Void Fraction Instrument operation and maintenance manual

International Nuclear Information System (INIS)

Borgonovi, G.; Stokes, T.I.; Pearce, K.L.; Martin, J.D.; Gimera, M.; Graves, D.B.

1994-09-01

This Operations and Maintenance Manual (O ampersand MM) addresses riser installation, equipment and personnel hazards, operating instructions, calibration, maintenance, removal, and other pertinent information necessary to safely operate and store the Void Fraction Instrument. Final decontamination and decommissioning of the Void Fraction Instrument are not covered in this document

Strategy for the development of EU Test Blanket Systems instrumentation

Energy Technology Data Exchange (ETDEWEB)

Calderoni, P., E-mail: Pattrick.Calderoni@f4e.europa.eu; Ricapito, I.; Poitevin, Y.

2013-10-15

Highlights: • We developed a strategy for the development of instrumentation for EU ITER TBSs. • TBSs instrumentation functions: safety, operation and scientific mission. • Described activities are in support of ITER design review process. -- Abstract: The instrumentation of the HCLL and HCPB Test Blanket System is fundamental in ensuring that ITER safety and operational requirements are satisfied as well as in enabling the scientific mission of the TBM program. It carries out three essential functions: (i) safety, intended as compliance with ITER requirements toward public and workers protection; (ii) system control, intended as compliance with ITER operational requirements and investment protection; and (iii) scientific mission, intended as validating technology and predictive tools for blanket concepts relevant to fusion energy systems. This paper describes the strategy for instrumentation development by providing details of the following five steps to be implemented in procured activities in the short to mid-term (3–4 years): (i) provide mapping of sensors requirements based on critical review of preliminary design data; (ii) develop functional specifications for TBS sensors based on the analysis of operative conditions in the various ITER buildings in which they are located; (iii) assess availability of commercial sensors against developed specifications; (iv) develop prototypes when no available solution is identified; and (v) perform single effect tests for the most critical solicitations and post-test examination of commercial products and prototypes. Examples of technology assessment in two technical areas are included to reinforce and complement the strategy description.

DAS: A Data Management System for Instrument Tests and Operations

Science.gov (United States)

Frailis, M.; Sartor, S.; Zacchei, A.; Lodi, M.; Cirami, R.; Pasian, F.; Trifoglio, M.; Bulgarelli, A.; Gianotti, F.; Franceschi, E.; Nicastro, L.; Conforti, V.; Zoli, A.; Smart, R.; Morbidelli, R.; Dadina, M.

2014-05-01

The Data Access System (DAS) is a and data management software system, providing a reusable solution for the storage of data acquired both from telescopes and auxiliary data sources during the instrument development phases and operations. It is part of the Customizable Instrument WorkStation system (CIWS-FW), a framework for the storage, processing and quick-look at the data acquired from scientific instruments. The DAS provides a data access layer mainly targeted to software applications: quick-look displays, pre-processing pipelines and scientific workflows. It is logically organized in three main components: an intuitive and compact Data Definition Language (DAS DDL) in XML format, aimed for user-defined data types; an Application Programming Interface (DAS API), automatically adding classes and methods supporting the DDL data types, and providing an object-oriented query language; a data management component, which maps the metadata of the DDL data types in a relational Data Base Management System (DBMS), and stores the data in a shared (network) file system. With the DAS DDL, developers define the data model for a particular project, specifying for each data type the metadata attributes, the data format and layout (if applicable), and named references to related or aggregated data types. Together with the DDL user-defined data types, the DAS API acts as the only interface to store, query and retrieve the metadata and data in the DAS system, providing both an abstract interface and a data model specific one in C, C++ and Python. The mapping of metadata in the back-end database is automatic and supports several relational DBMSs, including MySQL, Oracle and PostgreSQL.

Operational and reliability experience with reactor instrumentation

International Nuclear Information System (INIS)

Dixon, F.; Gow, R.S.

1978-01-01

In the last 15 years the CEGB has experienced progressive plant development, integration and changes in operating regime through nine nuclear (gas-cooled reactor) power stations with corresponding instrumentation advances leading towards more refined centralized control. Operation and reliability experience with reactor instrumentation is reported in this paper with reference to the progressive changes related to the early magnox, late magnox and AGR periods. Data on instrumentation reliability in terms of reactor forced outages are presented and show that the instrumentation contributions to loss of generating plant availability are small. Reactor safety circuits, neutron flux and temperature measurements, gas analysis and vibration monitoring are discussed. In reviewing the reactor instrumentation the emphasis is on reporting recent experience, particularly on AGR equipment, but overall performance and changes to magnox equipment are included so that some appreciation can be obtained of instrumentation requirements with respect to plant lifetimes. (author)

System for managing operation of instrument in atomic power plant facility

International Nuclear Information System (INIS)

Shinzawa, Katsuo.

1982-01-01

Purpose: To facilitate the management of the operating state of instruments operated in a site without necessity of large revision and additional cables of the instruments. Constitution: Tag-shaped instrument recognition indicators and instrument operation indicators for indicating the operating states of the respective instruments are mounted on the instruments such as openable valves. Each instrument recognition indicator represents the type and symbol of the instrument, and each instrument operation indicator represents the operating state such as open state or closed state of the valve of theinstrument. A reader reads a recorded data when the reader is touched to a magnetic plate and a magnetic sheet, and the data is recorded by a recorder on the magnetic tape. In this manner, the leakage of checking the data can be prevented, and the load of an operator can be alleviated. (Kamimura, M.)

Virtual Sensor Test Instrumentation

Science.gov (United States)

Wang, Roy

2011-01-01

Virtual Sensor Test Instrumentation is based on the concept of smart sensor technology for testing with intelligence needed to perform sell-diagnosis of health, and to participate in a hierarchy of health determination at sensor, process, and system levels. A virtual sensor test instrumentation consists of five elements: (1) a common sensor interface, (2) microprocessor, (3) wireless interface, (4) signal conditioning and ADC/DAC (analog-to-digital conversion/ digital-to-analog conversion), and (5) onboard EEPROM (electrically erasable programmable read-only memory) for metadata storage and executable software to create powerful, scalable, reconfigurable, and reliable embedded and distributed test instruments. In order to maximize the efficient data conversion through the smart sensor node, plug-and-play functionality is required to interface with traditional sensors to enhance their identity and capabilities for data processing and communications. Virtual sensor test instrumentation can be accessible wirelessly via a Network Capable Application Processor (NCAP) or a Smart Transducer Interlace Module (STIM) that may be managed under real-time rule engines for mission-critical applications. The transducer senses the physical quantity being measured and converts it into an electrical signal. The signal is fed to an A/D converter, and is ready for use by the processor to execute functional transformation based on the sensor characteristics stored in a Transducer Electronic Data Sheet (TEDS). Virtual sensor test instrumentation is built upon an open-system architecture with standardized protocol modules/stacks to interface with industry standards and commonly used software. One major benefit for deploying the virtual sensor test instrumentation is the ability, through a plug-and-play common interface, to convert raw sensor data in either analog or digital form, to an IEEE 1451 standard-based smart sensor, which has instructions to program sensors for a wide variety of

Operator/instrumentation interactions during the Three Mile Island incident

International Nuclear Information System (INIS)

Cummings, G.E.

1979-10-01

A discussion is presented of the operator/instrumentation interactions which had an effect on the course of the incident at the Three Mile Island-2 Nuclear Power Plant. A brief review of the sequence of occurrences at TMI-2 over the first 16 hours of the incident is given with particular emphasis on operator/instrumentation interactions. A breakdown of the six major items that seemed to have contributed to the characteristics of the incident is then given and also an outline of some of the currently proposed operator/instrumentation improvements. The six major items involve water level indication in the reactor, electromatic relief valve operation, auxiliary feed-water flow indication, containment isolation, extended range instrumentation, and computer readout

Comparison of defects in ProTaper hand-operated and engine-driven instruments after clinical use.

Science.gov (United States)

Cheung, G S P; Bian, Z; Shen, Y; Peng, B; Darvell, B W

2007-03-01

To compare the type of defects and mode of material failure of engine-driven and hand-operated ProTaper instruments after clinical use. A total of 401 hand-operated and 325 engine-driven ProTaper instruments were discarded from an endodontic clinic over 17 months. Those that had fractured were examined for plastic deformation in lateral view and remounted for fractographical examination in scanning electron microscope. The mode of fracture was classified as 'fatigue' or 'shear' failure. The lengths of fractured segments in both instruments were recorded. Any distortion in hand instrument was noted. Data were analysed using chi-square, Fisher's exact or Student's t-test, where appropriate. Approximately 14% of all discarded hand-operated instruments and 14% of engine-driven instruments were fractured. About 62% of hand instruments failed because of shear fracture, compared with approximately 66% of engine-driven instruments as a result of fatigue (P hand instruments were affected by shear, and either remained intact or was fractured, compared with 5% of engine-driven instruments (P hand versus engine-driven group (P hand instruments were discarded intact but distorted (rarely for engine-driven instruments); all were in the form of unscrewing of the flutes. The location of defects in hand Finishing instruments was significantly closer to the tip than that for Shaping instruments (P ProTaper engine-driven and hand-operated instruments appeared to be different, with shear failure being more prevalent in the latter.

Concluding from operating experience to instrumentation and control systems

International Nuclear Information System (INIS)

Pleger, H.; Heinsohn, H.

1997-01-01

Where conclusions are drawn from operating experience to instrumentation and control systems, two general statements should be made. First: There have been braekdowns, there have also been deficiencies, but in principle operating experience with the instrumentation and control systems of German nuclear power plants has been good. With respect to the debates about the use of modern digital instrumentation and control systems it is safe to say, secondly, that the instrumentation and control systems currently in use are working reliably. Hence, there is no need at present to replace existing systems for reasons of technical safety. However, that time will come. It is a good thing, therefore, that the use of modern digital instrumentation and control systems is to begin in the field of limiting devices. The operating experience which will thus be accumulated will benefit digital instrumentation and control systems in their qualification process for more demanding applications. This makes proper logging of operating experience an important function, even if it cannot be transferred in every respect. All parties involved therefore should see to it that this operating experience is collected in accordance with criteria agreed upon so as to prevent unwanted surprises later on. (orig.) [de

Testing Aircraft Instruments.

Science.gov (United States)

1981-02-11

1. Have test data been collected, recorded, and presented in accordance with this TOP? Yes No Comment : 2. Were the facilities, test equipment...instrumentation, and support accommodations adequate to accomplish the test objectives? Yes No Comment : 3. Have all data collected been reviewed for...correctness and completeness? Yes No Comment : 4. Were the test results compromised in any way due to insufficient test planning? Yes No Comment : 5. Were the

Neutron generator instrumentation at the Department 2350 Neutron Generator Test Facility

International Nuclear Information System (INIS)

Bryant, T.C.; Mowrer, G.R.

1979-06-01

The computer and waveform digitizing capability at the test facility has allowed several changes in the techniques used to test neutron generators. These changes include methods used to calibrate the instrumentation and changes in the operation of the test facility. These changes have increased the efficiency of the test facility as well as increasing both timing and amplitude accuracy of neutron generator waveforms

Operator Actions Within a Safety Instrumented Function

International Nuclear Information System (INIS)

Suttinger, L.T.

2002-01-01

This paper presents an overview of the factors that should be considered when crediting operator action for performing a safety function or being a part of the process of enabling a safety function. Criteria for evaluating operator action, such as required time response and operator training among others, are discussed. The paper will address these and other factors that should be considered when determining the reliability of the operator to respond and perform his/her part of the safety function. The entire safety function includes the operator and the reliability of the instrumented system that provides the alarm or indication, the final control element, and support systems. The integration of the operator performance with the hardware safety availability, including the effects of the supporting systems is discussed. The analysis of these factors will provide the justification for the amount of risk reduction or safety integrity level that can be credited for the Safety Instrumented Function (SIF), including operator action

Operational test procedure for Bldg 241-A-701 air compressor

International Nuclear Information System (INIS)

Desantis, G.N.

1995-01-01

This document is an Operability Test Procedure (OTP) which will verify and record that the 241-A-701 air compressor and associated equipment operates within their intended design parameters. The activities defined in this OTP will be performed to ensure the daily operation of the new compressed air system can be reliable and efficient. The Compressed Air System (CAS) for 241-A-701 supplies process and instrument air to the A, AX, AY, and AZ tank farms. The primary use of the CAS is for tank farms instrumentation, air operated valves, and air lift circulators

Under sodium reliability tests on core components and in-core instrumentation

International Nuclear Information System (INIS)

Ruppert, E.; Stehle, H.; Vinzens, K.

1977-01-01

A sodium test facility for fast breeder core components (AKB), built by INTERATOM at Bensberg, has been operating since 1971 to test fuel dummies and blanket elements as well as absorber elements under simulated normal and extreme reactor conditions. Individual full-scale fuel or blanket elements and arrays of seven elements, modelling a section of the SNR-300 reactor core, have been tested under a wide range of sodium mass flow and isothermal test conditions up to 925K as well as under cyclic changed temperature transients. Besides endurance testing of the core components a special sodium and high-temperature instrumentation is provided to investigate thermohydraulic and vibrational behaviour of the test objects. During all test periods the main subassembly characteristics could be reproduced and the reliability of the instrumentation could be proven. (orig.) [de

On-line testing of calibration of process instrumentation channels in nuclear power plants. Phase 2, Final report

International Nuclear Information System (INIS)

Hashemian, H.M.

1995-11-01

The nuclear industry is interested in automating the calibration of process instrumentation channels; this report provides key results of one of the sponsored projects to determine the validity of automated calibrations. Conclusion is that the normal outputs of instrument channels in nuclear plants can be monitored over a fuel cycle while the plant is operating to determine calibration drift in the field sensors and associated signal conversion and signal conditioning equipment. The procedure for on-line calibration tests involving calculating the deviation of each instrument channel from the best estimate of the process parameter that the instrument is measuring. Methods were evaluated for determining the best estimate. Deviation of each signal from the best estimate is updated frequently while the plant is operating and plotted vs time for entire fuel cycle, thereby providing time history plots that can reveal channel drift and other anomalies. Any instrument channel that exceeds allowable drift or channel accuracy band is then scheduled for calibration during a refueling outage or sooner. This provides calibration test results at the process operating point, one of the most critical points of the channel operation. This should suffice for most narrow-range instruments, although the calibration of some instruments can be verified at other points throughout their range. It should be pointed out that the calibration of some process signals such as the high pressure coolant injection flow in BWRs, which are normally off- scale during plant operation, can not be tested on-line

A Unique Outside Neutron and Gamma Ray Instrumentation Development Test Facility at NASA's Goddard Space Flight Center

Science.gov (United States)

Bodnarik, J.; Evans, L.; Floyd, S.; Lim, L.; McClanahan, T.; Namkung, M.; Parsons, A.; Schweitzer, J.; Starr, R.; Trombka, J.

2010-01-01

An outside neutron and gamma ray instrumentation test facility has been constructed at NASA's Goddard Space Flight Center (GSFC) to evaluate conceptual designs of gamma ray and neutron systems that we intend to propose for future planetary lander and rover missions. We will describe this test facility and its current capabilities for operation of planetary in situ instrumentation, utilizing a l4 MeV pulsed neutron generator as the gamma ray excitation source with gamma ray and neutron detectors, in an open field with the ability to remotely monitor and operate experiments from a safe distance at an on-site building. The advantage of a permanent test facility with the ability to operate a neutron generator outside and the flexibility to modify testing configurations is essential for efficient testing of this type of technology. Until now, there have been no outdoor test facilities for realistically testing neutron and gamma ray instruments planned for solar system exploration

42 CFR 493.1252 - Standard: Test systems, equipment, instruments, reagents, materials, and supplies.

Science.gov (United States)

2010-10-01

... 42 Public Health 5 2010-10-01 2010-10-01 false Standard: Test systems, equipment, instruments... SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY... storage of reagents and specimens, accurate and reliable test system operation, and test result reporting...

Automated testing of health physics instruments

International Nuclear Information System (INIS)

Swinth, K.L.; Endres, A.W.; Hadley, R.T.; Kenoyer, J.L.

1983-12-01

A microcomputer controlled CAMAC system has been adapted for automated testing of health physics survey instruments. Once the survey instrument is positioned, the system automatically performs tests for angular dependence or battery lifetime. Rotation of the instrument is performed by a computer controlled stepping motor while readout is performed by an auto ranging digital volt meter and data stored on computer disks

Cryo-Vacuum Testing of the Integrated Science Instrument Module for the James Webb Space Telescope

Science.gov (United States)

Kimble, Randy A.; Davila, P. S.; Drury, M. P.; Glazer, S. D.; Krom, J. R.; Lundquist, R. A.; Mann, S. D.; McGuffey, D. B.; Perry, R. L.; Ramey, D. D.

2011-01-01

With delivery of the science instruments for the James Webb Space Telescope (JWST) to Goddard Space Flight Center (GSFC) expected in 2012, current plans call for the first cryo-vacuum test of the Integrated Science Instrument Module (ISIM) to be carried out at GSFC in early 2013. Plans are well underway for conducting this ambitious test, which will perform critical verifications of a number of optical, thermal, and operational requirements of the IS 1M hardware, at its deep cryogenic operating temperature. We describe here the facilities, goals, methods, and timeline for this important Integration & Test milestone in the JWST program.

Solution assay instrument operations manual

International Nuclear Information System (INIS)

Li, T.K.; Marks, T.; Parker, J.L.

1983-09-01

An at-line solution assay instrument (SAI) has been developed and installed in a plutonium purification and americium recovery process area in the Los Alamos Plutonium Processing Facility. The instrument was designed for accurate, timely, and simultaneous nondestructive analysis of plutonium and americium in process solutions that have a wide range of concentrations and americium/plutonium ratios and for routine operation by process technicians who lack instrumentation background. The SAI, based on transmission-corrected, high-resolution gamma-ray spectroscopy, has two measurement stations attached to a single multichannel analyzer/computer system. To ensure the quality of assay results, the SAI has an internal measurement control program, which requires daily and weekly check runs and monitors key aspects of all assay runs. For a 25-ml sample, the assay precision is 5 g/l within a 2000-s count time

Plan for the testing of radiation measurement instrumentation intended for use at an excavation site

International Nuclear Information System (INIS)

Gehrke, R.J.

1994-11-01

This plan describes performance tests to be made with ionizing radiation measurement instrumentation designed and built for in-field assay at an excavation site. One instrument measures gross gamma-ray and neutron fields and the other identifies gamma-ray emitting radionuclides and also is capable of assaying for selected hazardous materials. These instruments will be operationally tested to verify that original specifications have been met and performance tested to establish and verify that they have the potential to function as intended at an excavation site

Operational Problems Associated with Head-Up Displays during Instrument Flight.

Science.gov (United States)

1980-10-01

Force project engineers were Major Michael F. Rundle and Mr. William L. Welde . 41 4 TABLE OF CONTENTS Page ABBREVIATIONS...of Automotive Engineers SETP Society of Experimental Test Pilots SI Solid Instruments SNPL Syndicat National des Pilotes des Lignes (French ALPA) TACAN...Factors Relevent to Jet Upsets ," Lessons with Emphasis on Flight Mechanics from Operating Experience, Incidents, and Accidents, AGARD CP-76, 1971 153 J

System Performance Testing of the Pulse-Echo Ultrasonic Instrument for Critical Velocity Determination during Hanford Tank Waste Transfer Operations - 13584

Energy Technology Data Exchange (ETDEWEB)

Denslow, Kayte M.; Bontha, Jagannadha R.; Adkins, Harold E.; Jenks, Jeromy W.J.; Hopkins, Derek F. [Pacific Northwest National Laboratory, Richland, Washington 99354 (United States); Thien, Michael G.; Kelly, Steven E.; Wooley, Theodore A. [Washington River Protection Solutions, Richland, Washington 99354 (United States)

2013-07-01

The delivery of Hanford double-shell tank waste to the Hanford Tank Waste Treatment and Immobilization Plant (WTP) is governed by specific Waste Acceptance Criteria that are identified in ICD 19 - Interface Control Document for Waste Feed. Waste must be certified as acceptable before it can be delivered to the WTP. The fluid transfer velocity at which solid particulate deposition occurs in waste slurry transport piping (critical velocity) is a key waste acceptance parameter that must be accurately characterized to determine if the waste is acceptable for transfer to the WTP. Washington River Protection Solutions and the Pacific Northwest National Laboratory have been evaluating the ultrasonic PulseEcho instrument since 2010 for its ability to detect particle settling and determine critical velocity in a horizontal slurry transport pipeline for slurries containing particles with a mean particle diameter of =14 micrometers (μm). In 2012 the PulseEcho instrument was further evaluated under WRPS' System Performance test campaign to identify critical velocities for slurries that are expected to be encountered during Hanford tank waste retrieval operations or bounding for tank waste feed. This three-year evaluation has demonstrated the ability of the ultrasonic PulseEcho instrument to detect the onset of critical velocity for a broad range of physical and rheological slurry properties that are likely encountered during the waste feed transfer operations between the Hanford tank farms and the WTP. (authors)

Testing the Solar Probe Cup, an Instrument Designed to Touch the Sun

Science.gov (United States)

Whittlesey, Phyllis L.; Case, Anthony W.; Kasper, Justin Christophe; Wright, Kenneth H., Jr.; Alterman, Ben; Cirtain, Jonathan W.; Bookbinder, Jay; Korreck, Kelly E.; Stevens, Michael Louis

2014-01-01

Solar Probe Plus will be the first, fastest, and closest mission to the sun, providing the first direct sampling of the sub-Alfvenic corona. The Solar Probe Cup (SPC) is a unique re-imagining of the traditional Faraday Cup design and materials for immersion in this high temperature environment. Sending an instrument of this type into a never-seen particle environment requires extensive characterization prior to launch to establish sufficient measurement accuracy and instrument response. To reach this end, a slew of tests for allowing SPC to see ranges of appropriate ions and electrons, as well as a facility that reproduces solar photon spectra and fluxes for this mission. Having already tested the SPC at flight like temperatures with no significant modification of the noise floor, we recently completed a round of particle testing to see if the deviations in Faraday Cup design fundamentally change the operation of the instrument. Results and implications from these tests will be presented, as well as performance comparisons to cousin instruments such as those on the WIND spacecraft.

Water NSTF Design, Instrumentation, and Test Planning

Energy Technology Data Exchange (ETDEWEB)

Lisowski, Darius D.; Gerardi, Craig D.; Hu, Rui; Kilsdonk, Dennis J.; Bremer, Nathan C.; Lomperski, Stephen W.; Kraus, Adam R.; Bucknor, Matthew D.; Lv, Qiuping; Farmer, Mitchell T.

2017-08-01

variations and off-normal configurations. The facility design follows, including as-built dimensions and specifications of the various mechanical and liquid systems, design choices for the test section, water storage tank, and network piping. Specifications of the instrumentation suite are then presented, along with specific information on performance windows, measurement uncertainties, and installation locations. Finally, descriptions of the control systems and heat removal networks are provided, which have been engineered to support precise quantification of energy balances and facilitate well-controlled test operations.

Surgical Instrument Sets for Special Operations Expeditionary Surgical Teams.

Science.gov (United States)

Hale, Diane F; Sexton, Justin C; Benavides, Linda C; Benavides, Jerry M; Lundy, Jonathan B

The deployment of surgical assets has been driven by mission demands throughout years of military operations in Iraq and Afghanistan. The transition to the highly expeditious Golden Hour Offset Surgical Transport Team (GHOST- T) now offers highly mobile surgical assets in nontraditional operating rooms; the content of the surgical instrument sets has also transformed to accommodate this change. The 102nd Forward Surgical Team (FST) was attached to Special Operations assigned to southern Afghanistan from June 2015 to March 2016. The focus was to decrease overall size and weight of FST instrument sets without decreasing surgical capability of the GHOST-T. Each instrument set was evaluated and modified to include essential instruments to perform damage control surgery. The overall number of main instrument sets was decreased from eight to four; simplified augmentation sets have been added, which expand the capabilities of any main set. The overall size was decreased by 40% and overall weight decreased by 58%. The cardiothoracic, thoracotomy, and emergency thoracotomy trays were condensed to thoracic set. The orthopedic and amputation sets were replaced with an augmentation set of a prepackaged orthopedic external fixator set). An augmentation set to the major or minor basic sets, specifically for vascular injuries, was created. Through the reorganization of conventional FST surgical instrument sets to maintain damage control capabilities and mobility, the 102nd GHOST-T reduced surgical equipment volume and weight, providing a lesson learned for future surgical teams operating in austere environments. 2017.

Vehicle for transporting instruments for testing against a wall

International Nuclear Information System (INIS)

Hyde, E.A.; Goldsmith, H.A.; Proudlove, M.J.

1981-01-01

This invention relates to a non-destructive testing apparatus and, in particular, to a vehicle that can be moved at will, for transporting instruments for testing against a surface remote from the operator. Under this invention a vehicle is intended, for instance, for testing the vessel of an installation containing a liquid metal cooled nuclear reactor of the pond type. Such an installation includes a nuclear reactor comprising an assembly containing a nuclear fuel immersed in a pond of liquid metal coolant, located in a vessel which is itself placed in a concrete containment vessel [fr

Operability test procedure for 244-U DCRT. Revision 1

International Nuclear Information System (INIS)

Erhart, M.F.

1995-01-01

This OPT will insure the operability of various systems and their general equipment, used in the operation of the 244-U DCRT. Systems that will be tested include the following: Leak Detection Systems; Heat Trace System; Vessel Temperature Measurement System; Dip Tube Water System; Weight Factor and Specific Gravity System; Instrument Air System; Vessel Liquid Level System; Vessel Liquid Transfer System; and Exhauster Differential Pressure Indicating Controller System. The tests will cover checks on equipment operation and electrical interlocks, but will not cover checks on associated annunciator alarms which are covered in a separate OTP

Removal of simulated biofilm: a preclinical ergonomic comparison of instruments and operators.

Science.gov (United States)

Graetz, Christian; Plaumann, Anna; Rauschenbach, Sebastian; Bielfeldt, Jule; Dörfer, Christof E; Schwendicke, Falk

2016-07-01

Periodontal scaling might cause musculoskeletal disorders, and scaling instruments might not only have different effectiveness and efficiency but also differ in their ergonomic properties. The present study assessed ergonomic working patterns of experienced (EO) and less experienced operators (LO) when using hand and powered devices for periodontal scaling and root planning. In an experimental study using periodontally affected manikins, sonic (AIR), ultrasonic (TIG) and hand instruments (GRA) were used by 11 operators (7 EO/4 LO) during simulated supportive periodontal therapy. Using an electronic motion monitoring system, we objectively assessed the working frequency and positioning of hand, neck and head. Operators' subjective evaluation of the instruments was recorded using a questionnaire. Hand instruments were used with the lowest frequency (2.57 ± 1.08 s(-1)) but greatest wrist deviation (59.57 ± 53.94°). EO used instruments more specifically than LO, and generally worked more ergonomically, with less inclination of head and neck in both the frontal and sagittal planes, especially when using hand instruments. All groups found hand instruments more tiring and difficult to use than powered instruments. Regardless of operators' experience, powered instruments were used more ergonomically and were subjectively preferred compared to hand instruments. The use of hand instruments has potential ergonomic disadvantages. However, with increasing experience, operators are able to recognise and mitigate possible risks.

High-Performance Operational and Instrumentation Amplifiers

NARCIS (Netherlands)

Shahi, B.

2015-01-01

This thesis describes techniques to reduce the offset error in precision instrumentation and operational amplifiers. The offset error which is considered a major error source associated with gain blocks, together with other errors are reviewed. Conventional and newer approaches to remove offset and

Design, development, and testing of the DCT Cassegrain instrument support assembly

Science.gov (United States)

Bida, Thomas A.; Dunham, Edward W.; Nye, Ralph A.; Chylek, Tomas; Oliver, Richard C.

2012-09-01

The 4.3m Discovery Channel Telescope delivers an f/6.1 unvignetted 0.5° field to its RC focal plane. In order to support guiding, wavefront sensing, and instrument installations, a Cassegrain instrument support assembly has been developed which includes a facility guider and wavefront sensor package (GWAVES) and multiple interfaces for instrumentation. A 2-element, all-spherical, fused-silica corrector compensates for field curvature and astigmatism over the 0.5° FOV, while reducing ghost pupil reflections to minimal levels. Dual roving GWAVES camera probes pick off stars in the outer annulus of the corrected field, providing simultaneous guiding and wavefront sensing for telescope operations. The instrument cube supports 5 co-mounted instruments with rapid feed selection via deployable fold mirrors. The corrected beam passes through a dual filter wheel before imaging with the 6K x 6K single CCD of the Large Monolithic Imager (LMI). We describe key development strategies for the DCT Cassegrain instrument assembly and GWAVES, including construction of a prime focus test assembly with wavefront sensor utilized in fall 2011 to begin characterization of the DCT primary mirror support. We also report on 2012 on-sky test results of wavefront sensing, guiding, and imaging with the integrated Cassegrain cube.

The VUV instrument SPICE for Solar Orbiter: performance ground testing

Science.gov (United States)

Caldwell, Martin E.; Morris, Nigel; Griffin, Douglas K.; Eccleston, Paul; Anderson, Mark; Pastor Santos, Carmen; Bruzzi, Davide; Tustain, Samuel; Howe, Chris; Davenne, Jenny; Grundy, Timothy; Speight, Roisin; Sidher, Sunil D.; Giunta, Alessandra; Fludra, Andrzej; Philippon, Anne; Auchere, Frederic; Hassler, Don; Davila, Joseph M.; Thompson, William T.; Schuehle, Udo H.; Meining, Stefan; Walls, Buddy; Phelan, P.; Dunn, Greg; Klein, Roman M.; Reichel, Thomas; Gyo, Manfred; Munro, Grant J.; Holmes, William; Doyle, Peter

2017-08-01

SPICE is an imaging spectrometer operating at vacuum ultraviolet (VUV) wavelengths, 70.4 - 79.0 nm and 97.3 - 104.9 nm. It is a facility instrument on the Solar Orbiter mission, which carries 10 science instruments in all, to make observations of the Sun's atmosphere and heliosphere, at close proximity to the Sun, i.e to 0.28 A.U. at perihelion. SPICE's role is to make VUV measurements of plasma in the solar atmosphere. SPICE is designed to achieve spectral imaging at spectral resolution >1500, spatial resolution of several arcsec, and two-dimensional FOV of 11 x16arcmins. The many strong constraints on the instrument design imposed by the mission requirements prevent the imaging performance from exceeding those of previous instruments, but by being closer to the sun there is a gain in spatial resolution. The price which is paid is the harsher environment, particularly thermal. This leads to some novel features in the design, which needed to be proven by ground test programs. These include a dichroic solar-transmitting primary mirror to dump the solar heat, a high in-flight temperature (60deg.C) and gradients in the optics box, and a bespoke variable-line-spacing grating to minimise the number of reflective components used. The tests culminate in the systemlevel test of VUV imaging performance and pointing stability. We will describe how our dedicated facility with heritage from previous solar instruments, is used to make these tests, and show the results, firstly on the Engineering Model of the optics unit, and more recently on the Flight Model. For the keywords, select up to 8 key terms for a search on your manuscript's subject.

Technological considerations in emergency instrumentation preparedness. Phase II-D. Evaluation testing and calibration methodology for emergency radiological instrumentation

International Nuclear Information System (INIS)

Bramson, P.E.; Andersen, B.V.; Fleming, D.M.; Kathren, R.L.; Mulhern, O.R.; Newton, C.E.; Oscarson, E.E.; Selby, J.M.

1976-09-01

In response to recommendations from the Advisory Committee on Reactor Safeguards, the Division of Operational Safety, U.S. ERDA has contracted with Battelle, Pacific Northwest Laboratories to survey the adequacy of existing instrumentation at nuclear fuel cycle facilities to meet emergency requirements and to develop technical criteria for instrumentation systems to be used in assessment of environmental conditions following plant emergencies. This report, the fifth in a series, provides: (1) calibration methods to assure the quality of radiological measurements and (2) testing procedures for determining whether an emergency radiological instrument meets the performance specifications. Three previous reports in this series identified the emergency instrumentation needs for power reactors, mixed oxide fuel plants, and fuel reprocessing facilities. Each of these three reports contains a Section VI, which sets forth applicable radiological instrument performance criteria and calibration requirements. Testing and calibration procedures in this report have been formatted in two parts: IV and V, each divided into three subsections: (1) Power Reactors, (2) Mixed Oxide Fuel Plants, and (3) Fuel Reprocessing Facilities. The three performance criteria subsections directly coincide with the performance criteria sections of the previous reports. These performance criteria sections have been reproduced in this report as Part III with references of ''required action'' added

Operability test procedure for 211BA flow proportional sampler

International Nuclear Information System (INIS)

Weissenfels, R.D.

1994-01-01

The purpose of this operability test procedure (OTP) is to verify the 211-BA flow proportional sampler system and components function correctly as intended by design. System test will include the sampling system, all associated instrumentation, and Facility Process Monitor and Control System (FPMCS). The combined chemical sewer stream from B Plant flows through sump 211BA-SMP-01 located in 211-BA and is continuously monitored for gamma and beta radiation and pH. 211-BA has been upgraded to include a flow proportional sampler. A specified sample volume will be withdrawn at programmed intervals from the 211BA sump and deposited in a 19 liter plastic carboy. The sampler will be programmed per the vendor installation and operations manual by B Plant instrument maintenance personnel. Samples will be taken during five consecutive sample cycles with the sample volumes and sample frequencies recorded for comparison purposes. Additional tests related to the sampler include the alarm circuitry for loss of power and failure to obtain sample

Military Publications, Index of Test Operations Procedures

Science.gov (United States)

1981-10-01

serial number, aad design information for majur components. Prescribes vehicle, major component, and system descrip- tive elements required; such as...mount operating characteristics. Discusses preparation for test, instrumentation, and facil- ities. Describes procedures for force measurement, carriage...backlash and accuracy, turret friction, gun balance, manual handcrank force , manual response ratio, weapon and sighting system backlash, power controller

Operating experience with LAMPF main beam lines instrumentation and control system

International Nuclear Information System (INIS)

van Dyck, O.B.; Harvey, A.; Howard, H.H.; Roeder, D.L.

1975-01-01

Instrumentation and control (I and C) for the Los Alamos Clinton P. Anderson Meson Physics Facility (LAMPF) main beam line is based upon central computer control through remote stations which provide input and output to most devices. Operating experience shows that the ability of the computer to give high-quality graphical presentation of the measurements enhances operator performance and instrument usefulness. Experience also shows that operator efficiency degrades rapidly with increasing instrument response time, that is, with increasing delay between the time a control is changed and the result can be observed. For this reason, instrumentation upgrade includes speeding up data acquisition and display times to under 10 s. Similarly, television-viewed phosphors are being retained where possible since their instantaneous response is very useful. Other upgrading of the instrumentation system is planned to improve data accuracy, reliability, redundancy, and instrument radiation tolerance. Past experience is being applied in adding or relocating devices to simplify tuning procedures. (U.S.)

Design and operation of dust measuring instrumentation based on the beta-radiation method

International Nuclear Information System (INIS)

Lilienfeld, P.

1975-01-01

The theory, instrument design aspects and applications of beta-radiation attenuation for the measurement of the mass concentration of airborne particulates are reviewed. Applicable methods of particle collection, beta sensing configurations, source ( 63 Ni, 14 C, 147 Pr, 85 Kr) and detector design criteria, electronic signal processing, digital control and instrument programming techniques are treated. Advantages, limitations and error sources of beta-attenuation instrumentation are analyzed. Applications to industrial dust measurements, source testing, ambient monitoring, and particle size analysis are the major areas of practical utilization of this technique, and its inherent capability for automated and unattended operation provides compatibility with process control synchronization and alarm, telemetry, and incorporation into pollution monitoring network sensing stations. (orig.) [de

The test beamline of the European Spallation Source – Instrumentation development and wavelength frame multiplication

International Nuclear Information System (INIS)

Woracek, R.; Hofmann, T.; Bulat, M.; Sales, M.; Habicht, K.; Andersen, K.; Strobl, M.

2016-01-01

The European Spallation Source (ESS), scheduled to start operation in 2020, is aiming to deliver the most intense neutron beams for experimental research of any facility worldwide. Its long pulse time structure implies significant differences for instrumentation compared to other spallation sources which, in contrast, are all providing short neutron pulses. In order to enable the development of methods and technology adapted to this novel type of source well in advance of the first instruments being constructed at ESS, a test beamline (TBL) was designed and built at the BER II research reactor at Helmholtz-Zentrum Berlin (HZB). Operating the TBL shall provide valuable experience in order to allow for a smooth start of operations at ESS. The beamline is capable of mimicking the ESS pulse structure by a double chopper system and provides variable wavelength resolution as low as 0.5% over a wide wavelength band between 1.6 Å and 10 Å by a dedicated wavelength frame multiplication (WFM) chopper system. WFM is proposed for several ESS instruments to allow for flexible time-of-flight resolution. Hence, ESS will benefit from the TBL which offers unique possibilities for testing methods and components. This article describes the main capabilities of the instrument, its performance as experimentally verified during the commissioning, and its relevance to currently starting ESS instrumentation projects.

The test beamline of the European Spallation Source – Instrumentation development and wavelength frame multiplication

Energy Technology Data Exchange (ETDEWEB)

Woracek, R., E-mail: robin.woracek@esss.se [European Spallation Source ESS ERIC, P.O. Box 176, SE-22100 Lund (Sweden); Hofmann, T.; Bulat, M. [Helmholtz-Zentrum Berlin für Materialien und Energie, Hahn-Meitner Platz 1, 14109 Berlin (Germany); Sales, M. [Technical University of Denmark, Fysikvej, 2800 Kgs. Lyngby (Denmark); Habicht, K. [Helmholtz-Zentrum Berlin für Materialien und Energie, Hahn-Meitner Platz 1, 14109 Berlin (Germany); Andersen, K. [European Spallation Source ESS ERIC, P.O. Box 176, SE-22100 Lund (Sweden); Strobl, M. [European Spallation Source ESS ERIC, P.O. Box 176, SE-22100 Lund (Sweden); Technical University of Denmark, Fysikvej, 2800 Kgs. Lyngby (Denmark)

2016-12-11

The European Spallation Source (ESS), scheduled to start operation in 2020, is aiming to deliver the most intense neutron beams for experimental research of any facility worldwide. Its long pulse time structure implies significant differences for instrumentation compared to other spallation sources which, in contrast, are all providing short neutron pulses. In order to enable the development of methods and technology adapted to this novel type of source well in advance of the first instruments being constructed at ESS, a test beamline (TBL) was designed and built at the BER II research reactor at Helmholtz-Zentrum Berlin (HZB). Operating the TBL shall provide valuable experience in order to allow for a smooth start of operations at ESS. The beamline is capable of mimicking the ESS pulse structure by a double chopper system and provides variable wavelength resolution as low as 0.5% over a wide wavelength band between 1.6 Å and 10 Å by a dedicated wavelength frame multiplication (WFM) chopper system. WFM is proposed for several ESS instruments to allow for flexible time-of-flight resolution. Hence, ESS will benefit from the TBL which offers unique possibilities for testing methods and components. This article describes the main capabilities of the instrument, its performance as experimentally verified during the commissioning, and its relevance to currently starting ESS instrumentation projects.

The GLAST LAT Instrument Science Operations Center

International Nuclear Information System (INIS)

Cameron, Robert A.; SLAC

2007-01-01

The Gamma-ray Large Area Space Telescope (GLAST) is scheduled for launch in late 2007. Operations support and science data processing for the Large Area Telescope (LAT) instrument on GLAST will be provided by the LAT Instrument Science Operations Center (ISOC) at the Stanford Linear Accelerator Center (SLAC). The ISOC supports GLAST mission operations in conjunction with other GLAST mission ground system elements and supports the research activities of the LAT scientific collaboration. The ISOC will be responsible for monitoring the health and safety of the LAT, preparing command loads for the LAT, maintaining embedded flight software which controls the LAT detector and data acquisition flight hardware, maintaining the operating configuration of the LAT and its calibration, and applying event reconstruction processing to down-linked LAT data to recover information about detected gamma-ray photons. The SLAC computer farm will be used to process LAT event data and generate science products, to be made available to the LAT collaboration through the ISOC and to the broader scientific community through the GLAST Science Support Center at NASA/GSFC. ISOC science operations will optimize the performance of the LAT and oversee automated science processing of LAT data to detect and monitor transient gamma-ray sources

Choreographer Pre-Testing Code Analysis and Operational Testing.

Energy Technology Data Exchange (ETDEWEB)

Fritz, David J. [Sandia National Laboratories (SNL-CA), Livermore, CA (United States); Harrison, Christopher B. [Sandia National Laboratories (SNL-CA), Livermore, CA (United States); Perr, C. W. [Sandia National Laboratories (SNL-CA), Livermore, CA (United States); Hurd, Steven A [Sandia National Laboratories (SNL-CA), Livermore, CA (United States)

2014-07-01

Choreographer is a "moving target defense system", designed to protect against attacks aimed at IP addresses without corresponding domain name system (DNS) lookups. It coordinates actions between a DNS server and a Network Address Translation (NAT) device to regularly change which publicly available IP addresses' traffic will be routed to the protected device versus routed to a honeypot. More details about how Choreographer operates can be found in Section 2: Introducing Choreographer. Operational considerations for the successful deployment of Choreographer can be found in Section 3. The Testing & Evaluation (T&E) for Choreographer involved 3 phases: Pre-testing, Code Analysis, and Operational Testing. Pre-testing, described in Section 4, involved installing and configuring an instance of Choreographer and verifying it would operate as expected for a simple use case. Our findings were that it was simple and straightforward to prepare a system for a Choreographer installation as well as configure Choreographer to work in a representative environment. Code Analysis, described in Section 5, consisted of running a static code analyzer (HP Fortify) and conducting dynamic analysis tests using the Valgrind instrumentation framework. Choreographer performed well, such that only a few errors that might possibly be problematic in a given operating situation were identified. Operational Testing, described in Section 6, involved operating Choreographer in a representative environment created through Emulytics^TM . Depending upon the amount of server resources dedicated to Choreographer vis-á-vis the amount of client traffic handled, Choreographer had varying degrees of operational success. In an environment with a poorly resourced Choreographer server and as few as 50-100 clients, Choreographer failed to properly route traffic over half the time. Yet, with a well-resourced server, Choreographer handled over 1000 clients without missrouting. Choreographer

Environmental Testing for Precision Parts and Instruments

International Nuclear Information System (INIS)

Choi, Man Yong; Park, Jeong Hak; Yun, Kyu Tek

2001-01-01

Precision parts and instruments are tested to evaluate performance in development-process and product-step to prement a potential defect due to a failure design. In this paper, Environmental test technology, which is the basis of reliability analysis, is introduced with examples of test criterion, test method for products, encoder and traffic signal controller, and measuring instruments. Recently, as the importance of the environmental test technology is recognised. It is proposed that training of test technician and technology of jig design and failure analysis are very essential

Development of Multichannel Eddy Current Testing Instrument

International Nuclear Information System (INIS)

Lee, Hee Jong; Cho, Chan Hee; Nam, Min Woo; Yoon, Byung Sik; Yoo, Hyun Joo

2010-01-01

Four main techniques of electromagnetic testing are used for commercial applications: eddy current testing, alternating current field testing, magnetic flux leakage testing and remote field testing. Eddy current testing is a nondestructive evaluation method, which makes eddy current flow on a specimen by applying driving pulse to eddy current probe coil, by using eddy current testing device, and makes the change of eddy current which is dependently caused by flaws, material characteristics, testing condition, receiving through eddy current, and analyzes material properties, flaws, status on the specimen. Application of EC instrumentation varies widely in industry from the identification of metal heat treatment to the inspection of steam generator tubing in nuclear power plants. In this study, we have designed multichannel EC instrument which can be applicable to the NDE of the tube in heat exchanger for electric power facility, chemistry, and military industry, and finally confirmed the proper function of EC instrumentation

Generation of on-line test signals for nuclear instrumentation for PFBR

International Nuclear Information System (INIS)

Ram, Rajit; Bhatnagar, P.V.; Rajesh, M.G.; Das, Debashis

2010-01-01

Neutron flux monitoring system for PFBR employs pulse signal processing in start up and intermediate power range of reactor operation and Campbell signal processing in intermediate and full power range of reactor operation. Pulse signal processing unit as well as Campbell signal processing unit incorporates FPGA that generates pulse/white noise signal for on-line testing and diagnostic of the channels. In pulse channel fixed/linearly/exponentially varying pulse rate signal is generated over three decades of reactor operation. In the Campbell channel, Poisson distributed noise varying linearly/exponentially is generated over four decades of reactor operation. Multiple numbers of Poisson distributed random pulse trains are summed and amplified to get the white noise signal. Exponentially increasing gain pattern, generated by MATLAB is used to increase the RMS value of the generated noise. The paper discuses the successful testing and validation of pulse and Campbell channel by making use of the generated pulse/white noise signal over wide range of operation for nuclear instrumentation. (author)

A CNES remote operations center for the MSL ChemCam instrument

Energy Technology Data Exchange (ETDEWEB)

Wiens, Roger C [Los Alamos National Laboratory; Lafaille, Vivian [CNES; Lorgny, Eric [CNES; Baroukh, Julien [CNES; Gaboriaud, Alain [CNES; Saccoccio, Muriel [CNES; Perez, Rene [CNES; Gasnault, Olivier [CNRS/CESR; Maurice, Sylvestre [CNRS/CESR; Blaney, Diana [JPL

2010-01-01

For the first time, a CNES remote operations center in Toulouse will be involved in the tactical operations of a Martian rover in order to operate the ChemCam science instrument in the framework of the NASA MSL (Mars Science Laboratory) mission in 2012. CNES/CESR and LANL have developed and delivered to JPL the ChemCam (Chemistry Camera) instrument located on the top of mast and in the body of the rover. This instrument incorporates a Laser-Induced Breakdown Spectrometer (LIBS) and a Remote Micro-Imager (RMI) for determining elemental compositions of rock targets or soil samples at remote distances from the rover (2-7 m). An agreement has been achieved for operating ChemCam, alternatively, from Toulouse (FR) and Los Alamos (NM, USA), through the JPL ground data system in Pasadena (CA, USA) for a complete Martian year (2 years on Earth). After a brief overview of the MSL mission, this paper presents the instrument, the mission operational system and JPL organization requirements for the scientific investigators (PI and Co-Is). This paper emphasizes innovations applied on the ground segment components and on the operational approach to satisfy the requirements and constraints due to these shared and distributed operations over the world.

