite encountering some issues with the state of the implementation itself. We thus conclude that there is no performance-based reason to avoid using such protocols for data management in future.

  19. Stereotype Threat in Middle School: The Effects of Prior Performance on Expectancy and Test Performance

    Science.gov (United States)

    Howard, Keith E.; Anderson, Kenneth A.

    2010-01-01

    Stereotype threat research has demonstrated how presenting situational cues in a testing environment, such as raising the salience of negative stereotypes, can adversely affect test performance (Perry, Steele, & Hilliard, 2003; Steele & Aronson, 1995) and expectancy (Cadinu, Maass, Frigerio, Impagliazzo, & Latinotti, 2003; Stangor, Carr, & Kiang,…

  20. Avoiding inaccurate interpretations when performing ultrasonic tests on welded joints

    International Nuclear Information System (INIS)

    As reported in this article, conventional procedures for assessing errors when performing ultrasonic tests on weldes seams of ten no longer meet modern-day requirements. However, the safety of welded seams can be assessed considerably more accurately by adopting suitable assessment techniques, such as pattern recognition. This will mean that inaccurate interpretations can be ruled out to a large extent. (RHM)

  1. Off-line performance tests on YAG (Ce) scintillator

    International Nuclear Information System (INIS)

    The performance of results of a newly developed inorganic scintillator, YAG(Ce), which has got very similar physical properties and peak emission wavelength like CsI(Tl) are given. The results on off-line tests of the linearity, energy resolution and timing properties of the scintillator using PMT based readout and standard ?-ray calibration sources are presented

  2. 40 CFR 60.58b - Compliance and performance testing.

    Science.gov (United States)

    2010-07-01

    ...evaluation procedures and acceptance criteria (e.g. ...fails a performance test audit (e.g. , cylinder...evaluation procedures and acceptance criteria. (4) Provisions...data; (F) Accuracy audit procedures for analytical...at a minimum, systems audits that include the...

  3. Thermal Performance Testing of Order Dependancy of Aerogels Multilayered Insulation

    Science.gov (United States)

    Johnson, Wesley L.; Fesmire, James E.; Demko, J. A.

    2009-01-01

    Robust multilayer insulation systems have long been a goal of many research projects. Such insulation systems must provide some degree of structural support and also mechanical integrity during loss of vacuum scenarios while continuing to provide insulative value to the vessel. Aerogel composite blankets can be the best insulation materials in ambient pressure environments; in high vacuum, the thermal performance of aerogel improves by about one order of magnitude. Standard multilayer insulation (MU) is typically 50% worse at ambient pressure and at soft vacuum, but as much as two or three orders of magnitude better at high vacuum. Different combinations of aerogel and multilayer insulation systems have been tested at Cryogenics Test Laboratory of NASA Kennedy Space Center. Analysis performed at Oak Ridge National Laboratory showed an importance to the relative location of the MU and aerogel blankets. Apparent thermal conductivity testing under cryogenic-vacuum conditions was performed to verify the analytical conclusion. Tests results are shown to be in agreement with the analysis which indicated that the best performance is obtained with aerogel layers located in the middle of the blanket insulation system.

  4. WhalePower tubercle blade power performance test report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-15

    Toronto-based WhalePower Corporation has developed turbine blades that are modeled after humpback whale flippers. The blades, which incorporate tubercles along the leading edge of the blade, have been fitted to a Wenvor 25 kW turbine installed in North Cape, Prince Edward Island at a test site for the Wind Energy Institute of Canada (WEICan). A test was conducted to characterize the power performance of the prototype wind turbine. This report described the wind turbine configuration with particular reference to turbine information, power rating, blade information, tower information, control systems and grid connections. The test site was also described along with test equipment and measurement procedures. Information regarding power output as a function of wind speed was included along with power curves, power coefficient and annual energy production. The results for the power curve and annual energy production contain a level of uncertainty. While measurements for this test were collected and analyzed in accordance with International Electrotechnical Commission (IEC) standards for performance measurements of electricity producing wind turbines (IEC 61400-12-1), the comparative performance data between the prototype WhalePower wind turbine blade and the Wenvor standard blade was not gathered to IEC data standards. Deviations from IEC-61400-12-1 procedures were listed. 6 tabs., 16 figs., 3 appendices.

  5. Performance evaluation of infrared imaging system in field test

    Science.gov (United States)

    Wang, Chensheng; Guo, Xiaodong; Ren, Tingting; Zhang, Zhi-jie

    2014-11-01

    Infrared imaging system has been applied widely in both military and civilian fields. Since the infrared imager has various types and different parameters, for system manufacturers and customers, there is great demand for evaluating the performance of IR imaging systems with a standard tool or platform. Since the first generation IR imager was developed, the standard method to assess the performance has been the MRTD or related improved methods which are not perfect adaptable for current linear scanning imager or 2D staring imager based on FPA detector. For this problem, this paper describes an evaluation method based on the triangular orientation discrimination metric which is considered as the effective and emerging method to evaluate the synthesis performance of EO system. To realize the evaluation in field test, an experiment instrument is developed. And considering the importance of operational environment, the field test is carried in practical atmospheric environment. The test imagers include panoramic imaging system and staring imaging systems with different optics and detectors parameters (both cooled and uncooled). After showing the instrument and experiment setup, the experiment results are shown. The target range performance is analyzed and discussed. In data analysis part, the article gives the range prediction values obtained from TOD method, MRTD method and practical experiment, and shows the analysis and results discussion. The experimental results prove the effectiveness of this evaluation tool, and it can be taken as a platform to give the uniform performance prediction reference.

  6. Using performance testing to assess security system effectiveness

    International Nuclear Information System (INIS)

    A balanced assessment of any complex system, including security systems, can be divided into two parts, namely 1) determining whether all critical components are present, and 2) determining whether all components function as intended, both individually and as a system. Many times, however, assessment focus only on the first part, which, for government-regulated security systems, can be thought of as compliance; whereas the second part, the actual system performance, is ignored, When performance testing is used, it often occurs at the individual component or sub-system level, leaving untested the complex interactions among all the combined system components. To achieve balanced assessment one must not only look at compliance, but at performance as well, both at the component or sub-system level, and at the overall system level. This paper describes why performance testing is essential to a balanced assessment, how performance testing can be applied to various parts of the security system, and some inherent limitations on its use

  7. Performance of the CANFLEX fuel bundle under mechanical flow testing

    International Nuclear Information System (INIS)

    CANFLEX is a 43-element fuel bundle consisting of two element sizes, to reduce element ratings, while maintaining the same bundle power, and an uranium content very close to the uranium content of a standard 37-element bundle. The overall dimensions of the bundle are designed to be the same as the overall dimensions of the standard 37-element fuel bundle. Several out-reactor tests were performed, under in-reactor operating conditions of flow, pressure and temperature, to demonstrate the hydraulic performance and mechanical integrity of the CANFLEX fuel-bundle design. The hydraulic performance and mechanical integrity of the CANFLEX fuel-bundle design were verified through various out-reactor tests conducted at the laboratories of KAERI and AECL to show that the CANFLEX bundle design meets the design requirements of the CANDU 6 reactor fuel [1] and that it is also compatible with the CANDU 6 fuelling machine. (author)

  8. Prescriptive vs. performance based cook-off fire testing.

    Energy Technology Data Exchange (ETDEWEB)

    Nakos, James Thomas; Tieszen, Sheldon Robert; Erikson, William Wilding; Gill, Walter; Blanchat, Thomas K.

    2010-07-01

    In the fire safety community, the trend is toward implementing performance-based standards in place of existing prescriptive ones. Prescriptive standards can be difficult to adapt to changing design methods, materials, and application situations of systems that ultimately must perform well in unwanted fire situations. In general, this trend has produced positive results and is embraced by the fire protection community. The question arises as to whether this approach could be used to advantage in cook-off testing. Prescribed fuel fire cook-off tests have been instigated because of historical incidents that led to extensive damage to structures and loss of life. They are designed to evaluate the propensity for a violent response. The prescribed protocol has several advantages: it can be defined in terms of controllable parameters (wind speed, fuel type, pool size, etc.); and it may be conservative for a particular scenario. However, fires are inherently variable and prescribed tests are not necessarily representative of a particular accident scenario. Moreover, prescribed protocols are not necessarily adaptable and may not be conservative. We also consider performance-based testing. This requires more knowledge and thought regarding not only the fire environment, but the behavior of the munitions themselves. Sandia uses a performance based approach in assuring the safe behavior of systems of interest that contain energetic materials. Sandia also conducts prescriptive fire testing for the IAEA, NRC and the DOT. Here we comment on the strengths and weakness of both approaches and suggest a path forward should it be desirable to pursue a performance based cook-off standard.

  9. MOTIVATION AND PERFORMANCE IN PHYSICAL EDUCATION: AN EXPERIMENTAL TEST

    Directory of Open Access Journals (Sweden)

    Juan A. Moreno

    2010-03-01

    Full Text Available The purpose of this study was to analyse, experimentally, the relationships between motivation and performance in a lateral movement test in physical education. The study group consisted of 363 students (227 boys and 136 girls, aged between 12 and 16, who were randomly divided into three groups: an experimental group in which an incremental ability belief was induced, another experimental group in which an entity ability belief was induced, and a control group where there was no intervention. Measurements were made of situational intrinsic motivation, perceived competence in executing the task and performance. The results revealed that the incremental group reported higher scores on the situational intrinsic motivation scale. The entity group demonstrated better performance in the first test attempt than the incremental group but, in the second attempt, the performance was similar in the different groups. Perhaps the initial differences in performance disappeared because the incremental group counted on improving in the second attempt. These results are discussed in relation to the intensity with which the teacher conveys information relating to incremental ability belief of the pupil to increase intrinsic motivation and performance

  10. Performance test report for the 1000 kg melter

    Energy Technology Data Exchange (ETDEWEB)

    Eaton, W.C.

    1995-11-01

    A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense wastes stored in underground tanks at the Hanford Site in southeastern Washington State. Phase 1 of the melter demonstration tests using simulated LLW was completed during fiscal year 1995. This document is the 100 kg melter offgas report on testing performed by GTS Duratek Inc., in Columbia, Maryland. GTS Duratek (one of the seven vendors selected) was chosen to demonstrate Joule heated melter technology under WHC subcontract number MMI-SVV- 384215. The document contains the complete offgas report on the 100 kg melter as prepared by Parsons Engineering Science, Inc. A summary of this report is also contained in the ``GTS Duratek, Phase 1 Hanford Low-Level Waste Melter Tests: Final Report`` (WHC-SD-VI-027).

  11. Orion Exploration Flight Test-1 (EFT-1) Absolute Navigation Performance

    Science.gov (United States)

    Zanetti, Renato

    2015-01-01

    The Orion vehicle, being design to take men back to the Moon and beyond, successfully completed its first flight test, EFT-1 (Exploration Flight Test-1), on December 5th, 2014. The main objective of the test was to demonstrate the capability of re-enter into the Earth's atmosphere and safely splash-down into the pacific ocean. This un-crewed mission completes two orbits around Earth, the second of which is highly elliptical with an apogee of approximately 5908 km, higher than any vehicle designed for humans has been since the Apollo program. The trajectory was designed in order to test a high-energy re-entry similar to those crews will undergo during lunar missions. The mission overview is shown in Figure 1. The objective of this paper is to document the performance of the absolute navigation system during EFT-1 and to present its design.

  12. Performance test report for the 1000 kg melter

    International Nuclear Information System (INIS)

    A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense wastes stored in underground tanks at the Hanford Site in southeastern Washington State. Phase 1 of the melter demonstration tests using simulated LLW was completed during fiscal year 1995. This document is the 100 kg melter offgas report on testing performed by GTS Duratek Inc., in Columbia, Maryland. GTS Duratek (one of the seven vendors selected) was chosen to demonstrate Joule heated melter technology under WHC subcontract number MMI-SVV- 384215. The document contains the complete offgas report on the 100 kg melter as prepared by Parsons Engineering Science, Inc. A summary of this report is also contained in the ''GTS Duratek, Phase 1 Hanford Low-Level Waste Melter Tests: Final Report'' (WHC-SD-VI-027)

  13. Integrated chemical effects test program for PWR sump performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Bhagwat, P.J. [Office of Nuclear Regulatory Research, United States Nuclear Regulatory Commission, Washington, DC (United States)

    2007-07-01

    Products attributable to chemical interactions between the emergency core cooling system (ECCS) containment spray water and exposed materials (such as metal surfaces, paint chips, and fiberglass insulation debris) could impede the performance of ECCS recirculation following a loss-of-coolant accident (LOCA) at a pressurized-water reactor (PWR). Five tests have been conducted in the ICET (Integrated Chemical Effects Test) test loop in order to simulate the chemical environment present inside a PWR containment water pool following a LOCA. The tests were conducted for 30 days at a constant temperature of 60 Celsius degrees. The materials tested within this environment included representative amounts of submerged and un-submerged aluminum, copper, concrete, zinc, carbon steel, and insulation samples (either 100% fiberglass or a combination of 80% calcium-silicate and 20% fiberglass by volume). Representative amounts of concrete dust and latent debris were also added to the test solution. Water was circulated through the bottom portion of the test tank during the entire test to achieve representative flow rates over the submerged specimens. Overall, the ICET program provided some insights and initial understanding regarding solution chemistry, as well as the types and amounts of chemical reaction products that may form in the ECCS containment sump pool. The observed chemical products may potentially contribute to pressure losses across a debris-laden sump screen, as well as performance degradation of ECCS components downstream of the sump screen. The ICET results indicate that: -1) chemical reaction products with varied quantities, consistencies, attributes, and apparent formation mechanisms were found; -2) containment materials (metallic, non-metallic, and insulation debris), pH, buffering agent, temperature, and time are all important variables that influence chemical product formation; and -3) changes to one important environmental variable (e.g., pH adjusting agent, insulation material) can significantly affect the chemical products that form.

  14. Integrated chemical effects test program for PWR sump performance assessment

    International Nuclear Information System (INIS)

    Products attributable to chemical interactions between the emergency core cooling system (ECCS) containment spray water and exposed materials (such as metal surfaces, paint chips, and fiberglass insulation debris) could impede the performance of ECCS recirculation following a loss-of-coolant accident (LOCA) at a pressurized-water reactor (PWR). Five tests have been conducted in the ICET (Integrated Chemical Effects Test) test loop in order to simulate the chemical environment present inside a PWR containment water pool following a LOCA. The tests were conducted for 30 days at a constant temperature of 60 Celsius degrees. The materials tested within this environment included representative amounts of submerged and un-submerged aluminum, copper, concrete, zinc, carbon steel, and insulation samples (either 100% fiberglass or a combination of 80% calcium-silicate and 20% fiberglass by volume). Representative amounts of concrete dust and latent debris were also added to the test solution. Water was circulated through the bottom portion of the test tank during the entire test to achieve representative flow rates over the submerged specimens. Overall, the ICET program provided some insights and initial understanding regarding solution chemistry, as well as the types and amounts of chemical reaction products that may form in the ECCS containment sump pool. The observed chemical products may potentially contribute to pressure losses across a debris-laden sump screen, as well aross a debris-laden sump screen, as well as performance degradation of ECCS components downstream of the sump screen. The ICET results indicate that: -1) chemical reaction products with varied quantities, consistencies, attributes, and apparent formation mechanisms were found; -2) containment materials (metallic, non-metallic, and insulation debris), pH, buffering agent, temperature, and time are all important variables that influence chemical product formation; and -3) changes to one important environmental variable (e.g., pH adjusting agent, insulation material) can significantly affect the chemical products that form

  15. Performance test of single step continuous dry attrition mill

    International Nuclear Information System (INIS)

    This report describes the improvement of the two-step attrition mill to solve problems associated with its complexity and those of batch type attrition mill as well as the results of the performance test in view of the comparison. In the performance test of the improved single step continuous attrition mill, powder milling and discharge time per pass was systematically measured, and UO2-5wt%CeO2 powder mixture, UO2-5wt%CeO2 powder mixture with poreformer, M3O8 powder and/or MO2 scrap were milled to compare the performance of the milling operations between the 2-step attrition mill and improved single-step attrition mill. The results of the performance test shows, in addition to its improved milling operation, an improved function in less contamination with impurities, simpler handling with easier operation and maintenance and hence, less contamination of operational location, especially when used for the operation in a confinement system, for the improved single step attrition mill compared with a batch type or continuous 2-step attrition mill

  16. Initial operation and performance test results of the Accelerator System String Test (ASST) cryogenic system

    International Nuclear Information System (INIS)

    PSI has supplied three equal capacity helium cryogenic plants (dubbed ASST, MTL, and N15B). The first two plants will provide the helium refrigeration and liquefaction required for magnet testing in the Accelerator System String Test (ASST) facility and the Magnet Test Laboratory (MTL). The third plant (N15B) will supplement the ASST plant and will eventually be utilized for the N15 Sector Refrigeration System (SRS) requirements. This paper describes the results of the ASST plant initial operational commissioning and performance testing. Operating modes of the MTL/ASST system have been previously described

  17. Effects of load on wingate test performances and reliability.

    Science.gov (United States)

    Jaafar, Hamdi; Rouis, Majdi; Coudrat, Laure; Attiogbé, Elvis; Vandewalle, Henry; Driss, Tarak

    2014-12-01

    The purpose of this study was to examine the effects of 2 braking forces (8.7 and 11% of body mass, BM) on Wingate test performance, peak lactate ([La]pk), peak heart rate (HRpk), and rate of perceived exertion (RPE). Sixteen male physical education students (age: 22.7 ± 1.3 years, height: 1.81 ± 0.07 m, BM: 74.3 ± 9.6 kg) performed, in a randomized order, 2 Wingate tests at 8.7% BM and 2 Wingate tests at 11% BM on a Monark cycle ergometer on 4 separate sessions. The results showed that the reliability level of mechanical measures was not affected by the braking force and was relatively similar for each variable in both braking forces (0.886 fatigue slope, and RPE were significantly higher (8.2, 7.0, 11.9, and 4.1%, respectively, all reliability of the Wingate test does not depend on the used load, and a braking force of 11% BM is more optimal for power output during Wingate test in active adults. PMID:24936901

  18. Character pathology and neuropsychological test performance in remitted opiate dependence

    Directory of Open Access Journals (Sweden)

    Steinfeld Matthew

    2008-11-01

    Full Text Available Abstract Background Cognitive deficits and personality pathology are prevalent in opiate dependence, even during periods of remission, and likely contribute to relapse. Understanding the relationship between the two in vulnerable, opiate-addicted patients may contribute to the design of better treatment and relapse prevention strategies. Methods The Millon Multiaxial Clinical Inventory (MCMI and a series of neuropsychological tests were administered to three subject groups: 29 subjects receiving methadone maintenance treatment (MM, 27 subjects in protracted abstinence from methadone maintenance treatment (PA, and 29 healthy non-dependent comparison subjects. Relationships between MCMI scores, neuropsychological test results, and measures of substance use and treatment were examined using bivariate correlation and regression analysis. Results MCMI scores were greater in subjects with a history of opiate dependence than in comparison subjects. A significant negative correlation between MCMI scores and neuropsychological test performance was identified in all subjects. MCMI scores were stronger predictors of neuropsychological test performance than measures of drug use. Conclusion Formerly methadone-treated opiate dependent individuals in protracted opiate abstinence demonstrate a strong relationship between personality pathology and cognitive deficits. The cause of these deficits is unclear and most likely multi-factorial. This finding may be important in understanding and interpreting neuropsychological testing deficiencies in opiate-dependent subjects.

  19. 1997 Performance Testing of Multi-Metal Continuous Emissions Monitors

    International Nuclear Information System (INIS)

    Five prototype and two commercially available multi-metals continuous emissions monitors (CEMs) were tested in September 1997 at the Rotary Kiln Incinerator Simulator facility at the EPA National Risk Management Research Laboratory, Research Triangle Park, North Carolina. The seven CEMs were tested side by side in a long section of duct following the secondary combustion chamber of the RKIS. Two different concentrations of six toxic metals were introduced into the incinerator-approximately 15 and 75 g/dscm of arsenic, beryllium, cadmium, chromium, lead, and mercury (We also tested for antimony but we are not reporting on it here because EPA recently dropped antimony from the list of metals addressed by the draft MACT rule). These concentrations were chosen to be close to emission standards in the draft MACT rule and the estimated Method Detection Limit (MDL) required of a CEM for regulatory compliance purposes. Results from this test show that no CEMs currently meet the performance specifications in the EPA draft MACT rule for hazardous waste incinerators. Only one of the CEMs tested was able to measure all six metals at the concentrations tested. Even so, the relative accuracy of this CEM varied between 35% and 100%, not 20% or less as required in the EPA performance specification. As a result, we conclude that no CEM is ready for long-term performance validation for compliance monitoring applications. Because sampling and measuring Hg is a recurring problem for multi-metal CEMs as well as Hg CEMs, we recommended that developers participate in a 1998 DOE-sponsored workshop to solve these and other common CEM measurement issues

  20. 1997 Performance Testing of Multi-Metal Continuous Emissions Monitors

    Energy Technology Data Exchange (ETDEWEB)

    Sky +, Inc.

    1998-09-01

    Five prototype and two commercially available multi-metals continuous emissions monitors (CEMs) were tested in September 1997 at the Rotary Kiln Incinerator Simulator facility at the EPA National Risk Management Research Laboratory, Research Triangle Park, North Carolina. The seven CEMs were tested side by side in a long section of duct following the secondary combustion chamber of the RKIS. Two different concentrations of six toxic metals were introduced into the incinerator-approximately 15 and 75 µg/dscm of arsenic, beryllium, cadmium, chromium, lead, and mercury (We also tested for antimony but we are not reporting on it here because EPA recently dropped antimony from the list of metals addressed by the draft MACT rule). These concentrations were chosen to be close to emission standards in the draft MACT rule and the estimated Method Detection Limit (MDL) required of a CEM for regulatory compliance purposes. Results from this test show that no CEMs currently meet the performance specifications in the EPA draft MACT rule for hazardous waste incinerators. Only one of the CEMs tested was able to measure all six metals at the concentrations tested. Even so, the relative accuracy of this CEM varied between 35% and 100%, not 20% or less as required in the EPA performance specification. As a result, we conclude that no CEM is ready for long-term performance validation for compliance monitoring applications. Because sampling and measuring Hg is a recurring problem for multi-metal CEMs as well as Hg CEMs, we recommended that developers participate in a 1998 DOE-sponsored workshop to solve these and other common CEM measurement issues.

