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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. In-place testing of off-gas iodine filters

    International Nuclear Information System (INIS)

    At the Idaho National Engineering Laboratory, both charcoal and silver zeolite (AgX) filters are used for radioactive iodine off-gas cleanup of reactor systems. These filters are used in facilities which are conducting research in the areas of reactor fuel failure, reactor fuel inspection, and loss of fluids from reactor vessels. Iodine retention efficiency testing of these filters is dictated by prudent safety practices and regulatory guidelines. A procedure for determining iodine off-gas filter efficiency in-place has been developed and tested on both AgX and charcoal filters. The procedure involves establishing sample points upstream and downstream of the filter to be tested. A step-by-step approach for filter efficiency testing is presented

  4. 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.)

  5. 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)

  6. 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.

  7. 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

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

    International Nuclear Information System (INIS)

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

  9. 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.

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

    International Nuclear Information System (INIS)

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

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

    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

  12. 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

  13. 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

  14. 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

  15. 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.

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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.

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

    International Nuclear Information System (INIS)

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

  4. 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.

  5. 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

  6. 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

  7. 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.

  8. 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

  9. 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 increases in the sulfur impregnated activated carbon (AC-S) column. Data are provided in this final report for all the required emission samples as well as melter and off-gas conditions during all the sampling periods. Appended to this report are previously issued VSL Letter Reports on method development for monitoring allyl alcohol in melter exhaust streams, on the results of characterization of the selected AC-S carbon media (Donnau BAT37), and on DM1200 off-line tests on the AC-S bed; also appended are reports from Air Tech on emissions sampling, and reports from Keika Ventures on validation of analytical data provided by Severn Trent Laboratories of Knoxville, Tennessee.

  10. 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

  11. 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)

  12. 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.

  13. 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)

  14. 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

  15. 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.

  16. 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

  17. 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.

  18. 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)

  19. Laboratory Optimization Tests of Technetium Decontamination of Hanford Waste Treatment Plant Direct Feed Low Activity Waste Melter Off-Gas Condensate Simulant

    Energy Technology Data Exchange (ETDEWEB)

    Taylor-Pashow, K. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-12-23

    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. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable less integrated 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.

  20. 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

  1. Performance tests.

    OpenAIRE

    Wetherell, A

    1996-01-01

    This paper discusses the use of psychological performance tests to assess the effects of environmental stressors. The large number and the variety of performance tests are illustrated, and the differences between performance tests and other psychological tests are described in terms of their design, construction, use, and purpose. The stressor emphasis is on the effects of drugs since that is where most performance tests have found their main application, although other stressors, e.g., fatig...

  2. 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

  3. Adsorption modeling for off-gas treatment

    International Nuclear Information System (INIS)

    Off-gas generated from the reprocessing of used nuclear fuel contains a mixture of several radioactive gases including 129I2, 85Kr, HTO, and 14CO2. Over the past few decades, various separation and recovery processes have been studied for capturing these gases. Adsorption data for gaseous mixtures of species can be difficult to determine experimentally. Therefore, procedures capable of predicting the adsorption behavior of mixtures need to be developed from the individual isotherms of each of the pure species. A particular isotherm model of interest for the pure species is the Generalized Statistical Thermodynamic Adsorption isotherm. This model contains an adjustable number of parameters and will therefore describe a wide range of adsorption isotherms for a variety of components. A code has been developed in C++ to perform the non-linear regression analysis necessary for the determination of the isotherm parameters, as well as the least number of parameters needed to describe an entire set of data. (authors)

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. Off-gas system recombining system

    International Nuclear Information System (INIS)

    In a BWR type reactor, exhaust gases are accumulated in the upper portion of a condensator which contain hydrogen, oxygen, nirogen, etc. and, accordingly, can not be released as they are into the atmosphere. An off-gas system is disposed for processing the exhaust gases safely and releasing them into the atmosphere. The exhaust gases are sucked by a steam type extract or, sent to a preheater, warmed to about 160degC and then sent to a recombiner. The recombiner is adapted to recombine hydrogen and oxygen into steams while keeping them out of a detonating range to prevent an accidental explosion. Then, a hydrogen densitometer is disposed in the exhaust gases guided to the recombiner and oxygen is injected such that the oxygen density in the exhaust gases flowing into the recombiner is made higher thanb 1/2 of the hydrogen concentration depending on the signals from the densitometer. Since the inside of the recombiner is in an oxygen excess region, the catalyst performance is improved outstandingly to increase the hydrogen conversion ratio. Thus, it is possible to reduce the volume and the size of the catalyst and the recombiner. (N.H.)

  9. 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

  10. 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.

  11. Off-gas treatment in HTR fuel reprocessing

    International Nuclear Information System (INIS)

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

  12. 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.

  13. 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.

  14. 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.

  15. 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)

  16. 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...

  17. 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

  18. 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

  19. 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+/ΣFe 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.

  20. 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+/ΣFe 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.

  1. Separation technology for radioactive iodine from off-gas streams of nuclear facilities

    International Nuclear Information System (INIS)

    Iodine separation technology using an inorganic adsorption material has been investigated in order to apply the technology to the off-gas treatment systems of nuclear facilities. Iodine removal efficiencies were checked by laboratory experiments using simulated off-gas streams of various conditions and the developed adsorbent, silver impregnated alumina (AgA). Laboratory test results demonstrated effective iodine removal with high decontamination factors (DF's) at relatively high temperatures (?100degC). Then the removal efficiency were confirmed using actual off-gas streams sampled from the dissolver off-gas treatment system of the Karlsruhe reprocessing plant. The DF's were over 103 with the AgA bed depth of 10 cm and showed little change during the adsorption period, which indicated applicability of the iodine removal technology with AgA to nuclear fuel reprocessing plants. Iodine absorption capacity and its release property were also investigated using simulated off-gas streams. The former had a value of ?0.22 g/g-AgA and this value could well predict the breakthrough property. The adsorbed iodine was judged stable during the storage of AgA saturated with iodine in air at temperatures below 500degC and in water at ?20degC after changing the adsorbed iodine form from AgIO3 to AgI. Thus, the separation technology provided effective and stable iodine separation from the off-gas of nuclear facilities. (author)

  2. Enhancing energy recovery in the steel industry: Matching continuous charge with off-gas variability smoothing

    International Nuclear Information System (INIS)

    Highlights: A system based on phase change material is inserted into the off-gas-line of a continuous charge electric arc furnace. The off-gas temperature profile after scrap preheating is smoothed. A heat transfer fluid through phase change material containers allows to control overheating issues. The smoothed off-gas profiles enable efficient downstream power generation. The recovery system investment cost is decreased due to lower sizes of components. - Abstract: In order to allow an efficient energy recovery from off-gas in the steel industry, the high variability of heat flow should be managed. A temperature smoothing device based on phase change materials at high temperatures is inserted into the off-gas line of a continuous charge electric arc furnace process with scrap preheating. To address overheating issues, a heat transfer fluid flowing through containers is introduced and selected by developing an analytical model. The performance of the smoothing system is analyzed by thermo-fluid dynamic simulations. The reduced maximum temperature of off-gas allows to reduce the size and investment cost of the downstream energy recovery system, while the increased minimum temperature enhances the steam turbine load factor, thus increasing its utilization. Benefits on environmental issues due to dioxins generation are also gained

  3. 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)

  4. 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)

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

    International Nuclear Information System (INIS)

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

  6. 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.

  7. 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

  8. Electric furnace off-gas cleaning systems at PT Inco

    Energy Technology Data Exchange (ETDEWEB)

    Safe, P.; Russell, M.; Engel, G. [WorleyParsons Gas Cleaning, Irving, TX (United States)

    2008-07-01

    This presentation described an off-gas system designed for an electric furnace. The system was designed to lower particulate emissions, prevent sulphuric acid condensation, and provide capacity for planned furnace operation and production levels. The off-gas consisted mainly of carbon monoxide (CO) and hydrogen (H{sub 2}). Freeboard gas analyses were conducted to characterize off-gas volume and composition. A full combustion system was selected. Furnaces were operated with a slight negative draft setpoint to allow for fluctuations in gas generation. A combustion chamber was sized to maintain gas velocities in the range of 25 to 35 m/s. A spray chamber was used to cool the fully combusted gas, and furnace draft control was achieved by a louvered draft control damper. A secondary ventilation system was used to cool the primary off-gas to a temperature below 260 degrees C. A baghouse was used to remove particulates from the off-gas. Other equipment included an induced draft fan and dust handling equipment. It was concluded that the off-gas systems are now successfully operating in 4 furnaces. tabs., figs.

  9. Preliminary Results from Electric Arc Furnace Off-Gas Enthalpy Modeling

    Energy Technology Data Exchange (ETDEWEB)

    Nimbalkar, Sachin U [ORNL; Thekdi, Arvind [E3M Inc; Keiser, James R [ORNL; Storey, John Morse [ORNL

    2015-01-01

    This article describes electric arc furnace (EAF) off-gas enthalpy models developed at Oak Ridge National Laboratory (ORNL) to calculate overall heat availability (sensible and chemical enthalpy) and recoverable heat values (steam or power generation potential) for existing EAF operations and to test ORNL s new EAF waste heat recovery (WHR) concepts. ORNL s new EAF WHR concepts are: Regenerative Drop-out Box System and Fluidized Bed System. The two EAF off-gas enthalpy models described in this paper are: 1.Overall Waste Heat Recovery Model that calculates total heat availability in off-gases of existing EAF operations 2.Regenerative Drop-out Box System Model in which hot EAF off-gases alternately pass through one of two refractory heat sinks that store heat and then transfer it to another gaseous medium These models calculate the sensible and chemical enthalpy of EAF off-gases based on the off-gas chemical composition, temperature, and mass flow rate during tap to tap time, and variations in those parameters in terms of actual values over time. The models provide heat transfer analysis for the aforementioned concepts to confirm the overall system and major component sizing (preliminary) to assess the practicality of the systems. Real-time EAF off-gas composition (e.g., CO, CO2, H2, and H2O), volume flow, and temperature data from one EAF operation was used to test the validity and accuracy of the modeling work. The EAF off-gas data was used to calculate the sensible and chemical enthalpy of the EAF off-gases to generate steam and power. The article provides detailed results from the modeling work that are important to the success of ORNL s EAF WHR project. The EAF WHR project aims to develop and test new concepts and materials that allow cost-effective recovery of sensible and chemical heat from high-temperature gases discharged from EAFs.

  10. 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.

  11. 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.

  12. 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

  13. 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

  14. 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.

  15. 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

  16. 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.

  17. 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.

  18. Analysis on Storage Off-Gas Emissions from Woody, Herbaceous, and Torrefied Biomass

    OpenAIRE

    Jaya Shankar Tumuluru; C. Jim Lim; Xiaotao T. Bi; Xingya Kuang; Staffan Melin; Fahimeh Yazdanpanah; Shahab Sokhansanj

    2015-01-01

    Wood chips, torrefied wood chips, ground switchgrass, and wood pellets were tested for off?gas emissions during storage. Storage canisters with gas?collection ports were used to conduct experiments at room temperature of 20 C and in a laboratory oven set at 40 C. Commercially-produced wood pellets yielded the highest carbon monoxide (CO) emissions at both 20 and 40 C (1600 and 13,000 ppmv), whereas torrefied wood chips emitted the lowest of about

  19. Optimization of Off-gas Trapping Capabilities on Pyroprocessing at KAERI

    International Nuclear Information System (INIS)

    The objective of this report is to develop the optimization of off-gas trapping capabilities on pyroprocessing at KAERI. Based on KAERI's experimental results and experience on the trapping characteristics in terms of chemical species, vacuum degree, and trapping temperature, INL hot experiments will be performed in off-gas treatment system (OTS) for a voloxidizer. Experiments were performed using KAERI OTS (Off-gas Trapping System) to trap the volatile. A fly ash filter was used as a trapping media for cesium, rubidium, molybdenum, and cadmium. Ca-I and Ca-II filters were used a trapping media for technetium (rhenium), molybdenum, antimony, and tellurium, respectively. As results of trapping experiments, it was found that trapping efficiency of gaseous cesium by fly ash filter at 1100 .deg. C under a vacuum condition was increased by ? 10 times, in comparison with that of 1100 .deg. C. Trapping efficiency by fly ash filter at 1100 .deg C under a vacuum condition was increased by ? 10 times, in comparison with that of 1100 .deg. C. Successful trapping of Mo, Te, and mixed species by using Ca- II filter under a vacuum of 7.6 torr was achieved and rhenium was well trapped under a vacuum of 76 torr. Trapping performance of molybdenum by Ca- II filter was better than that of fly ash filter. This report will be used as a useful means for determining optimization of trapping capabilities for trapping semi-volatile fission products

  20. 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.

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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 CO2 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.

  3. 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

  4. 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.

  5. 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

  6. 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

  7. 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

  8. 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.

  9. 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

  10. 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)

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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%

  16. 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.

  17. Process for off-gas particulate removal and apparatus therefor

    International Nuclear Information System (INIS)

    In the event of a breach in the off-gas line of a melter operation requiring closure of the line, a secondary vessel vent line is provided with a particulate collector utilizing atomization for removal of large particulates from the off-gas. The collector receives the gas containing particulates and directs a portion of the gas through outer and inner annular channels. The collector further receives a fluid, such as water, which is directed through the outer channel together with a second portion of the particulate-laden gas. The outer and inner channels have respective ring-like termination apertures concentrically disposed adjacent one another on the outer edge of the downstream side of the particulate collector. Each of the outer and inner channels curves outwardly away from the collector's centerline in proceeding toward the downstream side of the collector. Gas flow in the outer channel maintains the fluid on the channel's wall in the form of a ''wavy film,'' while the gas stream from the inner channel shears the fluid film as it exits the outer channel in reducing the fluid to small droplets. Droplets formed by the collector capture particulates in the gas stream by one of three mechanisms: impaction, interception or Brownian diffusion in removing the particulates. The particulate-laden droplets are removed from the fluid stream by a vessel vent condenser or mist eliminator. 4 figs

  18. Performance Test Procedure for Fuel Test Loop

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Sung Ho; Lee, Jong Min; Park, Su Ki; Chi, Dae Young; Sim, Bong Sik; Lee, Chung Young; Kim, Young Ki; Lee, Kye Hong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2009-10-15

    Fuel Test Loop (FTL) is a test facility which can conduct a fuel irradiation test at HANARO. The FTL simulates commercial NPPs' operating conditions such as their pressure, temperature, flow, water chemistry and neutron flux levels to conduct the irradiation test. The performance test of the FTL has been performing since April, 2007 and expected to be completed in the last half of 2009. In this paper, the performance test procedure for the FTL is introduced.