Magnetospheric Multiscale Instrument Suite Operations and Data System

Science.gov (United States)

Baker, D. N.; Riesberg, L.; Pankratz, C. K.; Panneton, R. S.; Giles, B. L.; Wilder, F. D.; Ergun, R. E.

2016-03-01

The four Magnetospheric Multiscale (MMS) spacecraft will collect a combined volume of ˜100 gigabits per day of particle and field data. On average, only 4 gigabits of that volume can be transmitted to the ground. To maximize the scientific value of each transmitted data segment, MMS has developed the Science Operations Center (SOC) to manage science operations, instrument operations, and selection, downlink, distribution, and archiving of MMS science data sets. The SOC is managed by the Laboratory for Atmospheric and Space Physics (LASP) in Boulder, Colorado and serves as the primary point of contact for community participation in the mission. MMS instrument teams conduct their operations through the SOC, and utilize the SOC's Science Data Center (SDC) for data management and distribution. The SOC provides a single mission data archive for the housekeeping and science data, calibration data, ephemerides, attitude and other ancillary data needed to support the scientific use and interpretation. All levels of data products will reside at and be publicly disseminated from the SDC. Documentation and metadata describing data products, algorithms, instrument calibrations, validation, and data quality will be provided. Arguably, the most important innovation developed by the SOC is the MMS burst data management and selection system. With nested automation and "Scientist-in-the-Loop" (SITL) processes, these systems are designed to maximize the value of the burst data by prioritizing the data segments selected for transmission to the ground. This paper describes the MMS science operations approach, processes and data systems, including the burst system and the SITL concept.

Automated systems help prevent operator error during [reactor] I and C [instrumentation and control] testing

International Nuclear Information System (INIS)

Courcoux, R.

1989-01-01

On a nuclear steam supply system, even a minor failure can involve actuation of the whole reactor protection system (RPS). To reduce the likelihood of human error leading to unwanted trips during the maintenance of instrumentation and control systems, Framatome has been developing and installing various automated testing systems. Such automated systems are particularly helpful when periodic tests with a potential for RPS actuation have to be carried out, or when the test is on the critical path for the refuelling outage. The Sensitive Channel Programme described is an example of the sort of work that has been done. (author)

Learning to inhibit the response during instrumental (operant) extinction.

Science.gov (United States)

Bouton, Mark E; Trask, Sydney; Carranza-Jasso, Rodrigo

2016-07-01

Five experiments tested implications of the idea that instrumental (operant) extinction involves learning to inhibit the learned response. All experiments used a discriminated operant procedure in which rats were reinforced for lever pressing or chain pulling in the presence of a discriminative stimulus (S), but not in its absence. In Experiment 1, extinction of the response (R) in the presence of S weakened responding in S, but equivalent nonreinforced exposure to S (without the opportunity to make R) did not. Experiment 2 replicated that result and found that extinction of R had no effect on a different R that had also been reinforced in the stimulus. In Experiments 3 and 4, rats first learned to perform several different stimulus and response combinations (S1R1, S2R1, S3R2, and S4R2). Extinction of a response in one stimulus (i.e., S1R1) transferred and weakened the same response, but not a different response, when it was tested in another stimulus (i.e., S2R1 but not S3R2). In Experiment 5, extinction still transferred between S1 and S2 when the stimuli set the occasion for R's association with different types of food pellets. The results confirm the importance of response inhibition in instrumental extinction: Nonreinforcement of the response in S causes the most effective suppression of responding, and response suppression is specific to the response but transfers and influences performance of the same response when it is occasioned by other stimuli. Theoretical and practical implications are discussed. (PsycINFO Database Record (c) 2016 APA, all rights reserved).

Learning to inhibit the response during instrumental (operant) extinction

Science.gov (United States)

Bouton, Mark E.; Trask, Sydney; Carranza-Jasso, Rodrigo

2016-01-01

Five experiments tested implications of the idea that instrumental (operant) extinction involves learning to inhibit the learned response. All experiments used a discriminated operant procedure in which rats were reinforced for lever pressing or chain pulling in the presence of a discriminative stimulus (S), but not in its absence. In Experiment 1, extinction of the response (R) in the presence of S weakened responding in S, but equivalent nonreinforced exposure to S (without the opportunity to make R) did not. Experiment 2 replicated that result and found that extinction of R had no effect on a different R that had also been reinforced in the stimulus. In Experiments 3 and 4, rats first learned to perform several different stimulus and response combinations (S1R1, S2R1, S3R2, and S4R2). Extinction of a response in one stimulus (i.e., S1R1) transferred and weakened the same response, but not a different response, when it was tested in another stimulus (i.e., S2R1 but not S3R2). In Experiment 5, extinction still transferred between S1 and S2 when the stimuli set the occasion for R's association with different types of food pellets. The results confirm the importance of response inhibition in instrumental extinction: Nonreinforcement of the response in S causes the most effective suppression of responding, and response suppression is specific to the response but transfers and influences performance of the same response when it is occasioned by other stimuli. Theoretical and practical implications are discussed. PMID:27379715

Total dose tests for the PROMICS-3 instrument

International Nuclear Information System (INIS)

Verkasalo, R.

1991-01-01

The sensitivity of some analog and digital integrated circuits (IC's) to ionizing radiation was tested in order to evaluate their potential usefulness especially in the PROMICS-3 instrument. The PROMICS-3 is a plasma instrument to be flown on the Russian Interball satellites. The radiation tolerance requirement of the auroral Interball satellite is about 45 krad/year inside a shielding of 4 mm Aluminium. The IC's tested were: AD571 A/D- converter, ADDAC80 D/A-converter, LF442A and PM108A operational amplifiers, MPREF0l voltage reference, STC SPXO 6 MHZ oscillator,4N55 optocoupler, MC5lC98 and CY7C164 16k*4 static CMOS RAM. Co-60 was used as the irradiation source. The test methods and results are described in the paper. The RAM-circuits failed between 10 and 20 krad. D/A- and A/D-converters degraded only slightly after 100 krad, but one of the A/D-converters failed functionally at 190 krad. The LF442A began to degrade in the test connection at 100 krad, and PM108A at 30 krad. The output voltage of the voltage reference MPREF01 increased about 20 mV after 100 krad. No change was observed in the output frequency of the STC SPXD oscillator even after 300 krad. The current tansfer ratio of the 4N55 decreased continuously to about 75 % of the initial value after 100 krad

Instrumentation and test gear circuits manual

CERN Document Server

Marston, R M

2013-01-01

Instrumentation and Test Gear Circuits Manual provides diagrams, graphs, tables, and discussions of several types of practical circuits. The practical circuits covered in this book include attenuators, bridges, scope trace doublers, timebases, and digital frequency meters. Chapter 1 discusses the basic instrumentation and test gear principles. Chapter 2 deals with the design of passive attenuators, and Chapter 3 with passive and active filter circuits. The subsequent chapters tackle 'bridge' circuits, analogue and digital metering techniques and circuitry, signal and waveform generation, and p

Development status of irradiation devices and instrumentation for material and nuclear fuel irradiation tests in HANARO

Energy Technology Data Exchange (ETDEWEB)

Kim, Bong Goo; Sohn, Jae Min; Choo, Kee Nam [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2010-04-15

The High flux Advanced Neutron Application ReactOr (HANARO), an open-tank-in-pool type reactor, is one of the multi-purpose research reactors in the world. Since the commencement of HANARO's operations in 1995, a significant number of experimental facilities have been developed and installed at HANARO, and continued efforts to develop more facilities are in progress. Owing to the stable operation of the reactor and its frequent utilization, more experimental facilities are being continuously added to satisfy various fields of study and diverse applications. The irradiation testing equipment for nuclear fuels and materials at HANARO can be classified into capsules and the Fuel Test Loop (FTL). Capsules for irradiation tests of nuclear fuels in HANARO have been developed for use under the dry conditions of the coolant and materials at HANARO and are now successfully utilized to perform irradiation tests. The FTL can be used to conduct irradiation testing of a nuclear fuel under the operating conditions of commercial nuclear power plants. During irradiation tests conducted using these capsules in HANARO, instruments such as the thermocouple, Linear Variable Differential Transformer (LVDT), small heater, Fluence Monitor (F/M) and Self-Powered Neutron Detector (SPND) are used to measure various characteristics of the nuclear fuel and irradiated material. This paper describes not only the status of HANARO and the status and perspective of irradiation devices and instrumentation for carrying out nuclear fuel and material tests in HANARO but also some results from instrumentation during irradiation tests

Millimeter-wave Instrumentation Test Facility

Data.gov (United States)

Federal Laboratory Consortium — The Millimeter-wave Instrumentation Test Facility conducts basic research in propagation phenomena, remote sensing, and target signatures. The facility has a breadth...

ITER TASK T252 (1995):Gamma radiation testing of a GaAs operational amplifier for instrument applications

International Nuclear Information System (INIS)

Hiemstra, D.

1996-03-01

The purpose of this 1995 ITER task was : to build an improved operational amplifier using GaAs MESFET technology, to build a reference voltage subcircuit using GaAs MESFET technology and to investigate the potential of GaAs HBT's to improve the noise performance of the GaAs MESFET operational amplifier. This work addresses the need for instrumentation-grade components to read sensors in an experimental fusion reactor, where the anticipated total dose for a useful service life is 3Grad(GaAs). It is an extension of our 1994 work. 3 tabs., 6 figs

Strategy for improving instrumentation and control in operating nuclear power plants

International Nuclear Information System (INIS)

Abad Bassols, L.; Nino Perote, R.

1996-01-01

There are three basic reasons why nuclear power plants need to systematically upgrade their instrumentation and control equipment: Obsolete instrumentation and lack spares Little capacity of flexibility for extension Possibility of attaining better systems integration and improving systems-operations interface This article shows how to approach these issues using the following strategies: Use of distributed control systems and PLCs for control, signalling, command, communications, etc, in both nuclear and conventional applications Upgrading of process instrumentation equipment, sensors, transmitters, etc Upgrading of alarm-signalling systems In each group of equipment items consideration should be given to: Aspects regarding manufacturers-suppliers Effects on design, adaptation and documentation of operating plants Effects on the training and handling skills of operation and maintenance staff Strategy for incorporating the new system into the Plant with minimum impact on operation (Author)

Virtual Sensor Test Instrumentation, Phase II

Data.gov (United States)

National Aeronautics and Space Administration — Mobitrum has started the development of virtual sensor test instrumentation in Phase I for characterization and measurement of ground testing of propulsion systems....

Vibration test report on the instrumented capsule for fuel irradiation test

Energy Technology Data Exchange (ETDEWEB)

Ryu, Jeong Soo; Yoon, D. B.; Wu, J. S.; Oh, J. M.; Park, S. J.; Cho, M. S.; Kim, B. G.; Kang, Y. W

2003-01-01

The fluid-induced vibration level of instrumented capsule, which was manufactured for fuel irradiation test at the reactor core of HANARO, was investigated. For this purpose, the instrumented capsule was loaded at the OR site of the HANARO design verification test facility that could simulate identical flow condition as the HANARO core. Then, vibration signals of the instrumented capsule subjected to various flow conditions were measured by using vibration sensors. In time domain analysis, maximum amplitudes and RMS values of the measured acceleration and displacement signals were obtained. By using frequency domain analysis, frequency components of the fluid-induced vibration were analyzed. In addition, natural frequencies of the instrumented capsule were obtained by performing modal test. The frequency analysis results showed that the natural frequency components near 7.5Hz and 17.5Hz were dominant in the fluid-induced vibration signal. The maximum amplitude of the accelerations was measured as 12.04m/s{sup 2} that is within the allowable vibrational limit(18.99m/s{sup 2})of the reactor structure. Also, the maximum displacement amplitude was calculated as 0.191mm. Since these vibration levels are remarkably low, excessive vibration is not expected when the irradiation test of the instrumented capsule is performed at the HANARO core.

Field instrumentation and testing needs for a high level waste repository

International Nuclear Information System (INIS)

Marti, J.; Maini, T.

1981-03-01

A review has been conducted of the testing and measurement needs posed by a deep geologic High Level Waste (HLW) repository in crystalline or argillaceous rocks. Siting, design, construction, operation and decommissioning of the repository have been covered, together with the planning of a Test and Demonstration Facility. Instruments and methods available have been critically assessed in their ability to fulfil the aforementioned testing and monitoring programmes. Special attention has been paid to the relation of measurements to the data needs and to the tests likely to generate such data. This assessment has concentrated on measurements of absolute rock stresses, monitoring of changes in rock stress, evaluation of the rock mass deformability, measurement of relative displacements and determination of the hydrogeologic parameters of the rock mass. Other measurements have been studied with a lesser degree of attention. The overall conclusion is that, from the instrumentation and testing points of view, present plans for a test and demonstration facility in the early nineties and a repository soon after 2000 are indeed feasible. Specific conclusions on the state-of-the-art and development needs are presented in the report. (author)

Standards for radiation protection instrumentation: design of safety standards and testing procedures

International Nuclear Information System (INIS)

Meissner, Frank

2008-01-01

This paper describes by means of examples the role of safety standards for radiation protection and the testing and qualification procedures. The development and qualification of radiation protection instrumentation is a significant part of the work of TUV NORD SysTec, an independent expert organisation in Germany. The German Nuclear Safety Standards Commission (KTA) establishes regulations in the field of nuclear safety. The examples presented may be of importance for governments and nuclear safety authorities, for nuclear operators and for manufacturers worldwide. They demonstrate the advantage of standards in the design of radiation protection instrumentation for new power plants, in the upgrade of existing instrumentation to nuclear safety standards or in the application of safety standards to newly developed equipment. Furthermore, they show how authorities may proceed when safety standards for radiation protection instrumentation are not yet established or require actualization. (author)

Instrumentation of the thermal/structural interactions in situ tests at the Waste Isolation Pilot Plant (WIPP)

Energy Technology Data Exchange (ETDEWEB)

Munson, D.E. [Sandia National Labs., Albuquerque, NM (United States). Repository Isolation Systems Div.; Hoag, D.L.; Blankenship, D.A.; DeYonge, W.F.; Schiermeister, D.M. [RE/SPEC, Inc., Albuquerque, NM (United States); Jones, R.L.; Baird, G.T. [Tech Reps, Inc., Albuquerque, NM (United States)

1997-04-01

The Department of Energy has constructed the Waste Isolation Pilot Plant (WIPP) to develop the technology for the disposal of radioactive waste from defense programs. Sandia National Laboratories had the responsibility for the experimental activities at the WIPP and fielded several large-scale Thermal/Structural Interactions (TSI) in situ tests to validate techniques used to predict repository performance. The instrumentation of these tests involved the placement of over 4,200 gages including room closure gages, borehole extensometers, stress gages, borehole inclinometers, fixed reference gages, borehole strain gages, thermocouples, thermal flux meters, heater power gages, environmental gages, and ventilation gages. Most of the gages were remotely read instruments that were monitored by an automated data acquisition system, but manually read instruments were also used to provide early deformation information and to provide a redundancy of measurement for the remote gages. Instruments were selected that could operate in the harsh environment of the test rooms and that could accommodate the ranges of test room responses predicted by pretest calculations. Instruments were tested in the field prior to installation at the WIPP site and were modified to improve their performance. Other modifications were made to gages as the TSI tests progressed using knowledge gained from test maintenance. Quality assurance procedures were developed for all aspects of instrumentation including calibration, installation, and maintenance. The instrumentation performed exceptionally well and has produced a large quantity of quality information.

Instrumentation of the thermal/structural interactions in situ tests at the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Munson, D.E.; Jones, R.L.; Baird, G.T.

1997-04-01

The Department of Energy has constructed the Waste Isolation Pilot Plant (WIPP) to develop the technology for the disposal of radioactive waste from defense programs. Sandia National Laboratories had the responsibility for the experimental activities at the WIPP and fielded several large-scale Thermal/Structural Interactions (TSI) in situ tests to validate techniques used to predict repository performance. The instrumentation of these tests involved the placement of over 4,200 gages including room closure gages, borehole extensometers, stress gages, borehole inclinometers, fixed reference gages, borehole strain gages, thermocouples, thermal flux meters, heater power gages, environmental gages, and ventilation gages. Most of the gages were remotely read instruments that were monitored by an automated data acquisition system, but manually read instruments were also used to provide early deformation information and to provide a redundancy of measurement for the remote gages. Instruments were selected that could operate in the harsh environment of the test rooms and that could accommodate the ranges of test room responses predicted by pretest calculations. Instruments were tested in the field prior to installation at the WIPP site and were modified to improve their performance. Other modifications were made to gages as the TSI tests progressed using knowledge gained from test maintenance. Quality assurance procedures were developed for all aspects of instrumentation including calibration, installation, and maintenance. The instrumentation performed exceptionally well and has produced a large quantity of quality information

EPRI flow-loop/in situ test program for motor-operated valves

International Nuclear Information System (INIS)

Hosler, J.F.; Dorfman, L.S.

1994-01-01

The Electric Power Research Institute is undertaking a comprehensive research program to develop and validate methods for predicting the performance of common motor-operated gate, global, and butterfly valves. To assess motor-operated valve (MOV) performance characteristics and provide a basis for methods validation, full-scale testing was conducted on 62 MOVs. Tests were performed in four flow-loop facilities and in nine nuclear units. Forty-seven gate, five globe, and 10 butterfly valves were tested under a wide range of flow and differential pressure conditions. The paper describes the test program scope, test configurations, instrumentation and data acquisition, testing approach, and data analysis methods. Key results are summarized

Performance specifications for health physics instrumentation: portable instrumentation for use in normal work environments. Part 2. Test results

International Nuclear Information System (INIS)

Kenoyer, J.L.; Swinth, K.L.; Stoetzel, G.A.; Selby, J.M.

1986-09-01

The Pacific Northwest Laboratory evaluated a draft American National Standards Institute Standard N42.17 (ANSI N42.17) on performance specifications for health physics instrumentation through a project jointly funded by the US Department of Energy and the US Nuclear Regulatory Commission. The evaluation involved testing a representative cross section of instruments against criteria in the standard. This report presents results of the testing program. A brief history of the project is included in the introduction. The instrumentation tested is described in general terms (i.e., types, ranges); however, no direct relationship between the results and a specific instrument model is made in this report. Testing requirements in ANSI N42.17D4, Revision 1 (May 1985) are summarized and the methods by which the tests are performed are discussed. Brief descriptions of the testing equipment are included in the methods section of the report. More detailed information about the draft standard, testing requirements and procedures, and the test equipment is included in ''Performance Specifications for Health Physics Instrumentation - Portable Instrumentation for Use in Normal Work Environments, Part 1: Manual of Testing Procedures.'' Results of testing are given in two formats: test-by-test and instrument-by-instrument. Discussion is included on significant and interesting findings, on comparisons of results from the same type of instruments from same and different manufacturers, and on data grouped by manufacturer. Conclusions are made on the applicability and practicality of the proposed standard and on instrument performance. Changes that have been made to the proposed standard based on findings of the testing program are listed and discussed. 22 refs., 11 figs., 77 tabs

Instrumentation and operational plan for geokinetics retort No. 22

Energy Technology Data Exchange (ETDEWEB)

Parrish, R.L.; Hommert, P.J.

1980-04-01

This report outlines the general plan for the instrumentation and technical direction of a horizontal in siti retorting experiment to be conducted at the Geokinetics, Inc. field site in Uintah County, Utah. Bed preparation has been accomplished by Geokinetics by blasting the retort zone with explosives emplaced in wells drilled from the surface. Downhole instrumentation will consist of approx. 300 thermocouples and 28 combustion gas sampling ports to monitor the movement of the reaction front during the retorting process. Surface instrumentation will provide measurements of flow rates, gas composition, liquid products and other process parameters to monitor the overall operation of the process. The operational plan includes provision for data interpretation and real time material balance calculations in the field, including an evaluation of the effect on processing rates and oil yield due to the use of recycled combusted off gases and changes in rate of injection of inlet gases.

Welding of sule elements for nuclear reactors with solid state YAG laser using instrumentated testing equipments

International Nuclear Information System (INIS)

Bourgault, F.; Lacoste, J.; Schley, R.; Kluzinski, C.; Piednoir, P.

1985-09-01

The instrumentation of the equipment for carrying out safety tests on fuel elements for nuclear reactors requires special thermocouples adapted to the prevailing agressive medium. The investigations described deal essentially with the operational and metallurgical weldability tests out on the safety test zircaloy piping in the pressurized water circuit (PHEBUS-programme) [fr

Experience with the instrumentation tests in large sodium test facilities

International Nuclear Information System (INIS)

Lauhoff, Th.; Ruppert, E.; Stehle, H.; Vinzens, K.

1976-01-01

A facility is described for fast breeder core components (AKB) to test specially instrumented fuel dummies and blanket elements, and also absorber elements under simulated normal and extreme reactor conditions. In addition to endurance testing of a special sodium and high temperature sub-assembly, instrumentation is provided to investigate thermohydraulic and vibrational behaviour of core elements. During tests of > 3000 h at temperatures above 820 K the main sub-assembly characteristics, e.g. pressure drop, leakage flow, vibration and noise spectra can be reproduced. The use of eddy current flow meters, strain gauges, magnetostrictive noise sensors, pressure transducers, thermocouples, and acoustic surveillance devices, are described. (U.K.)

The Hydraulic Test Procedure for Non-instrumented Irradiation Test Rig of Annular Fuel

Energy Technology Data Exchange (ETDEWEB)

Kim, Dae Ho; Lee, Kang Hee; Shin, Chang Hwan; Park, Chan Kook

2008-08-15

This report presents the procedure of pressure drop test, vibration test and endurance test for the non-instrumented rig using the irradiation test in HANARO of advanced PWR annular fuel which were designed and fabricated by KAERI. From the out-pile thermal hydraulic tests, confirm the flow rate at the 200 kPa pressure drop and measure the RMS displacement at this time. And the endurance test is confirmed the wear and the integrity of the non-instrumented rig at the 110% design flow rate. This out-pile test perform the Flow-Induced Vibration and Pressure Drop Experimental Tester(FIVPET) facility. The instruments in FIVPET facility was calibrated in KAERI and the pump and the thermocouple were certified by manufacturer.

NASA's Newest SeaWinds Instrument Breezes Into Operation

Science.gov (United States)

2003-01-01

One of NASA's newest Earth-observing instruments, the SeaWinds scatterometer aboard Japan's Advanced Earth Observing Satellite (Adeos) 2--now renamed Midori 2--has successfully transmitted its first radar data to our home planet, generating its first high-quality images.From its orbiting perch high above Earth, SeaWinds on Midori 2 ('midori' is Japanese for the color green, symbolizing the environment) will provide the world's most accurate, highest resolution and broadest geographic coverage of ocean wind speed and direction, sea ice extent and properties of Earth's land surfaces. It will complement and eventually replace an identical instrument orbiting since June 1999 on NASA's Quick Scatterometer (QuikScat) satellite. Its three- to five-year mission will augment a long-term ocean surface wind data series that began in 1996 with launch of the NASA Scatterometer on Japan's first Adeos spacecraft.Climatologists, meteorologists and oceanographers will soon routinely use data from SeaWinds on Midori 2 to understand and predict severe weather patterns, climate change and global weather abnormalities like El Nino. The data are expected to improve global and regional weather forecasts, ship routing and marine hazard avoidance, measurements of sea ice extent and the tracking of icebergs, among other uses.'Midori 2, its SeaWinds instrument and associated ground processing systems are functioning very smoothly,' said Moshe Pniel, scatterometer projects manager at NASA's Jet Propulsion Laboratory, Pasadena, Calif. 'Following initial checkout and calibration, we look forward to continuous operations, providing vital data to scientists and weather forecasters around the world.' 'These first images show remarkable detail over land, ice and oceans,' said Dr. Michael Freilich, Ocean Vector Winds Science Team Leader, Oregon State University, Corvallis, Ore. 'The combination of SeaWinds data and measurements from other instruments on Midori 2 with data from other international

Core instrumentation and pre-operational procedures for core conversion HEU to LEU

International Nuclear Information System (INIS)

1984-02-01

This report is intended for the reactor operator, to be used as a manual or checklist for general guidance on pre-startup activities that need to be addressed in preparation for conversion to Low Enriched Fuel (LEU). All nuclear, thermodynamic and safety calculations should have been performed prior to this stage of the core conversion process. During these calculations and certainly before ordering the new LEU fuel elements the reactor operator needs to very carefully consider additional important factors concerning the new fuel: fuel reliability, reliability of fuel fabricator, reprocessing contract or fuel element storage and disposal, economics of the new fuel cycle. At this stage, too, a preoperational experimental programme has to be developed and presented to the regulatory authorities for approval. This experimental programme could lead to additional requirements on: in-core instrumentation, out-of-core instrumentation or additional experimental devices. Detailed instructions on specific tests and measurements are not provided in this report since much information on the subject is available in the open literature

Design and Testing of a Controller for the Martian Atmosphere Pressure and Humidity Instrument DREAMS-P/H

Science.gov (United States)

Tapani Nikkanen, Timo; Schmidt, Walter; Genzer, Maria; Harri, Ari-Matti; Haukka, Harri

2013-04-01

software is entirely interrupt driven, thus the MCU goes into a power saving standby mode whenever possible. Any measurement or other operation can be stopped by simply interrupting the controller with a telecommand. Software and functional tests of the DREAMS-P/H controller are needed to verify the performance of the instrument in nominal conditions and the correct operation and error detection in anomalous conditions. The nominal conditions tests range from simple functional and performance tests, to longer simulations of continued operation and measurements. Continued operation simulations can be implemented by executing accelerated runs of the expected normal measurement cycles. On the contrary, anomalous conditions tests are used to verify that the controller can handle bad telecommands or anomalous operation of the instrument transducers, for example in the case of malfunctioning sensors. Bad telecommand tests are done by feeding illegal parameters or scrambled telecommands to the controller. Malfunctioning sensors can be simulated by modifying the signals coming from the sensors and reference channels. All expected use cases and all imagined unexpected operating circumstances are studied to ensure that the system is robust. This also makes the planned modification of the design for other future missions easier and safer. Reference: [1] ESA ExoMars EDM mission: http://exploration.esa.int/science-e/www/object/index.cfm?fobjectid=47852 [2] FMI Space Projects website: http://space.fmi.fi/index.php?id=23

Cryogenic testing and analysis associated with Tevatron lower temperature operation

International Nuclear Information System (INIS)

Theilacker, J.C.

1996-09-01

An upgrade of the Tevatron cryogenic system was installed and commissioned in 1993 to allow lower temperature operation. As a result, higher energy operation is possible. Following the installation and initial commissioning, it was decided to continue the current colliding beam physics at the previous energy of 900 GeV. This has allowed us to perform parasitic lower temperature tests in the Tevatron over the last year and a half. This paper presents the results of operational experiences and thermal and hydraulic testing which has taken place. The primary goal of the testing is to better understand the operation of the cold compressor system, associated instrumentation, and the performance of the existing magnet system during lower temperature operation. This will lead to a tentatively scheduled higher energy test run in the fall of 1995. The test results have shown that more elaborate controlling methods are necessary in order to achieve reliable system operation. Fortunately, our new satellite refrigerator controls system is capable of the expansion necessary to reach our goal. New features are being added to the control system which will allow for more intelligent control and better diagnostics for component monitoring and trending

Geotechnical instrumentation requirements for atdepth testing and repository monitoring in tuff

International Nuclear Information System (INIS)

Zimmerman, R.M.

1983-01-01

This paper outlines geotechnical instrumentation requirements for the possible establishment of a nuclear waste repository in tuff on the Nevada Test Site (NTS). The Nuclear Regulatory Commission (NRC) has specified a continuing program to confirm performance during the operational period of the repository, which could last 50 years. Minimum required geotechnical measurements for confirmation of performance include thermal and thermomechanical responses; changes in stress, strain, and displacements; and pore pressure and groundwater flow characteristics. Conditions expected in tuff are: maximum rock temperatures of less than 250 0 C, stresses less than 100 MPa, strains between + or -0.01 mm/mm, and pore pressures less than 35 KPa in the unsaturated zone where hydraulic head is not the primary contributor. The paper describes instrumentation needed to make the desired measurements. In general, the instrumentation and data system are required to be stable and reliable for tens of years. Designs must consider requirements for temperature stability, temperature expansion compensation, moisture resistance, and long-term durability in mining-type environments. Severe requirements such as these suggest consideration of techniques for in-situ replacement of instrumentation. State-of-the-art instrumentation is briefly described along with a discussion of needs for refinement, replacement/recalibration and instrumentation development

Ten years of cryo-magnetic W7-X test facility construction and operation

International Nuclear Information System (INIS)

Renard, B.; Dispau, G.; Donati, A.; Genini, L.; Gournay, J.F.; Kuster, O.; Molinie, F.; Schild, T.; Touzery, R.; Vieillard, L.; Walter, C.

2011-01-01

The construction, commissioning, and operation phases of the W7-X cryo-magnetic test facility in CEA Saclay lasted ten years. The large diversity of equipments called, specialties involved and problems solved attest the expertise that was required to operate the test facility and test the coils. Nearly one hundred cryogenic tests were performed on the seventy W7-X coils, at a rate always increasing, using two cryostats each holding two coils. This paper presents the test facility and its operation first, the cryogenic difficulties that were confronted with their solutions, the electro-magnetic difficulties encountered along with corrective actions, and finally the instrumentation and data acquisition aspects. (authors)

Artificial intelligence in a mission operations and satellite test environment

Science.gov (United States)

Busse, Carl

1988-01-01

A Generic Mission Operations System using Expert System technology to demonstrate the potential of Artificial Intelligence (AI) automated monitor and control functions in a Mission Operations and Satellite Test environment will be developed at the National Aeronautics and Space Administration (NASA) Jet Propulsion Laboratory (JPL). Expert system techniques in a real time operation environment are being studied and applied to science and engineering data processing. Advanced decommutation schemes and intelligent display technology will be examined to develop imaginative improvements in rapid interpretation and distribution of information. The Generic Payload Operations Control Center (GPOCC) will demonstrate improved data handling accuracy, flexibility, and responsiveness in a complex mission environment. The ultimate goal is to automate repetitious mission operations, instrument, and satellite test functions by the applications of expert system technology and artificial intelligence resources and to enhance the level of man-machine sophistication.

Spent Fuel Test - Climax data acquisition system operations manual

International Nuclear Information System (INIS)

Nyholm, R.A.

1983-01-01

The Spent Fuel Test-Climax (SFT-C) is a test of the retrievable, deep geologic storage of commercially generated, spent nuclear reactor fuel in granite rock. Eleven spent fuel assemblies, together with 6 electrical simulators and 20 guard heaters, are emplaced 420 m below the surface in the Climax granite at the US Department of Energy Nevada Test Site. On June 2, 1978, Lawrence Livermore National Laboratory (LLNL) secured funding for the SFT-C, and completed spent fuel emplacement May 28, 1980. The multi-year duration test is located in a remote area and is unattended much of the time. An extensive array of radiological safety and geotechnical instrumentation is deployed to monitor the test performance. A dual minicomputer-based data acquisition system (DAS) collects and processes data from more than 900 analog instruments. This report documents the software element of the LLNL developed SFT-C Data Acquisition System. It defines the operating system and hardware interface configurations, the special applications software and data structures, and support software

Results of the first tests of the SIDRA satellite-borne instrument breadboard model

International Nuclear Information System (INIS)

Dudnik, O.V.; Kurbatov, E.V.; Avilov, A.M.; Titov, K.G.; Prieto, M; Sanchez, S.; Spassky, A.V.; Sylwester, J.; Gburek, S.; Podgorski, P.

2013-01-01

In this work, the results of the calibration of the solid-state detectors and electronic channels of the SIDRA satellite borne energetic charged particle spectrometer-telescope breadboard model are presented. The block schemes and experimental equipment used to conduct the thermal vacuum and electromagnetic compatibility tests of the assemblies and modules of the compact satellite equipment are described. The results of the measured thermal conditions of operation of the signal analog and digital processing critical modules of the SIDRA instrument prototype are discussed. Finally, the levels of conducted interference generated by the instrument model in the primary vehicle-borne power circuits are presented.

Operability Test Report for 241-U Compressed Air System and heat pump

International Nuclear Information System (INIS)

Rensink, G.E.

1995-01-01

The 241-U-701 compressed air system supplies instrument quality compressed air to Tank Farm 241-U. The system was upgraded. The operability test showed that the system operates within its intended design parameters. System performance was monitored, recorded, and used to identify areas of concern. Exceptions to the OTP and additional items for safe system performance were minimal and have been resolved; the air system is ready for Operation's use

Cryogenic testing and analysis associated with Tevatron lower temperature operation

International Nuclear Information System (INIS)

Theilacker, J.C.

1996-01-01

An upgrade of the Tevatron cryogenic system was installed and commissioned in 1993 to allow lower temperature operation. As a result, higher energy operation of the Fermilab superconducting Tevatron accelerator is possible. Following the installation and initial commissioning, it was decided to continue the current colliding beam physics run at the previous energy of 900 GeV. This has allowed the author to perform parasitic lower temperature tests in the Tevatron over the last year and a half. This paper presents the results of operational experiences and thermal and hydraulic testing which have taken place. The primary goal of the testing is to better understand the operation of the cold compressor system, associated instrumentation, and the performance of the existing magnet system during lower temperature operation. This will lead to a tentatively scheduled higher energy test run in the fall of 1995. The test results have shown that more elaborate controlling methods are necessary in order to achieve reliable system operation. Fortunately, the new satellite refrigerator controls system is capable of the expansion necessary to reach this goal. New features are being added to the controls systems which will allow for more intelligent control and better diagnostics for component monitoring and trending

Operating experience of steam generator test facility

International Nuclear Information System (INIS)

Sureshkumar, V.A.; Madhusoodhanan, G.; Noushad, I.B.; Ellappan, T.R.; Nashine, B.K.; Sylvia, J.I.; Rajan, K.K.; Kalyanasundaram, P.; Vaidyanathan, G.

2006-01-01

Steam Generator (SG) is the vital component of a Fast Reactor. It houses both water at high pressure and sodium at low pressure separated by a tube wall. Any damage to this barrier initiates sodium water reaction that could badly affect the plant availability. Steam Generator Test Facility (SGTF) has been set up in Indira Gandhi Centre for Atomic Research (IGCAR) to test sodium heated once through steam generator of 19 tubes similar to the PFBR SG dimension and operating conditions. The facility is also planned as a test bed to assess improved designs of the auxiliary equipments used in Fast Breeder Reactors (FBR). The maximum power of the facility is 5.7 MWt. This rating is arrived at based on techno economic consideration. This paper covers the performance of various equipments in the system such as Electro magnetic pumps, Centrifugal sodium pump, in-sodium hydrogen meters, immersion heaters, and instrumentation and control systems. Experience in the system operation, minor modifications, overall safety performance, and highlights of the experiments carried out etc. are also brought out. (author)

Fabrication of the instrumented fuel rods for the 3-Pin Fuel Test Loop at HANARO

International Nuclear Information System (INIS)

Sohn, Jae Min; Park, Sung Jae; Shin, Yoon Tag; Lee, Jong Min; Ahn, Sung Ho; Kim, Soo Sung; Kim, Bong Goo; Kim, Young Ki; Lee, Ki Hong; Kim, Kwan Hyun

2008-09-01

The 3-Pin Fuel Test Loop(hereinafter referred to as the '3-Pin FTL') facility has been installed at HANARO(High-flux Advanced Neutron Application Reactor) and the 3-Pin FTL is under a test operation. The purpose of this report is to fabricate the instrumented fuel rods for the 3-Pin FTL. The fabrication of these fuel rods was based on experiences and technologies of the instrumented fuel rods for an irradiation fuel capsule. The three instrumented fuel rods of the 3-Pin FTL have been designed. The one fuel rod(180 .deg. ) was designed to measure the centerline temperature of the nuclear fuels and the internal pressure of the fuel rod, and others(60 .deg. and 300 .deg. ) were designed to measure the centerline temperature of the fuel pellets. The claddings were made of the reference material 1 and 2 and new material 1 and 2. And nuclear fuel was used UO 2 (2.0w/o) pellet type with large grain and standard grain. The major procedures of fabrication are followings: (1) the assembling and weld of fuel rods with the pellet mockups and the sensor mockups for the qualification tests, (2) the qualification tests(dimension measurements, tensile tests, metallography examinations and helium leak tests) of weld, (3) the assembling and weld of instrumented fuel rods with the nuclear pellets and the sensors for the irradiation test, and (4) the qualification tests(the helium leak test, the dimensional measurement, electric resistance measurements of sensors) of test fuel rods. Satisfactory results were obtained for all the qualification tests of the instrumented fuel rods for the 3-Pin FTL. Therefore the three instrumented fuel rods for the 3-Pin FTL have been fabricated successfully. These will be installed in the In-Pile Section of 3-Pin FTL. And the irradiation test of these fuel rods is planned from the early next year for about 3 years at HANARO

Falsification Testing of Instrumental Variables Methods for Comparative Effectiveness Research.

Science.gov (United States)

Pizer, Steven D

2016-04-01

To demonstrate how falsification tests can be used to evaluate instrumental variables methods applicable to a wide variety of comparative effectiveness research questions. Brief conceptual review of instrumental variables and falsification testing principles and techniques accompanied by an empirical application. Sample STATA code related to the empirical application is provided in the Appendix. Comparative long-term risks of sulfonylureas and thiazolidinediones for management of type 2 diabetes. Outcomes include mortality and hospitalization for an ambulatory care-sensitive condition. Prescribing pattern variations are used as instrumental variables. Falsification testing is an easily computed and powerful way to evaluate the validity of the key assumption underlying instrumental variables analysis. If falsification tests are used, instrumental variables techniques can help answer a multitude of important clinical questions. © Health Research and Educational Trust.

Thermal and Alignment Analysis of the Instrument-Level ATLAS Thermal Vacuum Test

Science.gov (United States)

Bradshaw, Heather

2012-01-01

This paper describes the thermal analysis and test design performed in preparation for the ATLAS thermal vacuum test. NASA's Advanced Topographic Laser Altimeter System (ATLAS) will be flown as the sole instrument aboard the Ice, Cloud, and land Elevation Satellite-2 (ICESat-2). It will be used to take measurements of topography and ice thickness for Arctic and Antarctic regions, providing crucial data used to predict future changes in worldwide sea levels. Due to the precise measurements ATLAS is taking, the laser altimeter has very tight pointing requirements. Therefore, the instrument is very sensitive to temperature-induced thermal distortions. For this reason, it is necessary to perform a Structural, Thermal, Optical Performance (STOP) analysis not only for flight, but also to ensure performance requirements can be operationally met during instrument-level thermal vacuum testing. This paper describes the thermal model created for the chamber setup, which was used to generate inputs for the environmental STOP analysis. This paper also presents the results of the STOP analysis, which indicate that the test predictions adequately replicate the thermal distortions predicted for flight. This is a new application of an existing process, as STOP analyses are generally performed to predict flight behavior only. Another novel aspect of this test is that it presents the opportunity to verify pointing results of a STOP model, which is not generally done. It is possible in this case, however, because the actual pointing will be measured using flight hardware during thermal vacuum testing and can be compared to STOP predictions.

Operation of automated NDA instruments for in-line HEU accounting at Y-12

International Nuclear Information System (INIS)

Russo, P.A.; Strittmatter, R.B.; Sandford, E.L.; Jeter, I.W.; McCullough, E.; Bowers, G.L.

1983-01-01

Two automated nondestructive assay instruments developed at Los Alamos in support of nuclear materials accounting needs are currently operating in-line at the Y-12 Plant for recovery of highly enriched uranium. One instrument provides the HEU inventory in the secondary solvent extraction system, and the other monitors HEU concentration in the secondary intermediate evaporator. Both instruments were installed in December 1982. Operational evaluation of these instruments has been a joint effort of Y-12 and Los Alamos. This has included comparison of the solvent extraction system inventories with direct measurement performed on the dumped solution components of the solvent extraction system, as well as comparisons of concentration assay results with the external assays of samples withdrawn from the process. The function, design, and preliminary results of the operational evaluation are reported

Operational test for photovoltaic pumping systems; Procedimento para averiguacao operacional de sistemas fotovoltaicos de bombeamento

Energy Technology Data Exchange (ETDEWEB)

Fedrizzi, Maria Cristina; Brito, Alaan Ubaiara; Zilles, Roberto [Universidade de Sao Paulo (USP), SP (Brazil). Inst. de Eletrotecnica e Energia. Lab. de Sistemas Fotovoltaicos], e-mail: fedrizzi@iee.usp.br, e-mail: alaan@iee.usp.br, e-mail: zilles@iee.usp.br

2004-07-01

This paper presents an operational test for photovoltaic pumping systems daily production, m{sup 3}/dia. The procedure does not involve expensive instrumentation and is easy to be applied in the field as acceptance and qualification tools. In this way, the paper presents the boundary conditions for operational test accomplishment that allows its application. (author)

FMIT test-end instrumentation conceptual design

International Nuclear Information System (INIS)

Fuller, J.L.

1984-08-01

FMIT test-end measurement techniques and instrumentation concepts for deuteron beam control, test-end device protection, test cell radiation field characterization, lithium jet performance monitoring, and in-situ off-line target testing and examination are described. The test-end refers to the beam line-target-test assembly interface area inside the test cell, but TEI includes measurements inside and outside the cell. The measurement requirements are briefly reviewed and referenced. The sometimes severe environmental limitations are discussed. Where feasible, multifunctional systems have been configured. Special facility features have been minimized

[The development of an oral biomechanical testing instrument].

Science.gov (United States)

Zhang, X H; Sun, X D; Lin, Z

2000-03-01

An oral biomechanical testing instrument, which is portable, powered with batteries and controlled by single chip microcomputer, was described. The instrument was characterized by its multichannel, high accuracy, low power dissipation, wide rage of force measurement and stable performance. It can be used for acquisiting, displaying and storing data. And it may be expected to be an ideal instrument for oral biomechanical measurements.

Final Report: Part 1. In-Place Filter Testing Instrument for Nuclear Material Containers. Part 2. Canister Filter Test Standards for Aerosol Capture Rates.

