Improving electrical equipment and control systems for shield integrated mining systems

Energy Technology Data Exchange (ETDEWEB)

Rabinovich, Z.M.; Starikov, B.Ya.; Kibrik, I.S.

1984-06-01

The design and operation are discussed for electrical equipment and control systems for the 1AShchM, the ANShch and the 2ANShch shield integrated face systems consisting of shield supports, coal plow and chain conveyor. The shield system is used for mining inclined and steep coal seams endangered by coal dust explosions, methane or rock bursts. Control and electrical system for 3 types of shield face mining systems is similar. It cuts energy supply when methane content at working faces exceeds the maximum permissible level, controls haulage rate and cutting rate of a coal plow, controls operation of shield supports (using the Sirena system), controls dust suppression system and its water consumption. The system is also equipped with communications equipment. Tests of the control and electrical system for the integrated shield system carried out in the im. Gagarin mine in the Ukraine are described. The VAUS III control system developed by Dongiprouglemash was tested.

Program outline of seismic fragility capacity tests on nuclear power plant equipment

International Nuclear Information System (INIS)

Lijima, T.; Abe, H.; Fujita, T.

2004-01-01

A seismic probabilistic safety assessment (PSA) is an available method to evaluate residual risk of nuclear plant that is designed with definitive seismic design condition. Seismic fragility capacity data are necessary for seismic PSA, but we don't have sufficient data of active components of nuclear plants in Japan. This paper describes a plan of seismic fragility capacity tests on nuclear power plant equipment. The purpose of those tests is to obtain seismic fragility capacity of important equipment from a safety design point of view. And the equipment for the fragility capacity tests were selected considering effect on core damage frequency (CDF) that was evaluated by our preliminary seismic PSA. Consequently horizontal shaft pump, electric cabinets, Control Rod Drive system (CRD system) of BWR and PWR plant and vertical shaft pump were selected. The seismic fragility capacity tests are conducted from phase-1 to phase-3, and horizontal shaft pump and electric cabinets are tested on phase-1. The fragility capacity test consists of two types of tests. One is actual equipment test and another is element test. On actual equipment test, a real size model is tested with high-level seismic motion, and critical acceleration and failure mode are investigated. Regarding fragility test phase-1, we selected typical type horizontal shaft pump and electric cabinets for the actual equipment test. Those were Reactor Building Closed Cooling Water (RCW) Pump and eight kinds of electric cabinets such as relay cabinet, motor control center. On the test phase-1, maximum input acceleration for the actual equipment test is intended to be 6-G-force. Since the shaking table of TADOTSU facility did not have capability for high acceleration, we made vibration amplifying system. In this system, amplifying device is mounted on original shaking table and it moves in synchronization with original table. The element test is conducted with many samples and critical acceleration, median and

Weight/balance portable test equipment

International Nuclear Information System (INIS)

Whitlock, R.W.

1994-01-01

This document shows the general layout, and gives a part description for the weight/balance test equipment. This equipment will aid in the regulation of the leachate loading of tanker trucks. The report contains four drawings with part specifications. The leachate originates from lined trenches

Is there a role for a test controller in the development of new ATC equipment?

Science.gov (United States)

Westrum, Ron

1994-01-01

Earl Wiener points out that human factors problems fixed during the R & D stage are paid for once. When they are not fixed during R & D, they are then paid for every day. How users are involved in the R & D process to assist in developing equipment is a critical issue. Effective involvement can produce real improvements. Ineffective involvement can produce inefficient kludges or systems that are actually dangerous. The underlying problem is the management of information and ideas. To develop a really generative system a great deal would have to change in the way that the FAA innovates. Use of test controllers would solve only some of the problems. For instance, we have cockpit resource management now for pilots; we may have it soon for controllers. But the management of ideas in the innovation process also needs intellectual resource management. Simply involving users is not enough. Brought in at the wrong point in the development process, users can block or compromise innovation. User involvement must be carefully considered. A test controller may be one solution to this problem. It might be necessary to have several kinds of test controllers (en route versus TRACON, for instance). No doubt further problems would surface in getting test controllers into operation. I would recommend that the FAA engage in a series of case studies of controller involvement in the innovation process. A systematic comparison of effective and ineffective cases would do much to clarify what we ought to do in the future. Unfortunately, I have been unable to find any cases where test controllers have been used. Perhaps we need to create some, to see how they work.

Automatic dose-rate controlling equipment

International Nuclear Information System (INIS)

Szasz, T.; Nagy Czirok, Cs.; Batki, L.; Antal, S.

1977-01-01

The patent of a dose-rate controlling equipment that can be attached to X-ray image-amplifiers is presented. In the new equipment the current of the photocatode of the image-amplifier is led into the regulating unit, which controls the X-ray generator automatically. The advantages of the equipment are the following: it can be simply attached to any type of X-ray image-amplifier, it accomplishes fast and sensitive regulation, it makes possible the control of both the mA and the kV values, it is attached to the most reliable point of the image-transmission chain. (L.E.)

Regulation EM-GT-7. Quality control of the radiography equipment

International Nuclear Information System (INIS)

2015-01-01

The purpose of this document is to provide practical guidance of technical procedures for carrying out quality control in X-ray equipment. This guide is applicable to general purpose radiography equipment, although some of the procedures may be applied to other types of diagnostic imaging equipment. The tests described require the appointed instrumentation and some of these can be implemented in the radiodiagnostic given the simplicity of them and others require special equipment and can be performed by external specialized groups to these units.

Development of automatic Ultrasonic testing equipment for reactor pressure vessel

International Nuclear Information System (INIS)

Kim, Kor R.; Kim, Jae H.; Lee, Jae C.

1996-06-01

The selected weld areas of a reactor pressure vessel and adjacent piping are examined by the remote mechanized ultrasonic testing (MUT) equipment. Since the MUT equipment was purchased from southwest Research Institute (SwRI) in April 1985, 15 inservice inspections and 5 preservice inspections are performed with this MUT equipment. However due to the old age of the equipment and frequent movements to plant sites, the reliability of examination was recently decreased rapidly and it is very difficult to keep spare parts. In order to resolve these problems and to meet the strong request from plant sites, we intend to develop a new 3-axis control system including hardware and software. With this control system, we expect more efficient and reliable examination of the nozzle to shell weld areas, which is specified in ASME Code Section XI. The new 3-axis control system hardware and software were designed and development of our own control system, the advanced technologies of computer control mechanism were established and examination reliability of the nozzle to shell weld area was improved. With the development of our 3-axis control system for PaR ISI-2 computer control system, the reliability of nozzle to shell weld area examination has been improved. The established technologies from the development and detailed analysis of existing control system, are expected to be applied to the similar control systems in nuclear power plants. (author). 12 refs., 4 tabs., 33 figs

Development of automatic Ultrasonic testing equipment for reactor pressure vessel

Energy Technology Data Exchange (ETDEWEB)

Kim, Kor R.; Kim, Jae H.; Lee, Jae C.

1996-06-01

The selected weld areas of a reactor pressure vessel and adjacent piping are examined by the remote mechanized ultrasonic testing (MUT) equipment. Since the MUT equipment was purchased from southwest Research Institute (SwRI) in April 1985, 15 inservice inspections and 5 preservice inspections are performed with this MUT equipment. However due to the old age of the equipment and frequent movements to plant sites, the reliability of examination was recently decreased rapidly and it is very difficult to keep spare parts. In order to resolve these problems and to meet the strong request from plant sites, we intend to develop a new 3-axis control system including hardware and software. With this control system, we expect more efficient and reliable examination of the nozzle to shell weld areas, which is specified in ASME Code Section XI. The new 3-axis control system hardware and software were designed and development of our own control system, the advanced technologies of computer control mechanism were established and examination reliability of the nozzle to shell weld area was improved. With the development of our 3-axis control system for PaR ISI-2 computer control system, the reliability of nozzle to shell weld area examination has been improved. The established technologies from the development and detailed analysis of existing control system, are expected to be applied to the similar control systems in nuclear power plants. (author). 12 refs., 4 tabs., 33 figs.

Guidelines for Electromagnetic Interference Testing of Power Plant Equipment: Revision 3 to TR-102323

International Nuclear Information System (INIS)

Cunningham, J.; Shank, J.

2004-01-01

To continue meeting safety and reliability requirements while controlling costs, operators of nuclear power plants must be able to replace and upgrade equipment in a cost-effective manner. One issue that has been problematic for new plant equipment and especially for digital instrumentation and control (I and C) systems in recent years is electromagnetic compatibility (EMC). The EMC issue usually involves testing to show that critical equipment will not be adversely affected by electromagnetic interference (EMI) in the plant environment. This guide will help nuclear plant engineers address EMC issues and qualification testing in a consistent, comprehensive manner

Guidelines for Electromagnetic Interference Testing of Power Plant Equipment: Revision 3 to TR-102323

Energy Technology Data Exchange (ETDEWEB)

J. Cunningham and J. Shank

2004-11-01

To continue meeting safety and reliability requirements while controlling costs, operators of nuclear power plants must be able to replace and upgrade equipment in a cost-effective manner. One issue that has been problematic for new plant equipment and especially for digital instrumentation and control (I&C) systems in recent years is electromagnetic compatibility (EMC). The EMC issue usually involves testing to show that critical equipment will not be adversely affected by electromagnetic interference (EMI) in the plant environment. This guide will help nuclear plant engineers address EMC issues and qualification testing in a consistent, comprehensive manner.

Waste Handling Equipment Development Test and Evaluation Study

International Nuclear Information System (INIS)

R.L. Tome

1998-01-01

The purpose of this study is to identify candidate Monitored Geologic Repository (MGR) surface waste handling equipment for development testing. This study will also identify strategies for performing the development tests. Development testing shall be implemented to support detail design and reduce design risks. Development testing shall be conducted to confirm design concepts, evaluate alternative design concepts, show the availability of needed technology, and provide design documentation. The candidate equipment will be selected from MGR surface waste handling equipment that is the responsibility of the Management and Operating Contractor (M and O) Surface Design Department. The equipment identified in this study is based on Viability Assessment (VA) design. The ''Monitored Geologic Repository Test and Evaluation Plan'' (MGR T and EP), Reference 5.1, was used as a basis for this study. The MGR T and EP reflects the extent of test planning and analysis that can be conducted, given the current status of the MGR requirements and latest VA design information. The MGR T and EP supports the appropriate sections in the license application (LA) in accordance with 10 CFR 60.2 1(c)(14). The MGR T and EP describes the following test activities: site characterization to confirm, by test and analysis, the suitability of the Yucca Mountain site for housing a geologic repository; development testing to investigate and document design concepts to reduce risk; qualification testing to verify equipment compliance with design requirements, specifications, and regulatory requirements; system testing to validate compliance with MGR requirements, which include the receipt, handling, retrieval, and disposal of waste; periodic performance testing to verify preclosure requirements and to demonstrate safe and reliable MGR operation; and performance confirmation modeling, testing, and analysis to verify adherence to postclosure regulatory requirements. Development test activities can be

Improving the Thermal Testing Technology of Technological Equipment of Autonomous Complexes

Directory of Open Access Journals (Sweden)

V. V. Chugunkov

2017-01-01

Full Text Available The environmental conditions of autonomous objects of different-purpose technical complexes are in close relationship with increased values of operating temperatures. This requires thermal pretesting of the process equipment. The publication [1] considers the thermal test conditions in which the equipment elements under test are placed in a heated water tank covered by the globe insulators where, under automatic temperature control using a block of heaters, they are then kept for a specified period of time at a specified temperature range. Such an approach to the thermal tests of equipment allows us to reduce, but not eliminate completely the mass flows of water from evaporation with reducing power consumption of test equipment.Despite the results achieved, even a little bit of water vapor available when conducting the thermal tests may cause a failure of equipment. Therefore, there is a need in test equipment modernization for complete eliminating the fluxes of mass water and better power consumption in the test process. To this end, it is proposed to place a three-layer bubble wrap on the open surface of water.To justify an efficiency of the proposed option was developed a mathematical model of heat and mass transfer processes that occur during thermal tests, taking into account the geometric and thermo-physical characteristics of test tank, polymer film, and equipment. Using the laws and equations of heat and mass transfer enabled us to determine the required capacities for heating the tank with water and equipment to the required temperature range for a specified time, as well as the mass flows of water when evaporating from the tank surface.The efficiency of the three-layer bubble film as compared with the globe insulators as the elements for covering the test tank the surface has been analysed on the basis of the results obtained.The proposed film coating allowed almost complete elimination of evaporation losses of water mass and almost 8

Quality control test solutions for diagnostic radiology, nuclear medicine and health physics with PTW equipment

International Nuclear Information System (INIS)

Froescher, Olga

2007-01-01

Complete test of publication follows. In 1922 PTW-Freiburg was founded to produce and market a revolutionary new electromechanical component for measuring very small electrical charges. Today PTW is the specialist and one of the global market leaders for manufacturing and supplying high-quality products in diagnostic radiology, nuclear medicine, radiation therapy and health physics. The quality control of X-ray images is influenced by a number of parameters. To maintain a consistent performance of X-ray installations, quality checks have to be conducted regularly. PTW offers a variety of diagnostic test tools for different X-ray devices, and therefore to reduce patient exposure and costs for X-ray departments. PTW's 'Code of Practice' defines in an easy and compact way how to perform quality control measurements on different diagnostic X-ray installations. The necessary equipment for measuring main parameters as well as acceptable limits are mentioned accordingly. The 'Code of Practice' bases on actual standards.

Diagnosis - Using automatic test equipment and artificial intelligence expert systems

Science.gov (United States)

Ramsey, J. E., Jr.

Three expert systems (ATEOPS, ATEFEXPERS, and ATEFATLAS), which were created to direct automatic test equipment (ATE), are reviewed. The purpose of the project was to develop an expert system to troubleshoot the converter-programmer power supply card for the F-15 aircraft and have that expert system direct the automatic test equipment. Each expert system uses a different knowledge base or inference engine, basing the testing on the circuit schematic, test requirements document, or ATLAS code. Implementing generalized modules allows the expert systems to be used for any different unit under test. Using converted ATLAS to LISP code allows the expert system to direct any ATE using ATLAS. The constraint propagated frame system allows for the expansion of control by creating the ATLAS code, checking the code for good software engineering techniques, directing the ATE, and changing the test sequence as needed (planning).

WP EMPLACEMENT CONTROL AND COMMUNICATION EQUIPMENT DESCRIPTIONS

International Nuclear Information System (INIS)

Raczka, N.T.

1997-01-01

The objective and scope of this document are to list and briefly describe the major control and communication equipment necessary for waste package emplacement at the proposed nuclear waste repository at Yucca Mountain. Primary performance characteristics and some specialized design features of the required equipment are explained and summarized in the individual subsections of this document. This task was evaluated in accordance with QAP-2-0 and found not to be quality affecting. Therefore, this document was prepared in accordance with NAP-MG-012. The following control and communication equipment are addressed in this document: (1) Programmable Logic Controllers (PLC's); (2) Leaky Feeder Radio Frequency Communication Equipment; (3) Slotted Microwave guide Communication Equipment; (4) Vision Systems; (5) Radio Control Equipment; and (6) Enclosure Cooling Systems

Imaging Sensor Flight and Test Equipment Software

Science.gov (United States)

Freestone, Kathleen; Simeone, Louis; Robertson, Byran; Frankford, Maytha; Trice, David; Wallace, Kevin; Wilkerson, DeLisa

2007-01-01

The Lightning Imaging Sensor (LIS) is one of the components onboard the Tropical Rainfall Measuring Mission (TRMM) satellite, and was designed to detect and locate lightning over the tropics. The LIS flight code was developed to run on a single onboard digital signal processor, and has operated the LIS instrument since 1997 when the TRMM satellite was launched. The software provides controller functions to the LIS Real-Time Event Processor (RTEP) and onboard heaters, collects the lightning event data from the RTEP, compresses and formats the data for downlink to the satellite, collects housekeeping data and formats the data for downlink to the satellite, provides command processing and interface to the spacecraft communications and data bus, and provides watchdog functions for error detection. The Special Test Equipment (STE) software was designed to operate specific test equipment used to support the LIS hardware through development, calibration, qualification, and integration with the TRMM spacecraft. The STE software provides the capability to control instrument activation, commanding (including both data formatting and user interfacing), data collection, decompression, and display and image simulation. The LIS STE code was developed for the DOS operating system in the C programming language. Because of the many unique data formats implemented by the flight instrument, the STE software was required to comprehend the same formats, and translate them for the test operator. The hardware interfaces to the LIS instrument using both commercial and custom computer boards, requiring that the STE code integrate this variety into a working system. In addition, the requirement to provide RTEP test capability dictated the need to provide simulations of background image data with short-duration lightning transients superimposed. This led to the development of unique code used to control the location, intensity, and variation above background for simulated lightning strikes

The use of fuzzy logic in quality control testing of automotive and tractor equipment

Directory of Open Access Journals (Sweden)

Korobko А.

2016-08-01

Full Text Available The article analyzes the relevance of the research topics, defines goals and objectives, subject and object of research. On the basis of the literature analysis, the following eduction was made: not all the test methods in road and agricultural vehicles (tractors contribute to the effective implementation of the requirements of normative documents including international, inter-laboratory comparative tests. The approach in laboratory testing to the synthesis adaptive system of metrological assurance the use of fuzzy logic is proposed. These labs conduct testing of automotive and tractor equipment. The decision is under risk. The scheme of metrological assurance system covers all parties to ensure the necessary accuracy of measurements and tests; the necessary normative-technical documentation is provided; availability of measuring instruments and test equipment, standards and reference measures; availability of qualified personnel; the assurance that test results are accurate (correct and precision; provides effective decisions based on objective information.

Outline of sodium-water reaction test in case of large leak with SWAT-3 testing equipments

International Nuclear Information System (INIS)

Sato, Minoru

1978-01-01

The key component in sodium-cooled fast reactors in steam generators, and the sodium-water reaction owing to the break of heating tubes may cause serious damages in equipments and pipings. The main factor controlling this phenomenon is the rate of leak of water. When the rate of water leak is small, the propagation of heating tube breaking may occur owing to ''wastage phenomenon'', on the other hand, when the rate of water leak is large, the phenomena of explosive pressure and flow occur due to the reaction heat and a large quantity of hydrogen generated by the reaction. In PNC, the testing equipments of SWAT-2 for small water leak and SWAT-1 for large leak were constructed, and the development test has been carried out to establish the method of safety design experimentally. The synthetic test equipment for the safety of steam generators, SWAT-3, was constructed to carry out the large water leak test in the scale close to actual plants. The object of the test, the outline of the test equipment, the phenomena of pressure and flow in the water injection test, the confirmation of the occurrence of secondary breaking of adjacent heating tubes, and the disposal of reaction products are described in this paper. This test is till going on, and the final conclusion will be reported later. (Kako, I.)

Shaking table testing of electrical equipment in Argentina

International Nuclear Information System (INIS)

Carmona, J.S.; Zabala, F.; Santalucia, J.; Sisterna, C.; Magrini, M.; Oldecop, L.

1995-01-01

This paper describes the testing facility, the methodology applied and the results obtained in the seismic qualification tests of different types of electric equipment. These tests were carried out on a shaking table that was developed and built at the Earthquake Research Institute of the National University of San Juan, Argentine. The equipment tested consist of 500 KV and 132 KV current transformers, a 500 KV voltage transformer, a 145 KV disconnecter and a relay cabinet. The acceleration response of the tested equipment was measured at several locations distributed along its height, and strains were measured at critical points by strain gauges cemented on the base of the porcelain insulator. All the information was recorded with a data acquisition system at a sampling rate of 200 times per second in each channel. The facility developed at this Institute is the largest one in operation in Argentina at present and the equipment tested is the highest, heaviest and more slender one which has been seismically qualified on a shaking table in this country. These tests have been a valuable experience in the field of structural dynamic testing applied to equipment of hydroelectric and nuclear power plants. (author)

Test strategies for industrial testers for converter controls equipment

International Nuclear Information System (INIS)

Oleniuk, P.; Kasampalis, V.; Cosmo, M. Di; Nisbet, D.; Todd, B.; Uznański, S.

2017-01-01

Power converters and their controls electronics are key elements for the operation of the CERN accelerator complex, having a direct impact on its availability. To prevent early-life failures and provide means to verify electronics, a set of industrial testers is used throughout the converters controls electronics' life cycle. The roles of the testers are to validate mass production during the manufacturing phase and to provide means to diagnose and repair failed modules that are brought back from operation. In the converter controls electronics section of the power converters group in the technology department of CERN (TE/EPC/CCE), two main test platforms have been adopted: a PXI platform for mixed analogue-digital functional tests and a JTAG Boundary-Scan platform for digital interconnection and functional tests. Depending on the functionality of the device under test, the appropriate test platforms are chosen. This paper is a follow-up to results presented at the TWEPP 2015 conference, adding the boundary scan test platform and the first results from exploitation of the test system. This paper reports on the test software, hardware design and test strategy applied for a number of devices that has resulted in maximizing test coverage and minimizing test design effort.

Guidelines for Quality Control of Equipment Used in Diagnostic Radiology in the Netherlands

International Nuclear Information System (INIS)

Berg, L. van den; Aarts, C.N.M.; Beentjes, L.B.; Dalen, A. van; Elsakkers, P.; Julius, H.W.; Kicken, P.J.H.; Meer, F. van der; Teeuwisse, W.; Thijssen, M.A.O.; Zoetelief, J.

1998-01-01

The Dutch working group on 'Quality Criteria for Equipment Used in Diagnostic Radiology' has formulated guidelines providing technical criteria for equipment used in conventional diagnostic radiology. These guidelines are applicable to the technical parameters having a major impact on image quality and patient dose and include methods for testing. The following parameters are included: tube voltage, automatic exposure control, film processing, film-screen combination, light tightness and illumination of the dark room, half-value layer and filtration, light field, grid, focal spot size, viewing boxes and geometrical indicators. Each guideline consists of the following chapters: (1) Scope and field of application, (2) Background information, (3) Test procedure, (4) Test frequency, (5) Registration of observations, (6) Evaluation and interpretation, (7) Test report. Chapter 3 includes both the principles of the test method and a step by step description of the procedures. The principles of the test procedure provide a basis for adaptation to local circumstances. The step by step test procedure allows a quality control measurement to be performed with limited physical knowledge of the equipment. Chapter 6 includes limiting values. Draft guidelines were evaluated in practice in 20 hospitals. The final document has been accepted by the professional societies in the Netherlands and the Dutch Minister of Health as a reference set of tools to perform Quality Control of equipment used for conventional diagnostic radiology. (author)

Lessons learned in testing of Safeguards equipment

International Nuclear Information System (INIS)

Pepper, Susan; Farnitano, Michael; Carelli, Joseph

2001-01-01

Upgrade Travel Funding' - This subtask provides funding for the upgrade of DIS equipment installed in the field; E.125.3, 'DIS Radiation Field Characterization' - This subtask provides for the procurement by the IAEA of radiation measurement equipment and technical assistance for the characterization of radiation conditions in the locations where DIS will be installed. This will help the IAEA ensure that the design specifications for the equipment are consistent with the location where the instrument will be used; E.125.4, 'DIS Design Limit Testing and Advise to Strengthen IAEA's Current Equipment Qualification Criteria' - Under this subtask, Wyle Laboratories and Quanterion Solutions will conduct SDIS design limit testing, including harsh environmental testing and accelerated aging, to determine the expected lifetime and produce a design limit report to include maximum operating environment vs. design limit analysis. Additionally, this task will include the development of a strengthened environmental qualification test plan and reliability and maintainability definition methodology for all safeguards equipment. The implementation of new equipment by the Department of Safeguards is costly. Expected costs associated with the implementation of equipment include capital costs, training and in some cases travel. The cost is dramatically increased when operational issues arise due to the costs of studying the issues, modifying and upgrading the equipment and additional travel. The U.S. Support Program believes that the IAEA's Division of Safeguards Technical Support (SGTS) must strengthen its equipment-testing program to ensure that the equipment it approves for inspection use is reliable and will not place additional burden on the Department of Safeguards' maintenance and inspection staff. The U.S. Support Program recognizes that SGTS already requires a series of fundamentally important and revealing tests, but we believe that additional tests should be added to the testing

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

Cold Regions Logistic Supportability Testing of Electronic, Avionic and Communications Equipment.

Science.gov (United States)

1985-06-20

Comment : 2. Have all data collected been reviewed for correctness and completeness? YES NO . Comment : 3. Were the facilities, test equipment...insufficient test planning? YES NO . Comment : 5. Were the test results compromised in any way due to test performance procedures? YES NO . Comment : 6. Were the...test results compromised in any way due to test control pro- cedures? YES NO Comment : 7. Were the test results compromised in any way due to data

High Temperature Calcination - MACT Upgrade Equipment Pilot Plant Test

Energy Technology Data Exchange (ETDEWEB)

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

2004-02-01

About one million gallons of acidic, hazardous, and radioactive sodium-bearing waste are stored in stainless steel tanks at the Idaho Nuclear Technology and Engineering Center (INTEC), which is a major operating facility of the Idaho National Engineering and Environmental Laboratory. Calcination at high-temperature conditions (600 C, with alumina nitrate and calcium nitrate chemical addition to the feed) is one of four options currently being considered by the Department of Energy for treatment of the remaining tank wastes. If calcination is selected for future processing of the sodium-bearing waste, it will be necessary to install new off-gas control equipment in the New Waste Calcining Facility (NWCF) to comply with the Maximum Achievable Control Technology (MACT) standards for hazardous waste combustors and incinerators. This will require, as a minimum, installing a carbon bed to reduce mercury emissions from their current level of up to 7,500 to <45 {micro}g/dscm, and a staged combustor to reduce unburned kerosene fuel in the off-gas discharge to <100 ppm CO and <10 ppm hydrocarbons. The staged combustor will also reduce NOx concentrations of about 35,000 ppm by 90-95%. A pilot-plant calcination test was completed in a newly constructed 15-cm diameter calciner vessel. The pilot-plant facility was equipped with a prototype MACT off-gas control system, including a highly efficient cyclone separator and off-gas quench/venturi scrubber for particulate removal, a staged combustor for unburned hydrocarbon and NOx destruction, and a packed activated carbon bed for mercury removal and residual chloride capture. Pilot-plant testing was performed during a 50-hour system operability test January 14-16, followed by a 100-hour high-temperature calcination pilot-plant calcination run January 19-23. Two flowsheet blends were tested: a 50-hour test with an aluminum-to-alkali metal molar ratio (AAR) of 2.25, and a 50-hour test with an AAR of 1.75. Results of the testing

Development of an above-knee prosthesis equipped with a microcomputer-controlled knee joint: first test results.

Science.gov (United States)

Aeyels, B; Peeraer, L; Vander Sloten, J; Van der Perre, G

1992-05-01

The shortcomings of conventional above-knee prostheses are due to their lack of adaptive control. Implementation of a microcomputer controlling the knee joint in a passive way has been suggested to enhance the patient's gait comfort, safety and cosmesis. This approach was used in the design of a new prosthetic system for the above-knee amputee, and tested on one patient. The knee joint of a conventional, modular prosthesis was replaced by a knee joint mechanism, equipped with a controllable brake on the knee joint axis. Sensors and a microcomputer were added, keeping the system self-contained. The modularity of the design permits the use of an alternative, external, PC-based control unit, emulating the self-contained one, and offering extended data monitoring and storage facilities. For both units an operating environment was written, including sensor/actuator interfacing and the implementation of a real-time interrupt, executing the control algorithm. A double finite state approach was used in the design of the control algorithm. On a higher level, the mode identification algorithm reveals the patient's intent. Within a specific mode (lower level), the relevant mode control algorithm looks for the current phase within the gait cycle. Within a particular phase, a specific simple control action with the brake replaces normal knee muscle activity. Tests were carried out with one prosthetic patient using a basic control algorithm for level walking, allowing controlled knee flexion during stance phase. The technical feasibility of such a concept is illustrated by the test results, even though only flexion during early stance phase was controlled during the trials.(ABSTRACT TRUNCATED AT 250 WORDS)

Engineering Work Plan for the Development of Phased Startup Initiative (PSI) Phases 3 and 4 Test Equipment

International Nuclear Information System (INIS)

PITNER, A.L.

2000-01-01

A number of tools and equipment pieces are required to facilitate planned test operations during Phases 3 and 4 of the Phased Startup Initiative (PSI). These items will be used in assessing residual canister sludge quantities on cleaned fuel assemblies, sorting coarse and fine scrap fuel pieces, assessing the size distribution of scrap pieces, loading scrap into a canister, and measuring the depth of the accumulated scrap in a canister. This work plan supercedes those previously issued for development of several of these test items. These items will be considered prototype equipment until testing has confirmed their suitability for use in K West Basin. The process described in AP-EN-6-032 will be used to qualify the equipment for facility use. These items are considered non-OCRWM for PSI Phase 3 applications. The safety classification of this equipment is General Service, with Quality Level 0 (for PSI Phase 3). Quality Control inspections shall be performed to verify basic dimensions and overall configurations of fabricated components, and any special quality control verifications specified in this work plan (Section 3.1.5). These inspections shall serve to approve the test equipment for use in K West Basin (Acceptance Tag). This equipment is for information gathering only during PSI Phases 3 and 4 activities, and will be discarded at the completion of PSI. For equipment needed to support actual production throughput, development/fabrication/testing activities would be more rigorously controlled

Characterization of a PET-NEMA/IEC body phantom for quality control tests of PET/CT equipment

International Nuclear Information System (INIS)

Oliveira, Cassio M.; Vieira, Igor F.; Lima, Fernando R.A.; Sa, Lidia V. de

2011-01-01

The Brazilian Sanitary Agency from Ministry of Health requires that all PET/CT equipment must undergo minimal quality control tests using manufacturer simulators. The PET-NEMA/IEC body phantom is recommended by the IEC and NEMA to perform acceptance testing and quality control in PET/CT equipment according to specific protocols. It is essential that all simulator components (spheres and body) are properly characterized in relation to their size and internal structure volumes, since they are used to calculate the overall activity concentration and the total weight. The objective of this work was characterize a PET-NEMA/IEC body phantom for the true reconstruction in computational modeling and correct analysis of experimental results. The simulator is basically composed of three structures: the body (simulating a portion of the chest), an inner cylinder (simulating the lung tissue) and a top cover in which are coupled spheres of different sizes simulating 'hot' (tumors) and cold lesions. The spheres were evaluated in terms of volume. The same evaluations were performed with the body of the simulator and the inner cylinder, beyond of analysis of their weights (filled with water) and wall thickness. The data showed that the total weight of the simulator with all its internal structures is 12.5 kg and the volume of the 'hot' and 'cold' spheres are approximately equal to those presented by the manufacturer. The inner cylinder volume showed a significant difference between the measured and the presented in the manual. The results were used for reconstruction of the simulator in computational modeling using the code GATE. (author)

Measurement and control system for ITER remote maintenance equipment

Energy Technology Data Exchange (ETDEWEB)

Oka, Kiyoshi; Kakudate, Satoshi; Takeda, Nobukazu; Takiguchi, Yuji; Akou, Kentaro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-04-01

ITER in-vessel components such as blankets and divertors are categorized as scheduled maintenance components because they are subjected to severe plasma heat and particle loads. Blanket maintenance requires remote handling equipment and tools able to handle Heavy payloads of about 4 tons within a 2 mm precision tolerance. Divertor maintenance requires remote replacement of 60 cassettes with a dead weight of about 25 tons each. In the ITER R and D program, full-scale remote handling equipment for blanket and divertor maintenance has been designed and assembled for demonstration tests. This paper reviews the measurement and control system developed for full-scale remote handling equipment, the Japan Home Team contribution. (author)

Measurement and control system for ITER remote maintenance equipment

International Nuclear Information System (INIS)

Oka, Kiyoshi; Kakudate, Satoshi; Takeda, Nobukazu; Takiguchi, Yuji; Akou, Kentaro

1998-01-01

ITER in-vessel components such as blankets and divertors are categorized as scheduled maintenance components because they are subjected to severe plasma heat and particle loads. Blanket maintenance requires remote handling equipment and tools able to handle Heavy payloads of about 4 tons within a 2 mm precision tolerance. Divertor maintenance requires remote replacement of 60 cassettes with a dead weight of about 25 tons each. In the ITER R and D program, full-scale remote handling equipment for blanket and divertor maintenance has been designed and assembled for demonstration tests. This paper reviews the measurement and control system developed for full-scale remote handling equipment, the Japan Home Team contribution. (author)

Thermal fatigue equipment to test joints of materials for high heat flux components

International Nuclear Information System (INIS)

Visca, E.; Libera, S.; Orsini, A.; Riccardi, B.; Sacchetti, M.