  1. Reliability performance of standby equipment with periodic testing

    International Nuclear Information System (INIS)

    In this report, the reliability performance of standby equipment subjected to periodic testing is studied. analytical expressions have been derived for reliability measures, such as the man accumulated operating time to failure, the expected number of tests between two consecutive failures, the mean time to failure following an emergency start-up and the probability of failing to complete an emergency mission of a specified duration. These results are useful for the reliability assessment of standby equipment such as combustion turbine units of the emergency power supply system, and of the Class III power system at a nuclear generating station

  2. A LABORATORY TEST FOR THE EXAMINATION OF ALACTIC RUNNING PERFORMANCE

    Directory of Open Access Journals (Sweden)

    Armin Kibele

    2005-12-01

    Full Text Available A new testing procedure is introduced to evaluate the alactic running performance in a 10s sprint task with near-maximal movement velocity. The test is performed on a motor-equipped treadmill with inverted polarity that increases mechanical resistance instead of driving the treadmill belt. As a result, a horizontal force has to be exerted against the treadmill surface in order to overcome the resistant force of the engine and to move the surface in a backward direction. For this task, subjects lean with their hands towards the front safety barrier of the treadmill railing with a slightly inclined body posture. The required skill resembles the pushing movement of bobsleigh pilots at the start of a race. Subjects are asked to overcome this mechanical resistance and to cover as much distance as possible within a time period of 10 seconds. Fifteen male students (age: 27.7 ± 4.1 years, body height: 1.82 ± 0.46 m, body mass: 78.3 ± 6.7 kg participated in a study. As the resistance force was set to 134 N, subjects ran 35.4 ± 2.6 m on the average corresponding to a mean running velocity of 3.52 ± 0.25 m·s-1. The validity of the new test was examined by statistical inference with various measures related to alactic performance including a metabolic equivalent to estimate alactic capacity (2892 ± 525 mL O2, an estimate for the oxygen debt (2662 ± 315 ml, the step test by Margaria to estimate alactic energy flow (1691 ± 171 W, and a test to measure the maximal strength in the leg extensor muscles (2304 ± 351 N. The statistical evaluation showed that the new test is in good agreement with the theoretical assumptions for alactic performance. Significant correlation coefficients were found between the test criteria and the measures for alactic capacity (r = 0.79, p < 0.01 as well as alactic power (r = 0.77, p < 0.01. The testing procedure is easy to administer and it is best suited to evaluate the alactic capacity for bobsleigh pilots as well as for any other running discipline.

  3. Network Performance Testing for the BaBar Event Builder

    International Nuclear Information System (INIS)

    We present an overview of the design of event building in the BABAR Online, based upon TCP/IP and commodity networking technology. BABAR is a high-rate experiment to study CP violation in asymmetric e+e- collisions. In order to validate the event-builder design, an extensive program was undertaken to test the TCP performance delivered by various machine types with both ATM OC-3 and Fast Ethernet networks. The buffering characteristics of several candidate switches were examined and found to be generally adequate for our purposes. We highlight the results of this testing and present some of the more significant findings

  4. Results of tritium tests performed on Sandia Laboratories decontamination system

    International Nuclear Information System (INIS)

    The Tritium Research Laboratory (TRL), a facility for performing experiments using gram amounts of tritium, became operational on October 1, 1977. As secondary containment, the TRL employs sealed glove boxes connected on demand to two central decontamination systems, the Gas Purification System and the Vacuum Effluent Recovery System. Performance tests on these systems show the tritium removal systems can achieve concentration reduction factors (ratio of inlet to exhaust concentrations) much in excess of 1000 per pass at inlet concentrations of 1 part per million or less for both tritium and tritiated methane

  5. Pavement Subgrade Performance Study in the Danish Road Testing Machine

    DEFF Research Database (Denmark)

    Ullidtz, Per; Ertman Larsen, Hans JØrgen

    1997-01-01

    Most existing pavement subgrade criteria are based on the AASHO Road Test, where only one material was tested and for only one climatic condition. To study the validity of these criteria and to refine the criteria a co-operative research program entitled the "International Pavement Subgrade Performance Study" was sponsored by the FHWA with American, Finnish and Danish partners. This paper describes the first test series which was carried out in the Danish Road Testing Machine (RTM).The first step in this program is a full scale test on an instrumented pavement in the Danish Road Testing Machine. Pressure gauges and strain cells were installed in the upper part of the subgrade, for measuring stresses and strains in all three directions. During and after construction FWD testing was carried out to evaluate the elastic parameters of the materials. These parameters were then used with the theory of elasticity to calculate the stresses and strains at the position of the gauges and to compare these values to the stresses and strains recorded under the rolling wheel load.Plastic strains resulting from 50 000 applications of each of two load levels (20 kN and 40 kN) were recorded, as well as the permanent deformation of the pavement surface. A simple model describing the plastic strain has been developed.The test showed that currently used subgrade strain criteria are conservative if used with the measured strains in the subgrade. If used with strains calculated from FWD tests using linear elastic theory, however, the strain criteria seem to give a reasonably good prediction of the bearing capacity of the pavement.The differences between measured and theoretical values appear to be due to inhomogeneities in the pavement, to the non-linear elastic subgrade modulus and to a modulus gradient in the subgrade.

  6. 42 CFR 493.1415 - Condition: Laboratories performing moderate complexity testing; clinical consultant.

    Science.gov (United States)

    2010-10-01

    ...2010-10-01 false Condition: Laboratories performing moderate complexity testing...CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Personnel for Nonwaived Testing Laboratories Performing Moderate Complexity...

  7. 42 CFR 493.1409 - Condition: Laboratories performing moderate complexity testing; technical consultant.

    Science.gov (United States)

    2010-10-01

    ...2010-10-01 false Condition: Laboratories performing moderate complexity testing...CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Personnel for Nonwaived Testing Laboratories Performing Moderate Complexity...

  8. Performance tests during the ATLAS IBL Stave Integration

    CERN Document Server

    Jentzsch, Jennifer; The ATLAS collaboration

    2014-01-01

    In preparation of the ATLAS Pixel Insertable B-Layer integration, detector components, so called staves, were mounted around the Beryllium ATLAS beam pipe and tested using production quality assurance measurements as well as dedicated data taking runs to validate a correct grounding and shielding schema. Each stave consists of 32 FE-I4 readout chips of roughly 2x2cm size which sums up to over 860k pixels per stave. The integration tests include verification that neither the silicon n-in-n nor the silicon 3D sensors were damaged by mechanical stress, and that their readout chips, including their bump bond and wire bond connections, did not suffered from the integration process. Evolution of the IBL performance during its integration will be discussed as well as its final performance before installation.

  9. Performance test of the quenching meshes for hydrogen control

    International Nuclear Information System (INIS)

    The quenching distance of hydrogen gas was experimentally investigated by considering the effects of the initial pressure and steam addition. The quenching distance decreases with the initial pressure and there is a little increase with the addition of steam. Performance tests have been carried out to check the applicability of quenching mesh for the purpose of arresting hydrogen flame propagation during a severe accident in unclear power plants. The experimental facility for the performance test of the quenching mesh consisted of a model compartment, a visualization system and an ignition system. Dimensions of the single model compartment were 300x300x300 mm. Three-compartments are connected in parallel. The quenching mesh is located between the first and second compartments. It was observed that the flame from the first compartment where the ignition starts does not propagate to the second compartment. The quenching mesh played a role of preventing flame propagation. (author)

  10. Performance tests during the ATLAS IBL Stave Integration

    Science.gov (United States)

    Jentzsch, J.

    2015-04-01

    In preparation of the ATLAS Pixel Insertable B-Layer integration, detector components, so called staves, were mounted around the Beryllium ATLAS beam pipe and tested using production quality assurance measurements as well as dedicated data taking runs to validate a correct grounding and shielding schema. Each stave consists of 32 new generation readout chips which sum up to over 860k pixels per stave. The integration tests include verification that neither the silicon planar n+-in-n nor the silicon 3D sensors were damaged by mechanical stress, and that their readout chips, including their bump-bond and wire-bond connections, did not suffer from the integration process. Evolution of the detector performance during its integration will be discussed as well as its final performance before installation.

  11. Testing and Performance Analysis on Air Conditioner cum Water Dispenser

    Directory of Open Access Journals (Sweden)

    Dr. U. V.Kongrea , A. R. Chiddarwarb , P. C. Dhumatkarc , A.B.Aris

    2013-04-01

    Full Text Available The work on developing the heat pumps for space conditioning and water heating has been gone for half a century. The earlier water heating pumps and air to water heating pumps gives only hot water and space conditioning. But in this air conditioning cum water dispenser we get hot and cold water with hot and cold air, thus the system becomes multifunctional. The actual cycles and operating conditions for air and water cycle present in this paper. The paper introduced basic design principles and the test analysis performed in the laboratory. The test results were found encouraging especially the parameters of dispenser output along with air conditioner. The paper also introduced comfort conditions and suitable coefficient of performance with respect to atmospheric condition, without sacrificing the air conditioning output

  12. Performance testing of the LMT/GTM M2 positioner

    Science.gov (United States)

    Smith, David R.; Souccar, Kamal; Hernández Rebollar, José Luis; Arteaga Magaña, César; Gale, David M.; Cabrera Cuevas, Lizeth; Lucero Álvarez, Maribel; León-Huerta, Ándrea; Castro Santos, David; Hernández Rios, Emilio; Tzile Torres, Carlos; Lázaro Hernández, Josefina; Olmos Tapia, Arak

    2014-07-01

    Prior to the early science campaign of Spring 2013, the engineering team at the Large Millimeter Telescope/ Gran Telescopio Milimétrico (LMT/GTM) conducted a series of performance tests on the hexapod used for positioning the secondary reflector (M2 mirror). The tests were of particular interest to the project due to the high mass of the existing aluminum M2 mirror. The testing was conducted in a lower foundation room at the LMT site on a fixture that allowed the positioner and mirror to be oriented at both zenith and horizon orientations. In each of these positions, the repeatability of the system zero position was tested, along with both single degree-of-freedom (DOF) and combined DOF motions. Additionally, the tests investigated the stability of the system at constant command position to changes in the orientation of the unit with respect to gravity. Throughout these tests, a laser tracker was used for measurement of the position of targets on both the fixed base of the hexapod and on the outer rim of the M2 mirror. In this way, motions of the tracker head or of the support fixture could be eliminated from the analysis. In this paper, we present results of the accuracy and repeatability of the system, as well as comments on the effects of the laser tracker measurement geometry with respect to the system at the zenith and horizon orientations.

  13. A performance test for boar taint compounds in live boars

    OpenAIRE

    Baes, C.; Mattei, S; Luther, H; Ampuero, S; Sidler, X.; Bee, G.; Spring, P; Hofer, A.

    2013-01-01

    Genetically reducing boar taint using low-taint lines is considered the most sustainable and economic long-term alternative to surgical castration of male pigs. Owing to the high heritability of the main boar taint components (androstenone, skatole and indole), breeding is an excellent tool for reducing the number of tainted carcasses. To incorporate boar taint into breeding programmes, standardized performance testing is required. The objective of this study was to develop and formally prese...

  14. Development of Testing Methodologies to Evaluate Postflight Locomotor Performance

    Science.gov (United States)

    Mulavara, A. P.; Peters, B. T.; Cohen, H. S.; Richards, J. T.; Miller, C. A.; Brady, R.; Warren, L. E.; Bloomberg, J. J.

    2006-01-01

    Crewmembers experience locomotor and postural instabilities during ambulation on Earth following their return from space flight. Gait training programs designed to facilitate recovery of locomotor function following a transition to a gravitational environment need to be accompanied by relevant assessment methodologies to evaluate their efficacy. The goal of this paper is to demonstrate the operational validity of two tests of locomotor function that were used to evaluate performance after long duration space flight missions on the International Space Station (ISS).

  15. Comparative performance of image fusion methodologies in eddy current testing

    OpenAIRE

    S. Thirunavukkarasu; B.P.C. Rao; Anil Kumar Soni; S. Shuaib Ahmed; Jayakumar, T.

    2012-01-01

    Image fusion methodologies have been studied for improving the detectability of eddy current Nondestructive Testing (NDT). Pixel level image fusion has been performed on C-scan eddy current images of a sub-surface defect at two different frequencies. Multi-resolution analysis based Laplacian pyramid and wavelet fusion methodologies, statistical inference based Bayesian fusion and Principal Component Analysis (PCA) based fusion methodologies have been studied towards improving the detectabilit...

  16. Motivation and Performance in Physical Education: An Experimental Test

    OpenAIRE

    Moreno, Juan A.; David González-Cutre; José Martín-Albo; Eduardo Cervelló

    2010-01-01

    The purpose of this study was to analyse, experimentally, the relationships between motivation and performance in a lateral movement test in physical education. The study group consisted of 363 students (227 boys and 136 girls), aged between 12 and 16, who were randomly divided into three groups: an experimental group in which an incremental ability belief was induced, another experimental group in which an entity ability belief was induced, and a control group where there was no intervention...

  17. Rotor Performance at High Advance Ratio: Theory versus Test

    Science.gov (United States)

    Harris, Franklin D.

    2008-01-01

    Five analytical tools have been used to study rotor performance at high advance ratio. One is representative of autogyro rotor theory in 1934 and four are representative of helicopter rotor theory in 2008. The five theories are measured against three sets of well documented, full-scale, isolated rotor performance experiments. The major finding of this study is that the decades spent by many rotorcraft theoreticians to improve prediction of basic rotor aerodynamic performance has paid off. This payoff, illustrated by comparing the CAMRAD II comprehensive code and Wheatley & Bailey theory to H-34 test data, shows that rational rotor lift to drag ratios are now predictable. The 1934 theory predicted L/D ratios as high as 15. CAMRAD II predictions compared well with H-34 test data having L/D ratios more on the order of 7 to 9. However, the detailed examination of the selected codes compared to H-34 test data indicates that not one of the codes can predict to engineering accuracy above an advance ratio of 0.62 the control positions and shaft angle of attack required for a given lift. There is no full-scale rotor performance data available for advance ratios above 1.0 and extrapolation of currently available data to advance ratios on the order of 2.0 is unreasonable despite the needs of future rotorcraft. Therefore, it is recommended that an overly strong full-scale rotor blade set be obtained and tested in a suitable wind tunnel to at least an advance ratio of 2.5. A tail rotor from a Sikorsky CH-53 or other large single rotor helicopter should be adequate for this exploratory experiment.

  18. Temperature measurement. [liquid monopropellant rocket engine performance tests

    Science.gov (United States)

    1979-01-01

    The design, installation, checkout, calibration, and operation of a temperature measuring system to be used during tests of a liquid monopropellant rocket engine are discussed. Appendixes include: (1) temperature measurement system elemental uncertainties, and (2) tables and equations for use with thermocouples and resistance thermometers. Design guidelines are given for the critical components of each portion of the system to provide an optimum temperature measurement system which meets the performance criteria specified.

  19. Development and performance test of a small trailer-mounted moveable natural gas liquefier

    International Nuclear Information System (INIS)

    Highlights: ? A compact moveable small natural gas liquefier has been developed. ? All components used are easily available from the market as off-the-shelf products. ? A maximum liquefaction capacity of 15,000 Nm3/d was achieved using methane resources. ? The measured minimum specific power is 0.54 kW h/Nm3. ? Building a distributed liquefaction center with a group of liquefiers was proposed. - Abstract: A portable small liquefier for natural gas or coal-bed methane liquefaction has been designed and tested. The liquefier is very compact, and the compressor is directly mounted on a trailer. The liquefier is based on a mixed-refrigerant liquefaction cycle with R22 precooling. Most of the components in the liquefier are easily available off-the-shelf refrigeration products. An oil-lubricated single-stage R22 screw compressor is used for the mixed-refrigerant compression. An aluminum plate-fin heat exchanger with four flow passages was designed as the core of the cold box. The liquefier was tested for about 4 months by circulating pure methane as the natural gas resource. A maximum liquefaction capacity of 15,000 Nm3 was achieved with a minimum specific power consumption of about 0.54 kW h/Nm3. This liquefier can be used in various applications such as small natural gas or coalbed methane exploitations, distributed peak-shaving, and boil-off gas reliquefaction. These can also be used as a flexible distributed liquefas a flexible distributed liquefaction center with a set of small liquefiers.

  20. Seismic testing and performance of buckling-restrained bracing systems

    International Nuclear Information System (INIS)

    This paper describes a subassemblage seismic test program performed on six buckling-restrained braces (BRBs). Two different brace core segment lengths and two different buckling-restraining mechanisms were examined. The applied loading histories included a qualifying quasi-static cyclic test with stepwise incremental displacement amplitudes and a dynamically applied seismic loading. A test was also carried out on a conventional bracing member for comparison purposes. The concrete-filled tube specimens exhibited satisfactory performance under the quasi-static loading protocol, regardless of the length of the core segment. Strain hardening and frictional responses resulted in brace axial forces significantly exceeding the core yield capacity. The steel BRB system exhibited good performance under the quasi-static and dynamic loading sequences, provided that the clearance between the brace core and the buckling-restrained mechanism was kept to a minimum. The dynamic loading protocol was less severe for low-cycle fatigue than the quasi-static loading, but higher strain rates resulted in amplified yield resistance. The conventional bracing member withstood the entire quasi-static loading history but exhibited limited energy-dissipation capacity compared with the concrete-filled BRBs. (author)

  1. Results of performance tests on polymer zirconium compound (PZC)

    International Nuclear Information System (INIS)

    Three batches of polyzirconium compound (PZC) consisting of nine samples were tested for its application as column material for adsorbing reactor-produced molybdenum-99 (99Mo). Using low specific activity molybdenum solution (?500 ?Ci/267 mg Mo), the adsorption capacity, elution yield, elution volume and molybdenum breakthrough were measured. The average adsorption capacity of the nine samples is 239 ± 17 mg Mo/g PZC. The elution yield values obtained are lower than previously obtained and averaged at 47% with 30% variability. Molybdenum breakthrough also exceeded the limits for 99mTc eluates. Considering the better performance of 2002 PZC samples, the samples may have undergone some changes during storage (tests were performed in December 2003) and/or the adsorption process did not conform to the recommended procedure. If this were the case, it demonstrated the importance of strictly following the recommended protocol. Relative values showed that the last two batches (PZC 030718 and PC 030726) performed better than the first batch in terms of elution yield and elution profile. These two batches exhibited amorphous structure as seen by x-ray diffraction analysis of the PZC test samples. (author)

  2. Round robin performance testing of organic photovoltaic devices

    DEFF Research Database (Denmark)

    Gevorgyan, Suren; Zubillaga, Oihana

    2014-01-01

    This study addresses the issue of poor intercomparability of measurements of organic photovoltaic (OPV) devices among different laboratories. We present a round robin performance testing of novel OPV devices among 16 laboratories, organized within the framework of European Research Infrastructure Project (SOPHIA) and European Energy Research Alliance (EERA). Three types of OPVs with different structures, dimensions and encapsulations are studied and compared with reference Si solar cells certified by accredited laboratories. The agreement of the measurements of these among different laboratories is analyzed by focusing on testing procedures, testing equipment and sample designs. A number of deviations and pitfalls are revealed and based on the analyses, a set of recommendations are suggested for improving the agreement among the measurements of such OPV technologies. © 2013 Elsevier Ltd. All rights reserved.

  3. Imaging performance and tests of soft x-ray telescopes

    Energy Technology Data Exchange (ETDEWEB)

    Spiller, E.; McCorkle, R.; Wilczynski, J. (International Business Machines Corp., Yorktown Heights, NY (USA). Thomas J. Watson Research Center); Golub, L.; Nystrom, G. (Harvard-Smithsonian Center for Astrophysics, Cambridge, MA (USA)); Takacz, P.Z. (Brookhaven National Lab., Upton, NY (USA)); Welch, C. (Lockheed Missile and Space Co., Las Cruces, NM (USA))

    1990-08-01

    Photos obtained during 5 min. of observation time from the flight of our 10 in. normal incidence soft x-ray ({lambda} = 63.5{Angstrom}) telescope on September 11, 1989 are analyzed and the data are compared to the results expected from tests of the mirror surfaces. These tests cover a range of spatial periods from 25 cm to 1{Angstrom}. The photos demonstrate a reduction in the scattering of the multilayer mirror compared to a single surface for scattering angles above 1 arcmin, corresponding to surface irregularities with spatial periods below 10 {mu}m. Our results are used to predict the possible performance of future flights. Sounding rocket observations might be able to reach a resolution around 0.1 arcsec. Higher resolutions will require flights of longer durations and improvements in mirror testing for the largest spatial periods. 21 refs., 7 figs., 1 tab.

  4. High performance CLSM field mixing and pumping test results

    International Nuclear Information System (INIS)

    An improved low bleed water CLSM mix was field tested on May 13, 1997 at the Throop portable auger batching plant. Production and pumping tests were very successful. The four cubic yards of material pumped into a ply wood form where it flowed 48 feet (the entire length of the form). The CLSM slurry was very uniform, self leveling, cohesive, showed no segregation, and had no bleed water. Properties of the High Performance CLSM were the same for material collected at the auger and at the end of the pipeline except for the air content which was 5.5% at the auger and 3.2% at the end of the pipeline. This is exactly what was expected and indicates that this CLSM is easy to mix and pump in the Throop/BSRI equipment. CLSM Mix TW-10 is recommended for Tank Closure based on the field batching and pumping tests

  5. Final tests and performances verification of the European ALMA antennas

    Science.gov (United States)

    Marchiori, Gianpietro; Rampini, Francesco

    2012-09-01

    The Atacama Large Millimeter Array (ALMA) is under erection in Northern Chile. The array consists of a large number (up to 64) of 12 m diameter antennas and a number of smaller antennas, to be operated on the Chajnantor plateau at 5000 m altitude. The antennas will operate up to 950 GHz so that their mechanical performances, in terms of surface accuracy, pointing precision and dimensional stability, are very tight. The AEM consortium constituted by Thales Alenia Space France, Thales Alenia Space Italy, European Industrial Engineering (EIE GROUP), and MT Mechatronics is assembling and testing the 25 antennas. As of today, the first set of antennas have been delivered to ALMA for science. During the test phase with ESO and ALMA, the European antennas have shown excellent performances ensuring the specification requirements widely. The purpose of this paper is to present the different results obtained during the test campaign: surface accuracy, pointing error, fast motion capability and residual delay. Very important was also the test phases that led to the validation of the FE model showing that the antenna is working with a good margin than predicted at design level thanks also to the assembly and integration techniques.