Energy Technology Data Exchange (ETDEWEB)

Brown, Austin Douglas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Runnels, Joel T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Moore, Murray E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Reeves, Kirk Patrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2014-11-02

A portable instrument has been developed to assess the functionality of filter sand o-rings on nuclear material storage canisters, without requiring removal of the canister lid. Additionally, a set of fifteen filter standards were procured for verifying aerosol leakage and pressure drop measurements in the Los Alamos Filter Test System. The US Department of Energy uses several thousand canisters for storing nuclear material in different chemical and physical forms. Specialized filters are installed into canister lids to allow gases to escape, and to maintain an internal ambient pressure while containing radioactive contaminants. Diagnosing the condition of container filters and canister integrity is important to ensure worker and public safety and for determining the handling requirements of legacy apparatus. This report describes the In-Place-Filter-Tester, the Instrument Development Plan and the Instrument Operating Method that were developed at the Los Alamos National Laboratory to determine the “as found” condition of unopened storage canisters. The Instrument Operating Method provides instructions for future evaluations of as-found canisters packaged with nuclear material. Customized stainless steel canister interfaces were developed for pressure-port access and to apply a suction clamping force for the interface. These are compatible with selected Hagan-style and SAVY-4000 storage canisters that were purchased from NFT (Nuclear Filter Technology, Golden, CO). Two instruments were developed for this effort: an initial Los Alamos POC (Proof-of-Concept) unit and the final Los Alamos IPFT system. The Los Alamos POC was used to create the Instrument Development Plan: (1) to determine the air flow and pressure characteristics associated with canister filter clogging, and (2) to test simulated configurations that mimicked canister leakage paths. The canister leakage scenarios included quantifying: (A) air leakage due to foreign material (i.e. dust and hair

ExoMars Trace Gas Orbiter Instrument Modelling Approach to Streamline Science Operations

Science.gov (United States)

Munoz Fernandez, Michela; Frew, David; Ashman, Michael; Cardesin Moinelo, Alejandro; Garcia Beteta, Juan Jose; Geiger, Bernhard; Metcalfe, Leo; Nespoli, Federico; Muniz Solaz, Carlos

2018-05-01

ExoMars Trace Gas Orbiter (TGO) science operations activities are centralised at ESAC's Science Operations Centre (SOC). The SOC receives the inputs from the principal investigators (PIs) in order to implement and deliver the spacecraft pointing requests and instrument timelines to the Mission Operations Centre (MOC). The high number of orbits per planning cycle has made it necessary to abstract the planning interactions between the SOC and the PI teams at the observation level. This paper describes the modelling approach we have conducted for TGOís instruments to streamline science operations. We have created dynamic observation types that scale to adapt to the conditions specified by the PI teams including observation timing, and pointing block parameters calculated from observation geometry. This approach is considered and improvement with respect to previous missions where the generation of the observation pointing and commanding requests was performed manually by the instrument teams. Automation software assists us to effectively handle the high density of planned orbits with increasing volume of scientific data and to successfully meet opportunistic scientific goals and objectives. Our planning tool combines the instrument observation definition files provided by the PIs together with the flight dynamics products to generate the Pointing Requests and the instrument timeline (ITL). The ITL contains all the validated commands at the TC sequence level and computes the resource envelopes (data rate, power, data volume) within the constraints. At the SOC, our main goal is to maximise the science output while minimising the number of iterations among the teams, ensuring that the timeline does not violate the state transitions allowed in the Mission Operations Rules and Constraints Document.

Modeling of Highly Instrumented Honeywell Turbofan Engine Tested with Ice Crystal Ingestion in the NASA Propulsion System Laboratory

Science.gov (United States)

Veres, Joseph P.; Jorgenson, Philip C. E.; Jones, Scott M.

2016-01-01

The Propulsion Systems Laboratory (PSL), an altitude test facility at NASA Glenn Research Center, has been used to test a highly instrumented turbine engine at simulated altitude operating conditions. This is a continuation of the PSL testing that successfully duplicated the icing events that were experienced in a previous engine (serial LF01) during flight through ice crystal clouds, which was the first turbofan engine tested in PSL. This second model of the ALF502R-5A serial number LF11 is a highly instrumented version of the previous engine. The PSL facility provides a continuous cloud of ice crystals with controlled characteristics of size and concentration, which are ingested by the engine during operation at simulated altitudes. Several of the previous operating points tested in the LF01 engine were duplicated to confirm repeatability in LF11. The instrumentation included video cameras to visually illustrate the accretion of ice in the low pressure compressor (LPC) exit guide vane region in order to confirm the ice accretion, which was suspected during the testing of the LF01. Traditional instrumentation included static pressure taps in the low pressure compressor inner and outer flow path walls, as well as total pressure and temperature rakes in the low pressure compressor region. The test data was utilized to determine the losses and blockages due to accretion in the exit guide vane region of the LPC. Multiple data points were analyzed with the Honeywell Customer Deck. A full engine roll back point was modeled with the Numerical Propulsion System Simulation (NPSS) code. The mean line compressor flow analysis code with ice crystal modeling was utilized to estimate the parameters that indicate the risk of accretion, as well as to estimate the degree of blockage and losses caused by accretion during a full engine roll back point. The analysis provided additional validation of the icing risk parameters within the LPC, as well as the creation of models for

Power supply for control and instrumentation in Fast Breeder Test Reactor

International Nuclear Information System (INIS)

Raghavan, K.; Shanmugam, T.K.

1977-01-01

The design and operation of the four 'no-break' power supplies for control and instrumentation in the Fast Breeder Test Reactor (FBTR), Kalpakkam, are described. Interruptions in the power supplies are eliminated by redundancy and battery back-up source while voltage dips and transients are taken care by automatic regulation system. The four power supplies are : (1) 24 V D.C. exclusively for neutronic and safety circuits, (2) 48 V D.C. for control logic indication lamps and solenoid valves, (3) 220 V D.C. for switchgear control, control room emergency lighting and D.C. flushing oil pump for the turbine and (4) 220 V A.C. single-phase 50 H/Z for computers and electronics of control and instrumentation. Stationary lead-acid batteries (lead antimony type) in floating mode operation with rectifier/charger are used for emergency back-up. All these power supplies are fed by 415 V, 3-phase, 50 HZ emergency supply buses which are provided with diesel generator back-up. Static energy conversion system (in preference to mechanical rotation system) is used for A.C. to D.C. and also for A.C. to A.C. conversion. (M.G.B.)

Preliminary Results From a Heavily Instrumented Engine Ice Crystal Icing Test in a Ground Based Altitude Test Facility

Science.gov (United States)

Flegel, Ashlie B.; Oliver, Michael J.

2016-01-01

Preliminary results from the heavily instrumented ALF502R-5 engine test conducted in the NASA Glenn Research Center Propulsion Systems Laboratory are discussed. The effects of ice crystal icing on a full scale engine is examined and documented. This same model engine, serial number LF01, was used during the inaugural icing test in the Propulsion Systems Laboratory facility. The uncommanded reduction of thrust (rollback) events experienced by this engine in flight were simulated in the facility. Limited instrumentation was used to detect icing on the LF01 engine. Metal temperatures on the exit guide vanes and outer shroud and the load measurement were the only indicators of ice formation. The current study features a similar engine, serial number LF11, which is instrumented to characterize the cloud entering the engine, detect/characterize ice accretion, and visualize the ice accretion in the region of interest. Data were acquired at key LF01 test points and additional points that explored: icing threshold regions, low altitude, high altitude, spinner heat effects, and the influence of varying the facility and engine parameters. For each condition of interest, data were obtained from some selected variations of ice particle median volumetric diameter, total water content, fan speed, and ambient temperature. For several cases the NASA in-house engine icing risk assessment code was used to find conditions that would lead to a rollback event. This study further helped NASA develop necessary icing diagnostic instrumentation, expand the capabilities of the Propulsion Systems Laboratory, and generate a dataset that will be used to develop and validate in-house icing prediction and risk mitigation computational tools. The ice accretion on the outer shroud region was acquired by internal video cameras. The heavily instrumented engine showed good repeatability of icing responses when compared to the key LF01 test points and during day-to-day operation. Other noticeable

The Thermal-hydraulic Performance Test Report for the Non-instrumented Irradiation Test Rig of Annular Fuel

Energy Technology Data Exchange (ETDEWEB)

Kim, Dae Ho; Lee, Kang Hee; Shin, Chang Hwan

2008-09-15

This report presents the results of pressure drop test, vibration test and endurance test for the non-instrumented rig using the irradiation test in HANARO of the double cooled annular fuel which were designed and fabricated by KAERI. From the out-pile thermal hydraulic tests, corresponding to the pressure drop of 200 kPa is measured to be about 9.72 kg/sec. Vibration frequency for the non-instrumented rig ranges from 5.0 to 10.7 kg/s. RMS(Root Mean Square) displacement for non-instrumented rig is less than 11.73 m, and the maximum displacement is less than 54.87m. The flow rate for endurance test were 10.5 kg/s, which was 110% of 9.72 kg/s. And the endurance test was carried out for 3 days. The test results found not to the wear and satisfied to the limits of pressure drop, flow rate, vibration and wear in the non-instrumented rig. This test was performed at the FIVPET facility.

International standardization of instruments for neutron irradiation tests

International Nuclear Information System (INIS)

Tanimoto, Masataka; Shibata, Akira; Nakamura, Jinichi; Tsuchiya, Kunihiko; Cho, M.; Lee, C.; Park, S.; Choo, K.

2012-01-01

The JMTR in JAEA and HANARO in KAERI are the foremost testing/research reactors in the world and these are expected to contribute to many nuclear fields. As a part of instrument development in irradiation field, information exchange of instruments started from 2010 under the cooperation agreements between KAERI and JAEA. The instruments developed in JMTR and HANARO are introduced and cooperation experiments as future plan are discussed for international standardization. (author)

Instrumentation to Enhance Advanced Test Reactor Irradiations

Energy Technology Data Exchange (ETDEWEB)

J. L. Rempe; D. L. Knudson; K. G. Condie; J. E. Daw; S. C. Taylor

2009-09-01

The Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF) in April 2007 to support U.S. leadership in nuclear science and technology. By attracting new research users - universities, laboratories, and industry - the ATR will support basic and applied nuclear research and development, further advancing the nation's energy security needs. A key component of the ATR NSUF effort is to prove new in-pile instrumentation techniques that are capable of providing real-time measurements of key parameters during irradiation. To address this need, an assessment of instrumentation available and under-development at other test reactors has been completed. Based on this review, recommendations are made with respect to what instrumentation is needed at the ATR and a strategy has been developed for obtaining these sensors. Progress toward implementing this strategy is reported in this document. It is anticipated that this report will be updated on an annual basis.

Instrumentation to Enhance Advanced Test Reactor Irradiations

International Nuclear Information System (INIS)

Rempe, J.L.; Knudson, D.L.; Condie, K.G.; Daw, J.E.; Taylor, S.C.

2009-01-01

The Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF) in April 2007 to support U.S. leadership in nuclear science and technology. By attracting new research users - universities, laboratories, and industry - the ATR will support basic and applied nuclear research and development, further advancing the nation's energy security needs. A key component of the ATR NSUF effort is to prove new in-pile instrumentation techniques that are capable of providing real-time measurements of key parameters during irradiation. To address this need, an assessment of instrumentation available and under-development at other test reactors has been completed. Based on this review, recommendations are made with respect to what instrumentation is needed at the ATR and a strategy has been developed for obtaining these sensors. Progress toward implementing this strategy is reported in this document. It is anticipated that this report will be updated on an annual basis.

Testing of Environmental Satellite Bus-Instrument Interfaces Using Engineering Models

Science.gov (United States)

Gagnier, Donald; Hayner, Rick; Nosek, Thomas; Roza, Michael; Hendershot, James E.; Razzaghi, Andrea I.

2004-01-01

This paper discusses the formulation and execution of a laboratory test of the electrical interfaces between multiple atmospheric scientific instruments and the spacecraft bus that carries them. The testing, performed in 2002, used engineering models of the instruments and the Aura spacecraft bus electronics. Aura is one of NASA s Earth Observatory System missions. The test was designed to evaluate the complex interfaces in the command and data handling subsystems prior to integration of the complete flight instruments on the spacecraft. A problem discovered during the flight integration phase of the observatory can cause significant cost and schedule impacts. The tests successfully revealed problems and led to their resolution before the full-up integration phase, saving significant cost and schedule. This approach could be beneficial for future environmental satellite programs involving the integration of multiple, complex scientific instruments onto a spacecraft bus.

Test instruments used by Journal of Music Therapy authors from 1984-1997.

Science.gov (United States)

Gregory, D

2000-01-01

Issues of the Journal of Music Therapy from 1984 to 1997 were selected to investigate the application of test instruments in music therapy research. All experimental and descriptive research articles were reviewed to determine if the methodology included test instruments. Other types of measurements-physiological measures, behavioral observations, computerized devices, and self-reports were excluded from the analysis. Test instruments were categorized as either published, unpublished, or researcher-constructed. A test instrument was "published" if, after a search in the "Test Review Locator" of the Buros Mental Measurements Web Site, a reference was found in one or more of the following publications-Mental Measurement Yearbooks, Tests in Print, or Test Critiques. A test was categorized as "unpublished" if the developer was cited in the JMT article but the test was not located in one or more of the above publications. All other test instruments were categorized as researcher-constructed tests designed for the specific study in the article. From 1984-1997, 220 articles were published in JMT. Approximately 83% (n = 183) of the total were experimental or descriptive research studies. Of the 183 articles research studies, 92 (50%) included a test instrument. Reviews of method sections of the 92 articles resulted in a listing of 115 different test instruments. Percentages of researcher-constructed tests, unpublished tests, and published tests were 25%, 35%, and 40% respectively. Lists of tests document the all-encompassing range of client populations and the broad view of human behavior included in the practice of music as therapy. The Journal of Music Therapy, in addition to providing the latest research findings regarding the effectiveness of music as a therapeutic medium, provides an excellent source for updating information about the availability and applicability of test instruments for music therapy clinical practice and training.

TREFF: Reflectometer and instrument component test beamline at MLZ

Directory of Open Access Journals (Sweden)

Peter Link

2017-11-01

Full Text Available TREFF is a high resolution polarized neutron reflectometer and instrument component test beamline resulting in a highly modular instrument providing a flexible beam line for various applications.

Operating test report for project W-417, T-plant steam removal upgrade, waste transfer portion

International Nuclear Information System (INIS)

Myers, N.K.

1997-01-01

This Operating Test Report (OTR) documents the performance results of the Operating Test Procedure HNF-SD-W417-OTP-001 that provides steps to test the waste transfer system installed in the 221-T Canyon under project W-417. Recent modifications have been performed on the T Plant Rail Car Waste Transfer System. This Operating Test Procedure (OTP) will document the satisfactory operation of the 221-T Rail Car Waste Transfer System modified by project W-417. Project W-417 installed a pump in Tank 5-7 to replace the steam jets used for transferring liquid waste. This testing is required to verify that operational requirements of the modified transfer system have been met. Figure 2 and 3 shows the new and existing system to be tested. The scope of this testing includes the submersible air driven pump operation in Tank 5-7, liquid waste transfer operation from Tank 5-7 to rail car (HO-IOH-3663 or HO-IOH-3664), associated line flushing, and the operation of the flow meter. This testing is designed to demonstrate the satisfactory operation-of the transfer line at normal operating conditions and proper functioning of instruments. Favorable results will support continued use of this system for liquid waste transfer. The Functional Design Criteria for this system requires a transfer flow rate of 40 gallons per minute (GPM). To establish these conditions the pump will be supplied up to 90 psi air pressure from the existing air system routed in the canyon. An air regulator valve will regulate the air pressure. Tank capacity and operating ranges are the following: Tank No. Capacity (gal) Operating Range (gal) 5-7 10,046 0 8040 (80%) Rail car (HO-IOH-3663 HO-IOH-3664) 097219,157 Existing Tank level instrumentation, rail car level detection, and pressure indicators will be utilized for acceptance/rejection Criteria. The flow meter will be verified for accuracy against the Tank 5-7 level indicator. The level indicator is accurate to within 2.2 %. This will be for information only

The Hydraulic Test Report for Non-instrumented Irradiation Test Rig of DUO-Cooled Annular Pellet

International Nuclear Information System (INIS)

Kim, Dae Ho; Lee, Kang Hee; Shin, Chang Hwan; Yang, Yong Sik; Kim, Sun Ki; Bang, Je Geon; Song, Kun Woo

2007-08-01

This report presents the results of pressure drop test and vibration test for non-instrumented rig of Advanced PWR DUO-Fuel Annular Pellet which were designed and fabricated by KAERI. From the pressure drop test results, it is noted that the flow velocity across the non-instrumented rig of Advanced PWR DUO-Fuel Annular Pellet corresponding to the pressure drop of 200 kPa is measured to be about 8.30 kg/sec. Vibration frequency results for the non-instrumented rig at the pump spin frequency ranges from 19.0 to 32.0 Hz, RMS(Root Mean Square) displacement for the non-instrumented rig of Advanced PWR DUO-Fuel Annular Pellet is less than 7.25 m, and the maximum displacement is less than 31.27 μm. This test was performed at the FIVPET facility

Construction Of Critical Thinking Skills Test Instrument Related The Concept On Sound Wave

Science.gov (United States)

Mabruroh, F.; Suhandi, A.

2017-02-01

This study aimed to construct test instrument of critical thinking skills of high school students related the concept on sound wave. This research using a mixed methods with sequential exploratory design, consists of: 1) a preliminary study; 2) design and review of test instruments. The form of test instruments in essay questions, consist of 18 questions that was divided into 5 indicators and 8 sub-indicators of the critical thinking skills expressed by Ennis, with questions that are qualitative and contextual. Phases of preliminary study include: a) policy studies; b) survey to the school; c) and literature studies. Phases of the design and review of test instruments consist of two steps, namely a draft design of test instruments include: a) analysis of the depth of teaching materials; b) the selection of indicators and sub-indicators of critical thinking skills; c) analysis of indicators and sub-indicators of critical thinking skills; d) implementation of indicators and sub-indicators of critical thinking skills; and e) making the descriptions about the test instrument. In the next phase of the review test instruments, consist of: a) writing about the test instrument; b) validity test by experts; and c) revision of test instruments based on the validator.

Innovative operating modes and techniques for the spaceborne imaging radar-C instrument

Science.gov (United States)

Huneycutt, Bryan L.

1990-01-01

The operation of the spaceborne imaging radar-C (SIR-C) is discussed. The SIR-C instrument has been designed to obtain simultaneous multifrequency and simultaneous multipolarization radar images from a low earth orbit. It is a multiparameter imaging radar which will be flown during at least two different seasons. The instrument has been designed to operate in innovative modes such as the squint alignment mode, the extended aperture mode, the scansar mode, and the interferometry mode. The instrument has been designed to demonstrate innovative engineering techniques such as beam nulling for echo tracking, pulse-repetition frquency hopping for Doppler centroid tracking, generating the frequency step chirp for radar parameter flexibility, block floating point quantizing for data rate compression, and elevation beamwidth broadening for increasing the swath illumination.

Operation fusileer onsite radiological safety report for announced nuclear tests, October 1983-September 1984

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1985-08-01

Fusileer was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1983 through September 30, 1984. This report is limited to announced nuclear tests. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeros before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

Instrumentation and measurement method for the ATLAS test facility

Energy Technology Data Exchange (ETDEWEB)

Yun, Byong Jo; Chu, In Chul; Eu, Dong Jin; Kang, Kyong Ho; Kim, Yeon Sik; Song, Chul Hwa; Baek, Won Pil

2007-03-15

An integral effect test loop for pressurized water reactors (PWRs), the ATLAS is constructed by thermal-hydraulic safety research division in KAERI. The ATLAS facility has been designed to have the length scale of 1/2 and area scale of 1/144 compared with the reference plant, APR1400 which is a Korean evolution type nuclear reactors. A total 1300 instrumentations is equipped in the ATLAS test facility. In this report, the instrumentation of ATLAS test facility and related measurement methods were introduced.

49 CFR 572.200 - Instrumentation and test conditions.

Science.gov (United States)

2010-10-01

... TRAFFIC SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) ANTHROPOMORPHIC TEST DEVICES IIsD... Test, unless noted otherwise. (g) All instrumented response signal measurements shall be treated to the... conform to the Sign Convention For Vehicle Crash Testing, Surface Vehicle Information Report, SAE J1733...

Rover-Based Instrumentation and Scientific Investigations During the 2012 Analog Field Test on Mauna Kea Volcano, Hawaii

Science.gov (United States)

Graham, L. D.; Graff, T. G.

2013-01-01

Rover-based 2012 Moon and Mars Analog Mission Activities (MMAMA) were recently completed on Mauna Kea Volcano, Hawaii. Scientific investigations, scientific input, and operational constraints were tested in the context of existing project and protocols for the field activities designed to help NASA achieve the Vision for Space Exploration [1]. Several investigations were conducted by the rover mounted instruments to determine key geophysical and geochemical properties of the site, as well as capture the geological context of the area and the samples investigated. The rover traverse and associated science investigations were conducted over a three day period on the southeast flank of the Mauna Kea Volcano, Hawaii. The test area was at an elevation of 11,500 feet and is known as "Apollo Valley" (Fig. 1). Here we report the integration and operation of the rover-mounted instruments, as well as the scientific investigations that were conducted.

Construction, testing, and initial operation of Fort St. Vrain PCRV

International Nuclear Information System (INIS)

Ople, F.S. Jr.; Neylan, A.J.

1975-01-01

The Fort St. Vrain (FSV) Nuclear Generating Station is the first station in the USA to use a prestressed concrete reactor vessel (PCRV). The PCRV was designed and constructed by General Atomic. Construction of the PCRV was completed in 1970; the pressure and leak tests were completed in 1971. The structural behavior of the PCRV has been monitored by installed instrumentation since start of construction. The highlights of the actual construction, testing, and initial operation of the PCRV, including a comparison of structural behavior, where possible, between observed data and analytical predictions. (U.S.)

Severe accident management (SAM), operator training and instrumentation capabilities - Summary and conclusions

International Nuclear Information System (INIS)

2002-01-01

The Workshop on Operator Training for Severe Accident Management (SAM) and Instrumentation Capabilities During Severe Accidents was organised in collaboration with Electricite de France (Service Etudes et Projets Thermiques et Nucleaires). There were 34 participants, representing thirteen OECD Member countries, the Russian Federation and the OECD/NEA. Almost half the participants represented utilities. The second largest group was regulatory authorities and their technical support organisations. Basically, the Workshop was a follow-up to the 1997 Second Specialist Meeting on Operator Aids for Severe Accident Management (SAMOA-2) [Reports NEA/CSNI/R(97)10 and 27] and to the 1992 Specialist Meeting on Instrumentation to Manage Severe Accidents [Reports NEA/CSNI/R(92)11 and (93)3]. It was aimed at sharing and comparing progress made and experience gained from these two meetings, emphasizing practical lessons learnt during training or incidents as well as feedback from instrumentation capability assessment. The objectives of the Workshop were therefore: - to exchange information on recent and current activities in the area of operator training for SAM, and lessons learnt during the management of real incidents ('operator' is defined hear as all personnel involved in SAM); - to compare capabilities and use of instrumentation available during severe accidents; - to monitor progress made; - to identify and discuss differences between approaches relevant to reactor safety; - and to make recommendations to the Working Group on the Analysis and Management of Accidents and the CSNI (GAMA). The Workshop was organised into five sessions: - 1: Introduction; - 2: Tools and Methods; - 3: Training Programmes and Experience; - 4: SAM Organisation Efficiency; - 5: Instrumentation Capabilities. It was concluded by a Panel and General Discussion. This report presents the summary and conclusions: the meeting confirmed that only limited information is needed for making required decisions

Disturbance induced by surface preparation on instrumented indentation test

International Nuclear Information System (INIS)

Li, Yugang; Kanouté, Pascale; François, Manuel

2015-01-01

Surface preparation, which may induce considerable sample disturbance, plays an important role in instrumented indentation test (IIT). In this study, the sample disturbance (mainly divided into residual stresses and plastic strain) induced by the surface preparation process of instrumented indentation test specimens were investigated with both experimental tests and numerical simulations. Grazing incidence X-ray diffractions (GIXRD) and uniaxial tensile tests were conducted for characterizing the residual stresses and high plastic strain in the top surface layers of a carefully mechanically polished indentation sample, which, in the present work, is made of commercially pure titanium. Instrumented indentation tests and the corresponding finite element simulations were performed as well. For comparison, a reference sample (carefully mechanically polished & electrolytically polished) which represents the raw material was prepared and tested. Results showed that a careful mechanical polishing procedure can effectively reduce the level of residual stresses induced by this process. However, the high plastic strain in the surface region imposed by the polishing process is significant. The induced plastic strain can affect a depth up to 5 µm, which is deeper than the maximum penetration depth h max (3 µm) used for the instrumented indentation tests. In the near surface layer (in the range of depth about 350 nm), the plastic strain levels are fairly high. In the very top layer, the plastic strain was even estimated to reach more than 60%. The simultaneous use of indentation tests and numerical simulations showed that the existence of high plastic strain in the surface region will make the load vs depth (P–h) curve shift upwards, the contact hardness (H) increase and the contact stiffness (S) decrease

Disturbance induced by surface preparation on instrumented indentation test

Energy Technology Data Exchange (ETDEWEB)

Li, Yugang, E-mail: yugang.li@utt.fr [Université de Technologie de Troyes (UTT), ICD-LASMIS, UMR CNRS 6281, 12, rue Marie Curie-CS 42060, 10010 Troyes Cedex (France); Kanouté, Pascale, E-mail: pascale.kanoute@onera.fr [Université de Technologie de Troyes (UTT), ICD-LASMIS, UMR CNRS 6281, 12, rue Marie Curie-CS 42060, 10010 Troyes Cedex (France); The French Aerospace Lab (ONERA), DMSM/MCE, 29 avenue de la Division Leclerc-BP 72, F-92322 Chatillon Cedex (France); François, Manuel, E-mail: manuel.francois@utt.fr [Université de Technologie de Troyes (UTT), ICD-LASMIS, UMR CNRS 6281, 12, rue Marie Curie-CS 42060, 10010 Troyes Cedex (France)

2015-08-26

Surface preparation, which may induce considerable sample disturbance, plays an important role in instrumented indentation test (IIT). In this study, the sample disturbance (mainly divided into residual stresses and plastic strain) induced by the surface preparation process of instrumented indentation test specimens were investigated with both experimental tests and numerical simulations. Grazing incidence X-ray diffractions (GIXRD) and uniaxial tensile tests were conducted for characterizing the residual stresses and high plastic strain in the top surface layers of a carefully mechanically polished indentation sample, which, in the present work, is made of commercially pure titanium. Instrumented indentation tests and the corresponding finite element simulations were performed as well. For comparison, a reference sample (carefully mechanically polished & electrolytically polished) which represents the raw material was prepared and tested. Results showed that a careful mechanical polishing procedure can effectively reduce the level of residual stresses induced by this process. However, the high plastic strain in the surface region imposed by the polishing process is significant. The induced plastic strain can affect a depth up to 5 µm, which is deeper than the maximum penetration depth h{sub max} (3 µm) used for the instrumented indentation tests. In the near surface layer (in the range of depth about 350 nm), the plastic strain levels are fairly high. In the very top layer, the plastic strain was even estimated to reach more than 60%. The simultaneous use of indentation tests and numerical simulations showed that the existence of high plastic strain in the surface region will make the load vs depth (P–h) curve shift upwards, the contact hardness (H) increase and the contact stiffness (S) decrease.

Test report - caustic addition system operability test procedure

International Nuclear Information System (INIS)

Parazin, R.E.

1995-01-01

This Operability Test Report documents the test results of test procedure WHC-SD-WM-OTP-167 ''Caustic Addition System Operability Test Procedure''. The Objective of the test was to verify the operability of the 241-AN-107 Caustic Addition System. The objective of the test was met

Instrumentation Report No. 2: identification, evaluation, and remedial actions related to transducer failures at the spent fuel test-climax

Energy Technology Data Exchange (ETDEWEB)

Patrick, W.C.; Carlson, R.C.; Rector, N.L.

1981-11-30

The Spent Fuel Test-Climax (SFT-C) is a test of the feasibility of safe and reliable short-term storage and retrieval of spent fuel from commercial nuclear reactors. In support of operational and technical goals of the test, about 850 channels of instrumentation have been installed at the SFT-C. Failure of several near-field instruments began less than six months after emplacement of 11 canisters of spent fuel and activation of six thermally similar simulators. The failed units were linear potentiometers (used to make displacement measurements) and vibrating wire stressmeters (used to make change-in-stress measurements). This report discusses the observed problems and remedial actions taken to date.

Instrumentation Report No. 2: identification, evaluation, and remedial actions related to transducer failures at the spent fuel test-climax

International Nuclear Information System (INIS)

Patrick, W.C.; Carlson, R.C.; Rector, N.L.

1981-01-01

The Spent Fuel Test-Climax (SFT-C) is a test of the feasibility of safe and reliable short-term storage and retrieval of spent fuel from commercial nuclear reactors. In support of operational and technical goals of the test, about 850 channels of instrumentation have been installed at the SFT-C. Failure of several near-field instruments began less than six months after emplacement of 11 canisters of spent fuel and activation of six thermally similar simulators. The failed units were linear potentiometers (used to make displacement measurements) and vibrating wire stressmeters (used to make change-in-stress measurements). This report discusses the observed problems and remedial actions taken to date

The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results

International Nuclear Information System (INIS)

Prasser, H.M.; Beyer, M.; Carl, H.; Manera, A.; Pietruske, H.; Schuetz, P.; Weiss, F.P.

2006-01-01

A new multipurpose thermalhydraulic test facility TOPFLOW (TwO Phase FLOW) was built and put into operation at Forschungszentrum Rossendorf in 2002 and 2003. Since then, it has been mainly used for the investigation of generic and applied steady state and transient two phase flow phenomena and the development and validation of models of computational fluid dynamic (CFD) codes in the frame of the German CFD initiative. The advantage of TOPFLOW consists in the combination of a large scale of the test channels with a wide operational range both of the flow velocities as well as of the system pressures and temperatures plus finally the availability of a special instrumentation that is capable in high spatial and temporal resolving two phase flow phenomena, for example the wire-mesh sensors. (orig.)

Advanced Instrumentation for Transient Reactor Testing

Energy Technology Data Exchange (ETDEWEB)

Corradini, Michael L.; Anderson, Mark; Imel, George; Blue, Tom; Roberts, Jeremy; Davis, Kurt

2018-01-31

Transient testing involves placing fuel or material into the core of specialized materials test reactors that are capable of simulating a range of design basis accidents, including reactivity insertion accidents, that require the reactor produce short bursts of intense highpower neutron flux and gamma radiation. Testing fuel behavior in a prototypic neutron environment under high-power, accident-simulation conditions is a key step in licensing nuclear fuels for use in existing and future nuclear power plants. Transient testing of nuclear fuels is needed to develop and prove the safety basis for advanced reactors and fuels. In addition, modern fuel development and design increasingly relies on modeling and simulation efforts that must be informed and validated using specially designed material performance separate effects studies. These studies will require experimental facilities that are able to support variable scale, highly instrumented tests providing data that have appropriate spatial and temporal resolution. Finally, there are efforts now underway to develop advanced light water reactor (LWR) fuels with enhanced performance and accident tolerance. These advanced reactor designs will also require new fuel types. These new fuels need to be tested in a controlled environment in order to learn how they respond to accident conditions. For these applications, transient reactor testing is needed to help design fuels with improved performance. In order to maximize the value of transient testing, there is a need for in-situ transient realtime imaging technology (e.g., the neutron detection and imaging system like the hodoscope) to see fuel motion during rapid transient excursions with a higher degree of spatial and temporal resolution and accuracy. There also exists a need for new small, compact local sensors and instrumentation that are capable of collecting data during transients (e.g., local displacements, temperatures, thermal conductivity, neutron flux, etc.).

An instrument for real time detection of contamination in space environmental tests chambers

Science.gov (United States)

Richmond, R. G.; Harmon, H. N.

1972-01-01

An instrument for in situ vacuum detection of surface reflectance changes at 1216A was designed. Using successive reflections, this instrument is more sensitive as an indicator of reflectance changes than similar instruments having only a single reflection. The selection of each component of the instrument and its operational performance is discussed.

A Novel Design of Needle Aspiration Biopsy Monitoring Instrument (NAOMI Tested on a Low Cost Chest Phantom

Directory of Open Access Journals (Sweden)

Surakusumah Rino Ferdian

2016-01-01

Full Text Available Needle biopsy is a medical intervention method for taking a lung tissue sample that suspected as a cancer. The disadvantage is the physicians directly visualize the anatomical structures in an open surgery for lung cancer biopsy procedure. There is a need to develop an instrument that may help the physician to guarantee the accuracy and efficiency while performing needle aspiration biopsy. Therefore, a needle aspiration biopsy monitoring instrument or named as NAOMI is proposed. It consists of a microcontroller system, an IMU sensor, an ultrasonic ranging module, a bluetooth module, and a 9V lithium battery. The experimental testing consist of performance testing, functional testing using chest phantom, and user acceptances. The results showed that the NAOMI improve the accuracy and efficiency while performing the needle biopsy operation.

Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid ''P''

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Acceptance Test Report (ATR) provides the test results for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''P''. The ATR summaries the results and provides a copy of the ATP and inspections in the Appendix

Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid Q

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Acceptance Test Report (ATR) provides the test results for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''Q''. The ATR summaries the results and provides a copy of the ATP and inspections in the Appendix

49 CFR 572.21 - Test conditions and instrumentation.

Science.gov (United States)

2010-10-01

...-Year-Old Child § 572.21 Test conditions and instrumentation. (a)(1) The test probe used for head and... surface of the lumbar spine, and 0.3 inches dorsal to the accelerometer mounting plate surface. (1) The.... For thorax and lumbar spine tests, the seating surface is without the back support as shown in Figures...

49 CFR 572.127 - Test conditions and instrumentation.

Science.gov (United States)

2010-10-01

...-year-old Child Test Dummy, Beta Version § 572.127 Test conditions and instrumentation. (a) The test... ends of ribs #1 and #6 and at the spine box at the levels of #1 and #6 ribs as shown in 127-0000 sheet...) The optional lumbar spine force-moment transducer shall have the dimensions, response characteristics...

D-Catch instrument : development and psychometric testing of a measurement instrument for nursing documentation in hospitals

NARCIS (Netherlands)

Paans, Wolter; Sermeus, Walter; Nieweg, Roos; van der Schans, Cees P.

AIM: This paper is a report of the development and testing of the psychometric properties of an instrument to measure the accuracy of nursing documentation in general hospitals. BACKGROUND: Little information is available about the accuracy of nursing documentation. None of the existing instruments

Operation Aqueduct: Onsite radiological safety report for announced nuclear tests, October 1989--September 1990

International Nuclear Information System (INIS)

Hernandez, G.M.; Jacklin, A.K.

1992-01-01

Aqueduct was the name assigned to the series of underground nuclear weapons tests conducted at the Nevada Test Site (NTS) from October 1, 1989, through September 30, 1990. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear event by a telemetry system. Reynolds Electrical ampersand Engineering Co., Inc. (REECO) Health Protection Department (HPD) Radiation Protection Technicians (RPTS) with portable radiation detection instruments surveyed reentry routes into ground zeros (GZ) before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene (IH) coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

Ares I Scale Model Acoustic Tests Instrumentation for Acoustic and Pressure Measurements

Science.gov (United States)

Vargas, Magda B.; Counter, Douglas D.

2011-01-01

The Ares I Scale Model Acoustic Test (ASMAT) was a development test performed at the Marshall Space Flight Center (MSFC) East Test Area (ETA) Test Stand 116. The test article included a 5% scale Ares I vehicle model and tower mounted on the Mobile Launcher. Acoustic and pressure data were measured by approximately 200 instruments located throughout the test article. There were four primary ASMAT instrument suites: ignition overpressure (IOP), lift-off acoustics (LOA), ground acoustics (GA), and spatial correlation (SC). Each instrumentation suite incorporated different sensor models which were selected based upon measurement requirements. These requirements included the type of measurement, exposure to the environment, instrumentation check-outs and data acquisition. The sensors were attached to the test article using different mounts and brackets dependent upon the location of the sensor. This presentation addresses the observed effect of the sensors and mounts on the acoustic and pressure measurements.

Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid N

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This is a Test Report for Acceptance Test Procedure (ATP) RPP-5489. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''N''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document

Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid M

International Nuclear Information System (INIS)

KOCH, M.R.

1999-01-01

This is a Test Report for Acceptance Test Procedure (ATP) RPP-5073. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''M''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document

Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid L

International Nuclear Information System (INIS)

KOCH, M.R.

1999-01-01

This is a Test Report for Acceptance Test Procedure (ATP) RPP-5055. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''L''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document

Operability test procedure [Tank] 241-SY-101 equipment removal system

International Nuclear Information System (INIS)

Mast, J.C.

1994-01-01

The 241-SY-101 equipment removal system (ERS) consists of components, equipment, instrumentation and procedures that will provide the means to disconnect, retrieve, contain, load and transport the Mitigation Pump Assembly (MPA) from waste Tank 241-SY-101 to the Central Waste Complex (CWC). The Operability Test Procedure (OTP) will test the interfaces between ERS components and will rehearse the procedure for MPA removal and transportation to the extent they can be mocked-up at the CTF (Cold Test Facility). At the conclusion of the OTP, the ERS components and equipment will be removed from the CTF, entered into the Component Based Recall System (CBRS), and stored until needed for actual MPA removal and transportation

A new device to test cutting efficiency of mechanical endodontic instruments

Science.gov (United States)

Rubini, Alessio Giansiracusa; Plotino, Gianluca; Al-Sudani, Dina; Grande, Nicola M.; Putorti, Ermanno; Sonnino, GianPaolo; Cotti, Elisabetta; Testarelli, Luca; Gambarini, Gianluca

2014-01-01

Background The purpose of the present study was to introduce a new device specifically designed to evaluate the cutting efficiency of mechanically driven endodontic instruments. Material/Methods Twenty new Reciproc R25 (VDW, Munich, Germany) files were used to be investigated in the new device developed to test the cutting ability of endodontic instruments. The device consists of a main frame to which a mobile plastic support for the hand-piece is connected and a stainless-steel block containing a Plexiglas block against which the cutting efficiency of the instruments was tested. The length of the block cut in 1 minute was measured in a computerized program with a precision of 0.1mm. The instruments were activated by using a torque-controlled motor (Silver Reciproc; VDW, Munich, Germany) in a reciprocating movement by the “Reciproc ALL” program (Group 1) and in counter-clockwise rotation at 300 rpm (Group 2). Mean and standard deviations of each group were calculated and data were statistically analyzed with a one-way ANOVA test (P0.05). Conclusions The cutting testing device evaluated in the present study was reliable and easy to use and may be effectively used to test cutting efficiency of both rotary and reciprocating mechanical endodontic instruments. PMID:24603777

Operational Test Report (OTR) for U-105 Pumping and Instrumentation and Control (PIC) Skid

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

Attached is the completed Operation Test Procedure (OTP-200-004, Rev. A-18). OTP includes a print out of the Programmable Logic Controller (PLC) Ladder Diagram. Ladder Diagram was designed for installation in the PLC used to monitor and control pumping activity for Tank Farm 241-U-105. The completed OTP and OTR are referenced in the IS PIC Skid Configuration Drawing (H-2-829998)

Operational Test Report (OTR) for U-105 Pumping and Instrumentation and Control (PIC) Skid

Energy Technology Data Exchange (ETDEWEB)

KOCH, M.R.

2000-02-28

Attached is the completed Operation Test Procedure (OTP-200-004, Rev. A-18). OTP includes a print out of the Programmable Logic Controller (PLC) Ladder Diagram. Ladder Diagram was designed for installation in the PLC used to monitor and control pumping activity for Tank Farm 241-U-105. The completed OTP and OTR are referenced in the IS PIC Skid Configuration Drawing (H-2-829998).

Operational Test Report (OTR) for U-103 Pumping and Instrumentation and Control (PIC) Skid

Energy Technology Data Exchange (ETDEWEB)

KOCH, M.R.

2000-02-28

Attached is the completed Operation Test Procedure (OTP-200-004, Rev. A-16). OTP includes a print out of the Programmable Logic Controller (PLC) Ladder Diagram. Ladder Diagram was designed for installation in the PLC used to monitor and control pumping activity for Tank Farm 241-U-103. The completed OTP and OTR are referenced in the 25 PIC Skid Configuration Drawing (H-2-829998).

Quality of prenatal care questionnaire: instrument development and testing.

Science.gov (United States)

Heaman, Maureen I; Sword, Wendy A; Akhtar-Danesh, Noori; Bradford, Amanda; Tough, Suzanne; Janssen, Patricia A; Young, David C; Kingston, Dawn A; Hutton, Eileen K; Helewa, Michael E

2014-06-03

Utilization indices exist to measure quantity of prenatal care, but currently there is no published instrument to assess quality of prenatal care. The purpose of this study was to develop and test a new instrument, the Quality of Prenatal Care Questionnaire (QPCQ). Data for this instrument development study were collected in five Canadian cities. Items for the QPCQ were generated through interviews with 40 pregnant women and 40 health care providers and a review of prenatal care guidelines, followed by assessment of content validity and rating of importance of items. The preliminary 100-item QPCQ was administered to 422 postpartum women to conduct item reduction using exploratory factor analysis. The final 46-item version of the QPCQ was then administered to another 422 postpartum women to establish its construct validity, and internal consistency and test-retest reliability. Exploratory factor analysis reduced the QPCQ to 46 items, factored into 6 subscales, which subsequently were validated by confirmatory factor analysis. Construct validity was also demonstrated using a hypothesis testing approach; there was a significant positive association between women's ratings of the quality of prenatal care and their satisfaction with care (r = 0.81). Convergent validity was demonstrated by a significant positive correlation (r = 0.63) between the "Support and Respect" subscale of the QPCQ and the "Respectfulness/Emotional Support" subscale of the Prenatal Interpersonal Processes of Care instrument. The overall QPCQ had acceptable internal consistency reliability (Cronbach's alpha = 0.96), as did each of the subscales. The test-retest reliability result (Intra-class correlation coefficient = 0.88) indicated stability of the instrument on repeat administration approximately one week later. Temporal stability testing confirmed that women's ratings of their quality of prenatal care did not change as a result of giving birth or between the early postpartum

Quality of prenatal care questionnaire: instrument development and testing

Science.gov (United States)

2014-01-01

Background Utilization indices exist to measure quantity of prenatal care, but currently there is no published instrument to assess quality of prenatal care. The purpose of this study was to develop and test a new instrument, the Quality of Prenatal Care Questionnaire (QPCQ). Methods Data for this instrument development study were collected in five Canadian cities. Items for the QPCQ were generated through interviews with 40 pregnant women and 40 health care providers and a review of prenatal care guidelines, followed by assessment of content validity and rating of importance of items. The preliminary 100-item QPCQ was administered to 422 postpartum women to conduct item reduction using exploratory factor analysis. The final 46-item version of the QPCQ was then administered to another 422 postpartum women to establish its construct validity, and internal consistency and test-retest reliability. Results Exploratory factor analysis reduced the QPCQ to 46 items, factored into 6 subscales, which subsequently were validated by confirmatory factor analysis. Construct validity was also demonstrated using a hypothesis testing approach; there was a significant positive association between women’s ratings of the quality of prenatal care and their satisfaction with care (r = 0.81). Convergent validity was demonstrated by a significant positive correlation (r = 0.63) between the “Support and Respect” subscale of the QPCQ and the “Respectfulness/Emotional Support” subscale of the Prenatal Interpersonal Processes of Care instrument. The overall QPCQ had acceptable internal consistency reliability (Cronbach’s alpha = 0.96), as did each of the subscales. The test-retest reliability result (Intra-class correlation coefficient = 0.88) indicated stability of the instrument on repeat administration approximately one week later. Temporal stability testing confirmed that women’s ratings of their quality of prenatal care did not change as a result of giving

SPECTR System Operational Test Report

International Nuclear Information System (INIS)

Landman, W.H. Jr.

