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Sample records for off-gas performance test

  1. Performance test of the pretreatment unit for Kr-85 recovery system from off-gas in fuel reprocessing plant

    International Nuclear Information System (INIS)

    In a Kr-85 recovery system using cryogenic distillation method for a spent fuel-reprocessing plant, oxygen may cause hazardous explosion in the presence of hydrocarbon such as acetylene. To prevent such hazards, an automatic control system of hydrogen has been proposed to remove oxygen by the reduction reaction of hydrogen over palladium (Pd) catalyst. The objective of this study is to examine some characteristics of the controller for adjusting the concentration of H2 and O2 in the Pd converter. The automatic control system consists of P-I controller which can set two parameters, proportional band (Kp) and integral time (T sub(I)). In the present test, Kp and T sub(I) were selected from 200% to 500% and from 5 min to 15 min, respectively, and the concentrations of O2 and H2 were measured at the inlet and the outlet of the Pd converter, respectively. The effect of Kp on the maximum concentration of H2 and on the recovery time, and the effects of integral time and dilution on the hydrogen and oxygen concentrations are presented by curves. It is concluded that the automatic hydrogen control system employed in the present study can respond rather quickly to the stepwise change of oxygen concentration with small dilution range. (Aoki, K.)

  2. GNEP Coupled End-to-End Research, Development, and Demonstration Project: Integrated Off-gas Treatment System Design and Performance Testing

    International Nuclear Information System (INIS)

    Full text of publication follows: ORNL is conducting a complete, coupled end-to-end (CETE) demonstration of advanced nuclear fuel reprocessing to support the Global Nuclear Energy Partnership (GNEP). These small scale reprocessing operations provide a unique opportunity to test integrated off-gas treatment systems designed to recover the primary volatile fission and activation products (3H, 14C, 85Kr, and 129I) released from the spent nuclear fuel (SNF). The CETE project will demonstrate an advanced head-end process referred to as 'Voloxidation' designed to condition the spent nuclear fuel, separate the SNF from the cladding, and release of tritium contained in the fuel matrix. The off-gas from this process as well as from the more traditional fuel dissolution process will be treated separately and the volatile components recovered. This paper will provide descriptions of the off-gas treatment systems for both the Voloxidation process and for the fuel dissolution process, and provide preliminary results from the initial CETE processing runs. Impacts of processing parameters on the relative quantities of volatile components released and recovery efficiencies will be evaluated. (authors)

  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. Decontamination performance in off-gas cleaning system of radioactive solid waste incineration unit

    International Nuclear Information System (INIS)

    At the Tokai Research Establishment of Japan Atomic Energy Research Institute, the radioactive solid waste incineration unit with a capacity of 100 kg/h was installed in 1979, since then the unit has been routinly operated. An off-gas cleaning system of the unit consists mainly of a primary and secondary ceramic filters, a heat resistant HEPA filter and a scrubber. A series of hot test was carried out to examine the docontamination performance for radionuclides in the off-gas cleaning system. In the test, simulated wastes contaminated with a known quantity of radionuclides were burned in the unit, and radioactive concentrations in the off-gas were measured. And then, the following data were obtained: a retention factor of radionuclides in a furnace and a decontamination factor for radionuclides in each of off-gas cleaning components. And also overall decontamination factors, defined as the ratio of radioactivities input to the furnace to radioactivities passed through outlet of the HEPA filter, were 9 x 106 (2 x 107) or more for 58Co (60Co), 1 x 102 for 75Se, 4 x 104 for 106Ru and 1 x 108 or more for 134Cs. (author)

  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-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. 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.

  8. 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

  9. 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

  10. 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

  11. Off-gas treatment and characterization for a radioactive in situ vitrification test

    International Nuclear Information System (INIS)

    Effluents released to the off gas during the in situ vitrification (ISV) of a test site have been characterized. The site consisted of a 19 L waste package of soil containing 600 nCi/g transuranic and 30,000 nCi/g mixed fission products surrounded by uncontaminated soil. Radioactive isotopes present in the package were 241Am, /sup 238/239/Pu, 137Cs, 106Ru, 90Sr, and 60Co. The ISV process melted the waste package and surrounding soil and immobilized the radionuclides in place, producing a durable, 8.6 metric ton glass and crystalline monolith. The test successfully demonstrated that the process provides containment of radioactive material. No release to the environment was detected during processing or cooldown. Due to the high temperatures during processing, some gases were released into the off-gas hood that was placed over the test site. The hood was maintained at a light negative pressure to contain any volatile or entrained material during processing. Gases passed from the hood to an off-gas treatment system where they were treated using a venturi-ejector scrubber, a tandem nozzle gas cleaner scrubber followed by a condenser, heater, and two stages of HEPA filters. The off-gas treatment system is located in the semi-trailer to allow transport of the process to other potential test sites. Retention of all radionuclides by the vitrified zone was greater than 99%. Soil-to-off-gas decontamination factors (DFs) for transuranic elements averaged greater than 4000 and for fission products, DFs ranged from 130 for 137Cs to 3100 for 90Sr

  12. Off-gas treatment and characterization for a radioactive in situ vitrification test

    International Nuclear Information System (INIS)

    Effluents released to the off gas during the in situ vitrification (ISV) of a test site have been characterized by Pacific Northwest Laboratory. The site consisted of a 19 L waste package of soil containing 600 nCi/g transuranic and 30,000 nCi/g mixed fission products surrounded by uncontaminated soil. Radioactive isotopes present in the package were 241Am, 238/239Pu, 137Cs, 106Ru, 90Sr, and 60Co. The ISV process melted the waste package and surrounding soil and immobilized the radionuclides in place, producing a durable, 8.6 metric ton glass and crystalline monolith. The test successfully demonstrated that the process provides containment of radioactive material. No release to the environment was detected during processing of cooldown. Due to the high temperature during processing, some gases were released into the off-gas hood that was over the test site. The hood was maintained at a slight negative pressure to contain any volatile or entrained material during processing. Gases passed from the hood to an off-gas treatment system where they were treated using a venturi-ejector scrubber, a tandem nozzle gas cleaner scrubber followed by a condenser, heater, and two stages of HEPA filters. The off-gas treatment system is located in the semi-trailer to allow transport of the process to other potential test sites. Retention of all radionuclides by the vitrified zone was greater than 99%. Soil-to-off-gas decontamination factors (DFs) for transuranic elements averaged greater than 4000 and for fission products, DFs ranged from 130 for 137Cs to 3100 for 90Sr. 7 references, 15 figures, 4 tables

  13. Release model for in situ vitrification large-field test off-gas treatment system

    Energy Technology Data Exchange (ETDEWEB)

    Pafford, D.J.; Tung, V.X.

    1992-03-01

    A conceptual model for the vapor and aerosol transport and deposition in the in situ vitrification large-field test off-gas system (OGS) has been developed. This model can be used to predict the emissions from the OGS under normal and off-normal conditions. Results generated by the model can be used to evaluate design and/or procedural modifications, define tests, and predict results. The OGS vapor and aerosol transport and deposition is modeled using the PULSE/MOD-ISV/VER 1.0.0 developmental computer code. Input data requirements for this code include the specific geometries of the OGS components; the composition, rate, and temperature of the vapors and aerosols entering the OGS; and the OGS component surface temperatures or heat fluxes. Currently, not all of these model inputs are available. Therefore, conceptual input parameters are developed. Using this input data, preliminary calculations with the code have been performed. These calculations include a demonstration that the code predicts convergent results, a comparison of predicted results with performance data for one of the OGS components, and a preliminary sensitivity study of the complete model.

  14. Testing and monitoring of off-gas cleanup systems at nuclear facilities

    International Nuclear Information System (INIS)

    This report describes the methods currently employed, especially in nuclear power plants, for testing and monitoring the effectiveness of the cleanup systems installed to limit the emission of radioactive particulate aerosols, gases and vapours to the environment. The report does not generally refer to nuclear reprocessing plants and other nuclear facilities, but the cleaning methods employed there and the requirements for testing and monitoring are often similar to those for nuclear power plants. Particular, arbitrary selected examples are used to indicate some of the differences, but details will not usually be given. Chapter 1 describes the various particulate and gaseous emissions and the appropriate cleanup systems. The quantities of particulate aerosols and gaseous effluents released in normal operation are also given. Chapters 2-5 refer to different aspects of cleanup systems, namely particulate filter testing, iodine sorption system testing, noble gas delay system testing, and process control and performance monitoring. References are given to examples of national or operating agency standards. Chapter 6 deals with the criteria by which the performance of cleanup systems is evaluated. It is important that the individual plant criteria or limits should be seen in the context of the ICRP requirements. The general design objectives of nuclear plants aim at fulfilling ICRP recommendations and the ALARA principle. Chapter 7 draws attention to the further development of the technology of cleanup system testing and monitoring. The cost of designing, building, monitoring and testing a nuclear off-gas cleaning system is not inconsiderable. The impact of this economic pressure on system design and testing methods should not be underestimated. Finally, the report is summarized and a number of conclusions are given, together with recommendations for further international co-operation

  15. 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

  16. Development and testing of prototype alpha waste incinerator off-gas systems

    International Nuclear Information System (INIS)

    A test program is in progress at Savannah River Laboratory (SRL) to confirm and develop incinerator design technology for an SRP production Alpha Waste Incinerator (AWI) to be built in the mid-1980's. The Incinerator Components Test Facility (ICTF) is a full-scale (5 kg/h), electrically heated, controlled-air prototype incinerator built to burn nonradioactive solid waste. The incinerator has been operating successfully at SRL since March 1979 and has met or exceeded all design criteria. During the first 1-1/2 years of operation, liquid scrubbers were used to remove particulates and hydrochloric acid from the incinerator exhaust gases. A dry off-gas system is currently being tested to provide data to Savannah River Plant's proposed AWI

  17. 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

  18. Testing an iodine filter for the vessel off-gas of the German industrial-scale reprocessing plant

    International Nuclear Information System (INIS)

    An extensive retention of the iodine (iodine 129 and iodine 131) is required in the German industrial-scale reprocessing plant to be erected at Wackersdorf. This calls for iodine retention both in the dissolver off-gas and in the vessel off-gas. Various sorption materials have been tested under realistic conditions in the Karlsruhe Reprocessing Plant (WAK) in cooperation with The Karlsruhe Nuclear Research Center. The good laboratory results achieved with the AC 6129 material justified construction of an iodine filter for the vessel off-gas. The filter has been operated since October 1987 and exposed to a 10% side stream (10% iodine filter); the decontamination factor (DF) obtained is > 50. Based on this experience, it is envisaged to equip the WAK vessel offgas cleaning systems as from 1989 with iodine filters. From this measure and from iodine filtration in the dissolver off-gas applied since 1975, an iodine decontamination factor exceeding 500 for the total off-gas discharged is expected

  19. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Jarosch, T.R.; Haselow, J.S.; Rossabi, J.; Burdick, S.A.; Raymond, R.; Young, J.E.; Lombard, K.H.

    1995-01-23

    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.

  1. 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.

  2. Removal efficiency of silver impregnated filter materials and performance of iodie filters in the off-gas of the Karlsruhe reprocessing plant WAK

    Energy Technology Data Exchange (ETDEWEB)

    Herrmann, F.J.; Herrmann, B.; Hoeflich, V. [Wiederaufarbeitungsanlage Karlsruhe (Germany)] [and others

    1997-08-01

    An almost quantitative retention of iodine is required in reprocessing plants. For the iodine removal in the off-gas streams of a reprocessing plant various sorption materials had been tested under realistic conditions in the Karlsruhe reprocessing plant WAK in cooperation with the Karlsruhe research center FZK. The laboratory results achieved with different iodine sorption materials justified long time performance tests in the WAK Plant. Technical iodine filters and sorption materials for measurements of iodine had been tested from 1972 through 1992. This paper gives an overview over the most important results, Extended laboratory, pilot plant, hot cell and plant experiences have been performed concerning the behavior and the distribution of iodine-129 in chemical processing plants. In a conventional reprocessing plant for power reactor fuel, the bulk of iodine-129 and iodine-127 is evolved into the dissolver off-gas. The remainder is dispersed over many aqueous, organic and gaseous process and waste streams of the plant. Iodine filters with silver nitrate impregnated silica were installed in the dissolver off-gas of the Karlsruhe reprocessing plant WAK in 1975 and in two vessel vent systems in 1988. The aim of the Karlsruhe iodine research program was an almost quantitative evolution of the iodine during the dissolution process to remove as much iodine with the solid bed filters as possible. After shut down of the WAK plant in December 1990 the removal efficiency of the iodine filters at low iodine concentrations had been investigated during the following years. 12 refs., 2 figs., 2 tabs.

  3. Laboratory Scoping Tests Of Decontamination 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 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 (99Tc). 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 129I, 90Sr, 137Cs, and 241Am. This report discusses results of preliminary radionuclide decontamination testing of the simulant. Testing examined use of Monosodium Titanate (MST) to remove 90Sr and actinides, inorganic reducing agents for 99Tc, and zeolites for 137Cs. Test results indicate that excellent removal of 99Tc was achieved using Sn(II)Cl2 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 alkaline pH, with a DF of 17.9. As anticipated, ammonium ion probab

  4. 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

  5. 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

  6. 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.

  7. Dissolver off-gas cleaning in a reprocessing plant

    International Nuclear Information System (INIS)

    To demonstrate an advanced dissolver off-gas cleaning system, the PASSAT filter system and the WAESCHE off-gas simulation facility have been developed, constructed under licensing conditions pertinent to industrial scale reprocessing plants, and commissioned for trial operation. Major components of the PASSAT off-gas-cleaning system include the series-connected iodine-adsorption filters, for optimum utilization of the iodine-adsorption material, AC 6120, and also the packed-fiber mist eliminator, which has a flushing capability for initial removal of droplets and particles and which was installed to extend the service life of the HEPA filter. The tests performed so far and the experience accumulated in testing these remotely operated filter components under simulated dissolver off-gas conditions, are described and discussed

  8. 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

  9. Dissolution tests of spent fuel in the NUCEF ??-cell including dissolver off-gas treatment

    International Nuclear Information System (INIS)

    Dissolution tests of 8,000 MWd/t PWR spent fuel were carried out in the ?? cell of NUCEF as the first stage of a series of experimental works using spent fuels. The present dissolution tests included dissolution of 1.5 kg of the spent fuel, iodine treatment using AgS(silver impregnated silica gel), clarification, and preparation of dissolver solution for the extraction tests following the dissolution tests. Capture of carbon-14 was also studied in the dissolution tests. Dissolution behavior was studied by the concentration measurement of U, Pu, gamma species (Cs-134 and Cs-137, Eu-154 and Eu-155, Am-241), and other fission products (Sr, Ba, Zr, Mo, Ru, La, Ce, Nd, Sm and Pr). Insoluble residue was also analyzed by sampling and filtering the dissolver solution. In addition, amounts of I-129 and C-14 trapped were measured. Change in U concentration of dissolver solution showed that most of the dissolution of U finished at about 100 minutes after the dissolution was started. Dissolution behavior of the gamma species and FPs were shown to be almost the same as the U dissolution behavior. Iodine was removed from the dissolver solution at the iodine stripping tank in two steps. Total amount of iodine-129 trapped in AgS columns during the tests was found to be 2.10 x 105 Bq which corresponded to about 63% of the iodine-129 amount estimated by ORIGEN calculation. Amount of carbon-14 was measured to be about 2 x 106 Bq, which suggested that at least several ppms of nitrogen-14 was initially contained in the fuel as impurity. Analysis of insoluble residue showed that Ru, Mo, Pd, and Zr were major elements contained. The molar ratio between Mo and Zr contained in the residue and the X-ray diffractometry of residue suggested that zirconium molybdate precipitated during the dissolution. The dissolution tests successfully recovered about 94% of U amount contained initially in spent fuel. The U and nitric acid concentrations of the U product, which was used in the extraction tests, were 291.6 gU/L and 3.23 N, respectively. (author)

  10. Laboratory optimization tests of technetium decontamination of Hanford Waste Treatment Plant low activity waste melter off-gas condensate simulant

    Energy Technology Data Exchange (ETDEWEB)

    Taylor-Pashow, Kathryn M.L. [Savannah River Site (SRS), Aiken, SC (United States); McCabe, Daniel J. [Savannah River Site (SRS), Aiken, SC (United States)

    2015-11-01

    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 simplified 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.

  11. Dissolver off-gas cleaning in reprocessing plants: testing and operation of mist eliminators, HEPA and iodine filters

    International Nuclear Information System (INIS)

    A dissolver off-gas filter section with remotely handled filter components was designed, built and has been operated on trial since 1978 as a prototype for the head-end of a reprocessing plant; it attains a decontamination factor >=105 for droplet aerosols and particulates. It was supposed that about 0.1% of the ?-emitters of the dissolved, cut fuel is carried away as aerosols and more than 99% of the fission product iodine are transported as gas in the off-gas. The major components of the filter system for dissolver off-gas cleaning, PASSAT, include: the simulation system for the dissolver off-gas throughput 50-250 msub(n)3/h, with the feeds for vapor, aerosols (droplets and particulates), nitric oxides and iodine; the wave plate separator for droplets >10 ?m; the fiber pack mist eliminator (remotely operated) for mist elimination; the HEPA filter (remotely operated) for the removal of salt particles; and the two series-connected iodine sorption filters equipped with the inorganic iodine sorption material AC 6120 (remotely operated)

  12. Results of cleaning dissolver off-gas in the PASSAT prototype dissolver off-gas filter system

    International Nuclear Information System (INIS)

    For demonstration of an advanced dissolver off-gas cleaning system the new PASSAT filter system has been developed, set up under licensing conditions pertinent to industrial scale reprocessing facilities and commissioned for trial operation. Major components of the PASSAT off-gas cleaning system are the packed fiber mist eliminator with flushing capability (Brink filter) for initial removal of droplet and solid aerosols, which has been installed to extend the service life of HEPA filters, and the series connected iodine adsorption filters for optimum utilization of the iodine adsorption material, AC 6120. The tests performed so far and the experience accumulated in testing these remotely operated filter components under simulated dissolver off-gas conditions, are described and discussed

  13. Advanced Fuel Cycle Initiative Coupled End-to-End Research,Development and Demonstration Project: Integrated Off-gas Treatment System Design and Initial Performance - 9226

    International Nuclear Information System (INIS)

    Oak Ridge National Laboratory is conducting a complete, coupled end-to-end (CETE) demonstration of advanced nuclear fuel reprocessing to support the Advanced Fuel Cycle Initiative. This small-scale reprocessing operation provides a unique opportunity to test integrated off-gas treatment systems designed to recover the primary volatile fission and activation products (H-3, C-14, Kr-85, and I-139) released from the spent nuclear fuel (SNF). The CETE project will demonstrate an advanced head-end process, referred to as voloxidation, designed to condition the SNF, separate the SNF from the cladding, and release tritium contained in the fuel matrix. The off-gas from the dry voloxidation process as well as from the more traditional fuel dissolution process will be treated separately and the volatile components recovered. This paper provides descriptions of the off-gas treatment systems for both the voloxidation process and for the fuel dissolution process and provides preliminary results from the initial CETE processing runs. Impacts of processing parameters on the relative quantities of volatile components released and recovery efficiencies are evaluated.

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

    Energy Technology Data Exchange (ETDEWEB)

    Adamson, M G; Hsu, P C

    1999-05-01

    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 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.

  15. 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 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

  16. 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)

  17. LIBS: Application to toxic metal concentration measurements in a plasma torch off-gas emission system

    International Nuclear Information System (INIS)

    Laser-Induced Breakdown Spectroscopy (LIBS) has been used to monitor the metal concentrations of the off-gas system of a 250 kW plasma treatment system during vitrification of a Savannah River surrogate waste. LIBS spectra of different elements in the off-gas emission have been recorded in various spectral regions to select the appropriate spectral lines for the concentration measurements. The LIBS concentration measurement were then performed at different test run conditions. The results of various measurements are presented. These measurements demonstrated LIBS's capability for real-time toxic metal monitoring

  18. 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

  19. Clinoptilolite filter for the decontamination of radioactive off-gas

    International Nuclear Information System (INIS)

    A small scale burning apparatus and a fluidized bed filter filled with a sand or a clinoptilolite were made and the decontamination properties were tested. It was found that the off-gas cleaning by the passage through a clinoptilolite filter was advantageous than a sand filter and the overall decontamination factor for 32P was 3.6 x 106. The dusts or aerosols in the off-gas accompanying with moisture and radioisotope could be easily caught onto the surface or the cavities of the clinoptilolite. (auth.)

  20. CHARACTERIZATION OF DWPF MELTER OFF-GAS QUENCHER SAMPLE

    Energy Technology Data Exchange (ETDEWEB)

    Newell, J.

    2011-11-14

    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 {approx}750 C to {approx}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 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.

  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 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. 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.

  3. 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.

  4. 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

  5. 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.

  6. Sorption Modeling and verification for Off-Gas Treatment

    Energy Technology Data Exchange (ETDEWEB)

    Tavlarides, Lawrence L. [Syracuse Univ., NY (United States); Lin, Ronghong [Syracuse Univ., NY (United States); Nan, Yue [Syracuse Univ., NY (United States); Yiacoumi, Sotira [Georgia Inst. of Technology, Atlanta, GA (United States); Tsouris, Costas [Georgia Inst. of Technology, Atlanta, GA (United States); Ladshaw, Austin [Georgia Inst. of Technology, Atlanta, GA (United States); Sharma, Ketki [Georgia Inst. of Technology, Atlanta, GA (United States); Gabitto, Jorge [Prairie View A & M Univ., Prairie View, TX (United States); DePaoli, David [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    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.

  7. Spent fuel dissolution test including dissolver off-gas treatment in the NUCEF (Nuclear Fuel Cycle Safety Engineering Facility) alpha-gamma cell: Spent fuels with burnups up to 44 GWDT-1

    International Nuclear Information System (INIS)

    Spent fuel dissolution test was carried out to study the dissolution behavior of nuclides and the behavior of volatile nuclides, using a bench-scale reprocessing test rig in the NUCEF alpha-gamma cell. 29 and 44 GWdt-1 spen fuels were respectively dissolved. Study on the dissolution behavior showed that the dissolution rate of uranium and plutonium were similar. Also, other species: Cesium, Americium, Strontium and Neodymium were found to dissolve in the similar manor to uranium. The fraction of Mo dissolved was found to decrease during the dissolution. Zirconium molybdate (Zr(Mo2O7)(OH)2(H2O)2) was identified from the XRD pattern of residue in the 29 GWdt-1 spent fuel dissolution. Those results suggested the precipitation of the hydrate during dissolution. As for the iodine-129 removal, decontamination factor of AGS (silica-gel impregnated with silver nitrate) column was more than 36,000. Measurement of iodine-129 in the dissolver solution revealed that less than 0.57% of total iodine-129 generated, which was estimated by ORIGEN II calculation, was remained in the dissolver solution. Also, measurement of iodine-129 by an iodine-stripping operation from dissolver solution using potassium iodate suggested that another 2.72% of total iodine-129 precipitated as iodide. In addition, about 70% of total iodine generated was measured in the AGS columns. Rest of iodine-129 was supposed to adsorb to the HEPA filter and the inner surface of dissolver off-gas lines. Those results on iodine-129 distribution were found to be almost identical to the results obtained in the study using iodine-131 as tracer. Release of carbon-14 as carbon dioxide during dissolution was found to occur when the release of Kr-85. From the measurement of carbon-14, initial nitrogen-14 concentration in the fuel was estimated to be about several ppms, which was within the range reported. (author)

  8. 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.

  9. Adsorption Model for Off-Gas Separation

    International Nuclear Information System (INIS)

    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.

  10. 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...

  11. Literature review: Assessment of DWPF melter and melter off-gas system lifetime

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-30

    A glass melter for use in processing radioactive waste is a challenging environment for the materials of construction (MOC) resulting from a combination of high temperatures, chemical attack, and erosion/corrosion; therefore, highly engineered materials must be selected for this application. The focus of this report is to review the testing and evaluations used in the selection of the Defense Waste Processing Facility (DWPF), glass contact MOC specifically the Monofrax® K-3 refractory and Inconel® 690 alloy. The degradation or corrosion mechanisms of these materials during pilot scale testing and in-service operation were analyzed over a range of oxidizing and reducing flowsheets; however, DWPF has primarily processed a reducing flowsheet (i.e., Fe2+/?Fe of 0.09 to 0.33) since the start of radioactive operations. This report also discusses the materials selection for the DWPF off-gas system and the corrosion evaluation of these materials during pilot scale testing and non-radioactive operations of DWPF Melter #1. Inspection of the off-gas components has not been performed during radioactive operations with the exception of maintenance because of plugging.

  12. Literature review: Assessment of DWPF melter and melter off-gas system lifetime

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-30

    A glass melter for use in processing radioactive waste is a challenging environment for the materials of construction (MOC) resulting from a combination of high temperatures, chemical attack, and erosion/corrosion; therefore, highly engineered materials must be selected for this application. The focus of this report is to review the testing and evaluations used in the selection of the Defense Waste Processing Facility (DWPF), glass contact MOC specifically the Monofrax® K-3 refractory and Inconel® 690 alloy. The degradation or corrosion mechanisms of these materials during pilot scale testing and in-service operation were analyzed over a range of oxidizing and reducing flowsheets; however, DWPF has primarily processed a reducing flowsheet (i.e., Fe2+/?Fe of 0.09 to 0.33) since the start of radioactive operations. This report also discusses the materials selection for the DWPF off-gas system and the corrosion evaluation of these materials during pilot scale testing and non-radioactive operations of DWPF Melter #1. Inspection of the off-gas components has not been performed during radioactive operations with the exception of maintenance because of plugging.

  13. Iodine-129 process control monitor for evaporator off-gas streams

    International Nuclear Information System (INIS)

    The continuous monitoring of gaseous 129I in evaporator off-gas at nuclear fuel reprocessing facilities is desirable from both regulatory and process control viewpoints. Although a continuous 129I monitor for nuclear fuel reprocessing plant off-gas streams has already been developed, it needed to be evaluated under evaporator off-gas conditions. Characteristics of the off-gas that pose problems for 129I monitoring include: (1) high concentrations of nitric acid mist, organics, and radionuclides which may interfere with 129 detection, such as 137Cs; (2) off-gas that is predominantly water vapor; and (3) 129I in the form of liquid aerosols. The development and evaluation of an 129I monitor for evaporator off-gas using a laboratory-scale evaporator model are reported. The work was performed in two phases: 1) a suitable monitor configuration was determined; and 2) a 24 factorial design experiment was performed to determine the monitor's response to HNO3, organics, aerosols, and 137Cs. A filter was used in the monitor configuration to vary aerosol concentrations. The concentrations of HNO3, organics, and 137Cs in the evaporator feed were also varied from low to high levels. In the experimental monitor, an H2O selective permeation device was used to dry the off-gas stream before it passed through a charcoal bed where the iodine was adsorbed. The bed was counted for 125I with a NaI(Tl) detector. Results of this study show that the monitor should be operated with a filter. Based on these observations, the monitor when operated with a filter, was demonstrated to be suitable for use in evaporator off-gas streams

  14. Design of an Engineering Scale Off-gas Trapping System for Capturing Semi-volatile Nuclides

    International Nuclear Information System (INIS)

    Design of an engineering-scale trapping system to be used in PRIDE (Pyroprocess Integrated Inactive Demonstration) facility of KAERI to remove semi-volatile fission gases generated from the advanced vololoxdation process of 50 kg-SF/batch was performed. The design was performed to produce flow diagram for the off-gas trapping system. The gaseous waste arisings for off-gas trapping system was estimated considering the release rate of each target fission product. To design the off-gas trapping system, zero release concept was taken to the environment through off-gas trapping system. Each unit process in the trapping system is arranged to effectively remove the species of interest by considering the chemical properties of the target fission products to be trapped. Cs and Rb are trapped on a fly ash filter at around 900 .deg. C. Tc, Te, Se, and Mo on a calcium filter are trapped at about 700 .deg. C, and I on a AgX is trapped at about 250 .deg. C. Off-gas trapping system was designed based on the design requirements such as trapping media, fission products to be trapped, design temperatures of the trapping units, optimum operation temperatures and specifications of the filters. Off-gas trapping system was also designed based on the design requirements such as reomoteability, accessibility, operationability and flexibility of instrument, separability of trapping basket, material of instrument

  15. 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)

  16. Network Performance Testing Tool

    CERN Document Server

    Antonella, Goncalves

    2013-01-01

    To have a reliable network , it is important to test the network performance throughout the network devices. This is the reaon why, we developped a tool to test Atlas TDAQ network performance after the purchase of new Brocades devices.

  17. Adsorptive krypton separation from dissolver off-gas with consideration of trace impurities

    International Nuclear Information System (INIS)

    A process has been developed for separating Kr-85 from dissolving vessel off-gas entirely by means of adsorption. The krypton is adsorbed together with other contaminants onto activated charcoal at very low temperatures. In a subsequent chromatography process, with helium as purge gas, the off-gas contaminants are divided into individual fractions. Laboratory studies with an off-gas throughput of 1 Nm3/h were carried out to investigate operational parameters and the behaviour of trace contaminants in the off-gas purification system. It emerged from the test that if, for purposes of simplification, the dimensions are assumed to increase proportionally, an industrial-scale plant with a throughput of 100 Nm3/h would need a total column volume of at least 200 1 activated charcoal and minimum volume of helium corresponding to 4% of the total off-gas volume. This would result in krypton separation with a decontamination factor of >= 2000 and a purity of >= 98%. The xenon fraction can also be determined individually, but this would mean an increase in costs and the equipment required. Traces of CH4 remain in the Kr fraction and thus do not accumulate in the system. CO2 and N2O can be separated or allowed to remain in the xenon fraction. The radiolysis products O3 and NOsub(x) are not expected to pose any problems. (author)

  18. 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.

  19. 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.

  20. 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.

  1. 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 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

  2. Development of silver impregnated alumina for iodine separation from off-gas streams

    Energy Technology Data Exchange (ETDEWEB)

    Funabashi, Kiyomi; Fukasawa, Tetsuo; Kikuchi, Makoto [Energy Research Laboratory, Hitachi (Japan)] [and others

    1995-02-01

    An inorganic iodine adsorbent, silver impregnated alumina (AgA), has been developed to separate iodine effectively from off-gas streams of nuclear facilities and to decrease the volume of waste (spent adsorbent). Iodine removal efficiency was improved at relatively high humidity by using alumina carrier with two different pore diameters. Waste volume reduction was achieved by impregnating relatively large amounts of silver into the alumina pores. The developed adsorbent was tested first with simulated off-gas streams under various experimental conditions and finally with actual off-gas streams of the Karlsruhe reprocessing plant. The decontamination factor (DF) was about 100 with the AgA bed depth of 2cm at 70% relative humidity, which was a DF one order higher than that when AgA with one pore size was used. Iodine adsorption capacity was checked by passing excess iodine into the AgA bed. Values were about 0.12 and 0.35 g-I/cm`-AgA bed for 10 and 24wt% silver impregnated AgA, respectively. The results obtained in this study demonstrated the applicability of the developed AgA to the off-gas treatment system of nuclear facilities.

  3. Development of silver impregnated alumina for iodine separation from off-gas streams

    International Nuclear Information System (INIS)

    An inorganic iodine adsorbent, silver impregnated alumina (AgA), has been developed to separate iodine effectively from off-gas streams of nuclear facilities and to decrease the volume of waste (spent adsorbent). Iodine removal efficiency was improved at relatively high humidity by using alumina carrier with two different pore diameters. Waste volume reduction was achieved by impregnating relatively large amounts of silver into the alumina pores. The developed adsorbent was tested first with simulated off-gas streams under various experimental conditions and finally with actual off-gas streams of the Karlsruhe reprocessing plant. The decontamination factor (DF) was about 100 with the AgA bed depth of 2cm at 70% relative humidity, which was a DF one order higher than that when AgA with one pore size was used. Iodine adsorption capacity was checked by passing excess iodine into the AgA bed. Values were about 0.12 and 0.35 g-I/cm'-AgA bed for 10 and 24wt% silver impregnated AgA, respectively. The results obtained in this study demonstrated the applicability of the developed AgA to the off-gas treatment system of nuclear facilities

  4. 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

  5. Test and Performance Anxiety

    Science.gov (United States)

    Huberty, Thomas J.