2000-01-01

The activity, carried out in the framework of an ITER divertor task, was aimed at defining a suitable method in order to qualify junctions between armour materials and heat sink of plasma-facing components (PFCs) mock-ups. An equipment able to perform thermal fatigue testing by electrical heating and active water-cooling was constructed and a standard for the sample was defined. In this equipment, during operation cycles, two samples are heated by thermal contact up to a relevant temperature value (350 deg. C) and then the water flow is switched on, thus producing fast cooling with time constants and gradients close to the real operating conditions. The equipment works with a test cycle of about 60 s and is suitable for continuous operation. A complete test consists of about 10000 cycles. After the assembling, the equipment and the control software were optimized to obtain a good reliability. Preliminary tests on mock-ups with flat CFC tiles joined to copper heat sink were performed. Finite-elements calculations were carried out in order to estimate the value of the thermal stresses arising close to the joint under the transient conditions that are characteristic of this equipment

Electronic quality control on dental x-rays equipment

International Nuclear Information System (INIS)

Pomares C, Martin

1996-09-01

A brief description of dental x-ray equipment is done. The non-invasive quality control is treated as than the responsibilities from the dentists to the patient and the equipment. A propose for quality control for dental x-ray equipment, film and developer is include

Development of a Test Equipment for Performance Evaluation of Safety Systems

International Nuclear Information System (INIS)

Kim, S. J.; Kwon, S. M.; Lee, J. M.; Kim, C. K.; Cho, C. H.; Chun, J. H.; Park, M. K.

2004-07-01

The purpose of this study is to develop a test equipment for performance evaluation of safety systems in nuclear power plants. First, we develop an input-output simulator for reactor protection systems, ESF component control systems, and a data acquisition system for these I/O simulators as a hardware for this equipment. Then, we develop a software for human-machine interface system, which is easy-to-use and easy-to-modify. In addition, a simulation tool for a reactor trip switch gear is developed

Exposure parameters in fluoroscopy equipment. Quality control

International Nuclear Information System (INIS)

Alonso, M.; Castaneda, M.J.; Matorras, P.; Diaz-Caneja, N.; Gutierrez, I.

1992-01-01

Within the quality control program in Diagnostic Radiology currently being undertaken at the 'Marques de Valdecilla' University Hospital, the corresponding specification and procedure prototypes for the control of conventional radioscopy equipment have been elaborated and applied. This paper presents the values proposed in the specifications and those obtained for the following radioscopy equipment parameters: reference kerma, and its reproducibility, kerma linearity, maximum kerma at the skin, and total filtration. The results obtained indicate that the equipment studied could comply with specified requirements if a Maintenance Program were to be implemented in coordination with the Quality Control Program. (author)

Regulation EM-GT-8. Guidance for quality control of mammography equipment

International Nuclear Information System (INIS)

2015-01-01

Objective: To provide practical guidance of technical procedures for carrying out quality control in mammography equipment. Scope: This guide applies to mammography equipment. A number of methods which require the appointed instrumentation described, some of which can be implemented in radiology services own country given the low complexity of themselves and others that require specific equipment and can be performed by specialized groups external to these units. The guide does not constitute a mandatory, however, the parameters evaluated according to the tests described therein and their tolerances form the basis of regulations that establish the CCEEM about these teams. Overview: The success of mammographic studies depends on obtaining high-quality images combined with a low rate of patient dose. To ensure this objective the establishment of quality assurance programs on all aspects involving these services is necessary. This guide provides a number of quality control procedures aimed at x-ray equipment, which must be performed at least on an annual basis or when some maintenance occurs at x-ray equipment.

Investigation of possible methods for equipment self-tests in digital radiology

International Nuclear Information System (INIS)

Zoetelief, J.; Idris, H. H. E.; Jansen, J. T. M.

2005-01-01

Quality control in digital radiology can be time-consuming. Equipment self-tests may significantly decrease staff workload. The two most essential parameters for radiology systems are image quality and patient dose. Concerning patient dose, information on the dose-area product (DAP) values generally forms the basis for assessment of patient dose. DAP-values can be measured using a transmission ionisation chamber or calculated from equipment settings. In the present study, various image quality parameters were derived using a contrast-detail (C-D) phantom. The investigation included a computer-aided assessment of C-D images, which produced various parameters, and also parameters based upon scoring by human observers. In addition, another parameter was calculated from modulation transfer function (MTF) measurements. The automatically calculated parameters showed good correlation with human readings, although the number of X-ray systems studied is still limited. We propose a combined evaluation of DAP and automatically calculated C-D or MTF parameters for equipment self-tests. (authors)

Development of Partial Discharging Simulation Test Equipment

Science.gov (United States)

Kai, Xue; Genghua, Liu; Yan, Jia; Ziqi, Chai; Jian, Lu

2017-12-01

In the case of partial discharge training for recruits who lack of on-site work experience, the risk of physical shock and damage of the test equipment may be due to the limited skill level and improper operation by new recruits. Partial discharge simulation tester is the use of simulation technology to achieve partial discharge test process simulation, relatively true reproduction of the local discharge process and results, so that the operator in the classroom will be able to get familiar with and understand the use of the test process and equipment.The teacher sets up the instrument to display different partial discharge waveforms so that the trainees can analyze the test results of different partial discharge types.

submitter Test strategies for industrial testers for converter controls equipment

CERN Document Server

Oleniuk, P; Kasampalis, V; Nisbet, D; Todd, B; Uznański, S

2017-01-01

Power converters and their controls electronics are key elements for the operation of the CERN accelerator complex, having a direct impact on its availability. To prevent early-life failures and provide means to verify electronics, a set of industrial testers is used throughout the converters controls electronics' life cycle. The roles of the testers are to validate mass production during the manufacturing phase and to provide means to diagnose and repair failed modules that are brought back from operation. In the converter controls electronics section of the power converters group in the technology department of CERN (TE/EPC/CCE), two main test platforms have been adopted: a PXI platform for mixed analogue-digital functional tests and a JTAG Boundary-Scan platform for digital interconnection and functional tests. Depending on the functionality of the device under test, the appropriate test platforms are chosen. This paper is a follow-up to results presented at the TWEPP 2015 conference, adding the boundary s...

Specification and acceptance testing of nuclear medicine equipment

International Nuclear Information System (INIS)

Wegst, A.V.; Erickson, J.J.

1984-01-01

The purchase of nuclear medicine equipment is of prime importance in the operation of a clinical service. Failure to properly evaluate the potential uses of the instrumentation and the various operational characteristics of the equipment can often result in the purchase of inappropriate or inferior instruments. The magnitude of the purchase in terms of time and financial investments make it imperative that the purchase be approached in a systematic manner. Consideration of both the intended clinical functions and personnel requirements is important. It is necessary also to evaluate the ability of the equipment vendor to support the instrumentation after the purchase has been completed and the equipment installed in the clinical site. The desired specifications of the instrument characteristics should be stated in terms that can be verified by acceptance testing. The complexity of modern instrumentation and the sensitivity of it to the environment require the buyer to take into account the potential problems of controlling the temperature, humidity, and electrical power of the installation site. If properly and systematically approached, the purchase of new nuclear medicine instrumentation can result in the acquisition of a powerful diagnostic tool which will have a useful lifetime of many years. If not so approached, it may result in the expenditure of a large amount of money and personnel time without the concomitant return in useful clinical service. (author)

On-Line Radiation Test Facility for Industrial Equipment needed for the Large Hadron Collider at CERN

CERN Document Server

Rausch, R

1999-01-01

The future Large Hadron Collider to be built at CERN will use superconducting magnets cooled down to 1.2 K. To preserve the superconductivity, the energy deposition dose levels in equipment located outside the cryostat, in the LHC tunnel, are calculated to be of the order of 1 to 10 Gy per year. At such dose levels, no major radiation-damage problems are to be expected, and the possibility of installing Commercial Of The Shelf (COTS) electronic equipment in the LHC tunnel along the accelerator is considered. To this purpose, industrial electronic equipment and circuits have to be qualified and tested against radiation to insure their long term stability and reliability. An on-line radiation test facility has been setup at the CERN Super Proton Synchrotron (SPS) and a program of on-line tests for electronic equipment is ongoing. Equipment tested includes Industrial Programmable Logic Controllers (PLCs) from several manufacturers, standard VME modules, Fieldbuses like Profibus, WorldFIP and CAN, various electro...

Improved control rod drive handling equipment for BWRs [boiling-water reactors]: Final report

International Nuclear Information System (INIS)

Turner, A.P.L.; Gorman, J.A.

1987-08-01

Improved equipment for removing and replacing control rod drives (CRDs) in BWR plants has been designed, built and tested. Control rod drives must be removed from the reactor periodically for servicing. Removal and replacement of CRDs using equipment originally supplied with the plant has long been recognized as one of the more difficult and highest radiation exposure maintenance operations that must be performed at BWR plants. The improved equipment was used for the first time at Quad Cities, Unit 2, during a Fall 1986 outage. The trial of the equipment was highly successful, and it was shown that the new equipment significantly improves CRD handling operations. The new equipment significantly simplifies the sequence of operations required to lower a CRD from its housing, upend it to a horizontal orientation, and transport it out of the reactor containment. All operations of the new equipment are performed from the undervessel equipment handling platform, thus, eliminating the requirement for a person to work on the lower level of the undervessel gallery which is often highly contaminated. Typically, one less person is required to operate the equipment than were used with the older equipment. The new equipment incorporates a number of redundant and fail safe features that improve operations and reduce the chances for accidents

Performance of the standard FAIR equipment controller prototype

International Nuclear Information System (INIS)

Rauch, S.; Baer, R.C.; Panschow, W.; Thieme, M.

2012-01-01

For the control system of the new FAIR accelerator facility a standard equipment controller, the Scalable Control Unit (SCU), is presently under development. First prototypes have already been tested in real applications. The controller combines an *86 COM Express TM Board and an Altera Arria TM II FPGA. Over a parallel bus interface called the SCU bus, up to 12 slave boards can be controlled. Communication between CPU and FPGA is done by a PCIe link. We discuss the real time behaviour between the Linux OS and the FPGA Hardware. For the test, a Front-End Software Architecture (FESA) class, running under Linux, communicates with the PCIe bridge in the FPGA. Although we are using PCIe only for single 32 bit wide accesses to the FPGA address space, the performance still seems sufficient. The tests showed an average response time to IRQs of 50 μs with a 1.6 GHz Intel Atom CPU. This includes the context change to the FESA user space application and the reply back to the FPGA. Further topics are the bandwidth of the PCIe link for single/burst transfers and the performance of the SCU bus communication. (authors)

Nuclear electronic equipment for control and monitoring panel. Specifications and methods for testing radiation detectors

International Nuclear Information System (INIS)

Roguin, Andre.

1976-02-01

This document will be of interest to users and makers of neutron and gamma radiations detectors in the field of nuclear reactor control and protection. Information is given which will enable users to optimize their choice and methods of using equipment, and makers to optimize their methods of fabrication. It should also serve as a model from which official specifications, technical instructions and test methods for these detectors, could be established. A detailed description is given of the appropriate parameters, terminology and notations. General specifications, operating conditions and test methods are indicated. The following detectors are studied: in-core detectors: fission ionization chambers, self powered neutron detectors (S.P.N.D.); out-core detectors: boron ionization chambers (for monitoring), boron trifluoride proportional counter tubes, boron lined proportional counter tubes, helium-3 proportional counter tubes. The devices described in the document are intended for industrial radiation monitoring applications and not for calibration standards (dosimetry) or for health physics measurement purposes. They are characterized by their fidelity, fast response, reliability and long lifetimes [fr

Initial acceptance test experience with FFTF plant equipment

International Nuclear Information System (INIS)

Brown, R.K.; Coleman, K.A.; Mahaffey, M.K.; McCargar, C.G.; Young, M.W.

1978-09-01

The purpose of this paper is to examine the initial acceptance test experience of certain pieces of auxiliary equipment of the Fast Flux Test Facility (FFTF). The scope focuses on the DHX blowers and drive train, inert gas blowers, H and V containment isolation valves, and the Surveillance and In-service Inspection (SISI) transporter and trolley. For each type of equipment, the discussion includes a summary of the design and system function, installation history, preoperational acceptance testing procedures and results, and unusual events and resolutions

Research on Modularized Design and Allocation of Infectious Disease Prevention and Control Equipment in China.

Science.gov (United States)

Zhao, Xin; Wang, Yun-Dou; Zhang, Xiao-Feng; Gao, Shu-Tian; Guo, Li-Jun; Sun, Li-Na

2017-06-01

For the prevention and control of newly emergent or sudden infectious diseases, we built an on-site, modularized prevention and control system and tested the equipment by using the clustering analysis method. On the basis of this system, we propose a modular equipment allocation method and 4 applications of this method for different types of infectious disease prevention and control. This will help to improve the efficiency and productivity of anti-epidemic emergency forces and will provide strong technical support for implementing more universal and serialized equipment in China. (Disaster Med Public Health Preparedness. 2017;11:375-382).

Automatic system of tests for control equipment in combined cycle power stations; Sistema automatico de pruebas para equipos de control en centrales de ciclo combinado

Energy Technology Data Exchange (ETDEWEB)

Martinez M, Miguel A; Flores L, Zenon; Delgadillo V, Miguel A; Gutierrez A, Ruben [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

2001-07-01

This article deals on the Automatic System of Tests, denominated PROBADOR, used by the Gerencia de Control e Instrumentation (GCI) of the Instituto de Investigaciones Electricas (IIE)for the accomplishment of dynamic tests in laboratory, to the systems of acquisition and control developed with the electronic line SAC-IIE that are installed in the Thermoelectric Power station of Combined Cycle (CTCC) of Dos Bocas, Veracruz and Gomez Palacio, Durango, Mexico. Also the architecture, the functions that are carried out in the equipment of the System of Acquisition and control (SAC) and in the personal computer (PC) that conforms it are described, as well as the methodology used for the development of the tests. The PC constitutes Interface Man-Machine (IMM) and in the SAC equipment the simulation of the processes is made (by means of the execution of algebraic-differential equations) in the compressor, combustion chamber, gas turbine, heat recuperators, steam turbines and condenser equipment that integrate a CTCC. The equations that are used are based in the thermodynamics, flow dynamics and heat transfer; they become attached to the real process with a margin of error that is estimated in 10%. Finally, the tendencies of the PROBADOR and the technical and economic advantages are described that it has provided for the improvement in the performance of the control systems, before different situations, with no need to have the real process. [Spanish] Este articulo versa sobre el Sistema Automatico de Pruebas, denominado PROBADOR, utilizado por la Gerencia de Control e Instrumentacion (GCI) del Instituto de Investigaciones Electricas para la realizacion de pruebas dinamicas en laboratorio, a los sistemas de adquisicion y control desarrollado con la linea electronica SAC-IIE que estan instalados en las Centrales Termoelectricas de Ciclo Combinado (CTCC) de Dos Bocas, Veracruz y Gomez Palacio, Durango, Mexico. Tambien se describen la arquitectura, las funciones que se llevan

Some observations about quality control tests of Spect

International Nuclear Information System (INIS)

Robilotta, C.C.; Rebelo, M.F.S.; Oliveira, M.A.

1987-01-01

Some observations about quality control tests done in the tomographic system of Heart Institute are described. Among the tests, the traditional test of quality control with scintillation camera and the specific test for tomography systems are induced. The traditional tests are essential, but not sufficient for evaluating the Spect equipment and the specific tests have been effectuated in controlled conditions. (C.G.C.) [pt

Laser-based measuring equipment controlled by microcomputer

International Nuclear Information System (INIS)

Miron, N.; Sporea, D.; Velculescu, V.G.; Petre, M.

1988-03-01

Some laser-based measuring equipment controlled by microcomputer developed for industrial and scientific purposes are described. These equipments are intended for dial indicators verification, graduated rules measurement, and for very accurate measurement of the gravitational constant. (authors)

Methodically finding solutions of equipments for carrying out experiments in materials testing and research. Pt. 2

International Nuclear Information System (INIS)

Findeisen, D.; Nachtweide, D.; Kuntze, G.

1983-01-01

In comparison with the development of industrial products the development of test equipments is of special kind, which is demonstrated by methodical proceeding for finding solutions and by potentialities for technical design and production of test equipment engineering. Some general principles are turned out and explained by several realized examples of design belonging to the sphere of materials testing in den Federal Institute of Materials Testing (BAM) representative of other problems. User are large scientific institutes independent of university, scientific institutes as members of university just as test stands and quality control offices of industrial works. (orig.) [de

LESSONS LEARNED IN TESTING OF SAFEGUARDS EQUIPMENT

International Nuclear Information System (INIS)

Pepper, S.; Farnitano, M.; Carelli, J.; Hazeltine, J.; Bailey, D.

2001-01-01

The International Atomic Energy Agency's (IAEA) Department of Safeguards uses complex instrumentation for the application of safeguards at nuclear facilities around the world. Often, this equipment is developed through cooperation with member state support programs because the Agency's requirements are unique and are not met by commercially available equipment. Before approving an instrument or system for routine inspection use, the IAEA subjects it to a series of tests designed to evaluate its reliability. In 2000, the IAEA began to observe operational failures in digital surveillance systems. In response to the observed failures, the IAEA worked with the equipment designer and manufacturer to determine the cause of failure. An action plan was developed to correct the performance issues and further test the systems to make sure that additional operational issues would not surface later. This paper addresses the steps taken to address operation issues related to digital image surveillance systems and the lessons learned during this process

Advances in impact resistance testing for explosion-proof electrical equipment

Directory of Open Access Journals (Sweden)

Pasculescu Vlad Mihai

2017-01-01

Full Text Available The design, construction and exploitation of electrical equipment intended to be used in potentially explosive atmospheres presents a series of difficulties. Therefore, the approach of these phases requires special attention concerning technical, financial and occupational health and safety aspects. In order for them not to generate an ignition source for the explosive atmosphere, such equipment have to be subjected to a series of type tests aiming to decrease the explosion risk in technological installations which operate in potentially explosive atmospheres. Explosion protection being a concern of researchers and authorities worldwide, testing and certification of explosion-proof electrical equipment, required for their conformity assessment, are extremely important, taking into account the unexpected explosion hazard due to potentially explosive atmospheres, risk which has to be minimized in order to ensure the occupational health and safety of workers, for preventing material losses and for decreasing the environmental pollution. Besides others, one of the type tests, which shall be applied, for explosion-proof electrical equipment is the impact resistance test, described in detail in EN 60079 which specifies the general requirements for construction, testing and marking of electrical equipment and Ex components intended for use in explosive atmospheres. This paper presents an analysis on the requirements of the impact resistance test for explosion-proof electrical equipment and on the possibilities to improve this type of test, by making use of modern computer simulation tools based on finite element analysis, techniques which are widely used nowadays in the industry and for research purposes.

RESUME95 Nordic field test of mobile equipment for nuclear fall-out monitoring

Energy Technology Data Exchange (ETDEWEB)

Bourgeois, C.; Bresson, J.; Chiffot, T.; Guillot, L. [Centre d`Etudes de Valduc, Direction des Applications Militaires, Commissaiat a L`Energie Atomique, Tille (France)

1997-12-31

Nordic Safety Research (NKS) organised in August 1995 a field test of various techniques and instrumentation for monitoring radioactive fall-out. In an emergency situation, after a major release of radioactive material, many different measuring systems are going to be used, ranging from small hand hold intensitometer to complex spectrometer systems. In this test the following type of equipment were tested: Airborne spectrometers; Carborne spectrometers and dose rate meters; In situ spectrometers and intensitometers. Helinuc team was equipped of an airborne system and of a germanium device for in situ measurements. Different tasks were specified for each team: Mapping caesium fall-out and natural activity over two areas of 18 and 5 km{sup 2}; Research of hidden sources. For measurements and data processing the respect of time allowed was strictly controlled for testing the ability of each team. (au).

RESUME95 Nordic field test of mobile equipment for nuclear fall-out monitoring

Energy Technology Data Exchange (ETDEWEB)

Bourgeois, C; Bresson, J; Chiffot, T; Guillot, L [Centre d` Etudes de Valduc, Direction des Applications Militaires, Commissaiat a L` Energie Atomique, Tille (France)

1998-12-31

Nordic Safety Research (NKS) organised in August 1995 a field test of various techniques and instrumentation for monitoring radioactive fall-out. In an emergency situation, after a major release of radioactive material, many different measuring systems are going to be used, ranging from small hand hold intensitometer to complex spectrometer systems. In this test the following type of equipment were tested: Airborne spectrometers; Carborne spectrometers and dose rate meters; In situ spectrometers and intensitometers. Helinuc team was equipped of an airborne system and of a germanium device for in situ measurements. Different tasks were specified for each team: Mapping caesium fall-out and natural activity over two areas of 18 and 5 km{sup 2}; Research of hidden sources. For measurements and data processing the respect of time allowed was strictly controlled for testing the ability of each team. (au).

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

Project W320 52-inch diameter equipment container load test: Test report

International Nuclear Information System (INIS)

Bellomy, J.R.

1995-01-01

This test report summarizes testing activities and documents the results of the load tests performed on-site and off-site to structural qualify the 52-inch equipment containers designed and fabricated under Project W-320

Control of equipment isolation system using wavelet-based hybrid sliding mode control

Science.gov (United States)

Huang, Shieh-Kung; Loh, Chin-Hsiung

2017-04-01

Critical non-structural equipment, including life-saving equipment in hospitals, circuit breakers, computers, high technology instrumentations, etc., is vulnerable to strong earthquakes, and on top of that, the failure of the vibration-sensitive equipment will cause severe economic loss. In order to protect vibration-sensitive equipment or machinery against strong earthquakes, various innovative control algorithms are developed to compensate the internal forces that to be applied. These new or improved control strategies, such as the control algorithms based on optimal control theory and sliding mode control (SMC), are also developed for structures engineering as a key element in smart structure technology. The optimal control theory, one of the most common methodologies in feedback control, finds control forces through achieving a certain optimal criterion by minimizing a cost function. For example, the linear-quadratic regulator (LQR) was the most popular control algorithm over the past three decades, and a number of modifications have been proposed to increase the efficiency of classical LQR algorithm. However, except to the advantage of simplicity and ease of implementation, LQR are susceptible to parameter uncertainty and modeling error due to complex nature of civil structures. Different from LQR control, a robust and easy to be implemented control algorithm, SMC has also been studied. SMC is a nonlinear control methodology that forces the structural system to slide along surfaces or boundaries; hence this control algorithm is naturally robust with respect to parametric uncertainties of a structure. Early attempts at protecting vibration-sensitive equipment were based on the use of existing control algorithms as described above. However, in recent years, researchers have tried to renew the existing control algorithms or developing a new control algorithm to adapt the complex nature of civil structures which include the control of both structures and non

Presentation of accessibility equipment for primary pipings, IHX, pumps and appertaining manipulator tests

International Nuclear Information System (INIS)

Hahn, G.; Hoeft, E.

1980-01-01

Accessibility and inservice procedure of SNR-300 components are described. Due to the high radiation level in the primary system it was necessary to develop special equipment to permit access to the testing components. The pertinent examination methods for surveying welding seams are acoustic (ultrasonic) and optical procedures (TV cameras, surface crack tests). This can be done by remote-controlled manipulators and special devices, which can transport the inspection system by rails to the testing position. Presently, relatively limited experience exists for such remote-controlled handling in nuclear power plants. Thus model experiments were carried out on a model pipe section at INTERATOM. The performed test shows that the concept planned to perform inservice by using remote-controlled manipulators can be realized successfully. (author)

Guideline to good practices for control and calibration of measuring and test equipment (M ampersand TE) at DOE nuclear facilities

International Nuclear Information System (INIS)

1993-03-01

The purpose of the Guideline to Good Practices for Control and Calibration of Measuring and Test Equipment (M ampersand TE) at DOE Nuclear Facilities is to provide contractor maintenance organizations with information that may be used for the development and implementation of a rigorously controlled maintenance program directed at controlling and calibrating M ampersand TE used for maintenance tasks at DOE nuclear facilities. This document is intended to be an example guideline for the implementation of DOE Order 4330.4A, Maintenance Management Program, Chapter II, Element 11. DOE contractors should not feel obligated to adopt all parts of this guide. Rather, they should use the information contained herein as a guide for developing an M ampersand TE program applicable to their facility

A programming system for a modular, flexible multicomputer system for the automatic control of automated test equipment

International Nuclear Information System (INIS)

Schmidt, J.

1984-11-01

The hardware used is operationally directed, consisting of largely self-functioning, micro-computing modules, combined together over a parallel systembus. For communication purposes between the modules and to synchronize their activities a multi microcomputing operating system is being developed which corresponds to the specific demands of computerized process-control (handling of real-word events under real-time conditions and operation of several parallel-running subprocesses). In order to program the user-specific test cycles a programming language has to be made available which can be coordinated with the operational range of specific test equipment in terms of commands and syntax and which can also easily be learned by operators having no specialised knowledge of data processing. With this objective in mind, a structural system is developed in this work, by the aid of which application-oriented programming languages can be implemented. The adaption of the programming system to a wide spectrum of applications in automatic testing is facilitated by its modular structure. The efficiency of the system is demonstrated by means of an industrial pilot-scale implementation. (orig./HP) [de

Progress in control equipment for fuel-handling machinery

International Nuclear Information System (INIS)

Nutting, B.A.

1986-01-01

The paper outlines the development of the equipment used to control the fuel-handling machinery associated with nuclear reactors, from the early electromechanical equipment, through solid-state switching logic to programmable controllers and microprocessors. The control techniques have developed along with the technology, and modern systems offer versatility, reliability and ease of design, operation and maintenance. Future trends and developments are discussed together with possible limiting factors. (author)

High level radioactive waste vitrification process equipment component testing

International Nuclear Information System (INIS)

Siemens, D.H.; Heath, W.O.; Larson, D.E.; Craig, S.N.; Berger, D.N.; Goles, R.W.

1985-04-01

Remote operability and maintainability of vitrification equipment were assessed under shielded-cell conditions. The equipment tested will be applied to immobilize high-level and transuranic liquid waste slurries that resulted from plutonium production for defense weapons. Equipment tested included: a turntable for handling waste canisters under the melter; a removable discharge cone in the melter overflow section; a thermocouple jumper that extends into a shielded cell; remote instrument and electrical connectors; remote, mechanical, and heat transfer aspects of the melter glass overflow section; a reamer to clean out plugged nozzles in the melter top; a closed circuit camera to view the melter interior; and a device to retrieve samples of the glass product. A test was also conducted to evaluate liquid metals for use in a liquid metal sealing system

Automatic test equipment for C and I of compact LWR

International Nuclear Information System (INIS)

Mayya, Anuradha; Marathe, P.P.; Madala, Kalyan C.

2014-01-01

The C and I of compact LWR consist of a wide variety of electronic modules. Testing of these modules manually was found to be very cumbersome. To ease the testing of these modules, Automatic Test Equipments (ATE) were developed jointly by BARC and ECIL. This paper describes the design of two ATEs for testing 69 types of modules. A power supply ATE was developed for 43 types of power supply modules of type AC-AC, AC-DC, DC-DC and signal conditioning modules. A VME ATE was developed to test 26 types of VME bus based and other microcontroller based non-bussed modules. These ATEs are used for the automated black box testing of modules by feeding power and control inputs and checking the outputs without operator intervention. This paper describes the important considerations in design and the major design challenges. (author)

The UK market for gaseous emissions control equipment

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-09-01

The report analyses the changes in demand for gaseous emissions control equipment in the United Kingdom over the next 5 years. It discusses the factors affecting demand such as legislation reporting of environmental performance, and economic factors. It looks at environmental expenditure by UK industry. Markets are examined, for VOC abatement systems; thermal incinerators; adsorption equipment; catalytic oxidisers; absorption equipment; biological treatments; cryogenic equipment; SO{sub x} abatement equipment; wet FGD; wet dry FGD, dry scrubbers; NOx abatement systems; selective catalytic reduction; and selective non-catalytic reduction. Profiles are given of 16 leading suppliers.

The digital ultrasonic test unit for automatic equipment

International Nuclear Information System (INIS)

Hiraoka, T.; Matsuyama, H.

1976-01-01

The operations and features of the ultrasonic test unit used and the digital data processing techniques employed are described. This unit is used for a few hundred multi-channel automatic ultrasonic test equipment

Design of special purpose equipment - remote control dozer

International Nuclear Information System (INIS)

Aprameyan, K.

1990-01-01

Operation environment in handling hot slag, radio active material, clearing/dismantling buildings and loose rocky zones pose hazards with the operation of heavy duty vehicles. Under such hazardous environment conditions, elimination of operator becomes the prime criteria. Remote control of heavy vehicles is resorted to operate the equipment in various working conditions. Radio control systems coupled with penumatic/hydraulic actuators and proportional control logics aim total control of the equipment from a distance using hand pendants. Bharat Earth Moovers Limited has successfully developed remote control system for dozers of 200hp and 300hp. (author). 3 figs

Maintenance cost control at the Pacific Missile Test Center.

OpenAIRE

Jenson, Richard J.

1980-01-01

Approved for public release; distribution is unlimited The Pacific Missile Test Center (PMTC) is the Navy's largest Major Range and Test Facility Base, with an investment of over one billion dollars. The majority of this investment is in range test equipment and facilities including radar, telemetry, communication and command/ control systems. Concern is growing over the "excessively obsolete condition of PMTC technical equipment." Improvement of factors concerned with...

System for routine testing of self-contained and airline breathing equipment

Energy Technology Data Exchange (ETDEWEB)

McDermott, H.J.; Hermens, G.A.

1980-07-01

A system for routine testing of self-contained and airline breathing equipment, developed by Shell Oil Co., for testing breathing equipment at one of its refineries, consists of an 80 psig air supply for airline respirators; a 500-2100 psig air supply for self-contained units; a regulator test system which uses a mannequin head that simulates human inhalation and which tests the ability of the regulator to keep the mask interior at the correct positive pressure; and an exhalation valve test system which identifies a leaky or sticking valve. The testing system has been in use for about 30 mo and has led to increased acceptance of respiratory protective equipment by workers.

Diagnostic x-ray equipment compliance and facility survey. Recommended procedures for equipment and facility testing

International Nuclear Information System (INIS)

1994-01-01

The Radiation Protection Bureau has set out guidelines for the testing of diagnostic x-ray equipment and facilities. This guide provides information for the x-ray inspector, test engineer, technologist, medical physicist and any other person responsible for verifying the regulatory compliance or safety of diagnostic x-ray equipment and facilities. Diagnostic x-radiation is an essential part of present day medical practice. The largest contributor of irradiation to the general population comes from diagnostic x-radiation. Although individual irradiations are usually small, there is a concern of possible excess cancer risk when large populations are irradiated. Unnecessary irradiations to patients from radiological procedures can be significantly reduced with little or no decrease in the value of medical diagnostic information. This can be achieved by using well designed x-ray equipment which is installed, used and maintained by trained personnel, and by the adoption of standardized procedures. In general, when patient surface dose is reduced, there is a corresponding decrease in dose to x-ray equipment operators and other health care personnel. 2 tabs., 4 figs

Diagnostic x-ray equipment compliance and facility survey. Recommended procedures for equipment and facility testing

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

The Radiation Protection Bureau has set out guidelines for the testing of diagnostic x-ray equipment and facilities. This guide provides information for the x-ray inspector, test engineer, technologist, medical physicist and any other person responsible for verifying the regulatory compliance or safety of diagnostic x-ray equipment and facilities. Diagnostic x-radiation is an essential part of present day medical practice. The largest contributor of irradiation to the general population comes from diagnostic x-radiation. Although individual irradiations are usually small, there is a concern of possible excess cancer risk when large populations are irradiated. Unnecessary irradiations to patients from radiological procedures can be significantly reduced with little or no decrease in the value of medical diagnostic information. This can be achieved by using well designed x-ray equipment which is installed, used and maintained by trained personnel, and by the adoption of standardized procedures. In general, when patient surface dose is reduced, there is a corresponding decrease in dose to x-ray equipment operators and other health care personnel. 2 tabs., 4 figs.

Reliability performance of standby equipment with periodic testing

International Nuclear Information System (INIS)

Sim, S.H.

1985-11-01

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

Experience in testing and inspection and maintenance of material handling equipments

International Nuclear Information System (INIS)

Sharma, M.L.