2011-01-01

This report overviews installation of the Small Pressure Cycling Test Rig (SPECTR) and documents the system operational testing performed to demonstrate that it meets the requirements for operations. The system operational testing involved operation of the furnace system to the design conditions and demonstration of the test article gas supply system using a simulated test article. The furnace and test article systems were demonstrated to meet the design requirements for the Next Generation Nuclear Plant. Therefore, the system is deemed acceptable and is ready for actual test article testing.

Design type testing for digital instrumentation and control systems

International Nuclear Information System (INIS)

Bastl, W.; Mohns, G.

1997-01-01

The design type qualification of digital safety instrumentation and control is outlined. Experience shows that the concepts discussed, derived from codes, guidelines and standards, achieve useful results. It has likewise become clear that the systematics of design type qualification of the hardware components is also applicable to the software components. Design type qualification of the software, a premiere, could be performed unexpectedly smoothly. The hardware design type qualification proved that the hardware as a substrate of functionality and reliability is an issue that demands full attention, as compared to conventional systems. Another insight is that design qualification of digital instrumentation and control systems must include plant-independent systems tests. Digital instrumentation and control systems simply work very differently from conventional control systems, so that this testing modality is inevitable. (Orig./CB) [de

Industrial hygiene support of underground operations at the Nevada Test Site

International Nuclear Information System (INIS)

Porter, P.F.

1992-01-01

The Industrial Hygiene Section of the Health Protection Department provides industrial hygiene support of underground operations at the Nevada Test Site. This report describes support operations and summarizes the industrial hygiene data collected from July 31, 1989 through June 30, 1991. Air quality data were collected by means of personnel sampling by active and passive techniques using various kinds of industrial hygiene instrumentation and through localized and general area monitoring. The data collected were used to evaluate underground air quality and quantity requirements; evaluate worker exposures to a variety of air contaminants; determine the applicability and effectiveness of personal protective equipment

ORNL instrumentation performance for Slab Core Test Facility (SCTF)-Core I Reflood Test Facility

International Nuclear Information System (INIS)

Hardy, J.E.; Hess, R.A.; Hylton, J.O.

1983-11-01

Instrumentation was developed for making measurements in experimental refill-reflood test facilities. These unique instrumentation systems were designed to survive the severe environmental conditions that exist during a simulated pressurized water reactor loss-of-coolant accident (LOCA). Measurement of in-vessel fluid phenomena such as two-phase flow velocity and void fraction and film thickness and film velocity are required for better understanding of reactor behavior during LOCAs. The Advanced Instrumentation for Reflood Studies (AIRS) Program fabricated and delivered instrumentation systems and data reduction software algorithms that allowed the above measurements to be made. Data produced by AIRS sensors during three experimental runs in the Japanese Slab Core Test Facility are presented. Although many of the sensors failed before any useful data could be obtained, the remaining probes gave encouraging and useful results. These results are the first of their kind produced during simulated refill-reflood stage of a LOCA near actual thermohydrodynamic conditions

Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid L

Energy Technology Data Exchange (ETDEWEB)

KOCH, M.R.

1999-11-09

This is a Test Report for Acceptance Test Procedure (ATP) RPP-5055. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''L''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document.

Test Report for Acceptance Test Procedure for Pumping Instrumentation and Control Skid M

Energy Technology Data Exchange (ETDEWEB)

KOCH, M.R.

1999-12-13

This is a Test Report for Acceptance Test Procedure (ATP) RPP-5073. This test report provides the results of the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''M''. The ATP was successfully completed. A copy of the completed ATP is in the Appendix of this document.

Design and manufacturing of instrumented capsule (02F-06K/02F-11K) for nuclear fuel irradiation test in HANARO

International Nuclear Information System (INIS)

Kim, Bong Goo; Kang, Y. H.; Cho, M. S.; Sohn, J. M.; Choo, K. N.; Kim, D. S.; Oh, J. M.; Shin, Y.T.; Park, S.J.; Kim, Y. J.; Seo, C.G.; Ryu, J.S.; Cho, Y. G.

2003-02-01

To measure the characteristics of nuclear fuel during irradiation test, it is necessary to develop the instrumented capsule for the nuclear fuel irradiation test. Then considering the requirements for the nuclear fuel irradiation test and the compatibility with OR test hole in HANARO as well as the requirements for HANARO operation and related equipments, the instrumented capsule for the nuclear fuel irradiation test was designed and successfully manufactured. The structural integrity of the capsule design was verified by performing nuclear physics, structural and thermal analyses. And, not only out-of-pile tests such as pressure drop test, vibration test, endurance test, were performed in HANARO design verification test facility, but the mechanical and hydraulic safety of the capsule and the compatibility of the capsule with HANARO was verified

SuperAGILE onboard electronics and ground test instrumentation

International Nuclear Information System (INIS)

Pacciani, Luigi; Morelli, Ennio; Rubini, Alda; Mastropietro, Marcello; Porrovecchio, Geiland; Costa, Enrico; Del Monte, Ettore; Donnarumma, Immacolata; Evangelista, Yuri; Feroci, Marco; Lazzarotto, Francesco; Rapisarda, Massimo; Soffitta, Paolo

2007-01-01

In this paper we describe the electronics of the SuperAGILE X-ray imager on-board AGILE satellite and the instrumentation developed to test and improve the Front-End and digital electronics of the flight model of the imager. Although the working principle of the instrument is very well established, and the conceptual scheme simple, the budget and mechanical constraints of the AGILE small mission made necessary the introduction of new elements in SuperAGILE, regarding both the mechanics and the electronics. In fact the instrument is contained in a ∼44x44x16cm 3 volume, but the required performance is quite ambitious, leading us to equip a sensitive area of ∼1350cm 2 with 6144 Silicon μstrips detectors with a pitch of 121μm and a total length of ∼18.2cm. The result is a very light and power-cheap imager with a good sensitivity (∼15mCrab in 1 day in 15-45keV), high angular resolution (6arcmin) and gross spectral resolution. The test-equipment is versatile, and can be easily modified to test FEE based on self-triggered, data-driven and sparse-readout ASICs such as XA family chips

Operational Test Report (OTR) for U-102 Pumping and Instrumentation and Control (PIC) Skid

Energy Technology Data Exchange (ETDEWEB)

KOCH, M.R.

2000-02-28

Attached is the completed Operation Test Procedure (OTP-200-004, Rev. A-19 and Rev. A-20). OTP includes a print out of the Programmable Logic Controller (PLC) Ladder Diagram. Ladder Diagram was designed for installation in the PLC used to monitor and control pumping activity for Tank Farm 241-U-102. The completed OTP and OTR are referenced in the IS PIC Skid Configuration Drawing (H-2-829998).

Out-pile test of non-instrumented capsule for the advanced PWR fuel pellets in HANARO irradiation test

Energy Technology Data Exchange (ETDEWEB)

Kim, D. H.; Lee, C. B.; Oh, D. S.; Bang, J. K.; Kim, Y. M.; Yang, Y. S.; Jeong, Y. H.; Jeon, H. K.; Ryu, J. S. [KAERI, Taejon (Korea, Republic of)

2002-05-01

Non-instrumental capsule were designed and fabricated to irradiate the advanced pellet developed for the high burn-up LWR fuel in the HANARO in-pile capsule. This capsule was out-pie tested at Cold Test Loop-I in KAERI. From the pressure drop test results, it is noted that the flow velocity across the non-instrumented capsule of advanced PWR fuel pellet corresponding to the pressure drop of 200 kPa is measured to be about 7.45 kg/sec. Vibration frequency for the capsule ranges from 13.0 to 32.3 Hz. RMS displacement for non-instrumented capsule of advanced PWR fuel pellet is less than 11.6 {mu}m, and the maximum displacement is less that 30.5 {mu}m. The flow rate for endurance test were 8.19 kg/s, which was 110% of 7.45 kg/s. And the endurance test was carried out for 100 days and 17 hours. The test results found not to the wear satisfied to the limits of pressure drop, flow rate, vibration and wear in the non-instrumented capsule.

WATCH: Warwick Assessment insTrument for Clinical teacHing: Development and testing.

Science.gov (United States)

Haider, Sonia Ijaz; Johnson, Neil; Thistlethwaite, Jill Elizabeth; Fagan, Gay; Bari, Muhammad Furqan

2015-03-01

Medical education and teaching skills are core competencies included in the generic curriculum for specialty training. To support the development of these skills, there is need for a validated instrument. This study aims to develop and test an instrument to measure the attributes of specialty trainees as effective teachers. The study was conducted in two phases. In first phase, the content of the instrument was generated from the literature and tested using the Delphi technique. In second phase, the instrument was field tested for validity and reliability using factor analysis and generalizability study. Feasibility was calculated by the time taken to complete the instrument. Acceptability and educational impact were determined by qualitative analysis of written feedback. Attributes of specialty trainees were assessed by clinical supervisors, peers, and students. The Delphi study produced consensus on 15 statements which formed the basis of the instrument. In field study, a total of 415 instruments were completed. Factor analysis demonstrated a three-factor solution ('learning-teaching milieu', 'teaching skills', and 'learner-orientated'). A generalizability coefficient was 0.92. Mean time to complete the instrument was five minutes. Feedback indicated that it was an acceptable and useful method of assessment. This new instrument provides valid, reliable, feasible, and acceptable assessment of clinical teaching.

Paper on operation and maintenance experiences on radiation monitoring instrumentation at NAPS

International Nuclear Information System (INIS)

Gupta, J.P.; Vinod Kumar; Sen, S.K.; Malhotra, S.

2005-01-01

Narora Atomic Power Station (NAPS) is the first standardized Pressurised Heavy Water Reactor in India commissioned in the year 1989. Many new Radiation Monitoring Systems like Portal Monitors and Ventilation Exhaust Activity Monitors were first time introduced at NAPS. All the Personnel Contamination Monitors and Area Radiation Monitors used at NAPS were designed and developed by Electronics Division, BARC. Only the Portal Monitor was supplied by M/S Herfurth, Germany. The paper highlights the operation and maintenance experiences on Radiation Monitoring Instrumentation at NAPS in the last 15 years of operation. The paper also highlights the different problems faced in Radiation Instruments and our suggestions for improvement in their design for their better availability and long term reliability. (author)

Operations open-market as instrument money-credit politics of NBU

OpenAIRE

Karacharova, K.

2014-01-01

In the article essence and progress of operations trends aregeneralized open-market as an instrument of monetarypolicy of NBU. Connection is certain between the height ofamount of money and by a gross internal product. The basic obstacles of relatively active application of suchinstrument of monetary policy are certain, a operationsopen-market.

A comparison of two reciprocating instruments using bending stress and cyclic fatigue tests.

Science.gov (United States)

Scelza, Pantaleo; Harry, Davidowicz; Silva, Licinio Esmeraldo da; Barbosa, Igor Bastos; Scelza, Miriam Zaccaro

2015-01-01

The aim of this study was to comparatively evaluate the bending resistance at 45º, the static and dynamic cyclic fatigue life, and the fracture type of the WaveOne (Dentsply Maillefer, Ballaigues, Switzerland) 25-08 and Reciproc (VDW, Munich, Germany) 25-08 instruments. A total of 60 nickel-titanium (NiTi) instruments (30 Reciproc and 30 WaveOne) from three different lots, each of which was 25 mm in length, were tested. The bending resistance was evaluated through the results of a cantilever-bending test conducted using a universal testing machine. Static and dynamic cyclic fatigue testing was conducted using a custom-made device. For the static and dynamic tests, a cast Ni-Cr-Mo-Ti alloy metal block with an artificial canal measuring 1.77 mm in diameter and 20.00 mm in total length was used. A scanning electron microscope was used to determine the type of fracture. Statistical analyses were performed on the results. The WaveOne instrument was less flexible than the Reciproc (p fatigue tests (p ductile-type fracture characteristics. It can be concluded that the Reciproc 25-08 instrument was more resistant to static and dynamic cyclic fatigue than the WaveOne 25-08 instrument, while the WaveOne 25-08 instrument was less flexible. Bending and resistance to cyclic fracture were influenced by the instruments' geometries and transverse cross-sections. Both of the instruments showed ductile-type fracture characteristics.

Instrumentation report 1: specification, design, calibration, and installation of instrumentation for an experimental, high-level, nuclear waste storage facility

International Nuclear Information System (INIS)

Brough, W.G.; Patrick, W.C.

1982-01-01

The Spent Fuel Test-Climax (SFT-C) is being conducted 420 m underground at the Nevada Test Site under the auspices of the US Department of Energy. The test facility houses 11 spent fuel assemblies from an operating commercial nuclear reactor and numerous other thermal sources used to simulate the near-field effects of a large repository. We developed a large-scale instrumentation plan to ensure that a sufficient quality and quantity of data were acquired during the three- to five-year test. These data help satisfy scientific, operational, and radiation safety objectives. Over 800 data channels are being scanned to measure temperature, electrical power, radiation, air flow, dew point, stress, displacement, and equipment operation status (on/off). This document details the criteria, design, specifications, installation, calibration, and current performance of the entire instrumentation package

Operability test procedure for 241-U compressed air system and heat pump

International Nuclear Information System (INIS)

Freeman, R.D.

1994-01-01

The 241-U-701 compressed air system supplies instrument quality compressed air to Tank Farm 241-U. The supply piping to the 241-U Tank Farm is not included in the modification. Modifications to the 241-U-701 compressed air system include installation of a 15 HP Reciprocating Air Compressor, Ingersoll-Rand Model 10T3NLM-E15; an air dryer, Hankinson, Model DH-45; and miscellaneous system equipment and piping (valves, filters, etc.) to meet the design. A newly installed heat pump allows the compressor to operate within an enclosed relatively dust free atmosphere and keeps the compressor room within a standard acceptable temperature range, which makes possible efficient compressor operation, reduces maintenance, and maximizes compressor operating life. This document is an Operability Test Procedure (OTP) which will further verify (in addition to the Acceptance Test Procedure) that the 241-U-701 compressed air system and heat pump operate within their intended design parameters. The activities defined in this OTP will be performed to ensure the performance of the new compressed air system will be adequate, reliable and efficient. Completion of this OTP and sign off of the OTP Acceptance of Test Results is necessary for turnover of the compressed air system from Engineering to Operations

NASA SMD Airborne Science Capabilities for Development and Testing of New Instruments

Science.gov (United States)

Fladeland, Matthew

2015-01-01

The SMD NASA Airborne Science Program operates and maintains a fleet of highly modified aircraft to support instrument development, satellite instrument calibration, data product validation and earth science process studies. This poster will provide an overview of aircraft available to NASA researchers including performance specifications and modifications for instrument support, processes for requesting aircraft time and developing cost estimates for proposals, and policies and procedures required to ensure safety of flight.

Design of software platform based on linux operating system for γ-spectrometry instrument

International Nuclear Information System (INIS)

Hong Tianqi; Zhou Chen; Zhang Yongjin

2008-01-01

This paper described the design of γ-spectrometry instrument software platform based on s3c2410a processor with arm920t core, emphases are focused on analyzing the integrated application of embedded linux operating system, yaffs file system and qt/embedded GUI development library. It presented a new software platform in portable instrument for γ measurement. (authors)

A comparison of two reciprocating instruments using bending stress and cyclic fatigue tests

Directory of Open Access Journals (Sweden)

Pantaleo SCELZA

2015-01-01

Full Text Available The aim of this study was to comparatively evaluate the bending resistance at 45º, the static and dynamic cyclic fatigue life, and the fracture type of the WaveOne (Dentsply Maillefer, Ballaigues, Switzerland 25-08 and Reciproc (VDW, Munich, Germany 25-08 instruments. A total of 60 nickel-titanium (NiTi instruments (30 Reciproc and 30 WaveOne from three different lots, each of which was 25 mm in length, were tested. The bending resistance was evaluated through the results of a cantilever-bending test conducted using a universal testing machine. Static and dynamic cyclic fatigue testing was conducted using a custom-made device. For the static and dynamic tests, a cast Ni-Cr-Mo-Ti alloy metal block with an artificial canal measuring 1.77 mm in diameter and 20.00 mm in total length was used. A scanning electron microscope was used to determine the type of fracture. Statistical analyses were performed on the results. The WaveOne instrument was less flexible than the Reciproc (p < 0.05. The Reciproc instrument showed better resistance in the static and dynamic cyclic fatigue tests (p < 0.05. The transverse cross-section and geometry of the instruments were important factors in their resistance to bending and cyclic fracture. Both of the instruments showed ductile-type fracture characteristics. It can be concluded that the Reciproc 25-08 instrument was more resistant to static and dynamic cyclic fatigue than the WaveOne 25-08 instrument, while the WaveOne 25-08 instrument was less flexible. Bending and resistance to cyclic fracture were influenced by the instruments’ geometries and transverse cross-sections. Both of the instruments showed ductile-type fracture characteristics.

Use of a formal assessment instrument for evaluation of resident operative skills in pediatric neurosurgery.

Science.gov (United States)

Hadley, Caroline; Lam, Sandi K; Briceño, Valentina; Luerssen, Thomas G; Jea, Andrew

2015-08-28

OBJECT Currently there is no standardized tool for assessment of neurosurgical resident performance in the operating room. In light of enhanced requirements issued by the Accreditation Council for Graduate Medical Education's Milestone Project and the Matrix Curriculum Project from the Society of Neurological Surgeons, the implementation of such a tool seems essential for objective evaluation of resident competence. Beyond compliance with governing body guidelines, objective assessment tools may be useful to direct early intervention for trainees performing below the level of their peers so that they may be given more hands-on teaching, while strong residents can be encouraged by faculty members to progress to conducting operations more independently with passive supervision. The aims of this study were to implement a validated assessment tool for evaluation of operative skills in pediatric neurosurgery and determine its feasibility and reliability. METHODS All neurosurgery residents completing their pediatric rotation over a 6-month period from January 1, 2014, to June 30, 2014, at the authors' institution were enrolled in this study. For each procedure, residents were evaluated by means of a form, with one copy being completed by the resident and a separate copy being completed by the attending surgeon. The evaluation form was based on the validated Objective Structured Assessment of Technical Skills for Surgery (OSATS) and used a 5-point Likert-type scale with 7 categories: respect for tissue; time and motion; instrument handling; knowledge of instruments; flow of operation; use of assistants; and knowledge of specific procedure. Data were then stratified by faculty versus resident (self-) assessment; postgraduate year level; and difficulty of procedure. Descriptive statistics (means and SDs) were calculated, and the results were compared using the Wilcoxon signed-rank test and Student t-test. A p value assessment scores overall or in any of the 7 domains scores

Cryo Testing of tbe James Webb Space Telescope's Integrated Science Instrument Module

Science.gov (United States)

VanCampen, Julie

2004-01-01

The Integrated Science Instrument Module (ISIM) of the James Webb Space Telescope will be integrated and tested at the Environmental Test Facilities at Goddard Space Flight Center (GSFC). The cryogenic thermal vacuum testing of the ISIM will be the most difficult and problematic portion of the GSFC Integration and Test flow. The test is to validate the coupled interface of the science instruments and the ISIM structure and to sufficiently stress that interface while validating image quality of the science instruments. The instruments and the structure are not made from the same materials and have different CTE. Test objectives and verification rationale are currently being evaluated in Phase B of the project plan. The test program will encounter engineering challenges and limitations, which are derived by cost and technology many of which can be mitigated by facility upgrades, creative GSE, and thorough forethought. The cryogenic testing of the ISIM will involve a number of risks such as the implementation of unique metrology techniques, mechanical, electrical and optical simulators housed within the cryogenic vacuum environment. These potential risks are investigated and possible solutions are proposed.

Simple Instrumental and Visual Tests for Nonlaboratory Environmental Control

Directory of Open Access Journals (Sweden)

L. P. Eksperiandova

2016-01-01

Full Text Available Proposed are simple and available techniques that can be used for rapid and reliable environmental control specifically of natural water by means of instrumental and visual tests in outdoor conditions. Developed are the chemical colorimetric modes for fast detection of socially dangerous trace impurities in water such as Co(II, Pd(II, and Rh(III as well as NO2--ions and Fe(III serving as model impurities. Application of portable digital devices and scanner allows estimating the color coordinates and increasing the accuracy and sensitivity of the tests. The combination of complex formation with preconcentration of colored complexes replaces the sensitive but time-consuming and capricious kinetic method that is usually used for this purpose at the more convenient and reliable colorimetric method. As the test tools, the following ones are worked out: polyurethane foam tablets with sorbed colored complexes, the two-layer paper sandwich packaged in slide adapter and saturated by reagents, and polyethylene terephthalate blister with dried reagents. Fast analysis of polyurethane foam tablets is realized using a pocket digital RGB-colorimeter or portable photometer. Express analysis of two-layer paper sandwich or polyethylene terephthalate blister is realized by visual and instrumental tests. The metrological characteristics of the developed visual and instrumental express analysis techniques are estimated.

Tests of arc-welding-related EMI effects on startup instrumentation

International Nuclear Information System (INIS)

Qian, T.; Kalechstein, W.; Cosgrove, D.

1996-01-01

The tests described in this paper were conducted to characterize the effects that electromagnetic interference (EMI), from arc welding, has on startup instrumentation (SUI). This paper reviews the results of a literature search on EMI resulting from arc welding and gives the objective and scope of the tests conducted and describes the test equipment and setting, and test procedure and results. Are-welding-related EMI levels in an SUI system were measured to determine the dominant source of interference, the coupling path and the susceptible part of the SUI system. The effectiveness of easily implemented improvements in reducing the level of EMI in the SUI system were also tested. Recommendations are provided on how to eliminate or reduce the EMI effects on sensitive nuclear instruments. (author)

Testing as an inevitable instrument in today's language learning ...

African Journals Online (AJOL)

In the foregoing analysis, we have unequivocably declared that testing or assessment is an inevitable instrument in present day's language learning environment and that testing is the other side of teaching itself. In teaching any aspect of language, learner must be tested to determine the progress made so far as well as ...

Development of Welding and Instrumentation Technology for Nuclear Fuel Test Rod

International Nuclear Information System (INIS)

Joung, Chang Young; Ahn, Sung Ho; Heo, Sung Ho; Hong, Jin Tae; Kim, Ka Hye

2013-01-01

It is necessary to develop various types of welding, instrumentation and helium gas filling techniques that can conduct TIG spot welding exactly at a pin-hole of the end-cap on the nuclear fuel rod to fill up helium gas. The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rod. To manufacture the nuclear fuel test rod, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rod jointing the various sensors and end-caps on a fuel cladding tube, which is charged with fuel pellets and component parts. We therefore designed and fabricated an orbital TIG welding system and a laser welding system. This paper describes not only some experiment results from weld tests for the parts of a nuclear fuel test rod, but also the contents for the instrumentation process of the dummy fuel test rod installed with the C-type T. C. A dummy nuclear fuel test rod was successfully fabricated with the welding and instrumentation technologies acquired with various tests. In the test results, the round welding has shown a good weldability at both the orbital TIG welding system and the fiber laser welding system. The spot welding to fill up helium gas has shown a good welding performance at a welding current of 30A, welding time of 0.4 sec and gap of 1 mm in a helium gas atmosphere. The soundness of the nuclear fuel test rod sealed by a mechanical sealing method was confirmed by helium leak tests and microstructural analyses

Development of Welding and Instrumentation Technology for Nuclear Fuel Test Rod

Energy Technology Data Exchange (ETDEWEB)

Joung, Chang Young; Ahn, Sung Ho; Heo, Sung Ho; Hong, Jin Tae; Kim, Ka Hye [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-10-15

It is necessary to develop various types of welding, instrumentation and helium gas filling techniques that can conduct TIG spot welding exactly at a pin-hole of the end-cap on the nuclear fuel rod to fill up helium gas. The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rod. To manufacture the nuclear fuel test rod, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rod jointing the various sensors and end-caps on a fuel cladding tube, which is charged with fuel pellets and component parts. We therefore designed and fabricated an orbital TIG welding system and a laser welding system. This paper describes not only some experiment results from weld tests for the parts of a nuclear fuel test rod, but also the contents for the instrumentation process of the dummy fuel test rod installed with the C-type T. C. A dummy nuclear fuel test rod was successfully fabricated with the welding and instrumentation technologies acquired with various tests. In the test results, the round welding has shown a good weldability at both the orbital TIG welding system and the fiber laser welding system. The spot welding to fill up helium gas has shown a good welding performance at a welding current of 30A, welding time of 0.4 sec and gap of 1 mm in a helium gas atmosphere. The soundness of the nuclear fuel test rod sealed by a mechanical sealing method was confirmed by helium leak tests and microstructural analyses.

Nuclear instrumentation evaluation and analysis

International Nuclear Information System (INIS)

Park, Suk Jun; Han, Sang Joon; Chung, Chong Eun; Han, Kwang Soo; Kim, Dong Hwa; Park, Byung Hae; Moon, Je Sun; Lee, Chel Kwon; Song, Ki Sang; Choi, Myung Jin; Kim, Seung Bok; Kim, Jung Bok

1986-12-01

This project provides the program for improving instrumentation reliability as well as developing a cost-effective preventive maintenance activity through evaluation and analysis of nuclear instrumentation concerning pilot plants, large-scale test facilities and various laboratories on KAERI site. In addition, it discusses the program for enhancing safe operations and improving facility availability through establishment of maintenance technology. (Author)

Operation Grenadier. Onsite radiological safety report for announced nuclear tests, October 1984-September 1985

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1986-09-01

Grenadier was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1984 through September 30, 1985. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeros before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

Mid Infrared Instrument cooler subsystem test facility overview

Science.gov (United States)

Moore, B.; Zan, J.; Hannah, B.; Chui, T.; Penanen, K.; Weilert, M.

2017-12-01

The Cryocooler for the Mid Infrared Instrument (MIRI) on the James Webb Space Telescope (JWST) provides cooling at 6.2K on the instrument interface. The cooler system design has been incrementally documented in previous publications [1][2][3][4][5]. It has components that traverse three primary thermal regions on JWST: Region 1, approximated by 40K; Region 2, approximated by 100K; and Region 3, which is at the allowable flight temperatures for the spacecraft bus. However, there are several sub-regions that exist in the transition between primary regions and at the heat reject interfaces of the Cooler Compressor Assembly (CCA) and Cooler Control Electronics Assembly (CCEA). The design and performance of the test facility to provide a flight representative thermal environment for acceptance testing and characterization of the complete MIRI cooler subsystem are presented.

Analysis of in-core coolant temperatures of FFTF instrumented fuels tests at full power

International Nuclear Information System (INIS)

Hoth, C.W.

1981-01-01

Two full size highly instrumented fuel assemblies were inserted into the core of the Fast Flux Test Facility in December of 1979. The major objectives of these instrumented tests are to provide verification of the FFTF core conditions and to characterize temperature patterns within FFTF driver fuel assemblies. A review is presented of the results obtained during the power ascents and during irradiation at a constant reactor power of 400 MWt. The results obtained from these instrumented tests verify the conservative nature of the design methods used to establish core conditions in FFTF. The success of these tests also demonstrates the ability to design, fabricate, install and irradiate complex, instrumented fuel tests in FFTF using commercially procured components

Computer-aided testing and operational aids for PARR-1 nuclear reactor

International Nuclear Information System (INIS)

Ansari, S.A.

1990-01-01

The utilization of the plant computer of Pakistan Research Reactor (PARR-1) for automatic periodic testing of nuclear instrumentation in the reactor is described. Computer algorithms have been developed for on-line acquisition and real-time processing of nuclear channel signals. The mean value, standard deviation, and probability distributions of nuclear channel signals are obtained in real time, and the computer generates a warning message if the signal error exceeds the maximum permissible error. In this way a faulty channel is automatically identified. Other real-time algorithms are also described that assist the operator in safe reactor operation by automatically computing approach-to-criticality during reactor start-up and the control rod worth determination

Instrumental intelligent test of food sensory quality as mimic of human panel test combining multiple cross-perception sensors and data fusion

International Nuclear Information System (INIS)

Ouyang, Qin; Zhao, Jiewen; Chen, Quansheng

2014-01-01

Highlights: • To develop a novel instrumental intelligent test methodology for food sensory analysis. • A novel data fusion was used in instrumental intelligent test methodology. • Linear and nonlinear tools were comparatively used for modeling. • The instrumental test methodology can be imitative of human test behavior. - Abstract: Instrumental test of food quality using perception sensors instead of human panel test is attracting massive attention recently. A novel cross-perception multi-sensors data fusion imitating multiple mammal perception was proposed for the instrumental test in this work. First, three mimic sensors of electronic eye, electronic nose and electronic tongue were used in sequence for data acquisition of rice wine samples. Then all data from the three different sensors were preprocessed and merged. Next, three cross-perception variables i.e., color, aroma and taste, were constructed using principal components analysis (PCA) and multiple linear regression (MLR) which were used as the input of models. MLR, back-propagation artificial neural network (BPANN) and support vector machine (SVM) were comparatively used for modeling, and the instrumental test was achieved for the comprehensive quality of samples. Results showed the proposed cross-perception multi-sensors data fusion presented obvious superiority to the traditional data fusion methodologies, also achieved a high correlation coefficient (>90%) with the human panel test results. This work demonstrated that the instrumental test based on the cross-perception multi-sensors data fusion can actually mimic the human test behavior, therefore is of great significance to ensure the quality of products and decrease the loss of the manufacturers

Instrumental intelligent test of food sensory quality as mimic of human panel test combining multiple cross-perception sensors and data fusion

Energy Technology Data Exchange (ETDEWEB)

Ouyang, Qin; Zhao, Jiewen; Chen, Quansheng, E-mail: qschen@ujs.edu.cn

2014-09-02

Highlights: • To develop a novel instrumental intelligent test methodology for food sensory analysis. • A novel data fusion was used in instrumental intelligent test methodology. • Linear and nonlinear tools were comparatively used for modeling. • The instrumental test methodology can be imitative of human test behavior. - Abstract: Instrumental test of food quality using perception sensors instead of human panel test is attracting massive attention recently. A novel cross-perception multi-sensors data fusion imitating multiple mammal perception was proposed for the instrumental test in this work. First, three mimic sensors of electronic eye, electronic nose and electronic tongue were used in sequence for data acquisition of rice wine samples. Then all data from the three different sensors were preprocessed and merged. Next, three cross-perception variables i.e., color, aroma and taste, were constructed using principal components analysis (PCA) and multiple linear regression (MLR) which were used as the input of models. MLR, back-propagation artificial neural network (BPANN) and support vector machine (SVM) were comparatively used for modeling, and the instrumental test was achieved for the comprehensive quality of samples. Results showed the proposed cross-perception multi-sensors data fusion presented obvious superiority to the traditional data fusion methodologies, also achieved a high correlation coefficient (>90%) with the human panel test results. This work demonstrated that the instrumental test based on the cross-perception multi-sensors data fusion can actually mimic the human test behavior, therefore is of great significance to ensure the quality of products and decrease the loss of the manufacturers.

Fabrication and Testing of a Modular Micro-Pocket Fission Detector Instrumentation System for Test Nuclear Reactors

Science.gov (United States)

Reichenberger, Michael A.; Nichols, Daniel M.; Stevenson, Sarah R.; Swope, Tanner M.; Hilger, Caden W.; Roberts, Jeremy A.; Unruh, Troy C.; McGregor, Douglas S.

2018-01-01

Advancements in nuclear reactor core modeling and computational capability have encouraged further development of in-core neutron sensors. Measurement of the neutron-flux distribution within the reactor core provides a more complete understanding of the operating conditions in the reactor than typical ex-core sensors. Micro-Pocket Fission Detectors have been developed and tested previously but have been limited to single-node operation and have utilized highly specialized designs. The development of a widely deployable, multi-node Micro-Pocket Fission Detector assembly will enhance nuclear research capabilities. A modular, four-node Micro-Pocket Fission Detector array was designed, fabricated, and tested at Kansas State University. The array was constructed from materials that do not significantly perturb the neutron flux in the reactor core. All four sensor nodes were equally spaced axially in the array to span the fuel-region of the reactor core. The array was filled with neon gas, serving as an ionization medium in the small cavities of the Micro-Pocket Fission Detectors. The modular design of the instrument facilitates the testing and deployment of numerous sensor arrays. The unified design drastically improved device ruggedness and simplified construction from previous designs. Five 8-mm penetrations in the upper grid plate of the Kansas State University TRIGA Mk. II research nuclear reactor were utilized to deploy the array between fuel elements in the core. The Micro-Pocket Fission Detector array was coupled to an electronic support system which has been specially developed to support pulse-mode operation. The Micro-Pocket Fission Detector array composed of four sensors was used to monitor local neutron flux at a constant reactor power of 100 kWth at different axial locations simultaneously. The array was positioned at five different radial locations within the core to emulate the deployment of multiple arrays and develop a 2-dimensional measurement of

Dynamic instrumentation for the K-1600 seismic test facility recommissioning

International Nuclear Information System (INIS)

VanHoy, B.W.

1991-01-01

Martin Marietta Energy Systems, Inc. is the site contractor to the Department of Energy (DOE) for three Oak Ridge, Tennessee sites, the site in Portsmouth, Ohio, and the site in Paducah, Kentucky. To provide a focus for all natural phenomena engineering related problems, Martin Marietta Energy Systems, Inc. established the Center for Natural Phenomena Engineering under the technical direction of Dr. James E. Beavers. One of the Center's mandates is the determination of seismic properties of building structures containing sensitive processes. This has led to the recommissioning of the K-1600 Seismic Test Facility. The biaxial shake table in this facility was constructed during the eighties for seismic qualification of equipment of the Gas Centrifuge Enrichment Plant. After construction of the plant was terminated the Seismic Test Facility was placed in standby where it was left for six years. The facility's original instrumentation was evaluated versus the required instrumentation to augment its new expanded mission parameters. Instrumentation selection involving technology changes, age and attrition, and the new mission goals are discussed in this paper along with the rationale and budget that were involved with each decision. The testing potential of this facility along with the instrumentation upgrades necessary to accomplish these new tasks for the Center for Natural Phenomena Engineering are considered. New uses such as seismic qualification of equipment utilized in DOE's missions at various sites and waste treatment are proposed. This instrumentation selection is discussed in detail to show the rationale and proposed used of the facility as well as the capabilities of this DOE resource

Portable neutron and gamma-radiation instruments

International Nuclear Information System (INIS)

Murray, W.S.; Butterfield, K.B.

1990-01-01

This paper reports on the design and building of a smart neutron and gamma-radiation detection systems with embedded microprocessors programmed in the FORTH language. These portable instruments can be battery-powered and can provide many analysis functions not available in most radiation detectors. Local operation of the instruments is menu-driven through a graphics liquid crystal display and hex keypad; remote operation is through a serial communications link. While some instruments simply count particles, others determine the energy of the radiation as well as the intensity. The functions the authors have provided include absolute source-strength determination. Feynmann variance analysis, sequential-probability ratio test, and time-history recording

Operational parameters study of IPR-R1 TRIGA research reactor using virtual instruments

International Nuclear Information System (INIS)

Pinto, Antonio Juscelino; Mesquita, Amir Zacarias; Lameiras, Fernando Soares

2013-01-01

The instrumentation of nuclear reactors is designed with the principle of reliability, redundancy and diversification of control systems. Reliable monitoring of the parameters involved in the chain reaction is of great importance regarding efficiency and operational safety of the installation. The main goal of the simulation system in this proposed paper is to provide the study and improvement in understanding how these operational variables are interrelated and their behavior especially those related to neutronic and thermohydraulics. The work will be developed using the software LabVIEW ® (Laboratory Virtual Instruments Engineering Workbench). The program will enable the study of the variables involved in the operation of the installation throughout its operating range, for instance, a few mW up to 250 kW. The IPR-R1 TRIGA is a research nuclear reactor placed in open pool and cooled by light water with natural circulation. It is located at the Nuclear Technology Development Center (CDTN), in Belo Horizonte Brazil. The developing system employs the modern concept of virtual instruments (VIs), using microprocessors and visual interface on video monitors. LabVIEW ® breaks the paradigm of text-based programming language, for programming based on icons. The system will enable the use of this reactor in training and personnel training in the nuclear field. The work follows the recommendations of the International Atomic Energy Agency (IAEA), which has encouraged its members to develop strategic plans in order to use their research reactors. (author)

Operational parameters study of IPR-R1 TRIGA research reactor using virtual instruments

Energy Technology Data Exchange (ETDEWEB)

Pinto, Antonio Juscelino; Mesquita, Amir Zacarias; Lameiras, Fernando Soares, E-mail: ajp@cdtn.br, E-mail: amir@cdtn.br, E-mail: fsl@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2013-07-01

The instrumentation of nuclear reactors is designed with the principle of reliability, redundancy and diversification of control systems. Reliable monitoring of the parameters involved in the chain reaction is of great importance regarding efficiency and operational safety of the installation. The main goal of the simulation system in this proposed paper is to provide the study and improvement in understanding how these operational variables are interrelated and their behavior especially those related to neutronic and thermohydraulics. The work will be developed using the software LabVIEW ® (Laboratory Virtual Instruments Engineering Workbench). The program will enable the study of the variables involved in the operation of the installation throughout its operating range, for instance, a few mW up to 250 kW. The IPR-R1 TRIGA is a research nuclear reactor placed in open pool and cooled by light water with natural circulation. It is located at the Nuclear Technology Development Center (CDTN), in Belo Horizonte Brazil. The developing system employs the modern concept of virtual instruments (VIs), using microprocessors and visual interface on video monitors. LabVIEW ® breaks the paradigm of text-based programming language, for programming based on icons. The system will enable the use of this reactor in training and personnel training in the nuclear field. The work follows the recommendations of the International Atomic Energy Agency (IAEA), which has encouraged its members to develop strategic plans in order to use their research reactors. (author)

14 CFR 33.51 - Operation test.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Operation test. 33.51 Section 33.51... STANDARDS: AIRCRAFT ENGINES Block Tests; Reciprocating Aircraft Engines § 33.51 Operation test. The operation test must include the testing found necessary by the Administrator to demonstrate backfire...

Fabrication of Non-instrumented capsule for DUPIC simulated fuel irradiation test in HANARO

Energy Technology Data Exchange (ETDEWEB)

Kim, B.G.; Kang, Y.H.; Park, S.J.; Shin, Y.T. [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-10-01

In order to develope DUPIC nuclear fuel, the irradiation test for simulated DUPIC fuel was planed using a non-instrumented capsule in HANARO. Because DUPIC fuel is highly radioactive material the non-instrumented capsule for an irradiation test of simulated DUPIC fuel in HANARO was designed to remotely assemble and disassemble in hot cell. And then, according to the design requirements the non-instrumented DUPIC capsule was successfully manufactured. Also, the manufacturing technologies of the non-instrumented capsule for irradiating the nuclear fuel in HANARO were established, and the basic technology for the development of the instrumented capsule technology was accumulated. This report describes the manufacturing of the non-instrumented capsule for simulated DUPIC fuel. And, this report will be based to develope the instrumented capsule, which will be utilized to irradiate the nuclear fuel in HANARO. 26 refs., 4 figs. (Author)

14 CFR 33.89 - Operation test.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Operation test. 33.89 Section 33.89... STANDARDS: AIRCRAFT ENGINES Block Tests; Turbine Aircraft Engines § 33.89 Operation test. (a) The operation test must include testing found necessary by the Administrator to demonstrate— (1) Starting, idling...

The installation and operation of the seismic instrumentation in Korean NPPs

International Nuclear Information System (INIS)

Lee, Kye Hyun; Baek, Yong Lak; Chung, Yun Suk

1994-01-01

Including the 7 October, 1978, Hongsung earthquake, many earthquakes have occurred in our country. The Korean peninsular is no longer a safety zone against earthquakes, and there are possibilities of the damage they cause. So therefore, it is essential to verify the safety of the safety-related facilities in the event of an earthquake. If an earthquake occurs, seismic instrumentation provides information on the vibratory ground motion and resultant vibratory responses of representative safety-related structures and equipment so that an evaluation can be made immediately as to whether or not the design response spectra have been exceeded. In this paper, general descriptions of the seismic instrumentation installed in domestic NPPs will be discussed; this includes instrument type and location, the Operating Basis Earthquake (OBE) exceedance criteria, and processing and evaluation of earthquake response data, and items to be studied for further enhancement of post-earthquake evaluation techniques are presented

Temperature buffer test. Dismantling operation

Energy Technology Data Exchange (ETDEWEB)

Aakesson, Mattias [Clay Technology AB, Lund (Sweden)

2010-12-15

The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aespoe HRL. It was installed during the spring of 2003. Two heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by bentonite in the usual way, whereas the upper heater was surrounded by a ring of sand. The test was dismantled and sampled during a period from the end of October 2009 to the end of April 2010, and this report describes this operation. Different types of samples have been obtained during this operation. A large number of diameter 50 mm bentonite cores have been taken for analysis of water content and density. Large pieces, so-called big sectors, have been taken for hydro-mechanical and chemical characterizations. Finally, there has been an interest to obtain different types of interface samples in which bentonite were in contact with sand, iron or concrete. One goal has been to investigate the retrievability of the upper heater, given the possibility to remove the surrounding sand shield, and a retrieval test has therefore been performed. The sand in the shield was first removed with an industrial vacuum cleaner after loosening the material through mechanical means (with hammer drill and core machine). A front loader was subsequently used for applying a sufficient lifting force to release the heater from the bentonite underneath. The experiment has been documented in different aspects: measurements of the coordinate (height or radius) of different interfaces (between bentonite blocks and between bentonite and sand); verification of sensor positions and retrieval of sensors for subsequent

Temperature buffer test. Dismantling operation

International Nuclear Information System (INIS)

Aakesson, Mattias

2010-12-01

The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aespoe HRL. It was installed during the spring of 2003. Two heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by bentonite in the usual way, whereas the upper heater was surrounded by a ring of sand. The test was dismantled and sampled during a period from the end of October 2009 to the end of April 2010, and this report describes this operation. Different types of samples have been obtained during this operation. A large number of diameter 50 mm bentonite cores have been taken for analysis of water content and density. Large pieces, so-called big sectors, have been taken for hydro-mechanical and chemical characterizations. Finally, there has been an interest to obtain different types of interface samples in which bentonite were in contact with sand, iron or concrete. One goal has been to investigate the retrievability of the upper heater, given the possibility to remove the surrounding sand shield, and a retrieval test has therefore been performed. The sand in the shield was first removed with an industrial vacuum cleaner after loosening the material through mechanical means (with hammer drill and core machine). A front loader was subsequently used for applying a sufficient lifting force to release the heater from the bentonite underneath. The experiment has been documented in different aspects: measurements of the coordinate (height or radius) of different interfaces (between bentonite blocks and between bentonite and sand); verification of sensor positions and retrieval of sensors for subsequent

Advanced In-Pile Instrumentation for Materials Testing Reactors

Science.gov (United States)

Rempe, J. L.; Knudson, D. L.; Daw, J. E.; Unruh, T. C.; Chase, B. M.; Davis, K. L.; Palmer, A. J.; Schley, R. S.

2014-08-01

The U.S. Department of Energy sponsors the Advanced Test Reactor (ATR) National Scientific User Facility (NSUF) program to promote U.S. research in nuclear science and technology. By attracting new research users - universities, laboratories, and industry - the ATR NSUF facilitates basic and applied nuclear research and development, advancing U.S. energy security needs. A key component of the ATR NSUF effort is to design, develop, and deploy new in-pile instrumentation techniques that are capable of providing real-time measurements of key parameters during irradiation. This paper describes the strategy developed by the Idaho National Laboratory (INL) for identifying instrumentation needed for ATR irradiation tests and the program initiated to obtain these sensors. New sensors developed from this effort are identified, and the progress of other development efforts is summarized. As reported in this paper, INL researchers are currently involved in several tasks to deploy real-time length and flux detection sensors, and efforts have been initiated to develop a crack growth test rig. Tasks evaluating `advanced' technologies, such as fiber-optics based length detection and ultrasonic thermometers, are also underway. In addition, specialized sensors for real-time detection of temperature and thermal conductivity are not only being provided to NSUF reactors, but are also being provided to several international test reactors.

Project W-320, operational test procedure OTP-320-003 test report

International Nuclear Information System (INIS)

Bevins, R.R.