  6. Addendum to ''Test Plan: Small-Scale Seal Performance Tests (SSSPT)''

    International Nuclear Information System (INIS)

    This document describes activities that are intended to update the data base of fluid flow measurements made on expansive salt concrete (ESC) seals as part of the Small-Scale Seal Performance Tests (SSSPT). The original plans for the SSSPT experiments are described by Stormont (1985a and 1985b). These seals have previously been tested with brine and gas during the early stages (less than 450 days) after emplacement. The purpose of this Test Plan Addendum is to detail the activities necessary to, update the gas and brine measurements previously performed on the SSSPT Series A and Series B seals and to identify the key personnel responsible for implementing these activities. This addendum describes a limited undertaking and does NOT change the scope of the original test plan

  7. The benefits of testing for learning on later performance.

    Science.gov (United States)

    McConnell, Meghan M; St-Onge, Christina; Young, Meredith E

    2015-05-01

    Testing has been shown to enhance retention of learned information beyond simple studying, a phenomena known as test-enhanced learning (TEL). Research has shown that TEL effects are greater for tests that require the production of responses [e.g., short-answer questions (SAQs)] relative to tests that require the recognition of correct answers [e.g., multiple-choice questions (MCQs)]. High stakes licensure examinations have recently differentiated MCQs that require the application of clinical knowledge (context-rich MCQs) from MCQs that rely on the recognition of "facts" (context-free MCQs). The present study investigated the influence of different types of educational activities (including studying, SAQs, context-rich MCQs and context-free MCQs) on later performance on a mock licensure examination. Fourth-year medical students (n = 224) from four Quebec universities completed four educational activities: one reading-based activity and three quiz-based activities (SAQs, context-rich MCQs, and context-free MCQs). We assessed the influence of the type of educational activity on students' subsequent performance in a mock licensure examination, which consisted of two types of context-rich MCQs: (1) verbatim replications of previous items and (2) items that tested the same learning objective but were new. Mean accuracy scores on the mock licensure exam were higher when intervening educational activities contained either context-rich MCQs (Mean z-score = 0.40) or SAQs (M = 0.39) compared to context-free MCQs (M = -0.38) or study only items (M = -0.42; all p learning through testing compared to context-free MCQs or studying alone. The extent to which these findings generalize beyond verbatim questions remains to be seen. PMID:24973998

  8. Test experience, 490 N high performance (321 sec Isp) engine

    Science.gov (United States)

    Schoenman, L.; Rosenberg, S. D.; Jassowski, D. M.

    1992-07-01

    Engines with area ratios of 44:1 and 286:1 are tested by means of hot fire tests using the NTO/MMH bipropellant to maximize the performance of the combined technologies. The low-thrust engine systems are designed with oxidation resistant materials that can operate at temperatures of more than 2204 C for tens of hours. The chamber is attached to the injector in a configuration that prevents overheating of the injector, valve, and the spacecraft interface. Three injectors with 44:1 area ratios are capable of nominal specific impulse values of 309 sec, and a performance of 321 lbf-sec/lbm is noted for an all-welded engine assembly with area ratio of 286:1. The all-welded engine is shown to have an acceptable design margin for thermal characteristics. High-performance liquid apogee engines are shown to perform optimally when based on iridium/rhenium chamber technology, use of a special platelet injector, and the minimization of losses due to fuel-film cooling.

  9. Test experience, 490 N high performance (321 sec Isp) engine

    Science.gov (United States)

    Schoenman, L.; Rosenberg, S. D.; Jassowski, D. M.

    1992-01-01

    Engines with area ratios of 44:1 and 286:1 are tested by means of hot fire tests using the NTO/MMH bipropellant to maximize the performance of the combined technologies. The low-thrust engine systems are designed with oxidation resistant materials that can operate at temperatures of more than 2204 C for tens of hours. The chamber is attached to the injector in a configuration that prevents overheating of the injector, valve, and the spacecraft interface. Three injectors with 44:1 area ratios are capable of nominal specific impulse values of 309 sec, and a performance of 321 lbf-sec/lbm is noted for an all-welded engine assembly with area ratio of 286:1. The all-welded engine is shown to have an acceptable design margin for thermal characteristics. High-performance liquid apogee engines are shown to perform optimally when based on iridium/rhenium chamber technology, use of a special platelet injector, and the minimization of losses due to fuel-film cooling.

  10. Comparative performance of image fusion methodologies in eddy current testing

    Directory of Open Access Journals (Sweden)

    S. Thirunavukkarasu

    2012-12-01

    Full Text Available Image fusion methodologies have been studied for improving the detectability of eddy current Nondestructive Testing (NDT. Pixel level image fusion has been performed on C-scan eddy current images of a sub-surface defect at two different frequencies. Multi-resolution analysis based Laplacian pyramid and wavelet fusion methodologies, statistical inference based Bayesian fusion and Principal Component Analysis (PCA based fusion methodologies have been studied towards improving the detectability of defects. The performance of the fusion methodologies has been compared using image metrics such as SNR and entropy. Bayesian based fusion methodology has shown better performance as compared to other methodologies with 33.75 dB improvement in the SNR and an improvement of 3.22 in the entropy.

  11. Diagnostic Performance of Visual Screening Tests in the Elderly

    Science.gov (United States)

    Lança, Carla Costa; Carolino, Elisabete

    2011-09-01

    This study aimed to determine and evaluate the diagnostic accuracy of visual screening tests for detecting vision loss in elderly. This study is defined as study of diagnostic performance. The diagnostic accuracy of 5 visual tests -near convergence point, near accommodation point, stereopsis, contrast sensibility and amsler grid—was evaluated by means of the ROC method (receiver operating characteristics curves), sensitivity, specificity, positive and negative likelihood ratios (LR+/LR-). Visual acuity was used as the reference standard. A sample of 44 elderly aged 76.7 years (±9.32), who were institutionalized, was collected. The curves of contrast sensitivity and stereopsis are the most accurate (area under the curves were 0.814-p = 0.001, C.I.95%[0.653;0.975]— and 0.713-p = 0.027, C.I.95%[0,540;0,887], respectively). The scores with the best diagnostic validity for the stereopsis test were 0.605 (sensitivity 0.87, specificity 0.54; LR+ 1.89, LR-0.24) and 0.610 (sensitivity 0.81, specificity 0.54; LR+ 1.75, LR-0.36). The scores with higher diagnostic validity for the contrast sensibility test were 0.530 (sensitivity 0.94, specificity 0.69; LR+ 3.04, LR-0.09). The contrast sensitivity and stereopsis test's proved to be clinically useful in detecting vision loss in the elderly.

  12. Test-taking Strategies & Performance on Reading Comprehension Tests by Iranian EFL Learners

    Directory of Open Access Journals (Sweden)

    Natasha Pourdana

    2012-07-01

    Full Text Available This study attempted to explore the possible relationship between test-taking strategies and (a successful performance on English as a Foreign Language (EFL reading comprehension, (b EFL learners’ level of language proficiency. To accomplish the purpose of this study, 68 students of English translation of both genders were randomly selected and placed in the three Beginner, Intermediate and Advanced levels, at Alborz Institute for Higher Education, Qazvin, Iran. Analysis of Variances (ANOVA proved that there was a significant and positive correlation between the scores in reading comprehension test and Oxford Placement Test. While the scores in reading comprehension test did not show any significant correlations with using the majority of test-taking strategies, they had a relatively low and negative but significant correlation with test management strategy. The findings in this study were interpreted as the low knowledge of test-taking strategies in Iranian EFL context and the importance of attending to the cognitive processes effective in taking language tests was emphasized. Keywords: Test-taking, Strategies, EFL, Reading Comprehension, Proficiency level

  13. A performance test for boar taint compounds in live boars.

    Science.gov (United States)

    Baes, C; Mattei, S; Luther, H; Ampuero, S; Sidler, X; Bee, G; Spring, P; Hofer, A

    2013-05-01

    Genetically reducing boar taint using low-taint lines is considered the most sustainable and economic long-term alternative to surgical castration of male pigs. Owing to the high heritability of the main boar taint components (androstenone, skatole and indole), breeding is an excellent tool for reducing the number of tainted carcasses. To incorporate boar taint into breeding programmes, standardized performance testing is required. The objective of this study was to develop and formally present a performance test for the main boar taint compounds on live breeding candidates. First, a standardized performance test for boar taint was established. A biopsy device was developed to extract small tissue samples (200 to 300 mg) from breeding candidates. Quantification of boar taint components from these small samples using specialized chemical extraction methods proved accurate and repeatable (r = 0.938). Following establishment of the method, biopsy samples of 516 live boars (100 to 130 kg live weight) were collected in the second step. Various mixed linear models were tested for each boar taint compound; models were ranked in terms of their information content. Pedigree information of 2245 ancestors of biopsied animals was included, and genetic parameters were estimated using univariate and multivariate models. Androstenone (in ?g/g liquid fat (LF): mean = 0.578, ? = 0.527), skatole (in ?g/g LF: mean = 0.033, ? = 0.002) and indole (in ?g/g LF: mean = 0.032, ? = 0.002) levels obtained by biopsy were plausible. Heritability estimates for androstenone calculated with univariate (0.453) and multivariate (0.452) analyses were comparable to those in the literature. Heritabilities for skatole (0.495) and indole (0.550) were higher than that for androstenone. Genetic and phenotypic correlations were similar to those published previously. Our results show that data on boar taint compounds from small adipose samples obtained by biopsy provide similar genetic parameters as that described in the literature for larger samples and are therefore a reliable performance test for boar taint in live breeding candidates. PMID:23211445

  14. Relationships between Chinese College Test Takers' Strategy Use and EFL Reading Test Performance: A Structural Equation Modeling Approach

    Science.gov (United States)

    Zhang, Limei; Zhang, Lawrence Jun

    2013-01-01

    This article investigates the relationships between test takers' strategy use and test performance on an EFL reading test. For this study 209 Chinese college students were invited to participate in a reading comprehension test and answer a 30-item strategy use questionnaire. Results showed that two factors underlay test takers' reading test

  15. CET performance at ROSA/LSTF tests. Twelve tests with core heat-up

    International Nuclear Information System (INIS)

    This report summarizes performance of core exit thermocouple (CET) observed in twelve ROSA/LSTF tests which include ten small-break loss-of-coolant accident (SBLOCA) tests and two abnormal transient tests. The report was prepared to a task group in the Working Group of Analysis and Management of Accident (WGAMA) at OECD/NEA, which had been set up to review and consolidate background knowledge of CET application to PWR accident management (AM) measures. The LSTF is the largest PWR simulator in the world with full-height, full-pressure and 1/48 volumetric scaling design. General CET performance to detect core heat-up in the LSTF tests is clarified as follows. (1) A time delay to detect core heat-up and a significant temperature difference from the hottest core are observed in most tests, (2) no CET heat-up was observed in two tests in which fall-back water from hot legs significantly influenced not only the CETs but also the local core cooling, (3) steam flow concentration into the control rod guide tube (CRGT) in case of a PV top SBLOCA test delayed heat-up of CETs installed outside of the CRGT, (4) two abnormal transient tests showed needs of CET superheat indication above saturation temperature during significantly high and low pressure boil-off transients, and (5) applicability of LSTF CET performance to PWR conditions should be carefully analyzed with respect to the fall-back water effects on atypical upper plenum configuration. (author)

  16. Calibration and performance testing of electronic personal dosimeters (EPD)

    International Nuclear Information System (INIS)

    In modern radiation protection practices, active personal dosimeters are becoming absolutely necessary operational tools for satisfying the ALARA principle. The aim of this work was to carry out calibration and performance testing of ten electronic personal dosimeters (EPD) used for the individual monitoring. The EPDs were calibrated in terms of operation radiation protection quantity, personal dose equivalent, Hp (10). Calibrations were carried out at three of x-ray beam qualities described in ISO 4037 namely 60, 100 and 150 kV in addition to Cs-137 gamma ray quality. The calibrations were performed using polymethylmethacrylate (PMMA) phantom with dimensions 20*20*15 cm3. Conversion coefficient Hp (10)/K air for the phantom was also calculated. The response and linearity of the dosimeter at the specified energies were also tested. The EPDs tested showed that the calibration coefficient ranged from 0.60 to 1.31 and an equivalent response for the specified energies that ranged from 0.76 to 1.67. The study demonstrated the possibility of using non standard phantom for calibrating dosimeters used for individual monitoring. The dosimeters under study showed a good response in all energies except the response in quality 100 kV. The linearity of the dosimeters was within ±15%, with the exception of the quality 100 kV where this limit was exceeded.(Author)

  17. Safety Performance of Airborne Separation: Preliminary Baseline Testing

    Science.gov (United States)

    Consiglio, Maria C.; Hoadley, Sherwood T.; Wing, David J.; Baxley, Brian T.

    2007-01-01

    The Safety Performance of Airborne Separation (SPAS) study is a suite of Monte Carlo simulation experiments designed to analyze and quantify safety behavior of airborne separation. This paper presents results of preliminary baseline testing. The preliminary baseline scenario is designed to be very challenging, consisting of randomized routes in generic high-density airspace in which all aircraft are constrained to the same flight level. Sustained traffic density is varied from approximately 3 to 15 aircraft per 10,000 square miles, approximating up to about 5 times today s traffic density in a typical sector. Research at high traffic densities and at multiple flight levels are planned within the next two years. Basic safety metrics for aircraft separation are collected and analyzed. During the progression of experiments, various errors, uncertainties, delays, and other variables potentially impacting system safety will be incrementally introduced to analyze the effect on safety of the individual factors as well as their interaction and collective effect. In this paper we report the results of the first experiment that addresses the preliminary baseline condition tested over a range of traffic densities. Early results at five times the typical traffic density in today s NAS indicate that, under the assumptions of this study, airborne separation can be safely performed. In addition, we report on initial observations from an exploration of four additional factors tested at a single traffic density: broadcast surveillance signal interference, extent of intent sharing, pilot delay, and wind prediction error.

  18. General Atomic's superconducting high field test facility and initial performance

    International Nuclear Information System (INIS)

    General Atomic has established a high field test facility whose primary mission is to investigate the J-B-T and stability performance margins of commercial NbTi superconductor in the 10 tesla, 4.20K region. This work is part of the overall DOE/MFE/MAGNETIC SYSTEMS effort to provide an adequate technological base for construction of superconducting toroidal field coils for the next generation of large tokamak fusion devices. The principal components of the facility are the coil/cryostat assembly, the helium refrigerator-liquefier/compressor system, and the gaseous helium recovery and storage system. The epoxy impregnated, layer wound main background field coil generates 8 tesla within its 40 cm diameter bore. The insert background field coil was layer wound with cooling channels provided by ''barber pole'' mylar conductor insulation. Ten tesla is generated within its 22 cm bore. The initial performance of the facility will be discussed. Future testing calls for operating test coils with implanted heating elements to simulate mechanically induced perturbations. The normal zone growth and recovery behavior will be observed for various disturbance energies. This data will then be compared with results obtained from the transient recovery analysis developed at General Atomic

  19. Ultradian rhythms in performance on tests of specialized cognitive function.

    Science.gov (United States)

    Gordon, H W; Stoffer, D S; Lee, P A

    1995-12-01

    Performance on cognitive tasks cycled at ultradian frequencies for 24 males over a test period of eight hours. The verbal task of written word production cycled at 80 minutes; the spatial task of locating points in space cycled at 96 minutes. Multiple cycles were seen for a perceptual speed task that factor loads on both the verbal and spatial task. Replication of the results for the first 12 and second 12 subjects demonstrated their robustness. The verbal and spatial tasks were chosen to reflect specialized functions of the left and right cerebral hemispheres, respectively. Accordingly, the results are interpreted as evidence that specialized task performances are associated with independent neurochemical systems. In addition, blood samples were taken at task performance to assess cyclicity of hormone levels. Luteinizing hormone had a period of 120 minutes, testosterone and cortisol were inconsistent and none seemed to be related to the cognitive tasks. However when subjects were divided according to a winter or summer testing schedule, the spatial periodicity was absent for the summer group and the verbal periodicity was absent for the winter peak. PMID:8869428

  20. AULA virtual reality test as an attention measure: convergent validity with Conners' Continuous Performance Test.

    Science.gov (United States)

    Díaz-Orueta, Unai; Garcia-López, Cristina; Crespo-Eguílaz, Nerea; Sánchez-Carpintero, Rocío; Climent, Gema; Narbona, Juan

    2014-01-01

    The majority of neuropsychological tests used to evaluate attention processes in children lack ecological validity. The AULA Nesplora (AULA) is a continuous performance test, developed in a virtual setting, very similar to a school classroom. The aim of the present study is to analyze the convergent validity between the AULA and the Continuous Performance Test (CPT) of Conners. The AULA and CPT were administered correlatively to 57 children, aged 6-16 years (26.3% female) with average cognitive ability (IQ mean = 100.56, SD = 10.38) who had a diagnosis of attention deficit/hyperactivity disorder (ADHD) according to DSM-IV-TR criteria. Spearman correlations analyses were conducted among the different variables. Significant correlations were observed between both tests in all the analyzed variables (omissions, commissions, reaction time, and variability of reaction time), including for those measures of the AULA based on different sensorial modalities, presentation of distractors, and task paradigms. Hence, convergent validity between both tests was confirmed. Moreover, the AULA showed differences by gender and correlation to Perceptual Reasoning and Working Memory indexes of the WISC-IV, supporting the relevance of IQ measures in the understanding of cognitive performance in ADHD. In addition, the AULA (but not Conners' CPT) was able to differentiate between ADHD children with and without pharmacological treatment for a wide range of measures related to inattention, impulsivity, processing speed, motor activity, and quality of attention focus. Additional measures and advantages of the AULA versus Conners' CPT are discussed. PMID:23638628

  1. Testing the equality of students' performance using Alexander-Govern test with adaptive trimmed means

    Science.gov (United States)

    Abdullah, Suhaida; Yahaya, Sharipah Soaad Syed; Yusof, Zahayu Md

    2014-06-01

    Analyzing the equality of independent group has to be done with caution. The classical approaches such as ttest for two groups and analysis of variance (ANOVA) for more than two groups always are favorable selection by researchers. However, sometime these methods were abused by the presence of nonnormality or variance heterogeneity or both. It is known that ANOVA is restricted to the assumptions of normality and homogeneity of variance. In real life data, sometimes these requirements are hard to attain. The Alexander-Govern test with adaptive trimmed mean (AG_atm) is one approach that can be chosen as alternative to the classical tests when their assumptions are violated. In this paper, the performances of AG_atm were compared to the original AG test and ANOVA using simulated and real life data. The simulation study proved that the AG_atm performs better than the original AG test and the classical test. For real life data, student's performance in decision analysis course, measured by final examination score was chosen. Based on the exploratory data analysis, this data found to have problem of nonnormality.

  2. Development of the preparation technology of macroporous sorbent for industrial off-gas treatment including 14C

    International Nuclear Information System (INIS)

    For environmental and health effects due to increasing levels of pollution in the atmosphere, it is necessary to develop environmentally sound technologies for the treatment of greenhouse gases (CO2, CH4, CFC, etc.) and acid gases (SOx, NOx, etc.). Specifically, advanced technology for CO2 capturing is currently one of the most important environmental issues in worldwide. 14CO2, specially which has been gradually emerging issue in the nuclear facilities, is generated about 330 ppm from the CANDU (Canadian Deuterium Uranium Reactor) nuclear power plant and the DUPIC (Direct Use of spent PWR fuel in CANDU reactors) process which is the process of spent fuel treatment. For this purpose, it is necessary to develop the most efficient treatment technology of CO2 capture by various lime materials in semi- or dry process, it should be also considering a removal performance, waste recycling and safety of disposal. In order to develop a highly active slaked lime as a sorbent for CO2 and high temperature desulfurization, macroporous slaked lime is necessarily prepared by modified swelling process and equipment, which was developed under carrying out this project. And also for the optimal removal process of off-gases the removal performance tests of various sorbents and the effects of relative humidity and bed depth on the removal capacity must be considered

  3. FINAL REPORT INTEGRATED DM1200 MELTER TESTING OF REDOX EFFECTS USING HLW AZ-101 AND C-106/AY-102 SIMULANTS VSL-04R4800-1 REV 0 5/6/

    Energy Technology Data Exchange (ETDEWEB)

    KRUGER AA; MATLACK KS; GONG W; BARDAKCI T; D' ANGELO NA; LUTZE W; BIZOT PM; CALLOW RA; BRANDYS M; KOT WK; PEGG IL

    2011-12-29

    This report documents melter and off-gas performance results obtained on the DM1200 HLW Pilot Melter during processing of AZ-101 and C-106/AY-102 HLW simulants. The tests reported herein are a subset of three tests from a larger series of tests described in the Test Plan for the work; results from the remaining tests will be reported separately. Three nine day tests, one with AZ-101 and two with C-106/AY-102 feeds were conducted with variable amounts of added sugar to address the effects of redox. The test with AZ-101 included ruthenium spikes to also address the effects of redox on ruthenium volatility. One of tests addressed the effects of increased flow-sheet nitrate levels using C-106/AY-102 feeds. With high nitrate/nitrite feeds (such as WTP LAW feeds), reductants are required to prevent melt foaming and deleterious effects on glass production rates. Sugar is the baseline WTP reductant for this purpose. WTP HLW feeds typically have relatively low nitrate/nitrite content in comparison to the organic carbon content and, therefore, have typically not required sugar additions. However, HLW feed variability, particularly with respect to nitrate levels, may necessitate the use of sugar in some instances. The tests reported here investigate the effects of variable sugar additions to the melter feed as well as elevated nitrate levels in the waste. Variables held constant to the extent possible included melt temperature, bubbling rate, plenum temperature, cold cap coverage, the waste simulant composition, and the target glass composition. The principal objectives of the DM1200 melter testing were to determine the achievable glass production rates for simulated HLW feeds with variable amounts of added sugar and increased nitrate levels; characterize melter off-gas emissions; characterize the performance of the prototypical off-gas system components as well as their integrated performance; characterize the feed, glass product, and off-gas effluents; and perform pre- and post test inspections of system components. The specific objectives (including test success criteria) of this testing, along with how each objective was met, are outlined in a table.

  4. Final Report Integrated DM1200 Melter Testing Of Redox Effects Using HLW AZ-101 And C-106/AY-102 Simulants VSL-04R4800-1, Rev. 0, 5/6/04

    International Nuclear Information System (INIS)

    This report documents melter and off-gas performance results obtained on the DM1200 HLW Pilot Melter during processing of AZ-101 and C-106/AY-102 HLW simulants. The tests reported herein are a subset of three tests from a larger series of tests described in the Test Plan for the work; results from the remaining tests will be reported separately. Three nine day tests, one with AZ-101 and two with C-106/AY-102 feeds were conducted with variable amounts of added sugar to address the effects of redox. The test with AZ-101 included ruthenium spikes to also address the effects of redox on ruthenium volatility. One of tests addressed the effects of increased flow-sheet nitrate levels using C-106/AY-102 feeds. With high nitrate/nitrite feeds (such as WTP LAW feeds), reductants are required to prevent melt foaming and deleterious effects on glass production rates. Sugar is the baseline WTP reductant for this purpose. WTP HLW feeds typically have relatively low nitrate/nitrite content in comparison to the organic carbon content and, therefore, have typically not required sugar additions. However, HLW feed variability, particularly with respect to nitrate levels, may necessitate the use of sugar in some instances. The tests reported here investigate the effects of variable sugar additions to the melter feed as well as elevated nitrate levels in the waste. Variables held constant to the extent possible included melt temperature, bubbling rate, plenum temperature, cold cap coverage, the waste simulant composition, and the target glass composition. The principal objectives of the DM1200 melter testing were to determine the achievable glass production rates for simulated HLW feeds with variable amounts of added sugar and increased nitrate levels; characterize melter off-gas emissions; characterize the performance of the prototypical off-gas system components as well as their integrated performance; characterize the feed, glass product, and off-gas effluents; and perform pre- and post test inspections of system components. The specific objectives (including test success criteria) of this testing, along with how each objective was met, are outlined in a table.