  19. Performance Test Procedure for Fuel Test Loop

    International Nuclear Information System (INIS)

    Fuel Test Loop (FTL) is a test facility which can conduct a fuel irradiation test at HANARO. The FTL simulates commercial NPPs' operating conditions such as their pressure, temperature, flow, water chemistry and neutron flux levels to conduct the irradiation test. The performance test of the FTL has been performing since April, 2007 and expected to be completed in the last half of 2009. In this paper, the performance test procedure for the FTL is introduced

  20. CHARACTERIZATION OF DWPF MELTER OFF-GAS QUENCHER AND STEAM ATOMIZED SCRUBBER DEPOSIT SAMPLES

    Energy Technology Data Exchange (ETDEWEB)

    Zeigler, K; Ned Bibler, N

    2007-06-06

    This report summarizes the results from the characterization of deposits from the inlets of the primary off-gas Quencher and Steam Atomized Scrubber (SAS) in the Defense Waste Processing Facility (DWPF), as requested by a technical assistance request. DWPF requested elemental analysis and compound identification to help determine the potential causes for the substance formation. This information will be fed into Savannah River National Laboratory modeling programs to determine if there is a way to decrease the formation of the deposits. The general approach to the characterization of these samples included x-ray diffraction (XRD), scanning electron microscopy (SEM), and chemical analysis. The following conclusions are drawn from the analytical results found in this report: (1) The deposits are not high level waste glass from the DWPF melt pool based on comparison of the compositions of deposits to the composition of a sample of glass taken from the pour stream of the melter during processing of Sludge Batch 3. (2) Chemical composition results suggest that the deposits are probably a combination of sludge and frit particles entrained in the off-gas. (3) Gamma emitters, such as Co-60, Cs-137, Eu-154, Am-241, and Am-243 were detected in both the Quencher and SAS samples with Cs-137 having the highest concentration of the gamma emitters. (4) No evidence existed for accumulation of fissile material (U-233, U-235, and Pu-239) relative to Fe in either deposit. (5) XRD results indicated both samples were primarily amorphorous and contained some crystals of the iron oxides, hematite and magnetite (Fe{sub 2}O{sub 3} and Fe(Fe{sub 2}O{sub 4})), along with sodium nitrate (NaNO{sub 3}). The other main crystalline compound in the SAS deposit was mercurous chloride. The main crystalline compound in the Quencher deposit was a uranium oxide compound. These are all sludge components. (6) SEM analysis of the Quencher deposit revealed crystalline uranium compounds within the sample. SEM analysis of the SAS sample could not be performed due to the presence of a significant concentration of Hg in the sample. (7) Essentially all the Na and the S in the off-gas samples were soluble in water. (8) The main soluble anion was NO{sub 3}{sup -} with SO{sub 4}{sup 2-} being second. (9) In contrast to the results for the off-gas deposits analyzed in 2003, soluble compounds of fluoride and chloride were detected; however, their concentrations in the Quencher and SAS deposits were less than one weight percent. (10) The results suggest that the S is primarily in the deposits as the sulfate anion.

  1. Effect of anode off-gas recycling on reforming of natural gas for solid oxide fuel cell systems

    Energy Technology Data Exchange (ETDEWEB)

    Halinen, M.; Thomann, O.; Kiviaho, J. [VTT Technical Research Centre of Finland, Espoo (Finland)

    2012-10-15

    The effect of anode off-gas recycling (AOGR) on the characteristic performance of a natural gas reformer equipped with a precious metal catalyst is investigated experimentally. The reformer is operated both with synthetic AOGR gas and in steam reforming (SR) conditions. The characteristic performance in SR and AOGR mode are compared with equilibrium, and it is found that equilibrium is more readily achieved in AOGR mode. The reformer is used for extended periods of time (100-1,000 h) in conditions where carbon formation is thermodynamically possible to measure any changes in characteristic performance. No significant change in the performance is observed due to carbon formation or catalyst deactivation. The reformer could be successfully implemented in a 10 kW SOFC system with an anode off-gas recycling loop. (Copyright copyright 2012 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  2. 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.)

  3. 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

  4. 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

  5. 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.

  6. Analysis of Off Gas From Disintegration Process of Graphite Matrix by Electrochemical Method

    International Nuclear Information System (INIS)

    Using electrochemical method with salt solutions as electrolyte, some gaseous substances (off gas) would be generated during the disintegration of graphite from high-temperature gas-cooled reactor fuel elements. The off gas is determined to be composed of H2, O2, N2, CO2 and NOx by gas chromatography. Only about 1.5% graphite matrix is oxidized to CO2. Compared to the direct burning-graphite method, less off gas,especially CO2, is generated in the disintegration process of graphite by electrochemical method and the treatment of off gas becomes much easier. (authors)

  7. 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

  8. 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

  9. 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

  10. 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)

  11. 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

  12. 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

  13. Improvement of melter off-gas design for commercial HALW vitrification facility

    International Nuclear Information System (INIS)

    The Japan commercial reprocessing plant is now under construction, and it will commence the operation in 2005. The High Active Liquid Waste (HALW) generated at the plant is treated into glass product at the vitrification facility using the Liquid Fed Joule-Heated Ceramic Melter (LFCM). The characteristic of the LFCM is that the HALW is fed directly onto the molten glass surface with the glass forming material. This process was developed by the Japan Nuclear Cycle Development Institute (JNC). The JNC process was first applied to the Tokai Vitrification Facility (TVF), which is a pilot scale plant having about 1/6 capacity of the commercial facility. The TVF has been in operation since 1995. During the operation, the rapid increase of the differential pressure between the melter plenum and the dust scrubber was observed. This phenomenon is harmful to the long-term continuous operation of TVF. And, it is also anticipated that the same phenomenon will occur in commercial vitrification facility. In order to solve this problem, the countermeasures were studied and developed. Through the study on the deposit growing mechanism, it was probable that the rapid increased differential pressure was attributed to the condensation of meta-boric acid at the outlet of the air-film cooler slits. And, the heating and the humidification of purge air were judged to be effective as the countermeasures to suppress the condensation. On the other hand, the water injection into melter off-gas pipe was found to be very effective to reduce the differential pressure as the results of the various tests. The deposit adhered on the inner surface of the off-gas pipe was almost washed out. And, it was also demonstrated that the system was superior to other systems by virtue of its simplicity and stability. In order to apply the system to the commercial scale plant, the scale-up tests were conducted at JNC mock-up facility using the acrylic model. (author)

  14. 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.

  15. 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.

  16. 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.

  17. 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

  18. 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

  19. 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...

  20. 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

  1. 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.

  2. 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

  3. Collaborative Test Reviews: Student Performance

    Science.gov (United States)

    Bhatia, Anuradha; Makela, Carole J.

    2010-01-01

    A group study method proved helpful in improving senior-level students' performance on unit tests through collaborative learning. Students of a History of Textiles course voluntarily attended study sessions to review course content and prepare for unit tests. The students who attended the group reviews scored better on tests than those who did

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

    International Nuclear Information System (INIS)

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

  5. Techniques applied and future development trend in off-gas cleaning systems for LWR reactors

    International Nuclear Information System (INIS)

    As an introduction, the techniques applied in off-gas systems are shortly discussed. An off-gas system now under construction - developed by RWE, BBR and Linde in a cooperative effort - is used as an example to illustrate the main features of this auxiliary system of a 1,100 MW PWR. Future development possibilities in the fields of adsorptive delay of noble gases at low temperatures and 85Kr separation by destillation are shortly mentioned. (orig./AK)

  6. Glass melter off-gas system pluggages: Cause, significance, and remediation

    International Nuclear Information System (INIS)

    Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. Experimental glass melters, used to develop the vitrification process, have occasionally experienced problems with pluggage of the off-gas line with solid deposits. The deposits were determined to be mixtures of alkali rich chlorides, sulfates, borates, and fluorides with entrained insoluble particles of Fe2O3 spinel, and frit. The distribution and location of the alkali deposits throughout the off-gas system indicate that the deposits form by vapor-phase transport and condensation. Condensation of the alkali-rich phases cements the entrained particulates causing the off-gas system pluggages. The identification of vapor phase transport as the operational mechanism causing off-gas system pluggages indicates that deposition can be effectively eliminated by increasing the off-gas velocity. The cementitious alkali borates, halides, and sulfates comprising the off-gas line deposits were determined to be water soluble. Thus pluggage can be effectively removed with water and/or steam

  7. 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.

  8. 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

  9. Sport performance and agility tests

    OpenAIRE

    Kr?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...

  10. 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

  11. 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.

  12. Performance Testing of Cutting Fluids

    DEFF Research Database (Denmark)

    Belluco, Walter

    2001-01-01

    The importance of cutting fluid performance testing has increased with documentation requirements of new cutting fluid formulations based on more sustainable products, as well as cutting with minimum quantity of lubrication and dry cutting. Two sub-problems have to be solved: i) which machining tests feature repeatability, reproducibility and sensitivity to cutting fluids, and ii) to what extent results of one test ensure relevance to a wider set of machining situations. The present work is aime...

  13. 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 individual candidates, we...

  14. 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

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

    International Nuclear Information System (INIS)

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

  16. 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

  17. On-line measurements of helium in the off-gas system of BWRs

    Energy Technology Data Exchange (ETDEWEB)

    Larsson, Irina

    2010-06-15

    Supervision of fuel and control rod integrity in a nuclear reactor core is very important for maintaining a safe and reliable operation of the reactor. Fuel and control rod failures can cause increased doses to personnel in the power plant, limitations of the reactor operation and unplanned shut downs, which can lead to large economical losses. To monitor the fuel and control rod integrity in the reactor core, normally grab samples of the off-gases and the reactor water are taken with regular time intervals. However, in this thesis a new developed system consisting of combined on-line gamma and He measurements in the off-gases is described. This system is providing continuous and reliable information of both the fuel and control rod integrity. The work described in the thesis was performed in collaboration with Kernkraftwerk Leibstadt (KKL) in Switzerland and Forsmarks Kraftgrupp AB in Sweden. The objectives of the work were to install He detector system in the off-gas systems at the nuclear power plants and to evaluate the abilities of detecting fuel and control rods failures. A He detector system was installed at KKL in September 2008 as a complement to an online gamma measurement system, which has been in operation since 2004. The He measuring system has shown good reliability and efficiency and a detailed evaluation of the system and its performance are summarised in a proprietary report. Installation of a He measuring system at Forsmark 3 is planned to take place during summer 2010

  18. 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)

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

    International Nuclear Information System (INIS)

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

  20. 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

  1. Online titrimetric and off-gas analysis for examining nitrification processes in wastewater treatment.

    Science.gov (United States)

    Gapes, Daniel; Pratt, Steven; Yuan, Zhiguo; Keller, Jurg

    2003-06-01

    The two steps of nitrification, namely the oxidation of ammonia to nitrite and nitrite to nitrate, often need to be considered separately in process studies. For a detailed examination, it is desirable to monitor the two-step sequence using online measurements. In this paper, the use of online titrimetric and off-gas analysis (TOGA) methods for the examination of the process is presented. Using the known reaction stoichiometry, combination of the measured signals (rates of hydrogen ion production, oxygen uptake and carbon dioxide transfer) allows the determination of the three key process rates, namely the ammonia consumption rate, the nitrite accumulation rate and the nitrate production rate. Individual reaction rates determined with the TOGA sensor under a number of operation conditions are presented. The rates calculated directly from the measured signals are compared with those obtained from offline liquid sample analysis. Statistical analysis confirms that the results from the two approaches match well. This result could not have been guaranteed using alternative online methods. As a case study, the influences of pH and dissolved oxygen (DO) on nitrite accumulation are tested using the proposed method. It is shown that nitrite accumulation decreased with increasing DO and pH. Possible reasons for these observations are discussed. PMID:12753845

  2. 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

  3. 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

  4. SBAS ionospheric performance evaluation tests

    OpenAIRE

    Prats Menndez, Xavier; Ors Prez, Ral; 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. 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.)

  6. 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

  7. Radioactive material packaging performance testing

    International Nuclear Information System (INIS)

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

  8. Human performance testing and simulators.

    Science.gov (United States)

    Cadeddu, Jeffrey A; Kondraske, George V

    2007-03-01

    Virtual-reality (VR) simulation offers the opportunity to practice surgical techniques and gain experience outside the operating room. Using VR simulators and tools recently developed by human performance researchers, different aspects of human performance (innate ability) can be measured objectively. These novel tools, General Systems Performance Theory, and application of nonlinear causal resource analysis (NCRA) may allow us to utilize VR simulators, not only to train physicians, but possibly to predict their performance prior to training. By analyzing objective measures of basic performance resources (BPRs) with performance models developed with NCRA, we showed that BPRs can predict a subject's ability to perform high-level tasks. Two pilot studies suggested that this approach may objectively identify limitations of the surgeons with the most worrisome performance scores. Thus, VR simulation and performance testing may help with identification and remediation of residents with poor endoscopic skills and with optimization of surgical training protocols. Although the initial observations provide encouraging results for objective prediction of surgical performance and identification of performance-limiting resources, further investigation in larger cohorts of surgical trainees appears warranted. PMID:17444775

  9. GEM: Performance and aging tests

    International Nuclear Information System (INIS)

    Performance and aging tests have been done to characterize Gas Electron Multipliers (GEMs), including further design improvements such as a thicker GEM and a closed GEM. Since the effective GEM gain is typically smaller than the absolute GEM gain, due to trapping of avalanche electrons at the bottom GEM electrode, the authors performed field simulations and measurements for better understanding, and discuss methods to eliminate this effect. Other performance parameters of the GEMs are also presented, including absolute GEM gain, short-term and long-term gain stabilities

  10. 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

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

    International Nuclear Information System (INIS)

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

  12. 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.)

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

    International Nuclear Information System (INIS)

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

  14. Reflectors for SAR performance testing.

    Energy Technology Data Exchange (ETDEWEB)

    Doerry, Armin Walter

    2008-01-01

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

  15. 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.)

  16. 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)

  17. Analysis on Storage Off-Gas Emissions from Woody, Herbaceous, and Torrefied Biomass

    Directory of Open Access Journals (Sweden)

    Jaya Shankar Tumuluru

    2015-03-01

    Full Text Available Wood chips, torrefied wood chips, ground switchgrass, and wood pellets were tested for off?gas emissions during storage. Storage canisters with gas?collection ports were used to conduct experiments at room temperature of 20 C and in a laboratory oven set at 40 C. Commercially-produced wood pellets yielded the highest carbon monoxide (CO emissions at both 20 and 40 C (1600 and 13,000 ppmv, whereas torrefied wood chips emitted the lowest of about <200 and <2000 ppmv. Carbon dioxide (CO2 emissions from wood pellets were 3000 ppmv and 42,000 ppmv, whereas torrefied wood chips registered at about 2000 and 25,000 ppmv, at 20 and 40 C at the end of 11 days of storage. CO emission factors (milligrams per kilogram of biomass calculated were lowest for ground switchgrass and torrefied wood chips (2.68 and 4.86 mg/kg whereas wood pellets had the highest CO of about 10.60 mg/kg, respectively, at 40 C after 11 days of storage. In the case of CO2, wood pellets recorded the lowest value of 55.46 mg/kg, whereas switchgrass recorded the highest value of 318.72 mg/kg. This study concludes that CO emission factor is highest for wood pellets, CO2 is highest for switchgrass and CH4 is negligible for all feedstocks except for wood pellets, which is about 0.374 mg/kg at the end of 11-day storage at 40 C.

  18. 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

  19. 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

  20. MUSE instrument global performance test

    Science.gov (United States)

    Loupias, M.; Kosmalski, J.; Adjali, L.; Bacon, R.; Boudon, D.; Brotons, L.; Caillier, P.; Capoani, L.; Daguis, E.; Jarno, A.; Hansali, G.; Kelz, A.; Laurent, F.; Migniau, J. E.; Pcontal-Rousset, A.; Piqueras, L.; Remillieux, A.; Renault, E.; Streicher, O.; Weilbacher, P.; Zins, G.

    2012-09-01

    MUSE (Multi Unit Spectroscopic Explorer) is a second generation instrument developed for ESO (European Southern Observatory) and will be assembled to the VLT (Very Large Telescope) in 2013. The MUSE instrument can simultaneously record 90.000 spectra in the visible wavelength range (465-930nm), across a 1*1arcmin field of view, thanks to 24 identical Integral Field Units (IFU). A collaboration of 7 institutes has partly validated and sent their subsystems to CRAL (Centre de Recherche Astrophysique de Lyon) in 2011, where they have been assembled together. The global test and validation process is currently going on to reach the Preliminary Acceptance in Europe in 2012. The sharing of performances has been based on 5 main functional sub-systems. The Fore Optics sub-system derotates and anamorphoses the VLT Nasmyth focal plane image, the Splitting and Relay Optics associated with the Main Structure are feeding each IFU with 1/24th of the field of view. Each IFU is composed of a 3D function insured by an image slicer system and a spectrograph, and a detection function by a 4k*4k CCD cooled down to 163K. The 5th function is the calibration and data reduction of the instrument. This article depicts the sequence of tests that has been completely reshafled mainly due to planning constraints. It highlights the priority given to the most critical performances tests of the sub-systems and their results. It enhances then the importance given to global tests. Finally, it makes a status on the verification matrix and the validation of the instrument and gives a critical view on the risks taken.