1998-01-01

This report documents and summarizes the results of OTP-320-003 Project W-320 Operational Testing of the WRSS Supernate Transfer System. Project W-320 Operational Test OTP-320-003 was performed to verify components of the Waste Retrieval Sluicing System (WRSS) supernate transfer system functioned as designed following construction completion and turnover to operations. All equipment operation was performed by Tank Farms Operations personnel following the operational test procedure and referenced operating procedures. Supernate Transfer line Flushing System Testing was completed over the course of approximately 4 weeks as tank farm conditions and configuration, equipment availability, and operations resources allowed. All testing was performed with the 702-AZ ventilation system and the 296-P-16 ventilation systems in operation. Test procedure OTP-320-003 required two revisions during testing to incorporate Procedure Changes Authorizations (PCAs) necessary to facilitate testing. Various sections of testing are documented on each procedure revision. The completed test procedure is included as Attachment A. Exception Reports generated during the course of testing are included as Attachment B

Thermal vacuum test of space equipment: tests of SIR-2 instrument Chandrayaan-1 mission

Science.gov (United States)

Sitek, P.

2008-11-01

We describe the reasons of proceeding Thermal-Vacuum tests for space electronic. We will answer on following questions: why teams are doing TV tests, what kind of phases should be simulated, which situations are the most critical during TV tests, what kind of results should be expected, which errors can be detect. As an example, will be shown TV-test of SIR-2 instrument for Chandrayaan-1 moon mission.

Acoustic emission measurement during instrumented impact tests

International Nuclear Information System (INIS)

Crostack, H.A.; Engelhardt, A.H.

1983-01-01

Results of instrumented impact tests are discussed. On the one hand the development of the loading process at the hammer tup was recorded by means of a piezoelectric transducer. This instrumentation supplied a better representation of the load versus time than the conventional strain gauges. On the other hand the different types of acoustic emission occurring during a test could be separated. The acoustic emission released at the impact of the hammer onto the specimen is of lower frequency and its spectrum is strongly decreasing with increasing frequency. Plastic deformation also emits signals of lower frequency that are of quasi-continuous character. Both signal types can be discriminated by filtering. As a consequence typical burst signal were received afterwards that can be correlated with crack propagation. Their spectra exhibit considerable portions up to about 1.9 MHz. The development in time of the burst signals points to the kind of crack propagation resp. its sequence of appearance. However, definitive comparison between load and acoustic emission should become possible, only when the disadvantages of the common load measurement can be reduced, e.g. by determining the load directly at the specimen instead of the hammer tup

Cyclic fatigue resistance of ProTaper Universal instruments when subjected to static and dynamic tests.

Science.gov (United States)

Lopes, Hélio P; Britto, Izabelle M O; Elias, Carlos N; Machado de Oliveira, Julio C; Neves, Mônica A S; Moreira, Edson J L; Siqueira, José F

2010-09-01

This study evaluated the number of cycles to fracture of ProTaper Universal S2 instruments when subjected to static and dynamic cyclic fatigue tests. ProTaper Universal S2 instruments were used until fracture in an artificial curved canal under rotational speed of 300 rpm in either a static or a dynamic test model. Afterward, the length of the fractured segments was measured and fractured surfaces and helical shafts analyzed by scanning electron microscopy (SEM). The number of cycles to fracture was significantly increased when instruments were tested in the dynamic model (Pductile mode. Plastic deformation was not observed in the helical shaft of fractured instruments. The number of cycles to fracture ProTaper Universal S2 instruments significantly increased with the use of instruments in a dynamic cyclic fatigue test compared with a static model. These findings reinforce the need for performing continuous pecking motions during rotary instrumentation of curved root canals. Copyright (c) 2010 Mosby, Inc. All rights reserved.

The wavelength frame multiplication chopper system for the ESS test beamline at the BER II reactor—A concept study of a fundamental ESS instrument principle

International Nuclear Information System (INIS)

Strobl, M.; Bulat, M.; Habicht, K.

2013-01-01

Contributing to the design update phase of the European Spallation Source ESS–scheduled to start operation in 2019–a test beamline is under construction at the BER II research reactor at Helmholtz Zentrum Berlin (HZB). This beamline offers experimental test capabilities of instrument concepts viable for the ESS. The experiments envisaged at this dedicated beamline comprise testing of components as well as of novel experimental approaches and methods taking advantage of the long pulse characteristic of the ESS source. Therefore the test beamline will be equipped with a sophisticated chopper system that provides the specific time structure of the ESS and enables variable wavelength resolutions via wavelength frame multiplication (WFM), a fundamental instrument concept beneficial for a number of instruments at ESS. We describe the unique chopper system developed for these purposes, which allows constant wavelength resolution for a wide wavelength band. Furthermore we discuss the implications for the conceptual design for related instrumentation at the ESS

Operational test report for LERF Basin 242AL-44 integrity test

International Nuclear Information System (INIS)

Galioto, T.M.

1994-01-01

This operational test report documents the results of LERF operational testing per operational test procedure (OTP) TFPE-WP-0231, ''LERF Basin Integrity Testing.'' The primary purpose of the OTP was to resolve test exceptions generated as a result of TFPE-WP-0184. The TOP was prepared and performed in accordance with WHC-SD-534-OTP-002, ''Operational Test Plan for the 242-A Evaporator Upgrades and the Liquid Effluent Retention Facility.'' WHC-S-086, ''Specification for Operational Testing of the Liquid Effluent Retention Facility, Basin Integrity Testing,'' identified the test requirements and acceptance criteria. The completed, signed-off test procedure is contained in Appendix A. The test log is contained in Appendix B. Section 2.1 describes all the test exceptions written during performance of the Operational Test Procedure. The test revisions generated during the testing are discussed in Section 2.2. The dispositioned test exception forms are contained in Appendix C

Static Load Test on Instrumented Pile - Field Data and Numerical Simulations

Science.gov (United States)

Krasiński, Adam; Wiszniewski, Mateusz

2017-09-01

Static load tests on foundation piles are generally carried out in order to determine load - the displacement characteristic of the pile head. For standard (basic) engineering practices this type of test usually provides enough information. However, the knowledge of force distribution along the pile core and its division into the friction along the shaft and the resistance under the base can be very useful. Such information can be obtained by strain gage pile instrumentation [1]. Significant investigations have been completed on this technology, proving its utility and correctness [8], [10], [12]. The results of static tests on instrumented piles are not easy to interpret. There are many factors and processes affecting the final outcome. In order to understand better the whole testing process and soil-structure behavior some investigations and numerical analyses were done. In the paper, real data from a field load test on instrumented piles is discussed and compared with numerical simulation of such a test in similar conditions. Differences and difficulties in the results interpretation with their possible reasons are discussed. Moreover, the authors used their own analytical solution for more reliable determination of force distribution along the pile. The work was presented at the XVII French-Polish Colloquium of Soil and Rock Mechanics, Łódź, 28-30 November 2016.

ER-E3 regulation. Minimal instrumentation that must operate nuclear medicine in Cuba

International Nuclear Information System (INIS)

2015-01-01

The purpose of this regulation is to define the instrumentation that must exist in any institution conducting the practice of nuclear medicine in Cuba. This regulation emphasizes two aspects: The minimum equipment necessary to operate a nuclear medicine laboratory for use 'in vitro' and the minimum equipment required to operate a Nuclear Medicine use 'in vivo'

Vibration test report for in-chimney bracket and instrumented fuel assembly

Energy Technology Data Exchange (ETDEWEB)

Ryu, Jeong Soo; Yoon, D. B.; Cho, Y. G.; Ahn, G. H.; Lee, J. H.; Park, J.H

2000-10-01

The vibration levels of in-chimney bracket structure which is installed in reactor chimney and instrumented fuel assembly(Type-B Bundle) are investigated under the steady state normal operating condition of the reactor. For this purpose, 4 acceleration data on the guide tube of the instrumented fuel assembly and in-chimney bracket structures subjected to fluid induced vibration are measured. For the analysis of the vibration data, vibration analysis program which can perform basic time and frequency domain analysis, is prepared, and its reliability is verified by comparing the analysis results with those of commercial analysis program(I-DEAS). In time domain analysis, maximum amplitudes, and RMS values of accelerations and displacements from the measured vibration signal, are obtained. The frequency components of the vibration data are analyzed by using the frequency domain analysis. These analysis results show that the levels of the measured vibrations are within the allowable level, and the low frequency component near 10 Hz is dominant in the vibration signal. For the evaluation of the structural integrity on the in-chimney bracket and related structures including the instrumented fuel assembly, the static analysis for ANSYS finite element model is carried out. These analysis results show that the maximum stresses are within the allowable stresses of the ASME code, and the maximum displacement of the top of the flow tube is within the displacement limit. Therefore any damage on the structural integrity is not expected when the irradiation test is performed using the in-chimney bracket.

Vibration test report for in-chimney bracket and instrumented fuel assembly

International Nuclear Information System (INIS)

Ryu, Jeong Soo; Yoon, D. B.; Cho, Y. G.; Ahn, G. H.; Lee, J. H.; Park, J.H.

2000-10-01

The vibration levels of in-chimney bracket structure which is installed in reactor chimney and instrumented fuel assembly(Type-B Bundle) are investigated under the steady state normal operating condition of the reactor. For this purpose, 4 acceleration data on the guide tube of the instrumented fuel assembly and in-chimney bracket structures subjected to fluid induced vibration are measured. For the analysis of the vibration data, vibration analysis program which can perform basic time and frequency domain analysis, is prepared, and its reliability is verified by comparing the analysis results with those of commercial analysis program(I-DEAS). In time domain analysis, maximum amplitudes, and RMS values of accelerations and displacements from the measured vibration signal, are obtained. The frequency components of the vibration data are analyzed by using the frequency domain analysis. These analysis results show that the levels of the measured vibrations are within the allowable level, and the low frequency component near 10 Hz is dominant in the vibration signal. For the evaluation of the structural integrity on the in-chimney bracket and related structures including the instrumented fuel assembly, the static analysis for ANSYS finite element model is carried out. These analysis results show that the maximum stresses are within the allowable stresses of the ASME code, and the maximum displacement of the top of the flow tube is within the displacement limit. Therefore any damage on the structural integrity is not expected when the irradiation test is performed using the in-chimney bracket

Quality control procedures applied to nuclear instruments. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2008-11-01

Quality Control (QC), test procedures for Nuclear Instrumentation are important for assurance of proper and safe operation of the instruments, especially with regard to equipment related to radiological safety, human health and national safety. Correct measurements of radiation parameters must be ensured, i.e., accurate measurement of the number of radioactive events, counting times and in some cases accurate measurements of the radiation energy and occurring time of the nuclear events. There are several kinds of testing on nuclear instruments, for example, type-testing done by suppliers, acceptance testing made by the end users, Quality Control tests after repair and Quality Assurance/Quality Controls tests made by end-users. All of these tests are based in many cases on practical guidelines or on the experience of the own specialist, the available standards on this topic also need to be adapted to specific instruments. The IAEA has provided nuclear instruments and supported the operational maintenance efforts of the Member States. Although Nuclear Instrumentation is continuously upgraded, some older or aged instruments are still in use and in good working condition. Some of these instruments may not, however, meet modern requirements for the end-user therefore, Member States, mostly those with emerging economies, modernize/refurbish such instruments to meet the end-user demands. As a result, new instrumentation which is not commercially available, or modernized/refurbished instruments, need to be tested or verified with QC procedures to meet national or international certification requirements. A technical meeting on QC procedures applied to nuclear instruments was organized in Vienna from 23 to 24 August 2007. Existing and required QC test procedures necessary for the verification of operation and measurement of the main characteristics of nuclear instruments was the focus of discussion at this meeting. Presentations made at the technical meeting provided

A multi-functional testing instrument for heat assisted magnetic recording media

International Nuclear Information System (INIS)

Yang, H. Z.; Chen, Y. J.; Leong, S. H.; An, C. W.; Ye, K. D.; Hu, J. F.; Yin, M. J.

2014-01-01

With recent developments in heat assisted magnetic recording (HAMR), characterization of HAMR media is becoming very important. We present a multi-functional instrument for testing HAMR media, which integrates HAMR writing, reading, and a micro-magneto-optic Kerr effect (μ-MOKE) testing function. A potential application of the present instrument is to make temperature dependent magnetic property measurement using a pump-probe configuration. In the measurement, the media is heated up by a heating (intense) beam while a testing (weak) beam is overlapped with the heating beam for MOKE measurement. By heating the media with different heating beam power, magnetic measurements by MOKE at different temperatures can be performed. Compared to traditional existing tools such as the vibrating sample magnetometer, the present instrument provides localized and efficient heating at the measurement spot. The integration of HAMR writing and μ-MOKE system can also facilitate a localized full investigation of the magnetic media by potential correlation of HAMR head independent write/read performance to localized magnetic properties

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

Energy Technology Data Exchange (ETDEWEB)

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

2000-05-15

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

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

International Nuclear Information System (INIS)

Enkvist, J.; Edland, A.; Svenson, Ola

2000-05-01

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

Characterization of the Goubau line for testing beam diagnostic instruments

Science.gov (United States)

Kim, S. Y.; Stulle, F.; Sung, C. K.; Yoo, K. H.; Seok, J.; Moon, K. J.; Choi, C. U.; Chung, Y.; Kim, G.; Woo, H. J.; Kwon, J.; Lee, I. G.; Choi, E. M.; Chung, M.

2017-12-01

One of the main characteristics of the Goubau line is that it supports a low-loss, non-radiated surface wave guided by a dielectric-coated metal wire. The dominant mode of the surface wave along the Goubau line is a TM01 mode, which resembles the pattern of the electromagnetic fields induced in the metallic beam pipe when the charged particle beam passes through it. Therefore, the Goubau line can be used for the preliminary bench test and performance optimization of the beam diagnostic instruments without requiring charged particle beams from the accelerators. In this paper, we discuss the basic properties of the Goubau line for testing beam diagnostic instruments and present the initial test results for button-type beam position monitors (BPMs). The experimental results are consistent with the theoretical estimations, which indicates that Goubau line allows effective testing of beam diagnostic equipment.

Commissioning Instrument for the GTC

Science.gov (United States)

Cuevas, S.; Sánchez, B.; Bringas, V.; Espejo, C.; Flores, R.; Chapa, O.; Lara, G.; Chavolla, A.; Anguiano, G.; Arciniega, S.; Dorantes, A.; González, J. L.; Montoya, J. M.; Toral, R.; Hernández, H.; Nava, R.; Devaney, N.; Castro, J.; Cavaller-Marqués, L.

2005-12-01

During the GTC integration phase, the Commissioning Instrument (CI) will be a diagnostic tool for performance verification. The CI features four operation modes: imaging, pupil imaging, Curvature WFS, and high resolution Shack-Hartmann WFS. This instrument was built by the Instituto de Astronomía UNAM and the Centro de Ingeniería y Desarrollo Industrial (CIDESI) under GRANTECAN contract after a public bid. In this paper we made a general instrument overview and we show some of the performance final results obtained when the Factory Acceptance tests previous to its transport to La Palma.

Instrumented Impact Testing: Influence of Machine Variables and Specimen Position

International Nuclear Information System (INIS)

Lucon, E.; McCowan, C. N.; Santoyo, R. A.

2008-01-01

An investigation has been conducted on the influence of impact machine variables and specimen positioning on characteristic forces and absorbed energies from instrumented Charpy tests. Brittle and ductile fracture behavior has been investigated by testing NIST reference samples of low, high and super-high energy levels. Test machine variables included tightness of foundation, anvil and striker bolts, and the position of the center of percussion with respect to the center of strike. For specimen positioning, we tested samples which had been moved away or sideways with respect to the anvils. In order to assess the influence of the various factors, we compared mean values in the reference (unaltered) and altered conditions; for machine variables, t-test analyses were also performed in order to evaluate the statistical significance of the observed differences. Our results indicate that the only circumstance which resulted in variations larger than 5 percent for both brittle and ductile specimens is when the sample is not in contact with the anvils. These findings should be taken into account in future revisions of instrumented Charpy test standards.

Instrumented Impact Testing: Influence of Machine Variables and Specimen Position

Energy Technology Data Exchange (ETDEWEB)

Lucon, E.; McCowan, C. N.; Santoyo, R. A.

2008-09-15

An investigation has been conducted on the influence of impact machine variables and specimen positioning on characteristic forces and absorbed energies from instrumented Charpy tests. Brittle and ductile fracture behavior has been investigated by testing NIST reference samples of low, high and super-high energy levels. Test machine variables included tightness of foundation, anvil and striker bolts, and the position of the center of percussion with respect to the center of strike. For specimen positioning, we tested samples which had been moved away or sideways with respect to the anvils. In order to assess the influence of the various factors, we compared mean values in the reference (unaltered) and altered conditions; for machine variables, t-test analyses were also performed in order to evaluate the statistical significance of the observed differences. Our results indicate that the only circumstance which resulted in variations larger than 5 percent for both brittle and ductile specimens is when the sample is not in contact with the anvils. These findings should be taken into account in future revisions of instrumented Charpy test standards.

Radiation Tests on the Complete System of the Instrumentation of the LHC Cryogenics at the CERN Neutrinos to Gran Sasso (CNGS) Test Facility

CERN Document Server

Gousiou, E; Casas Cubillos, J; de la Gama Serrano, J

2009-01-01

There are more than 6000 electronic cards for the instrumentation of the LHC cryogenics, housed in crates and distributed around the 27 km tunnel. Cards and crates will be exposed to a complex radiation field during the 10 years of LHC operation. Rad-tol COTS and rad-hard ASIC have been selected and individually qualified during the design phase of the cards. The test setup and the acquired data presented in this paper target the qualitative assessment of the compliance with the LHC radiation environment of an assembled system. It is carried out at the CNGS test facility which provides exposure to LHC-like radiation field.

The bone diagnostic instrument III: Testing mouse femora

Science.gov (United States)

Randall, Connor; Mathews, Phillip; Yurtsev, Eugene; Sahar, Nadder; Kohn, David; Hansma, Paul

2009-06-01

Here we describe modifications that allow the bone diagnostic instrument (BDI) [P. Hansma et al., Rev. Sci. Instrum. 79, 064303 (2008); Rev. Sci. Instrum. 77, 075105 (2006)], developed to test human bone, to test the femora of mice. These modifications include reducing the effective weight of the instrument on the bone, designing and fabricating new probe assemblies to minimize damage to the small bone, developing new testing protocols that involve smaller testing forces, and fabricating a jig for securing the smaller bones for testing. With these modifications, the BDI was used to test the hypothesis that short-term running has greater benefit on the mechanical properties of the femur for young growing mice compared to older, skeletally mature mice. We measured elastic modulus, hardness, and indentation distance increase (IDI), which had previously been shown to be the best discriminators in model systems known to exhibit differences in mechanical properties at the whole bone level. In the young exercised murine femora, the IDI was significantly lower than in young control femora. Since IDI has a relation to postyield properties, these results suggest that exercise during bone development increases post yield mechanical competence. We were also able to measure effects of aging on bone properties with the BDI. There was a significant increase in the IDI, and a significant decrease in the elastic modulus and hardness between the young and old groups. Thus, with the modifications described here, the BDI can take measurements on mouse bones and obtain statistically significant results.

Instruments for non-destructive evaluation of advanced test reactor inpile tubes

International Nuclear Information System (INIS)

Livingston, R.A.; Beller, L.S.; Edgett, S.M.

1986-01-01

The Advanced Test Reactor is a 250 MW LWR used primarily for irradiation testing of materials contained in inpile tubes that pass through the reactor core. These tubes provided the high pressure and temperature water environment required for the test specimens. The reactor cooling water surrounding the inpile tubes is at much lower pressure and temperature. The structural integrity of the inpile tubes is monitored by routine surveillance to ensure against unplanned reactor shutdowns to replace defective inpile tubes. The improved instruments developed for inpile tube surveillance include a bore profilometer, ultrasonic flaw detetion system and bore diameter gauges. The design and function of these improved instruments is presented

Evaluation of a draft standard on performance specifications for health physics instrumentation: results for environmental tests

International Nuclear Information System (INIS)

Kenoyer, J.L.; Swinth, K.L.; Mashburn, K.R.; Selby, J.M.

1984-06-01

Draft ANSI Standard N42.17 on performance specifications for health physics instrumentation is currently being evaluated by the Pacific Northwest Laboratory. Evaluation is performed by testing a cross-section of currently available instruments with testing procedures based on specifications of the standard and then determining the degree of conformance to the various elements of the proposed standard. Data will be presented on the performance of a cross-section of beta-gamma survey instruments under various environmental tests. Test results that will be presented include temperature effects, humidity effects, radio frequency (r.f.) susceptibility, ambient pressure effects, vibration effects, and shock effects. Tests performed to date show that most instruments will meet the temperature, humidity, and ambient pressure tests. A large variability is noted among instruments from the same or different vendors. Preliminary r.f. susceptibility tests have shown large artificial responses at some frequencies for specific instruments. The presentation will also include a discussion of procedures used in the testing and weaknesses identified in the proposed standard

Instrumentation and test of the Swiss LCT-coil

International Nuclear Information System (INIS)

Zichy, J.A.; Horvath, I.; Jakob, B.; Marinucci, C.; Vecsey, G.; Weymuth, P.; Zellweger, J.

1985-01-01

Just before Christmas 1983 the fabrication of the Swiss LCT-coil was finished. Tests at ambient temperature were performed on the factory site and after delivery in Oak Ridge. To avoid an undesirable delay of the rescheduled Partial-Array Test it was agreed to install the coil without its superconducting bus. In July 1984 the Swiss LCT-coil was successfully cooled down to LHe temperature together with the other two fully installed coils. Besides the cooling system, the instrumentation, measured parameters of the coil and some preliminary results obtained during the ongoing Partial-Array Test are presented

Nuclear electronic equipment for control and monitoring panel. Procedure guide for on-site tests of nuclear reactor instruments

International Nuclear Information System (INIS)

1975-10-01

By the use of a procedure for on-site testing of nuclear reactor instruments it should be possible to judge their ability to guarantee the reactor safety and availability at the moment of divergence or during operation. Such a procedure must therefore be created as a work implement for the quick and reliable installation of electronic devices necessary for nuclear reactor control and supervision. A standard document is proposed for this purpose, allowing a ''test programme'' to be set up before the equipment is installed on the site [fr

CERCA's fuel elements instrumentation manufacturing

International Nuclear Information System (INIS)

Harbonnier, G.; Jarousse, C.; Pin, T.; Febvre, M.; Colomb, P.

2005-01-01

When research and test reactors wish to further understand the Fuel Elements behavior when operating as well as mastering their irradiation conditions, operators carry out neutron and thermo hydraulic analysis. For thermal calculation, the codes used have to be preliminary validated, at least in the range of the reactor safety operational limits. When some further investigations are requested either by safety authorities or for its own reactor needs, instrumented tools are the ultimate solution for providing representative measurements. Such measurements can be conducted for validating thermal calculation codes, at nominal operating condition as well as during transients ones, or for providing numerous and useful data in the frame of a new products qualification program. CERCA, with many years of experience for implanting thermocouples in various products design, states in this poster his manufacturing background on instrumented elements, plates or targets. (author)

Instrumented measurements on radioactive waste disposal containers during experimental drop testing - 59142

International Nuclear Information System (INIS)

Quercetti, Thomas; Musolff, Andre; Mueller, Karsten

2012-01-01

In context with disposal container safety assessment of containers for radioactive waste the German Federal Institute for Materials Research and Testing (BAM) performed numerous drop tests in the last years. The tests were accompanied by extensive and various measurement techniques especially by instrumented measurements with strain gages and accelerometers. The instrumentation of a specimen is an important tool to evaluate its mechanical behavior during impact. Test results as deceleration-time and strain-time functions constitute a main basis for the validation of assumptions in the safety analysis and for the evaluation of calculations based on finite-element methods. Strain gauges are useful to determine the time dependent magnitude of any deformation and the associated stresses. Accelerometers are widely used for the measuring of motion i.e. speed or the displacement of the rigid cask body, vibration and shock events. In addition high-speed video technique can be used to visualize and analyze the kinematical impact scenario by motion analysis. The paper describes some selected aspects on instrumented measurements and motion analysis in context with low level radioactive waste (LLW) container drop testing. (authors)

Acceptance for Beneficial Use Pumping Instrumentation and Control Skid N

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This is a final Acceptance for Beneficial Use (ABU) for Pumping and Instrumentation Control (PIC) skid ''N''. PIC skid ''N'' is ready for pumping tank U-109. All the testing and documentation has been completed as required on the AE3U checklist. This AE3U covers only the readiness of the PIC skid ''N''. Other U-farm preparations including dilution tank fabrication, portable exhauster readiness, leak detection, valve pit preparation, and the Operation Control Station readiness are not part of this ABU. PIC skid ''N'' is a new skid fabricated and tested at Site Fabrication Services. The skid controls the jet pump and monitors various instruments associated with the pumping operation. This monitoring includes leak detection along the waste transfer route and flammable gases in the pump pit. This Acceptance for Beneficial Use documents that Pumping Instrumentation and Control (PIC) skid ''N'' is ready for field use. This document does not cover the field installation or operational testing

Sludge stabilization operability test report

International Nuclear Information System (INIS)

Lewis, W.S.

1994-01-01

Document provides the results of the Operability Test Procedure performed to test the operability of the HC-21C thermal stabilization process for sludge. The OTP assured all equipment functioned properly and established the baseline temperature profile for glovebox HC-21C

Causal null hypotheses of sustained treatment strategies: What can be tested with an instrumental variable?

Science.gov (United States)

Swanson, Sonja A; Labrecque, Jeremy; Hernán, Miguel A

2018-05-02

Sometimes instrumental variable methods are used to test whether a causal effect is null rather than to estimate the magnitude of a causal effect. However, when instrumental variable methods are applied to time-varying exposures, as in many Mendelian randomization studies, it is unclear what causal null hypothesis is tested. Here, we consider different versions of causal null hypotheses for time-varying exposures, show that the instrumental variable conditions alone are insufficient to test some of them, and describe additional assumptions that can be made to test a wider range of causal null hypotheses, including both sharp and average causal null hypotheses. Implications for interpretation and reporting of instrumental variable results are discussed.

The effects of display and autopilot functions on pilot workload for Single Pilot Instrument Flight Rule (SPIFR) operations

Science.gov (United States)

Hoh, Roger H.; Smith, James C.; Hinton, David A.

1987-01-01

An analytical and experimental research program was conducted to develop criteria for pilot interaction with advanced controls and displays in single pilot instrument flight rules (SPIFR) operations. The analytic phase reviewed fundamental considerations for pilot workload taking into account existing data, and using that data to develop a divided attention SPIFR pilot workload model. The pilot model was utilized to interpret the two experimental phases. The first experimental phase was a flight test program that evaluated pilot workload in the presence of current and near-term displays and autopilot functions. The second experiment was conducted on a King Air simulator, investigating the effects of co-pilot functions in the presence of very high SPIFR workload. The results indicate that the simplest displays tested were marginal for SPIFR operations. A moving map display aided the most in mental orientation, but had inherent deficiencies as a stand alone replacement for an HSI. Autopilot functions were highly effective for reducing pilot workload. The simulator tests showed that extremely high workload situations can be adequately handled when co-pilot functions are provided.

ICFA: Instrumentation school

Energy Technology Data Exchange (ETDEWEB)

Anon.

1987-10-15

74 students, including 45 from developing countries, ten lecturers and nine laboratory instructors participated in the novel instrumentation school held in June at the International Centre for Theoretical Physics (ICTP), Trieste, Italy, sponsored by ICTP and arranged through the Instrumentation Panel of the International Committee for Future Accelerators (ICF). During the two weeks of the course, students had the chance to construct and test a proportional chamber, measure the lifetime of cosmic ray muons, operate and analyse the performance of an 8-wire imaging drift chamber, or study noise and signal processing using a silicon photodiode.

ICFA: Instrumentation school

International Nuclear Information System (INIS)

Anon.

1987-01-01

74 students, including 45 from developing countries, ten lecturers and nine laboratory instructors participated in the novel instrumentation school held in June at the International Centre for Theoretical Physics (ICTP), Trieste, Italy, sponsored by ICTP and arranged through the Instrumentation Panel of the International Committee for Future Accelerators (ICF). During the two weeks of the course, students had the chance to construct and test a proportional chamber, measure the lifetime of cosmic ray muons, operate and analyse the performance of an 8-wire imaging drift chamber, or study noise and signal processing using a silicon photodiode

A cohort study of maternal and neonatal morbidity in relation to use of sequential instruments at operative vaginal delivery.

LENUS (Irish Health Repository)

Murphy, Deirdre J

2012-02-01

OBJECTIVE: To evaluate the risk factors and maternal and neonatal morbidity associated with sequential use of instruments (vacuum and forceps) at operative vaginal delivery. STUDY DESIGN: A cohort study of 1360 nulliparous women delivered by a single instrument (vacuum or forceps) or by both instruments, within two university teaching hospitals in Scotland and England. Outcomes were compared for use of sequential instruments versus use of any single instrument. A sub-group analysis compared sequential instruments versus forceps alone. Outcomes of interest included anal sphincter tears, postpartum haemorrhage, urinary retention, urinary incontinence, prolonged hospital admission, neonatal trauma, low Apgar scores, abnormal cord bloods and admission to the neonatal intensive care unit (NICU). RESULTS: Use of sequential instruments at operative vaginal delivery was associated with fetal malpositions, Odds Ratio (OR) 1.8 (95% Confidence Interval (CI) 1.3-2.6), and large neonatal head circumference (>37 cm) (OR 5.0, 95% CI 2.6-9.7) but not with maternal obesity or grade of operator. Sequential use of instruments was associated with greater maternal and neonatal morbidity than single instrument use (anal sphincter tear 17.4% versus 8.4%, adjusted OR 2.1, 95% CI 1.2-3.3; umbilical artery pH <7.10, 13.8% versus 5.0%, adjusted OR 3.3, 95% CI 1.7-6.2). Sequential instrument use had greater morbidity than single instrument use with forceps alone (anal sphincter tear OR 1.8, 95% CI 1.1-2.9; umbilical artery pH <7.10 OR 3.0, 95% CI 1.7-5.5). CONCLUSIONS: The use of sequential instruments significantly increases maternal and neonatal morbidity. Obstetricians need training in the appropriate selection and use of instruments with the aim of completing delivery safely with one instrument.

ESCRIME: testing bench for advanced operator workstations in future plants

International Nuclear Information System (INIS)

Poujol, A.; Papin, B.

1994-01-01

The problem of optimal task allocation between man and computer for the operation of nuclear power plants is of major concern for the design of future plants. As the increased level of automation induces the modification of the tasks actually devoted to the operator in the control room, it is very important to anticipate these consequences at the plant design stage. The improvement of man machine cooperation is expected to play a major role in minimizing the impact of human errors on plant safety. The CEA has launched a research program concerning the evolution of the plant operation in order to optimize the efficiency of the human/computer systems for a better safety. The objective of this program is to evaluate different modalities of man-machine share of tasks, in a representative context. It relies strongly upon the development of a specific testing facility, the ESCRIME work bench, which is presented in this paper. It consists of an EDF 1300MWe PWR plant simulator connected to an operator workstation. The plant simulator model presents at a significant level of details the instrumentation and control of the plant and the main connected circuits. The operator interface is based on the generalization of the use of interactive graphic displays, and is intended to be consistent to the tasks to be performed by the operator. The functional architecture of the workstation is modular, so that different cooperation mechanisms can be implemented within the same framework. It is based on a thorough analysis and structuration of plant control tasks, in normal as well as in accident situations. The software architecture design follows the distributed artificial intelligence approach. Cognitive agents cooperate in order to operate the process. The paper presents the basic principles and the functional architecture of the test bed and describes the steps and the present status of the program. (author)

Photogrammetry of the Map Instrument in a Cryogenic Vacuum Environment

Science.gov (United States)

Hill, M.; Packard, E.; Pazar, R.

2000-01-01

MAP Instrument requirements dictated that the instruments Focal Plane Assembly (FPA) and Thermal Reflector System (TRS) maintain a high degree of structural integrity at operational temperatures (photogrammetry camera. This paper will discuss MAP's Instrument requirements, how those requirements were verified using photogrammetry, and the test setup used to provide the environment and camera movement needed to verify the instrument's requirements.

Light Duty Utility Arm system pre-operational (cold test) test plan

International Nuclear Information System (INIS)

Bennett, K.L.

1995-01-01

The Light Duty Utility (LDUA) Cold Test Facility, located in the Hanford 400 Area, will be used to support cold testing (pre- operational tests) of LDUA subsystems. Pre-operational testing is composed of subsystem development testing and rework activities, and integrated system qualification testing. Qualification testing will be conducted once development work is complete and documentation is under configuration control. Operational (hot) testing of the LDUA system will follow the testing covered in this plan and will be covered in a separate test plan

Acceptance Test Procedure for New Pumping and Instrumentation Control Skid L

International Nuclear Information System (INIS)

KOCH, M.R.

1999-01-01

This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping and Instrumentation Control (PIC) skid designed as ''L''. The ATP will be performed after the construction of the PIC skid in the shop

Acceptance Test Procedure for New Pumping and Instrumentation Control Skid N

International Nuclear Information System (INIS)

KOCH, M.R.

1999-01-01

This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping and Instrumentation Control (PIC) skid designed as ''N''. The ATP will be performed after the construction of the PIC skid in the shop

Femoral Test Bed for Impedance Controlled Surgical Instrumentation

Directory of Open Access Journals (Sweden)

Christian Brendle

2012-01-01

Full Text Available The risk for patients during the standard procedure of revision of cemented artificial hip joints is unsatisfactorily highdue to its high level of invasiveness and limited access to the operative field. To reduce this risk we are developing anImpedance Controlled Surgical Instrumentation (ICOS system, which aims to establish real-time control during a BoneCement (BC milling process. For this, the relationship between the thickness of the BC and its frequency-dependentelectrical impedance is used to estimate the residual BC thickness. The aim is to avoid unintended cutting of boneby detecting the passage of the BC/bone boundary layer by the milling head. In a second step, an estimation of theresidual BC thickness will be used to improve process control. As a first step towards demonstrating the feasibility ofour approach, presented here are experimental studies to characterize the BC permittivity and to describe the process indetail. The results show that the permittivity properties of BC are dominated by its polymethyl methacrylate (PMMAfraction. Thus, PMMA can be used as a substitute for future experiments. Furthermore, a Femoral Test Bed (FTB wasdesigned. Using this setup we show it is feasible to accurately distinguish between slightly different thicknesses of BC.

FMIT test-end instrumentation systems scoping study

International Nuclear Information System (INIS)

Fuller, J.L.; Dixon, N.E.; Sheen, E.M.

1982-06-01

For the Fusion Materials Irradiation Test facility (FMIT), the high power density of the accelerated deuteron beam and the unique nature of the liquid lithium target underscore the need for sensitive, fast and reliable test-end diagnostic instrumentation. The intense radiation environment in the test cell places severe limits on candidate systems, as to a lesser degree do thermal and lithium compatibility factors. A beam-target diagnostic station at 180 in the HEBT can facilitate source emission and spot-on-target imaging. Analyses support the feasibility of several candidate imaging systems. Incorporation of electromagnetic and electrostatic beam position detectors as part of the target assembly, as previously proposed, should also be feasible. The possibilities for on-line, real-time ultrasonic/acoustic target diagnosis are favorable. The use of redundant thermocouple and ion detector test assembly beam location detectors is also supported because of the possible problems with thermocouples in the intense 14-MeV neutron field and the simplicity of the ion detectors

Development of a facility using robotics for testing automation of inertial instruments

Science.gov (United States)

Greig, Joy Y.; Lamont, Gary B.; Biezad, Daniel J.; Lewantowicz, Zdsislaw H.; Greig, Joy Y.

1987-01-01

The Integrated Robotics System Simulation (ROBSIM) was used to evaluate the performance of the PUMA 560 arm as applied to testing of inertial sensors. Results of this effort were used in the design and development of a feasibility test environment using a PUMA 560 arm. The implemented facility demonstrated the ability to perform conventional static inertial instrument tests (rotation and tumble). The facility included an efficient data acquisitions capability along with a precision test servomechanism function resulting in various data presentations which are included in the paper. Analysis of inertial instrument testing accuracy, repeatability and noise characteristics are provided for the PUMA 560 as well as for other possible commercial arm configurations. Another integral aspect of the effort was an in-depth economic analysis and comparison of robot arm testing versus use of contemporary precision test equipment.

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''P''

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''P''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid W

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''W''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid V

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control. (PIC) skid designed as ''V''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''V''

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designated as ''V''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''Q''

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''Q''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''T''

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designated as ''T''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid T

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Acceptance Test Procedure (ATP) provides for the inspection and testing Of the new Pumping Instrumentation and Control (PIC) skid designed as ''T''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid R

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''R''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''U''

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Acceptance Test Procedure (ATP) provides for the inspection and testing of the new Pumping Instrumentation and Control (PIC) skid designed as ''U''. The ATP will be performed after the construction of the PIC skid in the fabrication shop

Impact of proof test interval and coverage on probability of failure of safety instrumented function

International Nuclear Information System (INIS)

Jin, Jianghong; Pang, Lei; Hu, Bin; Wang, Xiaodong

2016-01-01

Highlights: • Introduction of proof test coverage makes the calculation of the probability of failure for SIF more accurate. • The probability of failure undetected by proof test is independently defined as P TIF and calculated. • P TIF is quantified using reliability block diagram and simple formula of PFD avg . • Improving proof test coverage and adopting reasonable test period can reduce the probability of failure for SIF. - Abstract: Imperfection of proof test can result in the safety function failure of safety instrumented system (SIS) at any time in its life period. IEC61508 and other references ignored or only elementarily analyzed the imperfection of proof test. In order to further study the impact of the imperfection of proof test on the probability of failure for safety instrumented function (SIF), the necessity of proof test and influence of its imperfection on system performance was first analyzed theoretically. The probability of failure for safety instrumented function resulted from the imperfection of proof test was defined as probability of test independent failures (P TIF ), and P TIF was separately calculated by introducing proof test coverage and adopting reliability block diagram, with reference to the simplified calculation formula of average probability of failure on demand (PFD avg ). Research results show that: the shorter proof test period and the higher proof test coverage indicate the smaller probability of failure for safety instrumented function. The probability of failure for safety instrumented function which is calculated by introducing proof test coverage will be more accurate.

Modeling motive activation in the Operant Motives Test

DEFF Research Database (Denmark)

Runge, J. Malte; Lang, Jonas W. B.; Engeser, Stefan

2016-01-01

The Operant Motive Test (OMT) is a picture-based procedure that asks respondents to generate imaginative verbal behavior that is later coded for the presence of affiliation, power, and achievement-related motive content by trained coders. The OMT uses a larger number of pictures and asks...... on the dynamic model were .52, .62, and .73 for the affiliation, achievement, and power motive in the OMT, respectively. The second contribution of this article is a tutorial and R code that allows researchers to directly apply the dynamic Thurstonian IRT model to their data. The future use of the OMT...... respondents to provide more brief answers than earlier and more traditional picture-based implicit motive measures and has therefore become a frequently used measurement instrument in both research and practice. This article focuses on the psychometric response mechanism in the OMT and builds on recent...

Advanced In-pile Instrumentation for Material and Test Reactors

International Nuclear Information System (INIS)

Rempe, J.L.; Knudson, D.L.; Daw, J.E.; Unruh, T.C.; Chase, B.M.; Davis, K.L.; Palmer, A.J.; Schley, R.S.

2013-06-01

The US Department of Energy sponsors the Advanced Test Reactor (ATR) National Scientific User Facility (NSUF) program to promote U.S. research in nuclear science and technology. By attracting new research users - universities, laboratories, and industry - the ATR NSUF facilitates basic and applied nuclear research and development, advancing U.S. energy security needs. A key component of the ATR NSUF effort is to design, develop, and deploy new in-pile instrumentation techniques that are capable of providing real-time measurements of key parameters during irradiation. This paper describes the strategy developed by the Idaho National Laboratory (INL) for identifying instrumentation needed for ATR irradiation tests and the program initiated to obtain these sensors. New sensors developed from this effort are identified; and the progress of other development efforts is summarized. As reported in this paper, INL staff is currently involved in several tasks to deploy real-time length and flux detection sensors, and efforts have been initiated to develop a crack growth test rig. Tasks evaluating 'advanced' technologies, such as fiber-optics based length detection and ultrasonic thermometers are also underway. In addition, specialized sensors for real-time detection of temperature and thermal conductivity are not only being provided to NSUF reactors, but are also being provided to several international test reactors. (authors)

Measurement techniques and instruments suitable for life-prediction testing of photovoltaic arrays. Interim report

Energy Technology Data Exchange (ETDEWEB)

Noel, G.T.; Sliemers, F.A.; Deringer, G.C.; Wood, V.E.; Wilkes, K.E.; Gaines, G.B.; Carmichael, D.C.

1978-01-15

The validation of a service life of 20 years for low-cost photovoltaic arrays must be accomplished through accelerated life-prediction tests. A methodology for such tests has been developed in a preceding study. The results discussed consist of the initial identification and assessment of all known measurement techniques and instruments that might be used in these life-prediction tests. Array failure modes, relevant materials property changes, and primary degradation mechanisms are discussed as a prerequisite to identifying suitable measurement techniques and instruments. Candidate techniques and instruments are identified on the basis of extensive reviews of published and unpublished information. These methods are organized in six measurement categories--chemical, electrical, optical, thermal, mechanical, and ''other physicals''. Using specified evaluation criteria, the most promising techniques and instruments for use in life-prediction tests of arrays are then selected. These recommended techniques and their characteristics are described. Recommendations are made regarding establishment of the adequacy, particularly with respect to precision, of the more fully developed techniques for this application, and regarding the experimental evaluation of promising developmental techniques. Measurement needs not satisfied by presently available techniques/instruments are also identified.

Instrumentation maintenance

International Nuclear Information System (INIS)

Mack, D.A.

1976-09-01

It is essential to any research activity that accurate and efficient measurements be made for the experimental parameters under consideration for each individual experiment or test. Satisfactory measurements in turn depend upon having the necessary instruments and the capability of ensuring that they are performing within their intended specifications. This latter requirement can only be achieved by providing an adequate maintenance facility, staffed with personnel competent to understand the problems associated with instrument adjustment and repair. The Instrument Repair Shop at the Lawrence Berkeley Laboratory is designed to achieve this end. The organization, staffing and operation of this system is discussed. Maintenance policy should be based on studies of (1) preventive vs. catastrophic maintenance, (2) records indicating when equipment should be replaced rather than repaired and (3) priorities established to indicate the order in which equipment should be repaired. Upon establishing a workable maintenance policy, the staff should be instructed so that they may provide appropriate scheduled preventive maintenance, calibration and corrective procedures, and emergency repairs. The education, training and experience of the maintenance staff is discussed along with the organization for an efficient operation. The layout of the various repair shops is described in the light of laboratory space and financial constraints

21 CFR 111.117 - What quality control operations are required for equipment, instruments, and controls?

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 2 2010-04-01 2010-04-01 false What quality control operations are required for equipment, instruments, and controls? 111.117 Section 111.117 Food and Drugs FOOD AND DRUG ADMINISTRATION... and Process Control System: Requirements for Quality Control § 111.117 What quality control operations...

Interactive CD based training on NDA instruments for facility operators and international inspectors

International Nuclear Information System (INIS)

Horley, E.C.; Smith, H.A.

1996-01-01

Interactive multimedia training is rapidly becoming a popular and highly effective medium for learning. An interactive CD based training module on the Active Well Coincidence counter is being developed for on-site training at nuclear facility, including foreign facilities. The training module incorporates interactive text, graphics and video that demonstrate the operating principles, and the use and set-up of the instrument. The user is in control of the pace of learning and of the directions taken to acquire information based on personal need. By being in control, the user stays highly motivated. A mix of visuals (text and graphics), audio clips (in different languages), and video (with audio) clips also keeps the interest level high. Skill reviews and evaluations can be incorporated into the training to provide feedback to the student. In addition, general background information is provided on gamma and neutron based MC and A measurements. This material serves as a condensed MC and A encyclopedia. By supplying an interactive CD with an NDA instrument, nuclear facilities will have greater assurance operators are properly trained in the set-up and operation of the NDA-equipment

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''P''

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Test Plan provides a test method to dedicate the leak detection relays used on the new Pumping Instrumentation and Control (PIC) skids. The new skids are fabricated on-site. The leak detection system is a safety class system per the Authorization Basis

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid Q

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Test Plan provides a test method to dedicate the leak detection relays used on the new Pumping Instrumentation and Control (PIC) skids. The new skids are fabricated on-site. The leak detection system is a safety class system per the Authorization Basis

Spirolit-2 instrument used to test pulmonary ventilation

Science.gov (United States)

Zhuravlev, V. V.