    2010-01-01

    Test and performance anxiety is not recognized easily in schools, in large part because adolescents rarely refer themselves for emotional concerns. Not wanting to risk teasing or public attention, anxious adolescents suffer in silence and under perform on school-related tasks. In school, anxiety is experienced often by students when being…

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

    Energy Technology Data Exchange (ETDEWEB)

    Flament, T.A.

    1998-08-25

    Several configurations have been reviewed for the NO{sub x} 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 NO{sub x} 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.

  7. 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

  8. Iodine Sorbent Performance in FY 2012 Deep Bed Tests

    Energy Technology Data Exchange (ETDEWEB)

    Nick Soelberg; Tony Watson

    2012-08-01

    Nuclear fission results in the production of fission products and activation products, some of which tend to be volatile during used fuel reprocessing and evolve in gaseous species into the reprocessing facility off-gas systems. Analyses have shown that I-129, due to its radioactivity, high potential mobility in the environment, and high longevity (half life of 15.7 million years), can require control efficiencies of up to 1,000x or higher to meet regulatory emission limits. Iodine capture is an important aspect of the Separations and Waste Forms Campaign Off-gas Sigma Team (Jubin 2011, Pantano 2011). Deep-bed iodine sorption tests for both silver-functionalized Aerogel and silver zeolite sorbents were performed during Fiscal Year 2012. These tests showed that: • Decontamination factors were achieved that exceed reasonably conservative estimates for DFs needed for used fuel reprocessing facilities in the U.S. to meet regulatory requirements for I-129 capture. • Silver utilizations approached or exceeded 100% for high inlet gas iodine concentrations, but test durations were not long enough to approach 100% silver utilization for lower iodine concentrations. • The depth of the mass transfer zone was determined for both low iodine concentrations (under 10 ppmv) and for higher iodine concentrations (between 10-50 ppmv); the depth increases over time as iodine is sorbed. • These sorbents capture iodine by chemisorption, where the sorbed iodine reacts with the silver to form very non-volatile AgI. Any sorbed iodine that is physisorbed but not chemically reacted with silver to form AgI might not be tightly held by the sorbent. The portion of sorbed iodine that tends to desorb because it is not chemisorbed (reacted to form AgI) is small, under 1%, for the AgZ tests, and even smaller, under 0.01%, for the silver-functionalized Aerogel.

  9. 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.

  10. Iodine-129 process control monitor for evaporator off-gas streams

    International Nuclear Information System (INIS)

    Continuous monitoring of gaseous 129I in evaporator off-gas at nuclear fuel reprocessing facilities is important from both regulatory and process control viewpoints. Accordingly, continuous monitoring of evaporator overheads would supply the necessary information to retain 129I in the evaporator bottoms should a process control mechanism for the evaporator be developed. Although a continuous 129I monitor for nuclear fuel reprocessing plant off-gas streams has already been developed, monitoring of evaporator overheads presents unique problems for 129I monitoring, including 129I in the form of liquid aerosols, high concentrations of nitric acid mist and organics, and high concentrations of other radionuclides such as 137Cs. The off-gas is also predominantly water vapor. A two-phase laboratory study was completed. First, the proper configuration to successfully detect 129I was examined. Second, a 24 factorial design experiment was performed to determine the monitor's response to aerosols, organics, HNO3, and 137Cs. Both response and variability for the monitor were determined. Major conclusions were: the presence of HNO3 had no statistically significant effect on the response of the monitor; the presence of TBP significantly increased the response of the monitor; the use of a filter, corresponding to low aerosol conditions, significantly increased the response of the monitor. A filter should be used because the decreased monitor response if the filter is not used (high aerosol conditions); under conditions of the experiments, 137Cs remained in the evaporator bottoms; and no effect of 137Cs on the monitor was observed; and the variability of the monitor was not significantly affected by the filter, TBP, HNO3, or 137Cs. The monitor when used with a filter, was considered suitable for use in evaporator off-gas streams

  11. 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.

  12. Design of off-gas and air cleaning systems at nuclear power plants

    International Nuclear Information System (INIS)

    The primary purpose of this report is to describe the current design of air and process off-gas cleaning technologies used in nuclear power plants (NPPs). Because of the large inventory of fission products that are produced in the fuel (i.e. in the range of 5x1019Bq per GW(e)·a) and the highly restrictive airborne radionuclide release limits being established by Member States, air and process off-gas cleaning technologies are constantly being improved to provide higher airborne radionuclide recovery efficiencies and a smaller probability of malfunction. For various technologies considered an attempt has been made to provide the following information: (a) Process description in terms of principles of off-gas and air cleaning, operating parameters and system performance; (b) Design for normal and accident situations; (c) Design of components with regard to construction materials, size, shape and geometry of the system, resistance to chemical and physical degradation from the operational environment, safety and quality assurance requirements

  13. Continuous chemical cold traps for reprocessing off-gas purification

    International Nuclear Information System (INIS)

    Absorption of nitrogen oxides and iodine from simulated reprocessing plant off-gas streams has been studied using nitric acid and nitric acid/hydrogen peroxide mixtures at low temperatures. The experiments were carried out at the laboratory and on the engineering scale. The pilot plant scale column has 0.8 m diameter and 16 absorption plates at 0.2 m spacing. Cooling coils on the plates allow operating temperatures down to -600C. The NO concentration in the feed gas usually has been 1% by volume and the flow rate 4-32 m3 (STP) per hour. The iodine behavior has been studied using I-123 tracer. Results of the study are presented. The chemistry of the processes and the advantages and disadvantages in correlation to the various applications for an off-gas purification in a reprocessing plant are compared and discussed. The processes are compatible with the PUREX process and do not produce additional waste

  14. Treatment of off-gas from lagoon sludge thermal decomposition

    International Nuclear Information System (INIS)

    Korea Atomic Energy Research Institute (KAERI) has launched a decommissioning program of the uranium conversion plant in 2001. The treatment of the sludge waste, which was generated during the operation of the plant and stored in the lagoon, is one of the most important tasks in the decommissioning program of the plant. The major compounds of the lagoon sludge are ammonium nitrate, sodium nitrate, calcium nitrate, calcium carbonate, and uranium compounds. The minor compounds are iron, magnesium, aluminum, silicon and phosphorus. A treatment process of the sludge was developed as figure 1 based on the results of the sludge characteristics and the developed treatment technologies. A treatment of off-gas evolved from the nitrate salts thermal decomposition is one of the important process. Off-gas treatment by using a selective catalytic reduction (SCR) method was investigated in this study

  15. 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 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.

  16. 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)

  17. Avoiding Carbon Bed Hot Spots in Thermal Process Off-Gas Systems

    Energy Technology Data Exchange (ETDEWEB)

    Nick Soelberg; Joe Enneking

    2011-05-01

    Mercury has had various uses in nuclear fuel reprocessing and other nuclear processes, and so is often present in radioactive and mixed (radioactive and hazardous) wastes. Test programs performed in recent years have shown that mercury in off-gas streams from processes that treat radioactive wastes can be controlled using fixed beds of activated sulfur-impregnated carbon, to levels low enough to comply with air emission regulations such as the Hazardous Waste Combustor (HWC) Maximum Achievable Control Technology (MACT) standards. Carbon bed hot spots or fires have occurred several times during these tests, and also during a remediation of tanks that contained mixed waste. Hot spots occur when localized areas in a carbon bed become heated to temperatures where oxidation occurs. This heating typically occurs due to heat of absoption of gas species onto the carbon, but it can also be caused through external means such as external heaters used to heat the carbon bed vessel. Hot spots, if not promptly mitigated, can grow into bed fires. Carbon bed hot spots and fires must be avoided in processes that treat radioactive and mixed waste. Hot spots are detected by (a) monitoring in-bed and bed outlet gas temperatures, and (b) more important, monitoring of bed outlet gas CO concentrations. Hot spots are mitigated by (a) designing for appropriate in-bed gas velocity, for avoiding gas flow maldistribution, and for sufficient but not excessive bed depth, (b) appropriate monitoring and control of gas and bed temperatures and compositions, and (c) prompt implementation of corrective actions if bed hot spots are detected. Corrective actions must be implemented quickly if bed hot spots are detected, using a graded approach and sequence starting with corrective actions that are simple, quick, cause the least impact to the process, and are easiest to recover from.

  18. 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.

  19. Cooler and particulate separator for an off-gas stack

    Science.gov (United States)

    Wright, George T. (15 Cherry Hills Dr., Aiken, SC 29803)

    1992-01-01

    An off-gas stack for a melter comprising an air conduit leading to two sets of holes, one set injecting air into the off-gas stack near the melter plenum and the second set injecting air downstream of the first set. The first set injects air at a compound angle, having both downward and tangential components, to create a reverse vortex flow, counter to the direction of flow of gas through the stack and also along the periphery of the stack interior surface. Air from the first set of holes pervents recirculation zones from forming and the attendant accumulation of particulate deposits on the wall of the stack and will also return to the plenum any particulate swept up in the gas entering the stack. The second set of holes injects air in the same direction as the gas in the stack to compensate for the pressure drop and to prevent the concentration of condensate in the stack. A set of sprayers, receiving water from a second conduit, is located downstream of the second set of holes and sprays water into the gas to further cool it.

  20. Investigation on volume reduction of off gas filtrating element

    International Nuclear Information System (INIS)

    Methods for volume reduction of the spent filtrating elements, which are installed in the off gas equipment of the high active waste treatment process, were investigated. Volume reduction of those spent filtrating elements is very important because the activities of them are supposed to be higher than that of the elements of other off gas systems. In this work, melting method of volume reduction for a glass fiber and silica gel beads, which were not so suitable for pressurized compaction, were studied. The major portion of the glass fiber for a mist filter consists of SiO2, B2O3 and some other components and the silica gel beads for a ruthenium adsorption column is composed of SiO2. The spent filtrating materials mentioned above will be possible to reuse as the glass former materials because both SiO2 and B2O3 are the major constituents of the borosilicate glass former that will be used in a vitrification process of high active liquid waste. After the composition of the glass fiber was adjusted to that of the borosilicate glass former, the volume reducing ratio of the melted glassy product and the initial glass fiber was about 15 vol. %. On the other hand, the silica gel beads were not melted in case of unadjusted composition, but melted into homogenized glass in case of adjusted composition. And then, the volume reducing ratio of the melted glassy product and the initial silica gel beads was about 23 vol%

  1. Cooler and particulate separator for an off-gas stack

    Science.gov (United States)

    Wright, G.T.

    1991-04-08

    This report describes an off-gas stack for a melter, furnace or reaction vessel comprising an air conduit leading to two sets of holes, one set injecting air into the off-gas stack near the melter plenum and the second set injecting air downstream of the first set. The first set injects air at a compound angle, having both downward and tangential components, to create a reverse vortex flow, counter to the direction of flow of gas through the stack and also along the periphery of the stack interior surface. Air from the first set of holes prevents recirculation zones from forming and the attendant accumulation of particulate deposits on the wall of the stack and will also return to the plenum any particulate swept up in the gas entering the stack. The second set of holes injects air in the same direction as the gas in the stack to compensate for the pressure drop and to prevent the concentration of condensate in the stack. A set of sprayers, receiving water from a second conduit, is located downstream of the second set of holes and sprays water into the gas to further cool it.

  2. 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

  3. 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

  4. 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

  5. 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.)

  6. Thoron filter design for the off-gas line of the ITREC reprocessing plant

    International Nuclear Information System (INIS)

    Operational tests of the ITREC reprocessing plant have shown some problems on the monitoring of beta-gamma emitters at the stack; the alarm threshold was reached within a few minutes, from the beginning of the fuel reprocessing steps. Nevertheless, this getting over was not attributable to beta - gamma emitter particulates which were not retained by the absolute filters of the off-gas line, but to the interference of the short lived radioactive particulate thoron daughters for which the limit of discharge is a thousand times higher. With the aim of avoiding such spurious alarms the authors examined the possibility of inserting a charcoal delay bed for reducing thoron concentration to an acceptable level by natural decay. The decontamination factor that the decay bed must satisfy depends on the decay constant of 220Rn and daughters. This can be evaluated from the characteristics of the measuring device on the basis of the off-gas flow rate, stack flow rate and monitoring line sampling flow rate. Dynamic adsorption characteristics of a selected charcoal were experimentally determined by the pulse technique and are reported in this paper. Finally sizing criteria are outlined and the filter design is shown

  7. ASSESSMENT OF THE IMPACT OF TOA PARTITIONING ON DWPF MELTER OFF-GAS FLAMMABILITY

    Energy Technology Data Exchange (ETDEWEB)

    Daniel, G.

    2013-06-18

    An assessment has been made to evaluate the impact on the DWPF melter off-gas flammability of increasing the amount of TOA in the current solvent used in the Modular Caustic-Side Solvent Extraction Process Unit (MCU) process. The results of this study showed that the concentrations of nonvolatile carbon of the current solvent limit (150 ppm) in the Slurry Mix Evaporator (SME) product would be about 7% higher and the nonvolatile hydrogen would be 2% higher than the actual current solvent (126 ppm) with an addition of up to 3 ppm of TOA when the concentration of Isopar? L in the effluent transfer is controlled below 87 ppm and the volume of MCU effluent transfer to DWPF is limited to 15,000 gallons per Sludge Receipt and Adjustment Tank (SRAT)/SME cycle. Therefore, the DWPF melter off-gas flammability assessment is conservative for up to an additional 3 ppm of TOA in the effluent based on these assumptions. This report documents the calculations performed to reach this conclusion.

  8. 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.

  9. 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.

  10. 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

  11. 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

  12. Filters for aerosol and iodine seperation from the dissolver off-gas of a future reprocessing plant

    International Nuclear Information System (INIS)

    For a future German reprocessing plant a dissolver off-gas line is developed at Karlsruhe Nuclear Research Centre, for which the separation of suspended matter and iodine is tested in the pilot plant PASSAT. For a pre-separation of droplets and solid aerosols, a remote-handled fibre package separator has been developed which can be backwashed when installed and which has such dimensions that it fits into a waste barrel and can be removed without any problem. The decontamination factors achieved are above 1,000 for droplet and solid aerosols under suitable differential pressures. Iodine separation is carried out by means of chemical sorption on a special filter containing iodine sorption material and in contrast to the wet scrubbing process, produces a solid, storable product in a single step. It has been possible to gain valuable experience and to obtain data for interpreting a head-end off-gas system. (RB)

  13. Sport performance and agility tests

    OpenAIRE

    Kür?at Karacabey

    2013-01-01

    The purpose of this study is to examine the effect agility on sports performance and agility measurement tests. Agility is described as a rapid whole body movement with change of velocity or direction in response to a stimulus. Good agility requires a combination of speed, balance, power and co-ordination. Agility, which is a motoric ability, can be improved by regular progressive exercise. As an important component, agility is used to be an acceptable method in sports performance test batter...

  14. Proctored and Unproctored Test Performance

    Science.gov (United States)

    Brallier, Sara; Palm, Linda

    2015-01-01

    This study examined test performance as a function of test format (proctored versus unproctored) and course type (traditional versus distance). The participants were 246 undergraduate students who completed introductory sociology courses during four semesters at a southeastern university. During each semester, the same instructor taught a…

  15. 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.

  16. 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 aime...

  17. 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...

  18. The development and design of the off-gas treatment system for the thermal oxide reprocessing plant (THORP) at Sellafield

    International Nuclear Information System (INIS)

    British Nuclear Fuels completed construction of its Thermal Oxide Reprocessing Plant (THORP) at Sellafield in 1992, at a cost of 1,850M. After Government and Regulatory approval, active commissioning was initiated on 17 January 1994. From the outset, the need to protect the workforce, the public and the environment in general from the plant's discharges was clearly recognised. The design intent was to limit radiation exposure of members of the general public to As Low as Reasonably Practicable. Furthermore no member of the most highly exposed group should receive an annual dose exceeding 50 microsieverts from either the aerial or marine discharge routes. This paper describes how the design intent has been met with respect to aerial discharges. It outlines the development programme which was undertaken to address the more demanding aspects of the performance specification. This ranged from small-scale experiments with irradiated fuel to inactive pilot plant trials and full-scale plant measurements. The resulting information was then used, with the aid of mathematical models, in the design of an off-gas treatment system which could achieve the overall goal. The principal species requiring treatment in the THORP off-gas system are iodine-129, carbon-14, nitrogen oxides (NOx), fuel dust particles and aerosols containing plutonium or mixed fission products. The paper describes the combination of abatement equipment used in different parts of the plant, including counter-current absorption columns, electrostatic precipitators, dehumidifiers and High Efficiency Particulate Air filters. Because a number of separate off-gas streams are combined before discharge, special depression control systems were developed which have already proved successful during plant commissioning. BNFL is confident that the detailed attention given to the development and design phases of the THORP off-gas system will ensure good performance when the plant moves into fully radioactive operation

  19. Performance testing for scintillation camera

    International Nuclear Information System (INIS)

    According to the test schedule there are thirteen number of tests to check the performance of a scintillation camera. But due to lack of apparatus, only nine tests were carried out during the study.Preset and manual PHA (Pulse Height Analyzer) window settings were tested using Tc sup 99m, I sup 131 sources and 20 percent window was used. Percentage change in count rate on changing from the manual mode to the present mode was measured. Intrinsic flood-field uniformity of the camera was tested by a point source of Tc sup 99m in solution with 20 percent window width. Values were obtained for useful field-of-view, (UFOV) and central field-of-view (CFOV). Intrinsic flood-field-uniformity over available PHA window widths also tested using a Tc sup 99m source and with 20 percent PHA window. Images were observed for each PHA window using a computer. Tc sup 99m solution containing flood phantom was used to test the system flood-field uniformity with a 20 percent PHA window. Digital image was observed. Flood phantom containing Tc sup 99m in solution and, quadrant bar phantoms were used to test the intrinsic s patial resolution of the camera. Intrinsic spatial resolution in terms of full width at half maximum (FWHM) was measured, also the digital image was observed. System spatial resolution of the camera was also measured and the digital image was observed. The intrinsic count-rate performance of the camera was tested using two point sources of Tc sup 99m. Maximum count- rate of the scintillation camera was measured by varying the distance of the Tc sup 99m point source from the surface of the detector. Finally the total performance of the scintillation camera used for the study was tested using a total performance phantom (Liver slice phantom). Images of liver phantom were observed. (author)

  20. Time-dependent analysis of dissolver off-gas cleaning installations in a reprocessing plant

    International Nuclear Information System (INIS)

    The iodine- and aerosol-filtering test facility PASSAT of the Nuclear Research Centre in Karlsruhe has been investigated using a method which allows time-dependent analyses under accident conditions. This method which is closely related to fault-tree analysis needs subdivision in barriers of the system, and their logical combination in a tree. The barriers have binary states: defect and intact. The defect state will be described by a fault tree, whereas the intact state includes dependences of a barrier operation on physical parameters. The intact state enables time-dependent calculations. Calculations have been done for iodine filtering, because the best known entrance data are given. Results demonstrate clearly that the amount of iodine released increases only if both heaters failed, which heat the off-gas from 300C to 800C and then to 1300C. Additionally the integrated amount of iodine released depends on time period between the failures of the heaters

  1. A plasma process controlled emissions off-gas demonstration

    International Nuclear Information System (INIS)

    Thermal technologies are currently identified as playing an important role in the treatment of many DOE waste streams, and emissions from these processes will be scrutinized by the public, regulators, and stakeholders. For some time, there has been a hesitancy by the public to accept thermal treatment of radioactive contaminated waste because of the emissions from these processes. While the technology for treatment of emissions from these processes is well established, it is not possible to provide the public complete assurance that the system will be in compliance with air quality regulations 100% of the operating time in relation to allowing noncompliant emissions to exit the system. Because of the possibility of noncompliant emissions and the public's concern over thermal treatment systems, it has been decided that the concept of a completely controlled emissions off-gas system should be developed and implemented on Department of Energy (DOE) thermal treatment systems. While the law of conservation of mass precludes a completely closed cycle system, it is possible to apply the complete control concept to emissions

  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. 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.

  4. SBAS ionospheric performance evaluation tests

    OpenAIRE

    Prats Menéndez, Xavier; Orús Pérez, Raül; Sanz Subirana, Jaume; Farnworth, Richard; Soley, Santiago

    2003-01-01

    Satellite Based Augmentation systems (SBAS) provide to Global Navigation Satellite Systems (GNSS) users with an extra set of information, in order to enhance accuracy and integrity levels of GNSS stand alone positioning. In this context, different test methods to analyze the ionospheric corrections performance are presented. The first set of tests involves two of the ionospheric calculations that are applied daily to the Global Ionospheric Maps (GIM), computed by the IGS Associate Analysis Ce...

  5. 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 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

  6. Cryogenic system for collecting noble gases from boiling water reactor off-gas

    International Nuclear Information System (INIS)

    In boiling water reactors, noncondensible gases are expelled from the main condenser. This off-gas stream is composed largely of radiolytic hydrogen and oxygen, air in-leakage, and traces of fission product krypton and xenon. In the Air Products' treatment system, the stoichiometric hydrogen and oxygen are reacted to form water in a catalytic recombiner. The design of the catalytic recombiner is an extension of industrial gas technology developed for purification of argon and helium. The off-gas after the recombiner is processed by cryogenic air-separation technology. The gas is compressed, passed into a reversing heat exchanger where water vapor and carbon dioxide are frozen out, further cooled, and expanded into a distillation column where refrigeration is provided by addition of liquid nitrogen. More than 99.99 percent of the krypton and essentially 100 percent of the xenon entering the column are accumulated in the column bottoms. Every three to six months, the noble-gas concentrate accumulated in the column bottom is removed as liquid, vaporized, diluted with steam, mixed with hydrogen in slight excess of oxygen content, and fed to a small recombiner where all the oxygen reacts to form water. The resulting gas stream, containing from 20 to 40 percent noble gases, is compressed into small storage cylinders for indefinite retention or for decay of all fission gases except krypton-85, followed by subsequent release under controlled conditions and favorable meteorology. This treatment system is based on proven technology that is practiced throughout the industrial gas industry. Only the presence of radioactive materials in the process stream and the application in a nuclear power plant environment are new. Adaptations to meet these new conditions can be made without sacrificing performance, reliability, or safety

  7. Assessment of the impact of the next generation solvent on DWPF melter off-gas flammability

    Energy Technology Data Exchange (ETDEWEB)

    Daniel, W. E.

    2013-02-13

    An assessment has been made to evaluate the impact on the DWPF melter off-gas flammability of replacing the current solvent used in the Modular Caustic-Side Solvent Extraction Process Unit (MCU) process with the Next Generation Solvent (NGS-MCU) and blended solvent. The results of this study showed that the concentrations of nonvolatile carbon and hydrogen of the current solvent in the Slurry Mix Evaporator (SME) product would both be about 29% higher than their counterparts of the NGS-MCU and blended solvent in the absence of guanidine partitioning. When 6 ppm of guanidine (TiDG) was added to the effluent transfer to DWPF to simulate partitioning for the NGS-MCU and blended solvent cases and the concentration of Isopar{reg_sign} L in the effluent transfer was controlled below 87 ppm, the concentrations of nonvolatile carbon and hydrogen of the NGS-MCU and blended solvent were still about 12% and 4% lower, respectively, than those of the current solvent. It is, therefore, concluded that as long as the volume of MCU effluent transfer to DWPF is limited to 15,000 gallons per Sludge Receipt and Adjustment Tank (SRAT)/SME cycle and the concentration of Isopar{reg_sign} L in the effluent transfer is controlled below 87 ppm, using the current solvent assumption of 105 ppm Isopar{reg_sign} L or 150 ppm solvent in lieu of NGS-MCU or blended solvent in the DWPF melter off-gas flammability assessment is conservative for up to an additional 6 ppm of TiDG in the effluent due to guanidine partitioning. This report documents the calculations performed to reach this conclusion.

  8. Assessment of the impact of the next generation solvent on DWPF melter off-gas flammability

    International Nuclear Information System (INIS)

    An assessment has been made to evaluate the impact on the DWPF melter off-gas flammability of replacing the current solvent used in the Modular Caustic-Side Solvent Extraction Process Unit (MCU) process with the Next Generation Solvent (NGS-MCU) and blended solvent. The results of this study showed that the concentrations of nonvolatile carbon and hydrogen of the current solvent in the Slurry Mix Evaporator (SME) product would both be about 29% higher than their counterparts of the NGS-MCU and blended solvent in the absence of guanidine partitioning. When 6 ppm of guanidine (TiDG) was added to the effluent transfer to DWPF to simulate partitioning for the NGS-MCU and blended solvent cases and the concentration of Isopar®L in the effluent transfer was controlled below 87 ppm, the concentrations of nonvolatile carbon and hydrogen of the NGS-MCU and blended solvent were still about 12% and 4% lower, respectively, than those of the current solvent. It is, therefore, concluded that as long as the volume of MCU effluent transfer to DWPF is limited to 15,000 gallons per Sludge Receipt and Adjustment Tank (SRAT)/SME cycle and the concentration of Isopar®L in the effluent transfer is controlled below 87 ppm, using the current solvent assumption of 105 ppm Isoparsign L or 150 ppm solvent in lieu of NGS-MCU or blended solvent in the DWPF melter off-gas flammability assessment is conservative for up to an additional 6 ppm of TiDG in the effluent due to guanidine partitioning. This report documents the calculations performed to reach this conclusion

  9. 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

  10. Dynamic Modelling of an Industrial Smelter Furnace and Converter Off-gas System

    OpenAIRE

    Shang, H; M. Dillabough; Nelson, P.; B. Salt

    2008-01-01

    In smelters, metal ores or concentrates are smelted to reduce a metal oxide to a metal through a series of reactions and processes. In a smelting process, a large amount of off-gas emissions are often generated, which can cause serious environmental and plant hygiene problems if not properly treated. Off-gas systems extract and treat the off-gas emissions, and ensure that the smelter operation is in accordance with environmental and industrial hygiene regulations. In this paper, the dynamic m...

  11. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  13. 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.

  14. Diesel auto-thermal reforming for solid oxide fuel cell systems: Anode off-gas recycle simulation

    International Nuclear Information System (INIS)

    Highlights: • Diesel reformation with solid oxide fuel cell anode off-gas recycle simulation. • Thermodynamic modeling complemented experiments to optimize fuel reformation. • Comparisons of diesel reforming with anode off-gas recycle and direct water/air. • Single-tube reformer with Rh/CeO2–ZrO2 catalyst for diesel autothermal reforming. - Abstract: Diesel auto-thermal reformation (ATR) with solid oxide fuel cell (SOFC) stack anode off-gas recycle (AOGR) has a reliable steam recycling supply to the reformer and improves overall system efficiency. For the lab-scale experiments, it is crucial to develop a cost-effective technique to simulate the AOGR effects on hydrocarbon catalytic reformation due to safety and cost considerations of providing the full recycle composition in the absence of fuel cell stack hardware. The present work combined thermodynamic modeling and experiments to compare diesel ATR performance with AOGR and with direct water/air inputs as recycle simulation (RS). Variations of input water and air flow were employed to simulate the effects of recycle gas on syngas production and to analyze the contribution of recycled CO2 dry reforming. A single-tube reformer with Rh/CeO2–ZrO2 catalyst was used for diesel ATR experiments with a photo-acoustic micro-soot meter to monitor carbon formation in the reformate effluent. Experimental results suggest water and air input flows are two key variables to simulate performance of diesel ATR with AOGR, whereas gas hourly space velocity and reforming temperature do not significantly affect the recycle simulation process in syngas production. The optimum AOGR ratio for an SOFC stack with 65% fuel utilization was identified as 45% for diesel ATR to achieve maximum syngas production and reforming efficiency with a given input air flow

  15. 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 discussed

  16. Stereotype Threat, Test Anxiety, and Mathematics Performance

    Science.gov (United States)

    Tempel, Tobias; Neumann, Roland

    2014-01-01

    We investigated the combined effects of stereotype threat and trait test anxiety on mathematics test performance. Stereotype threat and test anxiety interacted with each other in affecting performance. Trait test anxiety predicted performance only in a diagnostic condition that prevented stereotype threat by stereotype denial. A state measure of…

  17. Cut performance levels and testing.

    Science.gov (United States)

    Bennett, Bill; Moreland, Jeff

    2011-11-01

    While the ISEA performance levels and general recommendations detailed above can help tp provide guidance when selecting hand protection products, the responsibility for testing products for specific end-user applications still rests with the end user. We can indicate, for example, that a medium-weight, uncoated Kevlar glove will typically have an ISEA cut rating of 3, but we cannot say the glove will provide the level of protection needed for the range of jobs on an automobile assembly line. Another Level 3 glove might be better suited to an application the require the worker to have an oil grip. As glove manufacturers, we know gloves. We do not know the details about every workplace. We therefore, must look to our customers to provide us the properties they need for hand protection products that will sufficiently protect their workers on the job. PMID:22135955

  18. 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

  19. Self absorption and geometric correction factors for reactor off-gas samples relative to NBS standards

    International Nuclear Information System (INIS)

    Although they can be counted in identical bottles using identical counting systems, real gas samples differ from the NBS solution standards (e.g., mock reactor off-gas) in two respects--geometry and self absorption. Because both detector and source are real and finite, the simple ''narrow beam'' linear attenuation coefficient approximations currently used in the industry are quite inadequate for correction. Accordingly, the well-tested, complete-analog program, BIM 130, was used to compute the fraction of photons, and the photon energy spectra, reaching typical detectors used in the industry. Using this method, it was possible to correct the given NBS standard activity to its effective activity relative to a gas sample in an identical bottle. Factors were much closer to unity than predictions based on ''narrow beam'' linear attenuation coefficient approximations. At 80 keV, for example, such approximations gave 0.76, whereas the factor proved to be 1.03 for a 3'' x 3'' NaI(Tl) crystal and a 3 cm distance. Results are presented for various gamma energies of interest from 80 keV to 1,830 keV, and for the commonly used industrial distances of 3, 10, and 30 cm from the bottom of the sample bottle to the top of the detector container. Complete spectra for photons entering the detectors, as well as factors derived from these for typical NaI(Tl) and Ge(Li) detector resolutions, are given

  20. 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.)

  1. 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

  2. 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 evolved during pyrolysis of sludge-precipitate feed

  3. 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

  4. 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

  5. Studies in the dissolver off-gas system for a spent FBR fuel reprocessing plant

    International Nuclear Information System (INIS)

    Investigations of possible modifications of the process steps of a dissolver off-gas (DOG) system for a spent FBR fuel reprocessing plant are reported. The following operations are discussed: iodine removal from the fuel solution; behaviour of NOsub(x) and iodine in nitric acid off-gas scrubbers at different temperatures and nitric acid concentrations; iodine desorption from the scrub acid; selective absorption of noble gases in refrigerant-12; cold traps. The combination of suitable procedures to produce a total DOG system is described. (U.K.)

  6. 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

  7. Research of laser stealth performance test technology

    Science.gov (United States)

    Chen, Zhen-xing; Shi, Sheng-bing; Han, Fu-li; Wu, Yan-lin; Song, Chun-yan

    2014-09-01

    Laser stealth is an important way of photoelectric stealth weapons systems. According to operational principle of laser range finder, we actively explore and study the stealth performance approval testing technology of laser stealth materials, and bring forward and establish the stealth performance field test methods of stealth efficiency evaluation. Through contrastive test of two kinds of materials, the method is correct and effective.

  8. Development of off-gas filters for reprocessing plants

    International Nuclear Information System (INIS)

    Highly impregnated iodine sorption materials (AC 6,120/H1) was produced for the future GWA filters (German reprocessing plant for 1,500 to/a of uranium). The utilization of the capacity, the removal efficiency and the removal profile were determined in removal tests with elemental iodine on test beds of the depth planned for the GWA iodine filter system. Utilization of the Ag+ of the AC 6,120 impregnation amounted to > 90%; the removal efficiencies reached > 99.99%; the removal profile in the iodine sorption bed is so steep that satisfactory utilization of the sorption material may be anticipated in the two stage filter planned. The concepts of the WAK iodine filter system and of the GWA iodine filters were finished. Work on the reaction behavior of organic iodine compounds on AC 6,120 was continued. Only iodobenzene (as the model substance of an organic ring compound in which iodine is directly bound to the aromatic ring) did not react with AC 6,120. The other compounds exhibited a reactivity which was sufficient for removal purposes in the iodine filter under GWA conditions. Preliminary experiments have been started on the expulsion of iodine from the dissolver and the recovered acid and have exhibited high release values. (orig.)