  1. Demonstration of fly-ash filter for trapping volatile radioactive cesium in off-gas stream

    International Nuclear Information System (INIS)

    The object of this study is to design and operate the fly ash filter unit for trapping cesium in the vitrification pilot process of radioactive waste in the low and medium level. It is necessary to reuse fly ash, which is a kind of waste from coal fired power plant, in trapping cesium generated from vitrification process and improving safety and removal efficiency of off gas treatment system. According to the XRD analysis on the trapping cesium compounds by the fly ash filter, the thermally stable pollucite phase was formed when the SOx or NOx was used as the carrier gas. The trapping efficiency of volatile cesium by the fly ash filter was decreased with the increase of face velocity, whereas the efficiency was increased with the increase of the reaction temperature. And also, by increasing the reaction time, the efficiency was decreased. The trapping efficiency of volatile cesium by the fly ash filter was higher than 99.5 percent under the air or NOx/air as a carrier gas, however, the efficiency was decreased to 99.0 percent under the NOx/N2 as a carrier gas. By the way, the effect of NOx in the vitrification pilot process might be negligible due to the supply of the significant amount of oxygen. However, because using the SOx as the carrier gas the efficiency was slightly decreased to 93.5 percent, the influence of the SOx on the trapping cesium by the fly ash filter seems to be concerned in that pilot process. The fly ash filter unit was performed in the vitrification pilot process, but the trapping efficiency of cesium by that filter could not measured because analytical instruments can not detect the cesium. However, it is confirmed that the the stainless steel 310 can be used for the material of filter frame and housing and shows the corrosion resistance at high temperature (1000 deg C). (author)

  2. Radioactive material packaging performance testing

    International Nuclear Information System (INIS)

    In an effort to provide uniform packaging of hazardous material on an international level, recommendations for the transport of dangerous goods have been developed by the United Nations. These recommendations are performance oriented and contrast with a large number of packaging specifications in the US Department of Transportation's hazard materials regulations. This dual system presents problems when international shipments enter the US Department of Transportation's system. Faced with the question of continuing a dual system or aligning with the international system, the Research and Special Programs Administration of the US Department of Transportation responded with Docket HM-181. This began the transition toward the international transportation system. Following close behind is Docket HM-169A, which addressed low specific activity radioactive material packaging. This paper will discuss the differences between performance-oriented and specification packaging, the transition toward performance-oriented packaging by the US Department of Transportation, and performance-oriented testing of radioactive material packaging by Westinghouse Hanford Company. Dockets HM-181 and HM-169A will be discussed along with Type A (low activity) and Type B (high activity) radioactive material packaging evaluations

  3. Analysis and efficiency enhancement of a boil-off gas reliquefaction system with cascade cycle on board LNG carriers

    International Nuclear Information System (INIS)

    Highlights: • An LNG boil-off gas reliquefaction plant on board LNG carriers is improved. • Relevant improvements deals with a study on BOG–C2H4–C3H6 cascade system. • A novel design is proposed to reduce power consumption and COP improvement. • Efficiency improvement by BOG cold energy recovery and compression heat rejection. • Efficiency increase operating in parallel with the engine fuel gas supply system. - Abstract: In this paper, an LNG boil-off gas (BOG) reliquefaction plant operating in accordance with cascade vapor compression cycles, using propylene and ethylene as refrigerants, on board LNG carriers is investigated. As consequence of the analysis results, a new and original design is proposed to reduce power consumption and improve its exergy efficiency. Through energy and exergy analysis, a thermodynamic model is carried out to analyse and evaluate operating conditions as well as to obtain performance values such as the Coefficient of Performance (COP), exergy efficiency, irreversibilities and specific energy consumption. The thermodynamic analysis is performed using the Engineering Equation Solver (EES) software environment. The results of the improved design implemented on the reliquefaction plant for LNG tank conditions of -160.82 °C, a plant BOG input temperature of −125 °C and 25 °C seawater, give COP values of 0.22 and an exergetic efficiency of 37%, such values being 22.22% and 19.35% greater than the original design. The specific energy consumption decreases 14.66% to 0.64 kW h per kg/s of natural BOG. The proposal for improving efficiency is founded on BOG cold energy recovery and BOG compression heat rejection with cooling water in the intercoolers

  4. Test Performance Related Dysfunctional Beliefs

    Directory of Open Access Journals (Sweden)

    Recep TÜTÜNCÜ

    2012-11-01

    Full Text Available Objective: Examinations by using tests are very frequently used in educational settings and successful studying before the examinations is a complex matter to deal with. In order to understand the determinants of success in exams better, we need to take into account not only emotional and motivational, but also cognitive aspects of the participants such as dysfunctional beliefs. Our aim is to present the relationship between candidates’ characteristics and distorted beliefs/schemata just before an examination. Method: The subjects of the study were 30 female and 30 male physicians who were about to take the medical specialization exam (MSE in Turkey. Dysfunctional Attitude Scale (DAS and Young Schema Questionnaire Short Form (YSQ-SF were applied to the subjects. The statistical analysis was done using the F test, Mann-Whitney, Kruskal-Wallis, chi-square test and spearman’s correlation test. Results: It was shown that some of the DAS and YSQ-SF scores were significantly higher in female gender, in the group who could not pass the exam, who had repetitive examinations, who had their first try taking an examination and who were unemployed at the time of the examination. Conclusion: Our findings indicate that candidates seeking help before MSE examination could be referred for cognitive therapy or counseling even they do not have any psychiatric diagnosis due to clinically significant cognitive distortion. Measurement and treatment of cognitive distortions that have negative impact on MSE performance may improve the cost-effectiveness and mental well being of the young doctors.

  5. 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

  6. 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

  7. 40 CFR 60.8 - Performance tests.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 6 2010-07-01 2010-07-01 false Performance tests. 60.8 Section 60.8... PERFORMANCE FOR NEW STATIONARY SOURCES General Provisions 60.8 Performance tests. (a) Except as specified in... conduct performance test(s) and furnish the Administrator a written report of the results of...

  8. Design and operational experience with the off-gas cleaning system of the Seibersdorf incinerator plant

    International Nuclear Information System (INIS)

    After a description of the design and the construction principles of the incinerator building, the furnace and its attached auxilary devices are explained. The incinerator is layed out for low level wastes. It has a vertical furnace, operates with discontinuous feeding for trashes with heat-values between 600 and 10000 kcal/kg waste. The maximum throughput ammounts 40 kg/h. The purification of the off-gas is guaranteed by a multistage filter system: 2 stages with ceramic candles, an electrostatic filter and a HEPA-filter system. The control of the off-gas cleaning is carried out by a stack instrumentation, consisting of an aerosol-, gas-, iodine- and tritium-monitor; the building is surveilled by doserate- and aerosolmonitors. Finally the experiences of the first year of operation and the main problems in running the plant are described. (Author)

  9. 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

  10. 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

  11. 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.)

  12. 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)

  13. 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

  14. 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

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

    International Nuclear Information System (INIS)

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

  16. 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.

  17. Trinity Acceptance Tests Performance Summary.

    Energy Technology Data Exchange (ETDEWEB)

    Rajan, Mahesh [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-01

    Ensuring Real Applications perform well on Trinity is key to success. Four components: ASC applications, Sustained System Performance (SSP), Extra-Large MiniApplications problems, and Micro-benchmarks.

  18. 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

  19. 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

  20. Applied methods and future development trends for off-gas purification facilities of light-water reactors

    International Nuclear Information System (INIS)

    A purification facility for a PWR is introduced for removing oxyhydrogen gas constituents and Xe and Kr, which is designed for underpressure, but still has the possibility to store at excess pressure if off-gas quantities and specific activities require this. The off-gas is cold-dried and adsorptively delayed. The presented state of development concerning adsorptive and destillative separation is shown, also with a view to reprocessing plants. (HP)

  1. Ecotoxicological testing of performance fluids

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  3. AZUR. A plant for purification of dissolver off-gas from WAK

    International Nuclear Information System (INIS)

    The construction of AZUR means a considerable contribution to the eventual licensing and construction of a corresponding plant for the German reprocessing and waste-disposal center; because, according to the recommendation given by the German Commission on Radiological Protection, not only aerosols and iodine, but also krypton is to be removed on a long-term basis from the dissolver off-gas. During operation of AZUR under the realistic, hot conditions of a reprocessing plant results are expected confirming the possibility of industrial realization as well as demonstrating the operational availability under all safety requirements. (orig.)

  4. 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

  5. Performing and evaluating creep tests.

    Czech Academy of Sciences Publication Activity Database

    Dvo?k, Ji?; Blum, W.; Krl, Petr; Eisenlohr, P.; Skleni?ka, Vclav

    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 Mk(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

  6. 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.

  7. 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

  8. 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.)

  9. Concentrating solar collector-performance tests

    Science.gov (United States)

    1979-01-01

    Report summarizes test results from evaluation of concentrating solar collector thermal performance, from transient behavior, and incident-of-angle behavior. Tests were conducted using National Bureau of Standards recommedations and specifications.

  10. Integrated Performance Testing Workshop, Modules 6 - 11

    Energy Technology Data Exchange (ETDEWEB)

    Leach, Janice; Torres, Teresa M.

    2012-10-01

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

  11. 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

  12. Characteristics of off-gas production in plasma melting of non-combustible waste by using nitrogen gas

    International Nuclear Information System (INIS)

    In order to analyze the characteristics of off-gas generated from melting process of non-combustible waste in a plasma torch melter using nitrogen gas as a carrier gas, off-gas concentration was measured. Considerable amounts of NO and particulate were found in the off-gas, but no sulfur oxide or carbon oxide was detected. NO gas concentration in the off-gas was measured controlling the off-gas flow rate from the melter in order to investigate NO gas productive mechanism inside the melter. The results showed that air inleakage rate into the melter had an important role in the production of No gas. NO concentration could be reduced to less than 100ppm by sealing tightly the space between the torch body and the furnace wall of torch guide hole. It is necessary to design the waste feeding system of a commercial plasma torch melter to minimize NO gas production due to thermal mechanism of hot nitrogen gas with oxygen

  13. Novel Sorbent Development and Evaluation for the Capture of Krypton and Xenon from Nuclear Fuel Reprocessing Off-Gas Streams

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-09-01

    The release of volatile radionuclides generated during Used Nuclear Fuel reprocessing in the US will most certainly need to be controlled to meet US regulatory emission limits. A US DOE sponsored Off-Gas Sigma Team has been tasked with a multi-lab collaborative research and development effort to investigate and evaluate emissions and immobilization control technologies for the volatile radioactive species generated from commercial Used Nuclear Fuel (UNF) Reprocessing. Physical Adsorption technology is a simpler and potential economical alternative to cryogenic distillation processes that can be used for the capture of krypton and xenon and has resulted in a novel composite sorbent development procedure using synthesized mordenite as the active material. Utilizing the sorbent development procedure, INL sigma team members have developed two composite sorbents that have been evaluated for krypton and xenon capacities at ambient and 191 K temperature using numerous test gas compositions. Adsorption isotherms have been generated to predict equilibration and maximum capacities enabling modeling to support process equipment scale-up.

  14. Novel Sorbent Development and Evaluation for the Capture of Krypton and Xenon from Nuclear Fuel Reprocessing Off-Gas Streams

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-01

    The release of volatile radionuclides generated during Used Nuclear Fuel reprocessing in the US will most certainly need to be controlled to meet US regulatory emission limits. A US DOE sponsored Off-Gas Sigma Team has been tasked with a multi-lab collaborative research and development effort to investigate and evaluate emissions and immobilization control technologies for the volatile radioactive species generated from commercial Used Nuclear Fuel (UNF) Reprocessing. Physical Adsorption technology is a simpler and potential economical alternative to cryogenic distillation processes that can be used for the capture of krypton and xenon and has resulted in a novel composite sorbent development procedure using synthesized mordenite as the active material. Utilizing the sorbent development procedure, INL sigma team members have developed two composite sorbents that have been evaluated for krypton and xenon capacities at ambient and 191 K temperature using numerous test gas compositions. Adsorption isotherms have been generated to predict equilibration and maximum capacities enabling modeling to support process equipment scale-up.

  15. 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. Perform Ultrasonic Testing on Cs Capsule Overpacks

    International Nuclear Information System (INIS)

    This procedure provides a safe, uniform method for the performance of the ultrasonic weld inspection of the Cesium capsule overpacks. The inspection system will detect cracks, lack of fusion, and lack of penetration. This computer controlled automated system will perform the examination once the capsule overpack has been placed in the pool cell. Examination of the capsule overpacks will be in accordance with drawing H-283014, REV. 0 ,and a certified NDE examiner will perform the test procedure, provide analysis, and test documentation

  18. 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.)

  19. High-temperature corrosion in the off-gas system of a radioactive waste incinerator

    International Nuclear Information System (INIS)

    Corrosion in a low-level radioactive waste incinerator off-gas system at the Department of Energy's Savannah River Plant is discussed. Severe corrosive attack and failure of an Alloy 600 part exposed to high-temperature (>10000C) gases was observed. Rapid attack of carbon steel components, and cracking of austenitic stainless steel parts also occurred at locations where lower gas temperatures and periodic condensate exposure occurred. Investigation showed HCl, SO/sub 2/, SO/sub 3/ and phosphorus oxides were present and contributed to the failures. Mechanisms of high-temperature failure include alloy separation and reactions with phosphorus. Coupons placed in the incinerator discharge stream have provided information for selection of future materials of construction for the high-temperature system components. Several nickel- and iron-base alloys and a stainless steel with an aluminum diffusion coating were investigated

  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. 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

  3. 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

  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. 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

  6. 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

  7. Canadian national internal dosimetry performance testing programme

    International Nuclear Information System (INIS)

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

  8. 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

  9. 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.

  10. PNGV Battery Performance Testing and Analyses

    Energy Technology Data Exchange (ETDEWEB)

    Motloch, Chester George; Belt, Jeffrey R; Christophersen, Jon Petter; Wright, Randy Ben; Hunt, Gary Lynn; Sutula, Raymond; Duong, T.Q.; Barnes, J.A.; Miller, Ted J.; Haskind, H. J.; Tartamella, T. J.

    2002-03-01

    In support of the Partnership for a New Generation of Vehicles (PNGV), the Idaho National Engineering and Environmental Laboratory (INEEL) has developed novel testing procedures and analytical methodologies to assess the performance of batteries for use in hybrid electric vehicles (HEVs). Tests have been designed for both Power Assist and Dual Mode applications. They include both characterization and cycle life and/or calendar life. At periodic intervals during life testing, a series of Reference Performance Tests are executed to determine changes in the baseline performance of the batteries. Analytical procedures include a battery scaling methodology, the calculation of pulse resistance, pulse power, available energy, and differential capacity, and the modeling of calendar- and cycle-life data. PNGV goals, test procedures, analytical methodologies, and representative results are presented.

  11. 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 ...

  12. Cascade Distiller System Performance Testing Interim Results

    Science.gov (United States)

    Callahan, Michael R.; Pensinger, Stuart; Sargusingh, Miriam J.