  5. Performance and QA tests for thermometers used in hyperthermia

    International Nuclear Information System (INIS)

    Accuracy, precision, and reliability of thermometers is essential for good quality Hperthermia Treatments. Control of perturbation artifacts and uniformity of temperature calibrations are necessary if multi-institutional thermal doses are to intercompared. The Hyperthermia Physics Center, operating under NCI Contract, is developing a secondary standards thermometry calibration laboratory to conduct tests for thermometer performance. The authors define operational accuracy based on intercomparison of a test thermometer with NBS traceable standards. Precision is characterized by short term (few seconds) reproducibility of a reading at a given temperature. Stability is operationally characterized by reproducibility of probe response over the clinical treatment time of about 1 hour. In addition, the authors measure the thermometer response time, which is of relevance in selecting suitable systems for SAR or thermal washout measurements. Results of these measurements for a variety of thermometers tested thus far are reported. In addition, the measurement of perturbation in temperature reading by interference of EM or RF fields is being considered. Design criteria for the phantom and techniques to be used in this test and the results obtained for the fibre-optic and other minimally perturbed thermometers are be presented

  6. Performance testing of automatic vehicle radioactive sources monitors

    International Nuclear Information System (INIS)

    The tests of the stationary devices for the detection of the radioactive sources in moving trucks were performed by the Czech Metrological Institute - Inspectorate for Ionising Radiation, Prague in December 1996 and September 1997. Ten different systems were installed and tested at a railway polygon. The basic part of each system - two detection units were placed symmetrically at the rail in a distance 2.3 m from the axe of the rail. The train comprising empty and scrap-filled trucks passed along the detection units at a speed of 5 to 30 km/h. The wide range of radioactive sources with 137Cs (activity ranging from 0.4 MBq to 5 GBq) were located at different positions in the truck. The purpose was to determine a detection limit under different conditions. Sources with 57Co, 60Co, 241Am were also used. The truck passed the polygon more then 1000 times. About 250 passes were free of source. All systems were also tested in a climatic chamber. The main features evaluated were the detection limit for an empty truck, detection limit for a truck filled with scrap (density 0.89 t/m3), percentage of false alarms and stability of response to different temperatures. The other features like energy dependence, position dependence, linearity and overload, detection response time, etc., were also evaluated. The tested systems showing a positive result will be sued in the field of steel recycling, metallurgy and the supervision of illegal transport. (author)

  7. Gamma thermometer longevity test: Laguna Verde 2 instruments recent performance

    Energy Technology Data Exchange (ETDEWEB)

    Cuevas V, G. [Global Nuclear Fuel, Americas, 3901 Castle Hayne Road, Wilmington, North Carolina (United States); Avila N, A.; Calleros M, G., E-mail: Gabriel.Cuevas-Vivas@gnf.com [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verda, Carretera Veracruz-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

    2013-10-15

    This paper is informative of the General Electric Hitachi and Global Nuclear Fuel - Americas are collaboration with Comision Federal de Electricidad in a longevity test of thermocouples as power monitoring devices. The test conclusions will serve for final engineering design in detailing the Automated Fixed In-core Probes for calibration of the Local Power Range Monitors (LPRMs) of the Economic Simplified Boiling Water Reactor. This paper introduces the collaboration description and some recent performance evaluation of the thermocouples that are sensitive to gamma radiation and are known generically as Gamma Thermometers (G T). The G Ts in Laguna Verde 2 are radially located inside six instrumentation tubes in the core and consist of seven thermocouples, four are aligned with the LPRM heights and three are axially located between LPRM heights. The Laguna Verde 2 G T test has become the longest test of thermocouples as power monitoring devices in a BWR industry history and confirms their reliability in terms of time-dependent small noise under steady state reactor conditions and good agreement against Traversing In-core Probes power measurements. (Author)

  8. Gamma thermometer longevity test: Laguna Verde 2 instruments recent performance

    International Nuclear Information System (INIS)

    This paper is informative of the General Electric Hitachi and Global Nuclear Fuel - Americas are collaboration with Comision Federal de Electricidad in a longevity test of thermocouples as power monitoring devices. The test conclusions will serve for final engineering design in detailing the Automated Fixed In-core Probes for calibration of the Local Power Range Monitors (LPRMs) of the Economic Simplified Boiling Water Reactor. This paper introduces the collaboration description and some recent performance evaluation of the thermocouples that are sensitive to gamma radiation and are known generically as Gamma Thermometers (G T). The G Ts in Laguna Verde 2 are radially located inside six instrumentation tubes in the core and consist of seven thermocouples, four are aligned with the LPRM heights and three are axially located between LPRM heights. The Laguna Verde 2 G T test has become the longest test of thermocouples as power monitoring devices in a BWR industry history and confirms their reliability in terms of time-dependent small noise under steady state reactor conditions and good agreement against Traversing In-core Probes power measurements. (Author)

  9. Electrical performance characteristics of the SSC Accelerator System String Test

    International Nuclear Information System (INIS)

    The intent of the Accelerator System String Test (ASST) is to obtain data for model verification and information on the magnitudes of pressures and voltages encountered in an accelerator environment. The ASST milestone run was achieved during July and August, 1992 and consisted of demonstrating the accelerator components could be configured together as a system operating at full current. Following the milestone run, the string was warmed to counteract some design flaws that impeded the operational range. The string was again cooled to cryogenic temperatures in October, and a comprehensive power testing program was conducted through the end of January, 1993. This paper describes how the collider arc components operate in an accelerator environment during quenches induced by firing both strip heaters and spot heaters. Evaluation of the data illustrates how variations in the design parameters on magnets used in a string environment can impact system performance

  10. Electrical performance characteristics of the SSC accelerator system string test

    International Nuclear Information System (INIS)

    The intent of the Accelerator System String Test (ASST) is to obtain data for model verification and information on the magnitudes of pressures and voltages encountered in an accelerator environment. The ASST milestone run was achieved during July and August, 1992 and consisted of demonstrating that the accelerator components could be configured together as a system operating at full current. Following the milestone run, the string was warmed to counteract some design flaws that impeded the operational range. The string was again cooled to cryogenic temperatures in October, and a comprehensive power testing program was conducted through the end of January, 1993. This paper describes how the collider arc components operate in an accelerator environment during quenches induced by firing both strip heaters and spot heaters. Evaluation of the data illustrates how variations in the design parameters on magnets used in a string environment can impact system performance

  11. Performance of the CREAM calorimeter in accelerator beam test

    CERN Document Server

    Yoon, Y S; Bagliesi, M G; Bigongiari, G; Ganel, O; Han, J H; Hyun, H J; Jeon, J A; Kang, T G; Kim, H J; Kim, K C; Lee, J K; Lee, M H; Lutz, L; Maestro, P; Malinine, A; Marrocchesi, P S; Nam, S W; Park, H; Park, I H; Park, N H; Seo, E S; Sina, R; Wu, J; Yang, J; Zei, R; Zinn, S Y

    2010-01-01

    The CREAM calorimeter, designed to measure the spectra of cosmic-ray nuclei from under 1 TeV to 1000 TeV, is a 20 radiation length (X0) deep sampling calorimeter. The calorimeter is comprised of 20 layers of tungsten interleaved with 20 layers of scintillating fiber ribbons, and is preceded by a pair of graphite interaction targets providing about 0.42 proton interaction lengths (\\lambda int). The calorimeter was placed in one of CERN's SPS accelerator beams for calibration and testing. Beams of 150 GeV electrons were used for calibration, and a variety of electron, proton, and nuclear fragment beams were used to test the simulation model of the detector. In this paper we discuss the performance of the calorimeter in the electron beam and compare electron beam data with simulation results.

  12. Predictors of neuropsychological effort test performance in schizophrenia.

    Science.gov (United States)

    Morra, Lindsay F; Gold, James M; Sullivan, Sara K; Strauss, Gregory P

    2015-03-01

    There is some evidence that insufficient effort may be common in schizophrenia, posing significant threats to the validity of neuropsychological test results. Low effort may account for a significant proportion of variance in neuropsychological test scores and the generalized cognitive deficit that characterizes the disorder. The current study evaluated clinical predictors of insufficient effort in schizophrenia using an embedded effort measure, the Repeatable Battery for the Assessment of Neuropsychological Status (RBANS) Effort Index (EI). Participants were 330 patients meeting DSM-IV-TR criteria for schizophrenia, schizoaffective disorder, or another psychotic disorder who received a battery of neuropsychological tests, including: Wechsler Test of Adult Reading (WTAR), Wechsler Abbreviated Scale of Intelligence (WASI), and RBANS. Clinical assessments designed to measure functional outcome and symptoms were also obtained. Results indicated that 9.4% of patients failed the EI. Patients who failed had lower full-scale, verbal, and performance IQ, as well as poorer performance on RBANS domains not included in the EI (immediate memory, language, and visuospatial/construction). Patients who failed the EI also displayed poorer community-based vocational outcome, greater likelihood of having "deficit schizophrenia" (i.e., primary and enduring negative symptoms), and increased severity of positive symptoms. Regression analyses revealed that insufficient effort was most significantly predicted by a combination of low IQ, negative symptoms, and positive symptoms. Findings suggest that although insufficient effort may be relatively uncommon in schizophrenia, it is associated with important clinical outcomes. The RBANS EI may be a useful tool in evaluating insufficient effort in schizophrenia. PMID:25583248

  13. Performance Testing of Ion Nitridation System for Surface Treatment

    International Nuclear Information System (INIS)

    It has been carried out a performance testing of ion nitridation system for surface treatment. The purpose of the testing is to check the performance of constructed ion nitridation system for improving of surface hardness of the metal. Testing done cover the vacuum, utilization of ion nitridation system for treatment of the samples and its characterization. It’s found that the vacuum system with reactor tube can achieve in order of 3.7 X 10-2 mbar while without reactor tube, the vacuum in order of 3 x 10-2 mbar. From this result it can be concluded that there is no leak of vacuum system. Utilization testing of the ion nitridation system done by introducing N2 and N2 + H2 gas into reactor tube. It’s found that, if the reactive gas only N2, the improving hardness that can be achieved only in order of 523.5 KHN. While if the reactive gas is the mixing of N2 + H2, the improving hardness that can be achieved in order 868.5 KHN. It meant that there is an increasing in hardness in order of 4.05 times. Observation of the diffusion depth of the nitrogen has been done by measuring the hardness of the cross section microstructure samples. It ’s found that the diffusion depth of the nitrogen is in order of 110 ?m. From micro structure observation, it’s found that there are changing in grain size in order of 95 ?m from the surface. From these result, it can be concluded that the constructed ion nitridation system can be operated well. (author)

  14. Performance Tests of Shell and Plate Type Evaporator for OTEC

    Science.gov (United States)

    Nakaoka, Tsutomu; Uehara, Haruo

    Performance tests on a shell and plate type evaporator (total surface area = 21.95m2, length = 1450mm, width = 235mm, plate number = 100) for ocean thermal energy conversion (OTEC) plants. Freon 22 (R22) and ammonia (NH3) are used as working fluid. The empirical correlations are proporsed in order to predict the boiling heat transfer when using R22 and NH3 and water side heat transfer coefficients for a shell and plate type evaporator. The water side pressure drop is about 3 m at the warm water velocity of 0.7 m/s. The water side friction factor is obtained.

  15. Pressure measurement. [liquid monopropellant rocket engine performance tests

    Science.gov (United States)

    1979-01-01

    Practices are outlined for the design, installation, checkout, calibration, and operation of a pressure measuring system to be used during tests of a liquid monopropellant rocket engine. Appendixes include: (1) pressure measurement system elemental uncertainties; (2) short- and long-term pressure measurement system uncertainty; (3) shunt calibration of pressure transducers; (4) special considerations for vacuum measurement; and (5) methods of determining the dynamic characteristics of pressure transducers. Design guidelines are provided for the critical components of each portion of the system to provide a pressure measurement system which meets the performance criteria specified.

  16. Performance test for a TU-TPC prototype electronics

    International Nuclear Information System (INIS)

    TU-TPC electronics is used to get information on the arrival time and charge of the electrons which drift to the readout detector from the drift. The quantity of charge is measured by method of digital integral based on FADC results and the arrival time is recorded by HPTDC cell. It has excellent performance such as good resolution for time and charge measure, low noise and cross talk between different parts. First, the paper introduces the architecture and principle of TU-TPC electronics, and the presents some parameter measurements by some specific designed test. In the end, the electronic system was connected to the TPC chamber and take data,. Through off-line analysis, charged particle track was reconstructed and diffusion constant, spatial resolution was computed. It shows TU-TPC electronics has excellent performance and can be well capable of readout for TPC prototype. (authors)

  17. The Interaction between Cognitive Test-Taking Strategies, Reading Ability, and Reading Comprehension Test Performance of Iranian EFL Learners

    OpenAIRE

    Narjes Ghafournia; Akbar Afghari

    2013-01-01

    The study scrutinized the probable interaction between using cognitive test-taking strategies, reading proficiency, and reading comprehension test performance of Iranian postgraduate students, who studied English as a foreign language. The study also probed the extent to which the participants’ test performance was related to the use of certain cognitive test-taking strategies. The participants were 343 MA students, who took an English reading comprehension test and answered a test-taking str...

  18. 40 CFR 60.3027 - How do I conduct the initial and annual performance test?

    Science.gov (United States)

    2010-07-01

    ...consist of a minimum of three test runs conducted under conditions...operations. (b) All performance tests must be conducted using the...subpart. (c) All performance tests must be conducted using the...composition analysis, including measurement of oxygen...

  19. Jules Horowitz Reactor: a high performance material testing reactor

    International Nuclear Information System (INIS)

    The physical modelling of materials' behaviour under severe conditions requires flexible experiments integrating higher scales and coupled phenomena and offering high quality measurements; these experiments are performed in material testing reactors (MTR). Moreover, complementary representative experiments are usually performed in prototypes or dedicated facilities such as IFMIF for fusion. Only such a consistent set of tools operating on a wide range of scales, can provide an actual prediction capability. A program such as the development of silicon carbide composites (600 - 1200 C degrees) illustrates this multi-scale strategy. Facing the long term needs of experimental irradiations and the ageing of present MTRs, it was thought necessary to implement a new generation high performance MTR in Europe for supporting existing and future nuclear reactors. The Jules Horowitz Reactor (JHR) project copes with this context. It is funded by an international consortium and will start operation in 2014. JHR will provide improved performances such as high neutron flux (1015 n/cm2/s above 0.1 MeV) in representative environments (coolant, pressure, temperature) with online monitoring of experimental parameters (including stress and strain control). Experimental devices designing, such as high dpa and small thermal gradients experiments, is now a key objective requiring a broad collaboration to put together present scientific state of art, end-users requiremenentific state of art, end-users requirements and advanced instrumentation

  20. The development and performance testing of a biodegradable scale inhibitor

    Energy Technology Data Exchange (ETDEWEB)

    Hardy, Julie; Fidoe, Steve; Jones, Chris

    2006-03-15

    The oil industry is currently facing severe restrictions concerning the discharge of oil field chemicals into the environment. Many commonly used materials in both topside and downhole applications are phased for substitution for use in the North Sea, and more will be identified. The development of biodegradable and low toxicity chemicals, which afford equal or improved efficacy, compared to conventional technology, available at a competitive price, is a current industry challenge. A range of biodegradable materials are increasingly available, however their limited performance can result in a restricted range of applications. This paper discusses the development and commercialization of a readily biodegradable scale inhibitor, ideal for use in topside applications. This material offers a broad spectrum of activity, notably efficiency against barium sulphate, calcium sulphate and calcium carbonate scales, in a range of water chemistries. A range of performance testing, compatibility, stability and OCNS dataset will be presented. Comparisons with commonly used chemicals have been made to identify the superior performance of this phosphate ester. This paper will discuss a scale inhibitor suitable for use in a variety of conditions which offers enhanced performance combined with a favourable biodegradation profile. This material is of great benefit to the industry, particularly in North Sea applications. (author) (tk)

  1. Sleep deprivation impairs performance in the 5-choice continuous performance test: similarities between humans and mice.

    Science.gov (United States)

    van Enkhuizen, Jordy; Acheson, Dean; Risbrough, Victoria; Drummond, Sean; Geyer, Mark A; Young, Jared W

    2014-03-15

    Several groups undergo extended periods without sleep due to working conditions or mental illness. Such sleep deprivation (SD) can deleteriously affect attentional processes and disrupt work and family functioning. Understanding the biological underpinnings of SD effects may assist in developing sleep therapies and cognitive enhancers. Utilizing cross-species tests of attentional processing in humans and rodents would aid in mechanistic studies examining SD-induced inattention. We assessed the effects of 36h of: (1) Total SD (TSD) in healthy male and female humans (n=50); and (2) REM SD (RSD) in male C57BL/6 mice (n=26) on performance in the cross-species 5-choice continuous performance test (5C-CPT). The 5C-CPT includes target trials on which subjects were required to respond and non-target trials on which subjects were required to inhibit from responding. TSD-induced effects on human psychomotor vigilance test (PVT) were also examined. Effects of SD were also examined on mice split into good and poor performance groups based on pre-deprivation scores. In the human 5C-CPT, TSD decreased hit rate and vigilance with trend-level effects on accuracy. In the PVT, TSD slowed response times and increased lapses. In the mouse 5C-CPT, RSD reduced accuracy and hit rate with trend-level effects on vigilance, primarily in good performers. In conclusion, SD induced impaired 5C-CPT performance in both humans and mice and validates the 5C-CPT as a cross-species translational task. The 5C-CPT can be used to examine mechanisms underlying SD-induced deficits in vigilance and assist in testing putative cognitive enhancers. PMID:24333377

  2. Construction and performance tests of hydrogen secondary cooling system, (2)

    International Nuclear Information System (INIS)

    In order to simulate the heat exchanging system between the primary helium gas and the secondary reducing gas system of a multi-purpose VHTR, a hydrogen gas loop was constructed. The thermal performance tests of the heat exchangers as well as the thermal insulation in the high-temperature components of the hydrogen gas loop were made. The test conditions were almost the same as the operating conditions of the VHTR: Hydrogen gas temperature: --9000C, Hydrogen gas pressure: --40 kg/cm2.G, Helium gas temperature: --1,0000C, Helium gas pressure: --40 kg/cm2.G. The results obtained were as follows; (1) The experimental values of thermal performance of the heat exchangers, such as overall heat transfer coefficient and temperature efficiency, were in good agreement with the calculated ones. Accordingly it might be considered that the analytical method applied in this report was appropriate. (2) The temperature distribution of the pressure tubes of high-temperature components were found to be almost uniform, and no hot-spots were observed. Since the effective thermal conductivity of the thermal insulation agreed fairly well with the other data, it could be assumed that no defect in packing of thermal insulation occurred. (author)

  3. Performance Test of Engine Fuelled With Diesel and Ethanol Blends.

    Directory of Open Access Journals (Sweden)

    B.K.L.Murthy

    2015-04-01

    Full Text Available Environmental concerns and limited amount of petroleum fuels have caused interests in the development of alternative fuels for internal combustion (ICengines. As an alternative, biodegradable and renewable fuel, ethanol is receiving increasing attention. An experimental investigation on the application of the blends of ethanol with diesel to a diesel engine was carried out. First the solubility of ethanol and diesel was conducted with and without the additive of normal butanol (n-butanol. The purpose of this project is to find the optimum percentage of ethanol that gives simultaneously better performance and lower emissions. The experiments were conducted on a water-cooled single-cylinder Direct Injection (DI diesel engine using 0% (neat diesel fuel, 10% (E10-D, 15%(E15–D, 20% (E20–D, and 25%(E25–D ethanol–diesel blended fuels. Experimental tests were carried out to study the performance of the engine fuelled with the blends compared with those fuelled by diesel. The test results show that it is feasible and applicable for the blends with n-butanol to replace pure diesel as the fuel for diesel engine.

  4. Calculation of the radiation dose from an upset condition in the off-gas system for a boiling water power reactor

    International Nuclear Information System (INIS)

    A study has been made which considered the upset conditions to result in a rupture of the delay line or charcoal adsorber portions of the radioactive off-gas treatment system for a boiling water power reactor. Radiation dose calculations were made for an individual at a 300-meter boundary fence. The doses calculated were the whole body immersion dose and the thyroid, bone and lung doses due to inhalation. The relationship between the various operating and upset parameters of the off-gas system and the radiation doses were investigated. A semi-infinite cloud model with a ground level release was assumed. For a delay line rupture, the calculated gamma immersion dose varies from a high of 9 rad for a break at the condenser to a low of 0.2 rad for a break at the maximum end of a 300-minute delay line. The thyroid dose from inhalation of radioiodine was calculated to vary from 3 to 6 millirem for a delay line rupture and to be 0.6 rem for a charcoal bed rupture. The highest gamma immersion dose from a charcoal adsorber bed rupture was calculated to be 1.5 rad for the low flow rate condition with either an ambient or chilled bed system. Curves have been constructed which show the variation of the calculated doses with the various input parameters. (U.S.)

  5. ?-alanine supplementation improves YoYo intermittent recovery test performance

    Directory of Open Access Journals (Sweden)

    Saunders Bryan

    2012-08-01

    Full Text Available Abstract Background ?-alanine supplementation has been shown to improve high-intensity exercise performance and capacity. However, the effects on intermittent exercise are less clear, with no effect shown on repeated sprint activity. The aim of this study was to investigate the effects of ?-alanine supplementation on YoYo Intermittent Recovery Test Level 2 (YoYo IR2 performance. Methods Seventeen amateur footballers were allocated to either a placebo (PLA; N = 8 or ?-alanine (BA; N = 9 supplementation group, and performed the YoYo IR2 on two separate occasions, pre and post 12 weeks of supplementation during a competitive season. Specifically, players were supplemented from early to mid-season (PLA: N = 5; BA: N = 6 or mid- to the end of the season (PLA: N = 3; BA: N = 3. Data were analysed using a two factor ANOVA with Tukey post-hoc analyses. Results Pre supplementation scores were 1185 ± 216 and 1093 ± 148 m for PLA and BA, with no differences between groups (P = 0.41. YoYo performance was significantly improved for BA (+34.3%, P ? 0.001 but not PLA (?7.3%, P = 0.24 following supplementation. 2 of 8 (Early – Mid: 2 of 5; Mid – End: 0 of 3 players improved their YoYo scores in PLA (Range: -37.5 to + 14.7% and 8 of 9 (Early – Mid: 6 of 6; Mid – End: 2 of 3 improved for BA (Range: +0.0 to +72.7%. Conclusions 12 weeks of ?-alanine supplementation improved YoYo IR2 performance, likely due to an increased muscle buffering capacity resulting in an attenuation of the reduction in intracellular pH during high-intensity intermittent exercise.