  9. Organic iodine removal from simulated dissolver off-gas streams using partially exchanged silver mordenite

    International Nuclear Information System (INIS)

    The removal of methyl iodide by adsorption onto silver mordenite was studied using a simulated off-gas from the fuel dissolution step of a nuclear fuel reprocessing plant. The methyl iodide adsorption of partially exchanged silver mordenite was examined for the effects of NO/sub x/, humidity, filter temperature, and degree of silver exchange. Partially exchanged silver mordenite, in general, achieved significantly higher silver utilizations than the fully exchanged material. Silver utilizations of > 95% were achieved, assuming the formation of AgI. The experimental results indicate that CH3I loadings increase proportionally with silver loading up to 5 wt % silver and then appear to level off. Tests conducted to determine the effect of temperature on the loading showed higher loadings at 2000C than at either 150 or 2500C. The presence of NO, NO2, and H2O vapor showed negligible effects on the loading of CH3I. In contrast to iodine loaded onto fully exchanged silver mordenite, the iodine loaded onto the partially exchanged silver mordenite could not be stripped by either 4.5% hydrogen or 100% hydrogen at temperatures up to 5000C. A study of the regeneration characteristics of fully exchanged silver mordenite indicates a decreased adsorbent capacity after complete removal of the iodine with 4.5% hydrogen in the regeneration gas stream at 5000C. The loss of adsorbent capacity was much higher for silver mordenite regenerated in a stainless steel filter housing than in a glass filter housing. A cost evaluation for the use of the partially exchanged silver mordenite shows that the cost of the silver mordenite on a once-through basis is < $10/h of operation for a 0.5-t/d reprocessing plant

  10. Organic iodine removal from simulated dissolver off-gas systems utilizing silver-exchanged mordenite

    International Nuclear Information System (INIS)

    The removal of methyl iodide by adsorption onto silver mordenite was studied using a simulated off-gas from the fuel dissolution step of a nuclear fuel reprocessing plant. The adsorption of methyl iodide on silver mordenite was examined for the effect of NO/sub x/, humidity, iodine concentration, filter temperature, silver loadings and filter pretreatment. The highest iodine loading achieved in these tests was 142 mg CH3I per g of substrate on fully exchanged zeolite, approximately the same as elemental iodine loadings. A filter using fully exchanged silver mordenite operating at 2000C obtained higher iodine loadings than a similar filter operating at 1500C. Pretreatment of the sorbent bed with hydrogen rather than dry air, at a temperature of 2000C, also improved the loading. Variations in the methyl iodide concentration had minimal effects on the overall loading. Filters exposed to moist air streams attained higher loadings than those in contact with dry air. Partially exchanged silver mordenite achieved higher silver utilizations than the fully exchanged material. The partially exchanged mordenite also achieved higher loadings at 2000C than at 2500C. The iodine loaded onto these beds was not stripped at 5000C by either 4.5% hydrogen or 100% hydrogen; however, the iodine could be removed by air at 5000C, and the bed could be reloaded. A study of the regeneration characteristics of fully exchanged silver mordenite indicates limited adsorbent capacity after complete removal of the iodine with 4.5% hydrogen in the regeneration gas stream at 5000C. The loss of adsorbent capacity is much higher for silver mordenite regenerated in a stainless steel filter housing than in a glass filter housing

  11. 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)

  12. 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

  13. Performing and evaluating creep tests.

    Czech Academy of Sciences Publication Activity Database

    Dvo?ák, Ji?í; Blum, W.; Král, Petr; Eisenlohr, P.; Skleni?ka, Václav

    Toulouse : Institut Carnot CIRIMAT, 2015. s. 303-304. [CREEP 2015 - International Conference on Creep and Fracture of Engineering Materials and Structures /13./. 31.05.2015-04.06.2015, Toulouse] R&D Projects: GA MŠk(CZ) ED1.1.00/02.0068 Institutional support: RVO:68081723 Keywords : creep test * inelastic strain rate * crystallite boundaries * coper * dynamic recovery Subject RIV: JG - Metallurgy

  14. 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

  15. 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.

  16. JOYO MK-III performance test

    International Nuclear Information System (INIS)

    The MK-III upgrading project was completed in the experimental fast reactor JOYO to increase irradiation capability for irradiation tests. The performance tests were carried out from June 2003 as the last phase of MK-III modification work. During the performance tests, the reactor power was raised step by step, while confirming the nuclear and thermal characteristics of MK-III core and the heat removal capability of the intermediate heat exchanger (IHX) and the dump heat exchanger (DHX). All performance tests were successfully carried out and it was confirmed that the performance of JOYO MK-III plant satisfied the design requirement. A pre-use inspection pass certificate for JOYO MK-III was granted from Ministry of Education, Culture, Sports, Science and Technology in 27th November 2003 and the MK-III modification work was completed. This report shows the results of the performance tests of JOYO MK-III. (author)

  17. Cement solidification of simulated off-gas condensates from vitrification of low-level nuclear waste solutions.

    Science.gov (United States)

    Katz, A; Brough, A R; Kirkpatrick, R J; Struble, L J; Sun, G K; Young, J F

    2001-01-01

    Solidification in a cementitious matrix is a viable alternative for low-level nuclear waste management; it is therefore important to understand the behavior and properties of such wasteforms. We have examined the cementitious solidification of simulated off-gas waste streams resulting from the vitrification of low-level nuclear waste. Different possible methods for scrubbing the off-gasses from a vitrifier give rise to three possible types of waste compositions: acidic (from aqueous dissolution of volatile NOx and POx carried over from the vitrifier), basic (from neutralizing the former with sodium hydroxide), and fully carbonated (arising from a direct-combustion vitrifier). Six binder compositions were tested in which ordinary Portland cement was replaced at different proportions by fly ash and/or ground granulated blast furnace slag. A high solution to binder ratio of 1l/1 kg was used to minimize the volume of the wasteform and 10% attapulgite clay was added to all mixes to ensure that the fresh mix did not segregate prior to setting. The 28-day compressive strengths decreased when a high proportion of cement was replaced with fly ash, but were increased significantly when the cement was replaced with slag. The heats of hydration at early age for the various solids compositions decreased when cement was replaced with either fly ash or slag; however, for the fly ash mix the low heat was also associated with a significant decrease in compressive strength. High curing temperature (60 degrees C) or the use of extra-fine slag did not significantly affect the compressive strength. Recommendations for choice of binder formulations and treatment of off-gas condensates are discussed. PMID:11478621

  18. Effect of encouragement on walking test performance.

    Science.gov (United States)

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

    1984-11-01

    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 10 weeks. Simple encouragement improved performance (p less than 0.02 for the six minute walk), and the magnitude of the effect was similar to that reported for patients in studies purporting to show beneficial effects of therapeutic manoeuvres. Age and test repetition also affected performance. These results demonstrate the need for careful standardisation of the performance of walking tests, and suggest caution in interpreting studies in which standardisation is not a major feature of the study design. PMID:6505988

  19. 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

  20. On The Impact of Borescope Camera Air Purge on DWPF Melter Off-Gas Flammability

    International Nuclear Information System (INIS)

    DWPF Engineering personnel requested that a new minimum backup film cooler air flow rate, which will meet the off-gas safety basis limits for both normal and seismic sludge-only operations, be calculated when the air purge to the borescope cameras is isolated from the melter. Specifically, it was requested that the latest calculations which were used to set the off-gas flammability safety bases for the sludge batch 2 and 3 feeds be revised, while maintaining all other process variables affecting off-gas flammability such as total organic carbon (TOC), feed rate, melter air purges, and vapor space temperature at their current respective maximum or minimum limits. Before attempting to calculate the new minimum backup film cooler air flow, some of the key elements of the combustion model were reviewed, and it was determined that the current minimum backup film cooler air flow of 233 lb/hr is adequate to satisfy the off-gas flammability safety bases for both normal and seismic operations in the absence of any borescope camera air purge. It is, therefore, concluded that there is no need to revise the reference E-7 calculations. This conclusion is in essence based on the fact that the current minimum backup film cooler air flow was set to satisfy the minimum combustion air requirement under the worst-case operating scenario involving a design basis earthquake during which all the air purges not only to the borescope cameras but to the seal pot are presumed to be lost due to pipe ruptures. The minimum combustion air purge is currently set at 150 per cent of the stoichiometric air flow required to combust 3 times the normal flow of flammable gases. The DWPF control strategy has been that 100 per cent of the required minimum combustion air is to be provided by the controlled air purge through the backup film cooler alone

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

    Energy Technology Data Exchange (ETDEWEB)

    Vance, R.F.

    1991-12-01

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

  2. 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

  3. Development of filters for exhaust air or off-gas cleaning

    International Nuclear Information System (INIS)

    The activities of the 'Laboratorium fuer Aerosolphysik und Filtertechnik II' of the 'Kernforschungszentrum Karlsruhe' concentrate on the development of filters to be used for cleaning nuclear and conventional exhaust air and off-gas. Originally, these techniques were intended to be applied in nuclear facilities only. Their application for conventional gas purification, however, has led to a reorientation of research and development projects. By way of example, it is reported about the use of the multi-way sorption filter for radioiodine removal in nuclear power plants and following flue-gas purification in heating power plants as well as for off-gas cleaning in chemical industry. The improvement of HEPA filters and the development of metal fibre filters has led to components which can be used in the range of high humidity and moisture as well as at high temperatures and an increased differential pressure. The experience obtained in the field of high-efficiency filtering of nuclear airborne particles is made use of during the investigations concerning the removal of particles of conventional pollutants in the submicron range. A technique of radioiodine removal and an improved removal of airborne particles has been developed for use in the future reprocessing plant. Thus, a maximum removal efficiency can be achieved and an optimum waste management is made possible. It is reported about the components obtained as a result of these activities and their use for off-gas cleaning in the Wackersdorf reprocessing plant (WAW). (orig.)

  4. 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)

  5. Improving health physics measurements by performance testing

    International Nuclear Information System (INIS)

    Performance testing standards have been written to establish minimum performance requirements for personnel dosimeters, radiation survey instruments, and bioassay laboratory measurements. These standards were subjected to experimental evaluation and to a consensus review to assure that the requirements were practical. Programs have been established using the personnel dosimeters standards to improve and control the performance of dosimeter processors. Similarly, implementation of performance testing of instruments will result in improved reliability of field measurements and initiation of a program based on the bioassay standard will improve the accuracy, precision, and detectability levels for the measurement of radioactivity in occupationally exposed workers. Evaluating the performance of health physics measurement tools will lead to improved accuracy and precision and to an improved knowledge of personnel exposures. Performance testing will become a more widely recognized tool for maintenance of a quality program and the concept will be applied to additional measurements. 32 refs., 3 tabs

  6. Mathematical modelling of heat transfer in dedusting plants and comparison to off-gas measurements at electric arc furnaces

    International Nuclear Information System (INIS)

    A mathematical simulation tool is presented in order to model enthalpy flow rates of off-gas and heat transfer of cooling systems at dedusting plants in electric steel making sites. The flexibility of the simulation tool is based on a user-defined series of modular units that describe elementary units of industrial dedusting systems, e.g. water-cooled hot gas duct, air injector, drop-out box, mixing chamber, post-combustion chamber, filter, etc. Results of simulation were checked with measurements at industrial electric steel making plants in order to validate the models for turbulence, heat transfer and chemical reaction kinetics. Comparison between computed and measured gas temperature and composition yield excellent agreement. The simulation tool is used to calculate off-gas temperature and volume flow rate, where off-gas measurements are very difficult to apply due to high gas temperatures and high dust load. Heat transfer from the off-gas to the cooling system was calculated in detail for a pressurised hot water EAF cooling system in order to investigate the impact of the cooling system and the dedusting plant operation on the energy sinks of the electric arc furnace. It is shown that optimum efficiency of post-combustion of EAF off-gas in the water-cooled hot gas duct requires continuous off-gas analysis. Common operation parameters of EAF dedusting systems do not consider the non-steady-state of the EAF off-gas emission efficiently

  7. 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 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.

  8. 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.

  9. Effect of encouragement on walking test performance.

    OpenAIRE

    G.H. Guyatt; 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 ...

  10. A conceptual study on LH2 tank system with no relief of boil-off gas into the atmosphere

    International Nuclear Information System (INIS)

    The greenhouse effect is an important problem facing the global community, and it is caused in part by the use of fossil fuel in transportation. By changing the fossil fuel to hydrogen, a countermeasure was found. A challenge is hydrogen storage. The largest amount of energy per weight and volume is achieved with storing liquid hydrogen. The low temperature of the liquid hydrogen results in the generation of boil-off gas, causing heat inflow into the liquid hydrogen. This boil-off gas is then released into the atmosphere. The authors described a novel design concept for liquid hydrogen with an ultra-low temperature refrigerator installed in the tank in an effort to completely eliminate the release of boil-off gas in the atmosphere. It was concluded that using a commercially available refrigerator system can completely eliminate the boil-off gas. An improvement in the thermal efficiency of the system was noted. 4 refs., 1 tab., 8 figs

  11. 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

  12. 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.

  13. 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...

  14. Eurados trial performance test for photon dosimetry

    DEFF Research Database (Denmark)

    Stadtmann, H.; Bordy, J.M.; Ambrosi, P.; Bartlett, D.T.; Christensen, P.; Colgan, T.; Hyvonen, H.

    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 ...

  15. 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

  16. 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...

  17. 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.

  18. 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

  19. Radioactive contamination monitoring device for off-gas in ventilation system

    International Nuclear Information System (INIS)

    In a conventional method of detecting leakage for primary coolants, radioactive iodine in off-gases was detected while going up the off-gas system. As an event resulting in abnormality to radioactive rare gas level, leakage of water, leakage in cleanup system-recycling system, leakage in main steams and leakage from wastes processing system are considered. An off-gas system to be measured is selectively sampled by a sample changer in order to measure radioactive rare gases in the off-gases, and sample gases are introduced to detect radioactivity. Detection signals are received for analysis and quantitative determination, the result of the analysis is diagnosed and the presence or absence of abnormality in an object to be measured is determined. Subsequently, an abnormality alarm and the result of the analysis are outputted. Since the radioactive rare gases are chemically inactive, they are neither combined with other materials nor deposited to wall surfaces. Abnormality can be easily detected by always monitoring a composition pattern and a radioactivity level. (N.H.)

  20. 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

  1. 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 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

  2. Motivation and Test Anxiety in Test Performance across Three Testing Contexts: The CAEL, CET, and GEPT

    Science.gov (United States)

    Cheng, Liying; Klinger, Don; Fox, Janna; Doe, Christine; Jin, Yan; Wu, Jessica

    2014-01-01

    This study examined test-takers' motivation, test anxiety, and test performance across a range of social and educational contexts in three high-stakes language tests: the Canadian Academic English Language (CAEL) Assessment in Canada, the College English Test (CET) in the People's Republic of China, and the General English Proficiency…

  3. 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.

  4. 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.

  5. Thermal Performance Testing Of Cryogenic Piping Systems

    Science.gov (United States)

    Fesmire, J. E.; Augustynowicz, S. D.; Nagy, Z. F.

    2003-01-01

    Thermal performance measurement of piping systems under actual field conditions is important for space launch development and commercial industry. Knowledge of the true insulating effectiveness is needed in system design, development, and research activities. A new 18-meter-long test apparatus for cryogenic pipelines has been developed. Three different pipelines, rigid or flexible, can be tested simultaneously. Critical factors in heat leak measurements include eliminating heat transfer at end connections and obtaining proper liquid saturation condition. Effects due to variations in the external ambient conditions like wind, humidity, and solar radiation must be minimized. The static method of liquid nitrogen evaporation has been demonstrated, but the apparatus can be adapted for dynamic testing with cryogens, chilled water, or other working fluids. This technology is suited for the development of an industry standard test apparatus and method. Examples of the heat transfer data from testing commercially available pipelines are given. Prototype pipelines are currently being tested and evaluated at the Cryogenics Test Laboratory of NASA Kennedy Space Center.

  6. Fluidized-bed calcination of LWR fuel-reprocessing HLLW: requirements and potential for off-gas cleanup

    International Nuclear Information System (INIS)

    Fluidized-bed solidification (calcination) was developed on a pilot scale for a variety of simulated LWR high-level liquid-waste (HLLW) and blended high-level and intermediate-level liquid-waste (ILLW) compositions. It has also been demonstrated with ICPP fuel-reprocessing waste since 1963 in the Waste Calcining Facility (WCF) at gross feed rates of 5 to 12 m3/day. A fluidized-bed calciner produces a relatively large volume of off-gas. A calciner solidifying 6 m3/day of liquid waste would generate about 13 standard m3/min of off-gas containing 10 to 20 g of entrained solids per standard m3 of off-gas. Use of an off-gas system similar to that of the WCF could provide an overall process decontamination factor for particulates of about 2 x 1010. A potential advantage of fluidized-bed calcination over other solidification methods is the ability to control ruthenium volatilization from the calciner at less than 0.01% by calcining at 5000C or above. Use of an off-gas system similar to that of the WCF would provide an overall process decontamination factor for volatile ruthenium of greater than 1.6 x 107

  7. Testing for improvement in prediction model performance

    OpenAIRE

    Pepe, Margaret Sullivan; Kerr, Kathleen F; Longton, Gary; Wang, Zheyu

    2013-01-01

    New methodology has been proposed in recent years for evaluating the improvement in prediction performance gained by adding a new predictor, Y, to a risk model containing a set of baseline predictors, X, for a binary outcome D. We prove theoretically that null hypotheses concerning no improvement in performance are equivalent to the simple null hypothesis that Y is not a risk factor when controlling for X, H0: P (D = 1|X, Y) = P (D = 1|X). Therefore, testing for improvement in prediction perf...

  8. 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 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

  9. Performance tests during the IBL Stave Integration

    CERN Document Server

    Jentzsch, J; The ATLAS collaboration

    2014-01-01

    In preparation of the ATLAS Pixel Insertable B-Layer integration, two 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 ~ 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.

  10. Performance Tests during the IBL Stave Integration

    CERN Document Server

    Backhaus, M; 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 ~ 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.

  11. Performance test of 100 W linear compressor

    International Nuclear Information System (INIS)

    In this paper, we present test results of developed 100 W class linear compressor for Stirling-type pulse tube refrigerator. The fabricated linear compressor has dual-opposed configuration, free piston and moving magnet type linear motor. Power transfer, efficiency and required pressure waveform are predicted with designed and measured specifications. In experiments, room temperature test with flow impedance is conducted to evaluate performance of developed linear compressor. Flow impedance is loaded to compressor with metering valve for flow resistance, inertance tube for flow inertance and buffer volumes for flow compliance. Several operating parameters such as input voltage, current, piston displacement and pressure wave are measured for various operating frequency and fixed input current level. Behaviors of dynamics and performance of linear compressor as varying flow impedance are discussed with measured experimental results. The developed linear compressor shows 124 W of input power, 86 % of motor efficiency and 60 % of compressor efficiency at its resonant operating condition.

  12. 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

  13. 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

  14. Performance testing of large metallic seals

    Energy Technology Data Exchange (ETDEWEB)

    Leisher, W. B.; Trujillo, A. A.

    1980-01-01

    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.

  15. Performance test of a TMS calorimeter

    International Nuclear Information System (INIS)

    Performance tests of a first calorimeter module using the room temperature liquid tetramethylsilane (TMS) as active element are described in detail. As absorber planed carbon steel slabs had been used. The charge yield is 70% of that in a very pure sample of the liquid. A long term stability of the signal with a lifetime of half a year has been realized. Experiences are described and the results explained in detail. (orig.)

  16. 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.

  17. MEMS performance challenges: packaging and shock tests

    Science.gov (United States)

    Chang, Jiyoung; Yang, Chen; Zhang, Bin; Lin, Liwei

    2011-06-01

    This paper describes recent advances in the MEMS performance challenges with emphases on packaging and shock tests. In the packaging area, metal to metal bonding processes have been developed to overcome limitations of the glass frit bonding by means of two specific methods: (1) pre-reflow of solder for enhanced bonding adhesion, and (2) the insertion of thin metal layer between parent metal bonding materials. In the shock test area, multiscale analysis for a MEMS package system has been developed with experimental verifications to investigate dynamic responses under drop-shock tests. Structural deformation and stress distribution data are extracted and predicted for device fracture and in-operation stiction analyses for micro mechanical components in various MEMS sensors, including accelerometers and gyroscopes.

  18. Some aspects of the treatment of typical off-gas streams from reprocessing plants

    International Nuclear Information System (INIS)

    The development of a fluidized sand-bed filter for filtration of particulate activity as applied to the process off-gas systems in fuel reprocessing plants, and an evaluation of its efficiency, is described. A comparative statement of the relative merits of various other filtration systems, such as the deep-bed glass fibre filters and the fixed sand-bed filters for such application, is made and a composite filtration system consisting of a fluidized sand-bed pre-filter and a final glass fibre polishing filter is recommended. Also included are studies carried out on the use of stainless steel sieve plates as de-entrainers, proposing a correlation for efficiency. (author)

  19. Purification of exhaust air and off-gas in nuclear power stations

    International Nuclear Information System (INIS)

    The sources of radioactivity present in nuclear power stations, the significance of the fission products for the environmental impact of nuclear power stations, and the pathway of the airborne radioactivity will be treated briefly. The devices for the removal of radioactivity from the exhaust air and from off-gas are discussed and their function is explained. The HEPA-filters for the removal of aerosols, the sorption filters for the removal of gaseous radioiodine, and the fission gas holdup beds with activated charcoal for decreasing the discharge of radioactive isotopes of the noble gases xenon and krypton will be treated in detail. The degree of penetration of these devices will be given. The factors reducing the removal efficiency will be mentioned. (orig.)

  20. 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.

  1. 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

  2. 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

  3. 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)

  4. A model for utilizing industrial off-gas to support microalgae cultivation for biodiesel in cold climates

    International Nuclear Information System (INIS)

    Highlights: • Development of a model to assess process-coupled algae production in cold climates. • Algae growth temperatures in open tanks can be maintained with industrial off-gas. • Indirect and direct heat application from industrial off-gasses are assessed. • CO2-rich off-gas can be bubbled into algae tanks to provide a carbon source. • A nickel smelter’s off-gas is used to demonstrate how waste heat can be repurposed. - Abstract: Lipids produced by microalgae are a promising biofuel feedstock. However, as most commercial mass production of microalgae is in open raceway ponds it is generally considered only a practical option in regions where year-round ambient temperatures remain above 15 °C. To address this issue it has been proposed to couple microalgae production with industries that produce large amounts of waste heat and carbon dioxide (CO2). The CO2 would provide a carbon source for the microalgae and the waste heat would allow year-round cultivation to be extended to regions that experience seasonal ambient temperatures well below 15 °C. To demonstrate this concept, a dynamic model has been constructed that predicts the impact on algal pond temperature from both bubbled-in off-gas and heat indirectly recovered from off-gas. Simulations were carried out for a variety of global locations using the quantity off-gas and waste energy from a smelter’s operations to determine the volume of microalgae that could be maintained above 15 °C. The results demonstrate the feasibility of year-round microalgae production in climates with relatively cold winter seasons

  5. 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

  6. 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.

  7. Contract performance demonstration tests in the OPAL

    International Nuclear Information System (INIS)

    This paper will describe the measurements and calculations that were done in the OPAL Reactor to demonstrate compliance against contractual Design Features and Performance Acceptance Criteria. The contract specifies several neutronic aspects to be fulfilled by the core, the irradiation and the beam facilities design, which have to be verified during the commissioning tests. Guaranteed flux values will be taken as being for equilibrium core conditions. The relationship between values measured during commissioning (First Core) and the guaranteed values is largely based on calculations. The calculated values are obtained modelling with full detail the measurement conditions using the INVAP traditional calculation lines: CITVAP and MCNP calculation lines. (author)

  8. Fuel accident performance testing for small HTRs

    Science.gov (United States)

    Schenk, W.; Pott, G.; Nabielek, H.

    1990-04-01

    Irradiated spherical fuel elements containing 16400 coated UO 2 particles each were heated at temperatures between 1600 and 1800°C and the fission product release was measured. The demonstrated fission product retention at 1600°C establishes the basis for the design of small modular HTRs which inherently limit the temperature to 1600°C by passive means. In addition to this demonstration, the test data show that modern TRISO fuels provide an ample performance margin: release normally sets in at 1800°C; this occurs at 1600°C only with fuels irradiated under conditions which significantly exceed current reactor design requirements.

  9. Performance testing of UK personal dosimetry laboratories

    CERN Document Server

    Marshall, T O

    1985-01-01

    The proposed Ionising Radiations Regulations will require all UK personal dosimetry laboratories that monitor classified personnel to be approved for personal dosimetry by the Health and Safety Executive. It is suggested that these approvals should be based on general and supplementary criteria published by the British Calibration Service (BCS) for laboratory approval for the provision of personal dosimetry services. These criteria specify certain qualitative requirements and also indicate the need for regular tests of performance to be carried out to ensure constancy of dosimetric standards. This report concerns the latter. The status of the BCS criteria is discussed and the need for additional documents to cover new techniques and some modifications to existing documents is indicated. A means is described by which the technical performance of laboratories, concerned with personal monitoring for external radiations, can be assessed, both initially and ongoing. The costs to establish the scheme and operate it...

  10. 40 CFR 60.543 - Performance test and compliance provisions.

    Science.gov (United States)

    2010-07-01

    ...equipment design and performance specifications, as...shall repeat the performance test when directed...device efficiency or measurement of capture system...face velocity. The performance test shall be...

  11. Literature Review: Assessment of DWPF Melter and Melter Off-gas System Lifetime

    Energy Technology Data Exchange (ETDEWEB)

    Reigel, M. [Savannah River Site (SRS), Aiken, SC (United States)

    2015-07-30

    Testing to date for the MOC for the Hanford Waste Treatment and Immobilization Plant (WTP) melters is being reviewed with the lessons learned from DWPF in mind and with consideration to the changes in the flowsheet/feed compositions that have occurred since the original testing was performed. This information will be presented in a separate technical report that identifies any potential gaps for WTP processing.

  12. 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...

  13. Detonation Performance Testing of LX-19

    Science.gov (United States)

    Vincent, Samuel; Aslam, Tariq; Jackson, Scott

    2015-06-01

    CL-20 was developed at the Naval Surface Weapons Center at China Lake, CA in the mid 80's. Being less sensitive than PETN, but considerably more powerful than HMX, it is the highest energy and density compound known among organic chemicals. LX-19 was developed at LLNL in the early 90's. It is a high-energy plastic bonded explosive, composed of 95.8 wt% CL-20 and 4.2 wt% Estane binder, and is similar to LX-14 (composed of HMX and Estane), but with greater sensitivity characteristics with use of the more energetic CL-20 explosive. We report detonation performance results for unconfined cylindrical rate sticks of LX-19. The experimental diameter effects are shown, along with detonation front shapes, and reaction zone profiles for different test diameters. This data is critical for calibration to Detonation Shock Dynamics (DSD). LA-UR-15-20672.

  14. PERFORMANCE TESTING AND ANALYSIS OF CUPOLA FURNACE

    Directory of Open Access Journals (Sweden)

    PROF.HEMANT R. BHAGAT-PATIL

    2013-05-01

    Full Text Available In today’s industrial scenario huge losses/wastage occur in the manufacturing shop floor and foundry industries. The efficiency of any foundry largely depends on the efficiency of the melting process amulti-step operation where the metal is heated, treated, alloyed, and transported into die or mold cavities to form a casting. In this paper we represents the performance testing and analysis of Cupola Furnace, and reduces the problems occurs to give the best results. Our main focus in this work is to improve continuous working hours,reducing preparation time, reducing losses in melting, reducing slag formation and to increase the combustion efficiency of coke and overall productivity and to improve the quality and Mechanical properties of steel using Cupola.

  15. 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

  16. Performance testing of passive autocatalytic recombiners (PARs)

    Energy Technology Data Exchange (ETDEWEB)

    Blanchat, T. [Sandia National Laboratories, Albuquerque, NM (United States); Malliakos, A. [U.S. Nuclear Regulatory Commission, Washington, DC (United States)

    1997-03-01

    Passive autocatalytic recombiners (PARs) have been under consideration in the U.S. as a combustible gas control system in advanced light water reactor (ALWR) containments for design basis and severe accidents. PARs do not require a source of power. Instead they use palladium or platinum as a catalyst to recombine hydrogen and oxygen gases into water vapor upon contact with the catalyst. Energy from the recombination of hydrogen with oxygen is released at a relatively slow but continuous rate into the containment which prevents the pressure from becoming too high. The heat produced creates strong buoyancy effects which increases the influx of the surrounding gases to the recombiner. These natural convective flow currents promote mixing of combustible gases in the containment. PARs are self-starting and self-feeding under a very wide range of conditions. The recombination rate of the PAR system needs to be great enough to keep the concentration of hydrogen (or oxygen) below acceptable limits. There are several catalytic recombiner concepts under development worldwide. The USNRC is evaluating a specific design of a PAR which is in an advanced stage of engineering development and has been proposed for ALWR designs. Sandia National laboratories (SNL), under the sponsorship and the direction of the USNRC, is conducting an experimental program to evaluate the performance of PARs. The PAR will be tested at the SURTSEY facility at SNL. The test plan currently includes the following experiments: experiments will be conducted to define the startup characteristics of PARs (i.e., to define what is the lowest hydrogen concentration that the PAR starts recombining the hydrogen with oxygen); experiments will be used to define the hydrogen depletion rate of PARs as a function of hydrogen concentration; and experiments will be used to define the PAR performance in the presence of high concentrations of steam. (author)

  17. Performance testing of passive autocatalytic recombiners (PARs)

    International Nuclear Information System (INIS)

    Passive autocatalytic recombiners (PARs) have been under consideration in the U.S. as a combustible gas control system in advanced light water reactor (ALWR) containments for design basis and severe accidents. PARs do not require a source of power. Instead they use palladium or platinum as a catalyst to recombine hydrogen and oxygen gases into water vapor upon contact with the catalyst. Energy from the recombination of hydrogen with oxygen is released at a relatively slow but continuous rate into the containment which prevents the pressure from becoming too high. The heat produced creates strong buoyancy effects which increases the influx of the surrounding gases to the recombiner. These natural convective flow currents promote mixing of combustible gases in the containment. PARs are self-starting and self-feeding under a very wide range of conditions. The recombination rate of the PAR system needs to be great enough to keep the concentration of hydrogen (or oxygen) below acceptable limits. There are several catalytic recombiner concepts under development worldwide. The USNRC is evaluating a specific design of a PAR which is in an advanced stage of engineering development and has been proposed for ALWR designs. Sandia National laboratories (SNL), under the sponsorship and the direction of the USNRC, is conducting an experimental program to evaluate the performance of PARs. The PAR will be tested at the SURTSEY facility at SNL. The test plan currently includes the following experiments: experiments will be conducted to define the startup characteristics of PARs (i.e., to define what is the lowest hydrogen concentration that the PAR starts recombining the hydrogen with oxygen); experiments will be used to define the hydrogen depletion rate of PARs as a function of hydrogen concentration; and experiments will be used to define the PAR performance in the presence of high concentrations of steam. (author)

  18. 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.

  19. 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.)