    2014-01-01

    The Cascade Distillation System (CDS) is a rotary distillation system with potential for greater reliability and lower energy costs than existing distillation systems. Based upon the results of the 2009 distillation comparison test (DCT) and recommendations of the expert panel, the Advanced Exploration Systems (AES) Water Recovery Project (WRP) project advanced the technology by increasing reliability of the system through redesign of bearing assemblies and improved rotor dynamics. In addition, the project improved the CDS power efficiency by optimizing the thermoelectric heat pump (TeHP) and heat exchanger design. Testing at the NASA-JSC Advanced Exploration System Water Laboratory (AES Water Lab) using a prototype Cascade Distillation Subsystem (CDS) wastewater processor (Honeywell d International, Torrance, Calif.) with test support equipment and control system developed by Johnson Space Center was performed to evaluate performance of the system with the upgrades as compared to previous system performance. The system was challenged with Solution 1 from the NASA Exploration Life Support (ELS) distillation comparison testing performed in 2009. Solution 1 consisted of a mixed stream containing human-generated urine and humidity condensate. A secondary objective of this testing is to evaluate the performance of the CDS as compared to the state of the art Distillation Assembly (DA) used in the ISS Urine Processor Assembly (UPA). This was done by challenging the system with ISS analog waste streams. This paper details the results of the AES WRP CDS performance testing.

  13. 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 cycle. The goal of this task was to study what adverse impact the zero-mercury-removal scenario would have on the DWPF melter off-gas system operation. It is stressed again that this study was intended to be scoping in nature, so the results presented in this report are preliminary. Any further substantiation of these results for actual implementation into the DWPF flowsheet would require an in-depth modeling study of all three reaction zones, including the aqueous-phase reactions in the quencher, OGCT, Steam Atomized Scrubber (SAS), and off-gas condenser with recirculated condensate, and the proof-of-principle experiments.

  14. RHIC sextant test: Accelerator systems and performance

    International Nuclear Information System (INIS)

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

  15. Speeded up robust features (SURF) : performance test

    OpenAIRE

    Sayago Benito, Manuel

    2013-01-01

    This work presents a performance analysis of SURF features, an algorithm for feature detection and matching. The goal is to test the performance of SURF in the presence of noise: The analysis is performed both on synthetically generated observations as well on raw images. In first place we present SURF features. Introduction covers the concept of feature extraction, what it is and the interest of it, as well the feature points detection, description and matching. After the intr...

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

    International Nuclear Information System (INIS)

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

  17. NNWSI waste form performance test development

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  19. Blowdown tests performed in the KWU test facility in Karlstein

    International Nuclear Information System (INIS)

    From June to August 1975 the Kernkraftwerk Union in Karlstein performed blowdown tests relating to the dynamic behaviour of pressure-suppression system of boiling water reactors during loss-of-coolant accidents. Part of the blowdown channels used had the same dimensions as used in the BWR-line 69 (600 mm ID). The Institute of Reactor Development participated in these tests with its own instrumentation for pressure measurement. This report describes the test facility and the test performance and gives a survey of the pressures measured as a function of time. In addition, the report contains preliminary results of three-dimensional attenuation and of propagation rates of pressure pulses in the water pool. (orig.)

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, Dong Kee; Kim, Chun Tak; Yoon, Min Soo; Cha, Bong Jun; Kim, Jin Han; Yang, Soo Seok [Korea Aerospace Research Institute, Taejon (Korea, Republic of)

    2001-07-01

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

  2. Virtual Shaker Testing: Simulation Technology Improves Vibration Test Performance

    Science.gov (United States)

    Ricci, Stefano; Peeters, Bart; Fetter, Rebecca; Boland, Doug; Debille, Jan

    2008-01-01

    In the field of vibration testing, the interaction between the structure being tested and the instrumentation hardware used to perform the test is a critical issue. This is particularly true when testing massive structures (e.g. satellites), because due to physical design and manufacturing limits, the dynamics of the testing facility often couples with the test specimen one in the frequency range of interest. A further issue in this field is the standard use of a closed loop real-time vibration control scheme, which could potentially shift poles and change damping of the aforementioned coupled system. Virtual shaker testing is a novel approach to deal with these issues. It means performing a simulation which closely represents the real vibration test on the specific facility by taking into account all parameters which might impact the dynamic behavior of the specimen. In this paper, such a virtual shaker testing approach is developed. It consists of the following components: (1) Either a physical-based or an equation-based coupled electro-mechanical lumped parameter shaker model is created. The model parameters are obtained from manufacturer's specifications or by carrying out some dedicated experiments; (2) Existing real-time vibration control algorithm are ported to the virtual simulation environment; and (3) A structural model of the test object is created and after defining proper interface conditions structural modes are computed by means of the well-established Craig-Bampton CMS technique. At this stage, a virtual shaker test has been run, by coupling the three described models (shaker, control loop, structure) in a co-simulation routine. Numerical results have eventually been correlated with experimental ones in order to assess the robustness of the proposed methodology.

  3. 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.)

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

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

    International Nuclear Information System (INIS)

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

  6. 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)

  7. 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

  8. In situ vitrification pilot-scale radioactive test

    International Nuclear Information System (INIS)

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

  9. Estimating skimmer performance using controlled test data

    International Nuclear Information System (INIS)

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

  10. NIF power balance performance modeling and testing

    Science.gov (United States)

    Kalantar, D. H.; Dixit, S. N.; Haynam, C. A.; Mehta, N. C.; Shaw, M. J.; Widmayer, C. C.; Williams, W. H.

    2007-11-01

    A model for predicting power balance performance on the National Ignition Facility (NIF) has been developed. The Power Balance Model (PBM) uses Laser Performance Operations Model (LPOM) runs with statistical variations in laser performance beam-to-beam and quad-to-quad. We have used this model to predict power balance performance for full NIF ignition shots. These predictions will be presented and compared with results from a series of single quad laser shots where one beam was diagnosed at 3w with the Precision Diagnostic Station (PDS) [1]. The shot-to-shot power repeatability from these PDS tests is consistent with the predicted power balance performance, and with the performance requirements for the ignition campaigns. [1] C. Haynam, et al, International Conference on Inertial Fusion Sciences and Applications, 2007.

  11. Performance, requirements and testing in individual monitoring

    DEFF Research Database (Denmark)

    Julius, H.W.; Christensen, P.; Marshall, T.O.

    For implementation of the ICRP requirements in practical routine monitoring, a specification is needed with respect to specific performance criteria of the dosimetry system. This includes the dosemeters, and procedures for initial and on-going testing of the dosimetry systems to ensure that the...... specified criteria are continuously met. Methods are here specified for establishing performance criteria, and satisfying the ICRP overall accuracy requirements for individual monitoring. Furthermore, procedures are given for obtaining numerical values of the uncertainties connected with individual...

  12. Testing prospect theory in students performance

    OpenAIRE

    Prez Galdn, Patricia; Nicolau Gonzlbez, 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...

  13. Load responsive multilayer insulation performance testing

    International Nuclear Information System (INIS)

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

  14. Performance tests of HENDEL M1 loop

    International Nuclear Information System (INIS)

    The helium engineering demonstration loop (HENDEL) consists of the first and second helium loops (M1 and M2 loops) 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 first loop (M1 loop), during the test operation until March 1983. Finally M1 loop was comfirmed to be able to provide He gas of 4500C, 0.4 kg/s and 4.0 MPa to the fuel stack test section (T1). (author)

  15. 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.

  16. 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.

  17. Testing for Distortions in Performance Measures

    DEFF Research Database (Denmark)

    Sloof, Randolph; Van Praag, Mirjam

    2015-01-01

    Distorted performance measures in compensation contracts elicit suboptimal behavioral responses that may even prove to be dysfunctional (gaming). This paper applies the empirical test developed by Courty and Marschke (Review of Economics and Statistics, 90, 428-441) to detect whether the widely...... used class of residual income-based performance measures-such as economic value added (EVA)-is distorted, leading to unintended agent behavior. The paper uses a difference-in-differences approach to account for changes in economic circumstances and the self-selection of firms using EVA. Our findings...... indicate that EVA is a distorted performance measure that elicits the gaming response....

  18. 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. Normal carbon steel has been used as absorber. 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. (orig.)

  19. SIMS Prototype System 4: performance test report

    Energy Technology Data Exchange (ETDEWEB)

    1978-10-09

    The results obtained during testing of a self-contained, preassembled air type solar system, designed for installation remote from the dwelling, to provide space heating and hot water are presented. Data analysis is included which documents the system performance and verifies the suitability of SIMS Prototype System 4 for field installation.

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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)

  5. 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

  6. Entire performance test for recirculation pump

    International Nuclear Information System (INIS)

    A combination of a recirculation pump, a pump motor, a motor-generator set and associated control apparatus has been tested in the gross for the first time under simulated reactor conditions. A large amount of data, including the characteristics and performance of the equipment have been obtained and evaluated for the range of operation exceeding the normal operation at actual plants. The performance and reliability of every apparatus were confirmed to be sufficient for much severer condition than normal actual plant operation. (author)

  7. 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.).

  8. 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.)

  9. 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

  10. Performance Test of CCTV in a Test Field

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-10-15

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

  11. 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.

  12. 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.

  13. Performance test of 100 W linear compressor

    Energy Technology Data Exchange (ETDEWEB)

    Ko, J; Ko, D. Y.; Park, S. J.; Kim, H. B.; Hong, Y. J.; Yeom, H. K. [Korea Institute of Machinery and Materials, Daejeon(Korea, Republic of)

    2013-09-15

    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.

  14. 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.

  15. 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

  16. 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

  17. 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

  18. 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.

  19. 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.

  20. 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.)

  1. RHIC Sextant Test -- Physics and performance

    International Nuclear Information System (INIS)

    This paper presents beam physics and machine performance results of the Relativistic Heavy Ion Collider (RHIC) Sextant and AGS-to-RHIC (AtR) transfer line during the Sextant Test in early 1997. Techniques used to measure both machine properties (difference orbits, dispersion, and beamline optics) and beam parameters (energy, intensity, transverse and longitudinal emittances) are described. Good agreement was achieved between measured and design lattice optics. The gold ion beam quality was shown to approach RHIC design requirements

  2. 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.

  3. DPM PERFORMANCE TESTING USING RASPBERRY PIS

    CERN Document Server

    Regala, M

    2013-01-01

    This is the final report from attending CERNs 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 CERNs LHC experiments using the small, low-end ARM powered devices named Raspberry Pis. The idea behind it was to reason if its 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, Ill explain the setup used, the tests performed, and the conclusions reached. iii

  4. 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 1800C and the fission product release was measured. The demonstrated fission product retention at 1600C establishes the basis for the design of small modular HTRs which inherently limit the temperature to 1600C 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 1800C; this occurs at 1600C only with fuels irradiated under conditions which significantly exceed current reactor design requirements.

  5. 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.

    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...... 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...

  6. Performance test of wet type decontamination device

    International Nuclear Information System (INIS)

    The intervention area located at rear hot cell can be contaminated by hot cell maintenance work. For effective decontamination of the intervention floor a wet type decontamination device was developed. The device was assembled with a brush rotating part, a washing liquid supplying part, an intake part for recovering contaminated liquid and a device moving cart part. The device was made of stainless steel for easy decontamination and corrosion resistance. The function test carried out at intervention area of the PIE facility showed good performance

  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. 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...

  9. 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...

  10. 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.

  11. 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

  12. 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.

  13. 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 todays 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.

  14. Singlepath Salmonella. Performance Tested Method 060401.

    Science.gov (United States)

    Lindhardt, Charlotte; Schönenbrücher, Holger; Slaghuis, Jörg; Bubert, Andreas; Ossmer, Rolf

    2009-01-01

    Singlepath Salmonella is an immunochromatographic (lateral flow) assay for the presumptive qualitative detection of Salmonella spp. in food. A previous AOAC Performance Tested Method study evaluated Singlepath Salmonella as an effective method for the detection of Salmonella spp. in the following selected foods: dried skimmed milk, black pepper, dried pet food, desiccated coconut, cooked peeled frozen prawns, raw ground beef, and raw ground turkey. In this Emergency Response Validation extension, creamy peanut butter was inoculated with S. enterica. ser. Typhimurium. For low contamination level (1.08 CFU/25 g), a Chi-square value of 0.5 indicated that there was no significant difference between Singlepath Salmonella and the U.S. Food and Drug Administration's Bacteriological Analytical Manual (FDA-BAM) reference method. For high-level and uninoculated control there was 100% agreement between the methods. PMID:20166612

  15. 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)

  16. 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.

  17. 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)

  18. 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.

  19. 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.

  20. 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.

  1. Automated Performance Tests : Challenges and Opportunities: an Industrial Case Study

    OpenAIRE

    Hagner, Niklas; Carleberg, Sebastian

    2012-01-01

    Automated software testing is often very helpful when performing functionality testing. It makes it possible to have a lot of user actions performed within the application without the need for a human interaction. But would it be possible to extend the behavior of regular functionality testing scripts and use them for performance testing? This way we could have regular application usage testing performed automatically during longer runs as well as investigate how well the application performs...

  2. Technical development of the filter system for dissolver off gas cleanup

    International Nuclear Information System (INIS)

    PASSAT System: All operating data necessary for implementation of the experiments were set with the PASSAT system. The test cycles, which ran continuously over a period of four weeks, proceeded without any incidents. The performance data measured corresponded to the design data, except for the electric output of the trace heating. The overall pressure losses of the system at design data were lower than the differential pressure generated by the blower, which is in accordance with the design. Iodine Filter and Remote Operating Systems: The filters and remote operating systems were mechanically ready for use throughout the experiment. The filter exchanges performed and bagging-out of the spent filter elements together with the attachment of the screw lid of the waste drum (approx. 20 times) proceeded according to expectations and corroborated the correctness of the concept chosen. The required tightness of the iodine filter, which is to be -3 Torr 1/s (external leak and tightness between the filter drum with the filter housing, i.e., on the polluted and clean air sides), was always checked after filter exchanges and during operation. It always corresponded to the level referred to above. (orig./RW)

  3. Results for the DWPF Slurry Mix Evaporator Condensate Tank, Off Gas Condensate Tank, And Recycle Collection Tank Samples

    International Nuclear Information System (INIS)

    The Defense Waste Processing Facility, DWPF, currently generates approximately 1.4 million gallons of recycle water per year during Sludge-Only operations. DWPF has minimized condensate generation to 1.4 million gallons by not operating the Steam Atomized Scrubbers, SASs, for the melter off gas system. By not operating the SASs, DWPF has reduced the total volume by approximately 800,000 gallons of condensate per year. Currently, the recycle stream is sent to back to the Tank Farm and processed through the 2H Evaporator system. To alleviate the load on the 2H Evaporator system, an acid evaporator design is being considered as an alternate processing and/or concentration method for the DWPF recycle stream. In order to support this alternate processing option, the DWPF has requested that the chemical and radionuclide compositions of the Off Gas Condensate Tank, OGCT, Slurry Mix Evaporator Condensate Tank, SMECT, Recycle Collection Tank, RCT, and the Decontamination Waste Treatment Tank, DWTT, be determined as a part of the process development work for the acid evaporator design. Samples have been retrieved from the OGCT, RCT, and SMECT and have been sent to the Savannah River National Laboratory, SRNL for this characterization. The DWTT samples have been recently shipped to SRNL. The results for the DWTT samples will be issued at later date

  4. 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

  5. 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)

  6. Optimization of UA of heat exchangers and BOG compressor exit pressure of LNG boil-off gas reliquefaction system using exergy analysis

    Science.gov (United States)

    Kochunni, Sarun Kumar; Ghosh, Parthasarathi; Chowdhury, Kanchan

    2015-12-01

    Boil-off gas (BOG) generation and its handling are important issues in Liquefied natural gas (LNG) value chain because of economic, environment and safety reasons. Several variants of reliquefaction systems of BOG have been proposed by researchers. Thermodynamic analyses help to configure them and size their components for improving performance. In this paper, exergy analysis of reliquefaction system based on nitrogen-driven reverse Brayton cycle is carried out through simulation using Aspen Hysys 8.6, a process simulator and the effects of heat exchanger size with and without related pressure drop and BOG compressor exit pressure are evaluated. Nondimensionalization of parameters with respect to the BOG load allows one to scale up or down the design. The process heat exchanger (PHX) requires much higher surface area than that of BOG condenser and it helps to reduce the quantity of methane vented out to atmosphere. As pressure drop destroys exergy, optimum UA of PHX decreases for highest system performance if pressure drop is taken into account. Again, for fixed sizes of heat exchangers, as there is a range of discharge pressures of BOG compressor at which the loss of methane in vent minimizes, the designer should consider choosing the pressure at lower value.