2009-01-01

All the Industries, Power Projects/Stations, Organizations engaged in the field of process of manufacturing, power generation, transportation, design, layout, manufacturing, and supply have to utilize material handling equipment, machinery tools tackles, lifting gears for performing their tasks/activities. The major role of the material handling equipments play an important role and a component of 40% of the total activities of the system/process to achieve targeted output with the reliability and quality is performed by material handling equipment and machineries. The material handling equipment shall have to be chosen/selected to suit the process requirement at times to be specifically designed inspected and tested to meet the specific requirement. These equipment/machineries/lifting gears have to undergo for the periodical inspection and testing to qualify for further use in a specified period. All those equipment and machinery to be used for material handling if not found satisfactory during inspection and testing or otherwise also shall be dismantled/stripped to the extent of inspection requirement of the components/sub components and maintenance repair shall have to be done to make them worthy for reuse after testing and inspection duly witnessed by competent authority

Quality Control Program for radiodiagnostic equipment on the Department of Antioquia, Colombia

International Nuclear Information System (INIS)

Beltran, Camilo; Viloria, Carolina; Puerta, Anselmo; Morales, Javier; Martinez, Piedad

2008-01-01

The Health Sectional Direction of Antioquia DSSA and the National University of Colombia campus Medellin have been formalizing inter-administrative agreements to realize Quality Control Studies on the institutions of medical radiodiagnostics of the department. In the first phase of the project on 2006, quality control studies were completed on 40 conventional and 31 mammography equipment, in the second phase by the end of 2006, 21 fluoroscopy, interventionism and C arms equipment were also studied; the third phase, finished by the end of 2007, counted with 50 conventional equipment. The tests proposed on the ARCAL XLIX IAEA protocol, tests on the installations, on the generator, on the image systems and the patient dosimetry were performed. From the evaluations on the installations, reports with relevant recommendations to be considerate and implemented to perform a better use of own resources on each institution were elaborated. On this paper, current results, impact on the participating institutions and the benefits from the applications that these kinds of practices bring to the institutions are presented. Finally, the necessity to advance towards clear politics in order to impulse the implementation of quality assurance programs in radiodiagnostic institutions, looking to improve the quality of diagnostic images with patient benefits, higher trust on technical conditions of equipment for a better and adequate diagnose, as well as to advance on processes seeking the optimization of radiological protection on the patient and the personnel occupationally exposed, is presented. (author)

Configuration control during maintenance of safety related equipment

International Nuclear Information System (INIS)

Irish, C.S.

2001-01-01

Possibly the most important aspect of performing maintenance of safety related equipment is maintaining the component's original design basis. Assuring that the repaired item will perform the same safety function within the original performance and equipment qualification parameters is commonly referred to as configuration control. Maintaining configuration control of a technologically current well documented item is easy. Unfortunately, this does not describe most safety related items requiring maintenance within the global nuclear industry. Items such as motors, transformers, metal clad switchgear (low and medium voltage circuit breakers), refrigeration compressors, and electronic components (i.e. circuit boards, power supplies, regulators, etc.) which routinely require repair have been in service for twenty plus years. As a result, finding replacement parts and or material to repair the items to the original condition is becoming more and more difficult. An added difficulty is the lack of original technical documentation available on the item which is being repaired. The lack of technical documentation makes it difficult to identify replacement material and parts when the original part or material is not available. The lack of documentation also makes it difficult to test the repaired item to make sure that the original configuration has been maintained after the repair. The presentation will discuss the details of repairing various items including motors, metal clad switchgear, refrigeration compressors and power supplies and the controls which are necessary to maintain the configuration of the original item. The discussion will include the Quality Assurance and engineering necessary to identify and evaluate replacement material and parts necessary to perform repairs on safety related equipment when the original material or part is not available. Examples of repairs which required different parts or materials than the original to be used in the repair will be

Configuration control during maintenance of safety related equipment

International Nuclear Information System (INIS)

Irish, C.S.

2003-01-01

Possibly the most important aspect of performing maintenance of safety related equipment is maintaining the component's original design basis. Assuring that the repaired item will perform the same safety function within the original performance and equipment qualification parameters is commonly referred to as configuration control. Maintaining configuration control of a technologically current well documented item is easy. Unfortunately, this does not describe most safety related items requiring maintenance within the global nuclear industry. Items such as motors, transformers, metal clad switchgear (low and medium voltage circuit breakers), refrigeration compressors, and electronic components (i.e. circuit boards, power supplies, regulators, etc.) which routinely require repair have been in service for twenty plus years. As a result, finding replacement parts and or material to repair the items to the original condition is becoming more and more difficult. An added difficulty is the lack of original technical documentation available on the item which is being repaired. The lack of technical documentation makes it difficult to identify replacement material and parts when the original part or material is not available. The lack of documentation also makes it difficult to test the repaired item to make sure that the original configuration has been maintained after the repair. The presentation will discuss the details of repairing various items including motors, metal clad switchgear, refrigeration compressors and power supplies and the controls which are necessary to maintain the configuration of the original item. The discussion will include the Quality Assurance and engineering necessary to identify and evaluate replacement material and parts necessary to perform repairs on safety related equipment when the original material or part is not available. Examples of repairs which required different parts or materials than the original to be used in the repair will be

Regulation on control systems tests

International Nuclear Information System (INIS)

Grau, J.; Navarro, J.M.

1978-01-01

Requirements under regulation applicable to the testing of control systems and controlled equipments in the case of USA nuclear projects are examined. They are reviewed, in particular, the following standards and criteria: 10 Code of Federal Regulations 50, Appendix A, General Design Criteria 20 and 21; IEEE Standards 279 and 308; IEEE Standard 338; US Regulatory Guides 1.22 and 1.118.(J.E.de C.)

Performance testing of medical US equipment using US phantom (ATS-539)

International Nuclear Information System (INIS)

Kim, Do Hyung; Kwon, Deok Moon

2014-01-01

This study is to provide accurate information as medical imaging equipment to check for the presence of body disease US equipment. We investigated the status of medical US equipment performance in Daegu and criteria US phantom (ATS-539) for US equipment performance measurements. The results in this study, 1. US phantom measurement results: The test passed rate were 88.6% and the failed rate were 11.4%. 2. The difference between the group of mean and the pass/failed groups were statistically significant. Focal zone and 4 mm functional resolution in the two items that are not present the passing standard. 3. The difference was statistically significant number of years and used equipment and pass the failed equipment (4.13 vs 7.25 years). We investigated the performance status of US equipment used in the clinical area in Daegu. The basis for the two items are not present this proposed passing standard. Equipment performance was associated with the number of years of using US equipment. It is necessary to maintain the best performance of the equipment phantom measurements for performance testing of US equipment

Performance testing of medical US equipment using US phantom (ATS-539)

Energy Technology Data Exchange (ETDEWEB)

Kim, Do Hyung [Daegu Branch, Korea Association of Health Promotion, Daegu (Korea, Republic of); Kwon, Deok Moon [Dept. of Radiology, Daegu Health College, Daegu (Korea, Republic of)

2014-12-15

This study is to provide accurate information as medical imaging equipment to check for the presence of body disease US equipment. We investigated the status of medical US equipment performance in Daegu and criteria US phantom (ATS-539) for US equipment performance measurements. The results in this study, 1. US phantom measurement results: The test passed rate were 88.6% and the failed rate were 11.4%. 2. The difference between the group of mean and the pass/failed groups were statistically significant. Focal zone and 4 mm functional resolution in the two items that are not present the passing standard. 3. The difference was statistically significant number of years and used equipment and pass the failed equipment (4.13 vs 7.25 years). We investigated the performance status of US equipment used in the clinical area in Daegu. The basis for the two items are not present this proposed passing standard. Equipment performance was associated with the number of years of using US equipment. It is necessary to maintain the best performance of the equipment phantom measurements for performance testing of US equipment.

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 Test Procedure for Determining Models of LV Equipment

NARCIS (Netherlands)

Cuk, Vladimir; Cobben, Joseph F.G.; Kling, Wil L.; Timens, R.B.; Leferink, Frank Bernardus Johannes

2009-01-01

An automated test technique for determining parameters of low voltage equipment is presented in the paper. The aim of this research is to obtain simple models of household, office and industrial equipment which could be used to predict power quality problems during the design of low voltage

Equipment qualification testing methodology research at Sandia Laboratories

International Nuclear Information System (INIS)

Jeppesen, D.

1983-01-01

The Equipment Qualification Research Testing (EQRT) program is an evolutionary outgrowth of the Qualification Testing Evaluation (QTE) program at Sandia. The primary emphasis of the program has been qualification methodology research. The EQRT program offers to the industry a research-oriented perspective on qualification-related component performance, as well as refinements to component testing standards which are based upon actual component testing research

Nuclear electronic equipment for control and monitoring boards. Susceptibility of nuclear electronic pulse equipment to interference

International Nuclear Information System (INIS)

Buisson, Jacques; Cochinal, R.; Duquesnoy, J.; Roquefort, H.

1972-07-01

The correct functioning of pulse measurement units in industrial environmental conditions where interference is high, frequently gives rise to many installation problems which are difficult to solve. This paper offers some recommendations with a view to minimising the effect to electric interference on electronic equipment and gives a test method which enables this effect to be assessed qualitatively. It has been devised for nuclear electronic instrumentation but it may also be applied to other equipment and in particular the test method may be used for other cases. After a few preliminaries on how interference acts and on the terminology, the design of the equipment and the recommended connections are mentioned. Test methods are then indicated, followed by various technical comments. (author) [fr

Survey on quality control measurements for nuclear medicine imaging equipment in Finland in 2006

International Nuclear Information System (INIS)

Korpela, Helinae; Niemelae, Jarkko

2008-01-01

Routine quality control (QC) is an essential requirement in nuclear medicine (NM) in order to ensure optimal functioning of equipment. To harmonise the routine QC of NM imaging equipment in Finnish hospital s (planar gamma cameras, SPECT, coincidence gamma cameras, PET), the Radiation and Nuclear Safety Authority (STUK) will publish guidelines on QC in collaboration with several hospital physicists. Recommendations will be provided on routine QC measurements and on the frequency of testing. It is also planned to provide recommendations for the acceptance criteria when assessing different performance parameters for NM imaging equipment. In order to determine what performance parameters of NM equipment are currently measured in hospitals, how frequently they are measured and what acceptance criteria are used, a survey was carried out on the QC of NM equipment in Finland during 2006. (author)

Method and equipment for treating waste water resulting from the technological testing processes of NPP equipment

International Nuclear Information System (INIS)

Radulescu, M. C.; Valeca, S.; Iorga, C.

2016-01-01

Modern methods and technologies coupled together with advanced equipment for treating residual substances resulted from technological processes are mandatory measures for all industrial facilities. The correct management of the used working agents and of the all wastes resulted from the different technological process (preparation, use, collection, neutralization, discharge) is intended to reduce up to removal of their potential negative impact on the environment. The high pressure and temperature testing stands from INR intended for functional testing of nuclear components (fuel bundles, fuelling machines, etc.) were included in these measures since the use of oils, demineralized water chemically treated, greases, etc. This paper is focused on the method and equipment used at INR Pitesti in the chemical treatment of demineralized waters, as well as the equipment for collecting, neutralizing and discharging them after use. (authors)

Point-of-Care Test Equipment for Flexible Laboratory Automation.

Science.gov (United States)

You, Won Suk; Park, Jae Jun; Jin, Sung Moon; Ryew, Sung Moo; Choi, Hyouk Ryeol

2014-08-01

Blood tests are some of the core clinical laboratory tests for diagnosing patients. In hospitals, an automated process called total laboratory automation, which relies on a set of sophisticated equipment, is normally adopted for blood tests. Noting that the total laboratory automation system typically requires a large footprint and significant amount of power, slim and easy-to-move blood test equipment is necessary for specific demands such as emergency departments or small-size local clinics. In this article, we present a point-of-care test system that can provide flexibility and portability with low cost. First, the system components, including a reagent tray, dispensing module, microfluidic disk rotor, and photometry scanner, and their functions are explained. Then, a scheduler algorithm to provide a point-of-care test platform with an efficient test schedule to reduce test time is introduced. Finally, the results of diagnostic tests are presented to evaluate the system. © 2014 Society for Laboratory Automation and Screening.

Charge-Control Unit for Testing Lithium-Ion Cells

Science.gov (United States)

Reid, Concha M.; Mazo, Michelle A.; Button, Robert M.

2008-01-01

A charge-control unit was developed as part of a program to validate Li-ion cells packaged together in batteries for aerospace use. The lithium-ion cell charge-control unit will be useful to anyone who performs testing of battery cells for aerospace and non-aerospace uses and to anyone who manufacturers battery test equipment. This technology reduces the quantity of costly power supplies and independent channels that are needed for test programs in which multiple cells are tested. Battery test equipment manufacturers can integrate the technology into their battery test equipment as a method to manage charging of multiple cells in series. The unit manages a complex scheme that is required for charging Li-ion cells electrically connected in series. The unit makes it possible to evaluate cells together as a pack using a single primary test channel, while also making it possible to charge each cell individually. Hence, inherent cell-to-cell variations in a series string of cells can be addressed, and yet the cost of testing is reduced substantially below the cost of testing each cell as a separate entity. The unit consists of electronic circuits and thermal-management devices housed in a common package. It also includes isolated annunciators to signal when the cells are being actively bypassed. These annunciators can be used by external charge managers or can be connected in series to signal that all cells have reached maximum charge. The charge-control circuitry for each cell amounts to regulator circuitry and is powered by that cell, eliminating the need for an external power source or controller. A 110-VAC source of electricity is required to power the thermal-management portion of the unit. A small direct-current source can be used to supply power for an annunciator signal, if desired.

Design, manufacture and installation of measuring and control equipments for the advanced thermal prototype reactor 'Fugen'

International Nuclear Information System (INIS)

Hirota, Shigeo; Kawabata, Yoshinori

1979-01-01

The advanced thermal prototype reactor ''Fugen'' attained the criticality on March 20, 1978, and 100% output operation on November 13, 1978. On March 20, 1979, it passed the final inspection, and since then, it has continued the smooth operation up to now. The measuring and control equipments are provided for grasping the operational conditions of the plant and operating it safely and efficiently. At the time of designing, manufacturing and installing the measuring and control equipments for Fugen, it was required to clarify the requirements of the plant design, to secure the sufficient functions, and to improve the operational process, maintainability and the reliability and accuracy of the equipments. Many design guidelines and criteria were decided in order to coordinate the conditions among five manufacturers and give the unified state as one plant. The outline of the instrumentations for neutrons, radiation monitoring and process data, the control systems for reactivity, reactor output, pressure and water supply, the safety protection system, and the process computer are described. Finally, the installations and tests of the measuring and control equipments are explained. The aseismatic capability of the equipments was confirmed. (Kako, I.)

Analysis of quality control protocol implementation of equipment in radiotherapy services

International Nuclear Information System (INIS)

Calcina, Carmen S. Guzman; Lima, Luciana P. de; Rubo, Rodrigo A.; Ferraz, Eduardo; Almeida, Adelaide de

2000-01-01

Considering the importance of the Quality Assurance in the radiotherapy services, there was an interest to make tests' evaluation for a Quality Control for the cobalt equipment, linear accelerator and simulator as a classification and comparison. The work proposed is a suggestion that can serve as tool for medical physicists that are starting to work in the radiotherapy area and for the most experts. The discussions were made by the gathering of local tests and official protocols, resulting in a minimum protocol as a suggestion for a routine work, emphasizing the periodicity and level of tolerance of each one of the tests. (author)

Tank Monitoring and Control System (TMACS) Acceptance Test Procedure

International Nuclear Information System (INIS)

WANDLING, R.R.

1999-01-01

The purpose of this document is to describe tests performed to validate Revision 11.2 of the TMACS Monitor and Control System (TMCACS) and verify that the software functions as intended by design. The tests will be performed on the development system. The software to be tested is the TMACS knowledge bases (KB) and the I/O driver/services. The development system will not be talking to field equipment; instead, the field equipment is simulated using emulators or multiplexers in the lab

Tank Monitoring and Control System (TMACS) Acceptance Test Procedure

Energy Technology Data Exchange (ETDEWEB)

BARNES, D.A.

2000-06-01

The purpose of this document is to describe tests performed to validate Revision 12.0 of the TMACS Monitor and Control System (TMACS) and verify that the software functions as intended by design. This document is intended to test the software portion of TMACS. The tests will be performed on the development system. The software to be tested is the TMACS knowledge bases (KB) and the I/O driver/services. The development system will not be communicating to field equipment; instead, the field equipment is simulated using emulators or multiplexers in the lab.

Tank Monitoring and Control System (TMACS) Acceptance Test Procedure

International Nuclear Information System (INIS)

BARNES, D.A.

2000-01-01

The purpose of this document is to describe tests performed to validate Revision 12.0 of the TMACS Monitor and Control System (TMACS) and verify that the software functions as intended by design. This document is intended to test the software portion of TMACS. The tests will be performed on the development system. The software to be tested is the TMACS knowledge bases (KB) and the I/O driver/services. The development system will not be communicating to field equipment; instead, the field equipment is simulated using emulators or multiplexers in the lab

Performance test of ex-core high temperature and high pressure water loop test equipment (Contract research)

International Nuclear Information System (INIS)

Nakano, Hiroko; Uehara, Toshiaki; Takeuchi, Tomoaki; Shibata, Hiroshi; Nakamura, Jinichi; Matsui, Yoshinori; Tsuchiya, Kunihiko

2016-03-01

In Japan Atomic Energy Agency, we started research and development so as to monitor the situations in the Nuclear Plant Facilities during a severe accident, such as a radiation-resistant monitoring camera, a radiation-resistant transmission system for conveying the in-core information, and a heat-resistant signal cable. As a part of developments of the heat-resistant signal cable, we prepared ex-core high-temperature and high-pressure water loop test equipment, which can simulate the conditions of BWRs and PWRs, for evaluating reliability and properties of sheath materials of the cable. This equipment consists of autoclave, water conditioning tank, high-pressure metering pump, preheater, heat exchanger and water purification equipment, etc. This report describes the basic design and the performance test results of ex-core high-temperature and high-pressure water loop test equipment. (author)

Retrofit of waste-to-energy facilities equipped with electrostatic precipitators. Volume III: Test protocol

Energy Technology Data Exchange (ETDEWEB)

Rigo, H.G. [Rigo & Rigo Associates, Inc., Berea, OH (US); Chandler, A.J. [A.J. Chandler & Associates, Inc., Toronto, Ontario (Canada)

1996-04-01

The American Society of Mechanical Engineers' [ASME] Center for Research and Technology Development [CRTD] has been awarded a subcontract by the National Renewable Energy Laboratory [NREL] to demonstrate the technical performance and viability of flue gas temperature control in combination with dry acid gas reagent and activated carbon injection at an existing electrostatic precipitator [ESP] equipped municipal waste combustor [MWC]. The objective of this proof-of-concept demonstration test is to economically and reliably meet 40 CFR 60 Subpart Cb Emissions Guidelines for MWC's at existing ESP equipped facilities. The effort is being directed by a Subcommittee of tile ASME Research Committee on Industrial and Municipal Wastes [RCIMW] chaired by Dave Hoecke. Mr. Greg Barthold of ASME/CRTD is the Project Manager. ASME/CRTD contracted with Rigo & Rigo Associates, Inc. in cooperation with A.J. Chandler & Associates, Ltd. to be the Principal Investigator for the project and manage the day-t o-day aspects of the program, conduct the testing reduce and interpret the data and prepare the report. Testing will be conducted at the 2 by 210 TPD, ESP equipped MWC at the Davis County Resource Recovery Facility in Layton, Utah. The test plan calls for duplicate metals (Cd, Pb and Hg), dioxin and acid gas runs.

Testing of the West Valley Vitrification Facility transfer cart control system

International Nuclear Information System (INIS)

Halliwell, J.W.; Bradley, E.C.

1995-01-01

Oak Ridge National Laboratory (ORNL) has designed and tested the control system for the West Valley Demonstration Project Vitrification Facility transfer cart. The transfer cart will transfer canisters of vitrified high-level waste remotely within the Vitrification Facility. The control system operates the cart under battery power by wireless control. The equipment includes cart-mounted control electronics, battery charger, control pendants, engineer's console, and facility antennas. Testing was performed in several phases of development: (1) prototype equipment was built and tested during design, (2) board-level testing was then performed at ORNL during fabrication, and (3) system-level testing was then performed by ORNL at the fabrication subcontractor's facility for the completed cart system. These tests verified (1) the performance of the cart relative to design requirements and (2) operation of various built-in cart features. The final phase of testing is planned to be conducted during installation at the West Valley Vitrification Facility

Results of evaluation of quality control measurement instrument of x-ray diagnostic equipment by non-invasive method

International Nuclear Information System (INIS)

Laan, Flavio T. van der; Elbern, Alvin W.

1996-01-01

This work shows the results of the tests realized on Santa Rita Hospital (Porto Alegre), using a non invasive quality control measurement instrument, developed in this University for fast measurement of essential parameters of X-rays diagnostic equipment. In the tests we used a diagnostics Siemens X ray, model Heliofos 4E as our standard equipment. The linearity test of sensor probe and the exposure rate calibration was performed, with a Palmer Dosimeter. For the kVp and exposure time we used a RTI commercial instrument. (author)

Follow-up of the evolution of the characteristics and performance of the equipments tested during a KALI campaign

International Nuclear Information System (INIS)

Rouaud, J.

1985-01-01

One of the four parts of the K1 qualification of the 1E equipments concerns the design basis accidents. The KALI loops allows to create the thermodynamic conditions of these accidents. This paper presents the PROCESS II which concerns the installation of the equipment in conditions representative of those met in nuclear power plants, the control assurance before, during and after the thermodynamic test. A list of qualification tests carried out on the KALI loop is finally given [fr

Evolution of seismic shock test qualification of equipment

International Nuclear Information System (INIS)

Berriaud, C.

1979-01-01

From the first nuclear power plants a new industrial problem is appeared: the seismic test qualification of equipment. Nothing was existing in this range. Methods and test experiments were to be studied and perfected in order to obtain safe results. This paper presents the evolution of this question up to now [fr

Novel Field Test Equipment for Lithium-Ion Batteries in Hybrid Electrical Vehicle Applications

Directory of Open Access Journals (Sweden)

Goran Lindbergh

2011-04-01

Full Text Available Lifetime testing of batteries for hybrid-electrical vehicles (HEV is usually performed in the lab, either at the cell, module or battery pack level. Complementary field tests of battery packs in vehicles are also often performed. There are, however, difficulties related to field testing of battery-packs. Some examples are cost issues and the complexity of continuously collecting battery performance data, such as capacity fade and impedance increase. In this paper, a novel field test equipment designed primarily for lithium-ion battery cell testing is presented. This equipment is intended to be used on conventional vehicles, not hybrid vehicles, as a cheaper and faster field testing method for batteries, compared to full scale HEV testing. The equipment emulates an HEV environment for the tested battery cell by using real time vehicle sensor information and the existing starter battery as load and source. In addition to the emulated battery cycling, periodical capacity and pulse testing capability are implemented as well. This paper begins with presenting some background information about hybrid electrical vehicles and describing the limitations with today’s HEV battery testing. Furthermore, the functionality of the test equipment is described in detail and, finally, results from verification of the equipment are presented and discussed.

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

CERN Document Server

AIChE

2013-01-01

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

Framed bit error rate testing for 100G ethernet equipment

DEFF Research Database (Denmark)

Rasmussen, Anders; Ruepp, Sarah Renée; Berger, Michael Stübert

2010-01-01

rate. As the need for 100 Gigabit Ethernet equipment rises, so does the need for equipment, which can properly test these systems during development, deployment and use. This paper presents early results from a work-in-progress academia-industry collaboration project and elaborates on the challenges...

The introduction of compulsory compliance testing of medical diagnostic x-ray equipment in Western Australia

International Nuclear Information System (INIS)

Rafferty, M. W.; Jacob, C. S.

1995-01-01

Performance testing of medical diagnostic X-ray equipment can reveal equipment faults which, while not always clinically detectable, may contribute to reduced image quality and unnecessary radiation exposure of both patients and staff. Routine testing of such equipment is highly desirable to identify such faults and allows them to be rectified. The Radiological council of Western Australia is moving towards requiring compulsory compliance testing of all (new and existing) medical diagnostic X-ray equipment that all new mobile radiographic and new mammographic X-ray equipment be issued with a compliance test certificate as a prerequisite for registration. Workbooks which provide details of the tests required and recommended test methods have been prepared for medical radiographic (mobile and fixed), fluoroscopic and mammographic X-ray equipment. It is intended that future workbooks include details of the tests and methods for dental and computed tomography X-ray units. The workbooks are not limited to the compliance testing of items as specified in the Regulations, but include tests for other items such as film processing, darkrooms and image quality (for fluoroscopic equipment). Many of the workbook tests could be used within a regular quality assurance program for diagnostic X-ray equipment. Persons who conduct such compliance tests will need to be licensed and have all test certificates endorsed by a qualified expert. Suitable training and assessment of compliance testers will be required. Notification of such tests (including non-compliant items and corrective actions taken) will be required by the Radiological Council as a condition of equipment registration. 9 refs

SpaceWire: IP, Components, Development Support and Test Equipment

Science.gov (United States)

Parkes, S.; McClements, C.; Mills, S.; Martin, I.

SpaceWire is a communications network for use onboard spacecraft. It is designed to connect high data-rate sensors, large solid-state memories, processing units and the downlink telemetry subsystem providing an integrated data-handling network. SpaceWire links are serial, high-speed (2 Mbits/sec to 400 Mbits/sec), bi-directional, full-duplex, pointto- point data links which connect together SpaceWire equipment. Application information is sent along a SpaceWire link in discrete packets. Control and time information can also be sent along SpaceWire links. SpaceWire is defined in the ECSS-E50-12A standard [1]. With the adoption of SpaceWire on many space missions the ready availability of intellectual property (IP) cores, components, software drivers, development support, and test equipment becomes a major issue for those developing satellites and their electronic subsystems. This paper describes the work being done at the University of Dundee and STAR-Dundee Ltd with ESA, BNSC and internal funding to make these essential items available. STAR-Dundee is a spin-out company of the University of Dundee set up specifically to support users of SpaceWire.

Test and Analysis of Metallurgical Converter Equipment

Directory of Open Access Journals (Sweden)

Shan Pang

2013-05-01

Full Text Available Oxygen top-blow converter is the main equipment in steel making, and its work reliability decides the security and economy of steel production. Therefore, how to design and test analysis of convertor has been an important subject of industry research. Geometric modelling and structure analysis of converter tilting device by using Pro/E program .The design Principle, basic design structure were analyzed in detail. The computer simulation software of metallurgical converter equipment and how to use it were introduced .It developed by VC++ software. The position of barycentre and moment curve in No.3 and No.4 are calculated. The converter acceleration down dip can be resolved by comparing the moment curve and center curve.

Development of the testing procedure for units and elements of mining equipment

Directory of Open Access Journals (Sweden)

P. B. Gerike

2017-09-01

Full Text Available The author considers in detail the stages of creating a testing procedure for mining equipment based on the complex implementation of principles of nondestructive testing and technical diagnostics. The author substantiates effectiveness of application of a complex diagnostic approach for assessing the state of metal structures and energy-mechanical equipment of mining machines. The opportunity for timely detection of defects, regardless of their type and degree of danger, presents itself only with a wide application of the modern methods of vibration diagnostics and nondestructive testing. The author substantiates the effectiveness of specific combination of methods of nondestructive testing, most optimally suited for solving given tasks. The article contains the developed complex of more than 120 diagnostic rules, suitable for performing automated analysis of vibroacoustic signal and revealing the main damages of energy-mechanical equipment based on selective groups of informative frequencies. The author formulates the main criteria that one can use as a basic platform for improving the methodology for normalizing the parameters of mechanical oscillations. The developed diagnostic criteria became a basis for the development of individual spectral masks suitable for performing the analysis of parameters of vibroacoustic waves generated during operation of mining equipment. The author proves necessity of transition of repair and maintenance divisions of industrial enterprises to the system of maintenance of machinery according to its actual technical state, and the developed complex of diagnostic rules for detecting defects can serve as a platform for the implementation of basic elements of this system. The author substantiates the principal validity of the developed methodology for testing mining machines equipment and its individual elements, such as the predictive modeling of degradation of technical state of mining equipment and the

TANK 18 AND 19-F TIER 1A EQUIPMENT FILL MOCK UP TEST SUMMARY

Energy Technology Data Exchange (ETDEWEB)

Stefanko, D.; Langton, C.

2011-11-04

The United States Department of Energy (US DOE) has determined that Tanks 18-F and 19-F have met the F-Tank Farm (FTF) General Closure Plan Requirements and are ready to be permanently closed. The high-level waste (HLW) tanks have been isolated from FTF facilities. To complete operational closure they will be filled with grout for the purpose of: (1) physically stabilizing the tanks, (2) limiting/eliminating vertical pathways to residual waste, (3) discouraging future intrusion, and (4) providing an alkaline, chemical reducing environment within the closure boundary to control speciation and solubility of select radionuclides. Bulk waste removal and heel removal equipment remain in Tanks 18-F and 19-F. This equipment includes the Advance Design Mixer Pump (ADMP), transfer pumps, transfer jets, standard slurry mixer pumps, equipment-support masts, sampling masts, dip tube assemblies and robotic crawlers. The present Tank 18 and 19-F closure strategy is to grout the equipment in place and eliminate vertical pathways by filling voids in the equipment to vertical fast pathways and water infiltration. The mock-up tests described in this report were intended to address placement issues identified for grouting the equipment that will be left in Tank 18-F and Tank 19-F. The Tank 18-F and 19-F closure strategy document states that one of the Performance Assessment (PA) requirements for a closed tank is that equipment remaining in the tank be filled to the extent practical and that vertical flow paths 1 inch and larger be grouted. The specific objectives of the Tier 1A equipment grout mock-up testing include: (1) Identifying the most limiting equipment configurations with respect to internal void space filling; (2) Specifying and constructing initial test geometries and forms that represent scaled boundary conditions; (3) Identifying a target grout rheology for evaluation in the scaled mock-up configurations; (4) Scaling-up production of a grout mix with the target rheology

Reliability and maintainability data acquisition in equipment development tests

International Nuclear Information System (INIS)

Haire, M.J.; Gift, E.H.

1983-10-01

The need for collection of reliability, maintainability, and availability data adds a new dimension to the data acquisition requirements of equipment development tests. This report describes the reliability and maintainability data that are considered necessary to ensure that sufficient and high quality data exist for a comprehensive, quantitative evaluation of equipment and system availability. These necessary data are presented as a set of data collection forms. Three data acquisition forms are discussed: an inventory and technical data form, which is filed by the design engineer when the design is finished or the equipment is received; an event report form, which is completed by the senior test operator at each shutdown; and a maintainability report, which is a collaborative effort between senior operators and lead engineers and is completed on restart. In addition, elements of a reliability, maintainability evaluation program are described. Emphasis is placed on the role of data, its storage, and use in such a program

Backup control airstart performance on a digital electronic engine control-equipped F100-engine

Science.gov (United States)

Johnson, J. B.

1984-01-01

The air start capability of a backup control (BUC) was tested for a digital electronic engine control (DEEC) equipped F100 engine, which was installed in an F-15 aircraft. Two air start schedules were tested. Using the group 1 start schedule, based on a 40 sec timer, an air speed of 300 knots was required to ensure successful 40 and 25% BUC mode spooldown airstarts. If core rotor speed (N2) was less than 40% a stall would occur when the start bleed closed, 40 sec after initiation of the air start. All jet fuel starter (JFS) assisted air starts were successful with the group 1 start schedule. For the group 2 schedule, the time between pressurization and start bleed closure ranged between 50 sec and 72 sec. Idle rps was lower than the desired 65% for air starts at higher altitudes and lower air speeds.

Application of a path sensitizing method on automated generation of test specifications for control software

International Nuclear Information System (INIS)

Morimoto, Yuuichi; Fukuda, Mitsuko

1995-01-01

An automated generation method for test specifications has been developed for sequential control software in plant control equipment. Sequential control software can be represented as sequential circuits. The control software implemented in a control equipment is designed from these circuit diagrams. In logic tests of VLSI's, path sensitizing methods are widely used to generate test specifications. But the method generates test specifications at a single time only, and can not be directly applied to sequential control software. The basic idea of the proposed method is as follows. Specifications of each logic operator in the diagrams are defined in the software design process. Therefore, test specifications of each operator in the control software can be determined from these specifications, and validity of software can be judged by inspecting all of the operators in the logic circuit diagrams. Candidates for sensitized paths, on which test data for each operator propagates, can be generated by the path sensitizing method. To confirm feasibility of the method, it was experimentally applied to control software in digital control equipment. The program could generate test specifications exactly, and feasibility of the method was confirmed. (orig.) (3 refs., 7 figs.)

Survey of Equipment Quality Control in Radiotherapy Centers in Croatia: First Results

International Nuclear Information System (INIS)

Jurkovic, S.; Diklic, A.; Smilovic Radojcic, Dj.; Svabic, M.; Kasabasic, M.; Ivkovic, A.; Faj, D.