  20. Hydrogen and oxygen monitoring in containment and off-gas systems

    International Nuclear Information System (INIS)

    The hydrogen and oxygen concentrations in containment atmospheres and BWR off-gas recombiners effluents are at present being monitored by analysers originally developed by the General Electric Company for manned space applications. The sensors in these analysers are a good example of the application of space technology to meet difficult terrestrial problems. Hydrogen and oxygen partial pressures are continuously measured with these self-powered electrochemical sensors, which operate at the environmental ambient temperature (24-1700C), pressure (1 to 5atm), and humidity (1-100%RH). The oxygen sensor, which was flown on the Skylab, Apollo-Soyuz and Space Shuttle/Spacelab, and the hydrogen sensor are ideally suited to the requirements of the nuclear power plant because of their ability to operate within the atmosphere being monitored, thereby permitting measurement of hydrogen (or oxygen) in the wet sample. The basic hydrogen sensor design, specifically hardened to withstand the temperature and radiation environments in a post-loss of-coolant-accident (LOCA) situation, provides for measurement of hydrogen in any diluent (oxygen is not required) with a device which in no way represents a potential ignition source. (author)

  1. 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 applications

  2. Performance Test of the Salt transfer and Pellet fabrication of UCl{sub 3} Making Equipment for Electrorefining

    Energy Technology Data Exchange (ETDEWEB)

    Woo, M. S.; Jin, H. J.; Park, G. I.; Park, S. B. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The process to produce a uranium chloride salt includes two steps: a reaction process of gaseous chlorine with liquid cadmium to form the CdCl{sub 2} occurring in a Cd layer, followed by a process to produce UCl{sub 3} by the reaction of U in the LiCl-KCl eutectic salt and CdCl{sub 2}. Chemical reaction is next chlorination reaction; - Cd chlorination : Cd + Cl2 ? CdCl{sub 2} - U chlorination : 3CdCl2 + 2U ? 3Cd + 2UCl{sub 3} The apparatus for producing UCl{sub 3} 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Zamecnik, J.; Choi, A.

    2009-03-25

    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, Cl{sub 2}, 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 Hg{sub 2}Cl{sub 2}) to HgCl{sub 2} 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 Hg{sub 2}Cl{sub 2} 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 c

  4. 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.

  5. Performance of Four Multivariate Tests under Variance-Covariance Heteroscedasticity.

    Science.gov (United States)

    Tang, K. Linda; Algina, James

    1993-01-01

    Type I error rates of four multivariate tests (Pilai-Bartlett trace, Johansen's test, James' first-order test, and James' second-order test) were compared for heterogeneous covariance matrices in 360 simulated experiments. The superior performance of Johansen's test and James' second-order test is discussed. (SLD)

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

    International Nuclear Information System (INIS)

    REA-2023 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 EGandG 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. The cask designs include: solid and liquid neutron shields; lead, steel, and nodular cast iron gamma shields; stainless steel, aluminum, and copper baskets; and borated materials for criticality control. 4 refs., 8 figs., 6 tabs

  7. 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

  8. 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.

  9. 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

  10. 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)

  11. SNL Sigma Off-Gas Team Contribution to the FY15 DOE/NE-MRWFD Campaign Accomplishments Report.

    Energy Technology Data Exchange (ETDEWEB)

    Nenoff, Tina M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-08-21

    This program at Sandia is focused on Iodine waste form development for Fuel Cycle R&D needs. Our research has a general theme of “Capture and Storage of Iodine Fission Gas “ in which we are focused on silver loaded zeolite waste forms, evaluation of iodine loaded getter materials (eg., mordenite zeolite), and the development of low temperature glass waste forms that successfully incorporate iodine loaded getter materials from I2, organic iodide, etc. containing off-gas streams.

  12. Analysis of the off-gas from dissolution of nuclear oxide- and carbide fuels in nitric acid

    Energy Technology Data Exchange (ETDEWEB)

    Glatz, J.P.; Bokelund, H.; Zierfuss, S. (Commission of the European Communities, Karlsruhe (Germany, F.R.). European Inst. for Transuranium Elements)

    1990-01-01

    The off-gas composition upon dissolution of different types of non-irradiated nuclear fuels (UC, U{sub 2}C{sub 3}, UO{sub 2}, (U,Pu)C and (U,Pu)O{sub 2}) in HNO{sub 3} has been measured and the influence of dissolution parameters such as dissolution temperature, nitric acid molarity, fuel density and composition has been studied. For fast dissolutions less off-gas, especially NO{sub 2}, is produced than for slow ones. No CO could be measured for the carbide dissolutions and NO is the most important constituent in the off-gas. For oxides and sesquicarbides, the NO{sub 2} is the predominant species. Carbides are dissolved much faster than oxides and they don't leave any residue, but the solution stays dark and a slight NO{sub 2} and CO{sub 2} evolution continues after the dissolution is complete. This can be ascribed to the destruction of the organic compounds (mellitic acid, oxalic acid etc.) formed during dissolution. A nitric acid concentration of 6 M and temperatures of 80-90deg C are optimum conditions to dissolve fuel materials in a reasonable time with a low nitrogen oxide content in the off-gas. The activation energy calculated from the Arrhenius plot was found to be 43.5 kJ/mol for UC. For UO{sub 2} two values for activation energy were found, 64,1 kJ/mol if the fuel pellets are pressed from U{sub 3}O{sub 8} powder and 54.8 kJ/mol if the pellets are made from UO{sub 2} powder. (orig.).

  13. Analysis of the off-gas from dissolution of nuclear oxide- and carbide fuels in nitric acid

    International Nuclear Information System (INIS)

    The off-gas composition upon dissolution of different types of non-irradiated nuclear fuels (UC, U2C3, UO2, (U,Pu)C and (U,Pu)O2) in HNO3 has been measured and the influence of dissolution parameters such as dissolution temperature, nitric acid molarity, fuel density and composition has been studied. For fast dissolutions less off-gas, especially NO2, is produced than for slow ones. No CO could be measured for the carbide dissolutions and NO is the most important constituent in the off-gas. For oxides and sesquicarbides, the NO2 is the predominant species. Carbides are dissolved much faster than oxides and they don't leave any residue, but the solution stays dark and a slight NO2 and CO2 evolution continues after the dissolution is complete. This can be ascribed to the destruction of the organic compounds (mellitic acid, oxalic acid etc.) formed during dissolution. A nitric acid concentration of 6 M and temperatures of 80-90deg C are optimum conditions to dissolve fuel materials in a reasonable time with a low nitrogen oxide content in the off-gas. The activation energy calculated from the Arrhenius plot was found to be 43.5 kJ/mol for UC. For UO2 two values for activation energy were found, 64,1 kJ/mol if the fuel pellets are pressed from U3O8 powder and 54.8 kJ/mol if the pellets are made from UO2 powder. (orig.)

  14. Experimental evaluation of NO/sub x/ and I2 retention during the scrubbing of dissolver off-gas

    International Nuclear Information System (INIS)

    As part of the Consolidated Fuel Reprocessing Program, this study was conducted at the Oak Ridge National Laboratory to investigate the removal of nitrogen oxides from simulated dissolver off-gas, a gas blended to simulate that arising from the dissolution of nuclear fuel in reprocessing operations. Dissolver off-gas contains large quantities of water vapor and nitrogen oxides and much smaller quantities of iodine and other fission product gases. It is desirable to recover the nitrogen oxides by absorption into water, where subsequent reactions produce nitric acid, which may be recycled to dissolution operations. The NO/sub x/ scrubber system was operated in a mode through to be prototypic of a dissolver off-gas NO/sub x/ scrubber system for nuclear fuel reprocessing facilities, including recycle of the scrubbing liquid. Chemical reactions occurring simultaneously with the absorption of NO/sub x/ into dilute HNO3 solutions produce liquid HNO3 and HNO2. In general, the presence of HNO3 in dilute concentrations in the scrub solution does not have a significant effect on NO/sub x/ scrubbing efficiency; however, the presence of HNO2 in this solution does have a significant deleterious effect on NO/sub x/ scrubbing efficiency. 8 refs., 3 figs

  15. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Zamecnik, J.; Choi, A.

    2010-08-18

    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, Cl{sub 2}, 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 Hg{sub 2}Cl{sub 2}) to HgCl{sub 2} 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 Hg{sub 2}Cl{sub 2} 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 c

  17. Test operation results of radioactive solid waste incinerator

    International Nuclear Information System (INIS)

    Test operation of radioactive solid waste incinerator, which is composed of furnace, high temperature filter and other off-gas treatment equipments, has been performed in Oarai, JAERI, with non-active wastes and chemical tracer such as Co, Sr and Cs. As a result of this test operation, following characteristics on combustion and off-gas cleaning of the incinerator are obtained; (1) Ash accumulation ratio in the furnace is nearly 95%. (2) Dust collecting ratio of the High Temperature Filter is 99%. (3) Heating-up time of the High Temperature Filter are some length. (4) Decontamination factor (DF) of combined furnace and High Temperature Filter is 104 or more for such chemical tracer. (author)

  18. 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....

  19. Performance test results of ETS-6 Ni-Cd cells

    Science.gov (United States)

    Nakatani, Kensuke; Yano, Y.; Kuwajima, S.; Kusawake, Hiroaki

    1994-01-01

    The topics covered are presented in viewgraph form and include the following: development schedule; main specification; cell design; production flow; acceptance test (1); acceptance test (2); cell weight; 20 C performance; capacity; overcharge pressure; end of charge voltage; -5 C performance; ETS-VI simulation cycle test; and battery storage.

  20. 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

  1. Motivational and Cognitive Test-Taking Strategies and Their Influence on Test Performance in Mathematics

    Science.gov (United States)

    Peng, Yun; Hong, Eunsook; Mason, Elsa

    2014-01-01

    A structural equation model of relationships among testing-related motivation variables (test value, effort, self-efficacy, and test anxiety), test-taking strategies (test tactics and metacognitive strategies), gender, and math test performance were examined with a sample of 10th graders (N = 438; 182 males and 256 females). In general, motivation…

  2. 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.

  3. 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; 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...

  4. 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

  5. Optical performance test & analysis of intraocular lenses

    Science.gov (United States)

    Choi, Junoh

    Cataract is a condition in the eye that if left untreated, could lead to blindness. One of the effective ways to treat cataract is the removal of the cataractous natural crystalline lens and implantation of an artificial lens called an intraocular lens(IOL). The designs of the IOLs have shown improvements over the years to further imitate natural human vision. A need for an objective testing and analysis tool for the latest IOLs grow with the advancements of the IOLs. In this dissertation, I present a system capable of objective test and analysis of the advanced IOLs. The system consists of (1) Model eye into which an IOL can be inserted to mimic conditions of the human eye. (2) Modulation Transfer Function measurement setup capable of through-focus test for depth of field studies and polychromatic test for study of effects of chromatization. (3) Use of Defocus Transfer Function to simulate depth of field characteristic of rotationally symmetric multifocal designs and extension of the function to polychromatic conditions. (4) Several target imaging experiments for comparison of stray light artifacts and simulation using a non-sequential ray trace package.

  6. 49 CFR Appendix A to Part 665 - Tests To Be Performed at the Bus Testing Facility

    Science.gov (United States)

    2010-10-01

    ...Performed at the Bus Testing Facility A ...TRANSPORTATION BUS TESTING Pt. 665, App. A Appendix A...Performed at the Bus Testing Facility The...SAFETEA-LU and are based in part on tests...design of all new bus models that are...

  7. Comparing the Effects of Test Anxiety on Independent and Integrated Speaking Test Performance

    Science.gov (United States)

    Huang, Heng-Tsung Danny; Hung, Shao-Ting Alan

    2013-01-01

    Integrated speaking test tasks (integrated tasks) offer textual and/or aural input for test takers on which to base their subsequent oral responses. This path-analytic study modeled the relationship between test anxiety and the performance of such tasks and explored whether test anxiety would differentially affect the performance of independent…

  8. Process system evaluation-consolidated letters. Volume 1. Alternatives for the off-gas treatment system for the low-level waste vitrification process

    Energy Technology Data Exchange (ETDEWEB)

    Peurrung, L.M.; Deforest, T.J; Richards, J.R.

    1996-03-01

    This report provides an evaluation of alternatives for treating off-gas from the low-level waste (LLW) melter. The study used expertise obtained from the commercial nonradioactive off-gas treatment industry. It was assumed that contact maintenance is possible, although the subsequent risk to maintenance personnel was qualitatively considered in selecting equipment. Some adaptations to the alternatives described may be required, depending on the extent of contact maintenance that can be achieved. This evaluation identified key issues for the off-gas system design. To provide background information, technology reviews were assembled for various classifications of off-gas treatment equipment, including off-gas cooling, particulate control, acid gas control, mist elimination, NO{sub x} reduction, and SO{sub 2} removal. An order-of-magnitude cost estimate for one of the off-gas systems considered is provided using both the off-gas characteristics associated with the Joule-heated and combustion-fired melters. The key issues identified and a description of the preferred off-gas system options are provided below. Five candidate treatment systems were evaluated. All of the systems are appropriate for the different melting/feed preparations currently being considered. The lowest technical risk is achieved using option 1, which is similar to designs for high-level waste (HLW) vitrification in the Hanford Waste Vitrification Project (HWVP) and the West Valley. Demonstration Project. Option 1 uses a film cooler, submerged bed scrubber (SBS), and high-efficiency mist eliminator (HEME) prior to NO{sub x} reduction and high-efficiency particulate air (HEPA) filtration. However, several advantages were identified for option 2, which uses high-temperature filtration. Based on the evaluation, option 2 was identified as the preferred alternative. The characteristics of this option are described below.

  9. Performance tests on simulation apparatuses of shallow land

    International Nuclear Information System (INIS)

    Performance tests on simulation apparatuses of shallow land, in which natural condition soil can be used as testing materials, were carried out to study the migration behavior of radionuclides in a natural barrier. The apparatuses consist of the simulation apparatuses for aerated and aquifer zones, the air control apparatus, the measurement apparatuses of water and radionuclide moving velocities, etc. As performance tests, characteristics tests were done for these apparatuses and overall test of the simulation apparatuses for aerated and aquifer zones was also done under the actual test condition. It was confirmed that the all of apparatuses have achieved the designated performance requirements. This report describes the results of performance tests on simulation apparatuses of shallow land, which is categorized into three parts, that is, objective, method and result. (author)

  10. Hybrid Electric Vehicle Fleet and Baseline Performance Testing

    Energy Technology Data Exchange (ETDEWEB)

    J. Francfort; D. Karner

    2006-04-01

    The U.S. Department of Energy’s Advanced Vehicle Testing Activity (AVTA) conducts baseline performance and fleet testing of hybrid electric vehicles (HEV). To date, the AVTA has completed baseline performance testing on seven HEV models and accumulated 1.4 million fleet testing miles on 26 HEVs. The HEV models tested or in testing include: Toyota Gen I and Gen II Prius, and Highlander; Honda Insight, Civic and Accord; Chevrolet Silverado; Ford Escape; and Lexus RX 400h. The baseline performance testing includes dynamometer and closed track testing to document the HEV’s fuel economy (SAE J1634) and performance in a controlled environment. During fleet testing, two of each HEV model are driven to 160,000 miles per vehicle within 36 months, during which maintenance and repair events, and fuel use is recorded and used to compile life-cycle costs. At the conclusion of the 160,000 miles of fleet testing, the SAE J1634 tests are rerun and each HEV battery pack is tested. These AVTA testing activities are conducted by the Idaho National Laboratory, Electric Transportation Applications, and Exponent Failure Analysis Associates. This paper discusses the testing methods and results.

  11. Analytical method for assessing the gamma-ray exposure resulting from continuously discharged radioactive off-gas

    International Nuclear Information System (INIS)

    A simple model for computing the medium gamma dose rate under the radioactive off-gas plume of a continuously emitting source is described, in which the plume is assumed to be a radioactive slab source with a specific source strength inversely proportional to the distance from the release point but not varying with height above ground level. The model results in dose rates slightly higher than those obtained by means of METEOR II, the programme recommended for such computations in the GDR. However, it has the advantage of requiring only a pocket electronic calculator as calculating device. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Jae Hwan, E-mail: yjh98@kaeri.re.kr [Nuclear Fuel Cycle Process Development Division, Korea Atomic Energy Research Institute, 989-111 Daeduk-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 305-701 (Korea, Republic of); Shin, Jin Myeong; Park, Jang Jin; Park, Geun Il [Nuclear Fuel Cycle Process Development Division, Korea Atomic Energy Research Institute, 989-111 Daeduk-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Yim, Man Sung [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)

    2015-02-15

    New adsorbents based on bismuth were investigated for the capture of iodine-129 ({sup 129}I) 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.

  14. 40 CFR 60.56c - Compliance and performance testing.

    Science.gov (United States)

    2010-07-01

    ...Administrator. (k) The owner or operator of an affected facility may conduct a repeat performance test at any time to establish new values for the operating parameters. The Administrator may request a repeat performance test at any time. [62 FR 48382,...

  15. 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.

  16. 40 CFR 63.1349 - Performance testing requirements.

    Science.gov (United States)

    2010-07-01

    ... Standards for Hazardous Air Pollutants From the Portland Cement Manufacturing Industry Monitoring and... addition, the performance test report must include the brand and type of activated carbon used during the... percent reduction in THC across the control device using the performance test requirements in 40 CFR...

  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. 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)

  19. 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.

  20. Development of the FASTER process for removing krypton-85, carbon-14, and other contaminants from the off-gas of fuel reprocessing plants

    International Nuclear Information System (INIS)

    The Oak Ridge Gaseous Diffusion Plant has the primary responsibility for the development of the FASTER (Fluorocarbon Absorption System for Treating Effluents from Reprocessors) process for application to LMFBR and LWR fuel reprocessing plants. Krypton-85 removals in excess of 99.9% and carbon-14 as carbon dioxide removals greater than 99.99% have been obtained in a development pilot plant. So far, pilot plant tests show that the presence of other reprocessing plant off-gas components does not appreciably affect the general operability or removal efficiency of the process. Tests also indicate that the one process designed for krypton and carbon removal may be even more effective in removing other fission products and objectionable chemical contaminants such as nitrogen dioxide. Elemental and organic iodine removals in excess of 99.99% and nitrogen dioxide removals over 99% were recently achieved. Higher process decontaminations are possible. Trapping studies show that 13X molecular sieves are very effective in removing the fluorocarbon vapor from the process product stream

  1. 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.

  2. 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…

  3. Variations in Role-Play Tests of Heterosocial Performance.

    Science.gov (United States)

    Mahaney, Micah M.; Kern, Jeffrey M.

    1983-01-01

    Examined the effects of varying one test parameter, the confederates' prompt latency, on the heterosocial performance of 140 low- and high-frequency male undergraduate daters. The results indicated that these variations altered the test's content as well as the test's absolute difficulty level. (Author/RC)

  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. Expectancy of an open-book test decreases performance on a delayed closed-book test.

    Science.gov (United States)

    Agarwal, Pooja K; Roediger, Henry L

    2011-11-01

    Two experiments examined the influence of practice with, and the expectancy of, open-book tests (students viewed studied material while taking the test) versus closed-book tests (students completed the test without viewing the studied material) on delayed retention and transfer. Using GRE materials specifically designed for open-book testing, participants studied passages and then took initial open- or closed-book tests. Open-book testing led to better initial performance than closed-book testing, but on a delayed criterial (closed-book) test both types of testing produced similar retention after a two-day delay in Experiment 1. In Experiment 2 participants were informed in advance about the type of delayed criterial test to expect (open- or closed-book). Expecting an open-book test (relative to a closed-book test) decreased participants' time spent studying and their delayed test performance on closed-book comprehension and transfer tests, demonstrating that test expectancy can influence long-term learning. Expectancy of open-book tests may impair long-term retention and transfer compared to closed-book tests, despite superior initial performance on open-book tests and students' preference for open-book tests. PMID:21995673

  6. Measuring Several Aspects of Attention in One Test: The Factor Structure of Conners's Continuous Performance Test

    Science.gov (United States)

    Egeland, Jens; Kovalik-Gran, Iwona

    2010-01-01

    Objective: Continuous performance tests are known to typically measure sustained attention but usually also yield parameters that potentially measure other subprocesses of attention. The aim of the present study was to test the factor structure of the Conners's Continuous Performance Test (CCPT) in a heterogeneous clinical sample consisting of…

  7. Irradiation test and performance evaluation of DUPIC fuel

    International Nuclear Information System (INIS)

    The objective of the project is to establish the performance evaluation system of DUPIC fuel during the Phase II R and D. In order to fulfil this objectives, irradiation test of DUPIC fuel was carried out in HANARO using the non-instrumented and SPND-instrumented rig. Also, the analysis on the in-reactor behavior analysis of DUPIC fuel, out-pile test using simulated DUPIC fuel as well as performance and integrity assessment in a commercial reactor were performed during this Phase. The R and D results of the Phase II are summarized as follows : - Performance evaluation of DUPIC fuel via irradiation test in HANARO - Post irradiation examination of irradiated fuel and performance analysis - Development of DUPIC fuel performance code (modified ELESTRES) considering material properties of DUPIC fuel - Irradiation behavior and integrity assessment under the design power envelope of DUPIC fuel - Foundamental technology development of thermal/mechanical performance evaluation using ANSYS (FEM package)

  8. Mechanical/structural performance test method of a spacer grid

    International Nuclear Information System (INIS)

    The spacer grid is one of the main structural components in the fuel assembly, which supports the fuel rods, guides cooling water, and protects the system from an external impact load, such as earthquakes. In order to develop the spacer grid with the high mechanical performance, the mechanical and structural properties of the spacer grids must be extensively examined while designing it. In this report, the mechanical/structural test methods, i.e. the characteristic test of a spacer grid spring or dimple, static buckling test of a partial or full size spacer grid and dynamic impact test of them are described. The characteristic test of a spacer grid spring or dimple is accomplished with universal tensile test machine, a specimen is fixed with test fixture and then applied compressive load. The characteristic test data is saved at loading and unloading event. The static buckling test of a partial or full size spacer grid is executed with the same universal tensile testing machine, a specimen is fixed between cross-heads and then applied the compressive load. The buckling strength is decided the maximum strength at load vs. displacement curve. The dynamic impact test of a partial or full size spacer grid is performed with pendulum type impact machine and free fall shock test machine, a specimen is fixed with test fixture and then applied the impact load by impact hammer. Specially, the pendulum type impact test machine is also possible under the operating temperature because a furnace is separately attached with test machine

  9. 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.

  10. Nuclebras' installations for performance tests of nuclear power plants components

    International Nuclear Information System (INIS)

    The reasons for Nuclebras' Nuclear Technology Development Center to implement a laboratory for supporting Brazilian manufactures, giving to them the means for performing functional tests of industrial products, are presented. A brief description of facilities under construction: the components Test Loop and Facility for Testing N.P.P. components under Accident conditions, and other already in operation, as well as its objectives and main technical characteristics. Some test results had already obtained are also presented. (Author)

  11. 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.

  12. 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.

  13. Performance based testing and maintenance for check valves

    International Nuclear Information System (INIS)

    This paper proposes a methodology for optimizing check valve testing and maintenance activities. Generic Letter 89-04, open-quotes Guidance on Developing Acceptable Inservice Testing Programsclose quotes, and the 1989 Edition of the American Society of Mechanical Engineers (ASME) Code specify the current requirements for testing of check valves. Recent advances in technology and the trend toward performance-based approaches to testing and maintenance represent an opportunity to reduce check valve operation and maintenance costs. This paper describes an evaluation methodology that leads to the specification of an optimum set of inservice testing and maintenance activities for a plant check valve population. The process involves analyzing check valve performance based on preestablished performance attributes. Attributes include relative consequence of failure, historical reliability, maintenance frequency, physical degradation, and service fluid. Each check valve is numerically scored based on the valves' performance against the stated attributes. This score is used to justify a reprioritization of check valve work activities such that safety-significant (high-risk), poor performing valves receive a higher degree of maintenance and testing rigor, while good performing check valves receive less. Applying this methodology may allow justifications for alternative testing and maintenance to be developed and substantiated on the basis of valve performance characteristics versus across-the-board implementation of the ASME Code requirements

  14. Thermal Performance Testing of EMU and CSAFE Liquid Cooling Gannents

    Science.gov (United States)

    Rhodes, Richard; Bue, Grant; Meginnis, Ian; Hakam, Mary; Radford, Tamara

    2013-01-01

    Future exploration missions require the development of a new liquid cooling garment (LCG) to support the next generation extravehicular activity (EVA) suit system. The new LCG must offer greater system reliability, optimal thermal performance as required by mission directive, and meet other design requirements including improved tactile comfort. To advance the development of a future LCG, a thermal performance test was conducted to evaluate: (1) the comparable thermal performance of the EMU LCG and the CSAFE developed engineering evaluation unit (EEU) LCG, (2) the effect of the thermal comfort undergarment (TCU) on the EMU LCG tactile and thermal comfort, and (3) the performance of a torso or upper body only LCG shirt to evaluate a proposed auxiliary loop. To evaluate the thermal performance of each configuration, a metabolic test was conducted using the Demonstrator Spacesuit to create a relevant test environment. Three (3) male test subjects of similar height and weight walked on a treadmill at various speeds to produce three different metabolic loads - resting (300-600 BTU/hr), walking at a slow pace (1200 BTU/hr), and walking at a brisk pace (2200 BTU/hr). Each subject participated in five tests - two wearing the CSAFE full LCG, one wearing the EMU LCG without TCUs, one wearing the EMU LCG with TCUs, and one with the CSAFE shirt-only. During the test, performance data for the breathing air and cooling water systems and subject specific data was collected to define the thermal performance of the configurations. The test results show that the CSAFE EEU LCG and EMU LCG with TCU had comparable performance. The testing also showed that an auxiliary loop LCG, sized similarly to the shirt-only configuration, should provide adequate cooling for contingency scenarios. Finally, the testing showed that the TCU did not significantly hinder LCG heat transfer, and may prove to be acceptable for future suit use with additional analysis and testing.

  15. Recommended procedures for performance testing of radiobioassay laboratories: Volume 3, In vivo test phantoms

    International Nuclear Information System (INIS)

    Draft American National Standards Institute (ANSI) Standard N13.30 (Performance Criteria for Radiobioassay) was developed for the US Department of Energy and the US Nuclear Regulatory Commission to help ensure that bioassay laboratories provide accurate and consistent results. The draft standard describes the procedures necessary to establish a bioassay performance-testing laboratory and program. The bioassay performance-testing laboratory will conduct tests to evaluate the performance of service laboratories. Pacific Northwest Laboratory helped develop testing procedures as part of an effort to evaluate the draft ANSI N13.30 performance criteria by testing the existing measurement capabilities of various bioassay laboratories. This report recommends guidelines for the preparation, handling, storage, distribution, shipping, and documentation of test phantoms used for calibration of measurement systems for direct bioassay. The data base and recommended records system for documenting radiobioassay performance at the service laboratories are also presented

  16. 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)

  17. Overview on MOX fuel for LWRs: Design, performance and testing

    International Nuclear Information System (INIS)

    This overview looks at the historical background to the design, performance and testing of LWR MOX fuel over the last 30 to 40 years. It briefly examines the scenarios which encouraged the development of MOX fuel for utilisation in LWRs and looks at the design changes required on moving from UO2 to MOX fuel. The paper summarises the national irradiation testing programmes, the commercial developments and performance data obtained throughout this period, highlighting those aspects which have had an impact on manufacturing and design choices. The paper thus provides the historical background information for the contributed papers in Session 3 (Fuel Design, Performance and Testing) of the symposium. (author)

  18. 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.

  19. 40 CFR 60.3027 - How do I conduct the initial and annual performance test?

    Science.gov (United States)

    2010-07-01

    ...performance test? (a) All performance tests must consist of a...operations. (b) All performance tests must be conducted...this subpart. (c) All performance tests must be conducted...composition analysis, including measurement of oxygen...

  20. 40 CFR 60.2922 - How do I conduct the initial and annual performance test?

    Science.gov (United States)

    2010-07-01

    ...performance test? (a) All performance tests must consist of a...operations. (b) All performance tests must be conducted...this subpart. (c) All performance tests must be conducted...composition analysis, including measurement of oxygen...

  1. 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.

  2. CONFOCAL MICROSCOPY SYSTEM PERFORMANCE: QA TESTS, QUANTITATION AND SPECTROSCOPY

    Science.gov (United States)

    Confocal Microscopy System Performance: QA tests, Quantitation and Spectroscopy.Robert M. Zucker 1 and Jeremy M. Lerner 2,1Reproductive Toxicology Division, National Health and Environmental Effects Research Laboratory, Office of Research Development, U.S. Environmen...

  3. 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...

  4. Television computer games: a 'new look' in performance testing.

    Science.gov (United States)

    Kennedy, R S; Bittner, A C; Harbeson, M; Jones, M B

    1982-01-01

    Work at the Naval Biodynamics Laboratory aims at developing a battery of performance evaluation tests for environmental research (PETER). Because repeated-measures designs are virtually universal in environmental studies, the paradigm focuses on stabilisation with practice; thus far, over 50 tasks have been studied. The present report describes how five computerized video games fare as performance tests. The tasks were performed for 3 weeks each, in the same order, by the same subjects. The results show that four out of the five games meet all criteria satisfactorily and one does not, a favorable showing for the video games in comparison with conventional tests of either the paper-and-pencil or apparatus types. In terms of availability, equipment reliability, expense, and other practical considerations, the video games have many advantages. It is concluded that video games have considerable promise for performance testing and other applied contexts. PMID:7055490

  5. Adult Discrimination Performance for Pediatric Acuity Test Optotypes

    OpenAIRE

    CANDY, T. ROWAN; Mishoulam, Sylvia R.; Nosofsky, Robert M.; Dobson, Velma

    2011-01-01

    Pediatric acuity tests have a variety of optotype designs. Adult performance when discriminating these targets indicated that acuity estimates collected from children are likely to vary based solely on target design.

  6. US Department of Energy Central Training Academy performance testing fundamentals

    International Nuclear Information System (INIS)

    This paper reports that performance testing is required for training and inspection, and for validation of results of the vulnerability assessment which is a section of the US DOE Master Safeguards and Security Agreement (NSSA). It is essential, regardless of the reason for performing the test, that the collection of data be well planned to eliminate the bias of the data collector. Essential Elements of Analysis (EEA) is a proven technique that provides a systematic procedure for breaking down test objectives to obtain the optimum detailed measurement criteria. Developing clear, concise objectives removes most of the bias of the data collectors' observations. The EEA technique breaks down critical issues to a point at which test measurements and data can be quantified. Performance tests of procedures can be quantified using this technique, with a completed job task analysis serving as the basis for the EEA

  7. Performance Analysis of Hybrid Desiccant Chiller Based on Field Test

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Joon; Yun, Changho; Kang, Byung Ha [Kookmin Univ., Seoul (Korea, Republic of)

    2013-07-15

    Field tests of hybrid desiccant cooling systems were conducted from July to August 2011. Data were monitored and transferred in real time over the Internet. The monitored variables were analyzed to determine the performance characteristics under outdoor conditions. A series of system simulations has been conducted for outdoor conditions of the field tests. The results agree well with the experimental data in general. The system performance has been shown to deteriorate for wetter conditions, as predicted by the simulation.

  8. 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 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

  9. 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

  10. 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.

  11. SILEX final ground testing and in-flight performance assessment

    Science.gov (United States)

    Planche, Gilles; Laurent, Bernard; Guillen, Jean-Claude; Chorvalli, V.; Desplats, Eric

    1999-04-01

    SILEX (Semi-Conductor Inter-satellite Link EXperiment) consists of one optical terminal on-board the French LEO observation satellite SPOT 4, and another on-board the European GEO telecommunication satellite ARTEMIS. While the first part of the SILEX verification plan had been oriented towards verification at equipment and subsystem levels, the final stages have mainly been devoted to terminal and system (terminals coupling effects) verification. During this final stage, a thermal vacuum test was conducted in a class 100- cleanliness environment with optical ground support equipment of outstanding performances. The obtained tests results, used to determine software compensations and verify optical and static pointing performances, have been entered into overall system simulation models to finalize flight performances budgets. In addition, systems tests were performed on each terminal with respective partner simulator to validate system simulation models and assess link performances and robustness and to verify communication bit error rate.