  7. 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

  8. I-129, Kr-85, C-14 and NO/sub x/ removal from spent fuel dissolver off-gas at atmospheric pressure and at reduced off-gas flow

    International Nuclear Information System (INIS)

    A dissolver off-gas (DOG) system suitable for a LWR, FBR or HTR spent fuel reprocessing plant is described, incorporating the following features: (1) the DOG flow is reduced to a reasonably small volume, using fumeless dissolution conditions, by maintaining high concentrations, the retention procedures are simplified and accompanied by an economic reduction of the equipment size; (2) all process operations are conducted at atmospheric or subatmospheric pressure, including noble gas removal by selective absorption, without using high temperature processes; (3) all processes, except HEPA filtering, are continuous and do not accumulate large amounts of waste nuclides, the DOG process sequence is mutually compatible with itself and with processing in the headend, showing on-line redundancy for the removal of the most radiotoxic nuclides; and (4) the DOG system only deviates slightly from proven technology. The stage of development and relevant results are given both for a lab. scale and a pilot plant scale

  9. 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

  10. Nuclear material control and accountancy planning and performance testing

    International Nuclear Information System (INIS)

    An overview of performance testing as used at U.S. Department of Energy facilities is provided. Performance tests are performed on specific aspects of the regulations or site policy. The key issues in establishing a performance testing program are: identifying what needs to be tested; determining how to test; establishing criteria to evaluate test results. The program elements of performance testing program consist of: planning; coordination; conduct; evaluation. A performance test may be conducted of personnel or equipment. The DOE orders for nuclear material control and accountancy are divided into three functional areas: program administration, material accounting, and material control. Examples performance tests may be conducted on program administration, accounting, measurement and measurement control, inventory, and containment

  11. 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.

  12. A Literature Survey to Identify Potentially Volatile Iodine-Bearing Species Present in Off-Gas Streams

    Energy Technology Data Exchange (ETDEWEB)

    Bruffey, S. H. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Spencer, B. B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Strachan, D. M. [Strata-G, Knoxville, TN (United States); Jubin, R. T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Soelberg, N. R. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Riley, B. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-06-30

    Four radionuclides have been identified as being sufficiently volatile in the reprocessing of nuclear fuel that their gaseous release needs to be controlled to meet regulatory requirements (Jubin et al. 2011, 2012). These radionuclides are 3H, 14C, 85Kr, and 129I. Of these, 129I has the longest half-life and potentially high biological impact. Accordingly, control of the release of 129I is most critical with respect to the regulations for the release of radioactive material in stack emissions. It is estimated that current EPA regulations (EPA 2010) would require any reprocessing plant in the United States to limit 129I release to less than 0.05 Ci/MTIHM for a typical fuel burnup of 55 gigawatt days per metric tonne (GWd/t) (Jubin 2011). The study of inorganic iodide in off-gas systems has been almost exclusively limited to I2 and the focus of organic iodide studies has been CH3I. In this document, we provide the results of an examination of publically available literature that is relevant to the presence and sources of both inorganic and organic iodine-bearing species in reprocessing plants. We especially focus on those that have the potential to be poorly sequestered with traditional capture methodologies. Based on the results of the literature survey and some limited thermodynamic modeling, the inorganic iodine species hypoiodous acid (HOI) and iodine monochloride (ICl) were identified as potentially low-sorbing iodine species that could present in off-gas systems. Organic species of interest included both short chain alkyl iodides such as methyl iodide (CH3I) and longer alkyl iodides up to iodododecane (C10H21I). It was found that fuel dissolution may provide conditions conducive to HOI formation and has been shown to result in volatile long-chain alkyl iodides, though these may not volatilize until later in the reprocessing sequence. Solvent extraction processes were found to be significant sources of various organic iodine-bearing species; formation of these was facilitated by the presence of radiolytic decomposition products resulting from radiolysis of tri-n-butyl phosphate and dodecane. Primarily inorganic iodine compounds were expected from waste management processes, including chlorinated species such as ICl. Critical knowledge gaps that must still be addressed include confirmation of the existence and quantification of low-sorbing species in the off-gas of reprocessing facilities. The contributions from penetrating forms of iodine to the plant DF are largely unknown and highly dependent on the magnitude of their presence. These species are likely to be more difficult to remove and it is likely that their sequestration could be improved through the use of different sorbents, through design modifications of the off-gas capture system, or through chemical conversion prior to iodine abatement that would produce more easily captured forms.

  13. 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.

  14. 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

  15. Using educational analytics to improve test performance

    OpenAIRE

    Corrigan, Owen; Alan F. SMEATON; Glynn, Mark; Smyth, Sinead

    2015-01-01

    Learning analytics are being used in many educational applications in order to help students and Faculty. In our work we use predictive analytics, using student behaviour to predict the likely performance of end of semester final grades with a system we call PredictED. The main contribution of our approach is that our intervention automatically emailed students on a regular basis, with our prediction for the outcome of their exam performance. We targeted first year, first semester University ...

  16. Comparison of performance test for protective aprons

    International Nuclear Information System (INIS)

    Each one radioprotective apron (lead equivalent, 0.35 mmPb) was commercially available in November 1988 from 7 domestic and 3 foreign companies. According to the JIS standards 4803, these aprons were evaluated for the following items: 1) display of aprons, including packing and the structure; 2) non-breaking test, including appearance, size, lead equivalent, and uniformity; 3) breaking test, including lead equivalent, uniformity, stregth, and structure; 4) feeling of wearing an apron. An overall evaluation revealed that only two aprons were in accordance with the JIS standard. Careful wearing of the protective apron is stressed. (N.K.)

  17. 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.

  18. 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.

  19. 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....

  20. 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.

  1. 42 CFR 84.103 - Man tests; performance requirements.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 1 2010-10-01 2010-10-01 false Man tests; performance requirements. 84.103 Section...-Contained Breathing Apparatus 84.103 Man tests; performance requirements. (a) The apparatus shall satisfy... is 24 6 C. (75 10 F.), the maximum temperature of inspired air recorded during man tests...

  2. SBWR thermal hydraulic performance analysis and testing

    International Nuclear Information System (INIS)

    The design for the Simplified Boiling Water Reactor (SBWR) nuclear plant represents a complete conceptual design for a 600 MWe power plant. This paper provides a description of the SBWR passive safety design features and the thermal hydraulic analysis/testing to support them. The SBWR is a plant that is significantly simpler to build, operate and maintain compared to currently available designs. The reason for this simplification is inherent in some of the key features - elimination of the forced recirculation system, use of passive safety features and use of a direct cycle system. The use of passive safety systems has resulted in the elimination of all safety-grade pumps and diesel generators and has enabled significant simplification of the plant design

  3. Reliability performance testing of totally encapsulating chemical protective suits

    International Nuclear Information System (INIS)

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

  4. Stack-Test Work Package 2: Functional and performance testing on PEMFC stacks

    OpenAIRE

    Mitzel, Jens; Glzow, Erich

    2014-01-01

    The EU-funded research project Stack-Test has developed different test procedures for the functional and performance characterization of PEMFC stacks. The test procedures are based on test modules related to the variation of one test input parameter and the determination of the influence on the stack performance. These test modules are suitable for all stack applications and have a general nature. The procedure for parameter variation, the critical parameters and the test parameters of intere...

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

    International Nuclear Information System (INIS)

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

  6. 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.

  7. Fatigue Effects on Intelligence Test Performance in the Elderly

    Science.gov (United States)

    Cunningham, Walter R.; And Others

    1978-01-01

    The purpose was to investigate effects of fatigue on intelligence test performance in the elderly. Fatigue effects were investigated by varying number of previous tests, by introducing breaks, and by using a pre-test fatigue-producing condition. The elderly are not as susceptible to test fatigue as previous results suggested. (Author)

  8. 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

  9. 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

  10. 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.

  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

    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.

  12. Predicting the performance of batsmen in test cricket

    OpenAIRE

    Wickramasinghe, Indika Pradeep

    2014-01-01

    Cricket is one of the team games played over 50 countries in different levels. Though the performance of each batsman in the team can be easily quantified, the prediction of player performance is arduous. This paper demonstrates a methodology to predict the performance of cricket batsman in test-match series. In this study, longitudinal test cricket data have been collected over five years of period. A model is developed to predict the player performance as a function of certain characteristi...

  13. 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...

  14. 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

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

    Science.gov (United States)

    Frutos, Osvaldo D; Arvelo, Ilan A; Prez, Rebeca; Quijano, Guillermo; Muoz, Ral

    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

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

    Science.gov (United States)

    Estrada, Jos M; Quijano, Guillermo; Lebrero, Raquel; Muoz, Ral

    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. 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)

  18. 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 Energys 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 HEVs 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.

  19. 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.

  20. NO/sub x/ removal from nuclear fuel reprocessing plants off gas by catalytic reduction with NH3

    International Nuclear Information System (INIS)

    The selective reduction of NO/sub x/ with NH3 was investigated, using several kinds of titania catalysts and hydrogen mordenite (Hz, zeolite catalyst), as a basic study of the treatment of off gas generated in nuclear reprocessing plants, which was supposed to contain about 30% of O2 and a relatively large amount of NO2. N2O was remarkably formed regardless of the types of catalysts when the NO2/NO/sub x/ ratio was higher than 0.5. On the other hand, N2O was hardly formed when Hz and certain kinds of titania catalysts were used at NO2/NO/sub x/ ratios below 0.5. It has been concluded that these kinds of catalysts were suitable and that the NO/sub x/ should be decomposed according to the following reaction: NO + NO2 + 2NH3 ? 2N2 + 3H2O. Therefore, it is effective to decompose NO2 thermally to NO in the first step, to depress the formation of N2O when the NO2/NO/sub x/ ratio of the gas to be treated is higher than 0.5. Hz has catalytic abilities not only to reduce N2O with NH3 but also to decompose NH3, which means that a one reaction system of NO/sub x/ removal can be carried out for NO2 rich gases

  1. 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

  2. 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,...

  3. 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.

  4. 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...

  5. 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.

  6. 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)

  7. 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

  8. 40 CFR 60.444 - Performance test procedures.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 6 2010-07-01 2010-07-01 false Performance test procedures. 60.444 Section 60.444 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS... Sensitive Tape and Label Surface Coating Operations 60.444 Performance test procedures. (a)...

  9. 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.

  10. 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

  11. Tracking system performance tests in the MDS era

    Science.gov (United States)

    Buckles, B. J.

    1977-01-01

    Tracking system performance tests as developed to support DSN Mark III Data Subsystem implementation project and prepass readiness tests are described. The system test design, the rationale chosen for implementation, and the inevitable compromises imposed by schedule constraints and reserves are discussed.

  12. 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)

  13. 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

  14. Halogen occultation experiment (HALOE) performance verification test procedure

    Science.gov (United States)

    Mauldin, L. E., III

    1986-01-01

    The Performance Verification Test Procedure is given for the Halogen Occultation Experiment (HALOE) instrument, which is being developed in house at the Langley Research Center for the Upper Atmosphere Research Satellite (UARS). This procedure is used for comprehensive performance testing of the HALOE instrument which occurs before, during, and after flight environmental tests. The radiometric performance tests include noise, drift, linearity, instantaneous field-of-view, cal wheel gas cell characterization, and self thermal emissions. Pointer/tracker performance tests include sun sensor performance, gimbal performance, control system performance, and boresight alignment. In addition, the instrument is tested functionally in simulated orbit sequences and all command operating modes are exercised. The data analysis required for each test is specified and pass/fail criteria are given where applicable. This test will fully demonstrate the HALOE instrument's ability to achieve science mission requirements. The HALOE instrument is a gas correlation radiometer that measures vertical distribution of eight upper atmospheric constituents: O3, HCl, HF, NO, CH4, H2O, NO2, and CO2.

  15. 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)

  16. Verification test of an engineering-scale multi-purpose radwaste incinerator

    International Nuclear Information System (INIS)

    The verification test of an engineering-scale multi-purpose radwaste incinerator was implemented. The test items include performance determination for the system when solid wastes (include resins) or spent oil were incinerating and off gas was cleaning, tracer test for determining decontamination factor and 72 h continuos running test. 500 h tests verify the reliability and feasibility of designs of technological process, main structure, instrument control and system safety. The incineration system ran smoothly, devices and instruments worked stably. The specifications such as capacity, volume reduction factor, carbon remainder in ash and decontamination factor all meet the design requirements

  17. Performance Analysis of Saturated Induction Motors by Virtual Tests

    Science.gov (United States)

    Ojaghi, M.; Faiz, J.; Kazemi, M.; Rezaei, M.

    2012-01-01

    Many undergraduate-level electrical machines textbooks give detailed treatments of the performance of induction motors. Students can deepen this understanding of motor performance by performing the appropriate practical work in laboratories or in simulation using proper software packages. This paper considers various common and less-common tests

  18. 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.)

  19. 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

  20. 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)

  1. 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

  2. Relative Utility of Performance and Symptom Validity Tests.

    Science.gov (United States)

    Copeland, Christopher T; Mahoney, James J; Block, Cady K; Linck, John F; Pastorek, Nicholas J; Miller, Brian I; Romesser, Jennifer M; Sim, Anita H

    2016-02-01

    This investigation adds to the burgeoning body of research concerned with discriminating performance and symptom validity tests (SVTs) through examination of their differential relationships with cognitive performance and symptom self-report measures. To the authors' current knowledge, prior studies have not assessed differences between participants who fail either a performance validity test (PVT) or an SVT but not both. As part of their neuropsychological evaluations at four Veterans Affairs medical centers across the United States, participants were administered a fixed, standardized battery that consisted of performance validity, symptom validity, cognitive performance, and symptom self-report measures. Compared with participants who failed a PVT and an SVT, participants who passed both and participants who only passed a PVT demonstrated better cognitive performance and self-reported fewer symptoms. Results support differential clinical utility of performance validity and SVTs when assessing cognitive performance and symptom self-report. PMID:26537776

  3. 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)

  4. 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)

  5. 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.

  6. Performance Testing Methodology for Safety-Critical Programmable Logic Controller

    International Nuclear Information System (INIS)

    The Programmable Logic Controller (PLC) for use in Nuclear Power Plant safety-related applications is being developed and tested first time in Korea. This safety-related PLC is being developed with requirements of regulatory guideline and industry standards for safety system. To test that the quality of the developed PLC is sufficient to be used in safety critical system, document review and various product testings were performed over the development documents for S/W, H/W, and V/V. This paper provides the performance testing methodology and its effectiveness for PLC platform conducted by KOPEC

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

    Energy Technology Data Exchange (ETDEWEB)

    MacLellan, J.A.; Traub, R.J.

    1988-11-01

    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.