2011-01-01

accelerators and six simulators. Conventional simulators are also important part of radiotherapy equipment. For the purpose of this work we collected and statistically analyzed a large number of data obtained through measurements that were done on six simulators, some of them testing mechanical and some radiation accuracy. Regarding mechanical accuracy of the machines, results showed that crosshair intersection stability with collimator rotation was most frequently out of tolerance. Tests of radiation accuracy showed that rotation of treatment couch and gantry was troublesome. Over 20 % of the values obtained with these tests were over 2 mm. Also, machines equipped with a multileaf collimator have 25 % out-of-tolerance values for width of stripes in MLC grid test. Results are also divided in two categories within tolerance values having in mind that values between 1 - 2 mm are already a caution level. The light/radiation coincidence in symmetric and especially asymmetric fields is an important test due to frequent use of half-fields in radiotherapy. Overlapping or distinction in asymmetric fields can result in non-precise dose delivery therefore causing damage of organs at risk or low tumor control. 46.2 % of out-of-tolerance values on central axis for asymmetric fields seem to be quite significant. The values for symmetric fields are mostly in tolerance. Flatness and symmetry were checked using PTW QuickCheck Webline system for both photons (on two different depths) and electrons. Since the accuracy of this system is lower then checking radiation parameters in water phantom, tolerance values are increased a bit. Results showed great stability in symmetry value but also some out-of-tolerance values for flatness, especially for measurements for photons on larger depth. Some linear accelerators in Croatia (five of nine) are equipped with the system for portal imaging. Unfortunately, only two of them were suitable for measurements at the time of our collection of data. Tested

Establishment of nuclear equipment qualification system

International Nuclear Information System (INIS)

Joo, Po Kook; Lim, Nam Jin; Lee, Young Gun

2003-04-01

This study is carried out by KEARI(Korea Atomic Energy Research Institute) as the lead organization in cooperation with KIMM(Korea Institute of Machinery and Materials), KTL(Korea Testing Laboratory) and KRISS(Korea Research Institute of Standards and Science) to construct a basis of efficient management of nuclear equipment qualification business by expanding test equipment of each of participating organization, and developing qualification technologies. As for KIMM, control system of large scale shaker was replaced with advanced system, and LOCA(Loss of Coolant Accident) test facility was installed. KTL is now capable of conducting seismic tests of nuclear I and C as a result of installation of seismic test equipment during the first two project years. KRISS participated in the Project with a view to have large scale EMI test equipment and related technologies. In parallel with expansion of test equipment, a industrial-educational-research cooperation committee, as an intermediate step toward integrated equipment qualification system to maximize the usage of test equipment, was established and cooperation methods were investigated. As a result, Korea Nuclear Equipment Qualification Association, an corporate juridical person, was established. Research on development of thermal and radiation aging test technology of nuclear materials was carried out by Hanyang University and SECO(Saehan Engineering and Qualification Co., Ltd.). Integrated Equipment Qualification Database was developed which contains material test data, equipment qualification data and other EQ related informations. Standard qualification procedures were developed in order for test laboratories and manufacturers to establish design requirements and to efficiently perform tests

Ballooning test equipment for use in hot cells

International Nuclear Information System (INIS)

Broendsted, P.; Adrian, F.

1979-12-01

An equipment for testing the LOCA behaviour of irradiated cladding materials is described. The details of the construction and of the installation in the Hot Cells are reported. Pilot tests carried out showed that the performance of the system fulfills the basic experimental prerequisites, which were: heating rate of 2-3degC/s, final temperature 1150degC/s, internal pressure max. 30 atm, external pressure max. 1 atm, test atmosphere either air or steam. (author)

The development of synthetic test procedure for hot cell equipment systems in IMEF

International Nuclear Information System (INIS)

Ahn, Sang Bok; Lee, Key Soon; Park, Dae Kyu; Hong, Kwon Pyo; Choo, Yong Sun

1998-04-01

Hot cell facility should be confirmed to operation safety through pre-commissioning test after construction. In this report, the detailed procedure of hot cell equipment are described. The contents are as follows: 1. Entrance equipment of hot cell 2. Specimen transportation equipment between hot cells 3. Waste discharge equipment in hot cell 4. Specimen loading equipment to hot cell 5. Interlinking equipment in hot cell. (author). 4 tabs

Development of ultrasonic testing equipment incorporating electromagnetic acoustic transducer

International Nuclear Information System (INIS)

Sato, Michio; Kimura, Motohiko; Okano, Hideharu; Miyazawa, Tatsuo; Nagase, Koichi; Ishikawa, Masaaki

1989-01-01

An ultrasonic testing equipment for use in in-service inspection of nuclear power plant piping has been developed, which comprises an angle-beam electromagnetic acoustic transducer mounted on a vehicle for scanning the piping surface to be inspected. The transducer functions without direct contact with the piping surface through couplant, and the vehicle does not require a guide track installed on the piping surface, being equipped with magnetic wheels that adhere to the piping material, permitting it to travel along the circumferential weld joint of a carbon steel pipe. The equipment thus dispenses with the laborious manual work involved in preparing the piping for inspection, such as removal of protective coating, surface polishing and installation of guide track and thereby considerably reduces the duration of inspection. The functioning principle and structural features of the transducer and vehicle are described, together with the results of trial operation of a prototype unit, which proved a 1mm deep notch cut on a test piece of 25mm thick carbon steel plate to be locatable with an accuracy of ±2mm. (author)

Development of manufacturing equipment and QC equipment for DUPIC fuel

International Nuclear Information System (INIS)

Yang, Myung Seung; Park, J.J.; Lee, J.W.; Kim, S.S.; Yim, S.P.; Kim, J.H.; Kim, K.H.; Na, S.H.; Kim, W.K.; Shin, J.M.; Lee, D.Y.; Cho, K.H.; Lee, Y.S.; Sohn, J.S.; Kim, M.J.

1999-05-01

In this study, DUPIC powder and pellet fabrication equipment, welding system, QC equipment, and fission gas treatment are developed to fabricate DUPIC fuel at IMEF M6 hot cell. The systems are improved to be suitable for remote operation and maintenance with the manipulator at hot cell. Powder and pellet fabrication equipment have been recently developed. The systems are under performance test to check remote operation and maintenance. Welding chamber and jigs are designed and developed to remotely weld DUPIC fuel rod with manipulators at hot cell. Remote quality control equipment are being tested for analysis and inspection of DUPIC fuel characteristics at hot cell. And trapping characteristics is analyzed for cesium and ruthenium released under oxidation/reduction and sintering processes. The design criteria and process flow diagram of fission gas treatment system are prepared incorporating the experimental results. The fission gas treatment system has been successfully manufactured. (Author). 33 refs., 14 tabs., 91 figs

Nuclear material control and accountancy planning and performance testing

International Nuclear Information System (INIS)

Mike Enhinger; Dennis Wilkey; Rod Martin; Ken Byers; Brian Smith

1999-01-01

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

Acceptance test procedure for K basins dose reduction project clean and coat equipment

International Nuclear Information System (INIS)

Creed, R.F.

1996-01-01

This document is the Acceptance Test Procedure (ATP) for the clean and coat equipment designed by Oceaneering Hanford, Inc. under purchase order MDK-XVC-406988 for use in the 105 K East Basin. The ATP provides the guidelines and criteria to test the equipment's ability to clean and coat the concrete perimeter, divider walls, and dummy elevator pit above the existing water level. This equipment was designed and built in support of the Spent Nuclear Fuel, Dose Reduction Project. The ATP will be performed at the 305 test facility in the 300 Area at Hanford. The test results will be documented in WHC-SD-SNF-ATR-020

Development of an automatic test equipment for nano gauging displacement transducers

Energy Technology Data Exchange (ETDEWEB)

Wang, Y-C [National Yunlin University of Science and Technology, Taiwan (China); Jywe, W-Y [National Formosa University, Taiwan (China); Liu, C-H [National Formosa University, Taiwan (China)

2005-01-01

In order to satisfy the increasing demands on the precision in manufacturing technology, nanaometrology gradually becomes more important in manufacturing process. To ensure the precision of manufacture, precise measuring instruments and sensors play a decisive role for the accurate characterization and inspection of products. For linear length inspection, high precision gauging displacement transducers, i.e. nano gauging displacement transducers (NGDT), have been often utilized, which have been often utilized, which have the resolution in the nanometer range and can achieve an accuracy of less than 100 nm. Such measurement instruments include transducers based on electronic as well as optical measurement principles, e.g. inductive, incremental-optical or interference optical. To guarantee the accuracy and the traceability to the definition of the meter, calibration and test of NGDT are essential. Currently, there are some methods and machines for test of NGDT, but they suffer from various disadvantages. Some of them permit only manual test procedures which are time-consuming, e.g. with high accurate gauge blocks as material measures. Other tests can reach higher accuracy only in the micrometer range or result in uncertainties of more than 100 nm in the large measuring ranges. To realize the test of NGDT with a high resolution as well as a large measuring range, an automatic test equipment was constructed, that has a resolution of 1.24 nm, a measuring range of up to 20 nm (60 mm) and a measuring uncertainty of approximate {+-}10 nm can fulfil the requirements of high resolution within the nanometer range while simultaneously covering a large measuring range in the order of millimeters. The test system includes a stable frame, a polarization interferometer, an angle sensor, an angular control, a drive system and piezo translators. During the test procedure, the angular control and piezo translators minimize the Abbe error. For the automation of the test procedure a

Development of an automatic test equipment for nano gauging displacement transducers

International Nuclear Information System (INIS)

Wang, Y-C; Jywe, W-Y; Liu, C-H

2005-01-01

In order to satisfy the increasing demands on the precision in manufacturing technology, nanaometrology gradually becomes more important in manufacturing process. To ensure the precision of manufacture, precise measuring instruments and sensors play a decisive role for the accurate characterization and inspection of products. For linear length inspection, high precision gauging displacement transducers, i.e. nano gauging displacement transducers (NGDT), have been often utilized, which have been often utilized, which have the resolution in the nanometer range and can achieve an accuracy of less than 100 nm. Such measurement instruments include transducers based on electronic as well as optical measurement principles, e.g. inductive, incremental-optical or interference optical. To guarantee the accuracy and the traceability to the definition of the meter, calibration and test of NGDT are essential. Currently, there are some methods and machines for test of NGDT, but they suffer from various disadvantages. Some of them permit only manual test procedures which are time-consuming, e.g. with high accurate gauge blocks as material measures. Other tests can reach higher accuracy only in the micrometer range or result in uncertainties of more than 100 nm in the large measuring ranges. To realize the test of NGDT with a high resolution as well as a large measuring range, an automatic test equipment was constructed, that has a resolution of 1.24 nm, a measuring range of up to 20 nm (60 mm) and a measuring uncertainty of approximate ±10 nm can fulfil the requirements of high resolution within the nanometer range while simultaneously covering a large measuring range in the order of millimeters. The test system includes a stable frame, a polarization interferometer, an angle sensor, an angular control, a drive system and piezo translators. During the test procedure, the angular control and piezo translators minimize the Abbe error. For the automation of the test procedure a

Development of an automatic test equipment for nano gauging displacement transducers

Science.gov (United States)

Wang, Yung-Chen; Jywe, Wen-Yuh; Liu, Chien-Hung

2005-01-01

In order to satisfy the increasing demands on the precision in manufacturing technology, nanaometrology gradually becomes more important in manufacturing process. To ensure the precision of manufacture, precise measuring instruments and sensors play a decesive role for the accurate characterization and inspection of products. For linear length inspection, high precision gauging displacement transducers, i.e. nano gauging displacement transducers (NGDT), have been often utilized, which have been often utilized, which have the resolution in the nanometer range and can achieve an accuracy of less than 100 nm. Such measurement instruments include transducers based on electronic as well as optical measurement principles, e.g. inductive, incremental-optical or interference optical. To guarantee the accuracy and the traceability to the definition of the meter, calibration and test of NGDT are essential. Currently, there are some methods and machines for test of NGDT, but they suffer from various disadvantages. Some of them permit only manual test procedures which are time-consuming, e.g. with high accurate gauge blocks as material measures. Other tests can reach higher accuracy only in the micrometer range or result in uncertainties of more than 100 nm in the large measuring ranges. To realize the test of NGDT with a high resolution as well as a large measuring range, an automatic test equipment was constructed, that has a resolution of 1.24 nm, a measuring range of up to 20 nm (60 mm) and a measuring uncertainty of approximate ±10 nm can fulfil the requirements of high resolution within the nanometer range while simultaneously covering a large measuring range in the order of millimeters. The test system includes a stable frame, a polarization interferometer, an angle sensor, an angular control, a drive system and piezo translators. During the test procedure, the angular control and piezo translators minimize the Abbe error. For the automation of the test procedure a

Qualification of class 1e equipment: regulation, technological margins and test experience

International Nuclear Information System (INIS)

Pasco, Y.; Le Meur, M.; Henry, J.Y.; Droger, J.P.; Morange, E.; Roubault, J.

1986-10-01

French regulation requires licensee to qualify electrical equipment important to safety for service in nuclear power plants to ensure that the equipment can perform its safety function under the set of plausible operating conditions. The French regulatory texts entitled Fundamental safety rules have classified safety related electrical equipment in three main categories: k1, k2, k3, according to their location and operating conditions. The definition of a design basis accident test profile must account for margins applied to thermal hydraulic code outputs. Specific safety margins was added to cover uncertainties in qualification test representativity. Up to now, accidental sequence studies have shown the validity of such a qualification test profile. On the other hand, the results from post accident simulation tests have shown that it is useful not only to validate post accident operating life but also to reveal failures initiated during previous tests [fr

Measurement and control system for the ITER remote handling mock-up test

International Nuclear Information System (INIS)

Oka, K.; Kakudate, S.; Takiguchi, Y.; Ako, K.; Taguchi, K.; Tada, E.; Ozaki, F.; Shibanuma, K.

1998-01-01

The mock-up test platforms composed of full-scale remote handling (RH) equipment were developed for demonstrating remote replacement of the ITER blanket and divertor. In parallel, the measurement and control system for operating these RH equipment were constructed on the basis of open architecture with object oriented feature, aiming at realization of fully-remoted automatic operation required for ITER. This paper describes the design concept of the measurement and control system for the remote handling equipment of ITER, and outlines the measured performances of the fabricated measurement system for the remote handling mock-up tests, which includes Data Acquisition System (DAS), Visual Monitoring System (VMS) and Virtual Reality System (VRS). (authors)

Universal machine ''Shtrek'' and the tractor-lifter with pneumatic-equipment control. [Auxiliary multipurpose materials handling equipment

Energy Technology Data Exchange (ETDEWEB)

Bal' bert, B M; Borumenskiy, V A; Lishenko, A P; Mitchenko, G A

1982-01-01

The machine ''Shtrek'' is described. It makes it possible to mechanize over 20 auxiliary operations: loading-unloading operations: extraction of old and deformed timbering; dissmantling of obstructions; erection of different types of timbering; making and restoring of drainage channels; laying and straightening of a drift and its leveling; assembly and disassembly of pipelines and mine equipment, etc. Depending on the type of operation, the machine has the corresponding suspended equipment. The elementary variant has a limited area of application at mines of the central region of the Dunbass. Currently a pneumatic variant of the machine ''Shtrek'' has been developed. The electric motor and the starter of the pumping equipment of the machine have been replaced by a pneumatic motor and pneumatically controlled valve KTM-50. In this case there was significant reduction in the weight of the pumping equipment and in its overall dimensions; the electric drive of the hydraulic distributors for controlling the mechanisms were replaced by simpler pneumatic ones; the logical circuit of the control system was constructed on the USEPPA elements. A specialized tractor-lifter designed for moving suspended loads is described for auxiliary operations in the near-face zone of the preparatory drifts. The machine also lifts and lowers the boom, rotates the boom by 270/sup 0/ and additionally lifts and lowers the weight-lifting hook.

Control of Nuclear Materials and Special Equipment (Nuclear Safety Regulations)

International Nuclear Information System (INIS)

Cizmek, A.; Prah, M.; Medakovic, S.; Ilijas, B.

2008-01-01

Based on Nuclear Safety Act (OG 173/03) the State Office for Nuclear Safety (SONS) in 2008 adopted beside Ordinance on performing nuclear activities (OG 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (OG 74/06) the new Ordinance on the control of nuclear material and special equipment (OG 15/08). Ordinance on the control of nuclear material and special equipment lays down the list of nuclear materials and special equipment as well as of nuclear activities covered by the system of control of production of special equipment and non-nuclear material, the procedure for notifying the intention to and filing the application for a license to carry out nuclear activities, and the format and contents of the forms for doing so. This Ordinance also lays down the manner in which nuclear material records have to be kept, the procedure for notifying the State administration organization (regulatory body) responsible for nuclear safety by the nuclear material user, and the keeping of registers of nuclear activities, nuclear material and special equipment by the State administration organization (regulatory body) responsible for nuclear safety, as well as the form and content of official nuclear safety inspector identification card and badge.(author)

Tank monitor and control system (TMACS) revision 11 acceptance test procedure

International Nuclear Information System (INIS)

HOLM, M.J.

1999-01-01

The purpose of this document is to describe tests performed to validate Revision 11 of the Tank Monitor and Control System (TMACS) and verify that the software functions as intended by design. This document is intended to test the software portion of TMACS. The tests will be performed on the development system. The software to be tested is the TMACS knowledge bases (KB) and the I/O driver/services. The development system will not be talking to field equipment; instead, the field equipment is simulated using emulators or multiplexers in the lab

Qualification test of Class 1E equipment based on IEEE323 Std 2003

International Nuclear Information System (INIS)

Kim, J. S.; Jung, S. C.; Kim, T. R.

2004-01-01

IEEE Standard for Qualifying Class 1E Equipment has been updated to 2003 edition since the issue of IEEE Std 323-1971, 1974, 1983. NRC approved the IEEE Std 323-1974 as Qualification standard of Class 1E Equipment in domestic nuclear power plant. IEEE Std 323-2003 was issued in September of 2003 and utility is waiting the approval of NRC. IEEE Std 323-2003 suggest a new qualification technique which adopts the condition monitoring. Performance of two transient during DBA test is no longer recommended in IEEE Std 323-2003. IEEE323 Std 2003 included a chapter of ''extension of Qualified life'' to make available the life extension of components during plant life extension. For the efficient control of preserving EQ in domestic nuclear power plant, IEEE323 Std 2003 is strongly recommended

Maintenance and fabrication of nuclear electronic equipment

International Nuclear Information System (INIS)

Hong, Seok Boong; Chung, Chong Eun; Hwang, In Koo; Koo, In Soo; Park, Bum; Kim, Soo Hee; Lee, Seong Joo; Kim, Min Seok; Choi, Wha Lim

2011-12-01

- process equipment at PIEF, Chemical Analysis Team and RWFTF have been calibrated. - The electronic equipment and radiation equipment at RWTF and PIEF have been prepared. - Development and installation of integrated RMS software for Hanaro Cold Neutron Laboratory Building(CNLB) RMS, and development and performance upgrade of a portal monitor for CNLB. - Performance test of the Hardware/Software of digital unit controller has been performed, and functional upgrade of the Hardware/Software of stimulator for SMART MMIS performance test facility has also been performed. - A controller of high voltage power supply for a small electron beam generator and a controller for razer pinning and a remote monitoring apparatus of cathode power supply for a 0.2 Mev. small electron beam generator have been designed and fabricated. - Database construction for effective maintenance for the process equipment and radiation instruments are designed and constructed

Development of a handmade device for collimation and central ray alignment tests in medical X-ray equipment

International Nuclear Information System (INIS)

Cruz, B.L. da; Brito, E.B.; Gomes, A.S.

2017-01-01

Ordinance 453/98 of the Ministry of Health establishes that medical X-ray equipment should be monitored by tests that prove its efficiency. This practice is called quality control (QC), and two important tests jointly evaluate the operation of the collimation and alignment systems of the central axis of the X-ray beam. The low supply and the high cost generate allegations of difficulties in the periodic realization of the tests. The aim of this work is to design, make and evaluate the performance of a handmade device for the mentioned tests, using low cost materials. Once built, the device had its performance evaluated and compared with the traditionally marketed device. The handmade device proved to be fit in its functions. It is possible to make a device that tests X-ray medical equipment, using the radiology technologist himself as the test runner. Radiation protection is promoted and legislation with no real financial burden

Quality control for the equipment of Nuclear medicine: experience of the H.U. de la Princesa

International Nuclear Information System (INIS)

Espana, M.L.; Gracia, A.; Prieto, C.; Lopez F, P.

1998-01-01

The quality control of the equipment used in a nuclear medicine service is a fundamental aspect in the Quality Assurance Program that in the present time is starting in our hospital. the objective of this work is to present the internal protocol used, its problematic associated with its starting, and the results obtained in the quality control as of the gamma camera as of the activimeter. In addition to the equipment own to the nuclear medicine service it has been used a Cs-137 source and puppets for several purposes. The results obtained demonstrated the stability of the controlled parameters which has led us to a restating of the established periodicities in our internal protocol, over all for some constancy tests. (Author)

Use of Industrial Components in SL/BT Equipment Controls

CERN Document Server

Carlier, E

1999-01-01

The control system of all SPS target stations, beam absorbers and other aperture limiting devices is presently being refurbished, using solely standard industrial hardware and software components. SIEMENS Simatic S7-300 programmable logic controllers serve as equipment controllers. They are connected through Profibus to a WinNT front-end running the SIEMENS WinCC SCADA package which acts as local controller and gateway for remote access. A variant configuration, where the PLCs are directly linked to Ethernet, has been used for controlling the SPS Q measurement kickers. These and some other SL/BT projects will be reviewed where fully off-the-shelf components have been successfully integrated into the SL accelerator controls infrastructure. The arguments leading to the various technical choices will be laid down including a report of the experience gained. Finally, the presentation will address the perspective and current ideas for using industrial components in controlling SL/BT equipment during the LHC era.

Soundness confirmation through cold test of the system equipment of HTTR

International Nuclear Information System (INIS)

Ono, Masato; Shinohara, Masanori; Iigaki, Kazuhiko; Tochio, Daisuke; Nakagawa, Shigeaki; Shimazaki, Yosuke

2014-01-01

HTTR was established at the Oarai Research and Development Center of Japan Atomic Energy Agency, for the purpose of the establishment and upgrading of high-temperature gas-cooled reactor technology infrastructure. Currently, it performs a safety demonstration test in order to demonstrate the safety inherent in high-temperature gas-cooled reactor. After the Great East Japan Earthquake, it conducted confirmation test for the purpose of soundness survey of facilities and equipment, and it confirmed that the soundness of the equipment was maintained. After two years from the confirmation test, it has not been confirmed whether the function of dynamic equipment and the soundness such as the airtightness of pipes and containers are maintained after receiving the influence of damage or deterioration caused by aftershocks generated during two years or aging. To confirm the soundness of these facilities, operation under cold state was conducted, and the obtained plant data was compared with confirmation test data to evaluate the presence of abnormality. In addition, in order to confirm through cold test the damage due to aftershocks and degradation due to aging, the plant data to compare was supposed to be the confirmation test data, and the evaluation on abnormality of the plant data of machine starting time and normal operation data was performed. (A.O.)

An equipment test for grading lumber by transverse vibration technique

Directory of Open Access Journals (Sweden)

Marcelo Rodrigo Carreira

2008-08-01

Full Text Available Due to the great variability of its mechanical properties, the rational use of lumber for structural purposes is directly conditioned to its grading. There are several techniques available for grading structural lumber. The most relevant one is the transverse vibration technique which obtained reliable results in non-destructive evaluation of lumber. The purpose of this work is to present the bases for the mechanical grading of lumber and the results of the calibration test of the frst transverse vibration equipment developed in Brazil. In this research 30 beams of cupiúba (Goupia glabra with nominal dimensions of 5 cm X 10 cm X 300 cm, were used. The tests were accomplished at the Wood and Timber Structures Laboratory (LaMEM of the University of São Paulo (USP. The results showed a strong correlation between the elasticity modulus measured by the static bending test and the one obtained with the transverse vibration equipment, showing the high reliability of the vibration method for the grading of structural lumber. A determination coeffcient (R² of 0.896 was obtained with the Brazilian equipment, showing that it can be used in the grading of lumber.

Shuttle orbiter Ku-band radar/communications system design evaluation. Deliverable test equipment evaluation

Science.gov (United States)

Maronde, R. G.

1980-07-01

The Ku-band test equipment, known as the Deliverable System Test equipment (DSTE), is reviewed and evaluated. The DSTE is semiautomated and computer programs were generated for 14 communication mode tests and 17 radar mode tests. The 31 test modules provide a good cross section of tests with which to exercise the Ku-band system; however, it is very limited when being used to verify Ku-band system performance. More detailed test descriptions are needed, and a major area of concern is the DSTE sell-off procedure which is inadequate.

Ways to control quality of electric equipment in the coal industry

Energy Technology Data Exchange (ETDEWEB)

Shipilov, A.D.; Nabokov, E.P.

1982-01-01

A structure is proposed for organization in the coal industry of a permanent service for controlling quality of electrical engineering equipment. A form was developed for introduction of recommendations to improve quality. Methods are suggested for evaluating the quality level as applied to specific tasks of controlling quality of the electrical equipment used in mining.

Robust control investigations for equipment loaded panels

DEFF Research Database (Denmark)

Aglietti, G.S.; Langley, R.S.; Rogers, E.

1998-01-01

This paper develops a modelling technique for equipment load panels which directly produces (adequate) models of the underlying dynamics on which to base robust controller design/evaluations. This technique is based on the use of the Lagrange's equations of motion and the resulting models...

Human factors evaluation of the engineering test reactor control room

International Nuclear Information System (INIS)

Banks, W.W.; Boone, M.P.

1981-03-01

The Reactor and Process Control Rooms at the Engineering Test Reactor were evaluated by a team of human factors engineers using available human factors design criteria. During the evaluation, ETR, equipment and facilities were compared with MIL-STD-1472-B, Human Engineering design Criteria for Military Systems. The focus of recommendations centered on: (a) displays and controls; placing displays and controls in functional groups; (b) establishing a consistent color coding (in compliance with a standard if possible); (c) systematizing annunciator alarms and reducing their number; (d) organizing equipment in functional groups; and (e) modifying labeling and lines of demarcation

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

International Nuclear Information System (INIS)

Woo, M. S.; Jin, H. J.; Park, G. I.; Park, S. B.

2014-01-01

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

Potentialities of fluorography in radiographic testing of nuclear power plant equipment

International Nuclear Information System (INIS)

Gromov, Yu.V.; Kapustin, V.I.

1984-01-01

Results of fluorography of steel 5-250 mm thick with the application of different radiation sources in accordance with existing test requirements and standards for NPP equipment under industrial conditions, are presented. Sensitivity curves of fluorographic and radiographic testing methods using the RUP-150/300-10 X-ray device, LUEh-15-15000 D linear accelerator flaw detectors with 192 Yr, 60 Co, 137 Cs sources, are given. The radiation energy range is 24O keV-8 MeV. It is shown that fluorographic method meets the requirements of sensitivity and is recommended to test welded joints 5-220 mm thick in NPP equipment under laboratory and industrial conditions

The equipment access software for a distributed UNIX-based accelerator control system

International Nuclear Information System (INIS)

Trofimov, Nikolai; Zelepoukine, Serguei; Zharkov, Eugeny; Charrue, Pierre; Gareyte, Claire; Poirier, Herve

1994-01-01

This paper presents a generic equipment access software package for a distributed control system using computers with UNIX or UNIX-like operating systems. The package consists of three main components, an application Equipment Access Library, Message Handler and Equipment Data Base. An application task, which may run in any computer in the network, sends requests to access equipment through Equipment Library calls. The basic request is in the form Equipment-Action-Data and is routed via a remote procedure call to the computer to which the given equipment is connected. In this computer the request is received by the Message Handler. According to the type of the equipment connection, the Message Handler either passes the request to the specific process software in the same computer or forwards it to a lower level network of equipment controllers using MIL1553B, GPIB, RS232 or BITBUS communication. The answer is then returned to the calling application. Descriptive information required for request routing and processing is stored in the real-time Equipment Data Base. The package has been written to be portable and is currently available on DEC Ultrix, LynxOS, HPUX, XENIX, OS-9 and Apollo domain. ((orig.))

Long-term preventive maintenance of instrumentation control equipment for PWR plants

International Nuclear Information System (INIS)

Sugitani, S.; Nanba, M.

2006-01-01

Since the PWR plants in Japan have been operated more than 30 years, main instrumentation control equipment of analog systems has been renewed to digital control systems. Renewal works had to be done in short period within periodical inspection term and for several facilities. The Mitsubishi LTD group had been provided with these market needs by its digital control system (MELTAC-NplusR 3) applicable to main instrumentation control equipment for primary and secondary systems and had already finished the renewal for practical plants. (T. Tanaka)

Non-destructive testing of a NPP's metallic equipment during operation

International Nuclear Information System (INIS)

Brodskij, B.R.; Monina, Eh.F.

1977-01-01

Some nondestructive testing methods and facilities currently used in the USSR and overseas to remotely control the quality of a NPPs metallic equipment during operation are reviewed. The ultrasonic and γ scanning devices designed to verify the integrity of nuclear reactor pressure vessels and piping weldments are considered. The acoustic emission techniques, ultrasonic holography and routine ultrasonic fault detection are acknowledged the most promising and safe when applied to reactor vessels. On the other hand, the radiographic methods are pointed out not to quarantee the identification of a flaw. There is also a description of a container designed to maintain and repair a nuclear reactor in the highly radioactive environment. The increased interest of foreign firms towards acoustic emission techniques is stressed

Apollo experience report: Development flight instrumentation. [telemetry equipment for space flight test program

Science.gov (United States)

Farmer, N. B.

1974-01-01

Development flight instrumentation was delivered for 25 Apollo vehicles as Government-furnished equipment. The problems and philosophies of an activity that was concerned with supplying telemetry equipment to a space-flight test program are discussed. Equipment delivery dates, system-design details, and flight-performance information for each mission also are included.

Tank Monitor and Control System (TMACS) Rev 11.0 Acceptance Test Review

Energy Technology Data Exchange (ETDEWEB)

HOLM, M.J.

1999-08-25

The purpose of this document is to describe tests performed to validate Revision 11 of the TMACS Monitor and Control System (TMACS) and verify that the software functions as intended by design. This document is intended to test the software portion of TMACS. The tests will be performed on the development system. The software to be tested is the TMACS knowledge bases (KB) and the I/O driver/services. The development system will not be talking to field equipment; instead, the field equipment is simulated using emulators or multiplexers in the lab.

Photoelectric detectors used in laser based control and alignment equipment

International Nuclear Information System (INIS)

Chis, I.; Ciura, A.I.; Udrea, M.V.

1988-03-01

Some theoretical considerations and practical results regarding the utilization of the ROL 50 photovoltaic cell in a leveling control system and glass quality control equipment are presented. (authors)

Suggestion for improvement of PET quality control tests in Brazil

International Nuclear Information System (INIS)

Ferreira, Fernanda C.L.; Magalhaes, Cinthia M.S.; Souza, Divanizia N.

2009-01-01

Nowadays nuclear medicine has a considerable importance among the other medical specialties. This medical specialty utilizes high-tech equipment for imaging in the diagnosis, obtaining information on the clinical functionality of organs and systems of the human body through the use of radioisotopes . In view of the importance of guaranteeing the image quality in SPECT and PET systems, enabling patients not repeat exams due to lack of quality control of equipment used in nuclear medicine, this paper aims to present a possible suggestion to update the quality control tests needed for quality assurance of nuclear medicine services. They were considered the requirements of the National Commission of Nuclear Energy (CNEN) and the National Health Surveillance Agency (ANVISA) in Brazil. The minimum requirements to be defined for inclusion of quality control tests on PET in the standard CNEN are extremely important because they will guide the evaluation of PET systems, determining the quality control tests to be performed. And those tests for PET will be a regulatory requirement by the CNEN and ANVISA. As the National Health Surveillance Agency has already publication of RDC 38 with recommendations for services of nuclear medicine. This study will continue with evaluation of PET systems and presenting the tests of quality control with additional objects and simulators to ensure safety in PET systems have not standardized in nuclear medicine services in Brazil. (author)

Shifting Control Algorithm for a Single-Axle Parallel Plug-In Hybrid Electric Bus Equipped with EMT

Directory of Open Access Journals (Sweden)

Yunyun Yang

2014-01-01

Full Text Available Combining the characteristics of motor with fast response speed, an electric-drive automated mechanical transmission (EMT is proposed as a novel type of transmission in this paper. Replacing the friction synchronization shifting of automated manual transmission (AMT in HEVs, the EMT can achieve active synchronization of speed shifting. The dynamic model of a single-axle parallel PHEV equipped with the EMT is built up, and the dynamic properties of the gearshift process are also described. In addition, the control algorithm is developed to improve the shifting quality of the PHEV equipped with the EMT in all its evaluation indexes. The key techniques of changing the driving force gradient in preshifting and shifting compensation phases as well as of predicting the meshing speed in the gear meshing phase are also proposed. Results of simulation, bench test, and real road test demonstrate that the proposed control algorithm can reduce the gearshift jerk and the power interruption time noticeably.

Using cyber vulnerability testing techniques to expose undocumented security vulnerabilities in DCS and SCADA equipment

International Nuclear Information System (INIS)

Pollet, J.