  12. 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

  13. Effects of Reference Performance Testing During Aging Using Commercial Cells

    Energy Technology Data Exchange (ETDEWEB)

    Jon P. Christophersen; Chinh D. Ho; David Howell

    2005-07-01

    The Advanced Technology Development Program, under the oversight of the U.S. Department of Energy’s FreedomCAR and Vehicle Technologies Program, is investigating lithium-ion batteries for hybrid-electric vehicle applications. Cells are aged under various test conditions, including temperatures and states-of-charge. Life testing is interrupted at regular intervals to conduct reference performance tests (RPTs), which are used to measure changes in the electrical performance of the cells and then to determine cell degradation as a function of test time. Although designed to be unobtrusive, data from the Advanced Technology Development Gen 2 cells indicated that RPTs actually contributed to cell degradation and failure. A study was performed at the Idaho National Laboratory using commercially available lithium-ion cells to determine the impact of RPTs on life. A series of partial RPTs were performed at regular intervals during life testing and compared to a control group that was life tested without RPT interruption. It was determined that certain components of the RPT were detrimental, while others appeared to improve cell performance. Consequently, a new "mini" RPT was designed as an unobtrusive alternative. Initial testing with commercial cells indicates that the impact of the mini RPT is significantly less than the Gen 2 cell RPT.

  14. Test results of the DPC-TJ: mechanical performance

    International Nuclear Information System (INIS)

    The mechanical performance of the DPC-TJ coil was measured during the charge-up test by strain gauges and displacement gauges attached directly to the coil surface. To estimate winding stiffness, expansion tests were performed on a winding model at both 300 and 77K. The test results obtained with the DPC-TJ coil were compared with calculations obtained by the finite element method (FEM) analysis and expansion test results. Such comparison showed that equivalent Young's moduli calculated by the FEM were in good agreement with those measured during the charge-up test of the DPC-TJ coil, which had a higher rigidity than the winding model. As a result of the charge-up test, it was demonstrated that the DPC-TJ coil had high rigidity, as designed. (author)

  15. 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

  16. 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.

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

    OpenAIRE

    Minoo Alemi; Parviz Birjandi

    2010-01-01

    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 e...

  18. 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...

  19. 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

  20. 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.

  1. 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.

  2. 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

  3. Play for Performance: Using Computer Games to Improve Motivation and Test-Taking Performance

    Science.gov (United States)

    Dennis, Alan R.; Bhagwatwar, Akshay; Minas, Randall K.

    2013-01-01

    The importance of testing, especially certification and high-stakes testing, has increased substantially over the past decade. Building on the "serious gaming" literature and the psychology "priming" literature, we developed a computer game designed to improve test-taking performance using psychological priming. The game primed…

  4. Double-shell tank integrity assessments ultrasonic test equipment performance test

    Energy Technology Data Exchange (ETDEWEB)

    Pfluger, D.C.

    1996-09-26

    A double-shell tank (DST) inspection (DSTI) system was performance tested over three months until August 1995 at Pittsburgh, Pennsylvania, completing a contract initiated in February 1993 to design, fabricate, and test an ultrasonic inspection system intended to provide ultrasonic test (UT) and visual data to determine the integrity of 28 DSTs at Hanford. The DSTs are approximately one-million-gallon underground radioactive-waste storage tanks. The test was performed in accordance with a procedure (Jensen 1995) that included requirements described in the contract specification (Pfluger 1995). This report documents the results of tests conducted to evaluate the performance of the DSTI system against the requirements of the contract specification. The test of the DSTI system also reflects the performance of qualified personnel and operating procedures.

  5. Fan Noise Source Diagnostic Test: Rotor Alone Aerodynamic Performance Results

    Science.gov (United States)

    Hughes, Christopher E.; Jeracki, Robert J.; Woodward, Richard P.; Miller, Christopher J.

    2005-01-01

    The aerodynamic performance of an isolated fan or rotor alone model was measured in the NASA Glenn Research Center 9- by 15- Foot Low Speed Wind Tunnel as part of the Fan Broadband Source Diagnostic Test conducted at NASA Glenn. The Source Diagnostic Test was conducted to identify the noise sources within a wind tunnel scale model of a turbofan engine and quantify their contribution to the overall system noise level. The fan was part of a 1/5th scale model representation of the bypass stage of a current technology turbofan engine. For the rotor alone testing, the fan and nacelle, including the inlet, external cowl, and fixed area fan exit nozzle, were modeled in the test hardware; the internal outlet guide vanes located behind the fan were removed. Without the outlet guide vanes, the velocity at the nozzle exit changes significantly, thereby affecting the fan performance. As part of the investigation, variations in the fan nozzle area were tested in order to match as closely as possible the rotor alone performance with the fan performance obtained with the outlet guide vanes installed. The fan operating performance was determined using fixed pressure/temperature combination rakes and the corrected weight flow. The performance results indicate that a suitable nozzle exit was achieved to be able to closely match the rotor alone and fan/outlet guide vane configuration performance on the sea level operating line. A small shift in the slope of the sea level operating line was measured, which resulted in a slightly higher rotor alone fan pressure ratio at take-off conditions, matched fan performance at cutback conditions, and a slightly lower rotor alone fan pressure ratio at approach conditions. However, the small differences in fan performance at all fan conditions were considered too small to affect the fan acoustic performance.

  6. RTG performance on Galileo and Ulysses and Cassini test results

    International Nuclear Information System (INIS)

    Power output from telemetry for the two Galileo RTGs are shown from the 1989 launch to the recent Jupiter encounter. Comparisons of predicted, measured and required performance are shown. Similar comparisons are made for the RTG on the Ulysses spacecraft which completed its planned mission in 1995. Also presented are test results from small scale thermoelectric modules and full scale converters performed for the Cassini program. The Cassini mission to Saturn is scheduled for an October 1997 launch. Small scale module test results on thermoelectric couples from the qualification and flight production runs are shown. These tests have exceeded 19,000 hours are continuing to provide increased confidence in the predicted long term performance of the Cassini RTGs. Test results are presented for full scale units both ETGs (E-6, E-7) and RTGs (F-2, F-5) along with mission power predictions. F-5, fueled in 1985, served as a spare for the Galileo and Ulysses missions and plays the same role in the Cassini program. It has successfully completed all acceptance testing. The ten years storage between thermal vacuum tests is the longest ever experienced by an RTG. The data from this test are unique in providing the effects of long term low temperature storage on power output. All ETG and RTG test results to date indicate that the power requirements of the Cassini spacecraft will be met. BOM and EOM power margins of at least five percent are predicted. copyright 1997 American Institute of Physics

  7. RTG performance on Galileo and Ulysses and Cassini test results

    International Nuclear Information System (INIS)

    Power output from telemetry for the two Galileo RTGs are shown from the 1989 launch to the recent Jupiter encounter. Comparisons of predicted, measured and required performance are shown. Similar comparisons are made for the RTG on the Ulysses spacecraft which completed its planned mission in 1995. Also presented are test results from small scale thermoelectric modules and full scale converters performed for the Cassini program. The Cassini mission to Saturn is scheduled for an October 1997 launch. Small scale module test results on thermoelectric couples from the qualification and flight production runs are shown. These tests have exceeded 19,000 hours are continuing to provide increased confidence in the predicted long term performance of the Cassini RTGs. Test results are presented for full scale units both ETGs (E-6, E-7) and RTGs (F-2, F-5) along with mission power predictions. F-5, fueled in 1985, served as a spare for the Galileo and Ulysses missions and plays the same role in the Cassini program. It has successfully completed all acceptance testing. The ten years storage between thermal vacuum tests is the longest ever experienced by an RTG. The data from this test are unique in providing the effects of long term low temperature storage on power output. All ETG and RTG test results to date indicate that the power requirements of the Cassini spacecraft will be met. BOM and EOM power margins of at least five percent are predicted

  8. Thermal performance analysis of an MHD simulation test facility

    International Nuclear Information System (INIS)

    To evaluate the performance of the downstream components of a coal-fired, baseline, open cycle MHD power plant, Mississippi State University has set up a simulation test facility. Reduced thermal data from this test stand for steady-state operating conditions are presented in the paper. A thermal model to predict the variation of important thermal parameters in the test stand is shown. Results from the reduced experimental data and the predictive thermal model are compared. In addition, results for calibration runs and from recent secondary combustion tests are discussed. 7 refs

  9. 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...

  10. 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

  11. Symptom validity test performance in the Huntington Disease Clinic.

    Science.gov (United States)

    Sieck, Barbara C; Smith, Megan M; Duff, Kevin; Paulsen, Jane S; Beglinger, Leigh J

    2013-03-01

    Symptom validity tests (SVTs) are often used in neuropsychological assessment; however, recent studies indicate that cognitive impairment/dementia may contribute to failing scores on some effort tests. The purpose of this study was to characterize how individuals with Huntington disease (HD) perform on three SVTs and to examine the relationship between SVT performance and demographic and clinical variables. Results indicate that while the majority of HD patients passed the Repeatable Battery for the Assessment of Neuropsychological Status (RBANS) Effort Index (EI; 82% of n = 121) and the Test of Memory Malingering (92% of n = 36), failure of these SVTs was associated with poorer cognitive and adaptive functioning, and greater motor impairment. Results showed that less than one-third passed the RBANS Effort Scale (ES; 30% of n = 43) and few clinical and demographic variables were correlated with this SVT performance. Although some SVTs may be better suited to HD, cognitive ability should be considered when evaluating effort in HD. PMID:23266566

  12. 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

  13. 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)

  14. Results of radiation hardness tests and performance tests of the HS9008RH flash ADC

    International Nuclear Information System (INIS)

    Results from tests characterizing the performance and radiation hardness of the HS9008RH flash analog to digital converter (FADC) are presented. These tests were performed primarily to evaluate the suitability of this device for use in the GEM Central Tracker at the SSC experiment. Basic performance characteristics and susceptibility of these characteristics to radiation were examined. Performance test results indicate that the device integral nonlinearity is sampling rate dependent and worsens rapidly above rate of 15 megasamples per second (MSPS). No degradation in performance of the device was observed after its exposure of up to 81 Mrad of 1.25 MeV ? radiation from a 60Co source. Exposure of the device to a reactor fast neutron fluence (E > 100keV) of 5 x 1014/cm2 resulted in no significant observed performance degradation as well

  15. 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...

  16. Dynamic Stress Test Diffusion Model Considering the Credit Score Performance

    OpenAIRE

    Genest, Benoit; Fares, Ziad; Gombert, Arnault

    2014-01-01

    After the crisis of 2008, and the important losses and shortfall in capital that it revealed, regulators conducted massive stress testing exercises in order to test the resilience of financial institutions in times of stress conditions. In this context, and considering the impact of these exercises on the banks’ capital, organization and image, this white paper proposes a methodology that diffuses dynamically the stress on the credit rating scale while considering the performance of the credi...

  17. 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.

  18. Delay model and performance testing for FPGA carry chain TDC

    International Nuclear Information System (INIS)

    Time-of-flight (TOF) information would improve the performance of PET (position emission tomography). TDC design is a key technique. It proposed Carry Chain TDC Delay model. Through changing the significant delay parameter of model, paper compared the difference of TDC performance, and finally realized Time-to-Digital Convertor (TDC) based on Carry Chain Method using FPGA EP2C20Q240C8N with 69 ps LSB, max error below 2 LSB. Such result could meet the TOF demand. It also proposed a Coaxial Cable Measuring method for TDC testing, without High-precision test equipment. (authors)

  19. 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)

  20. 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)

  1. 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%.

  2. A general test for distortions in performance measures

    OpenAIRE

    COURTY, Pascal; Marschke, Gerald

    2008-01-01

    Results from the incentive literature suggest that performance measures are often distorted, eliciting dysfunctional and unintended responses. The existence of these responses, however, is difficult to demonstrate in practice because this behavior is typically hidden from the researcher. We present a simple model showing that one can test for the existence of distortions by estimating the change in the association between a performance measure and the true goal of the organization with the me...

  3. 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)

  4. 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,…

  5. 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)

  6. Radiometric instrumentation and measurements guide for photovoltaic performance testing

    Energy Technology Data Exchange (ETDEWEB)

    Myers, D.

    1997-04-01

    The Photovoltaic Module and Systems Performance and Engineering Project at the National Renewable Energy Laboratory performs indoor and outdoor standardization, testing, and monitoring of the performance of a wide range of photovoltaic (PV) energy conversion devices and systems. The PV Radiometric Measurements and Evaluation Team (PVSRME) within that project is responsible for measurement and characterization of natural and artificial optical radiation which stimulates the PV effect. The PV manufacturing and research and development community often approaches project members for technical information and guidance. A great area of interest is radiometric instrumentation, measurement techniques, and data analysis applied to understanding and improving PV cell, module, and system performance. At the Photovoltaic Radiometric Measurements Workshop conducted by the PVSRME team in July 1995, the need to communicate knowledge of solar and optical radiometric measurements and instrumentation, gained as a result of NREL`s long-term experiences, was identified as an activity that would promote improved measurement processes and measurement quality in the PV research and manufacturing community. The purpose of this document is to address the practical and engineering need to understand optical and solar radiometric instrument performance, selection, calibration, installation, and maintenance applicable to indoor and outdoor radiometric measurements for PV calibration, performance, and testing applications. An introductory section addresses radiometric concepts and definitions. Next, concepts essential to spectral radiometric measurements are discussed. Broadband radiometric instrumentation and measurement concepts are then discussed. Each type of measurement serves as an important component of the PV cell, module, and system performance measurement and characterization process.

  7. Examinee Background Characteristics and GRE General Test Performance.

    Science.gov (United States)

    Stricker, Lawrence J.; Rock, Donald A.

    1995-01-01

    The relations between examinee background characteristics and performance on the Graduate Record Examinations (GRE) General Test were studied through structural equation modeling for 3,145 examinees. Findings regarding examinee characteristics underscore the importance of socioeconomic status and intervening process variables in research on group…

  8. Impulsivity and Speed-Accuracy Strategies in Intelligence Test Performance.

    Science.gov (United States)

    Phillips, Louise H.; Rabbitt, Patrick M. A.

    1995-01-01

    Whether relations between intelligence test performance and information processing measures depend on individual differences in speed-accuracy preferences rather than capacity limitations and whether the impact of strategic variables changes with increasing age or extraversion was studied with 83 adults ages 50 to 79 years. Results are discussed…

  9. 42 CFR 493.15 - Laboratories performing waived tests.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Laboratories performing waived tests. 493.15 Section 493.15 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN... rate—non-automated; (6) Hemoglobin—copper sulfate—non-automated; (7) Blood glucose by...

  10. 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.

  11. Developing and Testing the Guitar Songleading Performance Scale (GSPS)

    Science.gov (United States)

    Silverman, Michael J.

    2011-01-01

    Guitar songleading is a critical component in music education and music therapy training curricula. However, at present, there is no standardized instrument to evaluate guitar songleading performance that is both valid and reliable. The purpose of this article is to describe the construction, development, and testing of a guitar songleading…

  12. The SPIN project: testing of safety and performance indicators

    Energy Technology Data Exchange (ETDEWEB)

    Storck, R.; Becker, D.A. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Braunschweig (Germany); Alonso, J. [ENRESA (Spain); Hugi, M. [Nagra (Switzerland); Niemeyer, M. [Colenco (Switzerland); Laciok, A. [NRI (Czech Republic); Marivoet, J.; O' Sullivan, P. [NRG (Netherlands); Nordman, H. [VTT (Finland)

    2002-07-01

    Safety and performance indicators, as meant in this paper, are quantities following from a numerical performance assessment calculation for a repository, which allow an evaluation of the results, either by providing a measure for the overall safety of the system (safety indicators) or by demonstrating the functioning of the barrier system (performance indicators). The most commonly used safety indicator is the effective dose rate, the use of additional indicators, however, may increase the trust in model calculations. In the EC funded SPIN project a number of safety and performance indicators have been identified and systematically tested by re-calculating recent PA studies. The different indicators have been compared and assessed regarding their suitability and applicability in performance assessments. The indicator identification and assessment procedures are explained in this paper, and some results are presented. (orig.)

  13. Performance and endurance tests of a laboratory model multipropellant resistojet

    Science.gov (United States)

    Morren, W. Earl; Whalen, Margaret V.; Sovey, James S.

    1990-01-01

    This paper presents the results of an effort to demonstrate the technological readiness of a long-life multipropellant resistojet for Space Station auxiliary propulsion. A laboratory model resistojet made from grain-stabilized platinum served as a test bed to evaluate the design characteristics, fabrication methods, and operating strategies for an engineering model multipropellant resistojet developed as part of the NASA Space Station propulsion system Advanced Development Program. The laboratory model thruster was characterized for performance on a variety of fluids expected to be available onboard a Space Station, then subjected to a 2000-h, 2400-thermal-cycle endurance test using carbon dioxide propellant. Maximum thruster temperatures were approximately 1400 C. Significant observations from the laboratory model thruster performance and endurance tests are discussed as they relate to the design of the engineering model thruster.

  14. Leak and burst tests performed on pulled tubes

    International Nuclear Information System (INIS)

    The plugging criteria for tubes used in France for PWR plant steam generator tubes allow the presence of through wall cracks during operation. Calculations and tests show the cracks remain stable under accidental conditions and feedback shows that they do not generally result in large leaks. Tests performed on pulled tubes confirm the safety margins provided by the plugging criteria selected with respect to the risks of leakage and sudden propagation of corrosion cracks under accidental conditions. This paper proposes a method for roughly estimating the leakage rate under accidental conditions for a steam generator with corrosion at the top of the tubesheet or at the tube support plate elevation, which is based on tests performed exclusively on pulled tubes and the results of on-site inspections. (authors). 3 figs., 2 tabs., 7 refs

  15. 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.

  16. Step-feed biofiltration: a low cost alternative configuration for off-gas treatment.

    Science.gov (United States)

    Estrada, José M; Quijano, Guillermo; Lebrero, Raquel; Muñoz, Raúl

    2013-09-01

    Clogging due to biomass accumulation and the loss of structural stability of the packing media are common operational drawbacks of standard gas biofiltration inherent to the traditional biofilter design, which result in prohibitive pressure drop buildups and media channeling. In this work, an innovative step-feed biofilter configuration, with the air emission supplied in either two or three locations along the biofilter height, was tested and compared with a standard biofilter using toluene as a model pollutant and two packing materials: compost and perlite. When using compost, the step-feed biofilter supported similar elimination capacities (EC ? 80 g m(-3) h(-1)) and CO2 production rates (200 g m(-3) h(-1)) to those achieved in the standard biofilter. However, while the pressure drop in the step-feed system remained below 300 Pa m bed(-1) for 61 days, the standard biofilter reached this value in only 14 days and 4000 Pa m bed(-1) by day 30, consuming 75% more compression energy throughout the entire operational period. Operation with perlite supported lower ECs compared to compost in both the step-feed and standard biofilters (? 30 g m(-3) h(-1)), probably due to the high indigenous microbial diversity present in this organic packing material. The step-feed biofilter exhibited 65% lower compression energy requirements than the standard biofilter during operation with perlite, while supporting similar ECs. In brief, step-feed biofiltration constitutes a promising operational strategy capable of drastically reducing the operating costs of biofiltration due to a reduced energy consumption and an increased packing material lifespan. PMID:23764582

  17. 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

  18. Standardization of test conditions for gamma camera performance measurement

    International Nuclear Information System (INIS)

    The actual way of measuring gamma camera performance is to use point sources or flood sources in air, often in combination with bar phantoms. This method mostly brings best performance parameters for cameras but it has nothing in common with the use of a camera in clinical practice. Particular in the case of low energy emitters, like Tc-99m, the influence of scattered radiation over the performance of cameras is very high. Therefore it is important to have test conditions of radionuclide imaging devices, that will approach as best as practicable the measuring conditions in clinical applications. It is therefore a good news that the International Electrochemical Commission IEC has prepared a draft 'Characteristics and test conditions of radionuclide imaging devices' which is now submitted to the national committees for formal approval under the Six Months' Rule. Some essential points of this document are discussed in the paper. (orig.)

  19. The performance testing of timing measurement of BES III MDC electronics

    International Nuclear Information System (INIS)

    This paper outlines the testing methods and the tested results for the performance of the timing measurement system in BESIII MDC electronics. The testing mainly includes the time resolution testing, time differential nonlinearity testing and time integral nonlinearity testing. (authors)

  20. 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).

  1. 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.

  2. 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)

  3. 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.

  4. Design and operation of off-gas cleaning and ventilation systems in facilities handling low and intermediate level radioactive material

    International Nuclear Information System (INIS)

    The number of developing countries constructing new nuclear facilities is increasing. These facilities include the production and processing of radioisotopes, as well as all types of laboratories and installations, which handle radioactive material and deal with the treatment of radioactive wastes. Ventilation and air cleaning systems are a vital part of the general design of any nuclear facility. The combination of a well designed ventilation system with thorough cleaning of exhaust air is the main method of preventing radioactive contamination of the air in working areas and in the surrounding atmosphere. This report provides the latest information on the design and operation of off-gas cleaning and ventilation systems for designers and regulatory authorities in the control and operation of such systems in nuclear establishments. The report presents the findings of an Advisory Group Meeting held in Vienna from 1 to 5 December 1986 and attended by 12 experts from 11 Member States. Following this meeting, a revised report was prepared by the International Atomic Energy Agency Secretariat and three consultants, M.J. Kabat (Canada), W. Stotz (Federal Republic of Germany) and W.A. Fairhurst (United Kingdom). The final draft was commented upon and approved by the participants of the meeting. 69 refs, 37 figs, 12 tabs

  5. Standardization in Cryogenic Insulation Systems Testing and Performance Data

    Science.gov (United States)

    Fesmire, James E.

    The close relationship between industrial energy use and cryogenics drives the need for optimized thermal insulation systems. Emerging cryofuels usage is enabled by adequate isolation of the liquid hydrogen or liquefied natural gas from the ambient environment. Thermal performance data for the total insulation system, as rendered, are essential for both engineering designs and cost-benefit decisions involving comparisons among alternatives. These data are obtained through rigorous testing with suitable apparatus and repeatable methods. Properly defined terminology, analysis, and reporting are also vital. Advances in cryogenic insulation test apparatus and methods have led to the recent addition of two new technical standards of ASTM International: C1774 - Standard Guide for Thermal Performance Testing of Cryogenic InsulationSystems and C740 - Standard Guide for Evacuated Reflective Cryogenic Insulation. Among the different techniques described in the new standards is the cylindrical boiloff calorimeter for absolute heat measurement over the full range of vacuum pressure conditions. The details of this apparatus, test method, and data analysis are given. Benchmark thermal performance data, including effective thermal conductivity (ke) and heat flux (q) for the boundary temperatures of 293 K and 77 K, are given for a number of different multilayer insulation (MLI) systems in comparison with data for other commonly-used insulation systems including perlite powder, fiberglass, polyurethane foam, and aerogels.

  6. The effect of motivational music on wingate anaerobic test performance

    Directory of Open Access Journals (Sweden)

    Özkan I??k

    2015-09-01

    Full Text Available The aim of this study is to examine the effect of the motivational music on the Wingate Anaerobic Test (WAnT performance. 16 male students who studied at School of Physical Education and Sports, Kocatepe University participated in the study voluntarily. After demographic characteristics of the voluntaries [age, height, body weight (BW, body mass index (BMI] were measured without music (pre-test and with motivational music [>120 bpm (beats per minute] conditions (post-test. For the analyses of the data; Wilcoxon Rank Test was used in order to detect the difference among the variables. As a result of the measurements taken in with and without music conditions; it was found out that there was a statistically significant difference on behalf of condition with music in terms of maximum anaerobic power (MaxAP, maximum anaerobic capacity (MAC, relative anaerobic power (RAP, relative anaerobic capacity (RAC and fatigue index (FI values (p0,05. It was determined that the motivational music has positive effects on the WAnT performance. However; although it was seen that motivational music increased the WAnT performance, we were of the opinion that this effect emerged thanks to the increased psycho-physiological factors caused by music.

  7. Small-scale chamber test for internal blast performance

    International Nuclear Information System (INIS)

    The viability of using gram-scale amounts of explosives in a small test chamber to assess internal blast performance and predict effects at larger scales is investigated. Peak quasi-static pressures from five explosive formulations were measured, and energy released per gram was calculated. The smaller test used 12-g charges loaded in a steel holder, while data selected from the larger test was from bare charges between 2.7 and 21 kg. The energies for a given explosive were comparable for each size charge tested in the larger chamber. In the smaller chamber the energies were less, most likely due to heat losses to the holder. Explosives with the highest concentration of explosive ingredients incurred the highest energy losses in the small chamber. The current design of the smaller test provides a reasonable ranking of explosives with similar concentrations of explosive ingredients, thereby validating the use of the test for the newer explosives being assessed. However, it may be possible to obtain consistent rankings for all explosives given a change to the holder design in the smaller test.

  8. 40 CFR 62.14650 - How do I conduct the initial and annual performance test?

    Science.gov (United States)

    2010-07-01

    ...the waste burned during the performance test is representative...of waste burned during the performance test. (c) All performance tests must be conducted...composition analysis, including measurement of oxygen...

  9. 40 CFR 60.2125 - How do I conduct the initial and annual performance test?

    Science.gov (United States)

    2010-07-01

    ...the waste burned during the performance test is representative...of waste burned during the performance test. (c) All performance tests must be conducted...composition analysis, including measurement of oxygen...

  10. 40 CFR 60.2690 - How do I conduct the initial and annual performance test?

    Science.gov (United States)

    2010-07-01

    ...the waste burned during the performance test is representative...of waste burned during the performance test. (c) All performance tests must be conducted...composition analysis, including measurement of oxygen...

  11. 40 CFR 63.7187 - What performance tests and other compliance procedures must I use?

    Science.gov (United States)

    2010-07-01

    ...conducting the applicable performance test requirements specified in Table...calculations, as with performance tests (as specified in § 63...calculations, or performance test. (c) If you are using...the pollutant concentration or parametric signal analyzer, and the...

  12. SRNL report for the tank waste disposition integrated flowsheet: Corrosion testing

    Energy Technology Data Exchange (ETDEWEB)

    Wyrwas, R. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-09-30

    A series of cyclic potentiodynamic polarization (CPP) tests were performed in support of the Tank Waste Disposition Integrated Flowsheet (TWDIF). The focus of the testing was to assess the effectiveness of the SRNL model for predicting the amount of nitrite inhibitor needed to prevent pitting induced by increasing halide concentrations. The testing conditions were selected to simulate the dilute process stream that is proposed to be returned to tank farms from treating the off-gas from the low activity waste melter in the Waste Treatment and Immobilization Plant.

  13. SRNL report for the tank waste disposition integrated flowsheet: Corrosion testing

    International Nuclear Information System (INIS)

    A series of cyclic potentiodynamic polarization (CPP) tests were performed in support of the Tank Waste Disposition Integrated Flowsheet (TWDIF). The focus of the testing was to assess the effectiveness of the SRNL model for predicting the amount of nitrite inhibitor needed to prevent pitting induced by increasing halide concentrations. The testing conditions were selected to simulate the dilute process stream that is proposed to be returned to tank farms from treating the off-gas from the low activity waste melter in the Waste Treatment and Immobilization Plant.

  14. 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.

  15. 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

  16. 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.

  17. Orion Launch Abort System Performance on Exploration Flight Test 1

    Science.gov (United States)

    McCauley, R.; Davidson, J.; Gonzalez, Guillermo

    2015-01-01

    This paper will present an overview of the flight test objectives and performance of the Orion Launch Abort System during Exploration Flight Test-1. Exploration Flight Test-1, the first flight test of the Orion spacecraft, was managed and led by the Orion prime contractor, Lockheed Martin, and launched atop a United Launch Alliance Delta IV Heavy rocket. This flight test was a two-orbit, high-apogee, high-energy entry, low-inclination test mission used to validate and test systems critical to crew safety. This test included the first flight test of the Launch Abort System preforming Orion nominal flight mission critical objectives. NASA is currently designing and testing the Orion Multi-Purpose Crew Vehicle (MPCV). Orion will serve as NASA's new exploration vehicle to carry astronauts to deep space destinations and safely return them to earth. The Orion spacecraft is composed of four main elements: the Launch Abort System, the Crew Module, the Service Module, and the Spacecraft Adapter (Fig. 1). The Launch Abort System (LAS) provides two functions; during nominal launches, the LAS provides protection for the Crew Module from atmospheric loads and heating during first stage flight and during emergencies provides a reliable abort capability for aborts that occur within the atmosphere. The Orion Launch Abort System (LAS) consists of an Abort Motor to provide the abort separation from the Launch Vehicle, an Attitude Control Motor to provide attitude and rate control, and a Jettison Motor for crew module to LAS separation (Fig. 2). The jettison motor is used during a nominal launch to separate the LAS from the Launch Vehicle (LV) early in the flight of the second stage when it is no longer needed for aborts and at the end of an LAS abort sequence to enable deployment of the crew module's Landing Recovery System. The LAS also provides a Boost Protective Cover fairing that shields the crew module from debris and the aero-thermal environment during ascent. Although the Orion Program has tested a number of the critical systems of the Orion spacecraft on the ground, the launch environment cannot be replicated completely on Earth. A number of flight tests have been conducted and are planned to demonstrate the performance and enable certification of the Orion Spacecraft. Exploration Flight Test 1, the first flight test of the Orion spacecraft, was successfully flown on December 5, 2014 from Cape Canaveral Air Force Station's Space Launch Complex 37. Orion's first flight was a two-orbit, high-apogee, high-energy entry, low-inclination test mission used to validate and test systems critical to crew safety, such as heat shield performance, separation events, avionics and software performance, attitude control and guidance, parachute deployment and recovery operations. One of the key separation events tested during this flight was the nominal jettison of the LAS. Data from this flight will be used to verify the function of the jettison motor to separate the Launch Abort System from the crew module so it can continue on with the mission. The LAS nominal jettison event on Exploration Flight Test 1 occurred at six minutes and twenty seconds after liftoff (See Fig. 3). The abort motor and attitude control motors were inert for Exploration Flight Test 1, since the mission did not require abort capabilities. A suite of developmental flight instrumentation was included on the flight test to provide data on spacecraft subsystems and separation events. This paper will focus on the flight test objectives and performance of the LAS during ascent and nominal jettison. Selected LAS subsystem flight test data will be presented and discussed in the paper. Exploration Flight Test -1 will provide critical data that will enable engineering to improve Orion's design and reduce risk for the astronauts it will protect as NASA continues to move forward on its human journey to Mars. The lessons learned from Exploration Flight Test 1 and the other Flight Test Vehicles will certainly contribute to the vehicle architecture of a human-rated space launch vehicle.

  18. Operating conditions of the SP-1 fuel test: a basis for post-test performance analysis

    International Nuclear Information System (INIS)

    Two fast reactor irradiation tests, SP-1 and SP-2, provide a unique and self-consistent data set with which to evaluate the technical feasibility issues of potential fuel systems for the SP-100 space reactor. The first of these tests, SP-1, has completed its first irradiation period and is undergoing nondestructive and destructive examination. The results of these examinations will be reported in a separate paper in this session. An understanding of the fuel element and test capsule design and operating conditions is important to the interpretation and correct extrapolation of the observed performance. This paper discusses the procedures used to determine the SP-1 irradiation test operating conditions

  19. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Gildea, P.D.; Wall, W.R.; Gede, V.P.

    1978-05-01

    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.

  1. Performance testing of 3D point cloud software

    Science.gov (United States)

    Varela-González, M.; González-Jorge, H.; Riveiro, B.; Arias, P.

    2013-10-01

    LiDAR systems are being used widely in recent years for many applications in the engineering field: civil engineering, cultural heritage, mining, industry and environmental engineering. One of the most important limitations of this technology is the large computational requirements involved in data processing, especially for large mobile LiDAR datasets. Several software solutions for data managing are available in the market, including open source suites, however, users often unknown methodologies to verify their performance properly. In this work a methodology for LiDAR software performance testing is presented and four different suites are studied: QT Modeler, VR Mesh, AutoCAD 3D Civil and the Point Cloud Library running in software developed at the University of Vigo (SITEGI). The software based on the Point Cloud Library shows better results in the loading time of the point clouds and CPU usage. However, it is not as strong as commercial suites in working set and commit size tests.

  2. Performance verification tests of JT-60SA CS model coil

    Science.gov (United States)

    Obana, Tetsuhiro; Murakami, Haruyuki; Takahata, Kazuya; Hamaguchi, Shinji; Chikaraishi, Hirotaka; Mito, Toshiyuki; Imagawa, Shinsaku; Kizu, Kaname; Natsume, Kyohei; Yoshida, Kiyoshi

    2015-11-01

    As a final check of the coil manufacturing method of the JT-60 Super Advanced (JT-60SA) central solenoid (CS), we verified the performance of a CS model coil. The model coil comprised a quad-pancake wound with a Nb3Sn cable-in-conduit conductor. Measurements of the critical current, joint resistance, pressure drop, and magnetic field were conducted in the verification tests. In the critical-current measurement, the critical current of the model coil coincided with the estimation derived from a strain of -0.62% for the Nb3Sn strands. As a result, critical-current degradation caused by the coil manufacturing process was not observed. The results of the performance verification tests indicate that the model coil met the design requirements. Consequently, the manufacturing process of the JT-60SA CS was established.