1985-02-01

At the present time, the Spirolit-2 automatic analyzer of main respiratory gases, of the Junkalor Dessau firm, is used to examine parameters of gas exchange, levels of energy expended by man and animals with different degrees of activity. However, the capabilities of this model of the instrument are limited. A method of determining pulmonary ventilation with use of the Spirolit-2 is described. An additional exhalation valve is built into a valve box to which an anesthesia machine rubber bag is attached. Samples are collected into another bag concurrently with the usual tests on the Spirolit-2 instrument. Four to five minutes are sufficient to obtain stable parameters at relative rest of oxygen uptake, determine carbon dioxide output per minute and collect samples in for analysis of exhaled air. The proposed method can furnish information about the dynamics of development of respiratory function of the lungs at virtually any moment with a constant physical load. For this, there must be spare bags to collect samples. Stage-by-stage data can be obtained analogously as to ventilation volume during a step test while determining maximum oxygen uptake.

Intra-operative Assessment of the Spinal Cord Function: Awakening Compared to Ankle Clonus Test

International Nuclear Information System (INIS)

Amin, Wafik A.; Tealab, Ayman I.; Ei-Gendy, Eslah H.; Esmat, Hesham A.

2006-01-01

The spinal cord is at high risk of injury during special procedures such as correction of scoliosis. Recovery from impairement is directly proportional to the time of removal of the instrumentations. For this, methods used to detect the neurologic injury should be continuous, fast, sensitive and specific. The present study was performed to evaluate the ankle clonus as a test for the integrity of the spinal cord function intraoperatively. Twenty eight scoliotic patients were included in the study. The ankle clonus was tested before, during and after the correction and fixation followed by the wake-up test to correlate the results of both rests. The haemodynamics changes at the time of the two tests were compared. It was found out that, the ankle clonus test correlated well with the wake-up test, with only two false positive results. No false negative results were recorded which was an important finding. The haemodynamic changes were better during the ankle clonus test than during the wake-up test. It was concluded that the ankle clonus test is reliable, safe, and faster than the wake-up test. It is recommended to use the test to evaluate the integrity of the spinal cord during the operations with potential risk to the cord. In case the result of the ankle clonus is positive, the wake-up test should be done before an attempt to release or remove the instrumentations. (author)

Field instrumentation for hydrofracturing stress measurements

International Nuclear Information System (INIS)

Bjarnason, Bjarni; Torikka, Arne.

1989-08-01

A recently developed system for rock stress measurements by the hydraulic fracturing method is documented in detail. The new equipment is intended for measurement in vertical or nearvertical boreholes, down to a maximum depth of 1000 m. The minimum borehole, diameter required is 56 mm. Downhole instrumentation comprises a straddle packer assembly for borehole fracturing, equipment for determination of fracture orientations and a pressure transducer. The downhole tools are operated by means of a multihose system, containing high pressure hydraulic tubings, signal cable and carrying wire into one hose unit. The surface components of the equipment include a system for generation and control of water pressures up to approximately 75 MPa, an hydraulically operated drum for the multihose and a data acquisition system. All surface instrumentation is permanently mounted on a truck, which also serves as power source for the instrumentation. In addition to the description of instrumentation, the theoretical fundament and the testing procedures associated with the hydraulic fracturing method are briefly outlined

Design and manufacturing of non-instrumented capsule for advanced PWR fuel pellet irradiation test in HANARO

Energy Technology Data Exchange (ETDEWEB)

Kim, D. H.; Lee, C. B.; Song, K. W. [Korea Atomic Energy Research Institute, Taejeon (Korea)

2002-04-01

This project is preparing to irradiation test of the developed large grain UO{sub 2} fuel pellet in HANARO for pursuit fuel safety and high burn-up in 'Advanced LWR Fuel Technology Development Project' as a part Nuclear Mid and Long-term R and D Program. On the basis test rod is performed the nuclei property and preliminary fuel performance analysis, test rod and non-instrumented capsule are designed and manufactured for irradiation test in HANARO. This non-instrumented irradiation capsule of Advanced PWR Fuel pellet was referred the non-instrumented capsule for an irradiation test of simulated DUPIC fuel in HANARO(DUPIC Rig-001) and 18-element HANARO fuel, was designed to ensure the integrity and the endurance of non-instrumented capsule during the long term(2.5 years) irradiation. To irradiate the UO{sub 2} pellets up to the burn-up 70 MWD/kgU, need the time about 60 months and ensure the integrity of non-instrumented capsule for 30 months until replace the new capsule. This non-instrumented irradiation capsule will be based to develope the non-instrumented capsule for the more long term irradiation in HANARO. 22 refs., 13 figs., 5 tabs. (Author)

Evaluation of a draft standard on performance specifications for health physics instrumentation. Initial results for radiological tests

International Nuclear Information System (INIS)

Swinth, K.L.; Kenoyer, J.L.; Mileham, A.P.; Kathren, R.L.; Selby, J.M.

1983-06-01

The draft ANSI standard N42.17D2 on performance specifications for health physics instrumentation is currently being evaluated by the Pacific Northwest Laboratory. The primary objective of the project is the evaluation of the applicability and practicality of the proposed standard through testing of a cross-section of currently available commercial instruments to determine how well they conform to the standard. The standard is being tested against instruments such as ionization chambers, G.M. detectors, alpha survey meters, and neutron dose equivalent survey meters. This paper presents results of the preliminary radiological performance tests on ionization chambers and G.M. detectors. This includes both the data generated during the tests and a discussion of procedures developed to perform the testing. Results are reported for response time, accuracy, precision, radiation overloads, and angular dependence. In addition, results are reported for parameters that affect instrument performance including battery lifetime, geotropism and stability. Initial test indicates that some of the instruments will not meet the criteria specified in ANSI N42.17D2. Results cover approximately 40 instruments that have been obtained by direct purchase, by loan from instrument vendors or by loan from others including DOE licensees

CAMAC-controlled calibration system for nuclear reactor instruments

International Nuclear Information System (INIS)

McDowell, W.P.; Cornella, R.J.

1977-01-01

The hardware and the software which have been developed to implement a nuclear instrument calibration system for the Argonne National Laboratory ZPR-VI and ZPR-IX reactor complex are described. The system is implemented using an SEL-840 computer with its associated CAMAC crates and a hardware interface to generate input parameters and measure the required outputs on the instrument under test. Both linear and logarithmic instruments can be calibrated by the system and output parameters can be measured at various automatically selected values of ac line voltage. A complete report on each instrument is printed as a result of the calibration and out-of-tolerance readings are flagged. Operator interface is provided by a CAMAC-controlled Hazeltine terminal. The terminal display leads the operator through the complete calibration procedure. This computer-controlled system is a significant improvement over previously used methods of calibrating nuclear instruments since it reduces reactor downtime and allows rapid detection of long-term changes in instrument calibration

WRAP TRUPACT loading systems operational test report

International Nuclear Information System (INIS)

DOSRAMOS, E.V.

1999-01-01

This Operational Test Report documents the operational testing of the TRUPACT process equipment HNF-3918, Revision 0, TRUPACT Operational Test Procedure. The test accomplished the following: Procedure validation; Facility equipment interface; Facility personnel support; and Subcontractor personnel support interface. Field changes are documented as test exceptions with resolutions. All resolutions are completed or a formal method is identified to track the resolution through to completion

Void fraction instrument software, Version 1,2, Acceptance test report

International Nuclear Information System (INIS)

Gimera, M.

1995-01-01

This provides the report for the void fraction instrument acceptance test software Version 1.2. The void fraction will collect data that will be used to calculate the quantity of gas trapped in waste tanks

Instrumented impact testing machine with reduced specimen oscillation effects

International Nuclear Information System (INIS)

Rintamaa, R.; Rahka, K.; Wallin, K.

1984-07-01

Owing to small and inexpensive specimens the Charpy impact test is widely used in quality control and alloy development. Limitations in power reactor survellance capsules it is also widely used for safety analysis purposes. Instrumenting the tup and computerizing data acquisition, makes dynamic fracture mechanics data measurement possible and convenient. However, the dynamic effects (inertia forces, specimen oscillations) in the impact test cause inaccuracies in the recorded load-time diagram and hence diminish the reliability of the calculated dynamic fracture mechanics parameters. To decrease inaccuracies a new pendulum type of instrumented impact test apparatus has been developed and constructed in the Metals Laboratory of the Technical Research Centre of Finland. This tester is based on a new principle involving inverted test geometry. The purpose of the geometry inversion is to reduce inertia load and specimen oscillation effects. Further, the new impact tester has some other novel features: e.g. the available initia impact energy is about double compared to the conventional standard (300 J) impact tester allowing the use of larger (10 x 20 x 110 mm) bend specimens than normal Charpy specimens. Also, the rotation asix in the three point bending is nearly stationary making COD-measurements possible. An experimental test series is described in which the inertia effects and specimen oscillations are compared in the conventional and new impact tester utilizing Charpy V-notch specimens. Comparison of the two test geometries is also made with the aid of an analytical model using finite element method (FEM) analysis. (author)

Programming for a nuclear reactor instrument simulator

International Nuclear Information System (INIS)

Cohn, C.E.

1989-01-01

A new computerized control system for a transient test reactor incorporates a simulator for pre-operational testing of control programs. The part of the simulator pertinent to the discussion here consists of two microprocessors. An 8086/8087 reactor simulator calculates simulated reactor power by solving the reactor kinetics equations. An 8086 instrument simulator takes the most recent power value developed by the reactor simulator and simulates the appropriate reading on each of the eleven reactor instruments. Since the system is required to run on a one millisecond cycle, careful programming was required to take care of all eleven instruments in that short time. This note describes the special programming techniques used to attain the needed performance

Static Load Test on Instrumented Pile – Field Data and Numerical Simulations

Directory of Open Access Journals (Sweden)

Krasiński Adam

2017-09-01

Full Text Available Static load tests on foundation piles are generally carried out in order to determine load – the displacement characteristic of the pile head. For standard (basic engineering practices this type of test usually provides enough information. However, the knowledge of force distribution along the pile core and its division into the friction along the shaft and the resistance under the base can be very useful. Such information can be obtained by strain gage pile instrumentation [1]. Significant investigations have been completed on this technology, proving its utility and correctness [8], [10], [12]. The results of static tests on instrumented piles are not easy to interpret. There are many factors and processes affecting the final outcome. In order to understand better the whole testing process and soil-structure behavior some investigations and numerical analyses were done. In the paper, real data from a field load test on instrumented piles is discussed and compared with numerical simulation of such a test in similar conditions. Differences and difficulties in the results interpretation with their possible reasons are discussed. Moreover, the authors used their own analytical solution for more reliable determination of force distribution along the pile. The work was presented at the XVII French-Polish Colloquium of Soil and Rock Mechanics, Łódź, 28–30 November 2016.

Operation of the nuclear fuel cycle test facilities -Operation of the hot test loop facilities

International Nuclear Information System (INIS)

Chun, S. Y.; Jeong, M. K.; Park, C. K.; Yang, S. K.; Won, S. Y.; Song, C. H.; Jeon, H. K.; Jeong, H. J.; Cho, S.; Min, K. H.; Jeong, J. H.

1997-01-01

A performance and reliability of a advanced nuclear fuel and reactor newly designed should be verified by performing the thermal hydraulics tests. In thermal hydraulics research team, the thermal hydraulics tests associated with the development of an advanced nuclear fuel and reactor haven been carried out with the test facilities, such as the Hot Test Loop operated under high temperature and pressure conditions, Cold Test Loop, RCS Loop and B and C Loop. The objective of this project is to obtain the available experimental data and to develop the advanced measuring techniques through taking full advantage of the facilities. The facilities operated by the thermal hydraulics research team have been maintained and repaired in order to carry out the thermal hydraulics tests necessary for providing the available data. The performance tests for the double grid type bottom end piece which was improved on the debris filtering effectivity were performed using the PWR-Hot Test Loop. The CANDU-Hot Test Loop was operated to carry out the pressure drop tests and strength tests of CANFLEX fuel. The Cold Test Loop was used to obtain the local velocity data in subchannel within HANARO fuel bundle and to study a thermal mixing characteristic of PWR fuel bundle. RCS thermal hydraulic loop was constructed and the experiments have been carried out to measure the critical heat flux. In B and C Loop, the performance tests for each component were carried out. (author). 19 tabs., 78 figs., 19 refs

Operation of the nuclear fuel cycle test facilities -Operation of the hot test loop facilities

Energy Technology Data Exchange (ETDEWEB)

Chun, S. Y.; Jeong, M. K.; Park, C. K.; Yang, S. K.; Won, S. Y.; Song, C. H.; Jeon, H. K.; Jeong, H. J.; Cho, S.; Min, K. H.; Jeong, J. H.

1997-01-01

A performance and reliability of a advanced nuclear fuel and reactor newly designed should be verified by performing the thermal hydraulics tests. In thermal hydraulics research team, the thermal hydraulics tests associated with the development of an advanced nuclear fuel and reactor haven been carried out with the test facilities, such as the Hot Test Loop operated under high temperature and pressure conditions, Cold Test Loop, RCS Loop and B and C Loop. The objective of this project is to obtain the available experimental data and to develop the advanced measuring techniques through taking full advantage of the facilities. The facilities operated by the thermal hydraulics research team have been maintained and repaired in order to carry out the thermal hydraulics tests necessary for providing the available data. The performance tests for the double grid type bottom end piece which was improved on the debris filtering effectivity were performed using the PWR-Hot Test Loop. The CANDU-Hot Test Loop was operated to carry out the pressure drop tests and strength tests of CANFLEX fuel. The Cold Test Loop was used to obtain the local velocity data in subchannel within HANARO fuel bundle and to study a thermal mixing characteristic of PWR fuel bundle. RCS thermal hydraulic loop was constructed and the experiments have been carried out to measure the critical heat flux. In B and C Loop, the performance tests for each component were carried out. (author). 19 tabs., 78 figs., 19 refs.

Visual interface for the automation of the instrumented pendulum of Charpy tests used in the surveillance program of reactors vessel of nuclear power plants

International Nuclear Information System (INIS)

Rojas S, A.S.; Sainz M, E.; Ruiz E, J.A.

2004-01-01

Inside the Programs of Surveillance of the nuclear power stations periodic information is required on the state that keep the materials with those that builds the vessel of the reactor. This information is obtained through some samples or test tubes that are introduced inside the core of the reactor and it is observed if its physical characteristics remain after having been subjected to the radiation changes and temperature. The rehearsal with the instrumented Charpy pendulum offers information on the behavior of fracture dynamics of a material. In the National Institute of Nuclear Research (ININ) it has an instrumented Charpy pendulum. The operation of this instrument is manual, having inconveniences to carry out rehearsals with radioactive material, handling of high and low temperatures, to fulfill the normative ones for the realization of the rehearsals, etc. In this work the development of a computational program is presented (virtual instrument), for the automation of the instrumented pendulum. The system has modules like: Card of data acquisition, signal processing, positioning system, tempered system, pneumatic system, compute programs like it is the visual interface for the operation of the instrumented Charpy pendulum and the acquisition of impact signals. This system shows that given the characteristics of the nuclear industry with radioactive environments, the virtual instrumentation and the automation of processes can contribute to diminish the risks to the personnel occupationally exposed. (Author)

Status Report on Efforts to Enhance Instrumentation to Support Advanced Test Reactor Irradiations

Energy Technology Data Exchange (ETDEWEB)

J. L. Rempe; D. L. Knudson; J. E. Daw

2011-03-01

The Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF) in April 2007 to support U.S. leadership in nuclear science and technology. By attracting new research users - universities, laboratories, and industry - the ATR NSUF facilitates basic and applied nuclear research and development, further advancing the nation's energy security needs. A key component of the ATR NSUF effort is to prove new in-pile instrumentation techniques that are capable of providing real-time measurements of key parameters during irradiation. To address this need, an assessment of instrumentation available and under-development at other test reactors was completed. Based on this review, recommendations were made with respect to what instrumentation is needed at the ATR; and a strategy was developed for obtaining these sensors. In 2009, a report was issued documenting this program’s strategy and initial progress toward accomplishing program objectives. In 2009, a report was issued documenting this instrumentation development strategy and initial progress toward accomplishing instrumentation development program objectives. This document reports progress toward implementing this strategy in 2010.

Status Report on Efforts to Enhance Instrumentation to Support Advanced Test Reactor Irradiations

International Nuclear Information System (INIS)

Rempe, J.L.; Knudson, D.L.; Daw, J.E.

2011-01-01

The Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF) in April 2007 to support U.S. leadership in nuclear science and technology. By attracting new research users - universities, laboratories, and industry - the ATR NSUF facilitates basic and applied nuclear research and development, further advancing the nation's energy security needs. A key component of the ATR NSUF effort is to prove new in-pile instrumentation techniques that are capable of providing real-time measurements of key parameters during irradiation. To address this need, an assessment of instrumentation available and under-development at other test reactors was completed. Based on this review, recommendations were made with respect to what instrumentation is needed at the ATR; and a strategy was developed for obtaining these sensors. In 2009, a report was issued documenting this program's strategy and initial progress toward accomplishing program objectives. In 2009, a report was issued documenting this instrumentation development strategy and initial progress toward accomplishing instrumentation development program objectives. This document reports progress toward implementing this strategy in 2010.

Performance acceptance test of a portable instrument to detect uranium in water at the DOE Advanced Waste Water Treatment Plant, Fernald, Ohio

International Nuclear Information System (INIS)

Anderson, M.S.; Weeks, S.J.

1997-01-01

The Eppendorf-Biotronik Model IC 2001-2, a portable field ruggedized ion chromatography instrument, was rigorously tested at the DOE Advanced Waste Water Treatment Plant, Fernald, Ohio. This instrument rapidly detected the uranium concentration in water, and has a detection limit in the low ppb range without using the sample concentrating feature. The test set of samples analyzed included: ''Real World'' water samples from the AWWT containing uranium concentrations in the 9--110 ppb range, a sample blank, and a performance evaluation sample. The AWWT samples contained sets of both raw water and acid-preserved water samples. Selected samples were analyzed in quadruplicate to asses the instrument's precision, and these results were compared with the results from an off-site confirmatory laboratory to assess the instrument's accuracy. Additional comparisons with on-site laboratory instruments, Chemcheck KPA-11 and Scintrex UA-3 are reported. Overall, the Eppendorf-Biotronik IC 2001-2 performed exceptionally well providing a detection limit in the low ppb region (< 10 ppb) and giving rapid (< 5 minutes) accurate and reproducible analytical results for the AWWT, ''real world'', water samples with uranium concentrations in the region of interest (10--40 ppb). The per sample operating cost for this instrument is equivalent to the per sample cost for the currently used KPA. The time required to analyze a sample and provide a result is approximately the same for the CI 2001-2, KPA, and Scintrex instruments

The test beamline of the European Spallation Source - Instrumentation development and wavelength frame multiplication

DEFF Research Database (Denmark)

Woracek, R.; Hofmann, T.; Bulat, M.

2016-01-01

which, in contrast, are all providing short neutron pulses. In order to enable the development of methods and technology adapted to this novel type of source well in advance of the first instruments being constructed at ESS, a test beamline (TBL) was designed and built at the BER II research reactor...... wavelength band between 1.6 A and 10 A by a dedicated wavelength frame multiplication (WFM) chopper system. WFM is proposed for several ESS instruments to allow for flexible time-of-flight resolution. Hence, ESS will benefit from the TBL which offers unique possibilities for testing methods and components....... This article describes the main capabilities of the instrument, its performance as experimentally verified during the commissioning, and its relevance to currently starting ESS instrumentation projects....

Proposal for a Universal Test Mirror for Characterization of Slope Measuring Instruments

International Nuclear Information System (INIS)

Yashchuk, Valeriy V.; McKinney, Wayne R.; Warwick, Tony; Noll, Tino; Siewert, Frank; Zeschke, Thomas; Geckeler, Ralf D.

2007-01-01

The development of third generation light sources like the Advanced Light Source (ALS) or BESSY II brought to a focus the need for high performance synchrotron optics with unprecedented tolerances for slope error and micro roughness. Proposed beam lines at Free Electron Lasers (FEL) require optical elements up to a length of one meter, characterized by a residual slope error in the range of 0.1mu rad (rms),and rms values of 0.1 nm for micro roughness. These optical elements must be inspected by highly accurate measuring instruments, providing a measurement uncertainty lower than the specified accuracy of the surface under test. It is essential that metrology devices in use at synchrotron laboratories be precisely characterized and calibrated to achieve this target. In this paper we discuss a proposal for a Universal Test Mirror (UTM) as a realization of a high performance calibration instrument. The instrument would provide an ideal calibration surface to replicate a redundant surface under test of redundant figure. The application of a sophisticated calibration instrument will allow the elimination of the majority of the systematic error from the error budget of an individual measurement of a particular optical element. We present the limitations of existing methods, initial UTM design considerations, possible calibration algorithms, and an estimation of the expected accuracy

The Influence of Instrumented Striker Configuration on the Results of Dynamic Toughness Testing

International Nuclear Information System (INIS)

Lucon, E.

2008-01-01

Several studies are available on the influence of the edge radius of instrumented strikers (ASTM - 8 mm or ISO - 2 mm) on the results of both non instrumented and instrumented Charpy tests. This paper investigates the effect of using either a 2 mm or a 8 mm striker when performing dynamic toughness tests at impact loading rates on precracked Charpy specimens. Existing data from tests run in the ductile-to-brittle region (dynamic Master Curve reference temperature) and in the upper shelf regime (ductile initiation fracture toughness and crack resistance curves) have been analyzed. The results show that 2 mm strikers tend to yield lower cleavage fracture toughness in the transition region (although the effect cannot be considered statistically significant), whereas the influence of striker configuration is negligible in the upper shelf regime when data are generated using the low-blow multiple-specimen technique.

The Influence of Instrumented Striker Configuration on the Results of Dynamic Toughness Testing

Energy Technology Data Exchange (ETDEWEB)

Lucon, E.

2008-09-15

Several studies are available on the influence of the edge radius of instrumented strikers (ASTM - 8 mm or ISO - 2 mm) on the results of both non instrumented and instrumented Charpy tests. This paper investigates the effect of using either a 2 mm or a 8 mm striker when performing dynamic toughness tests at impact loading rates on precracked Charpy specimens. Existing data from tests run in the ductile-to-brittle region (dynamic Master Curve reference temperature) and in the upper shelf regime (ductile initiation fracture toughness and crack resistance curves) have been analyzed. The results show that 2 mm strikers tend to yield lower cleavage fracture toughness in the transition region (although the effect cannot be considered statistically significant), whereas the influence of striker configuration is negligible in the upper shelf regime when data are generated using the low-blow multiple-specimen technique.

Testing for the Best Instrument to Generate Sustainable Food Consumption

Directory of Open Access Journals (Sweden)

Luca Panzone

2011-12-01

Full Text Available  The increase in the level of greenhouse gas (GHG emissions in the atmosphere in the last centuries, and the subsequent increase in temperature, has been a widely studied area in the last few decades. Climate change has become a key item on the political agenda due to concerns regarding the sustainability of current human consumption for future generations. Consumption of food and agricultural goods constitutes an important part of household based GHG emissions, and the relatively low costs associated with environmental improvements make it an interesting area of study to understand behavioural changes. Despite general agreement on the need to curb the amount of GHG emissions worldwide, little evidence exists regarding the best instruments policymakers can employ to stimulate changes toward more sustainable consumption. The present work explores which instruments are most effective in fostering change to more environmentally friendly food consumption. The instruments tested are CO2 labelling, GHG abatement subsidy and product-specific bans. We used a simulated online shopping trip in supermarkets in the Greater London area in the United Kingdom, where respondents shopped in four product categories: cola, milk, meat (chicken and beef, and butter/margarine. Consumer preferences reveal that, in the presence of these instruments, quantity instruments performed better than price incentives and labelling.

Disassembly and removal of sodium instrumentation test loop

International Nuclear Information System (INIS)

Ishikawa, Okinobu; Onojima, Takamitu; Nagai, Keiichi

2000-07-01

In 1999, the Sodium Instrumentation Test Loop was disassembled and removed. This report describes the tasks and experiences obtained in removing sodium from a storage tank, disassembling, and cleansing components and related activities. Overall the disassembly, handling and cleansing tasks proceeded as planned and the activities were carried out efficiently and safely. Documentation of the process is meant to establish not only a procedure, but also a guideline for future similar tasks. (author)

ANALYSIS OF OPERATING INSTRUMENT LANDING SYSTEM ACCURACY UNDER SIMULATED CONDITIONS

Directory of Open Access Journals (Sweden)

Jerzy MERKISZ

2017-03-01

Full Text Available The instrument landing system (ILS is the most popular landing aid in the world. It is a distance-angled support system for landing in reduced visibility, while its task is the safe conduct of the aircraft from the prescribed course landing on the approach path. The aim of this study is to analyse the correctness of the ILS in simulated conditions. The study was conducted using a CKAS MotionSim5 flight simulator in the Simulation Research Laboratory of the Institute of Combustion Engines and Transport at Poznan University of Technology. With the advancement of technical equipment, it was possible to check the operation of the system in various weather conditions. Studies have shown that the impact of fog, rain and snow on the correct operation of the system is marginal. Significant influence has been observed, however, during landing in strong winds.

Instrumental intelligent test of food sensory quality as mimic of human panel test combining multiple cross-perception sensors and data fusion.

Science.gov (United States)

Ouyang, Qin; Zhao, Jiewen; Chen, Quansheng

2014-09-02

Instrumental test of food quality using perception sensors instead of human panel test is attracting massive attention recently. A novel cross-perception multi-sensors data fusion imitating multiple mammal perception was proposed for the instrumental test in this work. First, three mimic sensors of electronic eye, electronic nose and electronic tongue were used in sequence for data acquisition of rice wine samples. Then all data from the three different sensors were preprocessed and merged. Next, three cross-perception variables i.e., color, aroma and taste, were constructed using principal components analysis (PCA) and multiple linear regression (MLR) which were used as the input of models. MLR, back-propagation artificial neural network (BPANN) and support vector machine (SVM) were comparatively used for modeling, and the instrumental test was achieved for the comprehensive quality of samples. Results showed the proposed cross-perception multi-sensors data fusion presented obvious superiority to the traditional data fusion methodologies, also achieved a high correlation coefficient (>90%) with the human panel test results. This work demonstrated that the instrumental test based on the cross-perception multi-sensors data fusion can actually mimic the human test behavior, therefore is of great significance to ensure the quality of products and decrease the loss of the manufacturers. Copyright © 2014 Elsevier B.V. All rights reserved.

Instrumentation Technologies for Improving an Irradiation Testing of Nuclear Fuels and Materials at the HANARO

International Nuclear Information System (INIS)

Kim, Bong Goo; Park, Sung Jae; Choo, Ki Nam

2011-01-01

Over 50 years of nuclear fuels and materials irradiation testing has led to many countries developing significant improvements in instrumentation to monitor physical parameters and to control the test conditions in Materials Test Reactors (MTRs) or research reactors. Recent effort to deploy new fuels and materials in existing and advanced reactors has increased the demand for well-instrumented irradiation tests. Specifically, demand has increased for tests with sensors capable of providing real-time measurement of key parameters, such as temperature, geometry changes, thermal conductivity, fission gas release, cracking, coating buildup, thermal and fast flux, etc. This review paper documents the current state of instrumentation technologies in MTRs in the world and summarizes on-going research efforts to deploy new sensors. There is increased interest to irradiate new materials and reactor fuels for advanced PWRs and the Gen-IV reactor systems, such as SFRs (Sodium-cooled Fast Reactors), VHTRs (Very-High-Temperature Reactors), SCWRs (Supercritical-Water-cooled Reactors) and GFRs (Gas-cooled Fast Reactor). This review documents the current state of instrumentation technologies in MTRs in the world, identifies challenges faced by previous testing methods and how these challenges were overcome. A wide range of sensors are available to measure key parameters of interest during fuels and materials irradiations in MTRs. Such sensors must be reliable, small size, highly accurate, and able to withstand harsh conditions. On-going development efforts are focusing on providing MTR users a wider range of parameter measurements with increased accuracy. In addition, development efforts are focusing on reducing the impact of sensor on measurements by reducing sensor size. This report includes not only status of instrumentation using research reactors in the world to irradiate nuclear fuels and materials but also future directions relating to instrumentation technologies for

Instrumentation and control system upgrade plan for operating PWR plants in Japan

International Nuclear Information System (INIS)

Ishii, Hirofumi

1993-01-01

Digital technology has been applied to all non-safety grade instrumentation and control (I ampersand C) systems in the latest Japanese PWR plants, and has achieved more reliable and operable systems, easier maintenance and cable reductions. In the next stage APWR plants, the digital technology will be also applied to all the I ampersand C systems including safety grade systems. Parallel to the above efforts, many backfitting programs in which the digital technology is applied to operating plants are under way to improve reliability and operability. The backfitting programs for operating plants are proceeded in two phases, synthesizing various utility's needs to improve plant availability and operability, improvement of digital technology, and complexity of the practicable replacement procedures. Phase 1 is a partial application of digital technology, while Phase 2 is a complete application of digital technology. Phase 1 has been implemented in a number of operation plants, while Phase 2 studies are in the design stage, but have not been implemented at this point. This paper presents examples of the partial application of digital technology to operating plants, and the contents of basic design for the complete application of digital technology

Re-fabrication and Instrumentation - resume and outlook

International Nuclear Information System (INIS)

Kleeman, Hans-Joerg; Oberlaender, Barbara C.

2005-01-01

The special technique ''re-fabrication and instrumentation'' applied at the Institute for Energy Technology (IFE) makes further testing and measuring of irradiated fuel rods in the Halden Boiling Water Reactor (HBWR) possible. Machines, necessary for such operations, were designed and produced at IFE in the years 1991-92. Hot Lab-operations called ''re-fabrication'' include all modifications necessary to load an irradiated fuel rod, commercial or experimental, into the Halden reactor for further testing. ''Instrumentation'' includes all operations necessary to fit instruments into an irradiated fuel rod segment to measure for instance the temperature in the centreline of the fuel stack, pressure increase in the fuel rod and/or changes of the rod length during reactor experiments. The machines used are referred to as: ''Cutting and Grinding Unit'' for machining of the canning; ''Freezing and Drilling Unit'' for drilling of the centreline thermocouple hole in the active fuel stack;''Welding and Drying Unit'' a TIG welding machine for the circumferential welds and the seal welding; and a hydraulic ''Encapsulation Bench''. The ''Welding and Drilling Unit'' includes also a ''He-leak test chamber'' and a ''Hydraulic Press''. In addition, different types of PIE methods are used in quality assurance and documenting of the work done with the fuel rod. For example neutron radiography, visual inspection, dimension measurement, free volume measurements, equipment to measure the flow capability through the fuel stack and different function tests of the measuring devices. This paper will give an overview of the work done so far with this equipment and give information about new equipment which will be installed soon to deal with even more complicated test fuel designs. (Author)

Use of fuel reprocessing plant instrumentation for international safeguards

International Nuclear Information System (INIS)

Ayers, A.L.

1977-01-01

The International Atomic Energy Agency has a program for developing instrumentation to be used by safeguards inspectors at reprocessing facilities. These instruments have generally been individual pieces of equipment for improving the accuracy of existing measurement instrumentation or equipment to perform nondestructive assay on a selected basis. It is proposed that greater use be made of redundant plant instrumentation and data recovery systems that could augment plant instrumentation to verify the validity of plant measurements. Use of these methods for verfication must be proven as part of an operating plant before they can be relied upon for safeguards surveillance. Inspectors must be qualified in plant operations, or have ready access to those so qualified, if the integrity of the operation is to be properly assessed. There is an immediate need for the development and in-plant proof testing of an integrated gamma, passive neutron, and active neutron measurement system for drum quantities of radioactive trash. The primary safeguards effort should be limited to plutonium and highly enriched uranium

ASK Procedure for Instrumented Pre-cracked Charpy-Type Tests

International Nuclear Information System (INIS)

Varga, T.; Njo, D.H.; Prantl, G.

1981-01-01

The essential technical content of the ASK procedure originated from development work in Switzerland since 1963, and practical experiences gained since 1972. The remainder of the content and the format of the procedure are based on the ASTM E 24.03.03. (Tentative Draft Copy) 'Proposed Method for Pre-cracked Charpy Impact and Slow-Bend Testing of Metallic Materials' by C. E. Harbower, 1973. Two different velocities, 5 m/s and 0.1 m/s were used with a Schnadt-type machine of rigid construction. The stiffness of the machine proved to be very suitable for instrumented testing. The instrumented Schnadt-Type machine was equipped with strain gauges both on the top of the pendulum and on the chisel. A static force calibration was followed by energy calibration, comparing potential energy losses with the area under the force-deflection curve. Deflection was measured using a high frequency eddy current method on the pendulum, and for slow testing by means of an inductive gauge on the chisel. Charpy-Type specimens of 1.0 mm max notch depth and 0.12 mm max notch radius were pre-cracked using a resonant fatigue testing machine, or an eccentric drive machine. Crack propagation rate da/dN was measured using 'Russenberger' measuring gauges. In addition a new technique for the detection of dynamic crack initiation, developed at the Institute of Research and Technology (TVFA) in Vienna is discussed and some results presented

Methods and Models of Market Risk Stress-Testing of the Portfolio of Financial Instruments

Directory of Open Access Journals (Sweden)

Alexander M. Karminsky

2015-01-01

Full Text Available Amid instability of financial markets and macroeconomic situation the necessity of improving bank risk-management instrument arises. New economic reality defines the need for searching for more advanced approaches of estimating banks vulnerability to exceptional, but plausible events. Stress-testing belongs to such instruments. The paper reviews and compares the models of market risk stress-testing of the portfolio of different financial instruments. These days the topic of the paper is highly acute due to the fact that now stress-testing is becoming an integral part of anticrisis risk-management amid macroeconomic instability and appearance of new risks together with close interest to the problem of risk-aggregation. The paper outlines the notion of stress-testing and gives coverage of goals, functions of stress-tests and main criteria for market risk stress-testing classification. The paper also stresses special aspects of scenario analysis. Novelty of the research is explained by elaborating the programme of aggregated complex multifactor stress-testing of the portfolio risk based on scenario analysis. The paper highlights modern Russian and foreign models of stress-testing both on solo-basis and complex. The paper lays emphasis on the results of stress-testing and revaluations of positions for all three complex models: methodology of the Central Bank of stress-testing portfolio risk, model relying on correlations analysis and copula model. The models of stress-testing on solo-basis are different for each financial instrument. Parametric StressVaR model is applicable to shares and options stress-testing;model based on "Grek" indicators is used for options; for euroobligation regional factor model is used. Finally some theoretical recommendations about managing market risk of the portfolio are given.

Participation in testing and start up operations

International Nuclear Information System (INIS)

Prasad, Y.S.R.

1977-01-01

Testing and start up operations of a nuclear power plant require careful planning. A detailed program of tests and the responsibility of implementing them is discussed. Requirement of documentation covering the tests and operating procedures is explained. The performance of the system during normal and abnomal operating conditions is analysed and required are modifications carried out. Various phases of commissioning and their significance are explained. Preparation of maintenance documentation and training of operating and maintenance staff during this period are discussed. Necessity of close liaison between the regulatory body and the operating organization is explained. (orig.) [de

Test - retest reliability of two instruments for measuring public attitudes towards persons with mental illness

Directory of Open Access Journals (Sweden)

Leufstadius Christel

2011-01-01

Full Text Available Abstract Background Research has identified stigmatization as a major threat to successful treatment of individuals with mental illness. As a consequence several anti-stigma campaigns have been carried out. The results have been discouraging and the field suffers from lack of evidence about interventions that work. There are few reports on psychometric data for instruments used to assess stigma, which thus complicates research efforts. The aim of the present study was to investigate test-retest reliability of the Swedish versions of the questionnaires: FABI and "Changing Minds" and to examine the internal consistency of the two instruments. Method Two instruments, fear and behavioural intentions (FABI and "Changing Minds", used in earlier studies on public attitudes towards persons with mental illness were translated into Swedish and completed by 51 nursing students on two occasions, with an interval of three weeks. Test-retest reliability was calculated by using weighted kappa coefficient and internal consistency using the Cronbach's alpha coefficient. Results Both instruments attain at best moderate test-retest reliability. For the Changing Minds questionnaire almost one fifth (17.9% of the items present poor test-retest reliability and the alpha coefficient for the subscales ranges between 0.19 - 0.46. All of the items in the FABI reach a fair or a moderate agreement between the test and retest, and the questionnaire displays a high internal consistency, alpha 0.80. Conclusions There is a need for development of psychometrically tested instruments within this field of research.

Acceptance test report: Field test of mixer pump for 241-AN-107 caustic addition project

International Nuclear Information System (INIS)

Leshikar, G.A.

1997-01-01

The field acceptance test of a 75 HP mixer pump (Hazleton serial number N-20801) installed in Tank 241-AN-107 was conducted from October 1995 thru February 1996. The objectives defined in the acceptance test were successfully met, with two exceptions recorded. The acceptance test encompassed field verification of mixer pump turntable rotation set-up and operation, verification that the pump instrumentation functions within established limits, facilitation of baseline data collection from the mixer pump mounted ultrasonic instrumentation, verification of mixer pump water flush system operation and validation of a procedure for its operation, and several brief test runs (bump) of the mixer pump

Instrument performance evaluation

International Nuclear Information System (INIS)

Swinth, K.L.

1993-03-01

Deficiencies exist in both the performance and the quality of health physics instruments. Recognizing the implications of such deficiencies for the protection of workers and the public, in the early 1980s the DOE and the NRC encouraged the development of a performance standard and established a program to test a series of instruments against criteria in the standard. The purpose of the testing was to establish the practicality of the criteria in the standard, to determine the performance of a cross section of available instruments, and to establish a testing capability. Over 100 instruments were tested, resulting in a practical standard and an understanding of the deficiencies in available instruments. In parallel with the instrument testing, a value-impact study clearly established the benefits of implementing a formal testing program. An ad hoc committee also met several times to establish recommendations for the voluntary implementation of a testing program based on the studies and the performance standard. For several reasons, a formal program did not materialize. Ongoing tests and studies have supported the development of specific instruments and have helped specific clients understand the performance of their instruments. The purpose of this presentation is to trace the history of instrument testing to date and suggest the benefits of a centralized formal program

Bulk-assay calorimeter: Part 1. System design and operation. Part 2. Calibration and testing

International Nuclear Information System (INIS)

Perry, R.B.; Roche, C.T.; Harkness, A.L.; Winslow, G.H.; Youngdahl, G.A.; Lewis, R.N.; Jung, E.A.

1982-01-01

The Bulk-Assay Calorimeter is designed to measure the thermal power emitted by plutonium-containing samples. The sample power range of the instrument is 1.4 to 22.4 W. The instrument package consists of the calorimeter measurement chamber, the control circuit power bin, and the data acquisition system. Two sample preheating chambers and five calorimeter canisters for containing the samples are included. A set of 32 test points which monitor voltages at points within the calorimeter and its control circuitry are accessed by the data acquisition system. The use of the test points is described. System start-up and checkout are described. Sample assay and preheater operation procedures are given. The data acquisition system and data analysis software are described. The calorimeter was calibrated at 23 points with heat sources from 1.4 to 22.4 watts. The combined measurement error varied with sample power from 1.4% to 0.1% over the range of calibration measurements. Circuit diagrams for the calorimeter and schematics for the data acquisition system are included

SSC Test Operations Contract Overview

Science.gov (United States)

Kleim, Kerry D.

2010-01-01

This slide presentation reviews the Test Operations Contract at the Stennis Space Center (SSC). There are views of the test stands layouts, and closer views of the test stands. There are descriptions of the test stand capabilities, some of the other test complexes, the Cryogenic propellant storage facility, the High Pressure Industrial Water (HPIW) facility, and Fluid Component Processing Facility (FCPF).

Irradiation test on connector part for nuclear instrumentation of nuclear powered ship 'Mutsu'

International Nuclear Information System (INIS)

Kudo, Takahiro; Mizushima, Toshihiko; Tsunoda, Tsunemi; Nakazawa, Toshio

1991-01-01

The nuclear instrumetnation facility of the nuclear powered ship 'Mutsu' is composed of neutron detectors, signal cables and the circuits for measurement, and ocntinuously monitors neutron flux. Since this facility treats very faint signals, for the signal cables, coaxial cables and triple coaxial cables are used. The coaxial cables for the nuclear instrumentation are equipped with connectors at both ends, and those are called prefabricated cable. The prefabricated cables are connected to neutron detectors, and installed in the detection holes of the primary shielding tank in the containment vessel. Therefore, at the time of reactor operation, they are exposed to high radiation, and the deterioration of the characteristics of the prefabricated cables is feared. For the purpose of confirming that the part of deteriorating the insulation of the prefabricated cables is connectors, and clarifying the cause of the deterioration of insulation in connector part, the irradiation test of this time was carried out. The environment in which the prefabricated cables are laid, the specifications of the cables and connectors, the materials, gamma ray irradiation and the test results are reported. (K.I.)

Acceptance Test Procedure for New Pumping and Instrumentation Control Skid M

International Nuclear Information System (INIS)

KOCH, M.R.

1999-01-01

This Acceptance Test Procedure (ATP) verifies proper construction per the design drawings and tests for proper functioning of the Pumping and Instrumentation Control (PIC) skid ''M''. The Scope section lists the systems and functions to be checked. This ATP will be performed at the Site Fabrication Service's (SFS) shop upon completion of construction of the PIC skid

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''V''

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Acceptance Test Procedure (ATP) verifies proper construction per the design drawings and tests for proper functioning of the Pumping Instrumentation and Control (PIC) skid ''V''. The scope section lists the systems and functions to be checked. This ATP will be performed at the Site Fabrication Services (SFS) shop upon completion of the construction of the PIC skid

241-SY-101 DACS instrument problem screen (SCR 448) acceptance test procedure

International Nuclear Information System (INIS)

ERMI, A.M.

1999-01-01

The operability of the 241-SY-101 Data Acquisition and Control System (DACS) to provide proper control and monitoring of the mitigation mixer pump and instrumentation installed in the 241-SY-101 underground storage tank utilizing the [INSTPROB] screen will be systematically evaluated by the performance of this procedure

GPS Test Facility

Data.gov (United States)

Federal Laboratory Consortium — The Global Positioning System (GPS) Test Facility Instrumentation Suite (GPSIS) provides great flexibility in testing receivers by providing operational control of...

Testing the efficiency of rover science protocols for robotic sample selection: A GeoHeuristic Operational Strategies Test

Science.gov (United States)

Yingst, R. A.; Bartley, J. K.; Chidsey, T. C.; Cohen, B. A.; Gilleaudeau, G. J.; Hynek, B. M.; Kah, L. C.; Minitti, M. E.; Williams, R. M. E.; Black, S.; Gemperline, J.; Schaufler, R.; Thomas, R. J.

2018-05-01

The GHOST field tests are designed to isolate and test science-driven rover operations protocols, to determine best practices. During a recent field test at a potential Mars 2020 landing site analog, we tested two Mars Science Laboratory data-acquisition and decision-making methods to assess resulting science return and sample quality: a linear method, where sites of interest are studied in the order encountered, and a "walkabout-first" method, where sites of interest are examined remotely before down-selecting to a subset of sites that are interrogated with more resource-intensive instruments. The walkabout method cost less time and fewer resources, while increasing confidence in interpretations. Contextual data critical to evaluating site geology was acquired earlier than for the linear method, and given a higher priority, which resulted in development of more mature hypotheses earlier in the analysis process. Combined, this saved time and energy in the collection of data with more limited spatial coverage. Based on these results, we suggest that the walkabout method be used where doing so would provide early context and time for the science team to develop hypotheses-critical tests; and that in gathering context, coverage may be more important than higher resolution.