  8. 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

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

    Directory of Open Access Journals (Sweden)

    Minoo Alemi

    2010-09-01

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

  10. Performance test report of improved 'HEPA filter unit'

    International Nuclear Information System (INIS)

    The performance of JAERI-Type Filter Housing Model-ISE was tested for the purpose of finding out posibility to reduce the construction cost and to minimize the installation space of filter housings in exhaust machinary room which occupy the large amount of space in the nuclear power facilities, etc. And also, Model-ISE filter housing, featured different internal construction from that of conventional type, was expected to be proved by the test to have improved performance compared to the conventional type filter housings. The performance test was executed to compare performance of prototype of Model-ISE filter to that of the conventional one on the following items, resulting that Model-ISE filter was proved to have no inferior performance to the performance of conventional type filter. 1) Resistance to Air Flow. 2) Air Velocity Test. 3) Air Flow Distribution Test. 4) Efficiency for Submicron Particles. 5) Synthetic Dust Clogging. By the above test, Model-ISE filter was proved to have many advantage c.f. less installation space (approx. 10 ? 30 % less), and lower filter height (approx. 10 ? 15 % lower) than those of conventional type without performance reduction. (author)

  11. 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...

  12. 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

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

    Directory of Open Access Journals (Sweden)

    Adrian Cuzmo?

    2008-10-01

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

  14. 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)

  15. 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

  16. Predicting road test performance in drivers with stroke.

    Science.gov (United States)

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

    2014-01-01

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

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

    International Nuclear Information System (INIS)

    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

  18. Primer Stepper Motor Nomenclature, Definition, Performance and Recommended Test Methods

    Science.gov (United States)

    Starin, Scott; Shea, Cutter

    2014-01-01

    There has been an unfortunate lack of standardization of the terms and components of stepper motor performance, requirements definition, application of torque margin and implementation of test methods. This paper will address these inconsistencies and discuss in detail the implications of performance parameters, affects of load inertia, control electronics, operational resonances and recommended test methods. Additionally, this paper will recommend parameters for defining and specifying stepper motor actuators. A useful description of terms as well as consolidated equations and recommended requirements is included.

  19. 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.

  20. 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.

  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. 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 Energys 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.

  3. 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

  4. 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)

  5. 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.

  6. 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...

  7. 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.

  8. 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

  9. 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; Jrgensen, Kasper

    2013-01-01

    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...

  10. 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.

  11. 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...

  12. 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

  13. What Predicts Changes in Useful Field of View Test Performance?

    OpenAIRE

    Lunsman, Melissa; Edwards, Jerri D.; Andel, Ross; Small, Brent J; Ball, Karlene K.; Roenker, Daniel L.

    2008-01-01

    The Useful Field of View Test (UFOV1) has been used to examine age-related changes in visual processing and cognition and as an indicator of everyday performance outcomes, particularly driving, for over 20 years. How UFOV performance changes with age and what may impact such changes have not previously been investigated longitudinally. Predictors of change in UFOV performance over a five-year period among control-group participants (n = 690) from the Advanced Cognitive Training for Independen...

  14. Performance testing of dosimetry services and its regulatory aspects

    International Nuclear Information System (INIS)

    An essential part of a quality assurance programme is performance testing of the dosimetry service. i.e. the verification of the procedures applied by the dosimetry service, by introducing control samples into the routine. This paper concentrates on performance testing based on so-called trumpet curves derived from recommendations of ICRP Publication 35. But, as experience shows, the state-of-the-art in dosimetry must also be taken into account. Photon radiation above 20 keV is relatively easy to measure and these trumpet curves may be used for this. For neutron radiation, for example, additional wider trumpet curves are recommended. The dosimetry service should not be aware of the tests, i.e. 'blind'-performance testing should be carried out. This leads to some difficulties in practice, and as an alternative, performance testing 'by surprise' is described. Results of performance testing from Germany, Russia and the USA are presented and indicate that the proposed concept is feasible. (Author)

  15. 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.

  16. Performance testing of the Doorstopper biaxial strain cell

    Energy Technology Data Exchange (ETDEWEB)

    Stickney, R.G.; Senseny, P.E.; Hansen, F.D. (RE/SPEC, Inc., Rapid City, SD (USA))

    1983-11-01

    A laboratory testing program was conducted to evaluate the performance of the Council for Scientific and Industrial Research (CSIR) Doorstopper'' biaxial strain cell. This work was conducted in support of the Basalt Waste Isolation Project's in situ stress measurement program to be carried out within the reference repository horizon. Performance tests were designed to (1) select an adhesive suitable for installation of the Doorstopper, (2) evaluate the component parts of the Doorstopper, and (3) test the performance of the Doorstopper and selected adhesive. Test conditions were selected to simulate those expected at the reference repository horizon during overcoring (temperatures ranging from 40{degree}C to 65{degree}C with a humidity of up to 100 percent). 10 refs.

  17. Testing the abstractions used in total system performance assessments

    International Nuclear Information System (INIS)

    Multiple levels of complexity and detail are involved in the performance assessment models used in the Yucca Mountain project (YMP). Included are the detailed process-level models, and various higher level abstractions or idealizations of those process models, that may be used in the simpler total system simulators for performance assessments. Abstractions are applied to reduce the complex process models to simpler overall simulators for more direct total system analyses. Although seldom done in the past, the abstractions require appropriate testing to demonstrate that each is an appropriate simpler system representation. To be adequate, such testing must either: (1) Demonstrate that essential processes, conceptual representations, and the parameter variations in the original process-level models are neither lost nor the performance results unduly altered by applying the abstractions, or (2) Show that any significance lost is appropriately bounded by the abstraction assumptions and that subsequent assessments using such bounding assumptions still provide appropriate margins of safety in the overall repository performance. Failure to satisfy one of the above conditions requires changing the abstraction being test until it, in fact, verifies the representation is adequate. Such testing provides the foundation necessary for technically defensible performance assessments using the abstracted total system models. The objective of this paper is to outline an approach for testing any proposed or specific future abstractions of the process-level models used to obtain simpler system simulators for application in total system performance assessments (TSPAs)

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

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Min Kyu; Kim, Jung-Han; Choi, In-Kil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    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.

  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. Methodologies for the performance demonstration of nondestructive testing systems

    International Nuclear Information System (INIS)

    The importance of nondestructive testings have been well recognized through a number of big accidents such as the collapses of buildings and bridges in recent years. A nondestructive test to be performed should be fitted to its purpose. In order to assess the nondestructive testing systems whether they are capable of attaining their objectives, performance demonstration is carried out in addition to the existing personnel qualification and certification scheme. However, there are a lot of different ways how the performance demonstration is implemented depending not only on the safety relevance of the component but also on the significance of the defects. At present time, there are two distinct methodologies. One is the American approach and the other is the European approach. In this paper, typical methodologies on the performance demonstration of NDT systems are reviewed and compared. Hence, when a PD system is to be established, a better way can be employed.

  1. Automatic test stand for compressor performance; Automatischer Verdichterleistungspruefstand

    Energy Technology Data Exchange (ETDEWEB)

    Hempel, O.; Tzscheutschler, A.; Kinne, L.; Wobst, E. [Institut fuer Luft- und Kaeltetechnik gGmbH, Dresden (Germany)

    2005-07-01

    A new test stand for measuring the performance of refrigerant compressors according to the harmonised Norm EN 13771-1 has been set-up and tested at the Institute for Air and Refrigeration Technology. The refrigerating capacity range reaches from approx. 12 to 120 kW for the refrigerants R134a, R404A, R407C and R410A. The parameters of the compressor are measured automatically and a test report is prepared accordingly. The test stand was especially designed for higher operating pressures of the refrigerant R410A. After a test phase with comparative measurements of other test stands, further measurements are planned in the frame of compressor certification of the ASERCOM. The new norm EN 13771-1 puts higher demands on the measure and control exactness. Therefore single components of the test stand will also be checked regarding their application suitability for future projects. (orig.)

  2. 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

  3. 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

  4. 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

  5. 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.

  6. 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

  7. Evaluating Maintenance Performance: Test Administrator's Manual and Test Subject's Instructions for Criterion Referenced Job Task Performance Tests for Electronic Maintenance. Final Report.

    Science.gov (United States)

    Shriver, Edgar L.; And Others

    This document furnishes a complete copy of the Test Subject's Instructions and the Test Administrator's Handbook for a battery of criterion referenced Job Task Performance Tests (JTPT) for electronic maintenance. General information is provided on soldering, Radar Set AN/APN-147(v), Radar Set Special Equipment, Radar Set Bench Test Set-Up, and

  8. Performance testing of radiobioassay laboratories: In vivo measurements, Final Report

    Energy Technology Data Exchange (ETDEWEB)

    MacLellan, J.A.; Traub, R.J.; Olsen, P.C.

    1990-04-01

    A study of two rounds of in vivo laboratory performance testing was undertaken by Pacific Northwest Laboratory (PNL) to determine the appropriateness of the in vivo performance criteria of draft American National Standards Institute (ANSI) standard ANSI N13.3, Performance Criteria for Bioassay.'' The draft standard provides guidance to in vivo counting facilities regarding the sensitivity, precision, and accuracy of measurements for certain categories of commonly assayed radionuclides and critical regions of the body. This report concludes the testing program by presenting the results of the Round Two testing. Testing involved two types of measurements: chest counting for radionuclide detection in the lung, and whole body counting for detection of uniformly distributed material. Each type of measurement was further divided into radionuclide categories as defined in the draft standard. The appropriateness of the draft standard criteria by measuring a laboratory's ability to attain them were judged by the results of both round One and Round Two testing. The testing determined that performance criteria are set at attainable levels, and the majority of in vivo monitoring facilities passed the criteria when complete results were submitted. 18 refs., 18 figs., 15 tabs.

  9. Fast Flux Test Facility core restraint system performance

    International Nuclear Information System (INIS)

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

  10. Relationships Between Anaerobic Performance, Field Tests and Game Performance of Sitting Volleyball Players

    Directory of Open Access Journals (Sweden)

    Marszalek Jolanta

    2015-12-01

    Full Text Available The aim of this study was to evaluate relationships between anaerobic performance, field tests, game performance and anthropometric variables of sitting volleyball players. Twenty elite Polish sitting volleyball players were tested using the 30 s Wingate Anaerobic Test for arm crank ergometer and participated in six physical field tests. Heights in position to block and to spike, as well as arm reach were measured. Players were observed during the game on the court in terms of effectiveness of the serve, block, attack, receive and defense. Pearson analysis and the Spearman's rank correlation coefficient were used. The strongest correlations were found between the chest pass test and mean power and peak power (r=.846; p=.001 and r=.708; p=.0005, respectively, and also between the T-test and peak power (r= ?.718; p=.001. Mean power correlated with the 3 m test (r= ?.540; p=.014, the 5 m test (r= ?.592; p=.006, and the T-test (r= ?.582; p=.007. Peak power correlated with the 3 m test (r= ?.632; p=.003, the 5 m test (r= ?.613; p=.004, speed & agility (r= ?.552; p=.012 and speed & endurance (r=?.546; p=.013. Significant correlations were observed between anthropometric parameters and anaerobic performance variables (p?.001, and also between anthropometric parameters and field tests (p?.05. Game performance and physical fitness of sitting volleyball players depended on their anthropometric variables: reach of arms, the position to block and to spike. The chest pass test could be used as a non-laboratory field test of anaerobic performance of sitting volleyball players.

  11. 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

  12. 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

  13. 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...

  14. Performance testing of multi-metal continuous emissions monitors

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-11-17

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

  15. 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)

  16. Impact of peer interaction on conceptual test performance

    OpenAIRE

    Singh, Chandralekha

    2016-01-01

    We analyze the effectiveness of working in pairs on the Conceptual Survey of Electricity and Magnetism test in a calculus-based introductory physics course. Students who collaborated with a peer showed significantly larger normalized gain on individual testing than those who did not collaborate. We did not find statistically significant differences between the performance of students who were given an opportunity to formulate their own response before the peer discussions, compared to those w...

  17. 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...

  18. 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...

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

    International Nuclear Information System (INIS)

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

  20. 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.

  1. 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)

  2. Solar domestic water heating performance test program: interim report

    Energy Technology Data Exchange (ETDEWEB)

    Auris, R.H.; Draving, W.J.

    1981-01-01

    Several solar domestic water heating systems were installed and tested to evaluate the performance characteristics and cost effectiveness of the commercially available equipment, evaluate the distributor's/contractor's readiness and expertise in the design and installation of effective solar-thermal systems, and to determine the maintenance requirements of solar domestic water heating systems and their associated costs. The systems' thermal performance and reliability are evaluated and cost effectiveness and market potential are determined. The instrumentation used in the test is briefly described. (LEW)

  3. 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)

  4. 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.

  5. 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.

  6. 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%.

  7. 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

  8. 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

  9. Verification Test of Hydraulic Performance for Reactor Coolant Pump

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-01-15

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

  10. 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...

  11. Testing of reinforced high performance fibre concrete members in tension

    OpenAIRE

    Redaelli, Dario

    2006-01-01

    Ultra-high performance fibre reinforced concrete (UHPFC) is a high performance construction material, coupling strength, ductility and compacity. Up to the present time, its mechanical properties have been widely studied, but design approaches and structural applications in which it can be efficiently applied are needed. To improve this knowledge, a study on the behaviour of real-scale UHPFC ties with additional ordinary steel bars constitues an important step. The results of a test series pr...

  12. Predictive testing of performance of metals in HTR service environments

    International Nuclear Information System (INIS)

    Status of the material testing in simulated HTGR environment is reviewed with special attention focused on the methodology of the prediction of performance in long time. Importance of controlling effective chemical potentials relations in the material-environmental interface is stressed in regard of the complex inter-dependent kinetic relation between oxidation and carbon transport. Based on the recent experimental observations, proposals are made to establish some procedures for conservative prediction of the metal performance

  13. Anaerobic performance testing of professional soccer players 1995-2010

    OpenAIRE

    Haugen, Thomas A; Tnnessen, Espen; Seiler, Stephen

    2013-01-01

    Purpose: To compare sprint and countermovement-jump (CMJ) performance among competitive soccer players as a function of performance level, field position, and age. In addition, the authors wanted to quantify the evolution of these physical characteristics among professional players over a 15-y period. Methods: 939 athletes (22.1 +/- 4.3 y), including national-team players, tested 40-m sprint with electronic timing and CMJ on a force platform at the Norwegian Olympic Training Center between 19...

  14. Testing of Companies Financial Performance in the BIST - Tourism Sector

    Directory of Open Access Journals (Sweden)

    Nuray ERGL

    2014-06-01

    Full Text Available Financial performance of companies in the Istanbul Stock Exchange (BIST- Tourism sector are tested comparatively by using ELECTRE and TOPSIS methods. As a result of the study; both methods which provides the decision-making process have been determined to be successful methods to give an decision about the highest financial performance company in the BIST-Tourism Industry. In this study, BIST-Tourism Companies financial statements in the period of 2005 - 2012 are being used.

  15. 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

  16. Stereotype threat? Effects of inquiring about test takers' gender on conceptual test performance in physics

    CERN Document Server

    Maries, Alexandru

    2016-01-01

    It has been found that activation of a stereotype, for example by indicating one's gender before a test, typically alters performance in a way consistent with the stereotype, an effect called "stereotype threat". On a standardized conceptual physics assessment, we found that asking test takers to indicate their gender right before taking the test did not deteriorate performance compared to an equivalent group who did not provide gender information. Although a statistically significant gender gap was present on the standardized test whether or not students indicated their gender, no gender gap was observed on the multiple-choice final exam students took, which included both quantitative and conceptual questions on similar topics.