2006-01-01

This session starts by providing an overview of typical DCS (Distributed Control Systems) and SCADA (Supervisory Control and Data Acquisition) architectures, and exposes cyber security vulnerabilities that vendors never admit, but are found through a comprehensive cyber testing process. A complete assessment process involves testing all of the layers and components of a SCADA or DCS environment, from the perimeter firewall all the way down to the end devices controlling the process, including what to look for when conducting a vulnerability assessment of real-time control systems. The following systems are discussed: 1. Perimeter (isolation from corporate IT or other non-critical networks) 2. Remote Access (third Party access into SCADA or DCS networks) 3. Network Architecture (switch, router, firewalls, access controls, network design) 4. Network Traffic Analysis (what is running on the network) 5. Host Operating Systems Hardening 6. Applications (how they communicate with other applications and end devices) 7. End Device Testing (PLCs, RTUs, DCS Controllers, Smart Transmitters) a. System Discovery b. Functional Discovery c. Attack Methodology i. DoS Tests (at what point does the device fail) ii. Malformed Packet Tests (packets that can cause equipment failure) iii. Session Hijacking (do anything that the operator can do) iv. Packet Injection (code and inject your own SCADA commands) v. Protocol Exploitation (Protocol Reverse Engineering / Fuzzing) This paper will provide information compiled from over five years of conducting cyber security testing on control systems hardware, software, and systems. (authors)

Using cyber vulnerability testing techniques to expose undocumented security vulnerabilities in DCS and SCADA equipment

Energy Technology Data Exchange (ETDEWEB)

Pollet, J. [PlantData Technologies, Inc., 1201 Louisiana Street, Houston, TX 77002 (United States)

2006-07-01

This session starts by providing an overview of typical DCS (Distributed Control Systems) and SCADA (Supervisory Control and Data Acquisition) architectures, and exposes cyber security vulnerabilities that vendors never admit, but are found through a comprehensive cyber testing process. A complete assessment process involves testing all of the layers and components of a SCADA or DCS environment, from the perimeter firewall all the way down to the end devices controlling the process, including what to look for when conducting a vulnerability assessment of real-time control systems. The following systems are discussed: 1. Perimeter (isolation from corporate IT or other non-critical networks) 2. Remote Access (third Party access into SCADA or DCS networks) 3. Network Architecture (switch, router, firewalls, access controls, network design) 4. Network Traffic Analysis (what is running on the network) 5. Host Operating Systems Hardening 6. Applications (how they communicate with other applications and end devices) 7. End Device Testing (PLCs, RTUs, DCS Controllers, Smart Transmitters) a. System Discovery b. Functional Discovery c. Attack Methodology i. DoS Tests (at what point does the device fail) ii. Malformed Packet Tests (packets that can cause equipment failure) iii. Session Hijacking (do anything that the operator can do) iv. Packet Injection (code and inject your own SCADA commands) v. Protocol Exploitation (Protocol Reverse Engineering / Fuzzing) This paper will provide information compiled from over five years of conducting cyber security testing on control systems hardware, software, and systems. (authors)

Review of foreign equipment for powered support control

Energy Technology Data Exchange (ETDEWEB)

Sikora, W; Sobczyk, J

1986-10-01

A new generation of control systems are comparatively evaluated developed by Dowty, Hemscheidt and Thyssen-Siemens for powered supports and shield supports. Types of functions controlled by each system are discussed: support advancing (lowering support canopy, advancing, increasing pressure), control of support position, advancing chain conveyor. The following control systems are described: fully automatic control, remote control from a gate road, manual control from an adjacent support unit. Types of electronic equipment used in the control systems are described: microcomputers (8-bit CMOS device), 8-bit microcomputers, transmission systems, measuring instruments. Advantages of control systems developed and manufactured by the 3 companies are comparatively evaluated.

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-05-15

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

Data acquisition, remote control and equipment monitoring for ISOLDE RILIS

Energy Technology Data Exchange (ETDEWEB)

Rossel, R.E., E-mail: ralf.erik.rossel@cern.ch [CERN, Geneva (Switzerland); Institut für Physik, Johannes Gutenberg-Universität, Mainz (Germany); Hochschule RheinMain, Fachbereich Design Informatik Medien, Wiesbaden (Germany); Fedosseev, V.N.; Marsh, B.A. [CERN, Geneva (Switzerland); Richter, D. [Hochschule RheinMain, Fachbereich Design Informatik Medien, Wiesbaden (Germany); Rothe, S. [CERN, Geneva (Switzerland); Institut für Physik, Johannes Gutenberg-Universität, Mainz (Germany); Wendt, K.D.A. [Institut für Physik, Johannes Gutenberg-Universität, Mainz (Germany)

2013-12-15

Highlights: • The requirements for continuous and automated RILIS operation are outlined. • Laser wavelength, power, beam position and pulse timing are continuously monitored. • A network-extended LabVIEW-based equipment operation framework was developed. • The system serves as a foundation for collaborative laser spectroscopy data acquisition. • Example applications have been successfully tested with ISOLDE experiment setups. -- Abstract: With a steadily increasing on-line operation time up to a record 3000 h in the year 2012, the Resonance Ionization Laser Ion Source (RILIS) is one of the key components of the ISOLDE on-line isotope user facility at CERN. Ion beam production using the RILIS is essential for many experiments due to the unmatched combination of ionization efficiency and selectivity. To meet the reliability requirements the RILIS is currently operated in shift duty for continuous maintenance of crucial laser parameters such as wavelength, power, beam position and timing, as well as ensuring swift intervention in case of an equipment malfunction. A recent overhaul of the RILIS included the installation of new pump lasers, commercial dye lasers and a complementary, fully solid-state titanium:sapphire laser system. The framework of the upgrade also required the setup of a network-extended, LabVIEW-based system for data acquisition, remote control and equipment monitoring, to support RILIS operators as well as ISOLDE users. The system contributes to four key aspects of RILIS operation: equipment monitoring, machine protection, automated self-reliance, and collaborative data acquisition. The overall concept, technologies used, implementation status and recent applications during the 2012 on-line operation period will be presented along with a summary of future developments.

Unsolved problems in applying U.S. regulatory guides to control system equipment

International Nuclear Information System (INIS)

Stade, R.E.

1978-01-01

Two current problems encountered when designing control systems to the United States Regulatory Guide requirements are discussed. They are: 1) Level of surge voltages that should be specified when procuring solid state control and instrumentation systems and equipment. 2) The approach to be used qualifying equipment that must meet the aging requirements. (author)

14 CFR Appendix J to Part 23 - HIRF Environments and Equipment HIRF Test Levels

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false HIRF Environments and Equipment HIRF Test Levels J Appendix J to Part 23 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF.... 23, App. J Appendix J to Part 23—HIRF Environments and Equipment HIRF Test Levels This appendix...

Quick setup of test unit for accelerator control system

International Nuclear Information System (INIS)

Fu, W.; D'Ottavio, T.; Gassner, D.; Nemesure, S.; Morris, J.

2011-01-01

Testing a single hardware unit of an accelerator control system often requires the setup of a program with graphical user interface. Developing a dedicated application for a specific hardware unit test could be time consuming and the application may become obsolete after the unit tests. This paper documents a methodology for quick design and setup of an interface focused on performing unit tests of accelerator equipment with minimum programming work. The method has three components. The first is a generic accelerator device object (ADO) manager which can be used to setup, store, and log testing controls parameters for any unit testing system. The second involves the design of a TAPE (Tool for Automated Procedure Execution) sequence file that specifies and implements all te testing and control logic. The sting third is the design of a PET (parameter editing tool) page that provides the unit tester with all the necessary control parameters required for testing. This approach has been used for testing the horizontal plane of the Stochastic Cooling Motion Control System at RHIC.

Microcomputer network for technological equipment monitoring and control

International Nuclear Information System (INIS)

Segec, O.

1990-01-01

The properties and purpose are characterized of a microcomputer network developed for monitoring and controlling the nuclear power plant chemistry. In the development, emphasis was put on simplicity of the components, reliability, ease of operation and availability of the components on the domestic market. So far, these criteria are only met by the DIAMO L(S) system equipped with an MH 8080 (Z80) processor. Its assets include simplicity and ruggedness, owing to which it is well suited to heavy-duty performance, whereas its drawbacks comprise a narrow extent of addressable memory and absence of any supporting software. Until now, 5 types of automated stations have been developed and submitted for test operation at the Bohunice V-2 nuclear power plant. Virtually any personal computer can be attached to the network. The system can also be installed in conventional power plants as well as beyond the power generation field. (Z.M.)

The Northern regional programme for the acceptance testing of X-ray equipment

International Nuclear Information System (INIS)

Faulkner, K.; Harrison, R.M.; Kotre, C.J.; Smith, S.; Davies, M.; Barker, P.

1989-01-01

Since 1984 the UK Northern Regional Medical Physics Department has participated in a regional acceptance testing programme for all X-ray equipment from mobile units to computed tomography scanners. Organizational and radiation physics aspects of the programme are described. Three levels of tests are performed by physicists: the first on installation, the second after 3 months, the final visit just prior to the end of the manufacturers warranty. The second test is only performed if any aspect of performance requires rechecking as a result of the first. Acceptance test protocols are based on those published by the Institute of Physical Sciences in Medicine. Details limiting values for the acceptance test measurements are given. In some instances testing has resulted in modifications to the design and construction of X-ray equipment. Acceptance testing is important in determining a baseline standard of performance against which routine quality assurance may be assessed. (author)

Replacement of the Advanced Test Reactor control room

International Nuclear Information System (INIS)

Durney, J.L.; Klingler, W.B.

1989-01-01

The control room for the Advanced Test Reactor has been replaced to provide modern equipment utilizing current standards and meeting the current human factors requirements. The control room was designed in the early 1960 era and had not been significantly upgraded since the initial installation. The replacement did not change any of the safety circuits or equipment but did result in replacement of some of the recorders that display information from the safety systems. The replacement was completed in concert with the replacement of the control room simulator which provided important feedback on the design. The design successfully incorporates computer-based systems into the display of the plant variables. This improved design provides the operator with more information in a more usable form than was provided by the original design. The replacement was successfully completed within the scheduled time thereby minimizing the down time for the reactor. 1 fig., 1 tab

Replacement of the Advanced Test Reactor control room

International Nuclear Information System (INIS)

Durney, J.L.; Klingler, W.B.

1990-01-01

The control room for the Advanced Test Reactor has been replaced to provide modern equipment utilizing current standards and meeting the current human factors requirements. The control room was designed in the early 1960 era and had not been significantly upgraded since the initial installation. The replacement did not change any of the safety circuits or equipment but did result in replacement of some of the recorders that display information from the safety systems. The replacement was completed in concert with the replacement of the control room simulator which provided important feedback on the design. The design successfully incorporates computer-based systems into the display of the plant variables. This improved design provides the operator with more information in a more usable form than was provided by the original design. The replacement was successfully completed within the scheduled time thereby minimizing the down time for the reactor

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...

The Northern Regional Programme for the acceptance testing of X-ray equipment

International Nuclear Information System (INIS)

Faulkner, K.; Harrison, R.M.; Kotre, C.J.; Smith, S.; Davies, M.; Barker, P.

1989-01-01

Since 1984 the Regional Medical Physics Department has participated in a regional acceptance testing programme for all X-ray equipment from mobile units to computed tomography scanners. The organizational and radiation physics aspects of the programme are described. Three levels of tests are performed by physicists: the first on installation, the second after 3 months, and the final visit just prior to the end of the manufacturer's warranty. The second test is only performed if any aspect of performance requires rechecking as a result of the first visit. Acceptance test protocols are based on those published by the Institute of Physical Sciences in Medicine. Details of the limiting values for the acceptance test measurements are given. The results of the programme are discussed. In some instances the testing has resulted in modifications to the design and construction of X-ray equipment. Acceptance testing is important in determining a baseline standard of performance against which routine quality assurance may be assessed. (author)

Application of new technologies for the nondestructive testing equipment Novovoronezh NPP-2 and Leningrad 2

International Nuclear Information System (INIS)

Nichev, V.; Cvitanović, M.; Nadinic, B.

2016-01-01

This presentation demonstrates the latest technology and means of nondestructive testing of equipment of reactor VVER-1200, realized at the Novovoronezh NPP-2 and Leningrad NPP-2. The developments are based on a contract between ATOMKOMPLEKT with HRID, Croatia as a designer and contractor and and Rosatom. The activities of the presented company and IQC are associated with the qualification of methodologies control of components important to safety as required by the European methodology and requirements of Russian legislation

A study on the test of efficiency of the diagnostic X-ray equipment according to their rectifications

International Nuclear Information System (INIS)

Seon, Jong Ryul

1997-01-01

For the efficient management of the diagnostic x-ray equipment, a nation-wide inspection of hospitals was performed by an inspection institute in Taejon in the first half of 1997. Among those hospitals inspected, 28 equipments(machines) which were over 500 mA were randomly selected according to their characteristics : 7 condenser type x-ray equipments, 7 three control phase of full wave rectification of type remote control x-ray equipments, 7 single phase of full wave rectification type for general radiography equipments, and 7 single phase of full wave rectification type of R/F equipments. We obtained the following results by conducting the experiment based on the efficiency of the equipments mentioned above. 1) When te equipments are analyzed, 2 out of 7 single phase of full wave rectification type of general radiography equipments(28.6%), 3 out of 7 single phase of full wave rectification type of R/F equipments(42.9%), 5 out of 7 three phase of full wave rectification type remote of control x-ray equipments(71.4%), and 4 out of 7 condenser type of x-ray equipments(57.1%) showed suitability. It proves the superiority of the three phase of full wave rectification type of remote control x-ray equipments. 2) From the overall analysis, only about 50% of the equipments(suitability of 14 out of 28) maintain the efficient management. Therefore, maintenance management of equipments is more necessary. If the efficiency of the x-ray equipment is uniformly maintained and managed to prevent the breakdown(trouble) beforehand especially through the continuous inspection of tube voltage, tube current, exposure time, and collimator, the financial loss and exposure dose to the patient, as well as the workers engaged in radiation, can be reduced for better medical service

Analysis of bacterial contamination on surface of general radiography equipment and CT equipment in emergency room of radiology

Energy Technology Data Exchange (ETDEWEB)

Hong, Dong Hee; KIm, Hyeong Gyun [Dept. of Radiological Science, Far East University, Eumseong (Korea, Republic of)

2016-09-15

We aim to offer basic materials about infection management through conducting bacterial contamination test about general radiography equipment and CT equipment installed in ER of three general hospitals with 100 sickbeds or more located in Gyeongsangbuk-do Province, and suggest management plan. It had been conducted from 1st December 2015 to 31st December, and objects were general radiography equipment and CT equipment of emergency room located in Gyeongsangbuk-do Province. For general radiography equipment, sources were collected from 4 places such as upper side of control box which employees use most, upper side of exposure button, whole upper side of table which is touching part of patient's skin, upper side of stand bucky's grid, and where patients put their jaws on. For CT equipment, sources were collected from 3 places such as upper side of control box which radiography room employees use most, X-ray exposure button, whole upper side of table which is touching part of patient's skin, and gantry inner. Surface contamination strain found at general radiography equipment in emergency room of radiology are Providencia stuartii(25%), Stenotrophomonas maltophilia(18%), Enterobacter cloacae(8%), Pseudomonas species(8%), Staphylococcus epidermidis(8%), Gram negative bacilli(8%), and ungrown bacteria at incubator after 48 hours of incubation (67%) which is the biggest. Most bacteria were found at upper side of stand bucky-grid and stand bucky of radiology's general radiography equipment, and most sources of CT equipment were focused at patient table, which means it is contaminated by patients who have various diseases, and patients who have strains with decreased immunity may get severe diseases. Thus infection prevention should be made through 70% alcohol disinfection at both before test and after test.

Analysis of bacterial contamination on surface of general radiography equipment and CT equipment in emergency room of radiology

International Nuclear Information System (INIS)

Hong, Dong Hee; KIm, Hyeong Gyun

2016-01-01

We aim to offer basic materials about infection management through conducting bacterial contamination test about general radiography equipment and CT equipment installed in ER of three general hospitals with 100 sickbeds or more located in Gyeongsangbuk-do Province, and suggest management plan. It had been conducted from 1st December 2015 to 31st December, and objects were general radiography equipment and CT equipment of emergency room located in Gyeongsangbuk-do Province. For general radiography equipment, sources were collected from 4 places such as upper side of control box which employees use most, upper side of exposure button, whole upper side of table which is touching part of patient's skin, upper side of stand bucky's grid, and where patients put their jaws on. For CT equipment, sources were collected from 3 places such as upper side of control box which radiography room employees use most, X-ray exposure button, whole upper side of table which is touching part of patient's skin, and gantry inner. Surface contamination strain found at general radiography equipment in emergency room of radiology are Providencia stuartii(25%), Stenotrophomonas maltophilia(18%), Enterobacter cloacae(8%), Pseudomonas species(8%), Staphylococcus epidermidis(8%), Gram negative bacilli(8%), and ungrown bacteria at incubator after 48 hours of incubation (67%) which is the biggest. Most bacteria were found at upper side of stand bucky-grid and stand bucky of radiology's general radiography equipment, and most sources of CT equipment were focused at patient table, which means it is contaminated by patients who have various diseases, and patients who have strains with decreased immunity may get severe diseases. Thus infection prevention should be made through 70% alcohol disinfection at both before test and after test

IEEE Std 600: IEEE trial-use standard requirements for organizations that conduct qualification testing of safety systems equipment for use in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

The purpose of this standard is to provide requirements for establishing a program for conducting qualification tests of safety systems equipment used in nuclear power generating stations. Compliance with the requirements of this standard does not assure the adequacy of the qualification tests performed. This standard applies to organizations that conduct qualification tests on equipment that has a definable safety function and is an identifiable part of a safety system for use in nuclear power generating stations. It requires a technical program, a quality assurance program, and a demonstrated ability to meet specified technical requirements. It does not apply to materials tests, production tests, normal performance testing, qualification by analysis, qualification by operating experience, or reliability tests such as diesel-generator multiple start tests. The intent of this standard is to achieve greater consistency, reliability, and reproducibility of test results and to provide adequate control of qualification testing of safety systems equipment

Dynamic tension testing equipment for paperboard and corrugated fiberboard

Science.gov (United States)

W. D. Godshall

1965-01-01

The objective of this work was to develop a method, the testing equipment, and the instrumentation with which dynamic stress-strain information may be obtained for paperboards and built-up corrugated fiberboards as used in corrugated fiberboard containers. Much information is available on the properties of these materials when subjected to static or low rates of...

The process control and management on equipment qualification of nuclear power plant

International Nuclear Information System (INIS)

Liu Dong; Wang Hongyin; Zhang Yong

2013-01-01

The equipment qualification (EQ) to the safety class equipment is an important safety measure for the nuclear power plants (NPP), and also reflects the nuclear safety culture. Along with the continuous constructions of NPP in China, it has become an important issue for NPP engineering company and equipment suppliers how to effectively establish standard EQ process control and management, and provide sufficient technical arrangements to maintain this EQ management system. This paper summarizes three process of EQ including Design Input, EQ Establishment and EQ Maintenance, proposes the measures and key points for EQ process control and management in phase of NPP construction, and introduces the documents management during the whole process of EQ. (authors)

The heater system monitoring and control of the fuelling machines test rig fluid

International Nuclear Information System (INIS)

Iorga, C.; Iorga, H.

2016-01-01

The thermo-mechanical hot loop (HL) of the testing rig for the fuelling machines (F/Ms) represents a set of facilities and equipment that perform the pressure, temperature and flow thermo-hydraulic parameters similar to those from the fuel channel for CANDU 600 reactor types. The 2.1 MW electric heater (EH), part of the HL, working under the conditions of a pressure vessel (110 bars) and provides an average temperature of 300°C of the working agent. The monitoring equipment implemented aims to simultaneously control the temperature for each of the 12 modules that compose the EH, without influencing the work logic of the display/recording and protecting existing equipment. This paper presents the structure of the monitoring equipment and its performance obtained after performing the functional tests. (authors)

New equipment for the needs of mobile automatic ultrasonic testing

International Nuclear Information System (INIS)

Cost, H.; Vogt, M.

1989-01-01

A newly designed system of equipment - ECHOGRAPH 1030 MULTI - for multiplex operation is introduced. The frequency control unit which can distribute a pulse sequency frequency from a maximum of 8 KHz to up to 8 cycles and the monitor evaluation, are described. (MM) [de

Verification tests for remote controlled inspection system in nuclear power plants

International Nuclear Information System (INIS)

Kohno, Tadaaki

1986-01-01

Following the increase of nuclear power plants, the total radiation exposure dose accompanying inspection and maintenance works tended to increase. Japan Power Engineering and Inspection Corp. carried out the verification test of a practical power reactor automatic inspection system from November, 1981, to March, 1986, and in this report, the state of having carried out this verification test is described. The objects of the verification test were the equipment which is urgently required for reducing radiation exposure dose, the possibility of realization of which is high, and which is important for ensuring the safety and reliability of plants, that is, an automatic ultrasonic flaw detector for the welded parts of bend pipes, an automatic disassembling and inspection system for control rod driving mechanism, a fuel automatic inspection system, and automatic decontaminating equipments for steam generator water chambers, primary system crud and radioactive gas in coolant. The results of the verification test of these equipments were judged as satisfactory, therefore, the application to actual plants is possible. (Kako, I.)

Current trends in small vocabulary speech recognition for equipment control

Science.gov (United States)

Doukas, Nikolaos; Bardis, Nikolaos G.

2017-09-01

Speech recognition systems allow human - machine communication to acquire an intuitive nature that approaches the simplicity of inter - human communication. Small vocabulary speech recognition is a subset of the overall speech recognition problem, where only a small number of words need to be recognized. Speaker independent small vocabulary recognition can find significant applications in field equipment used by military personnel. Such equipment may typically be controlled by a small number of commands that need to be given quickly and accurately, under conditions where delicate manual operations are difficult to achieve. This type of application could hence significantly benefit by the use of robust voice operated control components, as they would facilitate the interaction with their users and render it much more reliable in times of crisis. This paper presents current challenges involved in attaining efficient and robust small vocabulary speech recognition. These challenges concern feature selection, classification techniques, speaker diversity and noise effects. A state machine approach is presented that facilitates the voice guidance of different equipment in a variety of situations.

Mounted Smartphones as Measurement and Control Platforms for Motor-Based Laboratory Test-Beds

OpenAIRE

Jared A. Frank; Anthony Brill; Vikram Kapila

2016-01-01

Laboratory education in science and engineering often entails the use of test-beds equipped with costly peripherals for sensing, acquisition, storage, processing, and control of physical behavior. However, costly peripherals are no longer necessary to obtain precise measurements and achieve stable feedback control of test-beds. With smartphones performing diverse sensing and processing tasks, this study examines the feasibility of mounting smartphones directly to test-beds to exploit their em...

Large Scale Leach Test Facility: Development of equipment and methods, and comparison to MCC-1 leach tests

International Nuclear Information System (INIS)

Pellarin, D.J.; Bickford, D.F.

1985-01-01

This report describes the test equipment and methods, and documents the results of the first large-scale MCC-1 experiments in the Large Scale Leach Test Facility (LSLTF). Two experiments were performed using 1-ft-long samples sectioned from the middle of canister MS-11. The leachant used in the experiments was ultrapure deionized water - an aggressive and well characterized leachant providing high sensitivity for liquid sample analyses. All the original test plan objectives have been successfully met. Equipment and procedures have been developed for large-sample-size leach testing. The statistical reliability of the method has been determined, and ''bench mark'' data developed to relate small scale leach testing to full size waste forms. The facility is unique, and provides sampling reliability and flexibility not possible in smaller laboratory scale tests. Future use of this facility should simplify and accelerate the development of leaching models and repository specific data. The factor of less than 3 for leachability, corresponding to a 200,000/1 increase in sample volume, enhances the credibility of small scale test data which precedes this work, and supports the ability of the DWPF waste form to meet repository criteria

Development of equipment qualification requirements for NPP instrumentation and control systems

International Nuclear Information System (INIS)

Siora, A. A.; Reshetitskij, S. V.; Harybin, A. V.

2012-01-01

The main stages of equipment qualification are presented. The aim of the work is to ensure compatibility between Ukrainian and international requirements. A comparison with US NRC requirements has been done. The approach in equipment qualification is presented for the resistance to: irradiation; dust; seismic motion, vibrations and mechanical impact; environmental impact (temperature, humidity, pressure); power supply parameters etc., as well as the technological testing

Compliance testing of medical diagnostic x-ray equipment: three years experience of a public hospital in western Australia

International Nuclear Information System (INIS)

Tuchyna, T.; Jacob, C.S.

2000-01-01

Full text: A formal compliance testing program which began on 1 January 1997 called for all medical and diagnostic x-ray equipment to be tested according to protocols established by the Western Australian Radiological Council. This work describes the impact of the legislation three years post implementation on a major teaching Hospital with 45 x-ray tubes located throughout 37 rooms. Testing is performed prior to scheduled service by licensed compliance testers according to test methods specified in the Western Australian Compliance Testing Workbook, 1997. A dedicated non-invasive x-ray beam analyser is instrumental in accurately determining radiation output parameters of the generator and x-ray tube. Assessment of compliance is determined by a Qualified Expert. Repair and re-testing of non-compliant items is coordinated with service personnel. Notices of non-compliance were received for approximately 60% of the equipment in the Hospital following the equipment' first annual test. Reasons and seriousness of failure varied according to equipment category, test category, equipment use and age. The majority of non-compliance issues were resolved within 90 days. At the end of the third year of testing, approximately 75% of the x-ray units tested met the compliance criteria. The main reasons for non-compliance were found to be design limitations associated with old technology and the current radiation legislation that makes it difficult for older equipment to meet the stringent criteria. The number and categories of failure did not significantly decrease in the second or third years of testing. Exemptions from compliance criteria have been sought for two units on the basis of age and design. Units unable to meet the criteria following several repair attempts or where the cost of repair was deemed not justified, were decommissioned. Formal testing of medical x-ray equipment has demonstrated various non-compliance issues that did not significantly improve during the

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...

Evaluation of the Nuclear Medicine facilities in Minas Gerais state: quality control program of equipment

International Nuclear Information System (INIS)

Kubo, Tadeu Takao Almodovar; Biancardi, Rodrigo; Rocha, Adriana Marcia Guimaraes; Ferreira, Denia Romao; Silva, Franciele Aquiles Anjos; Assuncao, Jonathan Buenos Aires; Alves, Ederson Henrique; Almeida, Ana Flavia Batista; Alves, Nathalia Fernandes; Xavier, Faber Henrique Zacarias; Gontijo, Rodrigo Modesto Gadelha; Mamede, Marcelo; Universidade Federal de Minas Gerais

2017-01-01

With the reformulation of the CNEN-NN-3.05 standard in December 2013, Brazil's Nuclear Medicine (NMS) services have to perform a greater number of quality controls for SPECT and PET equipment. However, little is known about the reality of the quality control programs of these services regarding the application of the new standard. Thus, in this context, the objective of the present study was to evaluate the quality control program of MNSs in the state of Minas Gerais. All NMSs in the state of Minas Gerais were invited to participate in the project. Of these, 34.48% (20 facilities) agreed to participate in the project, 50.00% (29 facilities) did not respond to the invitation and 15.52%(9 facilities) declined their participation. Thus, as of November 2015, 20 SPECT and 2 PET/CT equipment were evaluated for the performance of the quality control tests recommended by the new CNEN standard. The phantoms required for the evaluation came from the Laboratory of Dosimetry and Quality Control of UFMG. Even with the deadlines set by CNEN for the implementation of the quality control program in the NMSs, more than 50% of the evaluated services did not implement the quality controls, and the absence of specific phantoms is the main reason for the failure. Among the problems found in the installations, the most critical were: collimators with no conditions of use in the clinical routine, linearity problems of the evaluated image and values of image uniformity superior to the limits of acceptance. Problems in the uniformity and linearity of the image found directly impacted the performance of other tests, such as spatial resolution, SPECT performance, among others. In a general way, the NMSs in the state of Minas Gerais evaluated with the present study are in clinical feasible conditions. (author)

The LHC dipole test control architecture

International Nuclear Information System (INIS)

Gorskaya, E.; Samojlov, V.; Raimondo, A.; Rijllart, A.

2003-01-01

The next large accelerator project at CERN is the Large Hadron Collider, which is foreseen to be installed in the existing LEP tunnel, and scheduled to be commissioned in 2007. For this project, 1200 15-metre long dipole magnets need to be tested at CERN in warm and cold conditions on dedicated test benches that are under development. The final LHC dipole series test set-up will consist of 12 benches organized in 6 clusters of two benches sharing the largest and most expensive devices. This sharing is made possible by a deliberate de-phasing of the tests among magnets, ensuring an optimum use of resources, such as cryogenics and power equipment, without limiting the total throughput. An offered two-level control architecture includes: 1) the Test 'Master' that drives the test for a cluster; 2) the Resource 'Manager' that allocates common devices and central resources. The implementation of this architecture is done in the LabVIEW environment

40 CFR 1065.910 - PEMS auxiliary equipment for field testing.

Science.gov (United States)

2010-07-01

..., you may route engine intake air or exhaust through a flow meter. Route the engine intake air or exhaust as follows: (1) Flexible connections. Use short flexible connectors where necessary. (i) You may use flexible connectors to enlarge or reduce the pipe diameters to match that of your test equipment...

DEVELOPMENT OF THE TEMPERATURE CONTROL OF THE HOME-STREET AND MANAGING EXECUTIVE EQUIPMENT

Directory of Open Access Journals (Sweden)

Doshenko G.G.

2017-12-01

Full Text Available A home-street temperature control device and executive equipment management have been developed, which is characterized by high reliability and comparatively low cost. Due to the improvement of the analog circuit it is ensured to increase the speed of the developed device and its reliability. Practical recommendations for the manufacture of a home-street temperature control device and executive equipment management are presented

Dynamic monitoring equipment for earthworks and sub grades

International Nuclear Information System (INIS)

Alvarez de Sotomayor, R.

2013-01-01

This paper take into account some dynamic auscultation equipment s that currently are available in Spain for compaction quality control on earthworks and sub grades. Closed to the equipment description, a deformation modulus calculus approximation has been developed for each of them. A standards checking has been made from national and European point of view. some important research works that have been developed in our country about dynamic monitoring equipment s for quality control in earthworks has been mentioned. In addition to this, some variables are analyzed which have an influence on deformation modulus calculi and a possibility for comparing the equipment modulus calculated with a reference laboratory test has been offered. (Author) 18 refs.

NPP capital equipment life control facilities and tools

International Nuclear Information System (INIS)

Nekrasov, A.V.; Proskuryakov, K.N.

2009-01-01

Algorithms and simulation package for calculation of eigen modes of coolant pressure oscillations in equipment of primary coolant circuit of WWER-1000 NPP, tuned-circuit Q-factor of an oscillating contour of the coolant, fluctuation frequencies pass band and attenuation factors of were developed. Calculation results for cases of presence and absence of gaseous state radiolysis products in the coolant were obtained. Results analysis makes it possible to disclose operating conditions which result in raised vibrations, and to develop control response in NPP industrial control system for their prevention [ru

Strategy and implementation of resources control of key equipments in nuclear power plant

International Nuclear Information System (INIS)

Zha Qing

2014-01-01

The strategic resources of the construction of nuclear power plant, which include the main equipment of nuclear island, heavy forgings, the bottleneck equipment and strategic materials, is one of the key issues in the construction of nuclear power projects. The control of these strategic resources has become the focus of competition in industry and the major nuclear power groups are willing to fight for this huge advantages. The resource control strategies of key equipment of nuclear power projects are analyzed in this paper. This paper put forward specific measures and methods for the strategic resources control. By the application to a plurality of nuclear power engineering construction projects, these specific measures and methods achieved good results and will be with important guidance and reference for the construction of future nuclear power projects in China. (author)

Development of maintenance equipment for nuclear material fabrication equipment in a highly active hot cell

International Nuclear Information System (INIS)

Park, J. J.; Yang, M. S.; Kim, K. H. and others

2000-09-01

This report presents the development of a maintenance system for a highly contaminated nuclear material handling equipment at a hot-cell. This maintenance system has mainly three subsystems - a gamma-radiation measurement module for detecting a gamma-radiation level and identifying its distribution in-situ, a dry-type decontamination device for cleaning up contaminated particles, and a maintenance chamber for isolating contaminated equipment. The mechanical design considerations, controller, capabilities and remote operation and manipulation of the maintenance system are described. Such subsystems developed were installed and tested in the IMEF (Irradiated Material Examination Facility) M6 hot-cell after mock-up tests and performed their specific tasks successfully

Development of maintenance equipment for nuclear material fabrication equipment in a highly active hot cell

Energy Technology Data Exchange (ETDEWEB)

Park, J. J.; Yang, M. S.; Kim, K. H. and others

2000-09-01

This report presents the development of a maintenance system for a highly contaminated nuclear material handling equipment at a hot-cell. This maintenance system has mainly three subsystems - a gamma-radiation measurement module for detecting a gamma-radiation level and identifying its distribution in-situ, a dry-type decontamination device for cleaning up contaminated particles, and a maintenance chamber for isolating contaminated equipment. The mechanical design considerations, controller, capabilities and remote operation and manipulation of the maintenance system are described. Such subsystems developed were installed and tested in the IMEF (Irradiated Material Examination Facility) M6 hot-cell after mock-up tests and performed their specific tasks successfully.