  3. 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.

  4. 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

  5. Round robin performance testing of organic photovoltaic devices

    DEFF Research Database (Denmark)

    Gevorgyan, Suren; Zubillaga, Oihana; de Seoane, José María Vega; Machado, Maider; Parlak, Elif Alturk; Tore, Nesrin; Voroshazi, Eszter; Aernouts, Tom; Müllejans, Harald; Bardizza, Giorgio; Taylor, Nigel; Verhees, Wiljan; Kroon, Jan M.; Morvillo, Pasquale; Minarini, Carla; Roca, Francesco; Castro, Fernando A.; Cros, Stéphane; Lechêne, Balthazar; Trigo, Juan F.; Guillén, Cecilia; Herrero, Jose; Zimmermann, Birger; Sapkota, Subarna Babu; Veit, Clemens; Würfel, Uli; Tuladhar, Pabitra S.; Durrant, James R.; Winter, Stefan; Rousu, Sanna; Välimäki, Marja; Hinrichs, Volker; Cowan, Sarah R.; Olson, Dana C.; Sommer-Larsen, Peter; Krebs, Frederik C

    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 certifi...

  6. Field hydraulic tests improve HPHT drilling safety and performance

    Energy Technology Data Exchange (ETDEWEB)

    Isambourg, P.; Bertin, D.L.; Brangetto, M.

    1999-12-01

    For the Elgin-Franklin UKCS fields, drilling of the high pressure/high temperature (HPHT) phase is critical due to the narrow margin between formation pore and fracturation pressures. This problem is accentuated by the extreme temperature (up to 205 C--400 F) and pressure (up to 1,200 bar--17,400 psi). A new generation of down-hole pressure while drilling (PWD) tools allows a better real-time monitoring of the bottom-hole pressure, but cannot withstand the extreme temperature of the entire HPHT phase. Furthermore, down-hole and surface pressures are dependent on complex hydraulic phenomena which make predictions challenging. Consequently, it was decided to perform hydraulic tests before drilling the HPHT section of the well 22/30c-G4 (first Elgin development well), in order to quantify the surface and down-hole pressures and temperatures on several operating conditions: circulating (with and without pipe rotation), tripping and flow check. Gelation tests, trapped pressure as well as pressure transmission tests were also performed. Objectives of these tests were to better understand some complex down-hole physical phenomena, to prepare practical guidelines, before drilling HPHT section, to check reliability and accuracy of new real-time PWD tools, and to collect accurate well data for further hydraulic software packages validation of improvement. These procedures led to great benefits, both in terms of safety and performance, when drilling the HPHT phases of the well: results were considered as highly positive. This paper details down-hole measurement procedures and results, operational guide lines, tools performances, lessons learned, and explains how to cope with sources of possible discrepancies between actual values and software predictions.

  7. Reflectors for SAR performance testing-second edition

    Energy Technology Data Exchange (ETDEWEB)

    Doerry, Armin Walter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-02-01

    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.

  8. Syntax Editing for Mark 4-A System Performance Test Software

    Science.gov (United States)

    Jacobson, G. N.

    1983-01-01

    This article describes the syntax editing concepts used by the Operations Sustaining Engineering Section in implementing System Performance Test software for the Mark 4-A era. The processing functions are discussed, as well as the necessary data structures and table generation macros used in implementing those functions. In addition, the procedural and software interfaces which have been developed for users of the syntax editor are described, including the forms required for establishing directive and parameter characteristics.

  9. Eurados trial performance test for neutron personal dosimetry

    DEFF Research Database (Denmark)

    Bordy, J.M.; Stadtmann, H.; Ambrosi, P.; Bartlett, D.T.; Christensen, P.; Colgan, T.; Hyvonen, H.

    2001-01-01

    This paper reports on the results of a neutron trial performance test sponsored by the European Commission and organised by EURADOS. As anticipated, neutron dosimetry results were very dependent on the dosemeter type and the dose calculation algorithm. Fast neutron fields were generally well measured, but particular problems were noted in the determination of intermediate energy fields and large incident angles, demonstrating the difficulties of neutron personal dosimetry. Of particular concern ...

  10. Design of performance testing system of superconducting strand sample

    International Nuclear Information System (INIS)

    Critical current is an important property of superconducting magnets, as well as the effect of temperature and magnetic field on the superconducting properties should be studied. The superconducting strand properties have close link with the performance of the coils in operation. In this paper a set of automatic testing system based on PC is introduced, which is designed for critical performance testing of ITER superconducting Nb3Sn strand samples. To measure critical current of superconducting strand, the background field is supplied by a magnet which is a high field superconducting magnet designed to produce fields up to 16 Tesla, and the direction of the magnetic field is vertical to the sample. Temperature in the testing dewar is automatically adjusted by a PID controller. And the temperature of strand sample can be controlled by regulating the vacuum valve. To meet the testing criteria the testing system is developed to acquire real-time and high accuracy data. Sensors with high accuracy and anti-magnetic capacity are selected and installed cautiously. Signal lines are wired normatively. Keithley programmable meters, communication cards and data acquisition card with good performance are included in hardware system. The software is programmed with Visual C++ 6.0 computer language, meanwhile, the Microsoft Access database and SCPI (Standard Command for Programmable Instrument) language are integrated in the software. Several methods have been used in order to show lab assistants experimental process clearly and timely. How to operate right and exclude complicated field noise is listed and error in experimental data is also calculated accurately. Measurement precision lower than 1uV is obtained despite kinds of noise interference. It proves to be a reliable system to meet the demands of ITER through experiments. (author)

  11. Off gas sampling device

    International Nuclear Information System (INIS)

    A mist filter collects radioactive mists of Cs-137, Ru-106 and Tc-99, in which a first absorbing tube collects C-14, H-3, I-129 and nitrogen dioxide and carbon dioxide among radioactive gases. An oxidation bubbler oxidizes carbon monoxide not collected by the first absorbing tube to carbon dioxide so as to make the carbon dioxide to be absorbed to the second absorbing tube. A H-3-C-14 collecting device collects H-3 in a state of hydrogen and organized H-3, C-14 and I-129. All of these mist filter, first and second absorbing tubes, oxidation bubbler and H-3-C-14 collecting device are contained in an air tight box and arranged compact so that a sampling gas flows in this order. The inside of the air tight box is kept at a negative pressure by an evacuating device in order to confine the radioactive gases. (N.H.)

  12. 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.

  13. Performance tests of HENDEL M2+A loop

    International Nuclear Information System (INIS)

    The helium engineering demonstration loop (HENDEL) consists of the first and second helium loops (M1 and M2 loops), adapter helium loop (A loop) and six test sections, the first of which was completed and the others to be designed. This report describes operational data of components (heater, blower and cooler) and overall performance of the second helium loop (M2 loop) and adapter helium loop (A loop), during the test operation until March 1983. Finally M2 and A loops were confirmed to be able to provide helium gas up to 1,0000C, 4.0 kg/s and 4.0 MPa to the in-core structure test section (T2) and the others which are to be installed. (author)

  14. 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.

  15. 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.

  16. The Gaia challenge: testing high performance CCDs in large quantities

    Science.gov (United States)

    Walker, Andrew; Eaton, Tim; Steward, Roy; Turton, John; Knoepfle, Anthony; Wynne, Tom; Gillespie, Peter; Curnock, Alastair; Cooper, David; Evans, Arwel; Watcham, Matt

    2008-10-01

    Gaia, funded by ESA with EADS Astrium as the prime contractor, is an ambitious space observatory designed to measure the positions of around one billion stars with unprecedented accuracy and is currently planned for launch in 2011. The Gaia instrument will feature a focal plane containing 106 large area CCD91-72s manufactured by e2v technologies. This will be the largest CCD focal plane ever flown in space covering an area of 0.286m2. To ensure that the devices meet the required high specification, they undergo significant testing before being accepted by the end user. This involves geometrical, mechanical, environmental, endurance, electrical and electro-optical testing. With the flight phase contract for Gaia requiring the delivery of 130 flight grade devices (plus another 40 engineering devices of various grades), the volume of testing is an order of magnitude greater than and of similar timescale to, the typical space programmes e2v technologies are involved with. This paper will begin by providing an overview of the Gaia mission and the custom CCD91-72 that e2v technologies have designed for it. Next the various phases of the Gaia programme will be outlined and how e2v approached the test requirements for each stage. Problems encountered, lessons learned, and technical and logistical solutions implemented at each stage will be presented, to discuss how e2v technologies improved the quality of the test data whilst reducing the test times. There will be particular emphasis on the electro-optical testing and the test cameras on which this is performed.

  17. Pilot test of ANSI draft standard N13.29 environmental dosimetry -- Performance criteria for testing

    International Nuclear Information System (INIS)

    American National Standards Institute Draft N13.29 describes performance tests for environmental radiation dosimetry providers. If approved it would be the first step toward applying the types of performance testing now required in personnel dosimetry to environmental radiation monitoring. The objective of this study was to pilot test the draft standard, before it undergoes final balloting, on a small group of dosimetry providers that were selected to provide a mix of facility types, thermoluminescent dosimeter designs and monitoring program applications. The first phase of the pilot test involved exposing dosimeters to laboratory photon, beta, and x-ray sources at routine and accident dose levels. In the second phase, dosimeters were subjected to ninety days of simulated environmental conditions in an environmental chamber that cycled through extremes of temperature and humidity. Two out of seven participants passed all categories of the laboratory testing phase, and all seven passed the environmental test phase. While some relatively minor deficiencies were uncovered in the course of the pilot test, the results show that draft N13.29 describes useful tests that could be appropriate for environmental dosimetry providers. An appendix to this report contains recommendations that should be addressed by the N13.29 working group before draft N13.29 is submitted for balloting

  18. Orion Launch Abort System Performance During Exploration Flight Test 1

    Science.gov (United States)

    McCauley, Rachel; Davidson, John; Gonzalez, Guillo

    2015-01-01

    The Orion Launch Abort System Office is taking part in flight testing to enable certification that the system is capable of delivering the astronauts aboard the Orion Crew Module to a safe environment during both nominal and abort conditions. Orion is a NASA program, Exploration Flight Test 1 is managed and led by the Orion prime contractor, Lockheed Martin, and launched on a United Launch Alliance Delta IV Heavy rocket. Although the Launch Abort System Office has tested the critical systems to the Launch Abort System jettison event on the ground, the launch environment cannot be replicated completely on Earth. During Exploration Flight Test 1, the Launch Abort System was to verify the function of the jettison motor to separate the Launch Abort System from the crew module so it can continue on with the mission. Exploration Flight Test 1 was successfully flown on December 5, 2014 from Cape Canaveral Air Force Station's Space Launch Complex 37. This was the first flight test of the Launch Abort System preforming Orion nominal flight mission critical objectives. The abort motor and attitude control motors were inert for Exploration Flight Test 1, since the mission did not require abort capabilities. Exploration Flight Test 1 provides critical data that enable engineering to improve Orion's design and reduce risk for the astronauts it will protect as NASA continues to move forward on its human journey to Mars. The Exploration Flight Test 1 separation event occurred at six minutes and twenty seconds after liftoff. The separation of the Launch Abort System jettison occurs once Orion is safely through the most dynamic portion of the launch. This paper will present a brief overview of the objectives of the Launch Abort System during a nominal Orion flight. Secondly, the paper will present the performance of the Launch Abort System at it fulfilled those objectives. The lessons learned from Exploration Flight Test 1 and the other Flight Test Vehicles will certainly contribute to the vehicle architecture of a human-rated space launch vehicle.

  19. 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.

  20. Performance Testing of a Resistojet Thruster for Small Satellite Applications

    Science.gov (United States)

    Lawrence, Timothy J.; Sweeting, Martin; Paul, Malcolm; Sellers, J. J.; LeDuc, J. R.

    1998-07-01

    Resistojets operating at low power (less than lOO W) and using liquid propellants have re-emerged as attractive propulsion options for orbit-raising small satellites deployed at Space Shuttle altitudes (approx. 2OO km). Compared to low power pulsed plasma thrusters (PPT), the resistojet produces two orders of magnitude more thrust (approximately 1.4 mN compared to 140 mN) which is required to overcome drag at solar maximum. The wet mass of both systems is approximately equal although the propellant volume for the PPT is significantly lower since it is stored in solid form. The major disadvantage of the resistojet propulsion system compared to the PPT, is in the complexity added from the propellant tanks. Shuttle integration concerns for the solid Teflon (trademark) propellant of the PPT are minimal or non-existent. Although non-toxic, the water or nitrous oxide propellant of the resistojet requires pressurized tanks and valves which increase safety requirements. To investigate the usefulness of the resistojet for small satellite applications, a series of performance tests have been completed at the AFRL Electric Propulsion Laboratory using the JPL inverted pendulum thrust stand. The tests were conducted for two types of resistojet thrusters developed at the University of Surrey which utilize a packed bed of SiC particles for the heat exchanger. Performance testing eas accomplished at power levels from 0-600 W for five propellants: water, nitrous oxide, water/ methanol, nitrogen, and helium. Two endurance tests were conducted to determine possible failure modes. Performance characterization and thermal models were developed for future design applications of these thrusters. Future USAF and Surrey Satellite Technology, Ltd. (SSTL) missions using these resistojets are also discussed.

  1. Sport performance and agility tests Sporda performans ve çeviklik testleri

    Directory of Open Access Journals (Sweden)

    Kursat Karacabey

    2013-06-01

    Full Text Available The purpose of this study is to examine the effect agility on sports performance and agility measurement tests. Agility is described as a rapid whole body movement with change of velocity or direction in response to a stimulus. Good agility requires a combination of speed, balance, power and co-ordination. Agility, which is a motoric ability, can be improved by regular progressive exercise. As an important component, agility is used to be an acceptable method in sports performance test batteries. As a result of the study; agility, which is a required characteristic in most of the sports activities, is a quality that successful athletes should have. While administering the sports performance test batteries to enhance sports performance both the exercise to improve agility and to develop dynamic balance that support agility has importance. Özet Bu çal??man?n amac? çevikli?in spor performans?na etkisini ve çeviklik ölçüm testlerini incelemektir. Çeviklik, belli bir uyar?c?ya cevap olarak tüm vücudun h?z veya yön de?i?tirerek ani hareketi olarak tan?mlan?r. Çevikli?in kalitesi, h?z, denge, güç ve koordinasyonun ortakl???n? gerektirir. Motor bir yetenek olan çeviklik, düzenli progresif egzersizle geli?tirilebilir. Önemli bir unsur olarak çeviklik spor performans ölçüm bataryalar?nda kullan?lan geçerli bir yöntemdir. Çal??man?n sonucu olarak, spor aktivitelerinin büyük ço?unlu?unda gerekli bir özellik olan çeviklik, ba?ar?l? sporcular?n sahip olmas? gereken önemli bir niteliktir. Sportif performans?n art?r?lmas? için sportif performans testleri uygulan?rken hem çevikli?i artt?r?c? egzersizler hem de çevikli?in artmas?n? sa?layan dinamik denge özelli?ini de geli?tirici egzersizler öneme sahiptir.

  2. 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

  3. Performance testing of a microfabricated propulsion system for nanosatellite applications

    Science.gov (United States)

    Ketsdever, Andrew D.; Lee, Riki H.; Lilly, Taylor C.

    2005-12-01

    There is a growing interest in the use of micro and nanosatellites within the aerospace community. Constellations of small satellites may eventually replace much larger, single function spacecraft as a cheaper, more flexible alternative. Micro-technologies will be required to enable small satellite missions including efficient, low-cost propulsion systems for maneuvering. A MEMS fabricated propulsion system has been developed for maneuvers on an upcoming University nanosatellite mission. The Free Molecule Micro-Resistojet (FMMR) is an electrothermal propulsion system designed for on-orbit maneuvers of nanosatellites, which are defined as spacecraft with an initial mass less than 10 kg. The FMMR has been tested using a torsion force balance to assess its performance using a variety of propellants including helium, argon, nitrogen and carbon dioxide. The experimental performance results compare favorably with results obtained from gas kinetic theory, which were used in the design phase to estimate the thruster's performance. The measured performance of the FMMR in this study has proven to be adequate to perform attitude control maneuvers for the University nanosatellite mission.

  4. 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)

  5. Thermal Performance Testing of Single Channel GRCop-84 SLM Components

    Science.gov (United States)

    Garcia, Chance P.; Cross, Matthew

    2015-01-01

    The surface finish found on components manufactured by sinter laser manufacturing (SLM) is rougher (0.013 - 0.0006 inches) than parts made using traditional fabrication methods. Internal features and passages built into SLM components do not readily allow for roughness reduction processes. Alternatively, engineering literature suggests that the roughness of a surface can enhance thermal performance within a pressure drop regime. To further investigate the thermal performance of SLM fabricated pieces, several GRCop-84 SLM single channel components were tested using a thermal conduction rig at MSFC. A 20 kW power source running at 25% duty cycle and 25% power level applied heat to each component while varying water flow rates between 2.1 - 6.2 gallons/min (GPM) at a supply pressure of 500 to 750 psi. Each test was allowed to reach quasi-steady state conditions where pressure, temperature, and thermal imaging data were recorded. Presented in this work are the heat transfer responses compared to a traditional machined OHFC Copper test section. An analytical thermal model was constructed to anchor theoretical models with the empirical data.

  6. 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)

  7. 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)

  8. Exercise testing and hemodynamic performance in healthy elderly persons

    International Nuclear Information System (INIS)

    To determine the effect of age on cardiovascular performance, 39 healthy elderly men and women, 70 to 83 years old, underwent treadmill thallium-201 exercise perfusion imaging and radionuclide equilibrium angiography at rest and during supine bicycle exercise. Five volunteers who had a positive exercise thallium test response were excluded from the study. Radionuclide left ventricular ejection fraction, regional wall abnormalities, relative cardiac output, stroke volume, end-diastolic volume and end-systolic volume were measured. Seventy-four percent of the subjects maintained or increased their ejection fraction with exercise. With peak exercise, mean end-diastolic volume did not change, end-systolic volume decreased and cardiac output and stroke volume increased. Moreover, in 35% of the subjects, minor regional wall motion abnormalities developed during exercise. There was no significant difference in the response of men and women with regard to these variables. However, more women than men had difficulty performing bicycle ergometry because they had never bicycled before. Subjects who walked daily performed the exercise tests with less anxiety and with a smaller increase in heart rate and systolic blood pressure

  9. 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 liquefaction center with a set of small liquefiers.

  10. 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)

  11. 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)

  12. Improving Test-Taking Performance of Secondary At-Risk Youth and Students with Disabilities

    Science.gov (United States)

    Banks, Tachelle; Eaton, India

    2014-01-01

    Preparing at-risk youth and students with mild disabilities for state and district tests is important for improving their test performance, and basic instruction in test preparation can significantly improve student test performance. The article defines noncognitive variables that adversely affect test-taker performance. The article also describes…

  13. Performance testing of a small vertical-axis wind turbine

    Energy Technology Data Exchange (ETDEWEB)

    Bravo, R.; Tullis, S.; Ziada, S. [McMaster Univ., Hamilton, ON (Canada). Dept. of Mechanical Engineering

    2007-07-01

    Full-scale wind tunnel testing of a prototype 3.5 kW vertical-axis wind turbine (VAWT) was conducted in a low speed wind tunnel in Ottawa. The tests were conducted to determine nominal power curves as well as the system's structural integrity, safety and operational characteristics. Dimensionless power curves were used to assess the relation between the wind turbine's rotary speed and the produced power for various wind speeds. Tests began at the lowest wind speed and revolutions per minute (RPM) and were gradually increased. A proximity sensor was used to determine the passing frequency of spaced bolts. The aerodynamic performance of the turbine was evaluated using a servo-controlled mechanical variable load with a disc brake calliper and electro-hydraulic servo-actuator. A load cell was used to measure torque produced by the turbine. An active closed loop speed control system was used to regulate the rotary speed of the turbine. The system used a high gain proportional control law to guarantee stability. Calculated power was based on the average rotary speed measurement. Results of the study suggested that the dimensional power performance of the turbine could be predicted from the curve for all rotary speeds and for wind speeds between 8 and 16 m/s. The maximum power coefficient of 0.3 occurred at a tip speed ratio of 1.6. Test results demonstrated that the turbine reached its rated power at 14 m/s. However, the range of tip speed ratios for power production were lower than the range for most other small VAWT. 2 refs., 3 figs.

  14. Eurados trial performance test for neutron personal dosimetry

    DEFF Research Database (Denmark)

    Bordy, J.M.; Stadtmann, H.

    2001-01-01

    This paper reports on the results of a neutron trial performance test sponsored by the European Commission and organised by EURADOS. As anticipated, neutron dosimetry results were very dependent on the dosemeter type and the dose calculation algorithm. Fast neutron fields were generally well measured, but particular problems were noted in the determination of intermediate energy fields and large incident angles, demonstrating the difficulties of neutron personal dosimetry. Of particular concern from a radiological protection point of view was the large number of results underestimating personal dose equivalent. A considerable over-response was noted in a few cases.

  15. Effects of Acute Hypoxia on the Performance of Psychological Tests

    Directory of Open Access Journals (Sweden)

    Irene Jain

    1965-04-01

    Full Text Available The effect of 'partial oxygen want' on general mental functioning of pilots flying at high altitudes has been investigated by subjecting flight cadets to different altitude conditions simulated in a decompression chamber. The study is restricted to an assessment of performance as reflected on the G.V.K. intelligence test series. The effects of hypoxia are apparent only at altitudes of 12,500 ft. and above. Oral administration of methylene blue does not seem to enhance tolerance to oxygen want.

  16. Acceptance test performance of the Rocketdyne radio frequency power system

    International Nuclear Information System (INIS)

    The authors present initial results of performance testing of the RF power system built for the Rocketdyne Free Electron Laser program. The RF power system consists of a SLAC 5045 klystron powered by a modulator unit built by the Beta Division of the Titan Corporation. The system is capable of providing 65 MW, 3.5 ?sec macropulses at 180 pps and employs innovative feedback and feed-forward control techniques in order to achieve amplitude flatness and phase stability. Preliminary rf amplitude, pulse flatness and phase stability measurements indicate phase stability better than ±0.25% are achievable at the 6.5 MW operating point

  17. Injector Cavities Fabrication, Vertical Test Performance and Primary Cryomodule Design

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Haipeng; Cheng, Guangfeng; Clemens, William; Davis, G; Henry, James; Macha, Kurt; Overton, Roland

    2015-09-01

    After the electromagnetic design * and the mechanical design ** of a ?=0.6, 2-cell elliptical SRF cavity, the cavity has been fabricated. Then both 2-cell and 7-cell cavities have been bench tuned to the target values of frequency, coupling external Q and field flatness. After buffer chemistry polishing (BCP) and high pressure rinses (HPR), Vertical 2K cavity test results have been satisfied the specifications and ready for the string assembly. We will report the cavity performance including Lorenz Force Detuning (LFD) and Higher Order Modes (HOM) damping data. Its integration with cavity tuners to the cryomodule design will be reported.

  18. Performance Improvement of a Measurement Station for Superconducting Cable Test

    CERN Document Server

    Arpaia, P; Montenero, G; Le Naour, S

    2012-01-01

    A fully digital system, improving measurements flexibility, integrator drift, and current control of superconducting transformers for cable test, is proposed. The system is based on a high-performance integration of Rogowski coil signal and a flexible direct control of the current into the secondary windings. This allows state-of-the-art performance to be overcome by means of out-of-the-shelf components: on a full-scale of 32 kA, current measurement resolution of 1 A, stability below 0.25 Amin-1, and controller ripple less than 50 ppm. The system effectiveness has been demonstrated experimentally on the superconducting transformer of the Facility for the Research of Superconducting Cables at the European Organization for Nuclear Research (CERN).

  19. 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...

  20. 40 CFR 65.158 - Performance test procedures for control devices.

    Science.gov (United States)

    2010-07-01

    ...false Performance test procedures for control devices...CONSOLIDATED FEDERAL AIR RULE Closed Vent Systems, Control...158 Performance test procedures for control devices...Total time of all testing intervals, hours...comply with the following procedures: (1) For...

  1. 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)

  2. Performance analysis in Japanese field test program; Field test data kara no chiiki hatsuden kaiseki hoho

    Energy Technology Data Exchange (ETDEWEB)

    Sugiyama, H.; Kurokawa, K.; Uchida, D. [Tokyo University of Agriculture and Technology, Tokyo (Japan); Otani, K.; Sakuta, K.; Tsuda, I. [Electrotechnical Laboratory, Tsukuba (Japan); Oshiro, T.; Sakamoto, K. [Japan Quality Assurance Organization, Tokyo (Japan)

    1997-11-25

    Power generation characteristics are investigated using data collected in photovoltaic power generation field tests being undertaken by NEDO (New Energy and Industrial Technology Development Organization). The photovoltaic power generation system performance is evaluated by examining loss factors leading to degradation in system performance, with weather conditions such as variation in insolation and air temperature, inverter performance, and shadows cast by surrounding buildings taken into consideration. As the result, it is found that the important loss factors are degradation in module performance due to elevated temperature, drift in the maximum output control, degraded inverter performance due to input power variation, effect of shadows, etc. It is learned that system is greatly affected by degradation in module performance due to increased temperature in summer and by shadows in winter, the two being responsible for the output coefficient dropping to approximately 75% throughout the year. The output coefficient frequency distribution charts for the 75 test sites confirm that the rate is as low as 70-80% at many sites. As for the system operating time, it tends to be longer in West Japan where the annual insolation rate is higher. 3 refs., 10 figs.

  3. Test Anxiety and Test Performance: Comparing Paper-based and Computer-Adaptive Versions of the Graduate Record Examinations (GRE) General Test.

    Science.gov (United States)

    Powers, Donald E.

    2001-01-01

    Tests the hypothesis that the introduction of computer-adaptive testing may help to alleviate test anxiety and diminish the relationship between test anxiety and test performance. Compares a sample of Graduate Record Examinations (GRE) General Test takers who took the computer-adaptive version of the test with another sample who took the…

  4. 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.

  5. TESTING OF TACTICAL PERFORMANCE IN YOUTH ELITE SOCCER

    Directory of Open Access Journals (Sweden)

    Daniel Memmert

    2010-06-01

    Full Text Available 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 creativity and game intelligence in talented young players. They produced tactical indicators that can be described as objective and valid, exhibit a sufficient degree of differentiation and are easy to record. Study 2 uses a longitudinal design to present a dynamic performance diagnostic tool for analyzing intra-individual improvements of German Soccer Foundation talents according to football-specific creativity and game intelligence. The results with respect to divergent tactical thinking clearly show that very different change processes were observed in the German Soccer Foundation players. Finally, the practical implications for the training process are discussed on the basis of both studies

  6. Performance tests of the reactor containment structures of HTTR

    Energy Technology Data Exchange (ETDEWEB)

    Sakaba, Nariaki; Iigaki, Kazuhiko; Kawaji, Satoshi; Iyoku, Tatsuo [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

    1998-03-01

    The containment structures of the HTTR consist of the reactor containment vessel (CV), service area (SA) and emergency air purification system, which minimize the release of FPs in the postulated accidents with FP release from the reactor facilities. The CV is designed to withstand the temperature and pressure transients and to be leak-tight within the specified leakage limit even in the case of a rupture of the primary concentric hot gas duct. The pressure of inside of the SA should be maintained slightly lower than that of atmosphere by the emergency air purification system. The radioactive materials are released from the stack to environment via the emergency air purification system under the accident condition. Then the emergency air purification system should remove airborne radio-activities and should maintain proper pressure in the SA. We established the method to measure leak rate of the CV with closed reactor coolant pressure boundary although it is normally measured under opened reactor coolant pressure boundary as employed in LWRs. The CV leak rate test was carried out by the newly developed method and the expected performance was obtained. The SA and emergency air purification system were also confirmed by the performance test. We concluded that the reactor containment structures were fabricated to minimize the release of FPs in the postulated accidents with FP release from the reactor facilities. (author)

  7. ARACOR Eagle-matched Operations and Neutron Detector Performance Tests

    International Nuclear Information System (INIS)

    A test campaign was undertaken during April 16-19 in LaHonda, California to match the operational performance of the Idaho National Engineering and Environmental Laboratory (INEEL)Varitron accelerator to that of an ARACOR Eagle accelerator. This Eagle-matched condition, with the INEEL Varitron, will be used during a concept demonstration test at Los Alamos National Laboratory (LANL). This operational characterization involved the use of similar electron beam energies, similar production of photoneutrons from selected non-nuclear materials, and similar production of photofission based, delayed neutrons from an INEEL-provided, depleted uranium sample. Then using the matched operation, the Varitron was used to define detector performances for several INEEL and LANL detectors using the depleted uranium target and Eagle-like, bremsstrahlung collimation. This summary report provides neutron measurements using the INEEL detectors. All delayed neutron data are acquired in the time interval ranging from 4.95 to 19.9 ms after each accelerator pulse. All prompt neutron data are acquired during 0.156 to 4.91 ms after each accelerator pulse. Prompt and delayed neutron counting acquisition intervals can still be optimized

  8. ARACOR Eagle-matched Operations and Neutron Detector Performance Tests

    Energy Technology Data Exchange (ETDEWEB)

    Jones, James Litton; Haskell, Kevin James; Hoggan, Jerry Matkin; Norman, Daren Reeve

    2002-06-01

    A test campaign was undertaken during April 16-19 in LaHonda, California to match the operational performance of the Idaho National Engineering and Environmental Laboratory (INEEL)Varitron accelerator to that of an ARACOR Eagle accelerator. This Eagle-matched condition, with the INEEL Varitron, will be used during a concept demonstration test at Los Alamos National Laboratory (LANL). This operational characterization involved the use of similar electron beam energies, similar production of photoneutrons from selected non-nuclear materials, and similar production of photofissionbased, delayed neutrons from an INEEL-provided, depleted uranium sample. Then using the matched operation, the Varitron was used to define detector performances for several INEEL and LANL detectors using the depleted uranium target and Eagle-like, bremsstrahlung collimation. This summary report provides neutron measurements using the INEEL detectors. All delayed neutron data are acquired in the time interval ranging from 4.95 to 19.9 ms after each accelerator pulse. All prompt neutron data are acquired during 0.156 to 4.91 ms after each accelerator pulse. Prompt and delayed neutron counting acquisition intervals can still be optimized.

  9. ?-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.

  10. Test Research for Basic Mechanics Performance of Inorganic Polymer Concrete

    Directory of Open Access Journals (Sweden)

    Huihong Liu

    2014-01-01

    Full Text Available The main objective of this study is to evaluate the basic mechanics properties (compressive strength, modulus of elasticity, Poisson’s ratio and splitting tensile strength of inorganic polymer concrete whose mix proportion is ripe recipe and try to provide an experimental and theoretical foundation for application of inorganic polymer concrete in the practical engineering. In this study, the basic mechanics properties of inorganic polymer concrete have been studied by test. At the same time, the same tests researches are made for the common Portland cement concrete for comparison. Through the comparison research, it can be found that the compressive bearing capacity of inorganic polymer concrete is stronger and the modulus of elasticity and Poisson’s ratio is slightly bigger than those of common concrete and that the splitting tensile strength is as poor as those of ordinary Portland cement concrete. In order to investigate its long-term performance, the shrinkage and creep tests of inorganic polymer concrete have been studied as well. The change rules of shrinkage and creep in inorganic polymer concrete with time are obtained. It is that initial deformation is bigger and late deformation gradually becomes small and stable. These rules are basic similar as common Portland cement concrete.

  11. 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

  12. Performance testing of LiDAR exploitation software

    Science.gov (United States)

    Varela-González, M.; González-Jorge, H.; Riveiro, B.; Arias, P.