  17. Stereotype threat? Effects of inquiring about test takers' gender on conceptual test performance in physics

    Science.gov (United States)

    Maries, Alexandru; Singh, Chandralekha

    2015-12-01

    It has been found that activation of a stereotype, for example by indicating one's gender before a test, typically alters performance in a way consistent with the stereotype, an effect called "stereotype threat." On a standardized conceptual physics assessment, we found that asking test takers to indicate their gender right before taking the test did not deteriorate performance compared to an equivalent group who did not provide gender information. Although a statistically significant gender gap was present on the standardized test whether or not students indicated their gender, no gender gap was observed on the multiple-choice final exam students took, which included both quantitative and conceptual questions on similar topics.

  18. Performance test of solar-assisted ejector cooling system

    KAUST Repository

    Huang, Bin-Juine

    2014-03-01

    A solar-assisted ejector cooling/heating system (SACH-2k) is built and test result is reported. The solar-driven ejector cooling system (ECS) is connected in series with an inverter-type air conditioner (IAC). Several advanced technologies are developed in SACH-k2, including generator liquid level control in ECS, the ECS evaporator temperature control, and optimal control of fan power in cooling tower of ECS. From the field test results, the generator liquid level control performs quite well and keeps stable performance of ejector. The ECS evaporator temperature control also performs satisfactorily to keep ejector performance normally under low or fluctuating solar radiation. The fan power control system cooling tower performs stably and reduces the power consumption dramatically without affecting the ECS performance. The test results show that the overall system COPo including power consumptions of peripheral increases from 2.94-3.3 (IAC alone) to 4.06-4.5 (SACH-k2), about 33-43%. The highest COPo is 4.5. © 2013 Elsevier Ltd and IIR. All rights reserved.

  19. Performance testing of West Valley Reference 6 glass

    International Nuclear Information System (INIS)

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

  20. 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)

  1. Numerical analysis on letdown system performance test for YGN 3

    International Nuclear Information System (INIS)

    Integrated performance test of Chemical and Volume control System was successfully performed in 1994. However, an extensive effort to correct hardware and software problems in the letdown line was required mainly due to the lack of adequate simulation code to predict the test accurately. Although the LTC computer code was used during the YGN 3 and 4 NSSS design process, the code can not satisfactorily predict the test due to its insufficient letdown line modeling. This study developed a numerical model to simulate the letdown test by modifying the current LTC code, and then verified the model by comparing with the test data. The comparison shows that the modified LTC computer code can predict the transient behavior of letdown system tests very well. Especially, the model was verified to be able to predict the instantaneous fluctuations in the letdown backpressure and flowrate which are caused by the 'Stiction (composition of stick and friction)' of valve. Therefore, it is concluded that the modified LTC computer code with the ability of calculating the 'Stiction' phenomena will be very useful for future plant design and test predictions. 1 tab., 11 figs., 7 refs. (Author)

  2. 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.

  3. Performance on the Pharmacy College Admission Test: An Exploratory Analysis.

    Science.gov (United States)

    Kawahara, Nancy E.; Ethington, Corinna

    1994-01-01

    Median polishing, an exploratory data statistical analysis technique, was used to study achievement patterns for men and women on the Pharmacy College Admission Test over a six-year period. In general, a declining trend in scores was found, and males performed better than females, with the largest differences found in chemistry and biology.

  4. 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... ratenon-automated; (6) Hemoglobincopper sulfatenon-automated; (7) Blood glucose by...

  5. Predicting Performance on a Firefighter's Ability Test from Fitness Parameters

    Science.gov (United States)

    Michaelides, Marcos A.; Parpa, Koulla M.; Thompson, Jerald; Brown, Barry

    2008-01-01

    The purpose of this project was to identify the relationships between various fitness parameters such as upper body muscular endurance, upper and lower body strength, flexibility, body composition and performance on an ability test (AT) that included simulated firefighting tasks. A second intent was to create a regression model that would predict…

  6. 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

  7. 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.

  8. 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

  9. Honeywell Cascade Distiller System Performance Testing Interim Results

    Science.gov (United States)

    Callahan, Michael R.; Sargusingh, Miriam

    2014-01-01

    The ability to recover and purify water through physiochemical processes is crucial for realizing long-term human space missions, including both planetary habitation and space travel. Because of their robust nature, distillation systems have been actively pursued as one of the technologies for water recovery. The Cascade Distillation System (CDS) is a vacuum rotary distillation system with potential for greater reliability and lower energy costs than existing distillation systems. The CDS was previously under development through Honeywell and NASA. In 2009, an assessment was performed to collect data to support down-selection and development of a primary distillation technology for application in a lunar outpost water recovery system. Based on the results of this testing, an expert panel concluded that the CDS showed adequate development maturity, TRL-4, together with the best product water quality and competitive weight and power estimates to warrant further development. The Advanced Exploration Systems (AES) Water Recovery Project (WRP) worked to address weaknesses identified by The Panel; namely bearing design and heat pump power efficiency. Testing at the NASA-JSC Advanced Exploration System Water Laboratory (AES Water Lab) using a prototype Cascade Distillation Subsystem (CDS) wastewater processor (Honeywell International, Torrance, Calif.) with test support equipment and control system developed by Johnson Space Center was performed to evaluate performance of the system with the upgrades. The CDS will also have been challenged with ISS analog waste streams and a subset of those being considered for Exploration architectures. This paper details interim results of the AES WRP CDS performance testing.

  10. WhalePower tubercle blade power performance test report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-15

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

  11. Fluid flow measurements of Test Series A and B for the Small Scale Seal Performance Tests

    International Nuclear Information System (INIS)

    The degree of waste isolation achieved by a repository seal system is dependent upon the fluid flow characteristics, or permeability, of the seals. In order to obtain meaningful, site-specific data on the performance of various possible seal system components, a series of in situ experiments called the Small Scale Seal Performance Tests (SSSPT) are being conducted at the Waste Isolation Pilot Plant (WIPP). This report contains the results of gas flow, tracer penetration, and brine flow tests conducted on concrete seals in vertical (Test Series A) and horizontal (Test Series B) configurations. The test objectives were to evaluate the seal performance and to determine if there existed scaling effects which could influence future SSSPT designs. 3 refs., 77 figs

  12. 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.

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

    International Nuclear Information System (INIS)

    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.)

  14. 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,

  15. 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)

  16. 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

  17. 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.

  18. Clock Face Drawing Test Performance in Children with ADHD

    Science.gov (United States)

    Ghanizadeh, Ahmad; Safavi, Salar; Berk, Michael

    2013-01-01

    Introduction The utility and discriminatory pattern of the clock face drawing test in ADHD is unclear. This study therefore compared Clock Face Drawing test performance in children with ADHD and controls. Methods 95 school children with ADHD and 191 other children were matched for gender ratio and age. ADHD symptoms severities were assessed using DSM-IV ADHD checklist and their intellectual functioning was assessed. The participants completed three clock-drawing tasks, and the following four functions were assessed: Contour score, Numbers score, Hands setting score, and Center score. Results All the subscales scores of the three clock drawing tests of the ADHD group were lower than that of the control group. In ADHD children, inattention and hyperactivity/ impulsivity scores were not related to free drawn clock test scores. When pre-drawn contour test was performed, inattentiveness score was statistically associated with Number score while none of the other variables of age, gender, intellectual functioning, and hand use preference were associated with that kind of score. In pre-drawn clock, no association of ADHD symptoms with any CDT subscales found significant. In addition, more errors are observed with free drawn clock and Pre-drawn contour than pre-drawn clock. Discussion Putting Numbers and Hands setting are more sensitive measures to screen ADHD than Contour and Center drawing. Test performance, except Hands setting, may have already reached a developmental plateau. It is probable that Hand setting deficit in children with ADHD may not decrease from age 8 to 14 years. Performance of children with ADHD is associated with complexity of CDT. PMID:25337328

  19. Investigation of a Concept for Simultaneous Reliquefaction of Boil-Off-Gas and Vaporization of LNG for Marine Atmospheric LNG Fuel Tanks

    OpenAIRE

    Battistelli, Arrigo

    2014-01-01

    The aim of this thesis is to design and optimize a heat pump process to reliquefy Boil-Off-Gas from Liquefied Natural Gas (LNG) cryogenic tanks, and simulataneously vaporize LNG at high pressure.The process is meant for use onboard LNG fuelled ship different from LNG carriers, equipped with LNG fuel tanks at atmospheric pressure and 2-strokes engines with high pressure gas injection, which is considered the most efficient propulsion arrangement for medium-large vessels.The studyis based on a ...

  20. Forward lunge as a functional performance test in ACL deficient subjects: test-retest reliability

    DEFF Research Database (Denmark)

    Alkjaer, Tine; Henriksen, Marius; Dyhre-Poulsen, Poul; Simonsen, Erik B

    2009-01-01

    The forward lunge movement may be used as a functional performance test of anterior cruciate ligament (ACL) deficient and reconstructed subjects. The purposes were 1) to determine the test-retest reliability of a forward lunge in healthy subjects and 2) to determine the required numbers of...

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

    Directory of Open Access Journals (Sweden)

    Juan A. Moreno

    2010-03-01

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

  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. 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.

  4. Performance of Scandinavian BWR-containments during pressure tests

    International Nuclear Information System (INIS)

    Seven prestressed concrete containment vessels for ASEA-ATOM's BWR-reactors have been constructed in Sweden during the last ten years and two similar vessels have been built in Finland. Each vessels has been subjected to the usual properational pressure tests in order to demonstrate its structural integrity and leaktightness and some of the structures have also been retested in compliance with the usual demands for periodic testing. Observations from the tests in the form of measured strains and deformations, leakage-rates, etc. constitute a valuable piece of experience and a basis for comparison with the result of theoretical analyses, making it possible to improve future calculations and predictions. Therefore the most important observation data from performed tests have been summarized and compared with predictions based on theoretical calculations, etc. (orig.)

  5. Performance test of a ceramic turbo-viscous pump

    International Nuclear Information System (INIS)

    In the special fields of nuclear fusion facilities and semiconductor production installation, the development of new vacuum pumps which can cope with strong magnetic fields, high temperature gas and corrosive gas is demanded. Mitsubishi Heavy Industries Ltd. has advanced the development of ceramic turbo-molecular pumps and ceramic turbo-viscous pumps, which use ceramic rotors and gas bearings since 1985. The evaluation test of the ceramic turbo-viscous vacuum pump CT-3000H which can evacuate from atmospheric pressure to high vacuum with one pump was carried out, and the experimental results on the performance and the reliability were obtained, therefore, those are reported in this paper. The structure, specification and features of the CT-3000H are shown. The exhaust performance test of the pump was carried out in conformity with the standard of the Vacuum Society of Japan, JVIS 005 'Method of performance test for turbo-molecular pumps'. The gases used were nitrogen and helium. The results are shown. The exhaust test from atmospheric pressure was carried out by two methods, and the results are shown. (K.I.)

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

    Directory of Open Access Journals (Sweden)

    Özkan Işık

    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. 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

  9. 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 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.

  10. 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.

  11. Test objects for evaluating the performance of radiological imaging systems. Leeds radiological test objects

    International Nuclear Information System (INIS)

    A range of test objects has been developed to assess the imaging performance of conventional and digital radiological imaging systems. These test objects have arisen as a result of involvement in both the laboratory evaluation of radiological imaging systems and the routine maintenance of such equipment in a large diagnostic radiology department. The philosophy behind the design and application of the test objects is briefly described. Particular attention is paid to the advantages of using the threshold-contrast detail-detectability technique to assess overall imaging performance. The great importance of ensuring optimum imaging performance prior to clinical acceptance is stressed. A strategy for implementing the test objects in a clinical department is present. The diagnostic information content of the clinical images which result measures the success of the quality control procedure adopted. (author)

  12. 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.

  13. Impact of peer interaction on conceptual test performance

    CERN Document Server

    Singh, Chandralekha

    2016-01-01

    We analyze the effectiveness of working in pairs on the Conceptual Survey of Electricity and Magnetism test in a calculus-based introductory physics course. Students who collaborated with a peer showed significantly larger normalized gain on individual testing than those who did not collaborate. We did not find statistically significant differences between the performance of students who were given an opportunity to formulate their own response before the peer discussions, compared to those who were not. Peer collaboration also shows evidence for co-construction of knowledge. Discussions with individual students show that students themselves value peer interaction. We discuss the effect of pairing students with different individual achievements.

  14. 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.

  15. 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

  16. 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.

  17. Performance test results of mock-up test facility of HTTR hydrogen production system

    International Nuclear Information System (INIS)

    Japan Atomic Energy Research Institute has been developing a hydrogen production system by means of a steam reforming of methane coupled with High Temperature Engineering Test Reactor (HTTR) to demonstrate effectiveness of high-temperature nuclear heat utilization. Prior to construction of HTTR hydrogen production system, a mock-up test facility was constructed to investigate transient behavior of the hydrogen production system and establish system controllability. This test facility is an approximately 1/30 scale model of the HTTR hydrogen production system and an electric heater is used as a heat source instead of a reactor. In order to investigate the performance of the test facility required from the planning mock-up test such as hydrogen reduction ability, controllability and so on, the performance test of the test facility was carried out, in the same pressure and temperature conditions as those of the HTTR hydrogen production system. It was confirmed that thermal disturbance of helium gas during the start-up could be mitigated by using a steam generator installed at the downstream of a steam reformer and that hydrogen was stably produced with a hot helium gas about 120 Nm3/h. This report describes the performance test program and results of the mock-up facility. (author)

  18. 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.

  19. 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

  20. 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.

  1. 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.

  2. Performance test of the quenching meshes for hydrogen control

    International Nuclear Information System (INIS)

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

  3. 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.

  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. 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.

  6. Improving Safety and Performance Testing for EV Batteries

    OpenAIRE

    WESTGEEST Alfons; BRETT Lois

    2013-01-01

    Alfons Westgeest and Lois Brett will present on the mutual activities of EUROBAT the Association of European Automotive and Industrial Battery Manufacturers and the European Commission Joint Research Centre (JRC) to improve the standardization framework for safety and performance testing for Hybrid Electric Vehicle (HEV) and Electric Vehicle (EV) batteries. EUROBAT and the JRC began formal cooperation in 2012 to support the JRC Institute for Energy and Transports (IET) battery energy ...

  7. Test Program for the Performance Analysis of DNS64 Servers

    OpenAIRE

    Gbor Lencse

    2015-01-01

    In our earlier research papers, bash shell scripts using the host Linux command were applied for testing the performance and stability of different DNS64 server implementations. Because of their inefficiency, a small multi-threaded C/C++ program (named dns64perf) was written which can directly send DNS AAAA record queries. After the introduction to the essential theoretical background about the structure of DNS messages and TCP/IP socket interface programming, the design decisions and implem...

  8. Round robin performance testing of organic photovoltaic devices

    DEFF Research Database (Denmark)

    Gevorgyan, Suren; Zubillaga, Oihana; de Seoane, Jos Mara Vega; Machado, Maider; Parlak, Elif Alturk; Tore, Nesrin; Voroshazi, Eszter; Aernouts, Tom; Mllejans, Harald; Bardizza, Giorgio; Taylor, Nigel; Verhees, Wiljan; Kroon, Jan M.; Morvillo, Pasquale; Minarini, Carla; Roca, Francesco; Castro, Fernando A.; Cros, Stphane; Lechne, Balthazar; Trigo, Juan F.; Guilln, Cecilia; Herrero, Jose; Zimmermann, Birger; Sapkota, Subarna Babu; Veit, Clemens; Wrfel, Uli; Tuladhar, Pabitra S.; Durrant, James R.; Winter, Stefan; Rousu, Sanna; Vlimki, 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...