  6. AIChe equipment testing procedure centrifugal compressors : a guide to performance evaluation and site testing

    CERN Document Server

    AIChE

    2013-01-01

    With its engineer-tested procedures and thorough explanations, Centrifugal Compressors is an essential text for anyone engaged in implementing new technology in equipment design, identifying process problems, and optimizing equipment performance.  This condensed book presents a step by step approach to preparing for, planning, executing, and analyzing tests of centrifugal compressors, with an emphasis on methods that can be conducted on-site and with an acknowledgement of the strengths and limitations of these methods. The book opens with an extensive and detailed section offering definitions

  7. Design and Preliminary Performance Testing of Electronegative Gas Plasma Thruster

    Science.gov (United States)

    Liu, Thomas M.; Schloeder, Natalie R.; Walker, Mitchell L. R.; Polzin, Kurt A.; Dankanich, John W.; Aanesland, Ane

    2014-01-01

    In classical gridded electrostatic ion thrusters, positively charged ions are generated from a plasma discharge of noble gas propellant and accelerated to provide thrust. To maintain overall charge balance on the propulsion system, a separate electron source is required to neutralize the ion beam as it exits the thruster. However, if high-electronegativity propellant gases (e.g., sulfur hexafluoride) are instead used, a plasma discharge can result consisting of both positively and negatively charged ions. Extracting such electronegative plasma species for thrust generation (e.g., with time-varying, bipolar ion optics) would eliminate the need for a separate neutralizer cathode subsystem. In addition for thrusters utilizing a RF plasma discharge, further simplification of the ion thruster power system may be possible by also using the RF power supply to bias the ion optics. Recently, the PEGASES (Plasma propulsion with Electronegative gases) thruster prototype successfully demonstrated proof-of-concept operations in alternatively accelerating positively and negatively charged ions from a RF discharge of a mixture of argon and sulfur hexafluoride.i In collaboration with NASA Marshall Space Flight Center (MSFC), the Georgia Institute of Technology High-Power Electric Propulsion Laboratory (HPEPL) is applying the lessons learned from PEGASES design and testing to develop a new thruster prototype. This prototype will incorporate design improvements and undergo gridless operational testing and diagnostics checkout at HPEPL in April 2014. Performance mapping with ion optics will be conducted at NASA MSFC starting in May 2014. The proposed paper discusses the design and preliminary performance testing of this electronegative gas plasma thruster prototype.

  8. Foodproof Salmonella Detection Kit. Performance Tested Method 120301.

    Science.gov (United States)

    Lindhardt, Charlotte; Schönenbrücher, Holger; Slaghuis, Jörg; Bubert, Andreas; Ossmer, Rolf; Junge, Benjamin; Berghof-Jäger, Kornelia

    2009-01-01

    The foodproof Salmonella Detection Kit was previously validated in the Performance Tested Methods program for the detection of Salmonella species in a variety of foods, including milk powder, egg powder, coconut, cocoa powder, chicken breast, minced meat, sliced sausage, sausage, smoked fish, pasta, white pepper, cumin, dough, wet pet food, dry pet food, ice cream, watermelon, sliced cabbage, food dye, and milk chocolate. The method was shown to be equivalent to the U.S. Food and Drug Administration's Bacteriological Analytical Manual (FDA-BAM) and the U.S. Department of Agriculture, Food Safety and Inspection Service's Microbiology Laboratory Guidebook reference culture procedures. In the first Emergency Response Validation (ERV) extension study, peanut butter was inoculated with S. enterica. ser Typhimurium. For the low inoculation level (1.08 CFU/25 g), a Chi-square value of 2.25 indicated that there was no significant performance difference between the foodproof Salmonella Detection Kit and the FDA-BAM reference method. For high-level inoculation (11.5 CFU/25 g) and uninoculated control, there was 100% agreement between the methods. In the second ERV extension study, peanut butter was inoculated with S. enterica. ser Typhimurium. For both inoculation levels (0.1 and 0.5 CFU/25 g by most probable number), Chi-square values of 0 indicated that there was no significant performance difference between foodproof Salmonella Detection Kit and the FDA-BAM reference method. PMID:20166611

  9. Determination of inflow performance relationship (IRR) by well testing

    Energy Technology Data Exchange (ETDEWEB)

    Jahanbani, A. [Petroleum Univ. of Technology, Tehran (Iran, Islamic Republic of); Calgary Univ., AB (Canada); Shadizadeh, S.R. [Petroleum Univ. of Technology, Tehran (Iran, Islamic Republic of)

    2009-07-01

    The knowledge of inflow performance relationship (IPR) is an important piece of information for well performance evaluation and optimization. For single phase oil flow, production rate is proportional to pressure drawdown and therefore the IPR curve is a straight line. Although limited in their application, several empirical relations have been proposed in the literature to predict the performance of oil wells producing with two phase flow conditions. This paper presented a general approach for determination of IPR curves of oil wells below the bubble point pressure. This approach uses the results of well test analysis along with relative permeability and PVT data in the proper fluid flow equations for generation of IPR curves. The proposed method was also capable of predicting future IPR curves. The proposed approach was applied to an example oil well in a naturally fractured reservoir in order to demonstrate that it was applicable to a wide variety of cases. The paper also provided a comparison of the new method proposed for fractured reservoirs with some of the empirical methods. It was demonstrated that the new method could predict well deliverability more accurately than other methods. 17 refs., 5 tabs., 11 figs., 1 appendix.

  10. Jules Horowitz Reactor: a high performance material testing reactor

    Science.gov (United States)

    Iracane, Daniel; Chaix, Pascal; Alamo, Ana

    2008-04-01

    The physical modelling of materials' behaviour under severe conditions is an indispensable element for developing future fission and fusion systems: screening, design, optimisation, processing, licensing, and lifetime assessment of a new generation of structure materials and fuels, which will withstand high fast neutron flux at high in-service temperatures with the production of elements like helium and hydrogen. JANNUS and other analytical experimental tools are developed for this objective. However, a purely analytical approach is not sufficient: there is a need for flexible experiments integrating higher scales and coupled phenomena and offering high quality measurements; these experiments are performed in material testing reactors (MTR). Moreover, complementary representative experiments are usually performed in prototypes or dedicated facilities such as IFMIF for fusion. Only such a consistent set of tools operating on a wide range of scales, can provide an actual prediction capability. A program such as the development of silicon carbide composites (600-1200 °C) illustrates this multiscale strategy. Facing the long term needs of experimental irradiations and the ageing of present MTRs, it was thought necessary to implement a new generation high performance MTR in Europe for supporting existing and future nuclear reactors. The Jules Horowitz Reactor (JHR) project copes with this context. It is funded by an international consortium and will start operation in 2014. JHR will provide improved performances such as high neutron flux ( 10 n/cm/s above 0.1 MeV) in representative environments (coolant, pressure, temperature) with online monitoring of experimental parameters (including stress and strain control). Experimental devices designing, such as high dpa and small thermal gradients experiments, is now a key objective requiring a broad collaboration to put together present scientific state of art, end-users requirements and advanced instrumentation. To cite this article: D. Iracane et al., C. R. Physique 9 (2008).

  11. Karnofsky Performance Scale (KPS) or Physical Performance Test (PPT)? That is the question.

    Science.gov (United States)

    Terret, Catherine; Albrand, Gilles; Moncenix, Géraldine; Droz, Jean Pierre

    2011-02-01

    Oncologists usually base treatment decision on the assessment of patients' performance status (PS). This study was undertaken to explore the ability of KPS to correctly assess the PS of elderly cancer patients, comparing it to a validated geriatric tool named Physical Performance Test (PPT). One single examiner assessed elderly cancer patients' PS at registration in our institution and performed the PPT on patients with KPS ? 60. A sample of 152 patients actually underwent PPT. A low refusal rate was observed (<5%). Most patients (82%) had a high PS (KPS ? 80), whereas only 20% had no health impairment according to PPT scores. Patients' gender and disease stage did not correlate with PPT scores. The KPS seems to be a less accurate tool than the PPT to assess functional status of elderly cancer patients. Then PPT could be used as an inclusion criterion instead of KPS before cancer treatment decision. PMID:20185330

  12. Modified performance test of vented lead acid batteries for stationary applications

    International Nuclear Information System (INIS)

    The concept of a modified performance test for vented lead acid batteries in stationary applications has been developed by the IEEE Battery Working Group. The modified performance test is defined as a test in the ''as found'' condition of the battery capacity and its ability to provide a high rate, short duration load (usually the highest rate of the duty cycle) that will confirm the battery's ability to meet the critical period of the load duty cycle, in addition to determining its percentage of rated capacity. This paper will begin by reviewing performance and service test requirements and concerns associated with both types of tests. The paper will then discuss the rationale for developing a modified performance test along with the benefits that can be derived from performing a modified performance test in lieu of a capacity test and/or a service test. The paper will conclude with an example on how to apply a modified performance test and test acceptance criteria

  13. Performance test results of intruder automated monitoring system

    International Nuclear Information System (INIS)

    JAEA is developing practical use of an intruder automated monitoring system aimed at early detection of intruders or suspicious objects entering into a site boundary or protected areas, etc. The system is aimed at rationalization and efficiency of guard functions by using monitoring camera and image analysis software to watch the action of intruder or suspicious individual. This paper introduces the results of comparative investigations, including the performance and function of intrusion detection, expansion of the system, the test results of environmental resistance over a long period of time (ex. climate conditions, small animals, weeds, behavior of intruders, etc.). The effectiveness of the monitoring system as a physical protection measure, and the scope of application other than nuclear facility are evaluated using typical foreign image analysis software. (author)

  14. Memory complaints and test performance in healthy elderly persons

    Directory of Open Access Journals (Sweden)

    Mattos Paulo

    2003-01-01

    Full Text Available In order to compare the use of a structured self-report questionnaire with direct questioning about memory problems, 71 healthy and independent aged individuals (63 women from the community without risk factors for cognitive deficits were objectively asked about subjective memory complaints (SMC, given the Memory Complaint Questionnaire (MAC-Q and then submitted to the Rey Auditory Verbal Learning Test (RAVLT. SMC positively correlated with higher scores on MAC-Q, although a significant percentage of the sample had SMC and lower scores on MAC-Q and also no SMC and higher scores on MAC-Q. Performance on RAVLT was significantly worse (p<0.05 for the group presenting SMC but not for the group with higher scores on the MAC-Q. We conclude that direct questioning maybe more clinically significant than a self report questionnaire, at least for elderly persons from the community without risk factors for cognitive decline or depression.

  15. Operation and performance of the NESTOR test detector

    Science.gov (United States)

    Aggouras, G.; Anassontzis, E. G.; Ball, A. E.; Bourlis, G.; Chinowsky, W.; Fahrun, E.; Grammatikakis, G.; Green, C.; Grieder, P.; Katrivanos, P.; Koske, P.; Leisos, A.; Ludvig, J.; Markopoulos, E.; Minkowsky, P.; Nygren, D.; Papageorgiou, K.; Przybylski, G.; Resvanis, L. K.; Siotis, I.; Sopher, J.; Staveris, T.; Tsagli, V.; Tsirigotis, A.; Zhukov, V. A.; Nestor Collaboration

    2005-11-01

    NESTOR is a deep-sea neutrino telescope that is under construction in the Ionian Sea off the coast of Greece at a depth of about 4000 m. This paper briefly reviews the detector structure and deployment techniques before describing in detail the calibration and engineering run of a test detector carried out in 2003. The detector was operated for more than 1 month and data was continuously transmitted to shore via an electro-optical cable laid on the sea floor. The performance of the detector is discussed and analysis of the data obtained shows that the measured cosmic ray muon flux is in good agreement with previous measurements and with phenomenological cosmic ray models.

  16. Biodiesel production through hydrodynamic cavitation and performance testing

    Energy Technology Data Exchange (ETDEWEB)

    Pal, Amit; Verma, Ashish; Kachhwaha, S.S.; Maji, S. [Department of Mechanical Engineering, Delhi College of Engineering, Bawana Road, Delhi 110042 (India)

    2010-03-15

    This paper presents the details of development of a biodiesel production test rig based on hydrodynamic cavitation followed by results of experimental investigation carried out on a four cylinder, direct injection water cooled diesel engine operating on diesel and biodiesel blend of Citrullus colocyntis (Thumba) oil. The experiment covers a wide range of engine rpm. Results show that biodiesel of Thumba oil produced through hydrodynamic cavitation technique can be used as an alternative fuel with better performance and lower emissions compared to diesel. The most significant conclusions are that (1) Biodiesel production through hydrodynamic cavitation technique seems to be a simple, efficient, time saving, eco-friendly and industrially viable process. (2) 30% biodiesel blend of Thumba oil shows relatively higher brake power, brake thermal efficiency, reduced bsfc and smoke opacity with favourable p-{theta} diagram as compared to diesel. (author)

  17. Testing and Performance of UFFO Burst Alert & Trigger Telescope

    CERN Document Server

    Ripa, J; Lee, J; Park, I H; Kim, J E; Lim, H; Jeong, S; Castro-Tirado, A J; Connell, P H; Eyles, C; Reglero, V; Rodrigo, J M; Bogomolov, V; Panasyuk, M I; Petrov, V; Svertilov, S; Yashin, I; Brandt, S; Budtz-Jorgensen, C; Chang, Y -Y; Chen, P; Huang, M A; Liu, T -C; Nam, J W; Wang, M -Z; Chen, C R; Choi, H S; Kim, S -W; Min, K W

    2015-01-01

    The Ultra-Fast Flash Observatory pathfinder (UFFO-p) is a new space mission dedicated to detect Gamma-Ray Bursts (GRBs) and rapidly follow their afterglows in order to provide early optical/ultraviolet measurements. A GRB location is determined in a few seconds by the UFFO Burst Alert & Trigger telescope (UBAT) employing the coded mask imaging technique and the detector combination of Yttrium Oxyorthosilicate (YSO) scintillating crystals and multi-anode photomultiplier tubes. The results of the laboratory tests of UBAT's functionality and performance are described in this article. The detector setting, the pixel-to-pixel response to X-rays of different energies, the imaging capability for <50 keV X-rays, the localization accuracy measurements, and the combined test with the Block for X-ray and Gamma-Radiation Detection (BDRG) scintillator detector to check the efficiency of UBAT are all described. The UBAT instrument has been assembled and integrated with other equipment on UFFO-p and should be launche...

  18. Materials Testing and Performance Optimization for the SAMURAI-TPC

    Science.gov (United States)

    Long, K. D.; Lynch, W. G.; Barney, J.; Chajecki, Z.; Estee, J.; Shane, R.; Tangwanchareon, S.; Tsang, M. B.; Yurkon, J.

    2012-10-01

    The SAMURAI time-projection chamber (TPC) will be used to make measurements of pion spectra from heavy ion collisions at RIBF in Japan. Such research provides an opportunity to study supra-saturation density neutron-rich matter in the laboratory, and is critical to understanding the structure of neutron stars. It will provide a complete, 3D picture of the ionization deposited in a gas volume, from which particle types and momenta can be determined. The gas-containment volume is composed of surfaces of aluminum and plastic, as well as halogen-free printed circuit board. During multiplication of the ionized electrons at the anode wire plane of the TPC, UV photons are produced. These cause unwanted discharges when they interact with oxidized aluminum surfaces, which have low work functions. This problem can be addressed by application of a suitable conductive paint or epoxy. Paints were investigated to insure they did not contain any materials capable of inhibiting the performance of the detector gas. These investigations were cross-checked by tests carried out using an existing BRAHMS-TPC. Details on these tests and the materials chosen will be shown. The design and optimization of the gating grid, used to limit data collection to triggered events, will also be discussed.

  19. CMM touch trigger performance verification using a probe test apparatus

    Directory of Open Access Journals (Sweden)

    Miguel P. A. Cauchick

    2003-01-01

    Full Text Available A probe test device has been developed to assess CMM touch trigger probe errors. A precise single axis translational table triggers the probe through the use of gauge blocks fixed to the table carriage. The position of the carriage is monitored by a laser interferometer. The gauge block surface is brought into contact with the probe ball tip until the probe is triggered at which point the coordinate position is displayed by the laser. The probe is rotated 360° using the motorized probe head in 7.5° intervals and the coordinate of each position is computed. Repeatability errors (i.e. the ability of the probe to trigger at the same point each time with a 95% confidence level and pre-travel variation (i.e. the distance traveled by a probe between the actual touching of a surface and the trigger event are then calculated. This paper reports the measurement strategy and the design of the prototype rig. Results are also provided to demonstrate the test apparatus performance.

  20. CMM touch trigger performance verification using a probe test apparatus

    Scientific Electronic Library Online (English)

    P. A. Cauchick, Miguel; T., King; A. J., Abackerli.

    2003-04-01

    Full Text Available A probe test device has been developed to assess CMM touch trigger probe errors. A precise single axis translational table triggers the probe through the use of gauge blocks fixed to the table carriage. The position of the carriage is monitored by a laser interferometer. The gauge block surface is b [...] rought into contact with the probe ball tip until the probe is triggered at which point the coordinate position is displayed by the laser. The probe is rotated 360° using the motorized probe head in 7.5° intervals and the coordinate of each position is computed. Repeatability errors (i.e. the ability of the probe to trigger at the same point each time with a 95% confidence level) and pre-travel variation (i.e. the distance traveled by a probe between the actual touching of a surface and the trigger event) are then calculated. This paper reports the measurement strategy and the design of the prototype rig. Results are also provided to demonstrate the test apparatus performance.

  1. Performance Test of a Magnetic Change Detection Sensorin a Test Field

    International Nuclear Information System (INIS)

    The fast development of technologies regarding detection sensors and access control systems allows the equipment designed by using those technologies to account for a greater part in facilities, physical protection system than ever before. The popular area for the equipment is an exterior intrusion detection system. The selection of intrusion detection equipment involves identifying the equipment and methods of installation that best meet the overall system objectives. The system objectives, including the purpose of the intrusion detection equipment and the types of assumed threats, should indicate the desired requirements of the exterior intrusion detection system in three primary areas: · Probability of detection of the intruder · Nuisance alarm rate and causes of the nuisance alarms · Vulnerability of the equipment to defeat These three areas are intimately interrelated with the characteristics of the particular equipment, the methods of installation and adjustment, the manner in which the equipment is interconnected, and the environment to which the equipment is exposed. While there are twenty nuclear power plants operating with various types of detection equipment deployed in Korea as of now, few studies have been conducted as to actual performance of deployed equipment and guidelines in both installing and operating those equipment. In order to tackle this lack of studies, KINAC established the test field and conducted some field tests on several sensors. Thiome field tests on several sensors. This paper aims at describing the procedures and results of the tests on a magnetic change detection sensor (herein called the 'MCDS') and sharing experiences earned through the actual test

  2. Breathing simulator of workers for respirator performance test.

    Science.gov (United States)

    Yuasa, Hisashi; Kumita, Mikio; Honda, Takeshi; Kimura, Kazushi; Nozaki, Kosuke; Emi, Hitoshi; Otani, Yoshio

    2015-04-01

    Breathing machines are widely used to evaluate respirator performance but they are capable of generating only limited air flow patterns, such as, sine, triangular and square waves. In order to evaluate the respirator performance in practical use, it is desirable to test the respirator using the actual breathing patterns of wearers. However, it has been a difficult task for a breathing machine to generate such complicated flow patterns, since the human respiratory volume changes depending on the human activities and workload. In this study, we have developed an electromechanical breathing simulator and a respiration sampling device to record and reproduce worker's respiration. It is capable of generating various flow patterns by inputting breathing pattern signals recorded by a computer, as well as the fixed air flow patterns. The device is equipped with a self-control program to compensate the difference in inhalation and exhalation volume and the measurement errors on the breathing flow rate. The system was successfully applied to record the breathing patterns of workers engaging in welding and reproduced the breathing patterns. PMID:25382381

  3. An Enhancement of Visual Test Performance for Nuclear Fuel Assembly

    International Nuclear Information System (INIS)

    In the overhaul period of the nuclear power plant, integrity of the neutron-irradiated fuel assembly is evaluated. Nuclear regulations require that nuclear power plants meet the design, operation, and inspection requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B and PV). Section XI of the ASME B and PV Code provides the specific requirements for inspecting the systems, structures, and components; Section V of the ASME Code provides requirements for inspection methods, including volumetric (e.g., ultrasonic testing), surface (e.g., eddy current testing), and visual testing (VT). Visual testing of neutron irradiated fuel assembly is conducted generally for a variety of purposes, for example to detect discontinuities and imperfections on the surface of fuel rods, to detect evidence of leakage from end-cap welds, and to determine the general mechanical and structural condition of one. VT is performed remotely using video camera. As the neutron-irradiated fuel assembly is a high dose-rate gamma-ray source, approximately a few kGy, radiation hardened underwater camera is used in the VT of the fuel assembly. Utilities today follow the EPRI guidelines for VT-1 tests on nuclear components (BWR Vessel and Internals Project-3 1995). The VT-1 guidelines specify which areas around a weld should be examined, how to measure the sizes of indications found, and how to test the resolving power of the visual equipment used for the test of the visual equipment used for the test. The EPRI guidelines use two 12?m (0.0005-in.) wires or notches as a resolution calibration standard. According to the EPRI guidelines (BWRVIP-03 1995), the camera systems employed were marginally able to detect the 0.0005-inch (12-?m) diameter wire on a steel background. In the some future, it is required that the VT of nuclear fuel assembly follows the EPRI VT-1 guideline. In order to meet the VT-1 guideline, any system used in VT (ranging from the naked eye to a digital closed-circuit TV system) will have a measurable visual acuity. The visual acuity parameter describes what a system can detect and discern. Current underwater radiation-hardened video camera, which is composed of tube- type vidicon image sensor, used in the VT of fuel assembly has not sufficient resolution regardless of high cost. As the resolution of the COTS SOTA (state-of-theart) CCD image sensor is higher than the tube-type image sensor, the VT of the fuel assembly clearly meets the EPRI VT-1 guideline, if assumed that the radiation-weakened SOTA CCD camera is properly shielded from the high dose rate gamma-ray source. In this paper, it is described that a radiation-tolerant camera system, which are composed of COTS SOTA CCD camera, zoom lens, anti-reflection mirror, and visible window, meets the EPRI VT-1 guideline for the VT of the nuclear fuel assembly. Generally, the VT of the four face of nuclear fuel assembly, which is a high dose-rate gamma source, is performed in the underwater canal. The width of canal, d1, is about 1,500mm. As the distance, d2, between the fuel assembly (d3, 224mm) and the camera system, assumed that the width of camera system is about 200mm, is short below one-tenth shielding thickness of gamma-ray of water, about 660mm, a COTS SOTA CCD camera cannot be used directly. As shown in Fig. 1 and Table 1, the observation distance between the fuel assembly and the CCD camera, is 438?588mm. These observation distances are shorter than the MOD (minimum object distance) of the SOTA CCD cameras (Sony FCB-PV480 and FCB-H10). The MOD of these SOTA color CCD camera are 800mm and 1,000mm. In this paper, in order to enhance the optimum observation performance, the close-up lens (No. 2) was used. An observation distance of 400mm from the test samples was acquired

  4. System design description for the whole element furnace testing system

    International Nuclear Information System (INIS)

    This document provides a detailed description of the Hanford Spent Nuclear Fuel (SNF) Whole Element Furnace Testing System located in the Postirradiation Testing Laboratory G-Cell (327 Building). Equipment specifications, system schematics, general operating modes, maintenance and calibration requirements, and other supporting information are provided in this document. This system was developed for performing cold vacuum drying and hot vacuum drying testing of whole N-Reactor fuel elements, which were sampled from the 105-K East and K West Basins. The proposed drying processes are intended to allow dry storage of the SNF for long periods of time. The furnace testing system is used to evaluate these processes by simulating drying sequences with a single fuel element and measuring key system parameters such as internal pressures, temperatures, moisture levels, and off-gas composition

  5. NEXT Long-Duration Test Neutralizer Performance and Erosion Characteristics

    Science.gov (United States)

    Herman, Daniel A.; Soulas, George C.; Patterson, Michael J.