    2013-04-01

    Mobile LiDAR systems are being used widely in recent years for many applications in the field of geoscience. One of most important limitations of this technology is the large computational requirements involved in data processing. Several software solutions for data processing are available in the market, but users are often unknown about the methodologies to verify their performance accurately. In this work a methodology for LiDAR software performance testing is presented and six different suites are studied: QT Modeler, AutoCAD Civil 3D, Mars 7, Fledermaus, Carlson and TopoDOT (all of them in x64). Results depict as QTModeler, TopoDOT and AutoCAD Civil 3D allow the loading of large datasets, while Fledermaus, Mars7 and Carlson do not achieve these powerful performance. AutoCAD Civil 3D needs large loading time in comparison with the most powerful softwares such as QTModeler and TopoDOT. Carlson suite depicts the poorest results among all the softwares under study, where point clouds larger than 5 million points cannot be loaded and loading time is very large in comparison with the other suites even for the smaller datasets. AutoCAD Civil 3D, Carlson and TopoDOT show more threads than other softwares like QTModeler, Mars7 and Fledermaus.

  13. Irradiation tests performed on the Herschel/Pacs bolometer arrays

    CERN Document Server

    Horeau, B; Rodriguez, L; Billot, N; Boulade, O; Doumayrou, E; Okumura, K; Pennec, J Le

    2010-01-01

    A new concept of bolometer arrays is used for the imager of PACS, one of the three instruments aboard the future Herschel space observatory. Within the framework of PACS photometer characterization, irradiation tests were performed on a dedicated bolometer array in order to study long-term and short-term radiation effects. The main objective was to study particles impacts on the detectors applicable to future observations in orbit and possible hard and/or soft curing to restore its performances. Cobalt-60 gamma ray irradiations did not show significant degradation, so we mainly focused on single events effects (SEE). Protons and alphas irradiations were then performed at the Van de Graaf tandem accelerator at the Institut de Physique Nucleaire (IPN, Orsay, France), respectively at 20MeV and 30MeV. Observation showed that the shape of signal perturbations clearly depends on the location of the impacts either on the detector itself or the read-out circuit. Software curing has then to be anticipated in order to ...

  14. IMPACT. National Energy Performance Certification Test. Compilation of national test reports

    Energy Technology Data Exchange (ETDEWEB)

    Sager, C.; Kraus, F. [Deutsche Energie-Agentur GmbH dena, Berlin (Germany)

    2006-10-15

    The background of the IMPACT project, which is conducted in the framework of the Intelligent Energy Europe Programme, is the implementation of the Directive on the Energy Performance of Buildings (EBPD) in 2006. In existing building certification schemes barriers have been reported regarding quality, communication aspects, certification of apartment buildings and lack of expert (auditor) capacity. To have an impact on the energy consumption of buildings all aspects in the certification process need to be addressed. In order to contribute to tackling these barriers IMPACT has the objective to: (1) test energy performance certification for existing buildings in practice in 6 country pilots; (2) exchange experiences and success factors; (3) derive recommendations for improvement of tools, certification schemes, training of experts and communication; (4) support the EPBD implementation process in 6 countries; (5) disseminate project results on a national and EU wide scale. The tests are conducted in: Belgium, Denmark, France, Germany, The Nether-lands and Spain.

  15. Sealing performance test for main flange of pressure vessel of T2 test section in HENDEL

    International Nuclear Information System (INIS)

    A pressure vessel of T2 test section in helium engineering demonstration loop (HENDEL) was fabricated to the same scale of the reactor pressure vessel made of 2(1/4)Cr-1Mo steel in high temperature engineering test reactor (HTTR). Also, the sealing structure of a main flange of pressure vessel in T2 test section was composed of the double metal O-rings and ?-seal which would be used in the sealing structure of HTTR. The sealing performance test for the main flange of the pressure vessel in T2 test section was carried out to confirm the integrity of sealing structure of a main flange in HTTR. T2 test section has been operated about 7700 hours in previous 18 cycles. The leakage of helium gas from inner metal O-ring was measured by the static pressurized process under the operating condition of HTTR (helium gas: 400degC, 40kg/cm2G, 4gk/s). The calculated leakage of helium gas was less than 9.6x10-7 atm·cm3/sec. From the result, it is expected that the sealing structure of main flange in HTTR would maintain the leak tightness in the life. (author)

  16. Indoor test for thermal performance of the Sunmaster evacuated tube (liquid) solar collector

    Science.gov (United States)

    1979-01-01

    The test procedures used to obtain the thermal performance data for a solar collector under simulated conditions are presented. Tests included a stagnation test, a time constant test, a thermal efficiency test, an incident angle modifier test, and a hot fill test. All tests were performed at ambient conditions and the transient effect and the incident angle effect on the collector were determined. The solar collector is a water working fluid type.

  17. Theoretical and testing performance of an innovative indirect evaporative chiller

    Energy Technology Data Exchange (ETDEWEB)

    Jiang, Yi; Xie, Xiaoyun [Department of Building Science and Technology, Tsinghua University, Beijing (China)

    2010-12-15

    An indirect evaporative chiller is a device used to produce chilled water at a temperature between the wet bulb temperature and dew point of the outdoor air, which can be used in building HVAC systems. This article presents a theoretical analysis and practical performance of an innovative indirect evaporative chiller. First, the process of the indirect evaporative chiller is introduced; then, the matching characteristics of the process are presented and analyzed. It can be shown that the process that produces cold water by using dry air is a nearly-reversible process, so the ideal produced chilled water temperature of the indirect evaporative chiller can be set close to the dew point temperature of the chiller's inlet air. After the indirect evaporative chiller was designed, simulations were done to analyze the output water temperature, the cooling efficiency relative to the inlet dew point temperature, and the COP that the chiller can performance. The first installation of the indirect evaporative chiller of this kind has been run for 5 years in a building in the city of Shihezi. The tested output water temperature of the chiller is around 14-20 C, which is just in between of the outdoor wet bulb temperature and dew point. The tested COP{sub r,s} of the developed indirect evaporative chiller reaches 9.1. Compared with ordinary air conditioning systems, the indirect evaporative chiller can save more than 40% in energy consumption due to the fact that the only energy consumed is from pumps and fans. An added bonus is that the indirect evaporative chiller uses no CFCs that pollute to the aerosphere. The tested internal parameters, such as the water-air flow rate ratio and heat transfer area for each heat transfer process inside the chiller, were analyzed and compared with designed values. The tested indoor air conditions, with a room temperature of 23-27 C and relative humidity of 50-70%, proved that the developed practical indirect evaporative chiller successfully satisfy the indoor air conditioning load for the demo building. The indirect evaporative chiller has a potentially wide application in dry regions, especially for large scale commercial buildings. Finally, this paper presented the geographic regions suitable for the technology worldwide. (author)

  18. 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

  19. Power Performance Test Report for the Viryd CS8 Wind Turbine

    Energy Technology Data Exchange (ETDEWEB)

    Roadman, J.; Murphy, M.; van Dam, J.

    2012-12-01

    This report contains the results of the power performance test that was performed on a Viryd CS8 wind turbine as part of the DOE Independent Testing project. The test is an accredited test to the IEC 61400-12-1 power performance standard.

  20. 40 CFR 60.45c - Compliance and performance test methods and procedures for particulate matter.

    Science.gov (United States)

    2010-07-01

    ...initial performance test as required under...subsequent performance tests as requested by...shall be used for gas analysis when applying Method...variables or other factors. (5) For Method...initial performance test, and a subsequent...11) During the correlation testing runs of...

  1. Static and dynamic performance tests of nuclear powered ship Mutsu reactor (report on nuclear ship Mutsu power-up tests)

    International Nuclear Information System (INIS)

    The power-up tests of the Mutsu reactor were performed from March 29th 1990 to December 14th. The tests were divided into six phases: The tests Phase 0 and Phase 1 were done in the state that the ship was moored at the quay of Sekinehama port in March and April; The tests Phase 2, Phase 3, Phase 4, and Phase 5 were done on the Pacific Ocean from July to December. Present report describes the test results on the static and dynamic plant performance. On static plant performance tests, there are 13 test items including measurements of primary system heat balance at low and high power levels, a virgin run of feed water pump with SG steam, a change-over test of steam supply of auxiliary boiler to SG. On the dynamic plant performance, there are 11 test items including a test of reactor power auto-control system, a test of main feed water auto-control system, a test of small load variation, a load increasing test, a turbine trip test, tests of ahead and astern maneuvering, a test of single loop operation, and a reactor scram test. The reactor power for each item's test was increased step by step from zero power to the goal of rated power of 100 %, 36 MWt. In order to confirm proper reactor system performance, criteria were laid down for the static and dynamic tests: for example, (1) reactor scram shall not occur, (2) pressurizer relief valve and steam generator safety valve shall not work, and (3) after the transients reactor systems shall become the steady state without manual adjustment of the reactor control system. The test results satisfied these criteria and some of test data showed that reactor had much more margin in any performance for design. It is verified, therefore, that the Mutsu reactor systems have adequate performances as a marine reactor and that one is capable to respond smoothly and safely to the load of ship's demand. (author)

  2. Performance test of the CMS link alignment system

    International Nuclear Information System (INIS)

    We have presented the conceptual principle of the CMS Link Alignment System and the details of the experimental set-up, installed at the 14 ISR hall, at CERN to validate the design. The experimental set-up reproduces one half of a ? CMS alignment plane with the final dimensions and covers a surface of 20x17 m2. We have described the different instrumentation present in the system (including calibration procedures and results), the DAS and the reconstruction software. The set-up includes a network of reference points that are accurately measured by levelling and photogrammetry survey techniques. Link System measurements are compared with the survey data. Results from this first global test performed with all the link elements running validates the conceptual optomechanical design. Spatial and angular reconstruction precisions reached in the present experimental set-up are already close to the CMS requirements. (author)

  3. 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.

  4. Confirmation test on confinement performance of improved glove box

    International Nuclear Information System (INIS)

    Glove boxes are used at nuclear facilities to confine radioactive materials by ensuring a high level of airtightness and negative internal pressure. The allowable rate of air leakage is 0.1% vol/hr or less at the pre-service inspection. The negative pressure value is normally maintained at about -30 mm H2 O. Structural strength and confinement reliability of glove boxes during earthquake are major concerns, and most important glove boxes are designed to withstand seismic class A events is Japan. This paper describes vibration tests done to confirm that improve large-sized glove boxes maintain their confinement performance and structural strength even during earthquake and that the design analysis methods used are appropriate. (author). 1 ref., 6 figs., 3 tabs

  5. LARGO hot water system thermal performance test report

    Science.gov (United States)

    1978-01-01

    The thermal performance tests and results on the LARGO Solar Hot Water System under natural environmental conditions is presented. Some objectives of these evaluations are to determine the amount of energy collected, the amount of energy delivered to the household as contributed by solar power supplied to operate the system and auxiliary power to maintain tank temperature at proper level, overall system efficiency and to determine temperature distribution within the tank. The Solar Hot Water system is termed a Dump-type because of the draining system for freeze protection. The solar collector is a single glazed flat plate. An 82-gallon domestic water heater is provided as the energy storage vessel. Water is circulated through the collector and water heater by a 5.3 GPM capacity pump, and control of the pump motor is achieved by a differential temperature controller.

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

    DEFF Research Database (Denmark)

    Rípa, Jakub; Bin Kim, Min

    2014-01-01

    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 launched on board the Lomonosov satellite in late-2015.

  7. 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...

  8. 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.

  9. Performance test of uninterruptible power system of PIEF

    International Nuclear Information System (INIS)

    Because of the special features of post-irradiation examination (PIE) facility to handle very high radioactive materials like spent nuclear fuels, the electric system of the facility was designed and constructed according to a very strict requirement which is applied to nuclear power plant. A safety grade of Class 1E was adopted in the power utility system of PIEF to guarantee stable power supply to the facility without any expected interruption. In order cope with a emergency condition like a power interruption of KEPCO, a emergency power supplying system consisting of a diesel generator (3-phase, 6600/440, 1,000 kW) and uninterruptibel power supply (UPS) system was installed in PIEF. UPS power is connected to the radiation monitoring system and several other main safety devices to assure of normal operations of them for not less than 30 minutes. According to the recommendations and regulations in nuclear law, a monthly and yearly regular inspection for the UPS and emergency power supplying system are performed. In this report, a brief description to establish self-inspection technology and procedures for the above mentioned electric power supplying system at PIEF, including a principle of operation, inspection scheme, trouble shooting, and performance test techniques were made. (author). 8 refs., 3 tabs., 4 figs

  10. Performance test of uninterruptible power system of PIEF

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jong Chae; Kim, Eun Ka; Chun, Yong Bum; Park, Dea Gyu; Chu, Yong Sun; Bae, Sang Min; Koo, Dae Seo

    1998-02-01

    Because of the special features of post-irradiation examination (PIE) facility to handle very high radioactive materials like spent nuclear fuels, the electric system of the facility was designed and constructed according to a very strict requirement which is applied to nuclear power plant. A safety grade of Class 1E was adopted in the power utility system of PIEF to guarantee stable power supply to the facility without any expected interruption. In order cope with a emergency condition like a power interruption of KEPCO, a emergency power supplying system consisting of a diesel generator (3-phase, 6600/440, 1,000 kW) and uninterruptibel power supply (UPS) system was installed in PIEF. UPS power is connected to the radiation monitoring system and several other main safety devices to assure of normal operations of them for not less than 30 minutes. According to the recommendations and regulations in nuclear law, a monthly and yearly regular inspection for the UPS and emergency power supplying system are performed. In this report, a brief description to establish self-inspection technology and procedures for the above mentioned electric power supplying system at PIEF, including a principle of operation, inspection scheme, trouble shooting, and performance test techniques were made. (author). 8 refs., 3 tabs., 4 figs.

  11. 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

  12. 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. 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

  13. Testing the performance of technical trading rules in the Chinese markets based on superior predictive test

    Science.gov (United States)

    Wang, Shan; Jiang, Zhi-Qiang; Li, Sai-Ping; Zhou, Wei-Xing

    2015-12-01

    Technical trading rules have a long history of being used by practitioners in financial markets. The profitable ability and efficiency of technical trading rules are yet controversial. In this paper, we test the performance of more than seven thousand traditional technical trading rules on the Shanghai Securities Composite Index (SSCI) from May 21, 1992 through June 30, 2013 and China Securities Index 300 (CSI 300) from April 8, 2005 through June 30, 2013 to check whether an effective trading strategy could be found by using the performance measurements based on the return and Sharpe ratio. To correct for the influence of the data-snooping effect, we adopt the Superior Predictive Ability test to evaluate if there exists a trading rule that can significantly outperform the benchmark. The result shows that for SSCI, technical trading rules offer significant profitability, while for CSI 300, this ability is lost. We further partition the SSCI into two sub-series and find that the efficiency of technical trading in sub-series, which have exactly the same spanning period as that of CSI 300, is severely weakened. By testing the trading rules on both indexes with a five-year moving window, we find that during the financial bubble from 2005 to 2007, the effectiveness of technical trading rules is greatly improved. This is consistent with the predictive ability of technical trading rules which appears when the market is less efficient.

  14. The Relationship between Tests of Neurocognition and Performance on a Laparoscopic Simulator

    OpenAIRE

    Muhammad Faisal Aslam; Amine Khachani; Imad Kuzbari; Rima A. A. Atiah; Pedram Bral; Howard Crystal; Oumar Kuzbari; Howard Minkoff

    2010-01-01

    Objective. To estimate if there is a relationship between the results of tests of neurocognition and performance on a laparoscopic surgery simulator. Methods and Materials. Twenty participants with no prior laparoscopic experience had baseline cognitive tests administered (Trail Making Test, Part A and B (TMT-A and TMT-B), Grooved Peg Board Test, Symbol Digit Modalities Test, Symbol Digit Recall Test, and Stroop Interference Test), completed a demographic questionnaire, and then performed lap...

  15. 40 CFR 60.44c - Compliance and performance test methods and procedures for sulfur dioxide.

    Science.gov (United States)

    2010-07-01

    ...Compliance and performance test methods and procedures for sulfur dioxide. 60.44c Section 60.44c Protection of Environment...Compliance and performance test methods and procedures for sulfur dioxide. (a) Except as provided in paragraphs...

  16. Optical Studies Accompanying a Performance Test of a HEMP Thruster in the JUMBO Test Facility

    Science.gov (United States)

    Weis, S.; Meiß, S.; Schartner, K.-H.; Feili, D.; Harmann, H.-P.; Koch, N.; Kornfeld, G.

    2004-10-01

    Ion thrusters are bright light sources allowing a spectral analysis in a short time without disturbance of the plume. Accordingly, the light emission of a Thales HEMP3) thruster DM6 was studied while the performance of the thruster was investigated in the JUMBO fest facility of the Giessen University. The front end of a light waveguide was positioned in the demagnified image of the thruster exit diaphragm and its other end fixed in the entrance slit of a monochromator of 30 cm focal length, equipped with a CCD as detector. The HEMP thruster was mounted on a thrust balance. The angular distribution of the emitted ions could be monitored by a three axis scanner. Mass flow and discharge voltage were varied during the performance test. The collected spectra contain lines from neutral, singly and doubly charged Xe serving as propellant. The dependence of the relative intensities of selected lines on the discharge parameters will be discussed.

  17. 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

  18. 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.

  19. 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.

  20. 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.

  1. Design and performance of the South Pole Acoustic Test Setup

    Energy Technology Data Exchange (ETDEWEB)

    Abdou, Y. [Department of Subatomic and Radiation Physics, University of Gent, B-9000 Gent (Belgium); Becker, K.-H. [Department of Physics, University of Wuppertal, D-42119 Wuppertal (Germany); Berdermann, J. [DESY, D-15735 Zeuthen (Germany); Bissok, M. [III. Physikalisches Institut, RWTH Aachen University, D-52056 Aachen (Germany); Bohm, C. [Oskar Klein Centre and Department of Physics, Stockholm University, SE-10691 Stockholm (Sweden); Boeser, S.; Bothe, M. [DESY, D-15735 Zeuthen (Germany); Carson, M. [Department of Subatomic and Radiation Physics, University of Gent, B-9000 Gent (Belgium); Descamps, F., E-mail: Freija.Descamps@icecube.wisc.edu [Department of Subatomic and Radiation Physics, University of Gent, B-9000 Gent (Belgium); Fischer-Wolfarth, J.-H. [DESY, D-15735 Zeuthen (Germany); Gustafsson, L.; Hallgren, A. [Department of Physics and Astronomy, Uppsala University, Box 516, S-75120 Uppsala (Sweden); Heinen, D. [III. Physikalisches Institut, RWTH Aachen University, D-52056 Aachen (Germany); Helbing, K. [Department of Physics, University of Wuppertal, D-42119 Wuppertal (Germany); Heller, R. [DESY, D-15735 Zeuthen (Germany); Hundertmark, S. [Oskar Klein Centre and Department of Physics, Stockholm University, SE-10691 Stockholm (Sweden); Karg, T. [Department of Physics, University of Wuppertal, D-42119 Wuppertal (Germany); Krieger, K. [DESY, D-15735 Zeuthen (Germany); Laihem, K.; Meures, T. [III. Physikalisches Institut, RWTH Aachen University, D-52056 Aachen (Germany); and others

    2012-08-11

    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.

  2. 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.

  3. Cooling performance test of the superconducting fault current limiter

    International Nuclear Information System (INIS)

    The superconducting fault current limiter (SFCL) is an electrical power system device that detects the fault current automatically and limits the magnitude of the current below a certain safety level. The SFCL module does not have any electrical resistance below the critical temperature, which facilitates lossless power transmission in the electric power system. Once given the fault current, however, the superconducting conductor exhibits extremely high electrical resistance, and the magnitude of the current is accordingly limited to a low value. Therefore, SFCL should be maintained at a temperature below the critical temperature, which justifies the cryogenic cooling system as a mandatory component. This report is a study which reported on the cooling system for the 154 kV-class hybrid SFCL owned by Korea Electric Power Corporation (KEPCO). Using the cryocooler, the temperature of liquid nitrogen (LN2) was lowered to 71 K. The cryostat was pressurized to 5 bars to improve the dielectric strength of nitrogen and suppress nitrogen bubble foaming during operation of SFCL. The SFCL module was immersed in the liquid nitrogen of the cryostat to maintain the superconducting state. The performance test results of the key components such as cryocooler, LN2 circulation pump, cold box, and pressure builder are shown in this paper.

  4. Enhancement of Tokamak Fusion Test Reactor performance by lithium conditioning*

    Energy Technology Data Exchange (ETDEWEB)

    Mansfield, D. K. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Hill, K. W. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Strachan, J. D. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Bell, M. G. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Scott, S. D. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Budny, R. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Marmar, E. S. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Snipes, J. A. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Terry, J. L. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Batha, S. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Bell, R. E. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Bitter, M. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Bush, C. E. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Chang, Z. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Darrow, D. S. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Ernst, D. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Fredrickson, E. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Grek, B. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Herrmann, H. W. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Janos, A. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Jassby, D. L. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Jobes, F. C. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Johnson, D. W. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Johnson, L. C. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Levinton, F. M. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Mikkelsen, D. R. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Mueller, D. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Owens, D. K. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Park, H. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Ramsey, A. T. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Roquemore, A. L. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Skinner, C. H. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Stevenson, T. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Stratton, B. C. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Synakowski, E. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Taylor, G. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); von Halle, A. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); von Goeler, S. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Wong, K. L. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); Zweben, S. J. [Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States); ., .

    1996-01-01

    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–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.

  5. 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.

  6. 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. Udgivelsesdato: 2007-Mar

  7. Enhancement of Tokamak Fusion Test Reactor performance by lithium conditioning

    Science.gov (United States)

    Mansfield, D. K.; Hill, K. W.; Strachan, J. D.; Bell, M. G.; Scott, S. D.; Budny, R.; Marmar, E. S.; Snipes, J. A.; Terry, J. L.; Batha, S.; Bell, R. E.; Bitter, M.; Bush, C. E.; Chang, Z.; Darrow, D. S.; Ernst, D.; Fredrickson, E.; Grek, B.; Herrmann, H. W.; Janos, A.; Jassby, D. L.; Jobes, F. C.; Johnson, D. W.; Johnson, L. C.; Levinton, F. M.; Mikkelsen, D. R.; Mueller, D.; Owens, D. K.; Park, H.; Ramsey, A. T.; Roquemore, A. L.; Skinner, C. H.; Stevenson, T.; Stratton, B. C.; Synakowski, E.; Taylor, G.; von Halle, A.; von Goeler, S.; Wong, K. L.; Zweben, S. J.

    1996-05-01

    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-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.

  8. 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

  9. 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.)

  10. 40 CFR 63.997 - Performance test and compliance assessment requirements for control devices.

    Science.gov (United States)

    2010-07-01

    ...demonstrated by applicable test methods and procedures; (2) Safe sampling platform...4) Utilities for sampling and testing equipment; and (5) Any other...source. (e) Performance test procedures. Where §§ 63.985...

  11. Network telemetry System Performance Tests in support of the Mark 3 data system implementation

    Science.gov (United States)

    Rey, R. D.; Nipper, E. J.

    1978-01-01

    The philocophy and the objectives of the telemetry system performance tests (SPTs) are discussed to demonstrate the benefits gained by performing these tests. The test procedure and test software are included. The results and the status of the Network Telemetry system are summarized.

  12. Largo hot water system long range thermal performance test report, addendum

    Science.gov (United States)

    1978-01-01

    The test procedure used and the test results obtained during the long range thermal performance tests of the LARGO Solar Hot Water System under natural environmental conditions are presented. Objectives of these tests were to determine the amount of energy collected, the amount of power required for system operation, system efficiency, temperature distribution, and system performance degradation.

  13. Performance of multiaxial strength tests on concrete samples

    International Nuclear Information System (INIS)

    Special testing machines and systems are necessary to exert force on the samples in the investigation of multiaxial rupture and deformation behaviour in concrete. The testing equipment of the 'Bundesanstalt fuer Materialpruefung' (BAM) and its function are described using selected test series. The equipment is designed for cubes with an edge of 10 cm length independent of the type of force-exerting system, for testing forces up to 2,000 kN. A universally usable testing machine is thus available for multiaxial strength tests. (orig./LH)

  14. Performance test of the upper head injection system at the ROSA-II test facility

    International Nuclear Information System (INIS)

    To evaluate upper head injection system (UHIS) performance during a postulated loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR), ten UHIS tests were conducted at the ROSA-II test facility. The experimental results were different from the expected UHIS performance in the following points. First, flashing took place in the upper head and a mixture level was formed before UHIS actuation. Second, emptying of the upper head was observed immediately after UHIS shut off. Third, part of the water which flowed down from the upper head, penetrated into the core and contributed to core cooling at the top part of the core, however, most of the water flowed out through the broken loop hot leg. In the case of higher injection water temperature (approx. 1200C), the fluid behavior in the pressure vessel differed significantly from the results for the low injection water temperature (approx. 200C), and the core cooling was remarkably improved. Therefore, high-temperature UHIS water is recommended for effective core cooling. The results described above are due to the following physical phenomena: (1) fluid mixing in the upper head is not good; (2) subcooled water, which flows into places such as the upper plenum where steam exists, causes strong condensation-depressurization which affects the flow behavior and core cooling. Although the magnitude of the thermal-hydraulic effects observed in the ROSA-II/UHI tests may be unique to this facility, the above two physical phenomena observed are applicable to all PWRs with a UHIS. Therefore, these two phenomena must be included in a LOCA analysis of a PWR with a UHIS

  15. Attribution and Self-Evaluation of Continuous Performance Test Task Performance in Medicated and Unmedicated Adults with ADHD

    Science.gov (United States)

    Barrilleaux, Katie; Advokat, Claire

    2009-01-01

    Objective: To determine if adults with ADHD differed from children with ADHD, in assessing their performance on the Conners Continuous Performance Test (CPT). Method: ADHD-diagnosed adults (n = 13) and adults without ADHD (n = 17) were tested twice on the CPT and then completed self-evaluation and attribution surveys. Results: Nonmedicated…

  16. Model-based control of off-gas desulphurization in the low-temperature range; Modellgestuetzte Regelung der Entschwefelung von Abgasen im Niedertemperaturbereich

    Energy Technology Data Exchange (ETDEWEB)

    Mittler, G.

    2001-07-01

    A process for dry desulphurisation of off-gas in the low-temperature range below 100 C, i.e. at minimum distance from the condensation temperature, was investigated. Calcium oxide and hydroxide were used as sorbents. A mathematical model and an artificial neuronal net model were developed as a basis for model-supported control of the temperature and relative moisture of the off-gas of the desulphurisation process with a view to industrial applications of the process. [German] Zur Abscheidung von Schwefeldioxid aus Abgasen gewinnen die als Trockenverfahren bezeichneten Abgasreinigungstechniken vor allem fuer die Aus- bzw. Nachruestung kleiner Verbrennungsanlagen (thermische Leistung <50 MW{sub th}), bei denen der Einsatz ueblicher Nassverfahren aus wirtschaftlichen Gruenden (hohe Investitions- und Betriebskosten) sowie wegen des hohen Platzbedarfes nicht in Frage kommt, zunehmend an Bedeutung. Bei dem hier untersuchten Verfahren handelt es sich um ein Reaktionsverfahren zur trockenen Abgasentschwefelung im Niedertemperaturbereich, d.h. bei Temperaturen <100 C in moeglichst geringem Abstand zum Taupunkt des Abgases, wobei fuer die chemische Einbindung des SO{sub 2}-Calciumoxid und -hydroxid als Sorbenzien verwendet werden. Daher ist die Zielsetzung der vorliegenden Arbeit die Entwicklung eines mathematischen Modells sowie eines KNN(Kuenstliche-Neuronale-Netze)-Modells am Beispiel der Versuchsanlage als Basis fuer eine modellgestuetzte Regelung der Temperatur und relativen Feuchte des Abgases im Entschwefelungsprozess, durch deren Einsatz eine automatisierte und sichere Prozessfuehrung gewaehrleistet und somit eine wesentliche Voraussetzung fuer die industrielle Anwendung des hier untersuchten Verfahrens erfuellt wird. (orig.)

  17. Evaluation technology for burnup and generated amount of plutonium by measurement of Xenon isotopic ratio in dissolver off-gas at reprocessing facility (Joint research)

    International Nuclear Information System (INIS)

    The amount of Pu in the spent fuel was evaluated from Xe isotopic ratio in off-gas in reprocessing facility, is related to burnup. Six batches of dissolver off-gas (DOG) at spent fuel dissolution process were sampled from the main stack in Tokai Reprocessing Plant (TRP) during BWR fuel (approx. 30GWD/MTU) reprocessing campaign. Xenon isotopic ratio was determined with Gas Chromatography/Mass Spectrometry. Burnup and generated amount of Pu were evaluated with Noble Gas Environmental Monitoring Application code (NOVA), developed by Los Alamos National Laboratory. Inferred burnup evaluated by Xe isotopic measurements and NOVA were in good agreement with those of the declared burnup in the range from -3.8% to 7.1%. Also, the inferred amount of Pu in spent fuel was in good agreed with those of the declared amount of Pu calculated by ORIGEN code in the range from -0.9% to 4.7%. The evaluation technique is applicable for both burnup credit to achieve efficient criticality safety control and a new measurement method for safeguards inspection. (author)

  18. A Culture-Free Performance Test of General Learning Ability.

    Science.gov (United States)

    Young, Peter Adams

    Random polygons were used as stimuli in a two-choice multiple discrimination learning paradigm designed to test individual learning ability. A nonverbal test was developed in order to avoid the cultural and racial bias which, according to the author, is inherent in verbal tests. Information processing rate (IPR) was used as the measure of learning…

  19. Phase 2 Methyl Iodide Deep-Bed Adsorption Tests

    Energy Technology Data Exchange (ETDEWEB)

    Soelberg, Nick [Idaho National Lab. (INL), Idaho Falls, ID (United States); Watson, Tony [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    Nuclear fission produces fission products (FPs) and activation products, including iodine-129, which could evolve into used fuel reprocessing facility off-gas systems, and could require off-gas control to limit air emissions to levels within acceptable emission limits. Research, demonstrations, and some reprocessing plant experience have indicated that diatomic iodine can be captured with efficiencies high enough to meet regulatory requirements. Research on the capture of organic iodides has also been performed, but to a lesser extent. Several questions remain open regarding the capture of iodine bound in organic compounds. Deep-bed methyl iodide adsorption testing has progressed according to a multi-laboratory methyl iodide adsorption test plan. This report summarizes the second phase of methyl iodide adsorption work performed according to this test plan using the deep-bed iodine adsorption test system at the Idaho National Laboratory (INL), performed during the second half of Fiscal Year (FY) 2014. Test results continue to show that methyl iodide adsorption using AgZ can achieve total iodine decontamination factors (DFs, ratios of uncontrolled and controlled total iodine levels) above 1,000, until breakthrough occurred. However, mass transfer zone depths are deeper for methyl iodide adsorption compared to diatomic iodine (I2) adsorption. Methyl iodide DFs for the Ag Aerogel test adsorption efficiencies were less than 1,000, and the methyl iodide mass transfer zone depth exceeded 8 inches. Additional deep-bed testing and analyses are recommended to (a) expand the data base for methyl iodide adsorption under various conditions specified in the methyl iodide test plan, and (b) provide more data for evaluating organic iodide reactions and reaction byproducts for different potential adsorption conditions.

  20. Ontario Hydro's containment testing program - practice, performance and direction

    International Nuclear Information System (INIS)

    CANDU multi-unit plants operated by Ontario Hydro employ large Vacuum Buildings for pressure suppression in the event of an accident. This paper describes the testing program to confirm the integrity of these containments for a system with 100 reactor-years of experience. The design limits overpressure periods to less than a minute and maintains the containment subatmospheric while short-lived radionuclides decay. Containment testing begins with a comprehensive commissioning program including tests of the Vacuum Building systems at maximum flow and a full range of positive and negative pressure leakage rate tests. Once in operation, emphasis is on frequent on-power testing of both components and the overall containment boundary. Sudden impairment can and has been rapidly detected such as a Vacuum Building roof seal failure at one station. Vacuum Building inspection results have shown no concern for component integrity. Some submerged metallic components were subject to bacterial corrosion. Off-power pressure test results have shown no ageing effects to-date and confirm the results of low pressure on-power tests. Three station outages are planned by the end of the decade for containment tests and inspections. This data will enable Ontario Hydro to assess ageing effects and will give a rational basis for the frequency of such tests as a supplement to our comprehensive on-power testing program. (author)

  1. Effects of age and gender on performance on Conners’ Continuous Performance Test in Brazilian adolescents

    Directory of Open Access Journals (Sweden)

    Mônica C. Miranda

    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 representative 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.