  9. Preliminary performance assessment of a Nevada test site waste

    Energy Technology Data Exchange (ETDEWEB)

    Price, L.L.; Olague, N.E. (Sandia National Labs., Albuquerque, NM (USA)); Zimmerman, D.A. (GRAM, Inc., Albuquerque, NM (USA))

    1990-01-01

    The performance of the Nevada Test Site Greater Confinement Disposal (GCD) site was assessed against the Environmental Protection Agency's (EPA) requirements for disposal of high-level waste, spent fuel and transuranic waste, 40 CFR Part 191. No new data were collected for this assessment. This preliminary assessment indicates that the GCD concept is a viable method of disposing of transuranic wastes. The results are being used to direct future site characterization activities. 6 refs., 3 figs., 2 tabs.

  10. 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.

  11. A performance evaluation test for laser line scanners on CMMs

    OpenAIRE

    Van Gestel, Nick; Cuypers, Steven; Bleys, Philip; Kruth, Jean-Pierre

    2009-01-01

    This paper presents a performance evaluation test for laser line scanners on 3D coordinate measuring machines (CMMs). Laser line scanners are becoming more popular in recent years, mainly for free form inspection tasks and reverse engineering. Error specification of these scanners is difficult because of many influencing factors like surface quality, surface orientation and scan depth. Therefore, procedures for evaluation and verification of conventional contact probes (e.g. touch-trigger pro...

  12. 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 ...

  13. 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.

  14. 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)

  15. 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.)

  16. 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)

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

    International Nuclear Information System (INIS)

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

  18. Test Program for the Performance Analysis of DNS64 Servers

    Directory of Open Access Journals (Sweden)

    Gbor Lencse

    2015-09-01

    Full Text Available In our earlier research papers, bash shell scripts using the host Linux command were applied for testing the performance and stability of different DNS64 server implementations. Because of their inefficiency, a small multi-threaded C/C++ program (named dns64perf was written which can directly send DNS AAAA record queries. After the introduction to the essential theoretical background about the structure of DNS messages and TCP/IP socket interface programming, the design decisions and implementation details of our DNS64 performance test program are disclosed. The efficiency of dns64perf is compared to that of the old method using bash shell scripts. The result is convincing: dns64perf can send at least 95 times more DNS AAAA record queries per second. The source code of dns64perf is published under the GNU GPLv3 license to support the work of other researchers in the field of testing the performance of DNS64 servers.

  19. Performance Test of the Prototype SSDM for KJRR

    International Nuclear Information System (INIS)

    The purpose of this paper is to introduce the basic performance test results for a prototype of BMSSDM for KJRR. The CRDM acts as the first reactor shutdown mechanism and reactor regulating as well. The SSDM provides an alternate and independent means of reactor shutdown. The Second Shutdown Rods (SSRs) of the SSDM are poised at the top of the core by the hydraulic system during the normal operation and drop by gravity within the specific time. The SSR drop is commanded by the Reactor Protection System (RPS), Alternate Protection System (APS), Automatic Seismic Trip System (ASTS), or by the reactor operator in KJRR. In summary, all of the performance requirements are satisfied from the performance test results. We confirmed that there are no structural failures for the impacted parts, or negligible wear for the moving parts, and no leakage for the hydraulic cylinder assembly and hydraulic system during all of the tests. However, the design for the BMSSDM can be improved because its related reactor components, which are the CRDM, penetration assembly, RSA, and FFA, will be progressed continuously to meet their requirements and interfaces. In addition, accurate environmental conditions including a thermal hydraulic response and FRS will be determined in the near future

  20. 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.

  1. Verification tests performed for development of an integral type reactor

    International Nuclear Information System (INIS)

    SMART is an integral type reactor with innovative design features aimed at achieving a highly enhanced safety and improved economics. The SMART design is based on proven reactor design technologies with the use of new advanced design features. Most of the design features implemented into the SMART have been proven, however the advanced design features implemented into the SMART should be proven by testing. Various thermal hydraulic experiments have been carried out and also planned to assure the fundamental behavior of major concepts of the SMART and to prove the performance of the systems with new innovative technologies. This paper describes the thermal hydraulic test program for the SMART development and briefly discusses the typical test results. (author)

  2. 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)

  3. 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.

  4. 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.

  5. Performance and test results of a regulated magnetron pulser

    International Nuclear Information System (INIS)

    This paper describes the test results and performance of a 5.0-kV, 750-mA, regulated current pulser used to drive an Hitachi model 2M130 2,425-MHz magnetron. The magnetron is used to modulate the plasma in a particle accelerator injector. In this application, precise and stable rf power is crucial to extract a stable and accurate particle beam. A 10-kV high-voltage triode vacuum tube with active feedback is used to control the magnetron current and output rf power. The pulse width may be varied from as little as ten microseconds to continuous duty by varying the width of a supplied gate pulse. The output current level can be programmed between 10 and 750 mA. Current regulation and accuracy are better than 1%. The paper discusses the overall performance of the pulser and magnetron including anode current and rf power waveforms, linearity compliance, and vacuum tube performance

  6. Performance Test of High Heat Flux Test Facility for the Calorimetry and Beam Control

    International Nuclear Information System (INIS)

    The Korea Heat Load Test facility, KoHLT-EB (Electron Beam) has been operating for the plasma facing components to develop fusion engineering in Korea. The ITER Neutral Beam Duct Liner (NBDL) was fabricated and tested to qualify the thermocouple fixation method for the temperature measurement during a direct collision of the high-power neutral beam during ITER operation. The NBDL is CuCrZr panels, which are actively water cooled using deep drilled channels. To perform the profile test, the assessment for the possibility of an electron beam Gaussian power density profile and the result of absorbed power for that profile before the test start is needed. To assess the possibility of Gaussian profile, for the qualification test of a Gaussian heat load profile, small calorimetry was manufactured to simulate a real heat profile in the neutral beam duct liner, and this calorimetry has two cooling channel with five thermocouples, which is the same as NBDL. Preliminary analyses with ANSYSCFX using a 3D model were performed with the calorimetry model. The heating area was modeled to be 60 mm x 250 mm. The simulated heat flux is 0.5 - 1.2 MW/m''2 at 0.75 kg/sec of the water flow rate. A steady heat flux test was performed to measure the surface heat flux, surface temperature profile. With a thermohydraulic analysis and heat load test, the Gaussian heat profile will be confirmed for this calorimetry and NBDL mockup. The Korean heat load test facility will be used to qualify the specifications of various plasma facing components in fusion devices. To conduct 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

  7. 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.

  8. 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

  9. Sport performance and agility tests Sporda performans ve eviklik 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. zet Bu al??man?n amac? evikli?in spor performans?na etkisini ve eviklik lm testlerini incelemektir. eviklik, belli bir uyar?c?ya cevap olarak tm vcudun h?z veya yn de?i?tirerek ani hareketi olarak tan?mlan?r. evikli?in kalitesi, h?z, denge, g ve koordinasyonun ortakl???n? gerektirir. Motor bir yetenek olan eviklik, dzenli progresif egzersizle geli?tirilebilir. nemli bir unsur olarak eviklik spor performans lm bataryalar?nda kullan?lan geerli bir yntemdir. al??man?n sonucu olarak, spor aktivitelerinin byk o?unlu?unda gerekli bir zellik olan eviklik, ba?ar?l? sporcular?n sahip olmas? gereken nemli bir niteliktir. Sportif performans?n art?r?lmas? iin sportif performans testleri uygulan?rken hem evikli?i artt?r?c? egzersizler hem de evikli?in artmas?n? sa?layan dinamik denge zelli?ini de geli?tirici egzersizler neme sahiptir.

  10. 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)

  11. Neuropsychological test performance of Spanish speakers: is performance different across different Spanish-speaking subgroups?

    Science.gov (United States)

    Bur-Reyes, Annelly; Hidalgo-Ruzzante, Natalia; Vilar-Lpez, Raquel; Gontier, Javier; Snchez, Laura; Prez-Garca, Miguel; Puente, Antonio E

    2013-01-01

    Even though theories and research have pointed out the importance of variables such as age, gender, or education on neuropsychological assessment, much less emphasis has been placed on language and culture. With the increasing population of Spanish speakers in North America and the limited amount of clinical and scholarly information currently available, neuropsychological assessment of this group has similarly become of increasing importance. Though several studies have been published over the last two decades, an assumption exists that all Spanish speakers, holding education and age constant, would perform similarly regardless of their origin. To address this assumption, a sample of 126 participants was tested from four different countries (Chile, Dominican Republic, Puerto Rico, and Spain). Participants were compared on the following commonly used neuropsychological tests: Verbal Serial Learning Curve, Rey- Osterrieth Complex Figure Test, Verbal Phonemic Fluency Test, the Stroop Color and Word Test, and the Trail Making Test. Analyses revealed significant differences across the groups in two of the five tests administered. Significant differences were observed in the delayed recall of the Serial Learning Test and in the Verbal Fluency Test. The findings highlight the importance of within-group differences between Spanish speakers. PMID:23496164

  12. Results of Performance Tests Performed on the John Watts Casing Connection on 7" Pipe

    Energy Technology Data Exchange (ETDEWEB)

    John D. Watts

    1999-08-01

    Stress Engineering Services (SES) was contracted by Mr. John Watts to test his threaded connection developed for oilfield oil and gas service. This particular test required the application of a variety of loads including axial tension and compression, internal pressure (gas), external pressure (water), bending and both low and elevated temperature. These loads were used to determine the sealing and structural limits of the connection. The connection design tested had tapered threads with 10 threads per inch. A square thread form and a round thread form were tested. The square thread form had a 2{sup o} load flank and 15{sup o} stab flank. The round thread had a 0{sup o} load flank and 20{sup o} stab flank. Most of the testing was performed on the round thread form. Both a coupled connection design and an integral connection design were tested. The coupling was a pin by pin (male) thread, with the pipe having a box (female) thread. Both designs have outside and inside diameters that are flush with the pipe body. Both designs also contain a small external shoulder. The test procedure selected for this evaluation was the newly written ISO 13679 procedure for full scale testing of casing and tubing connections. The ISO procedure requires a variety of tests that includes makeup/breakout testing, internal gas sealability/external water sealability testing with axial tension, axial compression, bending, internal gas thermal cycle tests and limit load (failure) tests. This test was performed with four coupled samples and included most of these loads. Two integral samples were also included for limit load testing ISO makeup/breakout tests are divided into three types--initial makeup, IML1, repeated makeup within the same sample, MBL, and repeated makeup using several samples called round robin, RR. IMU and MBL were performed in this project. The ISO sealing and structural procedure is divided into four primary tests and identified as Series A, B, C and Limit Load (failure). Series A and B test to 95% actual yield of the pipe and Series C uses 90% of actual yield. Samples 1 and 3 were tested to Series A and the loads are shown in Figure 1. For these samples, the axial compression was limited to 75% pipe body yield, which was set by Mr. Watts at the beginning of the test. Samples 2 and 4 were tested to Series B with loads shown in Figure 2. This series included 20 degrees per 100 feet bending but no external pressure. Due to premature leaks, no samples were subjected to Series C which included mechanical and thermal cycles. Samples 5 and 6 were tested to failure. The project started with the selection and purchase of a popular size of oilfield pipe, which was 7-inch OD, 32 pound per foot, P-110 casing. While the connections were being threaded, material tensile tests were performed to get the actual strength of the 7-inch pipe. The first samples contained a square thread form. Excessive galling was experienced during the first series of makeup/breakout tests and Mr. Watts decided to change the thread form and remachine the samples. The second samples had a round thread form and performed very well in the makeup/breakout tests. Basically no galling occurred of any consequence. Samples 1 and 3 were to be tested with external water (ISO Series A) while samples 2 and 4 were to be tested with bending (ISO Series B, no external pressure). Testing of all four samples started with tension and internal gas pressure. During this initial pressure testing, samples 1, 3 and 4 developed leaks and the test was stopped before any external pressure or bending was applied. Sample 2 successfully tested to ISO Load Point 5 which included bending before developing a leak. Figure 3 shows the loads at which the samples leaked and the relative pipe body performance capability. Sample 1 and end A of sample 2 held a high pressure while samples 3, 4 and end B of sample 2 leaked at relatively low pressures. All of these leaks were with nitrogen gas pressure. After reviewing the results, it was believed that several conditions may have contributed to the prema

  13. 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)

  14. 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.

  15. 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

  16. Core-support performance test in the component-flow test loop

    International Nuclear Information System (INIS)

    The CFTL is a closed-circuit, out-of-pile loop circulating helium at temperatures and pressures anticipated in gas-cooled reactors at flows sufficiently large to perform engineering-scale tests. It has the present capability for fast data acquisition and the control and measurement of gaseous impurities, and it has the potential to perform controlled rapid transients in pressure, flow, and power. The initial HTGR component to be tested in the CFTL is the core support structure for the prismatic bed HTGR. This structure has vertical posts mating with post seats, each with spherical curvatures of different radii. At the point of contact, Hertzian stress concentrations are produced. Under the load of the weight of the core plus the pressure gradient, the graphite will deform until the stress is below its yield limit. The Core Support Performance Test (CSPT) will subject this interface, using actual materials and geometry, to impure helium at HTGR operating temperatures, pressures, and flows under a simulated structural load. The concentration of water, hydrogen, and carbon dioxide will be controlled so that six months of test operation will simulate 40 years of reactor operation. The specification of this concentration is based on existing studies involving small graphite samples exposed to a variety of conditions at a few atmospheres. The extrapolation to concentrations that will duplicate both the amount and the nature of the corrosion is based on the oxidation kinetics of the Gadsby equation as parameterized by Velasquez. Ports are provided in the test vessel for in situ inspection of the graphite during the test period. Post-test examination of the structure will be used to correlate its performance with available computational methods

  17. 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)

  18. Test results of the SMES model coil. Pulse performance

    International Nuclear Information System (INIS)

    A model coil for superconducting magnetic energy storage (SMES model coil) has been developed to establish the component technologies needed for a small-scale 100 kWh SMES device. The SMES model coil was fabricated, and then performance tests were carried out in 1996. The coil was successfully charged up to around 30 kA and down to zero at the same ramp rate of magnetic field experienced in a 100 kWh SMES device. AC loss in the coil was measured by an enthalpy method as parameters of ramp rate and flat top current. The results were evaluated by an analysis and compared with short-sample test results. The measured hysteresis loss is in good agreement with that estimated from the short-sample results. It was found that the coupling loss of the coil consists of two major coupling time constants. One is a short time constant of about 200 ms, which is in agreement with the test results of a short real conductor. The other is a long time constant of about 30 s, which could not be expected from the short sample test results. (author)

  19. Performance testing of automatic vehicle radioactive sources monitors

    International Nuclear Information System (INIS)

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

  20. Performance testing of waste forms in a tuff environment

    International Nuclear Information System (INIS)

    This paper describes experimental work conducted to establish the chemical composition of water which will have reacted with Topopah Spring Member tuff prior to contact with waste packages. The experimental program to determine the behavior of spent fuel and borosilicate glass in the presence of this water is then described. Preliminary results of experiments using spent fuel segments with defects in the Zircaloy cladding are presented. Some results from parametric testing of a borosilicate glass with tuff and 304L stainless steel are also discussed. Experiments conducted using Topopah Spring tuff and J-13 well water have been conducted to provide an estimate of the post-emplacement environment for waste packages in a repository at Yucca Mountain. The results show that emplacement of waste packages should cause only small changes in the water chemistry and rock mineralogy. The changes in environment should not have any detrimental effects on the performance of metal barriers or waste forms. The NNWSI waste form testing program has provided preliminary results related to the release rate of radionuclides from the waste package. Those results indicate that release rates from both spent fuel and borosilicate glass should be below 1 part in 105 per year. Future testing will be directed toward making release rate testing more closely relevant to site specific conditions. 17 references, 7 figures