Process control for the Vivitron: the generator test set-up

International Nuclear Information System (INIS)

Lutz, J.R.; Marsaudon, J.C.; Baumann, R.; Kapps, E.; Knaebel, R.; Persigny, J.

1992-01-01

The VIVITRON is a 35 MV Van de Graaff tandem electrostatic accelerator under construction at the CRN since 1985. About half of the parameters are controlled by equipments which are highly stressed by their physical environment: sparks, electrostatic field, X-rays, vacuum, and gas pressure. It needs a dedicated process control system. The described control system is used since early 1991 to perform the voltage tests of the generator. It provides important information for the accelerator tuning and for the full size control under development. (author)

Interlaboratory comparison and accreditation in quality control testing of diagnostic X-ray equipment

International Nuclear Information System (INIS)

Kepler, K.; Vladimirov, A.; Servomaa, A.

2005-01-01

The Univ. of Tartu provides a quality control service to the majority of diagnostic X-ray departments in Estonia. Its methodology has been adopted from the IEC and other relevant standards. Recently the Testing Centre of the Univ. of Tartu was accredited on this methodology by ISO/IEC 17025. Besides the implementation of the quality management system, participation in interlaboratory comparison (ILC) was one of the prerequisites for the accreditation. Tests for estimating reproducibility of tube voltage and dose rate, accuracy of the voltage and accuracy of exposure time were carried out on a diagnostic X-ray unit in the Radiation and Nuclear Safety Authority in Helsinki. The measurement performance was judged by calculating deviation En normalised with respect to the stated uncertainties. En values for all tests were less than unity and by the common ILC criteria the testing performance could be considered as acceptable. (authors)

40 CFR 792.63 - Maintenance and calibration of equipment.

Science.gov (United States)

2010-07-01

... SUBSTANCES CONTROL ACT (CONTINUED) GOOD LABORATORY PRACTICE STANDARDS Equipment § 792.63 Maintenance and..., maintenance, testing, calibration, and/or standardization of equipment, and shall specify, when appropriate... 40 Protection of Environment 31 2010-07-01 2010-07-01 true Maintenance and calibration of...

Operation control equipment for BWR type reactor

International Nuclear Information System (INIS)

Izumi, Masayuki; Takeda, Renzo.

1981-01-01

Purpose: To improve the temperature balance in a feedwater heater by obtaining the objective value of a feedwater enthalpy upon calculation of respective measured values and controlling the opening or closing of an extraction valve so that the objective value may coincide with the measured value, thereby averaging the axial power distribution. Constitution: A plurality of stages of extraction lines are connected to a turbine, and extraction valves are respectively provided at the lines. By calculating the measured values of ractor pressure, reactor core flow rate, vapor flow rate and reactor core inlet enthalpy determined to predetermined value using heat balance the objective feedwater enthalpy is obtained, is fed as an extraction valve opening or closing signal from a control equipment, the extraction stages of the turbine extraction are altered in accordance with this signal, and the feedwater enthalpy is controlled. (Sekiya, K.)

Domestic manufacturing and reliability improvement of reactor water recirculation equipment

International Nuclear Information System (INIS)

Kobayashi, Hidekazu; Oi, Masao; Shida, Toichi; Yokomori, Takashi

1982-01-01

The reactor coolant recirculation system is one of the important systems to control the reactor output in BWR nuclear power plants. Its components require high reliability and maintainability as well as controllability. For many Japanese nuclear power plants, recirculation pumps, fluid couplings and others have been imported so far. Hitachi Ltd. has established a domestic manufacturing organization through the development and test of these equipment. The fundamental design conditions for these equipment are the improvement of the rate of utilization of plant facility, the capability to follow load, and output power stability. In this paper, the specifications, the investigation of moment of inertia and the design features of recirculation pumps, driving motors and variable frequency power supply systems are described. The paper also reports on the combination test implemented to evaluate the recirculation system. The combination test includes the test using water rheostat for the power source facility and the loading test for a recirculation pump. The application of those system equipment to an actual plant was analyzed and evaluated on a basis of the test data obtained. The result showed that the equipment can achieve the rate of change of reactor power of 30%/min. Those equipment have been employed for No. 2 reactor plant of the Fukushima No. 2 Nuclear Power Station, the Tokyo Electric Power Co., Inc. (Wakatsuki, Y.)

Seismic fragility levels of nuclear power plant equipment

International Nuclear Information System (INIS)

Bandyopadhyay, K.K.; Hofmayer, C.H.

1987-01-01

Seismic fragility levels of safety-related electrical and mechanical equipment used in nuclear power plants are discussed. The fragility level is defined as the vibration level corresponding to initiation of equipment malfunctions. The test response spectrum is used as a measure of this vibration level. The fragility phenomenon of an equipment is represented by a number of response spectra corresponding to various failure modes. Analysis methods are described for determination of the fragility level by use of existing test data. Useful conversion factors are tabulated to transform test response spectra from one damping value to another. Results are presented for switch-gears and motor control centers. The capacity levels of these equipment assemblies are observed to be limited by malfunctioning of contactors, motor starters, relays and/or switches. The applicability of the fragility levels, determined in terms of test response spectra, to Seismic Margin Studies and Probabilistic Risk Assessments is discussed and specific recommendations are provided

Contributions to the research programs in nuclear and industrial electronics, domestic production of instrumentation, safety and control systems and equipment for nuclear reactors and auxiliary installations

International Nuclear Information System (INIS)

Talpariu, C; Talpariu, J.; Matei, C.

2001-01-01

Domestic production of component system and equipment for the control and safety of nuclear facilities was one of the priority objective of the Nuclear Research Institute Pitesti. The problems addressed were particularly related to design and production of analog and digital equipment for measurements, triggering and display of the values of process parameters as well as to regulating complex functions of this equipment. Associated to this effort were the research works concerning: - reliability and in-service life-time of the electronic components and equipment in the safety and control systems for nuclear processes; - radiation endurance of industrial electronic components; utilization of whirling currents in calandria tube testing; - expert systems and applications in nuclear reactor control and safety; design and testing methods of process real time software packages for safety in control critical systems for nuclear domain. There are presented characteristics of the following equipment: 1. amplifier for ionization chambers with triggering comparator circuits for the CANDU 600 reactor shut down system; 2. amplifier for ionization chambers without triggering comparator circuits for power regulating system; 3. safety and regulating computerized system for C9 and C5 cans; 4. acquisition system for dosimetric data in nuclear facilities; 5. program able digital comparator for the reactor shut down system; 6. stationary gamma areal monitors for CANDU 600 reactors and other nuclear facilities

A Study on Performance and Safety Tests of Electrosurgical Equipment.

Science.gov (United States)

Tavakoli Golpaygani, A; Movahedi, M M; Reza, M

2016-09-01

Modern medicine employs a wide variety of instruments with different physiological effects and measurements. Periodic verifications are routinely used in legal metrology for industrial measuring instruments. The correct operation of electrosurgical generators is essential to ensure patient's safety and management of the risks associated with the use of high and low frequency electrical currents on human body. The metrological reliability of 20 electrosurgical equipment in six hospitals (3 private and 3 public) was evaluated in one of the provinces of Iran according to international and national standards. The achieved results show that HF leakage current of ground-referenced generators are more than isolated generators and the power analysis of only eight units delivered acceptable output values and the precision in the output power measurements was low. Results indicate a need for new and severe regulations on periodic performance verifications and medical equipment quality control program especially in high risk instruments. It is also necessary to provide training courses for operating staff in the field of meterology in medicine to be acquianted with critical parameters to get accuracy results with operation room equipment.

Equipment for inspection of austenitic stainless steel pipe welds

International Nuclear Information System (INIS)

Boehmer, W.D.; Horn, J.E.

1979-01-01

A computer controlled ultrasonic scanning system and a data acquisition and analysis system have been developed to perform the inservice inspection of welds in stainless steel sodium piping in the Fast Flux Test Facility. The scanning equipment consists of a six axis motion mechanism and control system which allows full articulation of an ultrasonic transducer as it follows the circumferential pipe welds. The data acquisition and analysis system consists of high speed ultrasonic waveform digitizing equipment, dedicated processors to perform on-line analysis, and data storage and display equipment

Radiation protection type testing and licensing of diagnostic X-ray equipment in the GDR

International Nuclear Information System (INIS)

Taschner, P.; Poulheim, K.F.; Feldheim, W.

1987-01-01

The results of more than 10 years experience in type testing and type licensing of diagnostic X-ray equipment with respect to meeting radiation protection requirements as well as the implications for the conduct of these procedures resulting from the introduction of new radiation protection legislation in 1983 and 1984, are described. At present an updated version of the 'Regulation of 16 December 1977 concerning radiation protection type testing and licensing of sealed radiation sources and equipment emitting ionizing radiation' is being prepared. (author)

77 FR 35310 - Revisions to the Export Administration Regulations (EAR): Control of Military Training Equipment...

Science.gov (United States)

2012-06-13

... for foreign made ``military commodities'' that incorporate more than 10% U.S.-origin ``600 series... Military Training Equipment and Related Items the President Determines No Longer Warrant Control Under the... longer warrant control under Category IX (Military Training Equipment and Training) of the United States...

Sipping machine control system new design to perform integrity of nuclear fuel test in Cofrentes power plant

Energy Technology Data Exchange (ETDEWEB)

Palomo, M., E-mail: mpalomo@iqn.upv.es [Departamento de Ingenieria Quimica y Nuclear. Universidad Politecnica de Valencia (Spain); Urrea, M., E-mail: Matias.urrea@iberdrola.es [C.N.Cofrentes - Iberdrola Generacion S.A., Cofrentes, Valencia (Spain); Curiel, M., E-mail: m.curiel@lainsa.com [LAINSA Grupo Dominguis, Valencia (Spain); Arnaldos, A., E-mail: a.arnaldos@titaniast.com [TITANIA Servicios Tecnologicos SL, Grupo Dominguis, Valencia (Spain)

2011-07-01

This paper we present is related to SIPPING machine control system new design to perform integrity of nuclear fuel test. This test is a non destructive technique used for evaluating the radiated nuclear fuel coating structural integrity. It is based on the radioactive emission detection of fission elements in the reactor cooling system, using the fuel inspection equipment (SIPPING). SIPPING equipment consists of one simultaneous test bell-shaped vessel of eight fuel elements, and another one for individual element test, a control workstation and some accessories (cables, thermocouples, hoses). SIPPING inspection is carried out by means of fuel element vessel. Through air injection, water flows around the element and heat evacuation is reduced, so fuel elements temperature increases. Those elements with faults shall expelled fission components dissolved in water and/or as a gas component. The project aim is the SIPPING system control design and software based on LabVIEW, for control, monitoring and documentation of the SIPPING Test. This project shall give a major functionality to the system and, at the same time, shall facilitate the user a friendlier and interactive environment allowing: to substitute the present work platform with a real-time electronic system based on cRIO and a control software ad-hoc designed for SIPPING system; to equip new system of a major redundancy for data storage, minimising loss probability of the same. (author)

Sipping machine control system new design to perform integrity of nuclear fuel test in Cofrentes power plant

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. [ISIRYM, Universidad Politecnica de Valencia, Camino de Vera s/n, Valencia (Spain); Urrea, M. [Iberdrola Generacion S. A., Central Nuclear Cofrentes, Carretera Almansa Requena s/n, 04662 Cofrentes, Valencia (Spain); Vaquer, J., 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 related to Sipping machine control system new design to perform integrity of nuclear fuel test. This test is a non destructive technique used for evaluating the radiated nuclear fuel coating structural integrity. It is based on the radioactive emission detection of fission elements in the reactor cooling system, using the fuel inspection equipment Sipping. The equipment consists of one simultaneous test bell-shaped vessel of eight fuel elements, and another one for individual element test, a control workstation and some accessories (cables, thermocouples, hoses). Sipping inspection is carried out by means of fuel element vessel. Through air injection, water flows around the element and heat evacuation is reduced, so fuel elements temperature increases. Those elements with faults shall expelled fission components dissolved in water and/or as a gas component. The project aim is the Sipping system control design and software based on LabVIEWTM, for control, monitoring and documentation of the Sipping test. This project shall give a major functionality to the system and, at the same time, shall facilitate the user a friendlier and interactive environment allowing: 1) To substitute the present work platform with a real-time electronic system based on cRIO and a control software ad-hoc designed for Sipping system. 2) To equip new system of a major redundancy for data storage, minimising loss probability of the same. (Author)

Sipping machine control system new design to perform integrity of nuclear fuel test in Cofrentes power plant

International Nuclear Information System (INIS)

Curiel, M.; Palomo, M. J.; Urrea, M.; Vaquer, J.

2010-10-01

This paper related to Sipping machine control system new design to perform integrity of nuclear fuel test. This test is a non destructive technique used for evaluating the radiated nuclear fuel coating structural integrity. It is based on the radioactive emission detection of fission elements in the reactor cooling system, using the fuel inspection equipment Sipping. The equipment consists of one simultaneous test bell-shaped vessel of eight fuel elements, and another one for individual element test, a control workstation and some accessories (cables, thermocouples, hoses). Sipping inspection is carried out by means of fuel element vessel. Through air injection, water flows around the element and heat evacuation is reduced, so fuel elements temperature increases. Those elements with faults shall expelled fission components dissolved in water and/or as a gas component. The project aim is the Sipping system control design and software based on LabVIEWTM, for control, monitoring and documentation of the Sipping test. This project shall give a major functionality to the system and, at the same time, shall facilitate the user a friendlier and interactive environment allowing: 1) To substitute the present work platform with a real-time electronic system based on cRIO and a control software ad-hoc designed for Sipping system. 2) To equip new system of a major redundancy for data storage, minimising loss probability of the same. (Author)

Project B610 process control configuration acceptance test report

International Nuclear Information System (INIS)

Silvan, G.R.

1995-01-01

The purpose of this test is to verify the Westinghouse configuration of the MICON A/S Distributed Control System for project B610. The following will be verified: (1) proper assignment and operation of all field inputs to and outputs from the MICON Termination panels; (2) proper operation of all display data on the operators' console; (3) proper operation of all required alarms; and (4) proper operation of all required interlocks. This test only verifies the proper operation of the Westinghouse control configuration (or program). It will not be responsible for verifying proper operation of the MICON hardware or operating software. Neither does it test any of the B610 instrument. The MICON hardware and software has been tested as part of the equipment procurement. Instrumentation and wiring installed under project B620 will be tested under a separate functional test. In some cases, precise transmitter ranges, alarm setpoints, and controller tuning parameters are not available at this time. Therefore, approximate values are used during the test. This should not affect the proper operation of the configuration or the validity of this test. Final values will be assigned during operability testing

Seismic test qualification of electrical equipment - testing methods in use to EDF

International Nuclear Information System (INIS)

Fabries, R.

1981-01-01

At the beginning, for the 900 MW Power Plant level, the testing method in application used the single axis test by sine beat of 10 cycles according to the specifications of the guide IEEE 344-71. When the french guide UTEC 20-420 came into force we have had to define another testing method (EDF standard: HN20 E52) which utilize the single-axis test either by a sine beat of 5-cycles or by a synthetized time history. We present here the mains criterions allowing to justify: -The single-axis test. The single frequency wave (when the Initial Response Spectrum (IRS) present a narrow band). The use of one sine beat of 5-cycles or one synthetized time history. The need of taking into account the high stress level. This oligocyclic stress fatigue explains why one beat of 5-cycles may be as severe as one time history of 20 seconds (with the same level of strong response spectrum). Then, we conclude that the durating of the testing wave applied to the equipment shall be considered as a relative parameter only. The weight of the SSE tests by respect to the OBE tests. The precautions to take in order to: generate and check accurately the synthetized time history, choice the test frequencies when the sine beat is used. (orig./HP)

Automated Risk Control in Medical Imaging Equipment Management Using Cloud Application

Directory of Open Access Journals (Sweden)

Sally M. Ghanem

2018-01-01

Full Text Available Medical imaging equipment (MIE is the baseline of providing patient diagnosis in healthcare facilities. However, that type of equipment poses high risk for patients, operators, and environment in terms of technology and application. Considering risk management in MIE management is rarely covered in literature. The study proposes a methodology that controls risks associated with MIE management. The methodology is based on proposing a set of key performance indicators (KPIs that lead to identify a set of undesired events (UDEs, and through a risk matrix, a risk level is evaluated. By using cloud computing software, risks could be controlled to be manageable. The methodology was verified by using a data set of 204 pieces of MIE along 104 hospitals, which belong to Egyptian Ministry of Health. Results point to appropriateness of proposed KPIs and UDEs in risk evaluation and control. Thus, the study reveals that optimizing risks taking into account the costs has an impact on risk control of MIE management.

Enhancing reliability of ultrasonic testing of welds of nuclear power plant equipment

International Nuclear Information System (INIS)

Shcherbinskij, V.G.

1981-01-01

Results of investigation of factors influencing the reliability of manual ultrasonic testing of welded joints and weld deposited metal power-generating equipment are presented. Recommendations on the enhancing of reliability are given [ru

Noise control of radiological monitoring equipment

International Nuclear Information System (INIS)

Rubick, R.D.; Stevens, W.W.; Burke, L.L.

1998-01-01

Although vacuum pumps on continuous air monitors (CAMs) do not produce noise levels above regulatory limits, engineering controls were used to establish a safer work environment. Operations performed in areas where CAMs are located are highly specialized and require precision work when handling nuclear materials, heavy metals, and inert gases. Traditional methods for controlling noise such as enclosing or isolating the source and the use of personal protection equipment were evaluated. An innovative solution was found by retrofitting CAMs with air powered multistage ejectors pumps. By allowing the air to expand in several chambers to create a vacuum, one can eliminate the noise hazard altogether. In facilities with adequate pressurized air, use of these improved ejector pumps may be a cost-effective replacement for noisy vacuum pumps. A workplace designed or engineered with noise levels as low as possible or as close to background adds to increased concentration, attention to detail, and increased production

Dynamic characteristics of lead rubber bearings with dynamic two-dimensional test equipment

International Nuclear Information System (INIS)

Ohtori, Y.; Ishida, K.; Mazda, T.

1994-01-01

Although studies have previously been done on the static mechanical properties of lead rubber bearings, this study aims to grasp the dynamic characteristics of lead rubber bearings from experimental results, using two-dimensional dynamic test equipment which is designed to grasp in detail such dynamic characteristics as deformation capacity and proof stress. This paper describes the results from three types of tests: (1) dynamic mechanical properties tests, (2) cyclic loading tests, and (3) dynamic ultimate tests. Through these tests, it was confirmed that the dynamic characteristics of lead rubber bearings are independent of strain rate

Implementation of a quality control program of the equipment of the nuclear medicine services in Chile

International Nuclear Information System (INIS)

Astudillo, R.; Diaz, G.; Ferreira, A.; Garcia, M.; Hermosilla, A.; Pacheco, F.; Vasquez, M.; Coca, M.

2014-08-01

Now days in Chile there are more of 43 Nuclear Medicine centers; most of them have gamma cameras in order to study physiological process in diagnostic and treatment of patients pathologies. This requires having the equipment in optimal operating condition and it is ensured with quality control programs that are based on a series of tests relating to protocols, such as TECDOC-602 y AAPM No.6. Planar test often applied in gamma cameras including: spatial resolution, spatial linearity, sensitivity and uniformity. SPECT tests consider: tomography uniformity, rotation center tomography resolution and total performance. The tests in dose calibrator are: background measurement, accuracy, precision, linearity and reproducibility. The tests above require the use of radioactive sources and specific simulators patterns or phantom based on international standards such as The National Electrical Manufacturers Association (Nema), International Atomic Energy Agency (IAEA) and The American Association of Medical Physics (AAPM). In this work we carried out several tests of quality control in a Nuclear Medicine Center of Temuco and we propose to implement the applied methodology in others similar Chilean centers. (author)

The Variation Test and Extraction Equipment to Optimum Asphalt by Using Gasoline Solvent

Science.gov (United States)

Soehardi, Fitridawati

2017-12-01

Based on the Binamarga Specification 2010 at third revision, the extraction test should be carried out using the specimen from the loose asphalt mixture extracted from the back of the finisher bitumen machine. The purpose of this research is to find out the result of pretest and posttest extraction asphalt content. The Extraction test using two equipment, they are Soklet and Centrifuge. The specimens was used AMP, Asphalt Finisher and Core, which involved gasoline solvent. Based on the asphalt level extraction test results, the appropriate equipment was used centrifuge with the level accuracy as requirement of Binamarga Specification 2010 at third revision and the level of ease used as equipment in the field study. The asphalt content obtained for AMP 5,51%, Asphalt Finisher5,46% and Core 5.34%. As for the socket asphalt content obtained is AMP 5.55%, Asphalt Finisher 5.50% and Core core 5. 41%. The extract test value of asphalt content decreased, so it can be formulated KA JMF value of Job mix used was 5.56% with the tolerance given according to Binamarga Specification 2010 at third revision is ± 0.30%. In accordance with the results obtained then the results of a centrifuge tool that matches and meets the requirements of time, accuracy of results and economic value.

Controller recovery from equipment failures in air traffic control: A framework for the quantitative assessment of the recovery context

International Nuclear Information System (INIS)

Subotic, Branka; Schuster, Wolfgang; Majumdar, Arnab; Ochieng, Washington

2014-01-01

Air Traffic Control (ATC) involves a complex interaction of human operators (primarily air traffic controllers), equipment and procedures. On the rare occasions when equipment malfunctions, controllers play a crucial role in the recovery process of the ATC system for continued safe operation. Research on human performance in other safety critical industries using human reliability assessment techniques has shown that the context in which recovery from failures takes place has a significant influence on the outcome of the process. This paper investigates the importance of context in which air traffic controller recovery from equipment failures takes place, defining it in terms of 20 Recovery Influencing Factors (RIFs). The RIFs are used to develop a novel approach for the quantitative assessment of the recovery context based on a metric referred to as the Recovery Context Indicator (RCI). The method is validated by a series of simulation exercises conducted at a specific ATC Centre. The proposed method is useful to assess recovery enhancement approaches within ATC centres

Equipment design for reliability testing of protection system

International Nuclear Information System (INIS)

Situmorang, Johnny; Tjahjono, H.; Santosa, A. Z.; Tjahjani, S.DT.; Ismu, P.H; Haryanto, D.; Mulyanto, D.; Kusmono, S

1999-01-01

The equipment for reliability testing of cable of protection system has been designed as a a furnace with the electric heater have a 4 kW power, and need time 10 minute to reach the designed maximum temperature 3000C. The dimension of furnace is 800 mm diameter and 2000 mm length is isolated use rockwool isolator and coated by aluminium. For the designed maximum temperature the surface temperature is 78 0c. Assemble of specimens is arranged horizontally in the furnace. The failure criteria will be defined based on the behaviour of the load circuit in each line of cable specimens

Instantaneous response spectrum in seismic testing of nuclear power plant equipment

International Nuclear Information System (INIS)

Morrone, A.

1977-01-01

Seismic response spectra, as used in seismic analyses, give the maximum responses of single degree of freedom oscillators without consideration of the different time in the seismic time history at which each of the maximum responses occur. For response spectrum seismic analysis, the use of time-independent maximum responses is appropriate. The time dependece is considered in a statistical manner, for multi-degree of freedom systems, usually by combining the modal effects by the square root of the sum of the squares. For seismic testing of electrical equipment. IEEE Std. 344-1975 makes use of the response spectrum to define the input motion of the shake table. One of the basic requirements is that the test response spectrum (TRS) that is, the response spectrum produced by the shake table motion, should envelop the required response spectrum (RRS) calculated from the building analysis at the support point of the equipment being tested. This paper presents the concept of instantaneous response spectrum (IRS) as the response of single degree of freedom oscillators at a particular time. It demonstrates that a shake table random motion whose standard TRS envelops the RRS does not necessarily satisfy the enveloping requirement instantaneously. (Auth.)

Simulation of ultra-long term behavior in HLW near-field by centrifugal model test. Part 1. Development of centrifugal equipment and centrifuge model test method

International Nuclear Information System (INIS)

Nishimoto, Soshi; Okada, Tetsuji; Sawada, Masataka

2011-01-01

The objective of this paper is to develop a centrifugal equipment which can continuously be run for a long time and a model test method in order to evaluate a long term behavior which is a coupled thermo-hydro-mechanical processes in the high level wastes geological disposal repository and the neighborhood (called 'near-field'). The centrifugal equipment of CRIEPI, 'CENTURY5000-THM', developed in the present study is able to run continuously up to six months. Therefore, a long term behavior in the near-field can be simulated in a short term, for instance, the behavior for 5000 equivalent years can be simulated in six months by centrifugalizing 100 G using a 1/100 size model. We carried out a test using a nylon specimen in a centrifugal force field of 30 G and confirmed the operations of CENTURY5000-THM, control and measurement for 11 days. As the results, it was able to control the stress in the pressure vessel and measure the values of strain, temperature and pressure. And, as a result of scanning the small model of near-field including the metal overpack, bentonite buffer and rock by a medical X-rays CT scanner, the internal structure of the model was able to be evaluated when the metal artifact was reduced. From these results, the evaluation for a long term behavior of a disposal repository by the method of centrifugal model test became possible. (author)

Photoelectric equipment type MFS-7 for analyzing oils

International Nuclear Information System (INIS)

Orlova, S.A.; Fridman, M.G.; Kholosha, T.V.; Ezhoda, G.D.; Nechitailov, V.V.

1987-01-01

The authors describe the equipment type MFS-7 which is intended for analyzing used oils for the wear products of motors. The difference between type MFS-7 and its predecessors lies in the application of computer techniques to control the equipment and process the output data; and in the design of the sample container, which allows for two methods of introducing the sample into the discharge. The photoelectric equipment consists of an excitation spectrum source IVS-28, having an ac arc mode and 1.v. spark, a polychoromator, a special sample holder for analyzing liquid samples, an electronic recording apparatus with digital voltmeter type ERU-18 and control computer system Spectr 2.2 based on a minicomputer with its own printer. The type MFS-7 equipment has been tested and put into mass production

Flight Tests of a Ministick Controller in an F/A-18 Airplane

Science.gov (United States)

Stoliker, Patrick C.; Carter, John

2003-01-01

In March of 1999, five pilots performed flight tests to evaluate the handling qualities of an F/A-18 research airplane equipped with a small-displacement center stick (ministick) controller that had been developed for the JAS 39 Gripen airplane (a fighter/attack/ reconnaissance airplane used by the Swedish air force). For these tests, the ministick was installed in the aft cockpit (see figure) and production support flight control computers (PSFCCs) were used as interfaces between the controller hardware and the standard F/A-18 flight-control laws. The primary objective of the flight tests was to assess any changes in handling qualities of the F/A-18 airplane attributable to the mechanical characteristics of the ministick. The secondary objective was to demonstrate the capability of the PSFCCs to support flight-test experiments.

The research on information security technology for the industrial control system of special equipment

International Nuclear Information System (INIS)

Chen Ligang; Liu Hongye; Zhang Wei; Sun Jianying; Lan Peng; Dai Sidan

2014-01-01

With the rapid development of information technology in enterprise application, industrial control network and management network is becoming more and more closely linked. Development and application of special equipment control system from the traditional industrial control system, not considered when designing communication security problem mainly, therefore, the industrial control system opened at the same time, isolation control system and the outside was weakened, the safety problems of industrial control system had become more and more serious. The practical application combined with the special equipment control system, analysis and elaboration in view of security problems for the control network, also, provide appropriate security solutions for professional characteristics of industrial control network, design on process control system specially, provide security partition protection scheme, in order to improve security ability of industrial control system information. (authors)

A Study on Performance and Safety Tests of Electrosurgical Equipment

Directory of Open Access Journals (Sweden)

Tavakoli Golpaygani A.

2016-09-01

Full Text Available Introduction: Modern medicine employs a wide variety of instruments with different physiological effects and measurements. Periodic verifications are routinely used in legal metrology for industrial measuring instruments. The correct operation of electrosurgical generators is essential to ensure patient’s safety and management of the risks associated with the use of high and low frequency electrical currents on human body. Material and Methods: The metrological reliability of 20 electrosurgical equipment in six hospitals (3 private and 3 public was evaluated in one of the provinces of Iran according to international and national standards. Results: The achieved results show that HF leakage current of ground-referenced generators are more than isolated generators and the power analysis of only eight units delivered acceptable output values and the precision in the output power measurements was low. Conclusion: Results indicate a need for new and severe regulations on periodic performance verifications and medical equipment quality control program especially in high risk instruments. It is also necessary to provide training courses for operating staff in the field of meterology in medicine to be acquianted with critical parameters to get accuracy results with operation room equipment.

Development of a model and test equipment for cold flow tests at 500 atm of small nuclear light bulb configurations

Science.gov (United States)

Jaminet, J. F.

1972-01-01

A model and test equipment were developed and cold-flow-tested at greater than 500 atm in preparation for future high-pressure rf plasma experiments and in-reactor tests with small nuclear light bulb configurations. With minor exceptions, the model chamber is similar in design and dimensions to a proposed in-reactor geometry for tests with fissioning uranium plasmas in the nuclear furnace. The model and the equipment were designed for use with the UARL 1.2-MW rf induction heater in tests with rf plasmas at pressures up to 500 atm. A series of cold-flow tests of the model was then conducted at pressures up to about 510 atm. At 504 atm, the flow rates of argon and cooling water were 3.35 liter/sec (STP) and 26 gal/min, respectively. It was demonstrated that the model is capable of being operated for extended periods at the 500-atm pressure level and is, therefore, ready for use in initial high-pressure rf plasma experiments.

A study on enforcement effects of radiation safety control regulations for diagnostic X-ray equipment

International Nuclear Information System (INIS)

Sung, Mo IL; Park, Myeong Hwan; Kwon, Duk Moon; Lee, Joon IL

1999-01-01

The purposes of this study are to analyze the realities after enforcements of safety control regulations for diagnostic X-ray equipment and to suggest means for an improvement of low radiation safety control. A questionnaire survey for medical radiologic technologists was carried out to determine enforcement effects of the safety control regulations. The results of analysis from the survey are as follows. That is, most of he respondents realized the importance of the radiation safety control system, but about a half of them revealed that regulations were not well observed in accordance with their purposes. Only 43.9 percent of the respondents took an active part in quality control of radiation. And responsibility, sex, age, and knowledge for safety control were important indicators for observations of the regulations. Training for the safety control regulations are needed to ensure safety control and proper usage of diagnostic X-ray equipment. And management of organizations using diagnostic X-ray equipment have to understand and stress the importance of radiation safety control system. (author)

Controlling the quality of replacement parts in nuclear station, class 1E equipment

International Nuclear Information System (INIS)

Pierson, R.K.; Clemons, R.W.

1984-01-01

Nuclear station owners have traditionally purchased replacement parts for Class 1E equipment from the original supplier of the equipment. By this method, part and equipment quality could be maintained. In recent years, however, this traditional source of parts has continuously declined as an increasing number of original equipment suppliers stop producing Class 1E equipment or no longer stock parts for older equipment. When replacement parts for Class 1E equipment are not obtainable from the original suppliers, equipment owners have created a variety of methods for assuring the quality of parts obtained from other sources. A standard that provides direction and guidance for maintaining the quality of Class 1E equipment when repaired with parts from alternate sources is, therefore, needed to assure the methods in use are satisfactory and to alert the equipment owners to additional acceptable methods. The standard has now been proposed. IEEE Standard P934 (June, 1983 Draft): ''Requirements for Replacement Parts for Class 1E Equipment in Nuclear Power Generating Stations'' (Ref-3) consist of an introductory section followed by sections on part selection, procurement, replacement (including inspections and tests), non-conforming conditions and records. The proposed standard also includes a non-mandatory appendix on acceptable procurement methods and a summary intended to assist the user in selecting a proper procurement method

The Design and Implementation of the Remote Centralized-Monitoring System of Well-Control Equipment Based on RFID Technique

Directory of Open Access Journals (Sweden)

Luo Bin

2017-01-01

Full Text Available At present, in domestic for the management of well control equipment continue to the traditional way of nameplates identifies and paper-based registration, there are many issues like the separation of data information of device, easy lose, difficult query, confused management and many other problems, which will make the problem device into the well field, and then resulting in well control runaway drilling accident. To solve the above problems, this paper put forward to the integrated remote centralized-monitoring management mode of the well-control equipment. Taking the advantages of IOT technology, adopting the RFID technology, and combining with the remote transmission, this paper designs the remote centralized-monitoring system of well-control equipment based on RFID, which realizes the intelligent management of well-control equipment and meets the actual demand of the well-control equipment safe use and timely scheduling, and it has the ability of field application.