Computer aided instrumented Charpy test applied dynamic fracture toughness evaluation system

International Nuclear Information System (INIS)

Kobayashi, Toshiro; Niinomi, Mitsuo

1986-01-01

Micro computer aided data treatment system and personal computer aided data analysis system were applied to the traditional instrumented Charpy impact test system. The analysis of Charpy absorbed energy (E i , E p , E t ) and load (P y , P m ), and the evaluation of dynamic toughness through whole fracture process, i.e. J Id , J R curve and T mat was examined using newly developed computer aided instrumented Charpy impact test system. E i , E p , E t , P y and P m were effectively analyzed using moving average method and printed out automatically by micro computer aided data treatment system. J Id , J R curve and T mat could be measured by stop block test method. Then, J Id , J R curve and T mat were effectively estimated using compliance changing rate method and key curve method on the load-load point displacement curve of single fatigue cracked specimen by personal computer aided data analysis system. (author)

Utilisation and performance of sodium instrumentation during start-up and initial operation of Phenix

International Nuclear Information System (INIS)

Lions, N.; Buis, H.; Baron, J.; Fournier, C.; Gourdon, J.

1976-01-01

The main process-instruments on the Phenix reactor are presented with the exception of the FFDL System and of the hydrogen-detector which are described in other papers. The results obtained during reactor start-up and during initial operation of the nuclear power-station are given [fr

Proceedings of the International topical meeting on VVER instrumentation and control

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-31

The Proceedings contain the full texts of 44 contributions, out of which 42 have been input to INIS. The papers cover various aspects of WWER instrumentation and control including reactor upgrading and modernization, testing and refurbishment of instrumentation, and operational experience and problems. (A.K.).

Proceedings of the International topical meeting on VVER instrumentation and control

International Nuclear Information System (INIS)

1997-11-01

The Proceedings contain the full texts of 44 contributions, out of which 42 have been input to INIS. The papers cover various aspects of WWER instrumentation and control including reactor upgrading and modernization, testing and refurbishment of instrumentation, and operational experience and problems. (A.K.)

In-pile instrumentation improvements for fuel irradiations in test reactor

International Nuclear Information System (INIS)

Blanc, J.Y.; Bernard, J.L.; Estrade, J.; Geoffroy, G.

1996-01-01

Knowledge of fuel limits and safety margins in normal and off-normal transients in nuclear power plants remains a constant preoccupation for electricity producers and fuel manufacturers. Accurate determination of such limits, through fuel irradiation testing in the OSIRIS reactor at Saclay is closely linked to the reliability of appropriate instrumentation techniques. Two paths are currently followed to obtain short experimental rods: segmented fuel coming directly from power plants, or re-fabrication of rods in hot cells with our FABRICE process. It can be associated with instrumentation such as fuel centerline thermocouple in annular pellets, pressure transducer or fission gas release measurement by gamma-spectrometry using helium sweeping, in analytic experiments. Our present development, to be implemented in 1993, is the the centerline instrumentation of a fuel column with solid pellets. Inserting the thermocouple requires a cold drilling machine, using CO 2 freezing of broken UO 2 (with liquid nitrogen). During the fuel rod irradiation itself, we try to lower the uncertainties associated to power determination, using thermal balance or neutronic calibration, or even gamma spectrometry. A description of the new test train designed for the ISABELLE water loop in OSIRIS is given, with special emphasis on instrumentation: a LVDT for measuring fuel rod elongation and eventual clad failure, and increased number and better localization of thermocouples and SPDN. The third part is devoted to the measurements by optical microdensitometry of neutron radiographs of the fuel pellet dish modification after irradiation. Dishes are generally disappearing through thermal and mechanical deformation of the pellet, and this can eventually be modelized to better understand pellet-cladding mechanical interaction. (author). 3 refs, 5 figs

Measurement of dose equivalent with personal dosemeters and instrumentation of radiological protection in the new operative magnitudes ICRU, for external fields of radiation beta. Part IV. Survey of the angular response of instruments used in radiological protection in secondary patron fields of beta radiation (90Sr/90Y (1850 MBq and 74 MBq), 204TI (18.5 MBq) and 147Pm (518 MBq)

International Nuclear Information System (INIS)

Alvarez R, J.T.

1994-02-01

Tests type were made (type test) in the following commercial instrumentation commonly used in radiological protection: Geiger-Mueller Counters (FH40 FE), Plastic Scintillators (NE-BP/6/4A), Ionization Chambers (RO-5) and Proportional Counters (HP-100A; gas:P-10). With object of checking the possibility that these they can carry out the new operative unit ICRU, H' (0.07; α). The tests consisted on determining the energy and angular response of the detectors in secondary patron fields of beta radiation, for isotopes of 90 Sr/ 90 Y (1850 MBq and 74 MBq and 147 Pm(518 MBq). The results show the inadequate of these commercial instruments for the realization of the H' operative unit (0.07; α) in beta external fields. Due to flaws in the design, construction and calibration of the instruments for this type of radiation fields (Author)

Human-Robot Collaboration Dynamic Impact Testing and Calibration Instrument for Disposable Robot Safety Artifacts.

Science.gov (United States)

Dagalakis, Nicholas G; Yoo, Jae Myung; Oeste, Thomas

2016-01-01

The Dynamic Impact Testing and Calibration Instrument (DITCI) is a simple instrument with a significant data collection and analysis capability that is used for the testing and calibration of biosimulant human tissue artifacts. These artifacts may be used to measure the severity of injuries caused in the case of a robot impact with a human. In this paper we describe the DITCI adjustable impact and flexible foundation mechanism, which allows the selection of a variety of impact force levels and foundation stiffness. The instrument can accommodate arrays of a variety of sensors and impact tools, simulating both real manufacturing tools and the testing requirements of standards setting organizations. A computer data acquisition system may collect a variety of impact motion, force, and torque data, which are used to develop a variety of mathematical model representations of the artifacts. Finally, we describe the fabrication and testing of human abdomen soft tissue artifacts, used to display the magnitude of impact tissue deformation. Impact tests were performed at various maximum impact force and average pressure levels.

In-Pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2013-12-01

For many years, the increase in efficiency in the production of nuclear electricity has been an economic challenge in many countries which have developed this kind of energy. The increase in fuel burnup and fuel residence time leads to a reduction in the volume of fresh fuel loaded and spent fuel discharged, respectively. More demanding nuclear fuel cycle parameters are combined with a need to operate nuclear power plants with maximal availability and load factors, in load-follow mode and with longer fuel cycles. In meeting these requirements, fuel has to operate in a demanding environment of high radiation fields, high temperatures, high mechanical stresses and high coolant flow. Requirements of increased fuel reliability and minimal fuel failures also remain in force. Under such circumstances, continuous development of more radiation resistant fuel materials, especially advanced cladding, careful and incremental examinations, and improved understanding and modelling of high burnup fuel behaviour are required. Following a recommendation of the IAEA Technical Working Group on Fuel Performance and Technology, the Technical Meeting on In-pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials was held in Halden, Norway, on 21-24 August 2012. The purpose of the meeting was to review the current status and the progress in methods and technologies used for the in-pile testing of nuclear fuel achieved since the previous IAEA meeting on In-core Instrumentation and Reactor Core Assessment, also held in Halden in 2007. Emphasis was placed on advanced techniques applied for the understanding of high burnup fuel behaviour of water cooled power reactors that represent the vast majority of the current nuclear reactor fleet. However, the meeting also included papers and discussion on testing techniques applied or developed specifically for new fuel and structural materials considered for Generation-IV systems. The meeting was attended by 43

A Method for Modeling the Virtual Instrument Automatic Test System Based on the Petri Net

Institute of Scientific and Technical Information of China (English)

MA Min; CHEN Guang-ju

2005-01-01

Virtual instrument is playing the important role in automatic test system. This paper introduces a composition of a virtual instrument automatic test system and takes the VXIbus based a test software platform which is developed by CAT lab of the UESTC as an example. Then a method to model this system based on Petri net is proposed. Through this method, we can analyze the test task scheduling to prevent the deadlock or resources conflict. At last, this paper analyzes the feasibility of this method.

Progress of the Hard-wired Instrumentation and Control Works for the Neutral Beam Test Stand at KAERI

Energy Technology Data Exchange (ETDEWEB)

Jung, Ki Sok

2005-12-15

Progress of the hard-wired instrumentation and control works for the neutral beam test stand(NB-TS) has been existed for the past one year period. Details of the installed arc detector circuit are explained. LN{sub 2} level and temperature control during the cryosorption pumping operation are explained with an emphasis on its control circuit. With an expectation of more accurate and sensitive measurement of temperatures than the thermocouple utilization during the calorimeter operation, PT-100 resistance temperature detector(RTD) utilization is initiated and the results are described. During the ion beam experiment, physical measurements are made with some delayed time than the beam extraction, and thus a delayed trigger pulse generator was fabricated and installed to the system. Underlying principles of the electronic circuits for the interlock implementation and optical signal transmission are introduced. These are basically the application of operational amplifier circuits. A cautious aspect of the SMPS(switch mode power supply) utilization is also give.

Progress of the Hard-wired Instrumentation and Control Works for the Neutral Beam Test Stand at KAERI

International Nuclear Information System (INIS)

Jung, Ki Sok

2005-12-01

Progress of the hard-wired instrumentation and control works for the neutral beam test stand(NB-TS) has been existed for the past one year period. Details of the installed arc detector circuit are explained. LN 2 level and temperature control during the cryosorption pumping operation are explained with an emphasis on its control circuit. With an expectation of more accurate and sensitive measurement of temperatures than the thermocouple utilization during the calorimeter operation, PT-100 resistance temperature detector(RTD) utilization is initiated and the results are described. During the ion beam experiment, physical measurements are made with some delayed time than the beam extraction, and thus a delayed trigger pulse generator was fabricated and installed to the system. Underlying principles of the electronic circuits for the interlock implementation and optical signal transmission are introduced. These are basically the application of operational amplifier circuits. A cautious aspect of the SMPS(switch mode power supply) utilization is also give

Irradiation test plan of instrumented capsule(05F-01K) for nuclear fuel irradiation in Hanaro (Revision 1)

Energy Technology Data Exchange (ETDEWEB)

Sohn, Jae Min; Kim, B. G.; Choi, M. H. (and others)

2006-09-15

An instrumented capsule was developed to be able to measure fuel characteristics, such as fuel temperature, internal pressure of fuel rod, fuel pellet elongation, and neutron flux, etc., during the irradiation test of nuclear fuel in HANARO. The instrumented capsule for measuring and monitoring fuel centerline temperature and neutron flux was designed and manufactured. And then, to verify the design of the instrumented capsule in the test hole, it was successfully irradiated in the test hole of HANARO from March 14, 2003 to June 1, 2003 (53.84 full power days at 24 MW). In the year of 2004, 3 test fuel rods and the 03F-05K instrumented fuel capsule were designed and fabricated to measure fuel centerline temperature, internal pressure of fuel rod, and fuel axial deformation during irradiation test. Now, this capsule was successfully irradiated in the test hole OR5 of HANARO reactor from April 27, 2004 to October 1, 2004 (59.5 full power days at 24-30 MW). The capsule and fuel rods have been be dismantled and fuel rods have been examined at the hot cell of IMEF. The instrumented fuel capsule (05F-01K) was designed and manufactured for a design verification test of the dual instrumented fuel rods. The irradiation test of the 05F-01K instrumented fuel capsule will be carried out at the OR5 vertical experimental hole of HANARO.

Financing Build, Operate and Transfer (BOT) Projects: The Case of Islamic Instruments

OpenAIRE

Khan, Tariqullah

2002-01-01

Several member countries of the Islamic Development Bank have embarked upon a program of developing and maintaining infrastructure projects by the private sector in the framework of build operate and transfer (BOT) mechanism and its various variants. The present paper reviews these experiences and the peculiar risks associated with investments in these projects as compared to the risks of traditional manufacturing sector and offers a framework for Islamic instruments to finance BOT projects.

Instrumentation and testing of a prestressed concrete containment vessel model

International Nuclear Information System (INIS)

Hessheimer, M.F.; Pace, D.W.; Klamerus, E.W.

1997-01-01

Static overpressurization tests of two scale models of nuclear containment structures - a steel containment vessel (SCV) representative of an improved, boiling water reactor (BWR) Mark II design and a prestressed concrete containment vessel (PCCV) for pressurized water reactors (PWR) - are being conducted by Sandia National Laboratories for the Nuclear Power Engineering Corporation of Japan and the U.S. Nuclear Regulatory Commission. This paper discusses plans for instrumentation and testing of the PCCV model. 6 refs., 2 figs., 2 tabs

Modeling safety instrumented systems with MooN voting architectures addressing system reconfiguration for testing

International Nuclear Information System (INIS)

Torres-Echeverria, A.C.; Martorell, S.; Thompson, H.A.

2011-01-01

This paper addresses the modeling of probability of dangerous failure on demand and spurious trip rate of safety instrumented systems that include MooN voting redundancies in their architecture. MooN systems are a special case of k-out-of-n systems. The first part of the article is devoted to the development of a time-dependent probability of dangerous failure on demand model with capability of handling MooN systems. The model is able to model explicitly common cause failure and diagnostic coverage, as well as different test frequencies and strategies. It includes quantification of both detected and undetected failures, and puts emphasis on the quantification of common cause failure to the system probability of dangerous failure on demand as an additional component. In order to be able to accommodate changes in testing strategies, special treatment is devoted to the analysis of system reconfiguration (including common cause failure) during test of one of its components, what is then included in the model. Another model for spurious trip rate is also analyzed and extended under the same methodology in order to empower it with similar capabilities. These two models are powerful enough, but at the same time simple, to be suitable for handling of dependability measures in multi-objective optimization of both system design and test strategies for safety instrumented systems. The level of modeling detail considered permits compliance with the requirements of the standard IEC 61508. The two models are applied to brief case studies to demonstrate their effectiveness. The results obtained demonstrated that the first model is adequate to quantify time-dependent PFD of MooN systems during different system states (i.e. full operation, test and repair) and different MooN configurations, which values are averaged to obtain the PFD avg . Also, it was demonstrated that the second model is adequate to quantify STR including spurious trips induced by internal component failure and

Data evaluation for operator-inspector differences for a specific NDA instrument

International Nuclear Information System (INIS)

Franklin, M.

1984-01-01

The Joint Research Centre (JRC) of the European Commission is developing a number of NDA instruments for safeguards use. In particular the JRC has developed a photo neutron active interrogation device (Phonid) for the assay of U-235 in bulk quantities. This report describes new statistical results for the D statistic in the context of data evaluation algorithms for the Phonid instrument. The Phonid instrument is useful for this purpose because its error propagation structure is well characterised and yet not trivially simple. The data evaluation for Phonid data is derived from its error propagation modelling plus new results for the sampling distribution of the D statistic. The problem of assigning an uncertainty to the D statistic value without any diversion strategy assumptions has long been an unresolved problem. The results described in this report provide the solution to this problem by considering the sampling distribution of the D statistic given the population of discrepancies. Discrepancy is defined as the difference between operator declared values and the true values measured by the inspector. This approach provides estimable expressions for the sampling moments of the D statistic without making any assumption about the cause (diversion, clerical error, measurement error) of the discrepancy. The report also provides a general discussion of the distinction between planning a verification and performing the data analysis after the verification has been carried out

Instrumentation of dynamic gas pulse loading system

Energy Technology Data Exchange (ETDEWEB)

Mohaupt, H.

1992-04-14

The overall goal of this work is to further develop and field test a system of stimulating oil and gas wells, which increases the effective radius of the well bore so that more oil can flow into it, by recording pressure during the gas generation phase in real time so that fractures can be induced more predictably in the producing formation. Task 1: Complete the laboratory studies currently underway with the prototype model of the instrumentation currently being studied. Task 2: Perform field tests of the model in the Taft/Bakersfield area, utilizing operations closest to the engineers working on the project, and optimize the unit for various conditions encountered there. Task 3: Perform field test of the model in DGPL jobs which are scheduled in the mid-continent area, and optimize the unit for downhole conditions encountered there. Task 4: Analyze and summarize the results achieved during the complete test series, documenting the steps for usage of downhole instrumentation in the field, and compile data specifying use of the technology by others. Task 5: Prepare final report for DOE, and include also a report on the field tests completed. Describe and estimate the probability of the technology being commercialized and in what time span. The project has made substantial technical progress, though we are running about a month behind schedule. Expenditures are in line with the schedule. Increased widespread interest in the use of DGPL stimulation has kept us very busy. The computer modeling and test instrumentation developed under this program is already being applied to commercial operations.

Electronic constant current and current pulse signal generator for nuclear instrumentation testing

International Nuclear Information System (INIS)

Brown, R.A.

1994-01-01

Circuitry is described for testing the ability of an intermediate range nuclear instrument to detect and measure a constant current and a periodic current pulse. The invention simulates the resistance and capacitance of the signal connection of a nuclear instrument ion chamber detector and interconnecting cable. An LED flasher/oscillator illuminates an LED at a periodic rate established by a timing capacitor and circuitry internal to the flasher/oscillator. When the LED is on, a periodic current pulse is applied to the instrument. When the LED is off, a constant current is applied. An inductor opposes battery current flow when the LED is on. 1 figures

Standard practice for evaluating performance characteristics of ultrasonic Pulse-Echo testing instruments and systems without the use of electronic measurement instruments

CERN Document Server

American Society for Testing and Materials. Philadelphia

2011-01-01

1.1 This practice describes procedures for evaluating the following performance characteristics of ultrasonic pulse-echo examination instruments and systems: Horizontal Limit and Linearity; Vertical Limit and Linearity; Resolution - Entry Surface and Far Surface; Sensitivity and Noise; Accuracy of Calibrated Gain Controls. Evaluation of these characteristics is intended to be used for comparing instruments and systems or, by periodic repetition, for detecting long-term changes in the characteristics of a given instrument or system that may be indicative of impending failure, and which, if beyond certain limits, will require corrective maintenance. Instrument characteristics measured in accordance with this practice are expressed in terms that relate to their potential usefulness for ultrasonic testing. Instrument characteristics expressed in purely electronic terms may be measured as described in E1324. 1.2 Ultrasonic examination systems using pulsed-wave trains and A-scan presentation (rf or video) may be ev...

The Harvard experiment on OSO-6 - Instrumentation, calibration, operation, and description of observations.

Science.gov (United States)

Huber, M. C. E.; Dupree, A. K.; Goldberg, L.; Parkinson, W. H.; Reeves, E. M.; Withbroe, G. L.; Noyes, R. W.

1973-01-01

The Harvard experiment carried by OSO-6 was an extreme-ultraviolet (EUV) spectrometer-spectroheliometer with a wavelength range of 285 to 1385 A, a spatial and spectral bandwidth of 35 x 35(arc sec) squared and 3 A, respectively. The instrument acquired data that have been deposited with the National Space Science Data Center and World Data Center A at the Goddard Space Flight Center in Greenbelt, Maryland, and are now available in their entirety to the scientific community. Aspects of the experiment that are relevant to potential users of the data are described - namely, instrument configuration and parameters, laboratory and inflight calibrations, as well as operational capabilities and procedures. The observations obtained are reported, and the nature, number, and dates of observation, where relevant, are listed.

Laboratory test for ice adhesion strength using commercial instrumentation.

Science.gov (United States)

Wang, Chenyu; Zhang, Wei; Siva, Adarsh; Tiea, Daniel; Wynne, Kenneth J

2014-01-21

A laboratory test method for evaluating ice adhesion has been developed employing a commercially available instrument normally used for dynamic mechanical analysis (TA RSA-III). This is the first laboratory ice adhesion test that does not require a custom-built apparatus. The upper grip range of ∼10 mm is an enabling feature that is essential for the test. The method involves removal of an ice cylinder from a polymer coating with a probe and the determination of peak removal force (Ps). To validate the test method, the strength of ice adhesion was determined for a prototypical glassy polymer, poly(methyl methacrylate). The distance of the probe from the PMMA surface has been identified as a critical variable for Ps. The new test provides a readily available platform for investigating fundamental surface characteristics affecting ice adhesion. In addition to the ice release test, PMMA coatings were characterized using DSC, DCA, and TM-AFM.

ALSAT-2A power subsystem behavior during launch, early operation, and in-orbit test

Science.gov (United States)

Larbi, N.; Attaba, M.; Beaufume, E.

2012-09-01

In 2006, Algerian Space Agency (ASAL) decided to design and built two optical Earth observation satellites. The first one, ALSAT-2A, was integrated and tested as a training and cooperation program with EADS Astrium. The second satellite ALSAT-2B will be integrated by ASAL engineers in the Satellite Development Center (CDS) at Oran in Algeria. On 12th July 2010, Algeria has launched ALSAT-2A onboard an Indian rocket PSLV-C15 from the Sriharikota launch base, Chennaï. ALSAT-2A is the first Earth observation satellite of the AstroSat-100 family; the design is based on the Myriade platform and comprising the first flight model of the New Astrosat Observation Modular Instrument (NAOMI). This Instrument offers a 2.5m ground resolution for the PAN channel and a 10m ground resolution for four multi-spectral channels which provides high imaging quality. The operations are performed from ALSAT-2 ground segment located in Ouargla (Algeria) and after the test phase ALSAT-2A provides successful images. ALSAT-2A electrical power subsystem (EPS) is composed of a Solar Array Generator (SAG ), a Li-ion battery dedicated to power storage and energy source during eclipse or high consumption phases and a Power Conditioning and Distribution Unit (PCDU). This paper focuses primarily on ALSAT-2A electrical power subsystem behavior during Launch and Early OPeration (LEOP) as well as In Orbit Test (IOT). The telemetry data related to the SAG voltage, current and temperature will be analyzed in addition to battery temperature, voltage, charge and discharge current. These parameters will be studied in function of satellite power consumption.

The moisture proof connection of signal cables on test rig instrumentation

Energy Technology Data Exchange (ETDEWEB)

Joung, Chang Young; Ahn, Sung Ho; Hong, Jin Tae; Jeong, Hwang Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-10-15

The rod inner pressure, centerline temperature, coolant temperature, and neutron flux resulting from the irradiation properties of nuclear fuel are an important factor for evaluating nuclear fuel properties in pile. In addition instrumentation and measurement techniques for nuclear fuel are necessary to measure the exact data. Special sensors such as a TC (thermocouple), LVDT (linear variable differential transformer) and SPND (self-powered neutron detector) are instrumented in and out of the fuel rod to measure the various irradiation characteristics of the nuclear fuel. These sensors are made up of the sensor itself and a signal cable. In the instrumentation, an MI (Mineral Insulated) cable used as the signal cable has such properties as high electrical insulation, heat resistance, and mechanical strength. However, it is difficult to handle and treat with care owing to the extremely hard composition, which is made up of weak signal wires and alumina powder in a stainless tube. The sealing of the end tip of the MI cable and extension cable is very important in terms of the insulation resistance to seal the insulator inside the MI cable tube from moisture. To maintain the insulation of sensors and signal cables, the insulation resistance must be checked in accordance with each process throughout the instrumentation and fabrication period. To safely mount the signal cables drawn from a fuel test rig on the terminal block of a junction panel, the MI and extension cables should be easy to connect. Therefore, it is necessary to develop instrumentation technologies of a moisture proof connection process for a fuel test rig. This paper will provide an overview of the work done with moisture proof connection procedures to connect the MI and extension cables to extend the MI cables jointed with the sensor.

Regulatory instrument review: Aging management of LWR cables, containment and basemat, reactor coolant pumps, and motor-operated valves

International Nuclear Information System (INIS)

Werry, E.V.; Somasundaram, S.

1995-09-01

The results of Stage 2 of the Regulatory Instrument Review are presented in this volume. Selected regulatory instruments, such as the Code of Federal Regulations (CFR), US Nuclear Regulatory Commission (NRC), Regulatory Guides, and ASME Codes, were investigated to determine the extent to which these regulations apply aging management to selected safety-related components in nuclear power plants. The Regulatory Instrument Review was funded by the NRC under the Nuclear Plant Aging Research (NPAR) program. Stage 2 of the review focused on four safety-related structures and components; namely, cables, containment and basemat, reactor coolant pumps, and motor-operated valves. The review suggests that the primary-emphasis of the regulatory instruments was on the design, construction, start-up, and operation of a nuclear power plant, and that aging issues were primarily addressed after an aging-related problem was recognized. This Stage 2 review confirms the results of the prior review; (see Regulatory Instrument Review: Management of Aging of LWR Major Safety-Related Components NUREG/CR-5490. The observations indicate that the regulations generally address management of age-related degradation indirectly. Specific age-related degradation phenomena frequently are dealt with in bulletins and notices or through generic issues, letters, etc. The major recommendation of this report, therefore, is that the regulatory instruments should more directly and explicitly address the aging phenomenon and the management of the age-related degradation process

Instrumentation of fuel safety test rods of the PWR system in the Phebus reactor

International Nuclear Information System (INIS)

Schley, Robert; Leveque, J.P.; Aujollet, J.M.; Dutraive, Pierre; Colome, Jean; Bouly, J.C.

1979-01-01

The tests were performed in an experimental cell centred in the core of the PHEBUS water reactor of 50 MW. The CEA make two types of apparatus for testing the safety of PWR fuel. One is for testing a single fuel stick and the other a bunch of 25 sticks. The instrumentation described enables the main parameters of the test to be known: temperatures of the fuel - central temperature of the UO 2 - cladding surface temperatures; temperature of the cooling circuits - thermal balance - temperatures of the structures, etc.; coolant pressure; internal pressure of the fuel sticks; direction and flow rate of the fluid. This instrumentation and the technological problems to be overcome are described and the results of the first tests carried out are given [fr

Test tube systems with cutting/recombination operations

Energy Technology Data Exchange (ETDEWEB)

Freund, R. [Technische Universitaet Wien (Austria); Csuhaj-Varju, E. [Computer and Automation Institute, Budapest (Hungary); Wachtler, F. [Universitaet Wien (Austria)

1996-12-31

We introduce test tube systems based on operations that are closely related to the splicing operations, i.e. we consider the operations of cutting a string at a specific site into two pieces with marking them at the cut ends and of recombining two strings with specifically marked endings. Whereas in the splicing of two strings these strings are cut at specific sites and the cut pieces are recombined immediately in a crosswise way, in CR(cutting/recombination)-schemes cutting can happen independently from recombining the cut pieces. Test tube systems based on these operations of cutting and recombination turn out to have maximal generative power even if only very restricted types of input filters for the test tubes are used for the redistribution of the contents of the test tubes after a period of cuttings and recombinations in the test tubes. 10 refs.

Patient-specific instrumentation for total knee arthroplasty does not match the pre-operative plan as assessed by intra-operative computer-assisted navigation.

Science.gov (United States)

Scholes, Corey; Sahni, Varun; Lustig, Sebastien; Parker, David A; Coolican, Myles R J

2014-03-01

The introduction of patient-specific instruments (PSI) for guiding bone cuts could increase the incidence of malalignment in primary total knee arthroplasty. The purpose of this study was to assess the agreement between one type of patient-specific instrumentation (Zimmer PSI) and the pre-operative plan with respect to bone cuts and component alignment during TKR using imageless computer navigation. A consecutive series of 30 femoral and tibial guides were assessed in-theatre by the same surgeon using computer navigation. Following surgical exposure, the PSI cutting guides were placed on the joint surface and alignment assessed using the navigation tracker. The difference between in-theatre data and the pre-operative plan was recorded and analysed. The error between in-theatre measurements and pre-operative plan for the femoral and tibial components exceeded 3° for 3 and 17% of the sample, respectively, while the error for total coronal alignment exceeded 3° for 27% of the sample. The present results indicate that alignment with Zimmer PSI cutting blocks, assessed by imageless navigation, does not match the pre-operative plan in a proportion of cases. To prevent unnecessary increases in the incidence of malalignment in primary TKR, it is recommended that these devices should not be used without objective verification of alignment, either in real-time or with post-operative imaging. Further work is required to identify the source of discrepancies and validate these devices prior to routine use. II.

Operational test report, integrated system test (ventilation upgrade)

International Nuclear Information System (INIS)

HARTY, W.M.

1999-01-01

Operational Final Test Report for Integrated Systems, Project W-030 (Phase 2 test, RECIRC and HIGH-HEAT Modes). Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks, including upgraded vapor space cooling and filtered venting of tanks AY101, AY102, AZ101, AZ102

Operational test report integrated system test (ventilation upgrade)

Energy Technology Data Exchange (ETDEWEB)

HARTY, W.M.

1999-10-05

Operational Final Test Report for Integrated Systems, Project W-030 (Phase 2 test, RECIRC and HIGH-HEAT Modes). Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks, including upgraded vapor space cooling and filtered venting of tanks AY101, Ay102, AZ101, AZ102.

Preventive maintenance instrumentation results in Spanish nuclear power plants

International Nuclear Information System (INIS)

Curiel, M.; Palomo, M. J.; Verdu, G.; Arnaldos, A.

2010-10-01

This paper is a recompilation of the most significance results in relation to the researching in preventive and predictive maintenance in critical nuclear instrumentation for power plant operation, which it is being developed by Logistica y Acondicionamientos Industriales and the Isirym Institute of the Polytechnic University of Valencia. Instrumentation verification and test, it is a priority of the power plants control and instrumentation department's technicians. These procedures are necessary information for the daily power plant work. It is performed according to different procedures and in different moments of the fuel cycle depending on the instrumentation critical state and the monitoring process. Normally, this study is developed taking into account the instantaneous values of the instrumentation measures and, after their conversion to physical magnitude, they are analyzed according to the power plant operation point. Moreover, redundant sensors measurements are taken into consideration to the equipment and/or power plant monitoring. This work goes forward and it is in advanced to the instrument analysis as it is, independently of the operation point, using specific signal analysis techniques for preventive and predictive maintenance, with the object to obtain not only information about possible malfunctions, but the degradation scale presented in the instrument or in the system measured. We present seven real case studies of Spanish nuclear power plants each of them shall give a significant contribution to problem resolution and power plant performance. (Author)

Re-irradiation tests of spent fuel at JMTR by means of re-instrumentation technique

International Nuclear Information System (INIS)

Nakamura, Jinichi; Shimizu, Michio; Endo, Yasuichi; Nabeya, Hideaki; Ichise, Kenichi; Saito, Junichi; Oshima, Kunio; Uetsuka, Hiroshi

1999-01-01

JAERI has developed re-irradiation test procedures of spent fuel irradiated at commercial reactor by means of re-instrumentation technique. Full length rods irradiated at commercial LWRs were re-fabricated to short length rods, and rod inner pressure gauges and fuel center thermocouples were re-instrumented to the rods. Re-irradiation tests to study the fuel behavior during power change were carried out by means of BOCA/OSF-1 facility at the JMTR. In the tests to study the fission gas release during power change, the rod inner pressure increase was observed during power change, especially during power reduction. The fission gas release during power reduction is estimated to be the release from fission gas bubbles on the grain boundary caused by the thermal stress in the pellet during power reduction. Re-irradiation test of gadolinia added fuel was performed by means of dual re-instrumentation technique (fuel center thermocouples and rod inner pressure gauge). A stepwise fission gas release during power change, and the following fuel center temperature change due to gap conductance change were observed. (author)

Testing Infrastructure for Operating System Kernel Development

DEFF Research Database (Denmark)

Walter, Maxwell; Karlsson, Sven

2014-01-01

Testing is an important part of system development, and to test effectively we require knowledge of the internal state of the system under test. Testing an operating system kernel is a challenge as it is the operating system that typically provides access to this internal state information. Multi......-core kernels pose an even greater challenge due to concurrency and their shared kernel state. In this paper, we present a testing framework that addresses these challenges by running the operating system in a virtual machine, and using virtual machine introspection to both communicate with the kernel...... and obtain information about the system. We have also developed an in-kernel testing API that we can use to develop a suite of unit tests in the kernel. We are using our framework for for the development of our own multi-core research kernel....

Development on experimental VHTR instrumentation

International Nuclear Information System (INIS)

Wakayama, N.; Ara, K.; Terada, H.; Yamagishi, H.; Tomoda, T.

1982-06-01

This paper describes developmental works on the instrumentation of the Experimental VHTR. In the area of the nuclear instrumentation for the reactor control, high temperature fission counter-chambers have been developed. These withstood the accelerated irradiation life tests at 600 deg. C, the long term in-reactor operating test at 600 deg. C and the 800 deg. C-operating tests for several hundred hours in a simulated accident condition. Platinum-Molybdenum alloy thermocouples have been studied as a neutron-irradiation-resistant high-temperature thermocouple for the in-core temperature distribution monitoring of the VHTR in the temperature range between 1000 deg. C and 1350 deg. C. The instability problems of the Pt-5% Mo/Pt-0.1% Mo thermocouple seem to be overcome by introducing a double sheath structure and adopting a better material to the inner sheath. A local failure and abnormality monitoring method for the HTR fuel is also studied using a gas-sweeping irradiation rig for the CPF compacts. This study aims mainly at the development of a method to compensate for the dependency of the FP-release rate on the fuel temperature, the neutron flux density, the burn-up and others, in order to increase the detection sensitivity of fuel failures. (author)

Maintenance of nuclear instruments

International Nuclear Information System (INIS)

Oliveira Rebelo, A.M. de; Santos, C.J.F. dos; Jesus, E.F.O. de; Silva, L.E.M.C.; Borges, J.C.

1988-01-01

A program to design and repairing of nuclear instruments for teaching and research was founded in the UFRJ to find solutions for technical support problem - The GEMD-RADIACOES. This group has assisted to several groups of the University in recuperation and conservation of devices like: Linear scanner, Cromatograph and system of radiation detection in general. Recuperation of these devices had required a study of theirs operations modes, to make it possible the setting up of a similar system. Recuperation also involves operation tests, calibration and technical for users, orienting them to get the best performance. (Author) [pt

Mechanical, electronic and instrumentation development for tracer tests at El Berrocal site

International Nuclear Information System (INIS)

Gutierrez, M.G.; Benitez, A.H.; Yllera de Llano, A.; Romero, P.R.; Aleixandre, J.; Bueno, J.; Gonzalez, O.; Tamarit, J.; Guimera, J.

1997-01-01

The international El Berrocal Project was an integrated exercise in geological, geochemical and hydrogeological characterization with the aim of understanding and modelling the past and present-day migration processes that control the behaviour and distribution of naturally occurring radionuclides in a fractured granitic environment. Information is presented concerning the design and manufacture of the instrumentation used for the large scale tracer tests performed at El Berrocal, and the instrumentation and data acquisition development is specified. (author)

Design, installation, commissioning and operation of a beamlet monitor in the negative ion beam test stand at NIFS

Energy Technology Data Exchange (ETDEWEB)

Antoni, V.; Agostinetti, P.; Brombin, M.; Cervaro, V.; Delogu, R.; Fasolo, D.; Franchin, L.; Ghiraldelli, R.; Molon, F.; Pasqualotto, R.; Serianni, G., E-mail: gianluigi.serianni@igi.cnr.it; Tollin, M.; Veltri, P. [Consorzio RFX (CNR, ENEA, INFN, Università di Padova, Acciaierie Venete SpA) (Italy); De Muri, M. [Consorzio RFX (CNR, ENEA, INFN, Università di Padova, Acciaierie Venete SpA) (Italy); INFN-LNL, v.le dell' Università 2, I-35020, Legnaro (PD) Italy (Italy); Ikeda, K.; Kisaki, M.; Nakano, H.; Takeiri, Y.; Tsumori, K. [National Institute for Fusion Science, 322-6 Oroshi, Toki, Gifu 509-5292 (Japan); Muraro, A. [Istituto di Fisica del Plasma (IFP-CNR) – Via Cozzi 53, 20125, Milano (Italy)

2015-04-08

In the framework of the accompanying activity for the development of the two neutral beam injectors for the ITER fusion experiment, an instrumented beam calorimeter is being designed at Consorzio RFX, to be used in the SPIDER test facility (particle energy 100keV; beam current 50A), with the aim of testing beam characteristics and to verify the source proper operation. The main components of the instrumented calorimeter are one-directional carbon-fibre-carbon composite tiles. Some prototype tiles have been used as a small-scale version of the entire calorimeter in the test stand of the neutral beam injectors of the LHD experiment, with the aim of characterising the beam features in various operating conditions. The extraction system of the NIFS test stand source was modified, by applying a mask to the first gridded electrode, in order to isolate only a subset of the beamlets, arranged in two 3×5 matrices, resembling the beamlet groups of the ITER beam sources. The present contribution gives a description of the design of the diagnostic system, including the numerical simulations of the expected thermal pattern. Moreover the dedicated thermocouple measurement system is presented. The beamlet monitor was successfully used for a full experimental campaign, during which the main parameters of the source, mainly the arc power and the grid voltages, were varied. This contribution describes the methods of fitting and data analysis applied to the infrared images of the camera to recover the beamlet optics characteristics, in order to quantify the response of the system to different operational conditions. Some results concerning the beamlet features are presented as a function of the source parameters.

The Design and Manufacturing Report of Plug Type Non-Instrumented Rig for Irradiation Test in HANARO OR Hole

Energy Technology Data Exchange (ETDEWEB)

Kim, Dae Ho; Bang, Je Geon; Lim, Ik Sung; Kim, Sun Ki; Yang, Yong Sik; Song, Kun Woo

2008-09-15

This project is developed the plug type non-instrumented irradiation test rig of the advanced nuclear fuel in HANARO for pursuit advanced performance in High Performance Fuel Technology Development as a part Nuclear Mid and Long-term R and D Program. This irradiation rig was confirmed the integrity and HANARO core compatibility by the optimum design and the thermal hydraulic out-pile test in FIVPET. The characteristic of plug type non-instrument rig is to possible irradiation test of variable in-pile condition and reduced the wastes for reusable as function. This plug type non-instrumented rig was satisfied the quality assurance requirements and written out the end of manufacturing report. This plug type non-instrumented rig is adopt to the irradiation test for nuclear fuel irradiation test in HANARO OR hole.

Commissioning of the STAR test section for experimental simulation of loss of coolant accident using the EC-208 instrumented fuel assembly of the IEA-R1 reactor

Energy Technology Data Exchange (ETDEWEB)

Maprelian, Eduardo; Torres, Walmir M.; Prado, Adelk C.; Umbehaun, Pedro E.; Franca, Renato L.; Santos, Samuel C.; Macedo, Luiz A.; Sabundjian, Gaiane, E-mail: emaprel@ipen.br, E-mail: wmtorres@ipen.br, E-mail: acprado@ipen.br, E-mail: umbehaun@ipen.br, E-mail: rlfranca@ipen.br, E-mail: samuelcs@ipen.br, E-mail: lamacedo@ipen.br, E-mail: gdjian@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SO (Brazil)

2015-07-01

The three basic safety functions of Research Reactors (RR) are the safe shutdown of the reactor, the proper cooling of the decay heat of the fuel elements and the confinement of radioactive materials. Compared to Nuclear Power Reactors, RR power release is small, yet its three safety functions must be met to ensure the integrity of the reactor. During a loss of coolant accident (LOCA) in pool type RR, partial or complete loss of pool water may occur, with consequent partial or complete uncovering of the fuel assemblies. In such an accident, the decay heat removal safety function must not be compromised. The Test Section for Experimental Simulation of Loss of Coolant Accident (STAR) is in commissioning phase. This test section will provide experimental data on partial and total uncovering of the EC-208 instrumented fuel assembly (IFA) irradiated in the IEA-R1. Experimental results will be useful in validation of computer codes for RR safety analysis, particularly on heat removal efficiency aspects (safety function) in accident conditions. STAR comprises a base on which is installed the IFA, the cylindrical stainless steel hull, the compressed air system for the test section emptying and refilling, and the instrumentation for temperature and level measurements. The commissioning tests or pre-operational check, consist of several preliminary tests to verify experimental procedures, the difficulties during assembling of STAR in the pool, the difficulties in control the emptying and refilling velocities, as well as, the repeatability capacity, tests of equipment, valves and systems and tests of instrumentation and data acquisition system. Safety, accuracy and easiness of operation will be checked. (author)

Do radio frequencies of medical instruments common in the operating room interfere with near-infrared spectroscopy signals?

Science.gov (United States)

Shadgan, Babak; Molavi, Behnam; Reid, W. D.; Dumont, Guy; Macnab, Andrew J.

2010-02-01

Background: Medical and diagnostic applications of near infrared spectroscopy (NIRS) are increasing, especially in operating rooms (OR). Since NIRS is an optical technique, radio frequency (RF) interference from other instruments is unlikely to affect the raw optical data, however, NIRS data processing and signal output could be affected. Methods: We investigated the potential for three common OR instruments: an electrical cautery, an orthopaedic drill and an imaging system, to generate electromagnetic interference (EMI) that could potentially influence NIRS signals. The time of onset and duration of every operation of each device was recorded during surgery. To remove the effects of slow changing physiological variables, we first used a lowpass filter and then selected 2 windows with variable lengths around the moment of device onset. For each instant, variances (energy) and means of the signals in the 2 windows were compared. Results: Twenty patients were studied during ankle surgery. Analysis shows no statistically significant difference in the means and variance of the NIRS signals (p < 0.01) during operation of any of the three devices for all surgeries. Conclusion: This method confirms the instruments evaluated caused no significant interference. NIRS can potentially be used without EMI in clinical environments such as the OR.

Prediction of safety critical software operational reliability from test reliability using testing environment factors

International Nuclear Information System (INIS)

Jung, Hoan Sung; Seong, Poong Hyun

1999-01-01

It has been a critical issue to predict the safety critical software reliability in nuclear engineering area. For many years, many researches have focused on the quantification of software reliability and there have been many models developed to quantify software reliability. Most software reliability models estimate the reliability with the failure data collected during the test assuming that the test environments well represent the operation profile. User's interest is however on the operational reliability rather than on the test reliability. The experiences show that the operational reliability is higher than the test reliability. With the assumption that the difference in reliability results from the change of environment, from testing to operation, testing environment factors comprising the aging factor and the coverage factor are developed in this paper and used to predict the ultimate operational reliability with the failure data in testing phase. It is by incorporating test environments applied beyond the operational profile into testing environment factors. The application results show that the proposed method can estimate the operational reliability accurately. (Author). 14 refs., 1 tab., 1 fig

Performing T-tests to Compare Autocorrelated Time Series Data Collected from Direct-Reading Instruments.

Science.gov (United States)

O'Shaughnessy, Patrick; Cavanaugh, Joseph E

2015-01-01

Industrial hygienists now commonly use direct-reading instruments to evaluate hazards in the workplace. The stored values over time from these instruments constitute a time series of measurements that are often autocorrelated. Given the need to statistically compare two occupational scenarios using values from a direct-reading instrument, a t-test must consider measurement autocorrelation or the resulting test will have a largely inflated type-1 error probability (false rejection of the null hypothesis). A method is described for both the one-sample and two-sample cases which properly adjusts for autocorrelation. This method involves the computation of an "equivalent sample size" that effectively decreases the actual sample size when determining the standard error of the mean for the time series. An example is provided for the one-sample case, and an example is given where a two-sample t-test is conducted for two autocorrelated time series comprised of lognormally distributed measurements.

Instrumentation for the study of low emittance tuning and beam dynamics at CESR

Science.gov (United States)

Billing, M. G.; Dobbins, J. A.; Forster, M. J.; Kreinick, D. L.; Meller, R. E.; Peterson, D. P.; Ramirez, G. A.; Rendina, M. C.; Rider, N. T.; Sagan, D. C.; Shanks, J.; Sikora, J. P.; Stedinger, M. G.; Strohman, C. R.; Williams, H. A.; Palmer, M. A.; Holtzapple, R. L.; Flanagan, J.

2017-11-01

The Cornell Electron-positron Storage Ring (CESR) has been converted from a High Energy Physics electron-positron collider to operate as a dedicated synchrotron light source for the Cornell High Energy Synchrotron Source (CHESS) and to conduct accelerator physics research as a test accelerator, capable of studying topics relevant to future damping rings, colliders and light sources. Some of the specific topics that were targeted for the initial phase of operation of the storage ring in this mode for CESR as a Test Accelerator (CesrTA) included 1) tuning techniques to produce low emittance beams, 2) the study of electron cloud development in a storage ring and 3) intra-beam scattering effects. The complete conversion of CESR to CesrTA occurred over a several year period, described elsewhere [1-3]. In addition to instrumentation for the storage ring, which was created for CesrTA, existing instrumentation was modified to facilitate the entire range of investigations to support these studies. Procedures were developed, often requiring coordinated measurements among different instruments [4]. This paper describes the instruments utilized for the study of beam dynamics during the operation of CesrTA. The treatment of these instruments will remain fairly general in this paper as it focusses on an overview of the instruments themselves. Their interaction and inter-relationships during sequences of observations is found in a companion paper describing the associated measurement techniques. More detailed descriptions and detailed operational performance for some of the instrumentation may be found elsewhere and these will be referenced in the related sections of this paper.