    2009-01-01

    The NASA's Evolutionary Xenon Thruster (NEXT) program is developing the next-generation ion propulsion system with significant enhancements beyond the state-of-the-art to provide future NASA science missions with enhanced capabilities at a low total development cost. A Long-Duration Test (LDT) was initiated in June 2005, to verify the NEXT propellant throughput capability to a qualification-level of 450 kg, 1.5 times the anticipated throughput requirement of 300 kg per thruster based on mission analyses. As of September 2, 2009, the thruster has accumulated 24,400 hr of operation with extensive durations at the following input powers: 6.9, 4.7, 1.1, and 0.5 kW. The thruster has processed 434 kg of xenon, surpassing the NASA Solar Technology Application Readiness (NSTAR) program thruster propellant throughput demonstrated during the extended life testing of the Deep Space 1 flight spare ion thruster and approaching the NEXT development qualification throughput goal of 450 kg. The NEXT LDT has demonstrated a total impulse of 16.1 10(exp 6zzz0 N s; the highest total impulse ever demonstrated by an ion thruster. A reduction in neutralizer flow margin has been the only appreciable source of thruster performance degradation. The behavior of the neutralizer is not easily predicted due to both erosion and deposition observed in previous wear tests. Spot-to-plume mode transition flow data and in-situ erosion results for the LDT neutralizer are discussed. This loss of flow margin has been addressed through a combination of a design change in the prototype-model neutralizer to increase flow margin at low emission current and to update the NEXT throttle table to ensure adequate flow margin as a function of propellant throughput processed. The new throttle table will be used for future LDT operations. The performance of the NEXT LDT neutralizer is consistent with that observed for long-life hollow cathodes. The neutralizer life-limiting failure modes are progressing as expected and the neutralizer data indicate none of the neutralizer failures are imminent.

  6. An Enhancement of Visual Test Performance for Nuclear Fuel Assembly

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Jai Wan; Choi, Young Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Shin, Jung Cheol [Korea Nuclear Fuel, Daejeon (Korea, Republic of)

    2009-05-15

    In the overhaul period of the nuclear power plant, integrity of the neutron-irradiated fuel assembly is evaluated. Nuclear regulations require that nuclear power plants meet the design, operation, and inspection requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B and PV). Section XI of the ASME B and PV Code provides the specific requirements for inspecting the systems, structures, and components; Section V of the ASME Code provides requirements for inspection methods, including volumetric (e.g., ultrasonic testing), surface (e.g., eddy current testing), and visual testing (VT). Visual testing of neutron irradiated fuel assembly is conducted generally for a variety of purposes, for example to detect discontinuities and imperfections on the surface of fuel rods, to detect evidence of leakage from end-cap welds, and to determine the general mechanical and structural condition of one. VT is performed remotely using video camera. As the neutron-irradiated fuel assembly is a high dose-rate gamma-ray source, approximately a few kGy, radiation hardened underwater camera is used in the VT of the fuel assembly. Utilities today follow the EPRI guidelines for VT-1 tests on nuclear components (BWR Vessel and Internals Project-3 1995). The VT-1 guidelines specify which areas around a weld should be examined, how to measure the sizes of indications found, and how to test the resolving power of the visual equipment used for the test. The EPRI guidelines use two 12{mu}m (0.0005-in.) wires or notches as a resolution calibration standard. According to the EPRI guidelines (BWRVIP-03 1995), the camera systems employed were marginally able to detect the 0.0005-inch (12-{mu}m) diameter wire on a steel background. In the some future, it is required that the VT of nuclear fuel assembly follows the EPRI VT-1 guideline. In order to meet the VT-1 guideline, any system used in VT (ranging from the naked eye to a digital closed-circuit TV system) will have a measurable visual acuity. The visual acuity parameter describes what a system can detect and discern. Current underwater radiation-hardened video camera, which is composed of tube- type vidicon image sensor, used in the VT of fuel assembly has not sufficient resolution regardless of high cost. As the resolution of the COTS SOTA (state-of-theart) CCD image sensor is higher than the tube-type image sensor, the VT of the fuel assembly clearly meets the EPRI VT-1 guideline, if assumed that the radiation-weakened SOTA CCD camera is properly shielded from the high dose rate gamma-ray source. In this paper, it is described that a radiation-tolerant camera system, which are composed of COTS SOTA CCD camera, zoom lens, anti-reflection mirror, and visible window, meets the EPRI VT-1 guideline for the VT of the nuclear fuel assembly. Generally, the VT of the four face of nuclear fuel assembly, which is a high dose-rate gamma source, is performed in the underwater canal. The width of canal, d{sub 1}, is about 1,500mm. As the distance, d{sub 2}, between the fuel assembly (d{sub 3}, 224mm) and the camera system, assumed that the width of camera system is about 200mm, is short below one-tenth shielding thickness of gamma-ray of water, about 660mm, a COTS SOTA CCD camera cannot be used directly. As shown in Fig. 1 and Table 1, the observation distance between the fuel assembly and the CCD camera, is 438{approx}588mm. These observation distances are shorter than the MOD (minimum object distance) of the SOTA CCD cameras (Sony FCB-PV480 and FCB-H10). The MOD of these SOTA color CCD camera are 800mm and 1,000mm. In this paper, in order to enhance the optimum observation performance, the close-up lens (No. 2) was used. An observation distance of 400mm from the test samples was acquired.

  7. Recycle Waste Collection Tank (RWCT) simulant testing in the PVTD feed preparation system

    International Nuclear Information System (INIS)

    (This is part of the radwaste vitrification program at Hanford.) RWCT was to routinely receive final canister decontamination sand blast frit and rinse water, Decontamination Waste Treatment Tank bottoms, and melter off-gas Submerged Bed Scrubber filter cake. In order to address the design needs of the RWCT system to meet performance levels, the PNL Vitrification Technology (PVTD) program used the Feed Preparation Test System (FPTS) to evaluate its equipment and performance for a simulant of RWCT slurry. (FPTS is an adaptation of the Defense Waste Processing Facility feed preparation system and represents the initially proposed Hanford Waste Vitrification Plant feed preparation system designed by Fluor-Daniel, Inc.) The following were determined: mixing performance, pump priming, pump performance, simulant flow characterization, evaporator and condenser performance, and ammonia dispersion. The RWCT test had two runs, one with and one without tank baffles

  8. Demonstration of the iodine and NO/sub x/ removal systems in the Oak Ridge National Laboratory integrated equipment test facility

    International Nuclear Information System (INIS)

    This report summarizes the findings from three sets of experiments on iodine and NO/sub x/ removal performance using dual downdraft condensers in the dissolver off-gas line. The initial experiments were conducted in the laboratory using glassware in proof-of-principle tests. Two additional sets of condenser experiments were conducted using equipment prototyical for a 0.5-t/d plant in the Integrated Equipment Test (IET) facility at the Oak Ridge National Laboratory. This report also describes the NO/sub x/ removal performance of a packed scrubber in the IET during the dissolution of depleted uranium oxides. The overall iodine pass-through efficiency of the condensers in the IET was high as desired. Removal efficiencies ranged from only 0.35 to 6.29%, indicating that the bulk of the iodine in the off-gas will be transferred on through the condensers to the iodox process for final disposal rather than recycled to the dissolver. The optimum operating temperature for the first condenser was in the range of 50 to 700C, with the temperature of the second condenser held near 200C. The NO/sub x/ removal performance of the combined dual condensers and packed scrubber resulted in effluent off-gas stream NO/sub x/ compositions of ?0.4 to 1.0%, which are acceptable levels for the iodox process. The NO/sub x/ removal efficiency of the condensers ranged from ?5 to 58%, but was generally around 20%. The removal efficiency of the packed tower scrubber was observed to be in the range of 40 to 60%. The NO/sub x/ removal performance of the condensers tended to complement the performance of the scrubber in that the condenser removal afficiency was high when the scrubber efficiency was low and vice versa

  9. Cross-cultural effects on IQ test performance: a review and preliminary normative indications on WAIS-III test performance.

    Science.gov (United States)

    Shuttleworth-Edwards, Ann B; Kemp, Ryan D; Rust, Annegret L; Muirhead, Joanne G L; Hartman, Nigel P; Radloff, Sarah E

    2004-10-01

    This article presents a review of cross-cultural influences on Wechsler IQ tests, together with a preliminary investigation into WAIS-III test performance (English administration) for a southern African sample (age range 19-30) stratified for white English first language and black African first language, level and quality of education. ('African language' is the term used to denote the indigenous languages of black populations in southern Africa). A two-way ANOVA revealed highly significant effects for both level and quality of education within the black African first language group. Scores for the white English and black African first language groups with advantaged education were comparable with the US standardization, whereas scores for black African first language participants with disadvantaged education were significantly lower than this. Thus indications from this research are that normative studies should take account of the influential variable of quality of education, in addition to level of education. Alternatively faulty conclusions may be drawn about the effects of ethnicity, with the potential for neuropsychological misdiagnosis. PMID:15742541

  10. Comparison of a fuel-driven and steam-driven ejector in solid oxide fuel cell systems with anode off-gas recirculation: Part-load behavior

    Science.gov (United States)

    Engelbracht, Maximilian; Peters, Roland; Blum, Ludger; Stolten, Detlef

    2015-03-01

    This paper investigates the use of ejectors for recirculating anode off-gas in an SOFC system, focusing on the part-load capability of two different systems. In the first system, recirculation was enabled by a fuel-driven ejector. The part-load threshold of this system was determined by carbon formation and was 77.8% assuming a fuel utilization of 70% and suitable ejector geometry. The second system was based on a steam-driven ejector. The simulation results for this system showed an improved part-load capability of 37.8% as well as a slightly improved electrical efficiency. Here, the minimal part load was determined by the condensation temperature of the condenser used in the system.

  11. 30 CFR 27.32 - Tests to determine performance of the system.

    Science.gov (United States)

    2010-07-01

    ...determine performance of the system. 27.32 Section 27...ADMINISTRATION, DEPARTMENT OF LABOR TESTING, EVALUATION, AND APPROVAL...PRODUCTS METHANE-MONITORING SYSTEMS Test Requirements § 27...determine performance of the system. (a) Laboratory...

  12. 42 CFR 493.20 - Laboratories performing tests of moderate complexity.

    Science.gov (United States)

    2010-10-01

    ...2010-10-01 2010-10-01 false Laboratories performing tests of moderate complexity...CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS General Provisions § 493.20 Laboratories performing tests of moderate...

  13. 42 CFR 493.25 - Laboratories performing tests of high complexity.

    Science.gov (United States)

    2010-10-01

    ...2010-10-01 2010-10-01 false Laboratories performing tests of high complexity...CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS General Provisions § 493.25 Laboratories performing tests of high...

  14. Fuel Retrieval Sub-Project (FRS) Decapping Station Performance Test Data Report

    International Nuclear Information System (INIS)

    This document is to provide the test data report for Decapping Station Performance Testing. These performance tests were full scale and viewed as a continuation of development testing performed earlier (SNF-2710). A prototype decapping station confinement box was tested, along with some special tools required for the process, providing assurance that the fuel handling equipment will operate as designed, allowing for release of the FRS equipment for installation

  15. Fuel Retrieval Sub (FRS) Project Decapping Station Performance Test Data Report

    Energy Technology Data Exchange (ETDEWEB)

    THIELGES, J.R.

    2000-01-13

    This document is to provide the test data report for Decapping Station Performance Testing. These performance tests were full scale and viewed as a continuation of development testing performed earlier (SNF-2710). A prototype decapping station confinement box was tested, along with some special tools required for the process, providing assurance that the fuel handling equipment will operate as designed, allowing for release of the FRS equipment for installation.

  16. System integration and performance of the EUV engineering test stand

    Energy Technology Data Exchange (ETDEWEB)

    Tichenor, Daniel A.; Ray-Chaudhuri, Avijit K.; Replogle, William C.; Stulen, Richard H.; Kubiak, Glenn D.; Rockett, Paul D.; Klebanoff, Leonard E.; Jefferson, Karen L.; Leung, Alvin H.; Wronosky, John B.; Hale, Layton C.; Chapman, Henry N.; Taylor, John S.; Folta, James A.; Montcalm, Claude; Soufli, Regina; Spiller, Eberhard; Blaedel, Kenneth; Sommargren, Gary E.; Sweeney, Donald W.; Naulleau, Patrick; Goldberg, Kenneth A.; Gullikson, Eric M.; Bokor, Jeffrey; Batson, Phillip J.; Attwood, David T.; Jackson, Keith H.; Hector, Scott D.; Gwyn, Charles W.; Yan, Pei-Yang; Yan, P.

    2001-03-01

    The Engineering Test Stand (ETS) is a developmental lithography tool designed to demonstrate full-field EUV imaging and provide data for commercial-tool development. In the first phase of integration, currently in progress, the ETS is configured using a developmental projection system, while fabrication of an improved projection system proceeds in parallel. The optics in the second projection system have been fabricated to tighter specifications for improved resolution and reduced flare. The projection system is a 4-mirror, 4x-reduction, ring-field design having a numeral aperture of 0.1, which supports 70 nm resolution at a k{sub 1} of 0.52. The illuminator produces 13.4 nm radiation from a laser-produced plasma, directs the radiation onto an arc-shaped field of view, and provides an effective fill factor at the pupil plane of 0.7. The ETS is designed for full-field images in step-and-scan mode using vacuum-compatible, magnetically levitated, scanning stages. This paper describes system performance observed during the first phase of integration, including static resist images of 100 nm isolated and dense features.

  17. Performance Tests of a Plate Type Condenser for OTEC

    Science.gov (United States)

    Nakaoka, Tsutomu; Uehara, Haruo

    The performance tests of a plate type condenser for ocean thermal energy conversion (OTEC) plants are carried out under conditions of OTEC. The total plates used in the condenser are 168 in number and the total surface area is 40.7 m2. The dimensions of plate used in this condenser are 1450 mm in length, 235 mm in width and 1.0 mm in thickness. Freon 22 is used as working fluid. The overall heat transfer coefficient is about 2500W/(m2K) at the cold water velocity of 1 m/s and the vapor inlet temperature of 22.8~23.2°C. The empirical correlations are proporsed for predicting the average condensation heat transfer coefficients and water side heat transfer coefficients for a plate type condenser. The water side pressure drop is 1 m at the cold water velocity of 1 m/s. The water side friction factor is about 0.25 at Reynolds number of 4×103.

  18. Design and performance of the South Pole Acoustic Test Setup

    CERN Document Server

    Abdou, Yasser; Berdermann, Jens; Bissok, Martin; Bohm, Christian; Boeser, Sebastian; Bothe, Martin; Carson, Michael; Descamps, Freija; Fischer-Wolfarth, Jan-Hendrik; Gustafsson, Leif; Hallgren, Allan; Heinen, Dirk; Helbing, Klaus; Heller, Reinhart; Hundertmark, Stephan; Karg, Timo; Krieger, Kevin; Laihem, Karim; Meures, Thomas; Nahnhauer, Rolf; Naumann, Uwe; Oberson, Filip; Paul, Larissa; Pohl, Mario; Price, Buford; Ribordy, Mathieu; Ryckbosch, Dirk; Schunck, Matthias; Semburg, Benjamin; Stegmaier, Jutta; Sulanke, Karl-Heinz; Tosi, Delia; Vandenbroucke, Justin; Wiebusch, Christopher

    2011-01-01

    The South Pole Acoustic Test Setup (SPATS) was built to evaluate the acoustic characteristics of the South Pole ice in the 10 kHz to 100 kHz frequency range, for the purpose of assessing the feasibility of an acoustic neutrino detection array at the South Pole. The SPATS hardware consists of four vertical strings deployed in the upper 500 m of the South Pole ice cap. The strings form a trapezoidal array with a maximum baseline of 543 m. Each string has 7 stages equipped with one transmitter and one sensor module. Sound is detected or generated by piezoelectric ceramic elements inside the modules. Analogue signals are sent to the surface on electric cables where they are digitized by a PC-based data acquisition system. The data from all strings are collected on a central computer in the IceCube Laboratory from where they are send to a central data storage facility via a satellite link or stored locally on tape. A technical overview of SPATS and its performance is presented.

  19. Design and performance of the South Pole Acoustic Test Setup

    International Nuclear Information System (INIS)

    The South Pole Acoustic Test Setup (SPATS) was built to evaluate the acoustic characteristics of the South Pole ice in the 10–100 kHz frequency range, for the purpose of assessing the feasibility of an acoustic neutrino detection array at the South Pole. The SPATS hardware consists of four vertical strings deployed in the upper 500 m of the South Pole ice cap. The strings form a trapezoidal array with a maximum baseline of 543 m. Each string has seven stages equipped with one transmitter and one sensor module (glaciophone). Sound is detected or generated by piezoelectric ceramic elements inside the modules. Analogue signals are sent to the surface on electric cables where they are digitized by a PC-based data acquisition system. The data from all strings are collected on a central computer in the IceCube Laboratory from where they are sent to a central data storage facility via a satellite link or stored locally on tape. A technical overview of SPATS and its performance is presented.

  20. System integration and performance of the EUV engineering test stand

    International Nuclear Information System (INIS)

    The Engineering Test Stand (ETS) is a developmental lithography tool designed to demonstrate full-field EUV imaging and provide data for commercial-tool development. In the first phase of integration, currently in progress, the ETS is configured using a developmental projection system, while fabrication of an improved projection system proceeds in parallel. The optics in the second projection system have been fabricated to tighter specifications for improved resolution and reduced flare. The projection system is a 4-mirror, 4x-reduction, ring-field design having a numeral aperture of 0.1, which supports 70 nm resolution at a k1 of 0.52. The illuminator produces 13.4 nm radiation from a laser-produced plasma, directs the radiation onto an arc-shaped field of view, and provides an effective fill factor at the pupil plane of 0.7. The ETS is designed for full-field images in step-and-scan mode using vacuum-compatible, magnetically levitated, scanning stages. This paper describes system performance observed during the first phase of integration, including static resist images of 100 nm isolated and dense features

  1. Enhancement of Tokamak Fusion Test Reactor performance by lithium conditioning

    International Nuclear Information System (INIS)

    Wall conditioning in the Tokamak Fusion Test Reactor (TFTR) [K. M. McGuire et al., Phys. Plasmas 2, 2176 (1995)] by injection of lithium pellets into the plasma has resulted in large improvements in deuterium endash tritium fusion power production (up to 10.7 MW), the Lawson triple product (up to 1021 m-3 s keV), and energy confinement time (up to 330 ms). The maximum plasma current for access to high-performance supershots has been increased from 1.9 to 2.7 MA, leading to stable operation at plasma stored energy values greater than 5 MJ. The amount of lithium on the limiter and the effectiveness of its action are maximized through (1) distributing the Li over the limiter surface by injection of four Li pellets into Ohmic plasmas of increasing major and minor radius, and (2) injection of four Li pellets into the Ohmic phase of supershot discharges before neutral-beam heating is begun. copyright 1996 American Institute of Physics

  2. The bilingual effect on Boston Naming Test performance

    DEFF Research Database (Denmark)

    Gollan, Tamar H; Fennema-Notestine, Christine

    2007-01-01

    The present study aimed to determine how older bilingual subjects' naming performance is affected by their knowledge of two languages. Twenty-nine aging (mean age = 74.0; SD = 7.1) Spanish-English bilinguals were asked to name all pictures in the Boston Naming Test (BNT) first in their dominant language and then in their less-dominant language. Bilinguals with similar naming scores in each language, or relatively balanced bilinguals, named more pictures correctly when credited for producing a correct name in either language. Balanced bilinguals also named fewer pictures in their dominant language than unbalanced bilinguals, and named more pictures correctly in both languages if the pictures had cognate names (e.g., dart is dardo in Spanish). Unbalanced bilinguals did not benefit from the alternative (either-language) scoring procedure and showed cognate effects only in their nondominant language. These findings may help to guide the interpretation of neuropsychological data for the purpose of determining cognitive status in older bilinguals and can be used to develop models of bilingual language processing. Bilinguals' ability to name pictures reflects their experience with word forms in both languages.

  3. Demonstration of a steam jet scrubber off-gas system and the burner efficiency of a mixed incinerator facility

    International Nuclear Information System (INIS)

    A full-scale incinerator system, the Consolidated Incineration Facility (CIF), is being designed to process solid and liquid low-level radioactive, mixed, and RCRA hazardous waste. This facility will consist of a rotary kiln, secondary combustion chamber (SCC), and a wet of-gas system. A prototype steam jet scrubber wastewater will be immobilized in a cement matrix after assumptions for the CIF. The scrubber wastewater will be immobilized in a cement matrix after the blowdown has been concentrated to a maximum solids concentration in a cross-flow filtration system. A sintered metal inertial filter system has been successfully tested. Burner efficiency was tested in a high intensity vortex burner, which destroyed the hazardous waste streams tested. These tests are detailed by the authors

  4. 40 CFR 63.1512 - Performance test/compliance demonstration requirements and procedures.