Control room inleakage testing using tracer gases at Zion Generating station

International Nuclear Information System (INIS)

Lagus, P.L.; Brown, J.H.; Dubois, L.J.; Fleming, K.M.

1993-01-01

In order to assess the amount of air inleakage into the Control Room Envelope at Zion Generating Station (ZGS), a series of tracer gas tests using sulfur hexafluoride (SF 6 ) were performed on the Control Room ventilation system (PV system) and the Computer Room/Miscellaneous Area ventilation system (OV system) during February, 1991. Two redundant trains, denoted A and B comprise the PV system. Inleakage was measured for each train. An OV supply duct passes through the Control Room Envelope. Leakage from this duct into the Control Room would constitute air leakage into the Control room Envelope and hence any potential leakage had to be quantified. Each test attempted to measure the contribution (if any) of a particular section of PV return duct or OV supply duct to the total air inleakage into the Control Room. This paper reviews the tracer gas tests. Described here are the control room inleakage testing, HVAC equipment room duct inleakage, purge plenum inleakage, OV duct leakage into the control room envelope, vestibule PV return inleakage, TSC duct inleakage, and cable spreading room inleakage. Conclusions from the testing are presented. 5 refs., 4 figs., 7 tabs

78 FR 63410 - Energy Conservation Program for Consumer Products: Test Procedures for Direct Heating Equipment...

Science.gov (United States)

2013-10-24

... test procedures for direct heating equipment and pool heaters established under the Energy Policy and... U.S.C. 6293(e)(2)) The current energy conservation standards for direct heating equipment and pool... DEPARTMENT OF ENERGY 10 CFR Part 430 [Docket Number EERE-2013-BT-TP-0004] RIN 1904-AC94 Energy...

Development of a telerobotic system for handling contaminated process equipment

International Nuclear Information System (INIS)

Fisher, J.J.; Ward, C.R.; Schuler, T.F.

1987-01-01

E. I. du Pont de Nemours and Company is evaluating a unique eight-degree-of-freedom Telerobot manipulator to perform size-reduction and material handling operations on contaminated process equipment at the Savannah River Plant (SRP). The Telerobot will be installed in the proposed Transuranic (TRU) Waste Processing Facility, which is scheduled to be operational by 1990. A full-scale prototype Telerobot, manufactured by GCA Corporation, St. Paul, MN is being tested with other process equipment in the Components Test Facility at the Savannah River Laboratory (SRL). All telerobotic operations required in the TRU Waste Facility such as crate unpacking, equipment dismantling, material size-reduction, and selected maintenance operations are being tested. This paper discusses the major mechanical and control features of the Telerobot system. Several system enhancements were added by SRL, including a new quick-hand-change coupling and expanded software control functions. The new software enables a system operator to perform both teleoperated and automatic tasks through several operating modes. These enhancements, as well as future mechanical, control system, and software features, are reviewed

Design and construction of stepper motor controller for brachy-therapy equipment

International Nuclear Information System (INIS)

Ahmad Rifai; Usep Setia Gunawan; Indarzah Masbatin Putra

2011-01-01

Based on a microcontroller, a stepper motor controller for brachy-therapy equipment has been designed and prototyped. The embedded control program routine and its other associated routines enable the microcontroller to generate required pulses via external commands for stepper motor based position control. The controller receives ASCII text command via a serial port. The constructed algorithm implements the widely used method that allows motor to rotate in three phases, i.e: acceleration, constant speed, and deceleration. (author)

A Study of Equipment Accuracy and Test Precision in Dual Energy X-ray Absorptiometry

International Nuclear Information System (INIS)

Dong, Kyung Rae; Kim, Ho Sung; Jung, Woon Kwan

2008-01-01

=0.96), P2 - (spine: 0.002±0.018 g/cm 2 , %CV=0.55, Femur: 0.001±0.013 g/cm 2 , %CV=0.48) in Group 3. The average error±2SD, %CV, and r value was spine : 0.006±0.024 g/cm 2 , %CV=0.86, r=0.995, Femur: 0±0.014 g/cm 2 , %CV=0.54, r=0.998 in Group 4. Both LUNAR ASP CV% and HOLOGIC Spine Phantom are included in the normal range of error of ±2% defined in ISCD. BMD measurement keeps a relatively constant value, so showing excellent repeatability. The Phantom has homogeneous characteristics, but it has limitations to reflect the clinical part including variations in patient's body weight or body fat. As a result, it is believed that quality control using Phantom will be useful to check mis-calibration of the equipment used. A value measured a patient two times with one equipment, and that of double-crossed two equipment are all included within 2SD Value in the Bland - Altman Graph compared results of Group 3 with Group 4. The r value of 0.99 or higher in Linear regression analysis(Regression Analysis) indicated high precision and correlation. Therefore, it revealed that two compatible equipment did not affect in tracking the patients. Regular testing equipment and capabilities of a tester, then appropriate calibration will have to be achieved in order to calculate confidential BMD.

A Study of Equipment Accuracy and Test Precision in Dual Energy X-ray Absorptiometry

Energy Technology Data Exchange (ETDEWEB)

Dong, Kyung Rae [Dept. of Radiological Technology, Gwangju Health College, Gwangju (Korea, Republic of); Kim, Ho Sung [Dept. of Nuclear Medicine, Asan Medical Center, Seoul (Korea, Republic of); Jung, Woon Kwan [Dept. of Nuclear Energy Technology, Chosun University, Gwangju (Korea, Republic of)

2008-03-15

.94, Femur: 0.001{+-}0.019 g/cm{sup 2}, %CV=0.96), P2 - (spine: 0.002{+-}0.018 g/cm{sup 2}, %CV=0.55, Femur: 0.001{+-}0.013 g/cm{sup 2}, %CV=0.48) in Group 3. The average error{+-}2SD, %CV, and r value was spine : 0.006{+-}0.024 g/cm{sup 2}, %CV=0.86, r=0.995, Femur: 0{+-}0.014 g/cm{sup 2}, %CV=0.54, r=0.998 in Group 4. Both LUNAR ASP CV% and HOLOGIC Spine Phantom are included in the normal range of error of {+-}2% defined in ISCD. BMD measurement keeps a relatively constant value, so showing excellent repeatability. The Phantom has homogeneous characteristics, but it has limitations to reflect the clinical part including variations in patient's body weight or body fat. As a result, it is believed that quality control using Phantom will be useful to check mis-calibration of the equipment used. A value measured a patient two times with one equipment, and that of double-crossed two equipment are all included within 2SD Value in the Bland - Altman Graph compared results of Group 3 with Group 4. The r value of 0.99 or higher in Linear regression analysis(Regression Analysis) indicated high precision and correlation. Therefore, it revealed that two compatible equipment did not affect in tracking the patients. Regular testing equipment and capabilities of a tester, then appropriate calibration will have to be achieved in order to calculate confidential BMD.

An open software system based on X Windows for process control and equipment monitoring

International Nuclear Information System (INIS)

Aimar, A.; Carlier, E.; Mertens, V.

1992-01-01

The construction and application of a configurable open software system for process control and equipment monitoring can speed up and simplify the development and maintenance of equipment specific software as compared to individual solutions. The present paper reports the status of such an approach for the distributed control systems of SPS and LEP beam transfer components, based on X Windows and the OSF/Motif tool kit and applying data modeling and software engineering methods. (author)

242A Distributed Control System Year 2000 Acceptance Test Report

Energy Technology Data Exchange (ETDEWEB)

TEATS, M.C.

1999-08-31

This report documents acceptance test results for the 242-A Evaporator distributive control system upgrade to D/3 version 9.0-2 for year 2000 compliance. This report documents the test results obtained by acceptance testing as directed by procedure HNF-2695. This verification procedure will document the initial testing and evaluation of the potential 242-A Distributed Control System (DCS) operating difficulties across the year 2000 boundary and the calendar adjustments needed for the leap year. Baseline system performance data will be recorded using current, as-is operating system software. Data will also be collected for operating system software that has been modified to correct year 2000 problems. This verification procedure is intended to be generic such that it may be performed on any D/3{trademark} (GSE Process Solutions, Inc.) distributed control system that runs with the VMSTM (Digital Equipment Corporation) operating system. This test may be run on simulation or production systems depending upon facility status. On production systems, DCS outages will occur nine times throughout performance of the test. These outages are expected to last about 10 minutes each.

242A Distributed Control System Year 2000 Acceptance Test Report

International Nuclear Information System (INIS)

TEATS, M.C.

1999-01-01

This report documents acceptance test results for the 242-A Evaporator distributive control system upgrade to D/3 version 9.0-2 for year 2000 compliance. This report documents the test results obtained by acceptance testing as directed by procedure HNF-2695. This verification procedure will document the initial testing and evaluation of the potential 242-A Distributed Control System (DCS) operating difficulties across the year 2000 boundary and the calendar adjustments needed for the leap year. Baseline system performance data will be recorded using current, as-is operating system software. Data will also be collected for operating system software that has been modified to correct year 2000 problems. This verification procedure is intended to be generic such that it may be performed on any D/3(trademark) (GSE Process Solutions, Inc.) distributed control system that runs with the VMSTM (Digital Equipment Corporation) operating system. This test may be run on simulation or production systems depending upon facility status. On production systems, DCS outages will occur nine times throughout performance of the test. These outages are expected to last about 10 minutes each

Application of owner technical management in hydraulic machinery and electrical equipment investment target control

International Nuclear Information System (INIS)

Luo, H

2012-01-01

Using technical means in investment target control is an effective method to improve investment benefit of a construction project. Take the practice of construction and management in hydropower station as an example, the investment and management need of the owner is put forward through the investment target decision-making process of electromechanical equipment. Owner technical management in the specific application measures and effects of investment target control was discussed in the paper, and the revelation in investment target control application of owner technical management was also summarized. The paper is aimed to provide a useful reference for the investment target control work in the construction of electromechanical equipment.

SPS/LEP beam transfer equipment control using industrial automation components

International Nuclear Information System (INIS)

Aimar, A.; Berard, G.; Bretin, J.L.; Carlier, E.; Dieperink, J.H.; Laffin, M.; Mertens, V.; Verhagen, H.

1992-01-01

Several control systems for SPS and LEP beam transfer equipment have to be commissioned in the near future. Tools for fast software development, easy maintenance and modifications, compliance with industrial standards, and independence of specific suppliers are considered to be essential. A large fraction of the systems can be realized using off-the-shelf industrial automation components like industrial I/O systems, programmable logic controllers, or diskless PCs. Specific electronics built up in G-64 can be integrated. Diskless systems running UNIX and X Windows are foreseen as process controllers and local access media. (author)

Tests to control the power distribution in the IRT-2,000 reactor

International Nuclear Information System (INIS)

Filipcuk, E.V.; Potapenko, P.T.; Krjukov, A.P.; Trofimov, A.P.; Kosilov, A.N.; Nebojan, V.T.; Timochin, E.S.

1976-01-01

Results of the investigations of a few structures of such control systems carried out with the help of the IRT 2,000 MIFI reactor in the years 1973/74 are presented in the present work. Within the framework of this study, the successful test of using the transmitter of the direct loading in equipment to control the neutron field was carried out. (orig./TK) [de

The Tanzania experience: clinical laboratory testing harmonization and equipment standardization at different levels of a tiered health laboratory system.

Science.gov (United States)

Massambu, Charles; Mwangi, Christina

2009-06-01

The rapid scale-up of the care and treatment programs in Tanzania during the preceding 4 years has greatly increased the demand for quality laboratory services for diagnosis of HIV and monitoring patients during antiretroviral therapy. Laboratory services were not in a position to cope with this demand owing to poor infrastructure, lack of human resources, erratic and/or lack of reagent supply and commodities, and slow manual technologies. With the limited human resources in the laboratory and the need for scaling up the care and treatment program, it became necessary to install automated equipment and train personnel for the increased volume of testing and new tests across all laboratory levels. With the numerous partners procuring equipment, the possibility of a multitude of equipment platforms with attendant challenges for procurement of reagents, maintenance of equipment, and quality assurance arose. Tanzania, therefore, had to harmonize laboratory tests and standardize laboratory equipment at different levels of the laboratory network. The process of harmonization of tests and standardization of equipment included assessment of laboratories, review of guidelines, development of a national laboratory operational plan, and stakeholder advocacy. This document outlines this process.

Quality control for dental X-rays equipment and film developers

International Nuclear Information System (INIS)

Pomares C, Martin

1998-01-01

Quality control in five dental X-ray equipments, film and film developers was done. It was for evaluating the radiologic practices in the odontologic services too. This work was made based on international standards, the results will be used for future works in quality assurance in dental radiology

Technical manual: operation and equipment instructions for in situ impulse test

International Nuclear Information System (INIS)

1979-11-01

This manual describes the test equipment and procedures for a new field test which determines the shear modulus of a soil deposit at strain levels equivalent to those experienced during actual earthquakes. Results from this test are typically used as input parameters to response analyses for evaluating local soil effects during earthquake shaking. The test employs a cross-hole wave propagation procedure with velocity transducers located in closely spaced adjacent borings. Clear, consistent, and repeatable data in all types of soil and a method of data reduction different from conventional geophysical first arrival techniques are unique aspects of this new test. In addition to describing the principles of the test and data reduction procedures, major discussions of the field procedures are also included. Detailed drilling and testing information is provided both for planning and executing a test program

ENGINEERING DESIGN OPTIMIZATION OF HEEL TESTING EQUIPMENT IN THE EXPERIMENTAL VALIDATION OF SAFE WALKING

Directory of Open Access Journals (Sweden)

Cristiano Fragassa

2017-06-01

Full Text Available Experimental test methods for the evaluation of the resistance of heels of ladies' shoes in the case of impact loads are fully defined by International Organization for Standardization (ISO procedures that indicate all the conditions of experiment. A first Standard (ISO 19553 specifies the test method for determining the strength of the heels in the case of single impact. The result offers a valuation of the liability to fail under the sporadic heavy blows. A second Standard (ISO 19556 details a method for testing the capability of heels of women' shoes to survive to the repetition of small impacts provoked by normal walking. These Standards strictly define the features for two different testing devices (with specific materials, geometries, weights, etc. and all the experimental procedures to be followed during tests. On the contrary, this paper describes the technical solutions adopted to design one single experimental device able to perform impact testing of heels in both conditions. Joining the accuracy of mechanic movements with the speed of an electronic control system, a new and flexible equipment for the complete characterization of heels respect to (single or fatigue impacts was developed. Moreover a new level of performances in experimental validation of heel resistance was introduced by the versatility of the user-defined software control programs, able to encode every complex time-depending cycle of impact loads. Dynamic simulations permitted to investigate the impacts on heel in different conditions of testing, optimizing the machine design. The complexity of real stresses on shoes during an ordinary walk and in other common situations (as going up and downstairs was considered for a proper dimensioning.

Testing of wet scrap recovery equipment for mixed oxide scrap reprocessing

International Nuclear Information System (INIS)

Demiter, J.A.; Klem, M.J.; Owen, T.J.

1984-08-01

The Wet Scrap Recovery (WSR) program was initiated at the Hanford Engineering Development Laboratory (HEDL) by Westinghouse Hanford Company in Richland, Washington to demonstrate fuel fabrication scrap recovery and reconversion to fuel grade oxide powder using the continuous coprecipitation-calcination (COPRECAL) conversion process. Advancements in process control equipment and instrumentation were also developed and demonstrated

A Method of Numerical Control Equipment Appearance Design Based on Product Identity

Science.gov (United States)

Zhu, Zhijuan; Zhou, Qi; Li, Bin; Visser, Steve

Research on numerical control (NC) equipment has been more and more abundant; however, there are few existing studies in the field of appearance design for NC equipments. This paper provided a method to generate new appearance design of NC equipments based on product identity (PI). For the purpose of providing guidelines to generate new concept of NC equipment design, this paper, therefore, took the DMG Company (a Germen NC equipment company) as a case, examined the total products of this company from two aspects: Product Image and Product Family. Task 1 was an evaluate task about the Product Image by using the semantic differential (SD) evaluation method; Task 2 was a study task about Product Family to find out features of the products and classify these features. During the Task 2, several features have been found out and summarized, and these features were classified into 3 different levels according to their frequency and importance. In the end, two appearance design samples have been generated based on the analysis above to prove the application of the research.

Quality control for the equipment of Nuclear medicine: experience of the H.U. de la Princesa; Control de calidad del equipamiento en Medicina Nuclear. Experiencia enel H.U. de la Princesa

Energy Technology Data Exchange (ETDEWEB)

Espana, M.L.; Gracia, A.; Prieto, C.; Lopez F, P. [Servicio de ProteccionRadiologica. Hospital Universitario de la Princesa C/ Diego de Leon 62, 28006Madrid (Spain)

1998-12-31

The quality control of the equipment used in a nuclear medicine service is a fundamental aspect in the Quality Assurance Program that in the present time is starting in our hospital. the objective of this work is to present the internal protocol used, its problematic associated with its starting, and the results obtained in the quality control as of the gamma camera as of the activimeter. In addition to the equipment own to the nuclear medicine service it has been used a Cs-137 source and puppets for several purposes. The results obtained demonstrated the stability of the controlled parameters which has led us to a restating of the established periodicities in our internal protocol, over all for some constancy tests. (Author)

Procedure for field axes measurement, beam indication adjustment, and figure of convergence determination within performance tests for radiation therapy equipment

Energy Technology Data Exchange (ETDEWEB)

Quast, U; Krause, K; Rassow, J [Essen Univ. (Gesamthochschule) (Germany, F.R.). Abt. fuer Klinische Strahlenphysik

1976-09-01

A routine measuring procedure for the verification of radiation field axes and figure of convergence within a spatial resolution of +- 0.5 mm is described. Measurements are done in two parallel planes in a certain distance before and behind the presumed isocentre. The used test arrangement permits rapid check and controlled adjustment of the alignment of beam or isocentre indicating devices for all isocentric radiation therapy equipment.

Investigation with automatic ultrasonic equipment to trace flaws in a large test piece, and experience gained in carrying out inspections

International Nuclear Information System (INIS)

Lindner, J.P.

1975-01-01

Based on the FRG codes providing guide lines for the Reactor Safety Commission regarding the size and location of flaws to be detected during in-service inspections, investigations were carried out into the possibility of detecting defects in thick-walled reactor pressure vessel components with the aid of ultrasonic inspection systems. A large test rig was used and, in a similar manner to the in-service inspections on a reactor, the tests were carried out with remote-controlled, automatically guided inspection equipment. For this purpose, a test specimen weighing about 10 tons was produced and provided with two weld seams having a large number of artificial defects. Essential parameters for the various reflectors in the test specimen were the size, location, angle and roughness or structure of the reflecting surfaces. As it is known that austenitic cladding has a considerable influence on flaw detection, the tests were undertaken first without cladding and then with cladding. A manipulator was designed for automatic remote-controlled inspection with which the inspection system travels on a meandering route over the area to be inspected. The inspection system employed was of the same type as the one used for baseline tests during external inspections of reactor vessel walls with parallel surfaces. Digital data collection was by a magnetic tape recorder designed to store both the data of the ultrasonic inspection system as well as the allied position data. The data stored on the tape are evaluated with electronic data processing programmes especially developed for this purpose. These programmes allow locally coherent indication patterns to be prepared, thus simplifying the interpretation of the data obtained. The author initially describes the equipment with the aid of which the studies were undertaken. A detailed discussion is then presented on the design of the test specimen and the inspection systems employed. Following this, the results obtained are explained and

Data center equipment location and monitoring system

DEFF Research Database (Denmark)

2011-01-01

A data center equipment location system includes both hardware and software to provide for location, monitoring, security and identification of servers and other equipment in equipment racks. The system provides a wired alternative to the wireless RFID tag system by using electronic ID tags...... connected to each piece of equipment, each electronic ID tag connected directly by wires to a equipment rack controller on the equipment rack. The equipment rack controllers then link over a local area network to a central control computer. The central control computer provides an operator interface......, and runs a software application program that communicates with the equipment rack controllers. The software application program of the central control computer stores IDs of the equipment rack controllers and each of its connected electronic ID tags in a database.; The software application program...

The qualification requirements for personnel carry out the testing for the pressure equipment materials

International Nuclear Information System (INIS)

Wojas, M.; Walczak, M.

2006-01-01

The article contains information about qualification requirements for personnel carry out the destructive and non-destructive testing for the pressure equipment materials based on the Directive 97/23/CE(PED). Competence laboratory carry out the testing. The responsibility lies with producer / employer. The producer / employer could elaborate the written practice procedure for qualification and certification testing personnel. (authors)

Handling and disposal of SP-100 ground test nuclear fuel and equipment

International Nuclear Information System (INIS)

Wilson, C.E.; Potter, J.D.; Hodgson, R.D.

1990-05-01

The post SP-100 reactor testing period will focus on defueling the reactor, packaging the various radioactive waste forms, and shipping this material to the appropriate locations. Remote-handling techniques will be developed to defuel the reactor. Packaging the spent fuel and activated reactor components is a challenge in itself. This paper presents an overview of the strategy, methods, and equipment that will be used during the closeout phase of nuclear testing

Handling and disposal of SP-100 ground test nuclear fuel and equipment

International Nuclear Information System (INIS)

Wilson, C.E.; Potter, J.D.; Hodgson, R.D.

1991-01-01

The post SP-100 reactor testing period will focus on defueling the reactor, packaging the various radiactive waste forms, and shipping this material to the appropriate locations. Remote-handling techniques will be developed to defuel the reactor. Packaging the spent fuel and activated reactor components is a challenge in itself. This paper presents an overview of the strategy, methods, and equipment that will be used during the closeout phase of nuclear testing

Routine quality control of high dose rate brachytherapy equipment

International Nuclear Information System (INIS)

Guzman Calcina, Carmen S.; Almeida, Adelaide de; Rocha, Jose R. Oliveira

2001-01-01

A Quality Assurance program should be installed also for High Dose Rate brachytherapy, in the order to achieve a correct dose administration to the patient and for the safety to those involved directly with the treatment. The work presented here has the following purposes: Analyze the types of equipment tests presented by the official protocols (TG40, TG56 e ARCAL XXX), evaluate the brachytherapy routine tests of protocols from various national and international radiotherapy services and compare the latter with those presented in the official protocols. As a result, we conclude the following: TG56 presents a higher number of tests when compared to the other official protocols and most of the tests presented by the analyzed services are present in TG56. A suggestion for a basic protocol is presented, emphasizing the periodicity and tolerance level of each of the tests. (author)

Design and construction of the Portable Industrial X-Ray Equipment

International Nuclear Information System (INIS)

Nguyen Phuc; Nguyen Van Si; Le Tien Quan; Trinh Anh Tuan; Nguyen Manh Hung; Trinh Dinh Tuong

2011-01-01

The main purposes of the project are the supporting to design and construction of the Portable Industrial X-Ray Equipment; with the accuracy ±2% of Output High Voltage 200 kV and Tube current 5 mA. The Equipment is composed of control unit, X-ray generator, and power cable, connection cable. X-ray generator is assembling construction X-ray tube, H.V transformer together with gas insulation (SF6) are sealed up in aluminum bucked cabinet, fan and heat-sink are mounted in the end of X-ray generator as cooling, SF6 is a gas electrical performance to H.V. Alarm lamp is used to warn, flashing, show generating X-ray. Control unit is box construction. Four printed circuit boards (PCB) and electronic device are mounted in it. All operating buttons switches and displays are equipped on the panel. We have completed to design and construct the Portable Industrial X-Ray Equipment; and have tested the electronic parameters of all test points and the main parameters of equipment (the accuracy ±2% of Output High Voltage 200 kV and Tube current 5 mA). We also have successful used the Portable Industrial X-Ray Equipment to evaluate the welds in industry. (author)

47 CFR 90.475 - Operation of internal transmitter control systems in specially equipped systems.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 5 2010-10-01 2010-10-01 false Operation of internal transmitter control... Control Internal Transmitter Control Systems § 90.475 Operation of internal transmitter control systems in specially equipped systems. (a) An internal transmitter control system need not be designed to meet the...

Mercury Control for Plants Firing Texas Lignite and Equipped with ESP-wet FGD

Energy Technology Data Exchange (ETDEWEB)

Katherine Dombrowski

2009-12-31

This report presents the results of a multi-year test program conducted as part of Cooperative Agreement DE-FC26-06NT42779, 'Mercury Control for Plants Firing Texas Lignite and Equipped with ESP-wet FGD.' The objective of this program was to determine the level of mercury removal achievable using sorbent injection for a plant firing Texas lignite fuel and equipped with an ESP and wet FGD. The project was primarily funded by the U.S. DOE National Energy Technology Laboratory. EPRI, NRG Texas, Luminant (formerly TXU), and AEP were project co-funders. URS Group was the prime contractor, and Apogee Scientific and ADA-ES were subcontractors. The host site for this program was NRG Texas Limestone Electric Generating Station (LMS) Units 1 and 2, located in Jewett, Texas. The plant fires a blend of Texas lignite and Powder River Basin (PRB) coal. Full-scale tests were conducted to evaluate the mercury removal performance of powdered sorbents injected into the flue gas upstream of the ESP (traditional configuration), upstream of the air preheater, and/or between electric fields within the ESP (Toxecon{trademark} II configuration). Phases I through III of the test program, conducted on Unit 1 in 2006-2007, consisted of three short-term parametric test phases followed by a 60-day continuous operation test. Selected mercury sorbents were injected to treat one quarter of the flue gas (e.g., approximately 225 MW equivalence) produced by Limestone Unit 1. Six sorbents and three injection configurations were evaluated and results were used to select the best combination of sorbent (Norit Americas DARCO Hg-LH at 2 lb/Macf) and injection location (upstream of the ESP) for a two-month performance evaluation. A mercury removal rate of 50-70% was targeted for the long-term test. During this continuous-injection test, mercury removal performance and variability were evaluated as the plant operated under normal conditions. Additional evaluations were made to determine any

Simulation-based Testing of Control Software

Energy Technology Data Exchange (ETDEWEB)

Ozmen, Ozgur [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Nutaro, James J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sanyal, Jibonananda [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Olama, Mohammed M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-02-10

It is impossible to adequately test complex software by examining its operation in a physical prototype of the system monitored. Adequate test coverage can require millions of test cases, and the cost of equipment prototypes combined with the real-time constraints of testing with them makes it infeasible to sample more than a small number of these tests. Model based testing seeks to avoid this problem by allowing for large numbers of relatively inexpensive virtual prototypes that operate in simulation time at a speed limited only by the available computing resources. In this report, we describe how a computer system emulator can be used as part of a model based testing environment; specifically, we show that a complete software stack including operating system and application software - can be deployed within a simulated environment, and that these simulations can proceed as fast as possible. To illustrate this approach to model based testing, we describe how it is being used to test several building control systems that act to coordinate air conditioning loads for the purpose of reducing peak demand. These tests involve the use of ADEVS (A Discrete Event System Simulator) and QEMU (Quick Emulator) to host the operational software within the simulation, and a building model developed with the MODELICA programming language using Buildings Library and packaged as an FMU (Functional Mock-up Unit) that serves as the virtual test environment.

Simulation Research on Adaptive Control of a Six-degree-of-freedom Material-testing Machine

Directory of Open Access Journals (Sweden)

Dan Wang

2014-02-01

Full Text Available This paper presents an adaptive controller equipped with a stiffness estimation method for a novel material-testing machine, in order to alleviate the performance depression caused by the stiffness variance of the tested specimen. The dynamic model of the proposed machine is built using the Kane method, and kinematic model is established with a closed-form solution. The stiffness estimation method is developed based on the recursive least-squares method and the proposed stiffness equivalent matrix. Control performances of the adaptive controller are simulated in detail. The simulation results illustrate that the proposed controller can greatly improve the control performance of the target material-testing machine by online stiffness estimation and adaptive parameter tuning, especially in low-cycle fatigue (LCF and high-cycle fatigue (HCF tests.

Tank Monitoring and Control System (TMACS) Acceptance Test Procedure

International Nuclear Information System (INIS)

HOLM, M.J.

1999-01-01

This document is intended to test the software portion of TMACS. The tests will be performed on the development system. The software to be tested is the TMACS knowledge bases (KB) and the I/O driver devices. The development system will not be talking to field equipment; instead, the field equipment is simulated using emulators or multiplexers in the lab

A Study on Performance and Safety Tests of Defibrillator Equipment.

Science.gov (United States)

Tavakoli Golpaygani, A; Movahedi, M M; Reza, M

2017-12-01

Nowadays, more than 10,000 different types of medical devices can be found in hospitals. This way, medical electrical equipment is being employed in a wide variety of fields in medical sciences with different physiological effects and measurements. Hospitals and medical centers must ensure that their critical medical devices are safe, accurate, reliable and operational at the required level of performance. Defibrillators are critical resuscitation devices. The use of reliable defibirillators has led to more effective treatments and improved patient safety through better control and management of complications during Cardiopulmonary Resuscitation (CPR). The metrological reliability of twenty frequent use, manual defibrillators in use ten hospitals (4 private and 6 public) in one of the provinces of Iran according to international and national standards was evaluated. Quantitative analysis of control and instrument accuracy showed the amount of the obtained results in many units are critical which had less value over the standard limitations especially in devices with poor battery. For the accuracy of delivered energy analysis, only twelve units delivered acceptable output values and the precision in the output energy measurements especialy in weak battry condition, after activation of discharge alarm, were low. Obtained results indicate a need for new and severe regulations on periodic performance verifications and medical equipment quality control program especially for high risk instruments. It is also necessary to provide training courses on the fundumentals of operation and performane parameters for medical staff in the field of meterology in medicine and how one can get good accuracy results especially in high risk medical devices.

Control and management of energy in a PV system equipped with batteries storage

Directory of Open Access Journals (Sweden)

Kamal Hirech

2016-06-01

Full Text Available In this paper we present a work concerning the conception, implementation and testing of a photovoltaic system that is equipped with a new concept of control and manage the energy in a PV system with a battery storage. The objective is to exploit the maximum of power using Hill climbing improved algorithm that considers optimal electrical characteristics of PV panels regardless of the system perturbation, to manage the energy between blocs of PV system in order to control the charge/discharge process and inject the energy surplus into the grid and also to estimate the state of charge with precision. Moreover, the system guarantees the acquisition and presentation of results on computer, supervision and so on. The results obtained show the robustness of the PV system, good control and protection of batteries under the maximum of energy provided by the PV panels. The state of charge estimation is evaluated by using measured parameters in real time; it shows an improvement of around 5% compared to the conventional technique.

The prevalence of visible and/or occult blood on anesthesia and monitoring equipment.

Science.gov (United States)

Perry, S M; Monaghan, W P

2001-02-01

The Occupational Safety and Health Administration (OSHA) and the Centers for Disease Control and Prevention (CDC) have attempted to stop the spread of blood-borne pathogens by issuing several recommendations and regulations. However, unless healthcare workers comply with these standards, they are not effective. In the anesthesia care environment, the anesthetist is responsible for ensuring that the equipment is clean, and disinfected, before use. We studied the prevalence of visible and occult blood on 6 types of anesthesia and monitoring equipment identified as ready for use in 28 operating suites, in 2 facilities. The sample consisted of 336 observations of the 6 types of equipment. The equipment was inspected for visible blood and then tested for occult blood using a 3-stage phenolphthalein test. Of the 336 observations, 110 (32.7%), were positive for occult blood with only 6 showing visible blood. The presence of blood on this equipment may be in direct violation of the OSHA Blood-borne Pathogen Standard and the infection control guidelines of the American Association of Nurse Anesthetists. Furthermore, the presence of blood on this equipment may increase the risk for nosocomial and occupational exposure to viral and bacterial pathogens. Recommendations were made to decrease the risks from this contamination by redesigning equipment, increasing the use of disposable equipment, and ensuring compliance with effective infection control practices.

The role of a certified calibration laboratory in a station's measuring and test equipment calibration, repair, and documentation program

International Nuclear Information System (INIS)

Ebenstreit, K.; MacIntosh, N.

1995-01-01

This paper outlines the role of a Certified Calibration Laboratory in- ensuring that the requirements of Measuring and Test Equipment calibration, identification, and traceability are met and documented. The Nuclear environment is one which is subject to influences from numerous 'quality agents'. One of the fields which comes under the scrutiny of the quality agents is that of equipment calibration and repair (both field components and M and TE). There is a responsibility to produce a superior product for the Ontario Consumer. The maintenance and calibration of Station Systems and their components have a direct impact on this output. The Measuring and Test Equipment element in each of these needs can be addressed by having a defined group of Maintenance Staff to execute a Measuring and Test Equipment Program which meets specific parameters. (author)

Open test assembly (OTA) shear demonstration testing work/test plan

International Nuclear Information System (INIS)

Hiller, S.W.