Enhanced in-pile instrumentation at the advanced test reactor

Energy Technology Data Exchange (ETDEWEB)

Rempe, J. L.; Knudson, D. L.; Daw, J. E.; Unruh, T.; Chase, B. M.; Palmer, J.; Condie, K. G.; Davis, K. L. [Idaho National Laboratory, MS 3840, P.O. Box 1625, Idaho Falls, ID 83415 (United States)

2011-07-01

Many of the sensors deployed at materials and test reactors cannot withstand the high flux/high temperature test conditions often requested by users at U.S. test reactors, such as the Advanced Test Reactor (ATR) at the Idaho National Laboratory. To address this issue, an instrumentation development effort was initiated as part of the ATR National Scientific User Facility in 2007 to support the development and deployment of enhanced in-pile sensors. This paper reports results from this effort. Specifically, this paper identifies the types of sensors currently available to support in-pile irradiations and those sensors currently available to ATR users. Accomplishments from new sensor technology deployment efforts are highlighted by describing new temperature and thermal conductivity sensors now available to ATR users. Efforts to deploy enhanced in-pile sensors for detecting elongation and realtime flux detectors are also reported, and recently-initiated research to evaluate the viability of advanced technologies to provide enhanced accuracy for measuring key parameters during irradiation testing are noted. (authors)

Enhanced In-Pile Instrumentation at the Advanced Test Reactor

Science.gov (United States)

Rempe, Joy L.; Knudson, Darrell L.; Daw, Joshua E.; Unruh, Troy; Chase, Benjamin M.; Palmer, Joe; Condie, Keith G.; Davis, Kurt L.

2012-08-01

Many of the sensors deployed at materials and test reactors cannot withstand the high flux/high temperature test conditions often requested by users at U.S. test reactors, such as the Advanced Test Reactor (ATR) at the Idaho National Laboratory. To address this issue, an instrumentation development effort was initiated as part of the ATR National Scientific User Facility in 2007 to support the development and deployment of enhanced in-pile sensors. This paper provides an update on this effort. Specifically, this paper identifies the types of sensors currently available to support in-pile irradiations and those sensors currently available to ATR users. Accomplishments from new sensor technology deployment efforts are highlighted by describing new temperature and thermal conductivity sensors now available to ATR users. Efforts to deploy enhanced in-pile sensors for detecting elongation and real-time flux detectors are also reported, and recently-initiated research to evaluate the viability of advanced technologies to provide enhanced accuracy for measuring key parameters during irradiation testing are noted.

Air pollution control system testing at the DOE offgas components test facility

International Nuclear Information System (INIS)

Burns, D.B.; Speed, D.; VanPelt, W.; Burns, H.H.

1997-01-01

In 1997, the Department of Energy (DOE) Savannah River Site (SRS) plans to begin operation of the Consolidated Incineration Facility (CIF) to treat solid and liquid RCRA hazardous and mixed wastes. The Savannah River Technology Center (SRTC) leads an extensive technical support program designed to obtain incinerator and air pollution control equipment performance data to support facility start-up and operation. A key component of this technical support program includes the Offgas Components Test Facility (OCTF), a pilot-scale offgas system test bed. The primary goal for this test facility is to demonstrate and evaluate the performance of the planned CIF Air Pollution Control System (APCS). To accomplish this task, the OCTF has been equipped with a 1/10 scale CIF offgas system equipment components and instrumentation. In addition, the OCTF design maximizes the flexibility of APCS operation and facility instrumentation and sampling capabilities permit accurate characterization of all process streams throughout the facility. This allows APCS equipment performance to be evaluated in an integrated system under a wide range of possible operating conditions. This paper summarizes the use of this DOE test facility to successfully demonstrate APCS operability and maintainability, evaluate and optimize equipment and instrument performance, and provide direct CIF start-up support. These types of facilities are needed to permit resolution of technical issues associated with design and operation of systems that treat and dispose combustible hazardous, mixed, and low-level radioactive waste throughout and DOE complex

Testing concordance of instrumental variable effects in generalized linear models with application to Mendelian randomization

Science.gov (United States)

Dai, James Y.; Chan, Kwun Chuen Gary; Hsu, Li

2014-01-01

Instrumental variable regression is one way to overcome unmeasured confounding and estimate causal effect in observational studies. Built on structural mean models, there has been considerale work recently developed for consistent estimation of causal relative risk and causal odds ratio. Such models can sometimes suffer from identification issues for weak instruments. This hampered the applicability of Mendelian randomization analysis in genetic epidemiology. When there are multiple genetic variants available as instrumental variables, and causal effect is defined in a generalized linear model in the presence of unmeasured confounders, we propose to test concordance between instrumental variable effects on the intermediate exposure and instrumental variable effects on the disease outcome, as a means to test the causal effect. We show that a class of generalized least squares estimators provide valid and consistent tests of causality. For causal effect of a continuous exposure on a dichotomous outcome in logistic models, the proposed estimators are shown to be asymptotically conservative. When the disease outcome is rare, such estimators are consistent due to the log-linear approximation of the logistic function. Optimality of such estimators relative to the well-known two-stage least squares estimator and the double-logistic structural mean model is further discussed. PMID:24863158

Submicronic Particle Measurement Instrumentation Test Bench Data Acquisition and Control System

International Nuclear Information System (INIS)

Alberdi, J.; Barcala, J. M.; Sanz, D.; Gomez, F. J.; Molinero, A.; Navarrete, J. J.

1999-01-01

This document describes the SAD-100 system characteristics. The unit makes the instrumentation test bench data acquisition and control, SAD-100 was designed and developed by Electronic and Automation Area (CIEMAT) and Aerosol Technology in Energy Generation Project (CIEMAT). (Author) 2 refs

Eddy current testing instruments manufactured by the production unit of the Brno Technical University

International Nuclear Information System (INIS)

Fiala, I.

1989-01-01

Three materials testing machines are described. The ECTER general-purpose machine for materials testing in diagnostics of selected components of nuclear power plants can be used in detection and monitoring of defects of non-ferromagnetic tubes in heat exchangers using an immersion probe for crack, wall thickness and corrosion detection. The instrument for inspection of pipe welding joints, DEST-1, is the sensor of the control system of a welder for axially welded pipes. The third instrument, a device for detection of surface defects in metallic materials is used for testing steel rod materials. It is used in screw mills. (M.D.). 2 figs

Engineering, installation, testing, and initial operation of the DIII-D Advanced Divertor

International Nuclear Information System (INIS)

Andersen, P.M.; Baxi, C.B.; Reis, E.E.; Schaffer, M.J.; Smith, J.P.

1990-09-01

The Advanced Divertor (AD) for General Atomics tokamak, DIII-D, was installed in the summer of 1990. The AD has enabled two classes of physics experiments to be run: divertor biasing and divertor baffling. Both are new experiments for DIII-D. The AD has two principal components: (1) a continuous ring electrode; and (2) a toroidally symmetric baffle. The tokamak can be run in bias baffle or standard DIII-D divertor modes by accurate positioning of the outer divertor strike point through the use of the DIII-D control system. The paper covers design, analysis, fabrication, installation, instrumentation, testing, initial operation, and future plans for the Advanced Divertor from an engineering viewpoint. 2 refs., 5 figs

Real-time operation without a real-time operating system for instrument control and data acquisition

Science.gov (United States)

Klein, Randolf; Poglitsch, Albrecht; Fumi, Fabio; Geis, Norbert; Hamidouche, Murad; Hoenle, Rainer; Looney, Leslie; Raab, Walfried; Viehhauser, Werner

2004-09-01

We are building the Field-Imaging Far-Infrared Line Spectrometer (FIFI LS) for the US-German airborne observatory SOFIA. The detector read-out system is driven by a clock signal at a certain frequency. This signal has to be provided and all other sub-systems have to work synchronously to this clock. The data generated by the instrument has to be received by a computer in a timely manner. Usually these requirements are met with a real-time operating system (RTOS). In this presentation we want to show how we meet these demands differently avoiding the stiffness of an RTOS. Digital I/O-cards with a large buffer separate the asynchronous working computers and the synchronous working instrument. The advantage is that the data processing computers do not need to process the data in real-time. It is sufficient that the computer can process the incoming data stream on average. But since the data is read-in synchronously, problems of relating commands and responses (data) have to be solved: The data is arriving at a fixed rate. The receiving I/O-card buffers the data in its buffer until the computer can access it. To relate the data to commands sent previously, the data is tagged by counters in the read-out electronics. These counters count the system's heartbeat and signals derived from that. The heartbeat and control signals synchronous with the heartbeat are sent by an I/O-card working as pattern generator. Its buffer gets continously programmed with a pattern which is clocked out on the control lines. A counter in the I/O-card keeps track of the amount of pattern words clocked out. By reading this counter, the computer knows the state of the instrument or knows the meaning of the data that will arrive with a certain time-tag.

Heavy vehicle simulator operations: protocol for instrumentation, data collection and data storage - 2nd draft

CSIR Research Space (South Africa)

Jones, DJ

2002-09-01

Full Text Available The instrumentation used is discussed under the relevant sections. Keywords: Accelerated pavement testing (APT), Heavy Vehicle Simulator (HVS) Proposals for implementation: Follow protocol in all future HVS testing. Update as required... future HVS testing. The protocol discusses staffing, site selection and establishment, and data collection, analysis and storage. 1.2. Accelerated Pavement Testing Accelerated Pavement Testing (APT) can be described as a controlled application...

Proceedings of the workshop on operator training for severe accident management and instrumentation capabilities during severe accidents

International Nuclear Information System (INIS)

2001-01-01

This Workshop was organised in collaboration with Electricite de France (Service Etudes et Projets Thermiques et Nucleaires). There were 34 participants, representing thirteen OECD Member countries, the Russian Federation and the OECD/NEA. Almost half the participants represented utilities. The second largest group was regulatory authorities and their technical support organisations. Basically, the Workshop was a follow-up to the 1997 Second Specialist Meeting on Operator Aids for Severe Accident Management (SAMOA-2) [Reports NEA/CSNI/R(97)10 and 27] and to the 1992 Specialist Meeting on Instrumentation to Manage Severe Accidents [Reports NEA/CSNI/R(92)11 and (93)3]. It was aimed at sharing and comparing progress made and experience gained from these two meetings, emphasizing practical lessons learnt during training or incidents as well as feedback from instrumentation capability assessment. The objectives of the Workshop were therefore: - to exchange information on recent and current activities in the area of operator training for SAM, and lessons learnt during the management of real incidents ('operator' is defined hear as all personnel involved in SAM); - to compare capabilities and use of instrumentation available during severe accidents; - to monitor progress made; - to identify and discuss differences between approaches relevant to reactor safety; - and to make recommendations to the Working Group on the Analysis and Management of Accidents and the CSNI (GAMA). The meeting confirmed that only limited information is needed for making required decisions for SAM. In most cases existing instrumentation should be able to provide usable information. Additional instrumentation requirements may arise from particular accident management measures implemented in some plants. In any case, depending on the time frame where the instrumentation should be relied upon, it should be assessed whether it is likely to survive the harsh environmental conditions it will be exposed

New type of radiation instrumentation system

International Nuclear Information System (INIS)

Matsuo, Keichi; Takaoka, Akira; Uranaka, Yasuo

2000-01-01

The Mitsubishi Electric Co., Ltd. developed a radiation instrumentation system introduced some recent techniques such as computation technique, network technique and so on into conventional radiation detection aiming at general market except power generation company. In a conventional system, a detector and an operation processing board was placed at a field and center, respectively, and a feeble pulse signal from the detector was transferred to the operation processing board. Then, on establishment of cables, detectors and operation processing board, it is essential to carry out engineering planning and field engineering conceiving on noise countermeasure. Noise resistance of the new type of radiation instrumentation system, not by adding operation processing function and network interface function into a detector unit in a field to transfer feeble signal, but by transferring testing result as a digital signal. And, noise removing function capable of selectively passing only signal pulse waveform from the detector to judge its signal waveform was also added to a detector unit in the field, to carry out a thoroughly removing noise. In addition, by connecting between each apparatus placed at the field with a network a system capable of reducing some cable engineering could be executed. Here were introduced on abstract of this new type of radiation instrumentation system and on noise removing function of its characteristics. (G.K.)

Instrumentation renewal at the FIR 1 research reactor in Finland

International Nuclear Information System (INIS)

Bars, Bruno; Kall, Leif

1982-01-01

The Finnish TRIGA Mark II reactor (FIR 1 100 kW, later 250 kW steady state power and pulsing capability up to 250 MW) has been in operation for 20 years. The reactor is the only research reactor in Finland and is an important research training and service facility, which obviously will be operated for 10...20 years ahead. The mechanical parts of the reactor are in good shape. Some minor modifications have previously been made in the instrumentation. However, the original instrumentation could hardly have been used for 10...20 years ahead without extensive modifications and modernization. After a careful evaluation and planning process the whole reactor instrumentation was renewed in 1981 at a cost of about 400 000 dollar. The renewal was carried out in cooperation with the Central Research Institute for Physics (KFKI) at the Hungarian Academy of Sciences, which delivered the nuclear part of the instrumentation and with the Finnish company Valmet Oy Instrument Works, which delivered the conventional instrumentation, including the automatic power control system and the control console. The instrumentation, which is located in-a new isolated control room is based on modern industrial standard modular units with standardized signal ranges, electronic testing possibilities, galvanically isolated outputs etc. The instrument renewal project was brought successfully to completion in November 1981 after only about 10 working days of shut down time. The reactor is now in routine operation and the experiences gained from the new instrumentation are excellent. (author)

Building the BIKE: Development and Testing of the Biotechnology Instrument for Knowledge Elicitation (BIKE)

Science.gov (United States)

Witzig, Stephen B.; Rebello, Carina M.; Siegel, Marcelle A.; Freyermuth, Sharyn K.; Izci, Kemal; McClure, Bruce

2014-10-01

Identifying students' conceptual scientific understanding is difficult if the appropriate tools are not available for educators. Concept inventories have become a popular tool to assess student understanding; however, traditionally, they are multiple choice tests. International science education standard documents advocate that assessments should be reform based, contain diverse question types, and should align with instructional approaches. To date, no instrument of this type targeting student conceptions in biotechnology has been developed. We report here the development, testing, and validation of a 35-item Biotechnology Instrument for Knowledge Elicitation (BIKE) that includes a mix of question types. The BIKE was designed to elicit student thinking and a variety of conceptual understandings, as opposed to testing closed-ended responses. The design phase contained nine steps including a literature search for content, student interviews, a pilot test, as well as expert review. Data from 175 students over two semesters, including 16 student interviews and six expert reviewers (professors from six different institutions), were used to validate the instrument. Cronbach's alpha on the pre/posttest was 0.664 and 0.668, respectively, indicating the BIKE has internal consistency. Cohen's kappa for inter-rater reliability among the 6,525 total items was 0.684 indicating substantial agreement among scorers. Item analysis demonstrated that the items were challenging, there was discrimination among the individual items, and there was alignment with research-based design principles for construct validity. This study provides a reliable and valid conceptual understanding instrument in the understudied area of biotechnology.

Innovative instrumentation for VVERs based in non-invasive techniques

International Nuclear Information System (INIS)

Jeanneau, H.; Favennec, J.M.; Tournu, E.; Germain, J.L.

2000-01-01

Nuclear power plants such as VVERs can greatly benefit from innovative instrumentation to improve plant safety and efficiency. In recent years innovative instrumentation has been developed for PWRs with the aim of providing additional measurements of physical parameters on the primary and secondary circuits: the addition of new instrumentation is made possible by using non-invasive techniques such as ultrasonics and radiation detection. These innovations can be adapted for upgrading VVERs presently in operation and also in future VVERs. The following innovative instrumentation for the control, monitoring or testing at VVERs is described: 1. instrumentation for more accurate primary side direct measurements (for a better monitoring of the primary circuit); 2. instrumentation to monitor radioactivity leaks (for a safer plant); 3. instrumentation-related systems to improve the plant efficiency (for a cheaper kWh)

Assessment of the measurement control program for solution assay instruments at the Los Alamos National Laboratory Plutonium Facility

International Nuclear Information System (INIS)

Goldman, A.S.

1985-05-01

This report documents and reviews the measurement control program (MCP) over a 27-month period for four solution assay instruments (SAIs) Facility. SAI measurement data collected during the period January 1982 through March 1984 were analyzed. The sources of these data included computer listings of measurements emanating from operator entries on computer terminals, logbook entries of measurements transcribed by operators, and computer listings of measurements recorded internally in the instruments. Data were also obtained from control charts that are available as part of the MCP. As a result of our analyses we observed agreement between propagated and historical variances and concluded instruments were functioning properly from a precision aspect. We noticed small, persistent biases indicating slight instrument inaccuracies. We suggest that statistical tests for bias be incorporated in the MCP on a monthly basis and if the instrument bias is significantly greater than zero, the instrument should undergo maintenance. We propose the weekly precision test be replaced by a daily test to provide more timely detection of possible problems. We observed that one instrument showed a trend of increasing bias during the past six months and recommend a randomness test be incorporated to detect trends in a more timely fashion. We detected operator transcription errors during data transmissions and advise direct instrument transmission to the MCP to eliminate these errors. A transmission error rate based on those errors that affected decisions in the MCP was estimated as 1%. 11 refs., 10 figs., 4 tabs

Adaptation and testing of psychosocial assessment instruments for cross-cultural use: an example from the Thailand Burma border.

Science.gov (United States)

Haroz, Emily E; Bass, Judith K; Lee, Catherine; Murray, Laura K; Robinson, Courtland; Bolton, Paul

2014-01-01

The purpose of this study was to develop valid and reliable instruments to assess priority psychosocial problems and functioning among adult survivors of systematic violence from Burma living in Thailand. The process involved four steps: 1) instrument drafting and piloting; 2) reliability and validity testing; 3) instrument revision; and 4) retesting revised instrument. A total of N = 158 interviews were completed. Overall subscales showed good internal consistency (0.73-0.92) and satisfactory combined test-retest/inter rater reliability (0.63-0.84). Criterion validity, was not demonstrated for any scale. The alcohol and functioning scales underperformed and were revised (step 3) and retested (step 4). Upon retesting, the function scale showed good internal consistency reliability (0.91-0.92), and the alcohol scale showed acceptable internal consistency (0.79) and strong test-retest/inter-rater reliability (0.86-0.89). This paper describes the importance and process of adaptation and testing, illustrated by the experiences and results for selected instruments in this population.

Instrument failure monitoring in nuclear power systems

International Nuclear Information System (INIS)

Tylee, J.L.

1982-01-01

Methods of monitoring dynamic systems for instrument failures were developed and evaluated. In particular, application of these methods to nuclear power plant components is addressed. For a linear system, statistical tests on the innovations sequence of a Kalman filter driven by all system measurements provides a failure detection decision and identifies any failed sensor. This sequence (in an unfailed system) is zero-mean with calculable covariance; hence, any major deviation from these properties is assumed to be due to an instrument failure. Once a failure is identified, the failed instrument is replaced with an optimal estimate of the measured parameter. This failure accommodation is accomplished using optimally combined data from a bank of accommodation Kalman filters (one for each sensor), each driven by a single measurement. Using such a sensor replacement allows continued system operation under failed conditions and provides a system operator with information otherwise unavailable. To demonstrate monitor performance, a liner failure monitor was developed for the pressurizer in the Loss-of-Fluid Test (LOFT) reactor plant. LOFT is a small-scale pressurized water reactor (PWR) research facility located at the Idaho National Engineering Laboratory. A linear, third-order model of the pressurizer dynamics was developed from first principles and validated. Using data from the LOFT L6 test series, numerous actual and simulated water level, pressure, and temperature sensor failures were employed to illustrate monitor capabilities. Failure monitor design was applied to nonlinear dynamic systems by replacing all monitor linear Kalman filters with extended Kalman filters. A nonlinear failure monitor was derived for LOFT reactor instrumentation. A sixth-order reactor model, including descriptions of reactor kinetics, fuel rod heat transfer, and core coolant dynamics, was obtained and verified with test data

Development of a web based instrument on higher education structures of industrial engineering

OpenAIRE

Tarba Ioan-Cristian

2017-01-01

The research and development of assisted operational instruments on higher education structures of industrial engineering represent a continuous and complex process. The present paper contributes to the building up of support elements and an assisted operational instrument on higher education structures of industrial engineering, with focus on the specific curricula. The use of tested and validated constructive solutions from other projects, as base for the new design, reduces the design time.

Characterization methods for ultrasonic test systems

International Nuclear Information System (INIS)

Busse, L.J.; Becker, F.L.; Bowey, R.E.; Doctor, S.R.; Gribble, R.P.; Posakony, G.J.

1982-07-01

Methods for the characterization of ultrasonic transducers (search units) and instruments are presented. The instrument system is considered as three separate components consisting of a transducer, a receiver-display, and a pulser. The operation of each component is assessed independently. The methods presented were chosen because they provide the greatest amount of information about component operation and were not chosen based upon such conditions as cost, ease of operation, field implementation, etc. The results of evaluating a number of commercially available ultrasonic test instruments are presented

Acceptance for Beneficial Use Pumping Instrumentation and Control Skid L

International Nuclear Information System (INIS)

KOCH, M.R.

1999-01-01

This is a final Acceptance for Beneficial Use (ABU) for Pumping and Instrumentation Control (PIC) skid ''L''. PIC skid ''L'' is ready for pumping tank U-105. All the testing and documentation has been completed as required on the ABU checklist. This ABU covers only the readiness of the PIC skid ''L''. Other U-farm preparations including dilution tank fabrication, portable exhauster readiness, leak detection, valve pit preparation, and the Operation Control Station readiness are not part of this ABU. PIC skid ''L'' is a new skid fabricated and tested at Site Fabrication Services. The skid controls the jet pump and monitors various instruments associated with the pumping operation. This monitoring includes leak detection along the waste transfer route and flammable gases in the pump pit

James Webb Space Telescope (JWST) Integrated Science Instruments Module (ISIM) Cryo-Vacuum (CV) Test Campaign Summary

Science.gov (United States)

Yew, Calinda; Whitehouse, Paul; Lui, Yan; Banks, Kimberly

2016-01-01

JWST Integrated Science Instruments Module (ISIM) has completed its system-level testing program at the NASA Goddard Space Flight Center (GSFC). In March 2016, ISIM was successfully delivered for integration with the Optical Telescope Element (OTE) after the successful verification of the system through a series of three cryo-vacuum (CV) tests. The first test served as a risk reduction test; the second test provided the initial verification of the fully-integrated flight instruments; and the third test verified the system in its final flight configuration. The complexity of the mission has generated challenging requirements that demand highly reliable system performance and capabilities from the Space Environment Simulator (SES) vacuum chamber. As JWST progressed through its CV testing campaign, deficiencies in the test configuration and support equipment were uncovered from one test to the next. Subsequent upgrades and modifications were implemented to improve the facility support capabilities required to achieve test requirements. This paper: (1) provides an overview of the integrated mechanical and thermal facility systems required to achieve the objectives of JWST ISIM testing, (2) compares the overall facility performance and instrumentation results from the three ISIM CV tests, and (3) summarizes lessons learned from the ISIM testing campaign.

Mechanical design and vibro-acoustic testing of ultrathin carbon foils for a spacecraft instrument

Energy Technology Data Exchange (ETDEWEB)

Bernardin, John D [Los Alamos National Laboratory; Baca, Allen G [SNL

2009-01-01

IBEX-Hi is an electrostatic analyzer spacecraft instrument designed to measure the energy and flux distribution of energetic neutral atoms (ENAs) emanating from the interaction zone between the Earth's solar system and the Milky Way galaxy. A key element to this electro-optic instrument is an array of fourteen carbon foils that are used to ionize the ENAs. The foils are comprised of an ultrathin (50-100 {angstrom} thick) layer of carbon suspended across the surface of an electroformed Nickel wire screen, which in turn is held taught by a metal frame holder. The electro formed orthogonal screen has square wire elements, 12.7 {micro}m thick, with a pitch of 131.1 wires/cm. Each foil holder has an open aperture approximately 5 cm by 2.5 cm. Designing and implementing foil holders with such a large surface area has not been attempted for spaceflight in the past and has proven to be extremely challenging. The delicate carbon foils are subject to fatigue failure from the large acoustic and vibration loads that they will be exposed to during launch of the spacecraft. This paper describes the evolution of the foil holder design from previous space instrument applications to a flight-like IBEX-Hi prototype. Vibro-acoustic qualification tests of the IBEX-Hi prototype instrument and the resulting failure of several foils are summarized. This is followed by a discussion of iterative foil holder design modifications and laser vibrometer modal testing to support future fatigue failure analyses, along with additional acoustic testing of the IBEX-Hi prototype instrument. The results of these design and testing activities are merged and the resulting flight-like foil holder assembly is proposed.

Design verification test of instrumented capsule (02F-11K) for nuclear fuel irradiation in HANARO

Energy Technology Data Exchange (ETDEWEB)

Kim, Bong Goo; Sohn, J. M.; Oh, J. M. [and others

2004-01-01

An instrumented capsule is being developed to be able to measure fuel characteristics, such as fuel temperature, internal pressure of fuel rod, fuel elongation, and neutron flux, etc., during the irradiation test of nuclear fuel in HANARO. The instrumented capsule for measuring and monitoring fuel centerline temperature and neutron flux was designed and manufactured. The instrumented capsule includes three test fuel rods installed thermocouple to measure fuel centerline temperature and three SPNDs (Self-Powered Neutron Detector) to monitor the neutron flux. Its stability was verified by out-of-pile performance test, and its safety evaluation was also shown that the safety requirements were satisfied. And then, to verify the design of the instrumented capsule in the test hole, it was successfully irradiated in the test hole of HANARO from March 14, 2003 to June 1, 2003 (53.8 full power days at 24 MWth). During irradiation, the centerline temperature of PWR UO{sub 2} fuel pellets fabricated by KEPCO Nuclear Fuel Company and the neutron flux were continuously measured and monitored. The test fuel rods were irradiated at less than 350 W/cm to 5.13 GWD/MTU with fuel centerline peak temperature below 1,375 .deg. C. The structural stability of the capsule was satisfied by the naked eye in service pool of HANARO. The capsule and test fuel rods were dismantled and test fuel rods were examined at the hot cell of IMEF (Irradiated Material Examination Facility)

Reactor operator screening test experiences

International Nuclear Information System (INIS)

O'Brien, W.J.; Penkala, J.L.; Witzig, W.F.

1976-01-01

When it became apparent to Duquesne Light Company of Pittsburgh, Pennsylvania, that the throughput of their candidate selection-Phase I training-reactor operator certification sequence was something short of acceptable, the utility decided to ask consultants to make recommendations with respect to candidate selection procedures. The recommendation implemented was to create a Nuclear Training Test that would predict the success of a candidate in completing Phase I training and subsequently qualify for reactor operator certification. The mechanics involved in developing and calibrating the Nuclear Training Test are described. An arbitration decision that resulted when a number of International Brotherhood of Electrical Workers union employees filed a grievance alleging that the selection examination was unfair, invalid, not job related, inappropriate, and discriminatorily evaluated is also discussed. The arbitration decision favored the use of the Nuclear Training Test

Research and realization of signal simulation on virtual instrument

Science.gov (United States)

Zhao, Qi; He, Wenting; Guan, Xiumei

2010-02-01

In the engineering project, arbitrary waveform generator controlled by software interface is needed by simulation and test. This article discussed the program using the SCPI (Standard Commands For Programmable Instruments) protocol and the VISA (Virtual Instrument System Architecture) library to control the Agilent signal generator (Agilent N5182A) by instrument communication over the LAN interface. The program can conduct several signal generations such as CW (continuous wave), AM (amplitude modulation), FM (frequency modulation), ΦM (phase modulation), Sweep. As the result, the program system has good operability and portability.

Preventive maintenance instrumentation results in Spanish nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Curiel, M. [Logistica y Acondicionamientos Industriales SAU, Sorolla Center, local 10, Av. de las Cortes Valencianas No. 58, 46015 Valencia (Spain); Palomo, M. J.; Verdu, G. [ISIRYM, Universidad Politecnica de Valencia, Camino de Vera s/n, Valencia (Spain); Arnaldos, A., E-mail: m.curiel@lainsa.co [TITANIA Servicios Tecnologicos SL, Sorolla Center, local 10, Av. de las Cortes Valencianas No. 58, 46015 Valencia (Spain)

2010-10-15

This paper is a recompilation of the most significance results in relation to the researching in preventive and predictive maintenance in critical nuclear instrumentation for power plant operation, which it is being developed by Logistica y Acondicionamientos Industriales and the Isirym Institute of the Polytechnic University of Valencia. Instrumentation verification and test, it is a priority of the power plants control and instrumentation department's technicians. These procedures are necessary information for the daily power plant work. It is performed according to different procedures and in different moments of the fuel cycle depending on the instrumentation critical state and the monitoring process. Normally, this study is developed taking into account the instantaneous values of the instrumentation measures and, after their conversion to physical magnitude, they are analyzed according to the power plant operation point. Moreover, redundant sensors measurements are taken into consideration to the equipment and/or power plant monitoring. This work goes forward and it is in advanced to the instrument analysis as it is, independently of the operation point, using specific signal analysis techniques for preventive and predictive maintenance, with the object to obtain not only information about possible malfunctions, but the degradation scale presented in the instrument or in the system measured. We present seven real case studies of Spanish nuclear power plants each of them shall give a significant contribution to problem resolution and power plant performance. (Author)

Power-Cooling-Mismatch Test Series Test PCM-7. Experiment operating specifications

International Nuclear Information System (INIS)

Sparks, D.T.; Smith, R.H.; Stanley, C.J.

1979-02-01

The experiment operating specifications for the Power-Cooling-Mismatch (PCM) Test PCM-7 to be conducted in the Power Burst Facility are described. The PCM Test Series was designed on the basis of a parametric evaluation of fuel behavior response with cladding temperature, rod internal pressure, time in film boiling, and test rod power being the variable parameters. The test matrix, defined in the PCM Experiment Requirements Document (ERD), encompasses a wide range of situations extending from pre-CHF (critical heat flux) PCMs to long duration operation in stable film boiling leading to rod failure

UPTF test instrumentation. Measurement system identification, engineering units and computed parameters

International Nuclear Information System (INIS)

Sarkar, J.; Liebert, J.; Laeufer, R.

1992-11-01

This updated version of the previous report /1/ contains, besides additional instrumentation needed for 2D/3D Programme, the supplementary instrumentation in the inlet plenum of SG simulator and hot and cold leg of broken loop, the cold leg of intact loops and the upper plenum to meet the requirements (Test Phase A) of the UPTF Programme, TRAM, sponsored by the Federal Minister of Research and Technology (BMFT) of the Federal Republic of Germany. For understanding, the derivation and the description of the identification codes for the entire conventional and advanced measurement systems classifying the function, and the equipment unit, key, as adopted in the conventional power plants, have been included. Amendments have also been made to the appendices. In particular, the list of measurement systems covering the measurement identification code, instrument, measured quantity, measuring range, band width, uncertainty and sensor location has been updated and extended to include the supplementary instrumentation. Beyond these amendments, the uncertainties of measurements have been precisely specified. The measurement identification codes which also stand for the identification of the corresponding measured quantities in engineering units and the identification codes derived therefrom for the computed parameters have been adequately detailed. (orig.)

Modelling of XCO2 Surfaces Based on Flight Tests of TanSat Instruments

Directory of Open Access Journals (Sweden)

Li Li Zhang

2016-11-01

Full Text Available The TanSat carbon satellite is to be launched at the end of 2016. In order to verify the performance of its instruments, a flight test of TanSat instruments was conducted in Jilin Province in September, 2015. The flight test area covered a total area of about 11,000 km2 and the underlying surface cover included several lakes, forest land, grassland, wetland, farmland, a thermal power plant and numerous cities and villages. We modeled the column-average dry-air mole fraction of atmospheric carbon dioxide (XCO2 surface based on flight test data which measured the near- and short-wave infrared (NIR reflected solar radiation in the absorption bands at around 760 and 1610 nm. However, it is difficult to directly analyze the spatial distribution of XCO2 in the flight area using the limited flight test data and the approximate surface of XCO2, which was obtained by regression modeling, which is not very accurate either. We therefore used the high accuracy surface modeling (HASM platform to fill the gaps where there is no information on XCO2 in the flight test area, which takes the approximate surface of XCO2 as its driving field and the XCO2 observations retrieved from the flight test as its optimum control constraints. High accuracy surfaces of XCO2 were constructed with HASM based on the flight’s observations. The results showed that the mean XCO2 in the flight test area is about 400 ppm and that XCO2 over urban areas is much higher than in other places. Compared with OCO-2’s XCO2, the mean difference is 0.7 ppm and the standard deviation is 0.95 ppm. Therefore, the modelling of the XCO2 surface based on the flight test of the TanSat instruments fell within an expected and acceptable range.

Power station instrumentation

International Nuclear Information System (INIS)

Jervis, M.W.

1993-01-01

Power stations are characterized by a wide variety of mechanical and electrical plant operating with structures, liquids and gases working at high pressures and temperatures and with large mass flows. The voltages and currents are also the highest that occur in most industries. In order to achieve maximum economy, the plant is operated with relatively small margins from conditions that can cause rapid plant damage, safety implications, and very high financial penalties. In common with other process industries, power stations depend heavily on control and instrumentation. These systems have become particularly significant, in the cost-conscious privatized environment, for providing the means to implement the automation implicit in maintaining safety standards, improving generation efficiency and reducing operating manpower costs. This book is for professional instrumentation engineers who need to known about their use in power stations and power station engineers requiring information about the principles and choice of instrumentation available. There are 8 chapters; chapter 4 on instrumentation for nuclear steam supply systems is indexed separately. (Author)

SCASim: A Flexible and Reusable Detector Simulator for the MIRI instrument of the JWST

Science.gov (United States)

Beard, S.; Morin, J.; Gastaud, R.; Azzollini, R.; Bouchet, P.; Chaintreuil, S.; Lahuis, F.; Littlejohns, O.; Nehme, C.; Pye, J.

2012-09-01

The JWST Mid Infrared Instrument (MIRI) operates in the 5-28μm wavelength range and can be configured for imaging, coronographic imaging, long-slit, low-resolution spectroscopy or medium resolution spectroscopy with an integral field unit. SCASim is one of a suite of simulators which operate together to simulate all the different modes of the instrument. These simulators are essential for the efficient operation of MIRI; allowing more accurate planning of MIRI observations on sky or during the pre-launch testing of the instrument. The data generated by the simulators are essential for testing the data pipeline software. The simulators not only need to reproduce the behaviour of the instrument faithfully, they also need to be adaptable so that information learned about the instrument during the pre-launch testing and in-orbit commissioning can be fed back into the simulation. SCASim simulates the behaviour of the MIRI detectors, taking into account cosmetic effects, quantum efficiency, shot noise, dark current, read noise, amplifier layout, cosmic ray hits, etc... The software has benefited from three major design choices. First, the development of a suite of MIRI simulators, rather than single simulator, has allowed MIRI simulators to be developed in parallel by different teams, with each simulator able to concentrate on one particular area. SCASim provides a facility common to all the other simulators and saves duplication of effort. Second, SCASim has a Python-based object-oriented design which makes it easier to adapt as new information about the instrument is learned during testing. Third, all simulator parameters are maintained in external files, rather than being hard coded in the software. These design choices have made SCASim highly reusable. In its present form it can be used to simulate any JWST detector, and it can be adapted for future instruments with similar, photon-counting detectors.

Multi-site testing and evaluation of remote sensing instruments for wind energy applications

DEFF Research Database (Denmark)

Sanz Rodrigo, J.; Borbon Guillen, F.; Gomez Arranz, P.

2013-01-01

A procedure for testing and evaluation of remote sensing instruments that makes use of two test sites in flat and complex terrain is presented. To illustrate the method, a system intercomparison experiment is presented involving one sodar and two lidars (pulsed and continuous-wave). The wind...

Development of an End-plug Welding Technology for an Instrumented Fuel Irradiation Test

International Nuclear Information System (INIS)

Kim, Soo Sung; Lee, Chul Yong; Shin, Yoon Taek; Choo, Kee Nam

2010-01-01

The irradiation test of end-plug specimens was planned for the evaluation of nuclear fuels performance. To establish the fabrication process, and for satisfying the requirements of the irradiation test, an orbital-GTA weld machine for the specimens of the dual rods was developed, and the preliminary welding experiments for optimizing the process conditions of the specimens of the dual rods were performed. Dual rods with a 9.5mm diameter and a 0.6mm wall thickness of the cladding tubes and end-plugs have been used and the optimum conditions of the pin-hole welding have also been selected. This paper describes the experimental results of the GTA welds of the specimens of the dual rods and the metallography examinations of the GTA welded specimens for various welding conditions for the instrumented fuel irradiation test. These investigations satisfied the requirements of the instrumented irradiation test and the GTA welds for the specimens of the dual rods at the HANARO research reactor

Mimicking Mars: a vacuum simulation chamber for testing environmental instrumentation for Mars exploration.

Science.gov (United States)

Sobrado, J M; Martín-Soler, J; Martín-Gago, J A

2014-03-01

We have built a Mars environmental simulation chamber, designed to test new electromechanical devices and instruments that could be used in space missions. We have developed this environmental system aiming at validating the meteorological station Rover Environment Monitoring Station of NASA's Mars Science Laboratory mission currently installed on Curiosity rover. The vacuum chamber has been built following a modular configuration and operates at pressures ranging from 1000 to 10(-6) mbars, and it is possible to control the gas composition (the atmosphere) within this pressure range. The device (or sample) under study can be irradiated by an ultraviolet source and its temperature can be controlled in the range from 108 to 423 K. As an important improvement with respect to other simulation chambers, the atmospheric gas into the experimental chamber is cooled at the walls by the use of liquid-nitrogen heat exchangers. This chamber incorporates a dust generation mechanism designed to study Martian-dust deposition while modifying the conditions of temperature, and UV irradiated.

Cryogenic instrumentation needs in the controlled thermonuclear research program

International Nuclear Information System (INIS)

Walstrom, P.L.

1976-01-01

The magnet development effort for the controlled thermonuclear research program will require extensive testing of superconducting coils at various sizes from small-scale models to full-size prototypes. Extensive use of diagnostic instrumentation will be required and to make detailed comparisons of predicted and actual performance in magnet tests and to monitor the test facility for incipient failure modes. At later stages of the program, cryogenic instrumentation will be required to monitor magnet system performance in fusion power reactors. Measured quantities may include temperature, strain, deflection, coil resistance, helium coolant pressure and flow, current, voltages, etc. The test environment, which includes high magnetic fields (up to 8-10 T) and low temperature, makes many commercial measuring devices inoperative or at least inaccurate. In order to ensure reliable measurements, careful screening of commercial devices for performance in the test environment will be required. A survey of potentially applicable instrumentation is presented along with available information on operation in the test environment based on experimental data or on analysis of the physical characteristics of the device. Areas where further development work is needed are delineated

The mechanical design and dynamic testing of the IBEX-H1 electrostatic analyzer spacecraft instrument

Energy Technology Data Exchange (ETDEWEB)

Bernardin, John D [Los Alamos National Laboratory; Baca, Allen G [SNL

2009-01-01

This paper presents the mechanical design, fabrication and dynamic testing of an electrostatic analyzer spacecraft instrument. The functional and environmental requirements combined with limited spacecraft accommodations, resulted in complex component geometries, unique material selections, and difficult fabrication processes. The challenging aspects of the mechanical design and several of the more difficult production processes are discussed. In addition, the successes, failures, and lessons learned from acoustic and random vibration testing of a full-scale prototype instrument are presented.

Instrumentation, control and data acquisition system with multiple configurations for test in nuclear environment

Energy Technology Data Exchange (ETDEWEB)

Monti, Chiara, E-mail: chiara.monti@enea.it; Neri, Carlo; Pollastrone, Fabio

2015-10-15

Highlights: • ENEA developed and characterized a first prototype of the In-Vessel Viewing System (IVVS) probe for ITER. • Piezo motor technology to be used in IVVS probe was tested in neutrons, gamma radiations, high temperature, vacuum and high magnetic fields. • A general architecture of the Data Acquisition and Control System (DACS) was defined and then specialized for each test. • The test campaign has validated instrumentation solutions, which can be effectively used in final IVVS implementation or other ITER diagnostics or applications. - Abstract: The In-Vessel Viewing System is a 3D laser scanning system which will be used to inspect the blanket first wall in ITER. To make the IVVS probe design compatible with the harsh environmental conditions present in ITER, a test campaign was performed in 2012–2013 to verify the adequacy of the main components of the IVVS probe. The IVVS components inspected were an optical encoder, passive components and two customized ultrasonic piezoceramic motors that were instrumented with various sensors. A general architecture of the Data Acquisition and Control System (DACS) was defined and then specialized for each test. To be suitable for this test campaign, the DACS had to host various I/O modules and to properly interface the driver of the customized piezo motors, in order to permit the full control of the test and the acquisition of experimental data. This paper presents the instrumentation solutions designed and implemented for different facilities constraints and the related DACS developed in four specialized versions for the described test campaign.

Operational reliability testing of FBR fuel in EBR-II

International Nuclear Information System (INIS)

Asaga, Takeo; Ukai, Shigeharu; Nomura, Shigeo; Shikakura, Sakae

1991-01-01

The operational reliability testing of FBR fuel has been conducting in EBR-II as a DOE/PNC collaboration program. This paper reviews the achieved summary of Phase-I test as well as outline of progressing Phase-II test. In Phase-I test, the reliability of FBR fuel pins including 'MONJU' fuel was demonstrated at the event of operational transient. Continued operation of the failed pins was also shown to be feasible without affecting the plant operation. The objectives of the Phase-II test is to extend the data base relating with the operational reliability for long life fuel, and to supply the highly quantitative evaluation. The valuable insight obtained in Phase-II test are considerably expected to be useful toward the achievement of commercial FBR. (author)

Temperature buffer test. Installation of buffer, heaters and instruments in the deposition hole

Energy Technology Data Exchange (ETDEWEB)

Johannesson, Lars-Erik; Sanden, Torbjoern; Aakesson, Mattias [Clay Technology AB, Lund (Sweden); Barcena, Ignacio; Garcia-Sineriz, Jose Luis [Aitemin, Madrid (Spain)

2010-12-15

During 2003 the Temperature Buffer Test was installed in Aespoe Hard Rock Laboratory. Temperature, water pressure, relative humidity, total pressure and displacements etc. are measured in numerous points in the test. Most of the cables from the transducers are led in the deposition hole through slots in the rock surface of the deposition hole in watertight tubes to the data collection system in a container placed in the tunnel close to the deposition hole. This report describes the work with the installations of the buffer, heaters, and instruments and yields a description of the final location of all instruments. The report also contains a description of the materials that were installed and the densities yielded after placement.

Temperature buffer test. Installation of buffer, heaters and instruments in the deposition hole

International Nuclear Information System (INIS)

Johannesson, Lars-Erik; Sanden, Torbjoern; Aakesson, Mattias; Barcena, Ignacio; Garcia-Sineriz, Jose Luis

2010-12-01

During 2003 the Temperature Buffer Test was installed in Aespoe Hard Rock Laboratory. Temperature, water pressure, relative humidity, total pressure and displacements etc. are measured in numerous points in the test. Most of the cables from the transducers are led in the deposition hole through slots in the rock surface of the deposition hole in watertight tubes to the data collection system in a container placed in the tunnel close to the deposition hole. This report describes the work with the installations of the buffer, heaters, and instruments and yields a description of the final location of all instruments. The report also contains a description of the materials that were installed and the densities yielded after placement

Instrumentation for three-dimensional tomography

International Nuclear Information System (INIS)

Derenzo, S.E.

1981-01-01

The Donner 280-crystal positron tomograph is described and its operation is explained. The instrument was put into operation in 1978. Possible uses of this instrument in human and animal studies are given

Facilitating Research and Learning in Petrology and Geochemistry through Classroom Applications of Remotely Operable Research Instrumentation