    Science.gov (United States)

    2010-07-01

    ...must conduct a performance test to measure THC and D/F emissions at the outlet of the...performance tests to measure emissions of THC, D/F, HCl, and PM at the outlet of...afterburner every 15 minutes during the THC and D/F performance tests; (ii)...

  5. A proposed performance test of X-ray radiographic equipment for quality assurance in diagnostic radiology

    International Nuclear Information System (INIS)

    The DGMP working group has established a test program by which it is possible to perform uniformly the performance test of radiographic devices referred to in DIN 6868, part 1. The program was based on the following fundamental purposes: 1) Uniformity of the testing extent, measuring conditions and test criteria, 2) Simple procedure of testing and 3) Definition of a reference dose value ('transmission dose') useable to assess the exposure of the patient required by the technique. Substantial requirements with regard to the necessary test object and the measuring arrangement are deduced from these criteria. A model test program, comprising the most essential single tests of a performance test, is presented. A model test certificate is introduced. The practical trial of the test methods has revealed the possibility to apply an informative performance test in a fast and simple way by using suitable measuring devices. (orig.)

  6. Candidate Fatigue and Performance on G.C.E. Objective Tests

    Science.gov (United States)

    Massey, A. J.

    1977-01-01

    It has long been recognized that students' performance on test questions may be affected by structural aspects of the test itself. Here, the extent to which items, placed at the end of General Certificate of Education tests, influence test taking is examined, and the effect on performance of items placed early or late is considered. (Author/RK)

  7. A study of relationships between performance in system tests and space

    Science.gov (United States)

    Timmins, A. R.

    1974-01-01

    Approaches for measuring the effectiveness of tests and test programs are considered, taking into account system test effectiveness, thermal-vacuum test effectiveness, and vibration test effectiveness. Methods for predicting space performance on the basis of system test effectiveness are discussed along with aspects of defect detection in thermal-vacuum tests. Questions regarding the thermal-vacuum test costs in relation to the probability of early space failures are also explored.

  8. A Cooperative Performance Test for Japanese University Conversation Classes.

    Science.gov (United States)

    Joritz-Nakagawa, Jane

    This document discusses a test devised for a university level English-as-a-foreign-language (EFL) course that tests students' conversational ability. The test has been used successfully in a Japanese university English communication class over three years. Learning not only to speak but to listen and respond appropriately to others is also an…

  9. A method for improving test rig performance using passive components

    Science.gov (United States)

    Johansson, Anders T.; Abrahamsson, Thomas J. S.

    2015-02-01

    The time waveform replication (TWR) algorithm is presently used in industry for calculating the actuation force needed to replicate a certain reference sensor output in a test rig. Power and force rate limitations restrict the feasible range of that actuation force. If the input force distribution of the reference test cannot be replicated in the test rig, the required test rig input force magnitudes may be large or the replication properties poor due to lack of controllability. To circumvent this, a theory of passive components to improve replication and limit the input force demands of dynamic test rigs is developed. The theory fits within the framework of the TWR algorithm.

  10. The Yo-Yo tests and twelve-minute run test performance in young Japanese cross-country skiers

    Directory of Open Access Journals (Sweden)

    Denda Yuki

    2013-04-01

    Full Text Available Purpose: The aim of the present study is to examine the performance of young Japanese cross-country skiers of different competitive levels with the use of Yo-Yo tests and the 12-minute run test (12MRT that have been demonstrated to be related to each level, and to know which test is suitable for different competitive performance. Methods: Elite group (N = 9 was 16.9 ± 0.3 years and moderate trained group (N = 22 was 16.1 ± 0.9 years. The testing sessions consisted of the following: 1 Vertical jump and 50m sprint; 2 the Yo-Yo tests level 1 and 2 (intermittent recovery; 3 12MRT. Results: Results showed the vertical jump heights and 50m sprint that no significant both performances differences were found among the two groups. Significant the Yo-Yo tests and 12MRT performances differences were found between the two groups (p

  11. The Relationship Between the Yo-Yo Tests, Anaerobic Performance and Aerobic Performance in Young Soccer Players

    OpenAIRE

    Karakoç, Bar??; AKALAN, Cengiz; Alemdaro?lu, Utku; Arslan, Er?an

    2012-01-01

    The purposes of this study were to determine the relationship between performance in the Yo-Yo intermittent recovery test level 1 (YIRT1), the Yo-Yo intermittent recovery test level 2 (YIRT2) and the Yo-Yo endurance test (continuous) (YET) with maximal oxygen uptake (VO2max) and Wingate anaerobic performance (WaNT) test results in young soccer players (age 15.00 ± 0.0 years, body height 176.3 ± 4.2 cm and body mass 68.1 ± 3.6 kg). An ergospirometry device was used during the treadmill test...

  12. 40 CFR 60.543 - Performance test and compliance provisions.

    Science.gov (United States)

    2010-07-01

    ...cementing operation, green tire spraying operation...meeting the equipment design and performance...Meeting the capture system design and performance specifications...operation, the cement application and drying area shall...this section; for each green tire spraying...

  13. Performance Tests of a Permeation Sensor for Test Blanket Modules Using Liquid Metal

    International Nuclear Information System (INIS)

    The tritium extraction from a breeder is one of the key technologies and its methods have been investigated. For developing the tritium extraction methods and evaluating the amount of tritium in the system, a reliable and correct sensor is required to measure the hydrogen concentration in liquid metal breeder. There are several researches for developing the sensors in the ITER participants and especially, EU has developed the permeation sensors trying to selecting materials with low Serviette's constant (solubility) and high hydrogen diffusivity coefficient. However, EU's response time is still too long time about tens of minutes to measure the tritium concentration in the online system. We have been performing the preliminary tests with designed and fabricated sensors to solve the late response of sensor. However, we could not continue the tests because of the membrane's oxidation (pure Fe) and the difficulty of welding nonferrous metals. In present study, a permeation sensor made of vacuum flanges with a porous plate inside is proposed not only to eliminate the difficulty of the fabrication but to optimize the performance of sensor. The permeation sensor to measure the hydrogen isotopes in liquid metal breeder has been proposed and evaluated to overcome the limitation of a long response time for various shapes and materials. We found that the previous sensors have limitation; the oxidation problems (pure Fe) and the difficulty in welding (nonferrous metals). Therefore we proposed a permeation sensor with the vacuum flanges filled with porous disks to eliminate the problems. By using the CF flanges, the problem caused by welding is removed. But the permeable response time of sensors took a long time to reach the pressure equivalent

  14. Performance Analysis of Text Alignment Tools Using Automated Test Bed

    Directory of Open Access Journals (Sweden)

    John Nabil

    2012-10-01

    Full Text Available The text alignment process is an important activity in the statistical machine translation (SMT upon thetraining phase of SMT systems on huge amounts of parallel corpora. We are evaluating five of the populartext aligners and analyzing the methodologies used in each of them, then we are introducing new opensource automated test bed for testing those text aligners and generating reports called pyTester, and finallydiscuss our observations about the test results generated from pyTester.

  15. Effects of age and gender on performance on Conners' Continuous Performance Test in Brazilian adolescents

    Scientific Electronic Library Online (English)

    Mônica C., Miranda; Thiago S., Rivero; Orlando F. Amodeo, Bueno.

    2013-06-01

    Full Text Available The present study analyzed the effects of age and gender on performance on the Conners' Continuous Performance Test (CCPT II) in a sample of Brazilian adolescents aged 12-17 years. The sample consisted of 480 participants (210 boys) with a mean age of 14.34 years (SD ± 1.61 years) who were represent [...] ative of the socioeconomic class distribution of the city of São Paulo, Brazil. The participants were prescreened for attention-deficit/hyperactivity disorder. The present results found effects of age and gender that were similar to other Brazilian age groups. Compared with males, female participants presented a lower rate of responding to non-target stimuli (i.e., commission errors), a greater ability to discriminate signals (d'), and fewer impulsive responses (i.e., less perseveration) but longer reaction times (Hit RT and Hit RT Std Error). A significant effect of age was found on RTs (Hit RT, Hit RT Sdt Error, Variability, Hit RT Block Change), commission errors, and perseveration. As age increased, the differences diminished. The present results may be useful for research and clinical studies with Brazilian adolescents.

  16. Performance test of the transmission components for KSTAR ICH system on the test bed

    International Nuclear Information System (INIS)

    6 MW will be coupled to the plasma by using four strap antenna in KSTAR (Korean Superconducting Tokamak Advanced Research) ICH system where 8 MW rf power is launched from the transmitter in the frequency range from 25 to 60 MHz. There are two important factors in the design of KSTAR ICH system. One is the breakdown voltage in the transmission system which limits the maximum rf power coupled to the ICH antenna and another is the removal of the heat from the rf ohmic loss during the long pulse operation. Maximum breakdown voltage and current in ICH system are 35 kV and 1kA, respectively and components are designed for the operation of 300 seconds. The test bed is designed to produce at least 35 kV/1 kA by applying low rf power up to 30 kW and high voltage/current test is performed on the vacuum feedthrough and other transmission components

  17. O teste de Zulliger e avaliação de desempenho / The Zulliger test and job performance evaluation

    Scientific Electronic Library Online (English)

    Marcia Eloisa Avona, Ferreira; Anna Elisa de, Villemor-Amaral.

    2005-12-01

    Full Text Available Este trabalho aborda a avaliação da personalidade no contexto organizacional, tendo como objetivo buscar evidências de validade para o teste Zulliger por meio da correlação com um questionário de Avaliação de Desempenho. Foram avaliados os resultados de uma amostra de 86 sujeitos, com formação em En [...] genharia Elétrica, Engenharia da Computação, Engenharia Eletrônica, Ciência da Computação, Análise de Sistemas e Estatística, com idades entre 22 e 43 anos, gêneros masculino e feminino. O Zulliger foi analisado conforme o Sistema Compreensivo. A Avaliação de desempenho considerou os itens relacionamento interpessoal, tomada de decisões, busca por inovação, organização e solução de problemas. As análises de correlação entre os dois instrumentos indicaram que profissionais mais disciplinados e organizados, que possuem iniciativa e uma visão prática e buscam resultados concretos são mais bem avaliados do que os imaturos emocionalmente, altamente críticos e mais egocentrados, que priorizam as próprias necessidades em detrimento das dos outros. Abstract in english This paper brings information about personality assessment in the organizational context, and the objective was to look for validity evidences for the Zulliger test in correlation with a questionnaire of Job Performance Evaluation. The results from a 86 subjects sample were examined. They had bachel [...] or's degree in Electric Engineering, Computer Engineering, Electronic Engineering, Computer Science, System Analysis, and Statistics, men and women between 22 and 43 years old. The Z-test was analyzed using the Comprehensive System. The results showed that more disciplined and organized professionals, having initiative and practical vision, which target realistic results had an overall better evaluation. Not so well did the emotionally immature ones, or the ones highly critical and self-centered, who prioritize their own needs instead of the other ones' necessities.

  18. 40 CFR 60.58a - Compliance and performance testing.

    Science.gov (United States)

    2010-07-01

    ...16) Not operating a sorbent...reduction standards for MWC acid...following procedures and test methods...7) Not operating a sorbent...reduction standards for MWC acid...following procedures and test methods...following procedures shall be...with the operating standards under §...

  19. Differential Gender Performance on the Major Field Test-Business

    Science.gov (United States)

    Bielinska-Kwapisz, Agnieszka; Brown, F. William

    2013-01-01

    The Major Field Test in Business (MFT-B), a standardized assessment test of business knowledge among undergraduate business seniors, is widely used to measure student achievement. Many previous studies analyzing scores on the MFT-B report gender differences on the exam even after controlling for student's aptitude, general intellectual…

  20. Heritability in Cognitive Performance: Evidence Using Computer-Based Testing

    Science.gov (United States)

    Hervey, Aaron S.; Greenfield, Kathryn; Gualtieri, C. Thomas

    2012-01-01

    There is overwhelming evidence of genetic influence on cognition. The effect is seen in general cognitive ability, as well as in specific cognitive domains. A conventional assessment approach using face-to-face paper and pencil testing is difficult for large-scale studies. Computerized neurocognitive testing is a suitable alternative. A total of…

  1. Modern off-gas treatment processes for wood furnaces. Part 1. Catalytic process for emission reduction from small furnaces

    International Nuclear Information System (INIS)

    A new, simple and low-cost catalyst for hydrocarbons was developed at the Institute of Energy and Environmental Engineering (Institut fuer Energie- und Umwelttechnik, IUTA). The catalyst consists of purified noble steel chips which are turned into a thermally and mechanically stable catalyst by doping with various transition metals. Further development activities resulted in a catalytic system for exhaust purification in small furnaces, which was tested in several private households in order to define the need for further optimisation in terms of practicability and availability. (orig.)

  2. Final Report - Glass Formulation Testing to Increase Sulfate Volatilization from Melter, VSL-04R4970-1, Rev. 0, dated 2/24/05

    Energy Technology Data Exchange (ETDEWEB)

    Kruger, Albert A.; Matlack, K. A.; Pegg, I. L.; Gong, W.

    2013-11-13

    The principal objectives of the DM100 and DM10 tests were to determine the impact of four different organics and one inorganic feed additive on sulfate volatilization and to determine the sulfur partitioning between the glass and the off-gas system. The tests provided information on melter processing characteristics and off-gas data including sulfur incorporation and partitioning. A series of DM10 and DM100 melter tests were conducted using a LAW Envelope A feed. The testing was divided into three parts. The first part involved a series of DM10 melter tests with four different organic feed additives: sugar, polyethylene glycol (PEG), starch, and urea. The second part involved two confirmatory 50-hour melter tests on the DM100 using the best combination of reductants and conditions based on the DM10 results. The third part was performed on the DM100 with feeds containing vanadium oxide (V{sub 2}O{sub 5}) as an inorganic additive to increase sulfur partitioning to the off-gas. Although vanadium oxide is not a reductant, previous testing has shown that vanadium shows promise for partitioning sulfur to the melter exhaust, presumably through its known catalytic effect on the SO{sub 2}/SO{sub 3} reaction. Crucible-scale tests were conducted prior to the melter tests to confirm that the glasses and feeds would be processable in the melter and that the glasses would meet the waste form (ILAW) performance requirements. Thus, the major objectives of these tests were to: ? Perform screening tests on the DM10 followed by tests on the DM100-WV system using a LAW -Envelope A feed with four organic additives to assess their impact on sulfur volatilization. ? Perform tests on the DM100-WV system using a LAW -Envelope A feed containing vanadium oxide to assess its impact on sulfur volatilization. ? Determine feed processability and product quality with the above additives. ? Collect melter emissions data to determine the effect of additives on sulfur partitioning and melter emissions. ? Collect and analyze discharged glass to determine sulfur retention in the glass. ? Prepare and characterize feeds and glasses with the additives to confirm that the feeds and the glass melts are suitable for processing in the DM100 melter. ? Prepare and characterize glasses with the additives to confirm that the glasses meet the waste form (ILAW) performance requirements.

  3. Performance demonstration tests for eddy current inspection of steam generator tubing

    Energy Technology Data Exchange (ETDEWEB)

    Kurtz, R.J.; Heasler, P.G.; Anderson, C.M.

    1996-05-01

    This report describes the methodology and results for development of performance demonstration tests for eddy current (ET) inspection of steam generator tubes. Statistical test design principles were used to develop the performance demonstration tests. Thresholds on ET system inspection performance were selected to ensure that field inspection systems would have a high probability of detecting and and correctly sizing tube degradation. The technical basis for the ET system performance thresholds is presented in detail. Statistical test design calculations for probability of detection and flaw sizing tests are described. A recommended performance demonstration test based on the design calculations is presented. A computer program for grading the probability of detection portion of the performance demonstration test is given.

  4. Performance demonstration tests for eddy current inspection of steam generator tubing

    International Nuclear Information System (INIS)

    This report describes the methodology and results for development of performance demonstration tests for eddy current (ET) inspection of steam generator tubes. Statistical test design principles were used to develop the performance demonstration tests. Thresholds on ET system inspection performance were selected to ensure that field inspection systems would have a high probability of detecting and and correctly sizing tube degradation. The technical basis for the ET system performance thresholds is presented in detail. Statistical test design calculations for probability of detection and flaw sizing tests are described. A recommended performance demonstration test based on the design calculations is presented. A computer program for grading the probability of detection portion of the performance demonstration test is given

  5. Performance of the modified Wilcoxon signed rank test

    Science.gov (United States)

    Ahad, Nor Aishah; Yahaya, Sharipah Soaad Syed; MdYusof, Zahayu; Abdullah, Suhaida; Fung, Lim Yai

    2014-12-01

    Nonparametric methods require only few assumptions to be made about the format of the data, and they may therefore be preferable when the assumptions required for parametric methods are not valid. The Wilcoxon signed rank test applies to matched pairs studies. For two tail test, it tests the null hypothesis that there is no systematic difference within pairs against alternatives that assert a systematic difference. The test is based on the Wilcoxon signed rank statistic W, which is the smaller of the two ranks sums. The steps to compute W consider the positive and negative differences and omit all the zero differences. In this study, we modify the Wilcoxon signed rank test using the indicator function of positive, zero and negative differences to compute the Wilcoxon statistic, W. The empirical Type I error rates of the modified statistical test was measured via Monte Carlo simulation. These rates were obtained under different distributional shapes, sample sizes, and number of replications. The modified Wilcoxon signed rank test was found to be robust under symmetric distributions even though the values are quite conservative. The finding also demonstrated that different number of replication does not influence the result because there is not much difference in the value of the Type I error rates obtained.

  6. 49 CFR Appendix E to Part 240 - Recommended Procedures for Conducting Skill Performance Tests

    Science.gov (United States)

    2010-10-01

    ...given a skill performance test prior to certification...for the conduct of that test. Railroads are...throttle use, brake application, and train speed...performance of a brake test. As the complexity...minimize the risk that personality factors adversely...

  7. DEVELOPMENT OF AN ANTIFOAM TRACKING SYSTEM AS AN OPTION TO SUPPORT THE MELTER OFF-GAS FLAMMABILITY CONTROL STRATEGY AT THE DWPF

    Energy Technology Data Exchange (ETDEWEB)

    Edwards, T.; Lambert, D.

    2014-08-27

    The Savannah River National Laboratory (SRNL) has been working with the Savannah River Remediation (SRR) Defense Waste Processing Facility (DWPF) in the development and implementation of an additional strategy for confidently satisfying the flammability controls for DWPF’s melter operation. An initial strategy for implementing the operational constraints associated with flammability control in DWPF was based upon an analytically determined carbon concentration from antifoam. Due to the conservative error structure associated with the analytical approach, its implementation has significantly reduced the operating window for processing and has led to recurrent Slurry Mix Evaporator (SME) and Melter Feed Tank (MFT) remediation. To address the adverse operating impact of the current implementation strategy, SRR issued a Technical Task Request (TTR) to SRNL requesting the development and documentation of an alternate strategy for evaluating the carbon contribution from antifoam. The proposed strategy presented in this report was developed under the guidance of a Task Technical and Quality Assurance Plan (TTQAP) and involves calculating the carbon concentration from antifoam based upon the actual mass of antifoam added to the process assuming 100% retention. The mass of antifoam in the Additive Mix Feed Tank (AMFT), in the Sludge Receipt and Adjustment Tank (SRAT), and in the SME is tracked by mass balance as part of this strategy. As these quantities are monitored, the random and bias uncertainties affecting their values are also maintained and accounted for. This report documents: 1) the development of an alternate implementation strategy and associated equations describing the carbon concentration from antifoam in each SME batch derived from the actual amount of antifoam introduced into the AMFT, SRAT, and SME during the processing of the batch. 2) the equations and error structure for incorporating the proposed strategy into melter off-gas flammability assessments. Sample calculations of the system are also included in this report. Please note that the system developed and documented in this report is intended as an alternative to the current, analytically-driven system being utilized by DWPF; the proposed system is not intended to eliminate the current system. Also note that the system developed in this report to track antifoam mass in the AMFT, SRAT, and SME will be applicable beyond just Sludge Batch 8. While the model used to determine acceptability of the SME product with respect to melter off-gas flammability controls must be reassessed for each change in sludge batch, the antifoam mass tracking methodology is independent of sludge batch composition and as such will be transferable to future sludge batches.

  8. The Yo-Yo tests and twelve-minute run test performance in young Japanese cross-country skiers

    OpenAIRE

    Denda Yuki; Oh Taewoong; Nakajima Setsuko

    2013-01-01

    Purpose: The aim of the present study is to examine the performance of young Japanese cross-country skiers of different competitive levels with the use of Yo-Yo tests and the 12-minute run test (12MRT) that have been demonstrated to be related to each level, and to know which test is suitable for different competitive performance. Methods: Elite group (N = 9) was 16.9 ± 0.3 years and moderate trained group (N = 22) was 16.1 ± 0.9 years. The testing sessions consisted of the following: 1) V...

  9. Project W-314 performance mock-up test procedure

    International Nuclear Information System (INIS)

    The purpose of this Procedure is to assist construction in the pre-operational fabrication and testing of the pit leak detection system and the low point drain assembly by: (1) Control system testing of the pit leak detection system will be accomplished by actuating control switches and verifying that the control signal is initiated, liquid testing and overall operational requirements stated in HNF-SD-W314-PDS-003, ''Project Development Specification for Pit Leak Detection''. (2) Testing of the low point floor drain assembly by opening and closing the drain to and from the ''retracted'' and ''sealed'' positions. Successful operation of this drain will be to verify that the seal does not leak on the ''sealed'' position, the assembly holds liquid until the leak detector actuates and the assembly will operate from on top of the mock-up cover block

  10. Subsurface barrier demonstration test strategy and performance specification

    International Nuclear Information System (INIS)

    This document was developed to help specify a major demonstration test project of subsurface barrier systems supporting the Tank Waste Remediation System (TWRS) Program. The document focuses discussion on requirements applicable to demonstration of three subsurface barrier concepts: (1) Injected Material, (2) Cryogenic, and (3) Desiccant. Detailed requirements are provided for initial qualification of a technology proposal followed by the pre-demonstration and demonstration test requirements and specifications. Each requirement and specification is accompanied by a discussion of the rationale for it. The document also includes information on the Hanford Site tank farms and related data; the related and currently active technology development projects within the DOE's EM-50 Program; and the overall demonstration test strategy. Procurement activities and other preparations for actual demonstration testing are on hold until a decision is made regarding further development of subsurface barriers. Accordingly, this document is being issued for information only

  11. Limitations in predicting student performance on standardized tests

    OpenAIRE

    Wittmann, Michael C.