  2. 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.

  3. Dual Purpose Simulation: New Data Link Test and Performance Limit Testing of Currently Deployed Data Link

    Science.gov (United States)

    Robinson, Daryl C.

    2002-01-01

    While the results of this paper are similar to those of [I], in this paper technical difficulties present in [I] are eliminated, producing better results, enabling one to more readily see the benefits of Prioritized CSMA (PCSMA). A new analysis section also helps to generalize this research so that it is not limited to exploration of the new concept of PCSMA. Commercially available network simulation software, OPNET version 7.0, simulations are presented involving an important application of the Aeronautical Telecommunications Network (ATN), Controller Pilot Data Link Communications (CPDLC) over the Very High Frequency Data Link Mode 2 (VDL-2). Communication is modeled for essentially all incoming and outgoing nonstop air-traffic for just three United States cities: Cleveland, Cincinnati, and Detroit. The simulation involves 111 Air Traffic Control (ATC) ground stations, 32 airports distributed throughout the U.S., which are either sources or destinations for the air traffic landing or departing from the three cities, and also 1,235 equally equipped aircraft-taking off, flying realistic free-flight trajectories, and landing in a 24-hr period. Collision-less PCSMA is successfully tested and compared with the traditional CSMA typically associated with VDL-2. The performance measures include latency, throughput, and packet loss. As expected, PCSMA is much quicker and more efficient than traditional CSMA. These simulation results show the potency of PCSMA for implementing low latency, high throughput and efficient connectivity. Moreover, since PCSMA outperforms traditional CSMA, by simulating with it, we can determine the limits of performance beyond which traditional CSMA may not pass. So we have the tools to determine the traffic-loading conditions where traditional CSMA will fail, and we are testing a new and better data link that could replace it with relative ease. Work is currently being done to drastically expand the number of flights to make the simulation more representative of the National Aerospace System.

  4. Functional Performance and Associations between Performance Tests and Neurological Assessment Differ in Men and Women with Parkinson's Disease

    Science.gov (United States)

    Medijainen, Kadri; Pääsuke, Mati; Lukmann, Aet; Taba, Pille

    2015-01-01

    Background. Neurological assessment of a patient with Parkinson's disease (PD) is expected to reflect upon functional performance. As women are known to report more limitations even for same observed functional performance level, present study was designed to examine whether associations between neurological assessments and functional performance differ across genders. Methods. 14 men and 14 women with PD participated. Functional performance was assessed by measuring walking speeds on 10-meter walk test (10MWT) and by performing timed-up-and-go-test (TUG). Neurological assessment included Hoehn and Yahr Scale (HY), Movement Disorders Society Unified Parkinson's Disease Rating Scale (MDS-UPDRS), Schwab and England Activities of Daily Living Scale (S-E), and Mini Mental State Examination (MMSE). Results. In women with PD, Kendall's tau-b correlation analyses revealed significant correlations between functional performance tests and neurological assessment measures, with the exception in MMSE. No corresponding associations were found for men, although they demonstrated better functional performance, as expected. Conclusion. Men in similar clinical stage of the PD perform better on functional tests than women. Disease severity reflects upon functional performance differently in men and women with PD. Results indicate that when interpreting the assessment results of both functional performance and neurological assessment tests, the gender of the patient should be taken into consideration. PMID:26586928

  5. Measurement protocol for performance testing of the determination of tritium in water

    International Nuclear Information System (INIS)

    In the Health and Safety Executive's ''Requirements for the Approval of Dosimetry Services under the Ionising Radiations Regulations 1985'', it is stipulated that dosimetry services seeking approval must show that they have successfully completed a performance test. The services must arrange for the tests to be carried out on application and thereafter every 18 months, by a laboratory which has received accreditation from the National Measurement Accreditation Service (NAMAS) for conducting the performance tests. Accreditation by NAMAS ensures that the laboratories carrying out the performance tests are of an appropriate standard. It includes requirements for quality control and audit procedures, to authenticate traceability to national standards, and to provide a reliable record keeping system for the performance tests. A list of laboratories which are accredited by NAMAS for carrying out HSE published performance tests will be maintained by the Secretary of the Dosimetry Services Panel. The performance tests must be carried out to published protocols. The results have to be expressed in terms of bias and random error, as defined in HSE's criteria for performance tests. The purpose here is to provide a protocol for laboratories to conduct performance tests on dosimetry services performing tritium determinations in urine. The test is deliberately not exhaustive, instead it is a simple test allowing the basic performance of a service to be assessed for approval. (author)

  6. 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.

  7. 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

  8. Construction and primary performance test of MDC III at BES

    International Nuclear Information System (INIS)

    This paper describes the construction of MDC III, such as the design of framework, construction process, wire tension measurement, high voltage leakage current measurement of the wire and the cosmic ray test. With these careful tests, we conclude that MDC III has reached its design goals

  9. Test-Taking Motivation and Mathematics Performance in TIMSS 2003

    Science.gov (United States)

    Eklof, Hanna

    2007-01-01

    This study explores the reported level of test-taking motivation and the relation between test-taking motivation and mathematics achievement in a sample of Swedish eighth-grade students (n = 343) participating in Trends in International Mathematics and Science Study (TIMSS) 2003. A majority of students reported that they were motivated to do their…

  10. Learning performances in young horses using two different learning tests.

    OpenAIRE

    Visser, E.K.; Reenen, C.G. van; Schilder, M. B. H.; Barneveld, A; Blokhuis, H.J.

    2003-01-01

    To achieve optimal performance in equine sports as well as in leisure not only the physical abilities of the horse should be considered, but also the horse's personality. Besides temperamental aspects, like emotionality, or the horse's reactivity towards humans in handling situations, the learning ability of the horse is another relevant personality trait. To study whether differences in learning performance are consistent over time and whether individual learning performance differs between ...

  11. A Grey Relational Analysis Between Some Selected Affective Factors and English Test Performance

    Directory of Open Access Journals (Sweden)

    Mei DONG

    2014-09-01

    Full Text Available With Grey relational analysis (GRA, the paper examined the sensitivity of eight variables influencing test performance at branch level. The eight variables involved included language proficiency, test anxiety, self-esteem, achievement motivation, achievement goal, English proficiency test anxiety (EPTA, state anxiety and trait anxiety. Results showed that: (1 Besides language proficiency, motivation-to-avoid- failure was most sensitive to English test performance; (2 Trait and state anxiety were more sensitive to English academic performance than general test anxiety as well as the four branches of the EPTA; (3 Compared with the other three branches of the EPTA, EPTAS-listening was most intimate to English test performance; (4 All the affective concepts involved in this study were quite sensitive to English academic performance at branch level because their comprehensive grey correlation degree values were all over 0.50. This research has practical implications for English teachers and students seeking to enhance their performance in English proficiency test.

  12. 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

  13. High-Stakes Testing and Mathematics Performance of Fourth Graders in North Cyprus.

    Science.gov (United States)

    Cankoy, Osman; Tut, Mehmet Ali

    2005-01-01

    The authors attempted to determine the effects of a high-stakes standardized testing-driven instructional approach on mathematical performance. The authors developed a multiple-choice mathematics performance test for 1,006 Grade 4 students in 28 North Cyprus schools. Analysis revealed that students who spent more time on test-taking skills…

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

    Energy Technology Data Exchange (ETDEWEB)

    Abrigo, G.P.; Daume, J.T.; Halstead, S.D.; Myers, R.L.; Beckette, M.R.; Freeman, C.J.; Hatchell, B.K.

    1996-03-01

    (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.

  15. 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

  16. Performance Analysis of Text Alignment Tools Using Automated Test Bed

    Directory of Open Access Journals (Sweden)

    John Nabil

    2012-09-01

    Full Text Available The text alignment process is an important activity in the statistical machine translation (SMT upon the training phase of SMT systems on huge amounts of parallel corpora. We are evaluating five of the popular text aligners and analyzing the methodologies used in each of them, then we are introducing new open source automated test bed for testing those text aligners and generating reports called pyTester, and finally discuss our observations about the test results generated from pyTester

  17. 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

  18. 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

  19. Performance testing of a profile monitor for heavy ion beams

    International Nuclear Information System (INIS)

    The SATURNE and GANIL accelerators will produce heavy ions beams to be visualized. In view of studying such a display system, one line of the ALICE accelerator at Orsay has been equiped with a wire chamber of the type of SATURNE and tested (19 September 1977) with using an oxygen beam. A second test was effected at the TANDEM at Saclay (30 September 1977) also with using an oxygen beam. The results are extrapolated to Saturne II operational conditions

  20. Implementation intentions and test anxiety: Shielding academic performance from distraction

    OpenAIRE

    Parks-Stamm, Elizabeth J.; Gollwitzer, Peter M.; Oettingen, Gabriele

    2010-01-01

    College students whose test anxiety was measured completed a working memory-intensive math exam with televised distractions. Students were provided with implementation intentions (if-then plans; Gollwitzer, 1999) designed to either help them ignore the distractions (i.e., temptation-inhibiting plans) or focus more intently on the math exam (i.e., task-facilitating plans). Regression analyses showed that as test anxiety increased, the effectiveness of temptation-inhibiting implementation inten...

  1. 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)

  2. Development and testing of the methodology for performance requirements

    International Nuclear Information System (INIS)

    The U.S. Department of Energy (DOE) is in the process of implementing a set of materials control and accountability (MC ampersand A) performance requirements. These graded requirements set a uniform level of performance for similar materials at various facilities against the threat of an insider adversary stealing special nuclear material (SNM). These requirements are phrased in terms of detecting the theft of a goal quantity of SNM within a specified time period and with a probability greater than or equal to a special value and include defense-in-depth requirements. The DOE has conducted an extensive effort over the last 2 1/2 yr to develop a practical methodology to be used in evaluating facility performance against the performance requirements specified in DOE order 5633.3. The major participants in the development process have been the Office of Safeguards and Security (OSS), Brookhaven National Laboratory, and Los Alamos National Laboratory. The process has included careful reviews of related evaluation systems, a review of the intent of the requirements in the order, and site visits to most of the major facilities in the DOE complex. As a result of this extensive effort to develop guidance for the MC ampersand A performance requirements, OSS was able to provide a practical method that will allow facilities to evaluate the performance of their safeguards systems against the performance requirements. In addition, the evaluations can be validated by the cognizant operations offices in a systematic manner

  3. 40 CFR 60.3036 - May I conduct a repeat performance test to establish new operating limits?

    Science.gov (United States)

    2010-07-01

    ...performance test to establish new operating limits? Yes, you may conduct a repeat performance test at any time to establish new values for the operating limits. The Administrator may request a repeat performance test at any time. Model...

  4. 40 CFR 60.2935 - May I conduct a repeat performance test to establish new operating limits?

    Science.gov (United States)

    2010-07-01

    ...performance test to establish new operating limits? Yes, you may conduct a repeat performance test at any time to establish new values for the operating limits. The Administrator may request a repeat performance test at any time....

  5. 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...

  6. Web-Based Testing: Exploring the Relationship between Hardware Usability and Test Performance

    Science.gov (United States)

    Huff, Kyle; Cline, Melinda; Guynes, Carl S.

    2012-01-01

    Web-based testing has recently become common in both academic and professional settings. A web-based test is administered through a web browser. Individuals may complete a web-based test at nearly any time and at any place. In addition, almost any computer lab can become a testing center. It is important to understand the environmental issues that…

  7. Waste isolation performance assessment and in-situ testing

    International Nuclear Information System (INIS)

    Thirty-three papers and summaries are included, under the categories of plenary lectures, performance assessment, and Asse experiments. Separate abstracts were prepared for 27 of the papers; one was previously abstracted

  8. Individual Differences in Gender Role Beliefs Influence Spatial Ability Test Performance

    Science.gov (United States)

    Massa, Laura J.; Mayer, Richard E.; Bohon, Lisa M.

    2005-01-01

    The gender role hypothesis posits that performance on a cognitive ability test is influenced by whether the test instructions frame the test as measuring a skill that is consistent or inconsistent with the test taker's gender role beliefs. The Bem sex role inventory was used to measure the gender role of female college students, and the group…

  9. 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…

  10. Does Relative Age Influence Motor Test Performance of Fourth Grade Pupils?

    Science.gov (United States)

    Wattie, Nick; Tietjens, Maike; Schorer, Jörg; Ghanbari, Marie-Christine; Strauss, Bernd; Seidel, Ilka; Baker, Joseph

    2014-01-01

    The aim of the current study was to explore relative age's influence on physical and motor tests among fourth grade children (9 to 10 years) from Germany. Data from 1218 children (49% female) who had performed the German Motor Ability Test (Bös et al., 2009) were analysed. The test battery, which was comprised of physical and motor tests,…

  11. Test Anxiety and its Relationship with Academic Performance among Nursing Students

    Directory of Open Access Journals (Sweden)

    Bahman Cheraghian

    2008-01-01

    Full Text Available Introduction: Test anxiety, a common phenomenon among college students, is one of the problems of educational systems. Because test anxiety affects academic performance, this study was performed to determine test anxiety and its relationship with academic performance among nursing students. Methods: In this descriptive- analytical study, 150 students of Abadan Nursing College were selected in 2007. Data were collected via a two-component questionnaire including demographic data and the test anxiety inventory that were completed self-directedly during the final exams. The data were analyzed by SPSS (13.0 software, using some measures of central tendency and variability, Mann Whitney test and Spearman correlation coefficient. Results: The mean score of test anxiety in students was 30.9± 23.2. Fourteen percent of participants did not have any test anxiety, 48.67% had low test anxiety, 34% had moderate test anxiety and 3.33% had severe test anxiety. In sum, 86% had some degrees of test anxiety. In this study, no significant relationship was found between test anxiety and academic performance (r= -0.12, p= 0.13, nor between test anxiety and age (P= 0.84,, nor between test anxiety and marital status (P=0.053, nor between test anxiety and level of education (P=0.057. Conclusion: Regarding the high prevalence of test anxiety in students, far further research is recommended to identify factors relevant to this phenomenon and to present strategies to reduce it

  12. 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)

  13. Models of the heat dynamics of solar collectors for performance testing

    DEFF Research Database (Denmark)

    Bacher, Peder; Madsen, Henrik; Perers, Bengt

    2011-01-01

    The need for fast and accurate performance testing of solar collectors is increasing. This paper describes a new technique for performance testing which is based on non-linear continuous time models of the heat dynamics of the collector. It is shown that all important performance parameters can be accurately estimated with measurements from a single day. The estimated parameters are compared with results from standardized test methods (Fischer et al., 2004). Modelling the dynamics of the collect...

  14. 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.

  15. 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

  16. A Grey Relational Analysis Between Some Selected Affective Factors and English Test Performance

    OpenAIRE

    DONG, MEI

    2014-01-01

    With Grey relational analysis (GRA), the paper examined the sensitivity of eight variables influencing test performance at branch level. The eight variables involved included language proficiency, test anxiety, self-esteem, achievement motivation, achievement goal, English proficiency test anxiety (EPTA), state anxiety and trait anxiety. Results showed that: (1) Besides language proficiency, motivation-to-avoid- failure was most sensitive to English test performance; (2) Trait and state anxie...

  17. 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.

  18. 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.

  19. Application of biological feedback for estimation of anaerobic performance in jumping test

    Directory of Open Access Journals (Sweden)

    Kovalenko S.O.

    2014-10-01

    Full Text Available Purpose : - To determine the effect of biofeedback to determine the level of anaerobic performance of healthy young men. Material: The characteristics of physical performance in 60-seconds jumping test without and with visual and audible biofeedback (BFB are determined at 23 healthy young men. Results : Significant individual peculiarities are found in performance features of 60-seconds jumping test both without and with BFB. The groups of performance indexes are maximum jumping height; jumping frequency and achieved performance level; correlation of jumping phases and achieved capacity of a separate jump; jumping dynamics during the test. The positive effect mostly on performance in BFB regime is found in the group of persons with low level of physical performance. Conclusion : The application of BFB in 60-seconds jumping test is proved to increase the objective character of measuring anaerobic performance.

  20. Implementation Intentions and Test Anxiety: Shielding Academic Performance from Distraction

    Science.gov (United States)

    Parks-Stamm, Elizabeth J.; Gollwitzer, Peter M.; Oettingen, Gabriele

    2010-01-01

    College students whose test anxiety was measured completed a working memory-intensive math exam with televised distractions. Students were provided with implementation intentions (if-then plans; Gollwitzer, 1999) designed to either help them ignore the distractions (i.e., temptation-inhibiting plans) or focus more intently on the math exam (i.e.,…

  1. 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)

  2. 40 CFR 63.7 - Performance testing requirements.

    Science.gov (United States)

    2010-07-01

    ...data. (ii) The internal QA program shall...an example of internal QA is the sampling... (iii) The external QA program shall...with only minor changes to those tests...intermediate or major change or alternative to...before the close of business on the 60th...

  3. Performance testing of compressed hydrogen vehicle fuel cylinders

    Energy Technology Data Exchange (ETDEWEB)

    Webster, C. [Powertech Labs Inc., Surrey, BC (Canada)

    1999-10-01

    Standard specifications for various types of fuel storage tanks have been reviewed. Based on this review it was suggested that since the storage requirements of hydrogen-fuelled vehicles are essentially the same as those of the natural gas vehicles, the hydrogen industry could enjoy reduced costs by using cylinders developed for storing the compressed natural gas used in natural gas vehicles. These lightweight cylinders have been developed by using higher strength aluminum alloys, higher strength steels, and composites of glass, aramid and carbon fibres. In this series of tests the integrity of the aluminum alloy liner of the Dynetek cylinder was confirmed by compressed hydrogen cycling and pressure cycling after long-term compressed hydrogen storage. Bonfire tests of compressed hydrogen cylinders showed that because of the pressure rise during the application of heat to the cylinder the rate of venting through the pressure relief valve increased, indicating that hydrogen gas under such conditions is in fact safer than compressed natural gas. Permeation test revealed no significant hydrogen loss from the metal-lined cylinder through permeation. Rapid release of compressed hydrogen gas during the gunfire tests showed no damage to the cylinder design. 4 refs.

  4. Test of job performance aids for power plants. Final report

    International Nuclear Information System (INIS)

    The objective of EPRI Research Project 1396-1 was to evaluate the applicability and effectiveness of Job Performance Aids (JPAs) in nuclear power plant situations. For over twenty years, JPAs have been developed in military situations to meet the problems of confusing, incomplete, and inaccurate procedures on maintenance jobs. Kinton, Incorporated of Alexandria, Virginia applied the military experience with JPAs to nuclear power plant situations and identified potential benefits in terms of cost reductions and improved performance. Sample JPAs were developed for Control Room Operations, Maintenance, Plant Operations, Instrumentation and Control, Health Physics, and Quality Assurance tasks (procedures) in selected nuclear plants. JPAs were also developed for a prototype condenser tube leak detection system in the design stage, as well as for generic classes of circuit breaker equipment. Based on the results of the study, the use of JPAs is recommended for plant procedures of medium to high difficulty and for those tasks performed infrequently, even if fairly simple

  5. Aeroacoustic and Performance Simulations of a Test Scale Open Rotor

    Science.gov (United States)

    Claus, Russell W.

    2013-01-01

    This paper explores a comparison between experimental data and numerical simulations of the historical baseline F31/A31 open rotor geometry. The experimental data were obtained at the NASA Glenn Research Center s Aeroacoustic facility and include performance and noise information for a variety of flow speeds (matching take-off and cruise). The numerical simulations provide both performance and aeroacoustic results using the NUMECA s Fine-Turbo analysis code. A non-linear harmonic method is used to capture the rotor/rotor interaction.

  6. Methods for Quantifying the Uncertainties of LSIT Test Parameters, Test Results, and Full-Scale Mixing Performance Using Models Developed from Scaled Test Data

    Energy Technology Data Exchange (ETDEWEB)

    Piepel, Gregory F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Cooley, Scott K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Kuhn, William L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Rector, David R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Heredia-Langner, Alejandro [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-05-01

    This report discusses the statistical methods for quantifying uncertainties in 1) test responses and other parameters in the Large Scale Integrated Testing (LSIT), and 2) estimates of coefficients and predictions of mixing performance from models that relate test responses to test parameters. Testing at a larger scale has been committed to by Bechtel National, Inc. and the U.S. Department of Energy (DOE) to “address uncertainties and increase confidence in the projected, full-scale mixing performance and operations” in the Waste Treatment and Immobilization Plant (WTP).

  7. Using provider performance incentives to increase HIV testing and counseling services in Rwanda.

    Science.gov (United States)

    de Walque, Damien; Gertler, Paul J; Bautista-Arredondo, Sergio; Kwan, Ada; Vermeersch, Christel; de Dieu Bizimana, Jean; Binagwaho, Agnès; Condo, Jeanine

    2015-03-01

    Paying for performance provides financial rewards to medical care providers for improvements in performance measured by utilization and quality of care indicators. In 2006, Rwanda began a pay for performance scheme to improve health services delivery, including HIV/AIDS services. Using a prospective quasi-experimental design, this study examines the scheme's impact on individual and couples HIV testing. We find a positive impact of pay for performance on HIV testing among married individuals (10.2 percentage points increase). Paying for performance also increased testing by both partners by 14.7 percentage point among discordant couples in which only one of the partners is an AIDS patient. PMID:25554976

  8. Fine-motor skills testing and prediction of endovascular performance

    DEFF Research Database (Denmark)

    Bech, Bo; Lönn, Lars

    2013-01-01

    Performing endovascular procedures requires good control of fine-motor digital movements and hand-eye coordination. Objective assessment of such skills is difficult. Trainees acquire control of catheter/wire movements at various paces. However, little is known to what extent talent plays for novice candidates at entry to practice.

  9. Dynamic compaction of salt: Initial demonstration and performance testing

    International Nuclear Information System (INIS)

    Reconsolidated crushed salt is proposed as the sole long-term shaft seal between the Waste Isolation Pilot Plant (WIPP) and the biosphere. The concept for a long-term shaft seal for the WIPP repository is to place crushed salt in the four shafts and to develop an effective seal as the surrounding salt creeps into the shafts, reconsolidating the salt. Permeability of the salt components is calculated to achieve performance objectives at some acceptable time in the future, an expectation which is a key to performance assessment calculations for the WIPP. Such a seal has never been constructed, and until now no performance measurements have been made on an appropriately large scale. A full understanding of construction methods, achievable initial density and permeability and time-wise performance of reconsolidating salt is required. This paper discusses nearly full-scale dynamic compaction of mine-run WIPP salt, preliminary measurements of density and permeability, and their variability within a relatively large volume of compacted material

  10. 40 CFR 63.1384 - Performance test requirements.

    Science.gov (United States)

    2010-07-01

    ...glass pull rate for each glass-melting furnace and, if different, the...for each existing and new glass-melting furnace. (5) During the performance...the owner or operator of a glass-melting furnace controlled by an ESP...

  11. Experience from performance testing of low NOx burners for refinery heaters; Tests de performance avec des bruleurs de raffinerie a basse emission de NOx

    Energy Technology Data Exchange (ETDEWEB)

    Boden, J.C. [Refining Technology, BP Oil International, Sunbury (United Kingdom)

    2001-07-01

    Developments in low NOx burner technology have resulted in major reductions in NOx emissions from refinery process heaters. However, the techniques used in low NOx burners to reduce NOx emissions can potentially affect other key aspects of burner performance, particularly flame stability and completeness of combustion. BP has evaluated many of the currently available low and ultra-low NOx burners, both natural and forced draught, in its purpose-built test furnace. This extensive test programme has shown that to be a reliable predictor of actual performance a test rig must recreate accurately the real furnace conditions, particularly with respect to furnace and hearth temperatures. The testing has demonstrated the NOx emissions to be expected in practice from different generic types of burner, conventional, low NOx and ultra-low NOx, and has highlighted the sets of conditions most likely to lead to combustion performance problems. (authors)

  12. Performance test of wavelength-shifting acrylic plastic Cherenkov detector

    CERN Document Server

    Beckford, B; de la Puente, A; Fuji, Y; Futatsukawa, K; Hashimoto, O; Kaneta, M; Kanda, H; Koike, T; Maeda, K; Matsumura, A; Nakamura, S N; Okayasu, Y; Perez, N; Reinhold, J; Shirotori, K; Tamura, H; Tang, L; Tsukada, K

    2010-01-01

    The collection efficiency for Cherenkov light incident on a wavelength shifting plate (WLS) has been determined during a beam test at the Proton Synchrotron facility located in the National Laboratory for High Energy Physics (KEK), Tsukuba, Japan. The experiment was conducted in order to determine the detector's response to photoelectrons converted from photons produced by a fused silica radiator; this allows for an approximation of the detector's quality. The yield of the photoelectrons was measured as a function of the momentum of the incident hadron beam. The yield is proportional to sin2{\\theta}c, where {\\theta}c is the opening angle of the Cherenkov light created. Based on estimations and results from similarly conducted tests, where the collection efficiency was roughly 39%, the experimental result was expected to be around 40% for internally produced light from the WLS. The results of the experiment determined the photon collection response efficiency of the WLS to be roughly 62% for photons created in...

  13. Latest developments in gamma-camera performance testing: resolution measurements

    International Nuclear Information System (INIS)

    Resolution for gamma cameras has two distinct aspects: spatial resolution, referring to the ability to image closely spaced point or line sources of radioactivity as separate entities; and temporal resolution, referring to the ability to properly register two events occurring within a very small time interval as separate events. The BRH Test Pattern has been proven to be a valuable tool for the evaluation of spatial resolution in a wide variety of gamma cameras. A reading from a transmission image of this pattern provides adequate accuracy (0.5 mm minimal separation) for determining intrinsic resolution, and for making an evaluation of spatial distortion and nonuniformities. This pattern can be used for acceptance testing of newly installed equipment and for quality control of all types of gamma cameras as well. Images taken weely may reveal changes in intrinsic resolution, field uniformity, and spatial distortion that may occur gradually over a period of time

  14. ENHANCING TEST SENSITIVITY IN TOXICITY TESTING BY USING A STATISTICAL PERFORMANCE STANDARD

    Science.gov (United States)

    Previous reports have shown that within-test sensitivity can vary markedly among laboratories. Experts have advocated an empirical approach to controlling test variability based on the MSD, control means, and other test acceptability criteria. (The MSD represents the smallest dif...

  15. The Impact of Personality and Test Conditions on Mathematical Test Performance

    Science.gov (United States)

    Hayes, Heather; Embretson, Susan E.

    2013-01-01

    Online and on-demand tests are increasingly used in assessment. Although the main focus has been cheating and test security (e.g., Selwyn, 2008) the cross-setting equivalence of scores as a function of contrasting test conditions is also an issue that warrants attention. In this study, the impact of environmental and cognitive distractions, as…

  16. INVITATION TO PERFORM Y2K TESTING UNDER UNIX

    CERN Multimedia

    CERN Y2K Co-ordinator

    1999-01-01

    IntroductionA special AFS cell Ôy2k.cern.chÕ has been established to allow service managers and users to test y2k compliance.In addition to AFS, the cluster consists of machines representing all the Unix flavours in use at CERN (AIX, DUNIX, HP-UX, IRIX, LINUX, and SOLARIS).More information can be obtained from the page: http://wwwinfo.cern.ch/pdp/bis/y2k/y2kplus.htmlTesting scheduleThe cluster will be set to 25 December 1999 on fixed days and then left running for three weeks. This gives people one week to prepare test programs in 1999 and two weeks to check the consequences of passing into year 2000. These fixed dates are set as follows:? 19 May 1999, date set to 25/12/99 (year 2000 starts on 26 May) ? 9 June1999, date set to 25/12/99 (year 2000 starts on 16 June)? 30 June 1999, date set to 25/12/99 (year 2000 starts on 7 July)If more than these three sessions are needed an announcement will be made later. RegistrationThe following Web page should be used for r...

  17. K-500-60/1500 turbine performance test results

    International Nuclear Information System (INIS)

    On the basis of calculation-experimental technique the manouvring characteristics of the K-500-60/1500 turbine have been investigated. The tests are made at the Novovoroneh-5. Temperature distribution in the vessel and rotor of joint of high and medium pressure turbie steam pressure before control valves and flange heating of turbine external vessel have been studied. Test results confirmed the efficiency of the calculation-experimental technique of alternating regimes of wet-steam turbines. According to test results the optimization of starting regimes and algorithms of automated control over turbine operation start-up is made. High manoeuvring characteristics of the turbine, and a possibility of a start-u after shutdown for 54 in particular, are confirmed. In the case of start-up from the cold state the turbine can get the full loading in 2 h 10 min med. In the case of start-up from the cold state the turbine can get the full loading in 2 h

  18. Cryogenic Thermal Performance Testing of Bulk-Fill and Aerogel Insulation Materials

    Science.gov (United States)

    Scholtens, B. E.; Fesmire, J. E.; Sass, J. P.; Augustynowicz, S. D.; Heckle, K. W.

    2007-01-01

    The research testing and demonstration of new bulk-fill materials for cryogenic thermal insulation systems was performed by the Cryogenics Test Laboratory at NASA Kennedy Space Center. Thermal conductivity testing under actual-use cryogenic conditions is a key to understanding the total system performance encompassing engineering, economics, and materials factors. A number of bulk fill insulation materials, including aerogel beads, glass bubbles, and perlite powder, were tested using a new cylindrical cryostat. Boundary temperatures for the liquid nitrogen boil-off method were 293 K and 78 K. Tests were performed as a function of cold vacuum pressure from high vacuum to no vacuum conditions. Results are compared with other complementary test methods in the range of 300 K to 20 K. Various testing techniques are shown to be required to obtain a complete understanding of the operating performance of a material and to provide data for answers to design engineering questions.

  19. Relationships Between the Yo-Yo Intermittent Recovery Test and Anaerobic Performance Tests in Adolescent Handball Players

    OpenAIRE

    Hermassi, Souhail; Aouadi, Ridha; Khalifa, Riadh; Van Den Tillaar, Roland; Shephard, Roy J; Chelly, Mohamed Souhaiel

    2015-01-01

    The aim of the present study was to investigate relationships between a performance index derived from the Yo-Yo Intermittent Recovery Test level 1 (Yo-Yo IR1) and other measures of physical performance and skill in handball players. The other measures considered included peak muscular power of the lower limbs (Wpeak), jumping ability (squat and counter-movement jumps (SJ, CMJ), a handball skill test and the average sprinting velocities over the first step (VS) and the first 5 m (V5m). Test s...

  20. The Effect of Stress and Recovery on Field-test Performance in Floorball.

    Science.gov (United States)

    van der Does, H T D; Brink, M S; Visscher, C; Huijgen, B C H; Frencken, W G P; Lemmink, K A P M

    2015-06-01

    Physical and psychosocial stress and recovery are important performance determinants. A holistic approach that monitors these performance determinants over a longer period of time is lacking. Therefore this study aims to investigate the effect of a player's physical and psychosocial stress and recovery on field-test performance. In a prospective non-experimental cohort design 10 female Dutch floorball players were monitored over 6 months. To monitor physical and psychosocial stress and recovery, daily training-logs and 3-weekly the Recovery-Stress Questionnaire for Athletes (RESTQ-Sport) were filled out respectively. To determine field-test performance 6 Heart rate Interval Monitoring System (HIMS) and 4 Repeated Modified Agility T-test (RMAT) measurements were performed. Multilevel prediction models were applied to account for within-players and between-players field-test performance changes. The results show that more psychosocial stress and less psychosocial recovery over 3-6 weeks before testing decrease HIMS performance (p?0.05). More physical stress over 6 weeks before testing improves RMAT performance (p?0.05). In conclusion, physical and psychosocial stress and recovery affect submaximal interval-based running performance and agility up to 6 weeks before testing. Therefore both physical and psychosocial stress and recovery should be monitored in daily routines to optimize performance. PMID:25734914