    2002-01-01

    The Maryland Physics Expectations Survey (MPEX) describes student attitudes and expectations toward learning, and might be used to predict normalized gains on tests such as the Force and Motion Concept Evaluation (FMCE). These predictions are incomplete, though, due to limitations of the standardized tests themselves. I illustrate the problems involved in using the MPEX to predict productive attitudes toward learning physics by focusing on two students, both with seemingly a...

  12. Off-gas ventilation system design for the shielding structure of the 100 MeV proton accelerator of PEFP

    International Nuclear Information System (INIS)

    In this paper, we describe a design of a ventilation system to limit the total doses given to workers by satisfying the regulatory limits. We suggest a radiation shielding design scheme to reduce the Ar-41 production rate in each target room of the Beam Application Research Area (BARA). Analyses were performed for the ventilation system design of Proton Engineering Frontier Project (PEFP). According to the analyses results, the radioactivity production rate in the accelerator tunnel is saturated at 5.57x10-3 Bq/cm3 in 16 h without a ventilation system operation, which satisfies the regulatory limits. In the target rooms of the BARA, the radioactivity production rate is reduced within the range from 329 Bq/cm3 to 5.19 Bq/cm3 by the proposed ventilation system for the PEFP radiation shielding scheme. (author)

  13. Final design and performance of in situ testing in Grimsel

    International Nuclear Information System (INIS)

    This report is focused on the design, engineering, and construction aspects of the in situ test carried out at the Grimsel underground laboratory in Switzerland. This reproduces the AGP-granite concept of ENRESA for HLW repositories in crystalline rock. Two heaters, similar in dimensions and weight to the canisters in the reference concept, have been placed in a horizontal drift with a 2.28-m diameter, a total test length of 17.4 m, and backfilled with a total of 115.7 † of highly-compacted bentonite blocks. The backfilled area has been closed with a concrete plug which is 2.7 m thick. More than 600 sensors have been installed in the test to monitor different parameters such as temperature, pressures, humidity, etc., within both the buffer material and the host rock. The installation was completed and commissioned in February 1997, and then the heating phase, which will last for at least 3 years, was started. During this period, the test will basically be operated in an automatic mode, controlled and monitored from Spain via modem. The report is the Final Report from AITEMIN for Phase 4 of the project and includes a description of the test configuration and layout; the design, engineering, and manufacturing aspects of the different test components and equipment; the emplacement operation; and the as built information regarding the final position of the main components and the sensors. (Author)

  14. 9 CFR 130.17 - User fees for other veterinary diagnostic laboratory tests performed at NVSL (excluding FADDL) or...

    Science.gov (United States)

    2010-01-01

    ...2010-01-01 false User fees for other veterinary diagnostic laboratory tests performed...FEES § 130.17 User fees for other veterinary diagnostic laboratory tests performed...authorized sites. (a) User fees for veterinary diagnostics tests performed at...

  15. Ankle Taping Does Not Impair Performance in Jump or Balance Tests

    OpenAIRE

    Javier Abián-Vicén; Alegre, Luis M.; Manuel Fernández-Rodríguez; Lara, Amador J.; Marta Meana; Xavier Aguado

    2008-01-01

    This study aimed to investigate the influence of prophylactic ankle taping on two balance tests (static and dynamic balance) and one jump test, in the push off and the landing phase. Fifteen active young subjects (age: 21.0 ± 4.4 years) without previous ankle injuries volunteered for the study. Each participant performed three tests in two different situations: with taping and without taping. The tests were a counter movement jump, static balance, and a dynamic posturography test. The tests ...

  16. 40 CFR 63.827 - Performance test methods.

    Science.gov (United States)

    2010-07-01

    ...the Printing and Publishing Industry § 63.827 Performance...fraction organic HAP of inks, coatings, varnishes, adhesives...fraction organic HAP of inks, coatings, varnishes, adhesives...fraction organic HAP of each ink, coating, varnish, adhesive,...

  17. 40 CFR 63.563 - Compliance and performance testing.

    Science.gov (United States)

    2010-07-01

    ...measured between the facility's vapor connection and its manual isolation valve, and the measured pressure must be below atmospheric...564(g)(1) of no more than 1,200 ppmv VOC. (7) Condenser/refrigeration unit. During the initial performance...

  18. Evaluation of radiographic testing performance with an advanced POD approach

    International Nuclear Information System (INIS)

    POD is the most often used approach for the evaluation of the reliability of non-destructive testing methods in critical areas. But especially for those cases the requirements for a sufficient amount of data, adequate type of defects and the statistical requirements are high. The claim for checking these requirements is not new, but never the less often ignored. Especially the large amount of data for critical real defects seems too often to be not really solvable. In this presentation we show an approach to use real defect data with knowledge from former testing results with the same equipment, in a useful adequate way. Furthermore we introduce a method to evaluate the real defect description parameters for the radiographic testing. This approach was used for a joint project with the company POSIVA, which is building a final depository for spent nuclear fuel in Finland. Radiographic testing is one of the NDT-methods they use to test the electron beam weld of the copper canister. The copper canister will be used in the deposit as a corrosion barrier within the deposit concept. Through the high sophisticated manufacturing methods of the canister there are almost no material defects, which could be used for reliability evaluation. In this context the idea of Bayesian Updating of the POD with real defect data with former results from artificial defect data was born to get a useful evaluation.

  19. Construct Validity of the Computerized Continuous Performance Test with Measures of Intelligence, Achievement, and Behavior.

    Science.gov (United States)

    Campbell, Janice Whitten; And Others

    1991-01-01

    Administered Continuous Performance Test (CPT), Wechsler Intelligence Scale for Children-Revised, Wide Range Achievement Test-Revised, Bender Visual-Motor Gestalt Test, and reading comprehension subtest of Peabody Individual Achievement Test to 54 school-aged children and adolescents referred for evaluation of learning disabilities. Parents…

  20. The Examination of Reliability According to Classical Test and Generalizability on a Job Performance Scale

    Science.gov (United States)

    Yelboga, Atilla; Tavsancil, Ezel

    2010-01-01

    In this research, the classical test theory and generalizability theory analyses were carried out with the data obtained by a job performance scale for the years 2005 and 2006. The reliability coefficients obtained (estimated) from the classical test theory and generalizability theory analyses were compared. In classical test theory, test retest…

  1. System Design and Performance Test of Hydraulic Intensifier

    International Nuclear Information System (INIS)

    Components such as pressure vessel, hydraulic hose assembly, accumulator, hydraulic cylinder, hydraulic valve, pipe, etc., are tested under the impulse-pressure conditions prescribed in ISO and SAE standards. The impulse pressure test machine needs to have a high pressure, a precise control system and a long life. It should satisfy the requirements for fabrication of the impulse tester to generate ultra high pressure in the hydraulic system. In the impulse tester, a servo-valve control system is adopted; although the control application is convenient, it is expensive owing to the cost of developing the system. The type of the control system determines the pressure wave, which affects the components that are tested. In this study, the manufacturing process and the intensifier system design related to the flow, pressure, and the increasing rate of pressure are investigated. The results indicate the ultra high pressure waves in the system

  2. Chemical products toxicological tests performed on lake and river fish

    International Nuclear Information System (INIS)

    The volume and toxical values of industrial and urban effluents are growing higher and therefore acute or chronic pollution hazard is proportionally increased. Hence it is necessary to determine the effluent components minimum lethal dose for fish (one hour or six hours according to applicable standards). The following tests are described in this report: toxicity of some chemical products, tested individually (sodium, sulphate, sodium chloride, sodium fluoride, etc...); toxicity of some metal ions (Al3+, Fe++, Fe3+, Pb++, etc...); toxicity of certain mixed compounds for various fish species (sun perch, tench, gold fish, roach, gudgeon, bleak). The test results obtained represent local values and may be used for reference and as a general basis for other investigation and calculation of the effluents data when released. (author)

  3. Performance of superplasticised fibrous concrete on RCPT test under thermoshock

    Directory of Open Access Journals (Sweden)

    G. Elangovan

    2010-01-01

    Full Text Available This experimental investigation is about the chloride ion penetration of concrete under effect of thermo shock on superplasticised fibrous concrete at 200 degree Celsius. As reported in previous studies concretes made with purely Ordinary Portland Cement (OPC showed evidence of a steady decline in residual strength when subjected to thermoshock under elevated temperatures. In the present study tests were conducted to minimize the reduction of residual strength under compression, minimize the chloride ion penetration of OPC concrete by using chemical admixtures like superplasticiser and with different individual fibers. This paper exposes the details of the test programme, results and also compares against the same with earlier reports. From this test results, it was found that the residual properties of concrete were not affected and data available here will be helpful in assessing the residual strength of concrete after thermoshock.

  4. Examination of performance validity test failure in relation to number of tests administered.

    Science.gov (United States)

    Davis, Jeremy J; Millis, Scott R

    2014-01-01

    This study examined the relationship among performance validity test (PVT) failure, number of PVTs administered, and participant characteristics including demographic, diagnostic, functional, and contextual factors in a clinical sample (N = 158) of outpatient physiatry referrals. The number of PVTs failed and the number administered showed a small non-significant correlation (rs = .13, p = .10). Participant characteristics showed associations with PVT failure consistent with prior research. A negative binomial regression model was fitted using number of PVTs failed as outcome and age, education, number of PVTs administered, clinical versus medico-legal context, and functional status as predictors. Although education and functional status were significant predictors of number of PVTs failed, the number of PVTs administered was not. A second analytic approach focused on observed false positive rates in a neurologic no-incentive (NNI) sample subset (n = 87). In contrast to a recent proposal based on statistical simulation, observed false positive rates were lower than predicted rates in NNI participants administered six, seven, or eight PVTs using a two-PVT failure cutoff. These results are interpreted as mitigating concerns that increased PVT failure is necessarily the outcome of increased PVT administration. PMID:24528190

  5. A system of miniaturized stirred bioreactors for parallel continuous cultivation of yeast with online measurement of dissolved oxygen and off-gas.

    Science.gov (United States)

    Klein, Tobias; Schneider, Konstantin; Heinzle, Elmar

    2013-02-01

    Chemostat cultivation is a powerful tool for physiological studies of microorganisms. We report the construction and application of a set of eight parallel small-scale bioreactors with a working volume of 10?mL for continuous cultivation. Hungate tubes were used as culture vessels connected to multichannel-peristaltic pumps for feeding fresh media and removal of culture broth and off-gas. Water saturated air is sucked into the bioreactors by applying negative pressure, and small stirrer bars inside the culture vessels allow sufficient mixing and oxygen transfer. Optical sensors are used for non-invasive online measurement of dissolved oxygen, which proved to be a powerful indicator of the physiological state of the cultures, particularly of steady-state conditions. Analysis of culture exhaust-gas by means of mass spectrometry enables balancing of carbon. The capacity of the developed small-scale bioreactor system was validated using the fission yeast Schizosaccharomyces pombe, focusing on the metabolic shift from respiratory to respiro-fermentative metabolism, as well as studies on consumption of different substrates such as glucose, fructose, and gluconate. In all cases, an almost completely closed carbon balance was obtained proving the reliability of the experimental setup. PMID:22887039

  6. Monitoring laboratory performance over time from proficiency testing by interlaboratory comparisons

    OpenAIRE

    Trancoso, Maria Ascensa?o; Sousa, Ana R.; Calisto, Sandra C.

    2014-01-01

    Proficiency testing by interlaboratory comparisons is used to determine the individual performance of a laboratory for a specific test or measurement and to monitor the continuing performance of laboratories. Monitoring PT performance over time allows to identify potential problems related to random and systematics errors. Participation in interlaboratory comparison tests (IEC), is a requirement of the accreditation bodies either for granting laboratory accreditation by EN ISO/IEC 17025:2...

  7. Development of Design Concept and Applied Technology for RCP Performance Test Facility

    International Nuclear Information System (INIS)

    Performance test facility for RCP (reactor coolant pump) is essential to verify the performance and reliability of RCP before installation in the nuclear power plant. The development of RCP for new-type reactor and the performance verification of hydraulic revolving body also needs the RCP test facility. The design concept of test loop and the technology of flow rate measurement are investigated in this research

  8. Performance Test of Korea Heat Load Test Facility (KoHLT-EB) for the Plasma Facing Components of Fusion Reactor

    International Nuclear Information System (INIS)

    The main components of the plasma facing components (PFCs) in the tokamak are the blanket first wall and divertor, which include the armour materials, the heat sink with the cooling mechanism, and the diagnostics devices for the temperature measurement. The Korea Heat Load Test facility by using electron beam (KoHLT-EB) has been operating for the plasma facing components to develop fusion engineering. This electron beam facility was constructed using a 300 kW electron gun and a cylindrical vacuum chamber. Performance tests were carried out for the calorimetric calibrations with Cu dummy mockup and for the heat load test of large Cu module. For the simulation of the heat load test of each mockup, the preliminary thermal-hydraulic analyses with ANSYS-CFX were performed. For the development of the plasma facing components in the fusion reactors, test mockups were fabricated and tested in the high heat flux test facility. To perform a beam profile test, an assessment of the possibility of electron beam Gaussian power density profile and the results of the absorbed power for that profile before the test starts are needed. To assess the possibility of a Gaussian profile, for the qualification test of the Gaussian heat load profile, a calorimeter mockup and large Cu module were manufactured to simulate real heat. For this high-heat flux test, the Korean high-heat flux test facility using an electron beam system was constructed. In this facility, a cyclic heat flux test will be performed to measure the surface heat flux, surface temperature profile, and cooling capacity

  9. Performance Test of Korea Heat Load Test Facility (KoHLT-EB) for the Plasma Facing Components of Fusion Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Suk-Kwon; Jin, Hyung Gon; Lee, Eo Hwak; Yoon, Jae-Sung; Lee, Dong Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Cho, Seungyon [National Fusion Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The main components of the plasma facing components (PFCs) in the tokamak are the blanket first wall and divertor, which include the armour materials, the heat sink with the cooling mechanism, and the diagnostics devices for the temperature measurement. The Korea Heat Load Test facility by using electron beam (KoHLT-EB) has been operating for the plasma facing components to develop fusion engineering. This electron beam facility was constructed using a 300 kW electron gun and a cylindrical vacuum chamber. Performance tests were carried out for the calorimetric calibrations with Cu dummy mockup and for the heat load test of large Cu module. For the simulation of the heat load test of each mockup, the preliminary thermal-hydraulic analyses with ANSYS-CFX were performed. For the development of the plasma facing components in the fusion reactors, test mockups were fabricated and tested in the high heat flux test facility. To perform a beam profile test, an assessment of the possibility of electron beam Gaussian power density profile and the results of the absorbed power for that profile before the test starts are needed. To assess the possibility of a Gaussian profile, for the qualification test of the Gaussian heat load profile, a calorimeter mockup and large Cu module were manufactured to simulate real heat. For this high-heat flux test, the Korean high-heat flux test facility using an electron beam system was constructed. In this facility, a cyclic heat flux test will be performed to measure the surface heat flux, surface temperature profile, and cooling capacity.

  10. Conceptual study of test reactor for fuel irradiation/reactor performance research

    International Nuclear Information System (INIS)

    This report describes the results of conceptual design study of a test reactor for fuel irradiation research and/or reactor performance research as a central facility of the 'Integrated Test Facilities for the Future LWR Technology' which have been developed by JAERI's Advanced LWR Technology Development Program Team. The conceptual design study included the activities concerning reactor system and structural design, and nuclear and thermal performance analyses. Four different types of test reactors were examined. They were a 'PWR/BWR dual type test reactor' to conduct fuel irradiation tests and reactor performance tests under either PWR conditions or BWR conditions, a 'PWR type test reactor' to conduct those tests under PWR conditions, a 'BWR type test reactor' to conduct those tests under BWR conditions, and a 'fuel irradiation test reactor' to conduct fuel irradiation tests only. For the former three test reactors, a central loop in the core and multiple core fuel assemblies in the outer region of the core were intended as fuel irradiation regions. The analyses indicate that these test reactors have a good capability of subjecting a test fuel rod to transient irradiation in the central loop and subjecting test fuel rod bundles to long-term steady irradiation in the core outer regions. As for reactor performance tests, a passive safety reactor was postulated as a test object, and necessary test reactor systems were considered. The fuel irradiation test reactor was designed to be operated under a low pressure and a low temperature and to have four irradiation loops in the core region and 18 vertical holes in the reflector region for irradiation loops and capsules. The analyses indicate that the test reactor has a good capability of subjecting test fuel rod bundles to long-term steady irradiation in the core region and subjecting test fuel rods to transient irradiation in the reflector region. (author)

  11. Limitations in predicting student performance on standardized tests

    CERN Document Server

    Wittmann, M C

    2002-01-01

    The Maryland Physics Expectations Survey (MPEX) describes student attitudes and expectations toward learning, and might be used to predict normalized gains on tests such as the Force and Motion Concept Evaluation (FMCE). These predictions are incomplete, though, due to limitations of the standardized tests themselves. I illustrate the problems involved in using the MPEX to predict productive attitudes toward learning physics by focusing on two students, both with seemingly appropriate expectations toward learning. While one had high normalized gains, the other did not, due to "false favorable" responses on the MPEX.

  12. Specialist committee's review reports for experimental fast reactor JOYO' MK-III performance tests

    International Nuclear Information System (INIS)

    Performance tests (startup-physics tests and power elevation tests) were planed for experimental fast reactor 'JOYO' MK-III where irradiation performances were upgraded by power increase from 100 to 140 MW. The reactor safety committee of O-arai Engineering Center has established a specialist committee for 'JOYO' MK-III Performance Tests at the first meeting of 2003 on 23th. April 2003, to accomplish the tests successfully. Subjects of the specialist committee were reviews of following items covering a wide range. 1) Contents of modification works. 2) Reflections of functional test results to the plant and facilities. 3) Reflections of safety rule modification to instruction and manual for operation. 4) Quality assurances and pre-calculation for performance test. 5) Inspection plan and its results. 6) Adequacy of performance test plan. 7) Confirmation of performance test results. Before test-starts, the specialist committee has confirmed by reviewing the items from 1) to 6) based on explanations and documents of the Division of Experimental Reactor, that the test plan and pre-inspections are adequate. After the tests, the specialist committee had confirmed by reviewing the item 7) in the same way, that the each test result satisfies the corresponding criterion. The specialist committee has concluded from these review's results before and after the tests that the 'JOYO' MK-III Performance Tests were carried out appropriately. Besides, the first criticality of the JOYO esides, the first criticality of the JOYO MK-III was achieved on 2nd. July 2003, and the continuous full power operation was carried on 20th. Nov. 2003. Finally, all performance tests were completed by the pass of the last governmental pre-serviced inspection (dose rate measurement during the shut down condition). (author)

  13. Vehicles Esp Control Performances on the Two-pitman Restriction Test System

    OpenAIRE

    Zhang Lu; Yang Liu; Wang Guoye; Zhang Zhongfu

    2013-01-01

    Real vehicle test is a necessary segment in the procedure of vehicle ESP control system research and development, which can really shows the real effect of vehicle ESP control and is a strong mean and final test method in the research and development. ESP control performances exist some problems such as high dangerous, long period, high cost of the common ESP control performances real vehicle test. Project the two-pitman restriction test system, establish its dynamic system model, Take exampl...

  14. Development of a standardized battery of performance tests for the assessment of noise stress effects

    Science.gov (United States)

    Theologus, G. C.; Wheaton, G. R.; Mirabella, A.; Brahlek, R. E.

    1973-01-01

    A set of 36 relatively independent categories of human performance were identified. These categories encompass human performance in the cognitive, perceptual, and psychomotor areas, and include diagnostic measures and sensitive performance metrics. Then a prototype standardized test battery was constructed, and research was conducted to obtain information on the sensitivity of the tests to stress, the sensitivity of selected categories of performance degradation, the time course of stress effects on each of the selected tests, and the learning curves associated with each test. A research project utilizing a three factor partially repeated analysis of covariance design was conducted in which 60 male subjects were exposed to variations in noise level and quality during performance testing. Effects of randomly intermittent noise on performance of the reaction time tests were observed, but most of the other performance tests showed consistent stability. The results of 14 analyses of covariance of the data taken from the performance of the 60 subjects on the prototype standardized test battery provided information which will enable the final development and test of a standardized test battery and the associated development of differential sensitivity metrics and diagnostic classificatory system.

  15. 42 CFR 493.1403 - Condition: Laboratories performing moderate complexity testing; laboratory director.

    Science.gov (United States)

    2010-10-01

    ... 2010-10-01 false Condition: Laboratories performing moderate complexity testing; laboratory director. 493.1403 Section 493...CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Personnel for...

  16. 42 CFR 493.1441 - Condition: Laboratories performing high complexity testing; laboratory director.

    Science.gov (United States)

    2010-10-01

    ... 2010-10-01 false Condition: Laboratories performing high complexity testing; laboratory director. 493.1441 Section 493...CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Personnel for...

  17. Overview of the new ASME Performance Test Code for wind turbines

    Science.gov (United States)

    Spera, David A.

    1986-01-01

    The principal technical features of the ASME Performance Test Code for wind turbines are presented and such issues as what sizes and types of wind turbines should be included, what the principal measure of performance should be, and how wind speed should be measured are discussed. It is concluded that the present test code is applicable to wind turbine systems of all sizes. The principal measure of performance as defined by this code is net energy output and the primary performance parameter is the 'test energy ratio' which is based on a comparison between the measured and predicted energy output for the test period.

  18. Age-Related Decrements in Stroop Color Test Performance.

    Science.gov (United States)

    Cohn, Nancy B.; And Others

    1984-01-01

    Administered a modified Stroop Color-Word Test to healthy males (N=80) aged 21-90 years as part of a study of neuropsychological functioning. Results showed differences on simple reading tasks; however, significant age effects were observed for the color naming and interference tasks. (LLL)

  19. Muon Walls Performance in 1998 and 1999 Tilecal Beam Tests

    CERN Document Server

    Bromberg, C; Miller, R; Richards, R; Schooltz, D; Gallas, E; Hruska, I; Lokajícek, M; Némécek, S; Slavik, J; Weichert, J; Davidek, T; Krivkova, P; Leitner, R; Palacky, J; Soustruznik, K; Suk, M

    1999-01-01

    Muon walls setup for beam test of the TILECAL barrel module~0 in June-July 1998 and July 1999 is described. The walls are remotely operated and their setting for hadronic shower leakage detection is described. The low energy tail suppression for events without leakage is illustrated.

  20. 40 CFR 63.7 - Performance testing requirements.

    Science.gov (United States)

    2010-07-01

    ...source at any other time when the action is authorized by section 114...this part or taking any other action under the Act. (c) Quality...provide a measure of test data bias. The external QA program may...the Administrator before final action on the plan. (ii) In...