1998-01-01

This document describes the development testing phase associated with the OTA Shear activity and defines the controls to be in place throughout the testing. The purpose of the OTA Shear Program was to provide equipment that is needed for the processing of 40 foot long, sodium wetted, irradiated core components previously used in the FFTF reactor to monitor fuel and materials tests. There are currently 15 of these OTA test stalks located in the Test Assembly Conditioning Station (TACS) inerted vault. These need to be dispositioned for a shutdown mission to eliminate this highly activated, high dose inventory prior to turnover to the ERC since they must be handled by remote operations. These would also need to be dispositioned for a restart mission to free up the vault they currently reside in. The waste handling and cleaning equipment in the J33M Cell was designed and built for the handling of reactor components up to the standard 12 foot length. This program will provide the equipment to the IEM Cell to remotely section the OTAS into pieces less than 12 feet in length to allow for the necessary handling and cleaning operations required for proper disposition. Due to the complexity of all operations associated with remote handling, the availability of the IEM Cell training facility, and the major difficulty with reworking contaminated equipment, it was determined that preliminary testing of the equipment was desirable, This testing activity would provide the added assurance that the equipment will operate as designed prior to performance of the formal Acceptance Test Procedure (ATP) at the IEM Cell, This testing activity will also allow for some operator familiarity and procedure checkout prior to actual installation into the IEM Cell. This development testing will therefore be performed at the conclusion of equipment fabrication and prior to transfer of the equipment to the 400 Area

The control, monitor, and alarm system for the ICT equipment of the ASTRI SST-2M telescope prototype for the Cherenkov Telescope Array

Science.gov (United States)

Gianotti, Fulvio; Fioretti, Valentina; Tanci, Claudio; Conforti, Vito; Tacchini, Alessandro; Leto, Giuseppe; Gallozzi, Stefano; Bulgarelli, Andrea; Trifoglio, Massimo; Malaguti, Giuseppe; Zoli, Andrea

2014-07-01

ASTRI is an Italian flagship project whose first goal is the realization of an end-to-end telescope prototype, named ASTRI SST-2M, for the Cherenkov Telescope Array (CTA). The prototype will be installed in Italy during Fall 2014. A second goal will be the realization of the ASTRI/CTA mini-array which will be composed of seven SST-2M telescopes placed at the CTA Southern Site. The Information and Communication Technology (ICT) equipment necessary to drive the infrastructure for the ASTRI SST-2M prototype is being designed as a complete and stand-alone computer center. The design goal is to obtain basic ICT equipment that might be scaled, with a low level of redundancy, for the ASTRI/CTA mini-array, taking into account the necessary control, monitor and alarm system requirements. The ICT equipment envisaged at the Serra La Nave observing station in Italy, where the ASTRI SST-2M telescope prototype will operate, includes computers, servers and workstations, network devices, an uninterruptable power supply system, and air conditioning systems. Suitable hardware and software tools will allow the parameters related to the behavior and health of each item of equipment to be controlled and monitored. This paper presents the proposed architecture and technical solutions that integrate the ICT equipment in the framework of the Observatory Control System package of the ASTRI/CTA Mini- Array Software System, MASS, to allow their local and remote control and monitoring. An end-toend test case using an Internet Protocol thermometer is reported in detail.

Quality control of conventional diagnostic radiology equipment in Serbia and Montenegro

International Nuclear Information System (INIS)

Ciraj, O.; Kosutic, D.; Markovic, S.

2003-01-01

There are more than 1500 diagnostic X-ray tubes in service in Serbia and Montenegro. Diagnostic X-ray equipment is checked on annual basis. X-ray equipment Qc protocols have been adopted from several international standards and guidelines [1,2], which have been modified according our practice and measuring equipment. According our inventory, about one half of all installed units is used for conventional X-ray diagnostics, 10% are mobile units, 2% of all in units in operation are mammographic devices an another 2% are computed tomography units. In addition there are about 600 dental X-ray units, which is 36% of all units. It is worth mentioning that almost 30 % of all installed units have single-phase generators, another 25% are tree phase (six and twelve pulse) generators and nearly 9% are high frequency units. Majority of units was installed more than 25 years ago. The Quality Control (QC) in radiography is a central part of QA programme, which deals with equipment maintenance and monitoring. QA in diagnostic radiology is a mean of maintaining standards in imaging and working towards minimizing patient and staff doses. As a part of QA programme in diagnostic radiology, the performance characteristics of 96 conventional X-ray units were measured in six months period during 2003. The diagnostic units were located in hospitals all over the country. They represent 25% of the total conventional diagnostic units of the country. About one half of measured X-ray units were new-installed. QC program has positive effect on X-ray equipment performance in a period of a few years. It is essential to perform QC tests for all installed X-ray units at least on annual basis. This would lead to production of consistent X-ray images, with minimal retake rate and hence, will contribute to decreasing of the patient dose. Patient doses are determined by multitude factors which interact in very complicated manner. It is very important to perform real patient dose measurements in

FIELD TEST PROGRAM TO DEVELOP COMPREHENSIVE DESIGN, OPERATING, AND COST DATA FOR MERCURY CONTROL SYSTEMS

Energy Technology Data Exchange (ETDEWEB)

Michael D. Durham

2003-05-01

With the Nation's coal-burning utilities facing the possibility of tighter controls on mercury pollutants, the U.S. Department of Energy is funding projects that could offer power plant operators better ways to reduce these emissions at much lower costs. Mercury is known to have toxic effects on the nervous system of humans and wildlife. Although it exists only in trace amounts in coal, mercury is released when coal burns and can accumulate on land and in water. In water, bacteria transform the metal into methylmercury, the most hazardous form of the metal. Methylmercury can collect in fish and marine mammals in concentrations hundreds of thousands times higher than the levels in surrounding waters. One of the goals of DOE is to develop technologies by 2005 that will be capable of cutting mercury emissions 50 to 70 percent at well under one-half of today's costs. ADA Environmental Solutions (ADA-ES) is managing a project to test mercury control technologies at full scale at four different power plants from 2000--2003. The ADA-ES project is focused on those power plants that are not equipped with wet flue gas desulfurization systems. ADA-ES has developed a portable system that will be tested at four different utility power plants. Each of the plants is equipped with either electrostatic precipitators or fabric filters to remove solid particles from the plant's flue gas. ADA-ES's technology will inject a dry sorbent, such as activated carbon, which removes the mercury and makes it more susceptible to capture by the particulate control devices. A fine water mist may be sprayed into the flue gas to cool its temperature to the range where the dry sorbent is most effective. PG&E National Energy Group is providing two test sites that fire bituminous coals and both are equipped with electrostatic precipitators and carbon/ash separation systems. Wisconsin Electric Power Company is providing a third test site that burns Powder River Basin (PRB) coal and

Aseismatic design of electrical equipments and instruments for nuclear power stations

International Nuclear Information System (INIS)

Suzuki, Yasuharu; Nishizawa, Kazuo; Miyazaki, Yoshio; Miura, Takumi

1977-01-01

The aseismatic design of electrical instruments is carried out according to IEEE Standard 344-1971 in the USA. In Japan also, the method of aseismatic design of electrical instruments has been investigated by the representatives of electric power companies and electric machine makers since 1972. In Hitachi Ltd., the statical method of confirming aseismatic property was established on the basis of the rigid design for electrical instruments. It is convenient to examine the aseismatic property of electrical equipments by classifying them into control and switch boards, electrical appliances, equipments and circuits. It is possible to use the static method treating earthquake force as static load by avoiding resonance with the electrical equipments which have the higher natural frequency than that of buildings. The purposes of the vibration test are to prove the validity of the theoretical analysis, to clarify the vibration characteristics, and to confirm the maintenance of functions and the strength of the equipments. The vibration tests of control boards, the switch boards of enclosed type, motor control centers, the racks for instrumentation, storage batteries and electrical appliances are explained. Moreover, the vibration analysis with a computer according to finite element method is described. (Kako, I.)

Dispensing Equipment Testing with Mid-Level Ethanol/Gasoline Test Fluid: Summary Report

Energy Technology Data Exchange (ETDEWEB)

Boyce, K.; Chapin, J. T.

2010-11-01

The National Renewable Energy Laboratory's (NREL) Nonpetroleum-Based Fuel Task addresses the hurdles to commercialization of biomass-derived fuels and fuel blends. One such hurdle is the unknown compatibility of new fuels with current infrastructure, such as the equipment used at service stations to dispense fuel into automobiles. The U.S. Department of Energy's (DOE) Vehicle Technology Program and the Biomass Program have engaged in a joint project to evaluate the potential for blending ethanol into gasoline at levels higher than nominal 10 volume percent. This project was established to help DOE and NREL better understand any potentially adverse impacts caused by a lack of knowledge about the compatibility of the dispensing equipment with ethanol blends higher than what the equipment was designed to dispense. This report provides data about the impact of introducing a gasoline with a higher volumetric ethanol content into service station dispensing equipment from a safety and a performance perspective.

Electrical equipment qualification

International Nuclear Information System (INIS)

Farmer, W.S.

1983-01-01

Electrical equipment qualification research programs being carried out by CEA, JAERI, and Sandia Laboratories are discussed. Objectives of the program are: (1) assessment of accident simulation methods for electrical equipment qualification testing; lower coarse (2) evaluation of equipment aging and accelerated aging methods; (3) determine radiation dose spectrum to electrical equipment and assess simulation methods for qualification; (4) identify inadequacies in electrical equipment qualification procedures and standards and potential failure modes; and (5) provide data for verifying and improving standards, rules and regulatory guides

Nondestructive testing of materials

International Nuclear Information System (INIS)

NUKEM has transferred know-how from reactor technology to materials testing. The high and to a large extent new quality standards in the nuclear industry necessitate reliable measuring and testing equipment of the highest precision. Many of the tasks presented to us could not be solved with the equipment available on the market, for which reason we have developed our own measuring, testing and control systems. We have therefore acquired considerable experience in dealing with specific measuring, testing and control tasks and can handle even out-of-the-way problems that are submitted to us from a wide variety of fields. Our mechanical systems for the checking of close-tolerance gaps, the automatic determination of pellet dimensions and the measurement of absolute lengths and absolute velocities are in use in many different industrial fields. We have succeeded in solving unusual testing and sorting problems with the aid of automated surface testing equipment working on optical principles. Our main activities in the field of non-destructive testing have been concentrated on ultrasonic and eddy current testing and, of late, acoustic emission analysis. NUKEM ultrasonic systems are notable for their high defect detection rate and testing accuracy, combined with high testing speed. The equipment we supply includes ultrasonic rotary systems for the production testing of quality tubes, ultrasonic immersion systems for the final testing of reactor cladding tubes, weld testing equipment, and test equipment for the bonds in multi-layer plates. (orig./RW) [de

A Study on Performance and Safety Tests of Defibrillator Equipment

Directory of Open Access Journals (Sweden)

Tavakoli Golpaygani A.

2017-12-01

Full Text Available Introduction: Nowadays, more than 10,000 different types of medical devices can be found in hospitals. This way, medical electrical equipment is being employed in a wide variety of fields in medical sciences with different physiological effects and measurements. Hospitals and medical centers must ensure that their critical medical devices are safe, accurate, reliable and operational at the required level of performance. Defibrillators are critical resuscitation devices. The use of reliable defibirillators has led to more effective treatments and improved patient safety through better control and management of complications during Cardiopulmonary Resuscitation (CPR. Materials and Methods: The metrological reliability of twenty frequent use, manual defibrillators in use ten hospitals (4 private and 6 public in one of the provinces of Iran according to international and national standards was evaluated. Results: Quantitative analysis of control and instrument accuracy showed the amount of the obtained results in many units are critical which had less value over the standard limitations especially in devices with poor battery. For the accuracy of delivered energy analysis, only twelve units delivered acceptable output values and the precision in the output energy measurements especialy in weak battry condition, after activation of discharge alarm, were low. Conclusion: Obtained results indicate a need for new and severe regulations on periodic performance verifications and medical equipment quality control program especially for high risk instruments. It is also necessary to provide training courses on the fundumentals of operation and performane parameters for medical staff in the field of meterology in medicine and how one can get good accuracy results especially in high risk medical devices.

Miravalles Geothermal Project: Portable Well Flow Test Equipment and Procedures Manual

Energy Technology Data Exchange (ETDEWEB)

None

1980-05-01

The well flow test program has been designed to facilitate the gathering of information, with portable test equipment, from various wells with regard to their capability of flow, the quality of steam produced at various back pressures, the composition and quantity of noncondensable gases flashed from the wells and the composition and quantity of solids in the well's liquid streams (brine). The test program includes procedures for obtaining the following basic flow data pertinent to the plant power cycle design: (1) Effluent steam and brine flows, pressures and temperatures; (2) Noncondensable and dissolved gas contents in steam and brine; (3) H{sub s}S content in gases formed; and (4) Solids content and chemical analysis of steam and brine.

Advanced Rooftop Control (ARC) Retrofit: Field-Test Results

Energy Technology Data Exchange (ETDEWEB)

Wang, Weimin; Katipamula, Srinivas; Ngo, Hung; Underhill, Ronald M.; Taasevigen, Danny J.; Lutes, Robert G.

2013-07-31

The multi-year research study was initiated to find solutions to improve packaged equipment operating efficiency in the field. Pacific Northwest National Laboratory (PNNL), with funding from the U.S. Department of Energy’s (DOE’s) Building Technologies Office (BTO) and Bonneville Power Administration (BPA) conducted this research, development and demonstration (RD&D) study. Packaged equipment with constant speed supply fans is designed to provide ventilation at the design rate at all times when the fan is operating as required by building code. Although there are a number of hours during the day when a building may not be fully occupied or the need for ventilation is lower than designed, the ventilation rate cannot be adjusted easily with a constant speed fan. Therefore, modulating the supply fan in conjunction with demand controlled ventilation (DCV) will not only reduce the coil energy but also reduce the fan energy. The objective of this multi-year research, development and demonstration project was to determine the magnitude of energy savings achievable by retrofitting existing packaged rooftop air conditioners with advanced control strategies not ordinarily used for packaged units. First, through detailed simulation analysis, it was shown that significant energy (between 24% and 35%) and cost savings (38%) from fan, cooling and heating energy consumption could be realized when packaged air conditioning units with gas furnaces are retrofitted with advanced control packages (combining multi-speed fan control, integrated economizer controls and DCV). The simulation analysis also showed significant savings for heat pumps (between 20% and 60%). The simulation analysis was followed by an extensive field test of a retrofittable advanced rooftop unit (RTU) controller.

Data Center Equipment Location and Monitoring System

DEFF Research Database (Denmark)

2013-01-01

Abstract: Data center equipment location systems include hardware and software to provide information on the location, monitoring, and security of servers and other equipment in equipment racks. The systems provide a wired alternative to the wireless RFID tag system by using electronic ID tags...... connected to each piece of equipment, each electronic ID tag connected directly by wires to an equipment rack controller on the equipment rack. The equipment rack controllers link to a central control computer that provides an operator ...

Development of controller strategies for a robotized filament winding equipment

Science.gov (United States)

Lobo, Edgar; Machado, José; Mendonça, João P.

2013-10-01

The composites reinforced with continuous fibers of polymeric material are increasingly used in applications where it is essential to reduce weight, mainly due to their high ratio of strength/weight and rigidity/weight. A conventional application are pressure vessels, used for storing liquids or gases subjected to low or high pressure, where the tape continuous fiber-reinforced polymeric matrix material is wound around a mandrel defining the final geometry. In this context the filament winding process is a very attractive process for the production of composite components. For optimal structural performance, and greater weight saving, an optimal path should be adopted, resulting only in axial tension in the longitudinal direction (slip). Such path is the geodesic winding and diverse equipment may be used to guarantee the process automation of the winding. This work herein presented is focused on the study and development of the controller program for a robotized filament winding equipment, taking into account customization of possible trajectories controlling filament winding. The automation of the custom path according to user needs increases exponentially the capabilities, where the use of a robotized solution increases process flexibility and repeatability.

Evaluation of climatic vibration testing on plastic waterproof enclosure for electronic equipment using ANSYS[reg] workbench

International Nuclear Information System (INIS)

Aw, K.C.; Huang, W.D.J.; De Silva, M.W.R.P.

2007-01-01

Designing and testing of waterproof enclosure for electronic equipment involves significant amount of time and resources. This paper concentrates on electronic equipment used for maritime application. Typical waterproof test perform is based on the IEC 60529 standards and is insufficient to determine its reliability. Since, these enclosures were subjected to environmental stress such as heat and vibration and there is a need to understand how these affect the waterproof performance. Simulation using ANSYS workbench software was performed to comprehend the effect of various parameters of accelerated testing performed on these waterproof enclosures. Experiments were performed to examine the correlation with simulation results. The results confirmed that accelerated testing with random vibration at cold temperature causes greatest stress and causes degradation to adhesive bonds and hence affect the waterproof performance

Financing of power supply systems and pollution control equipment. Models, dimensions, developments

Energy Technology Data Exchange (ETDEWEB)

Radtke, G; Raabe, G

1988-11-01

The authors explain the bankers' point of view of the financial and economic aspects of developments in the energy sector, discussing the financing of natural gas pipelines (Muro, Megal, etc.), of nuclear power plant construction, of projects in the oil supply sector, and of pollution abatement measures and equipment for the power industry and other industries. The different financial situations of small firms or large firms supplying pollution control equipment are discussed referring to the financing schemes to be set up, explaining among other things the profitability assessment taking into account long-term development or delays in return on capital investment from borrowed funds as induced, e.g., by delays in the licensing procedure. Future demand for borrowed capital for pollution control or nuclear power plant development is difficult to assess by the banking circles. (orig./RST).

Valorization procedure of x-ray equipment in the mammography equipment

International Nuclear Information System (INIS)

Ruiz, M. A.; Ordonez, J.; Antolin, E.; Andres, J. C. de; Gonzalez, I.; Arranz, L.; Sastre, J. M.; Ferrer, N.

2006-01-01

The Ramon y Cajal Hospital mammography service has three X-rays units, two of them with high resolution computed radiography (CR) system and one with flat-panel (FP)-based full-field digital mammography system. Periodic control dose tests in patients have shown lower glandular dose levels (DGM) than references provided by European Protocol for de Quality Control of de Physical and Technical Aspects of Mammography Screening. In this work, we have tried to establish an easy method for DGM calculation which is representative of the three equipment results. For this aim, we have defined an index which is measured along the time like a reference point. This index is defined as the relation between the blind test punctuations of a standard phantom image given by at least three radiologists in the Unit, and the average DGM values obtained in 20 patients in each Unit (using random thickness and random mama composition). (Author)

Analysis of QA audit checklist for equipment suppliers

International Nuclear Information System (INIS)

Tian Xuehang

2012-01-01

Eleven aspects during the equipment manufacturing by the suppliers, including the guidelines and objectives of quality assurance, management department review, document and record control, staffing and training, design control, procurement control, control of items, process control, inspection and testing control, non-conformance control, and internal and external QA audit, are analyzed in this article. The detailed QA audit checklist on these above mentioned aspects are described and the problems found in real QA audit are listed in this article. (authors)

High-Reynolds Number Circulation Control Testing in the National Transonic Facility

Science.gov (United States)

Milholen, William E., II; Jones, Gregory S.; Chan, David T.; Goodliff, Scott L.

2012-01-01

A new capability to test active flow control concepts and propulsion simulations at high Reynolds numbers in the National Transonic Facility at the NASA Langley Research Center is being developed. The first active flow control experiment was completed using the new FAST-MAC semi-span model to study Reynolds number scaling effects for several circulation control concepts. Testing was conducted over a wide range of Mach numbers, up to chord Reynolds numbers of 30 million. The model was equipped with four onboard flow control valves allowing independent control of the circulation control plenums, which were directed over a 15% chord simple-hinged flap. Preliminary analysis of the uncorrected lift data showed that the circulation control increased the low-speed maximum lift coefficient by 33%. At transonic speeds, the circulation control was capable of positively altering the shockwave pattern on the upper wing surface and reducing flow separation. Furthermore, application of the technique to only the outboard portion of the wing demonstrated the feasibility of a pneumatic based roll control capability.

Tracking reliability for space cabin-borne equipment in development by Crow model.

Science.gov (United States)

Chen, J D; Jiao, S J; Sun, H L

2001-12-01

Objective. To study and track the reliability growth of manned spaceflight cabin-borne equipment in the course of its development. Method. A new technique of reliability growth estimation and prediction, which is composed of the Crow model and test data conversion (TDC) method was used. Result. The estimation and prediction value of the reliability growth conformed to its expectations. Conclusion. The method could dynamically estimate and predict the reliability of the equipment by making full use of various test information in the course of its development. It offered not only a possibility of tracking the equipment reliability growth, but also the reference for quality control in manned spaceflight cabin-borne equipment design and development process.

Earth Observing System (EOS)/ Advanced Microwave Sounding Unit-A (AMSU-A): Special Test Equipment. Software Requirements

Science.gov (United States)

Schwantje, Robert

1995-01-01

This document defines the functional, performance, and interface requirements for the Earth Observing System/Advanced Microwave Sounding Unit-A (EOS/AMSU-A) Special Test Equipment (STE) software used in the test and integration of the instruments.

Irradiation position-control equipment for the HIMAC

Energy Technology Data Exchange (ETDEWEB)

Higashi, Seiichi; Kuma, Shoichiro [Mitsubishi Electric Corp., Tokyo (Japan); Nomura, Kazuaki; Endo, Masahiro; Minohara, Shin-ichi

1995-02-01

Use of heavy-ion beams to mount a pinpoint attack on unhealthy tissue requires that the target tissue be placed in the precise location specified by the therapy planning equipment. The article reports on the detailed specifications, positioning mechanism, position verification method and the interface with the therapy planning equipment. (author).

Nuclear electronics equipment for control and monitoring panel. Ratemeter data and test methods

International Nuclear Information System (INIS)

1977-09-01

This document first reviews the main notations used, and some definitions, then states its scope and gives a bibliography. The main characteristics of ratemeter electronic sub-assemblies are then given, and corresponding test methods are described. This type of instrument indicates, on a linear or logarithmic scale, the counting rate of pulses applied to its input. The document reviews analogue and digital ratemeters with linear or logarithmic characteristics, for general purpose applications, reactor control, health physics, plant and laboratory applications. The document is intended for electronics manufacturers, designers, persons participating in acceptance trials, plant operators and, generally, for members of the electronics profession [fr

Country-wide quality control of equipment in Norwegian laboratories performing in vivo nuclear medicine examinations

International Nuclear Information System (INIS)

Skretting, A.; Rootwelt, K.; Berthelsen, T.

1984-01-01

The report presents the methods used and the results obtained in quality control tests performd in all Norwegian hospital laboratories performing in vivo nuclear medicine examinations. The tests included activity meters and scintillation cameras. The activity meters were tested by means of calibrated, long-lived radioactive sources. The quality of these instruments were judged to be satisfactory for moderate and high activities, non of them showing a deviation of more than 10% from the calibration value. Deviations were larger at low activities and were for some laboratories unacceptable. The scintillation cameras test included studies of flood field (homogeneity), geometrical resolution and energy resolution, as well as measurements of count rate characteristics and sensitivity. 40% of the cameras were judged to have flood field responses with satisfactory homogeneity, whereas 32% of the cameras had a satisfactory resolution ability. A liver/abdomen phantom test was carried out by the staff of the actual laboratory. This test proved that only 20% of the laboratories had a satisfactory total performance, managing to detect and describe satisfactorily 4 out of 5 simulated defects in the liver phantom. Lack of information density and insufficient number of projections was the main reason for unsatisfactory results with good cameras. It is recommended that quality control equipment as used in the described tests should be made available to Norwegian hospitals for self assessment. Regular quality assurance tests as recommended by the Norwegian Association for Radiation Physics and Norwegian Society of Nuclear Medicine should be implemented in all hospitals. Moreover, a practical training course in quality assurance should be arranged. (RF)

Nuclear electronics equipment for control and monitoring panel

International Nuclear Information System (INIS)

Roquefort, Henri

1980-09-01

The purpose of this document is to fix what terminology should be used, to define the main specifications of supplies and to specify the test methods recommended to check these specifications. This document applies to low and high voltage supply sub-units fed by AC or DC mains supply and delivering direct current under stabilised DC voltage. These sub-units are used in nuclear electronics equipment and especially for reactor monitoring. Following the definition of some terms, current notations and a bibliography, the characteristics section and the corresponding test methods section are developed. Each section deals in particular with: input and output characteristics, linearity and display errors, fluctuations, influence and operation errors, variations, drift (stability), variations with the main influence quantities: mains, temperature, load, transient variations, insulation, shielding, microbreakdowns, emergency supply, electromagnetic perturbation sensitivity, reliability, maintainability and characteristics specific to certain supplies used for the polarisation of radiation detectors [fr

Development of corrosion testing equipment under heat transfer and irradiation conditions to evaluate corrosion resistance of materials used in acid recovery evaporator. Contract research

International Nuclear Information System (INIS)

Motooka, Takafumi; Numata, Masami; Kiuchi, Kiyoshi

2002-01-01

We have been evaluated the safety for corrosion of various metals applied to acid recovery evaporators by the mock-up tests using small scaled equipment and the reference tests in laboratories with small specimens. These tests have been conducted under-radioactive environment. The environment in practical reprocessing plants has many radioactive species. Therefore, the effect of irradiation on corrosion should be evaluated in detail. In this study, we have developed the corrosion testing equipment, which is employed to simulate environments in the acid recovery evaporators. This report describes the specification of corrosion testing equipment and the results of primary, reference and hot tests. Using the equipment, the corrosion test under heat transfer and irradiation conditions have been carried out for 930 hours in safety. It is expectable that useful corrosion test data in radioactive environment are accumulated with this equipment in future, and help the adequate choice of corrosion test condition in laboratories. (author)

Study concerning the power plant control and safety equipment by integrated distributed systems

International Nuclear Information System (INIS)

Optea, I.; Oprea, M.; Stanescu, P.

1995-01-01

The paper deals with the trends existing in the field of nuclear control and safety equipment and systems, proposing a high-efficiency integrated system. In order to enhance the safety of the plant and reliability of the structure system and components, we present a concept based on the latest computer technology with an open, distributed system, connected by a local area network with high redundancy. A modern conception for the control and safety system is to integrate all the information related to the reactor protection, active engineered safeguard and auxiliary systems parameters, offering a fast flow of information between all the agencies concerned so that situations can be quickly assessed. The integrated distributed control is based on a high performance operating system for realtime applications, flexible enough for transparent networking and modular for demanding configurations. The general design considerations for nuclear reactors instrumentation reliability and testing methods for real-time functions under dynamic regime are presented. Taking into account the fast progress in information technology, we consider the replacement of the old instrumentation of Cernavoda-1 NPP by a modern integrated system as an economical and efficient solution for the next units. (Author) 20 Refs

Data acquisition, remote control and equipment monitoring for ISOLDE RILIS

Science.gov (United States)

Rossel, R. E.; Fedosseev, V. N.; Marsh, B. A.; Richter, D.; Rothe, S.; Wendt, K. D. A.

2013-12-01

With a steadily increasing on-line operation time up to a record 3000 h in the year 2012, the Resonance Ionization Laser Ion Source (RILIS) is one of the key components of the ISOLDE on-line isotope user facility at CERN. Ion beam production using the RILIS is essential for many experiments due to the unmatched combination of ionization efficiency and selectivity. To meet the reliability requirements the RILIS is currently operated in shift duty for continuous maintenance of crucial laser parameters such as wavelength, power, beam position and timing, as well as ensuring swift intervention in case of an equipment malfunction. A recent overhaul of the RILIS included the installation of new pump lasers, commercial dye lasers and a complementary, fully solid-state titanium:sapphire laser system. The framework of the upgrade also required the setup of a network-extended, LabVIEW-based system for data acquisition, remote control and equipment monitoring, to support RILIS operators as well as ISOLDE users. The system contributes to four key aspects of RILIS operation: equipment monitoring, machine protection, automated self-reliance, and collaborative data acquisition. The overall concept, technologies used, implementation status and recent applications during the 2012 on-line operation period will be presented along with a summary of future developments.

Deep Borehole Field Test Requirements and Controlled Assumptions.

Energy Technology Data Exchange (ETDEWEB)

Hardin, Ernest [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-07-01

This document presents design requirements and controlled assumptions intended for use in the engineering development and testing of: 1) prototype packages for radioactive waste disposal in deep boreholes; 2) a waste package surface handling system; and 3) a subsurface system for emplacing and retrieving packages in deep boreholes. Engineering development and testing is being performed as part of the Deep Borehole Field Test (DBFT; SNL 2014a). This document presents parallel sets of requirements for a waste disposal system and for the DBFT, showing the close relationship. In addition to design, it will also inform planning for drilling, construction, and scientific characterization activities for the DBFT. The information presented here follows typical preparations for engineering design. It includes functional and operating requirements for handling and emplacement/retrieval equipment, waste package design and emplacement requirements, borehole construction requirements, sealing requirements, and performance criteria. Assumptions are included where they could impact engineering design. Design solutions are avoided in the requirements discussion. Deep Borehole Field Test Requirements and Controlled Assumptions July 21, 2015 iv ACKNOWLEDGEMENTS This set of requirements and assumptions has benefited greatly from reviews by Gordon Appel, Geoff Freeze, Kris Kuhlman, Bob MacKinnon, Steve Pye, David Sassani, Dave Sevougian, and Jiann Su.

Instrument Control (iC) - An Open-Source Software to Automate Test Equipment.

Science.gov (United States)

Pernstich, K P

2012-01-01

It has become common practice to automate data acquisition from programmable instrumentation, and a range of different software solutions fulfill this task. Many routine measurements require sequential processing of certain tasks, for instance to adjust the temperature of a sample stage, take a measurement, and repeat that cycle for other temperatures. This paper introduces an open-source Java program that processes a series of text-based commands that define the measurement sequence. These commands are in an intuitive format which provides great flexibility and allows quick and easy adaptation to various measurement needs. For each of these commands, the iC-framework calls a corresponding Java method that addresses the specified instrument to perform the desired task. The functionality of iC can be extended with minimal programming effort in Java or Python, and new measurement equipment can be addressed by defining new commands in a text file without any programming.

Survey and analysis on environmental and electromagnetic effect on instrumentation and control equipment of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hwang, In Koo; Lee, Dong Young; Cha, Kyung Ho

2001-03-01

As the instrumentation and control (I and C) equipment suppliers tend to provide digital components rather than conventional analog type components for instrumentation and control systems of nuclear power plants(NPPs), it is unavoidable to adopt digital equipment for safety I and C systems as well as non-safety systems. However, the full introduction of digital equipment for I and C systems of nuclear power plants raises several concerns which have not been considered in conventional analog I and C equipment. The two major examples of the issues of digital systems are environmental/electromagnetic compatibility (EMC) and software reliability. This report presents the survey and research results on environmental and electromagnetic effect on I and C equipment of nuclear power plants to give a guideline for aging management and design process. Electromagnetic site surveys were conducted to be used as a part of technical basis to demonstrate that I and C systems are compatible with the ambient electromagnetic noise in Korean nuclear power plants.

Seismic proving tests on the reliability for large components and equipment of nuclear power plants

International Nuclear Information System (INIS)

Ohno, Tokue; Tanaka, Nagatoshi

1988-01-01

Since Japan has destructive earthquakes frequently, the structural reliability for large components and equipment of nuclear power plants are rigorously required. They are designed using sophisticated seismic analyses and have not yet encountered a destructive earthquake. When nuclear power plants are planned, it is very important that the general public understand the structural reliability during and after an earthquake. Seismic Proving Tests have been planned by Ministry of International Trade and Industry (Miti) to comply with public requirement in Japan. A large-scale high-performance vibration table was constructed at Tasted Engineering Laboratory of Nuclear Power Engineering Test Center (NU PEC), in order to prove the structural reliability by vibrating the test model (of full scale or close to the actual size) in the condition of a destructive earthquake. As for the test models, the following four items were selected out of large components and equipment important to the safety: Reactor Containment Vessel; Primary Coolant Loop or Primary Loop Recirculation System; Reactor Pressure Vessel; and Reactor Core Internals. Here is described a brief of the vibration table, the test method and the results of the tests on PWR Reactor Containment Vessel and BWR Primary Loop Recirculation System (author)

Auxiliary controllers for data acquisition from scintillation detector electronic equipment

Energy Technology Data Exchange (ETDEWEB)

Leonenko, D A; Rybakov, V G; Sen' ko, V A [Gosudarstvennyj Komitet po Ispol' zovaniyu Atomnoj Ehnergii SSSR, Serpukhov. Inst. Fiziki Vysokikh Ehnergij

1983-01-01

Structural schemes of auxiliary controllers of three types ensuring compression, filtration and record in buffer storage of data from scintillation detectors electronic equipment are described. The electronics is made according to the CAMAC ideology. The KD-85 controller exercises data readout from analog-to-digital converters (ADC), subtraction of pedestal values, discrimination by the bottom level and record into the buffer storage module. The KD-86 controller summarizes data from all the ADC channels in a crate dicscriminates the summarized data by the upper and bottom levels, and rejects data classified as useless. The KD-90 controller ensures data reading from different modules of the crate according to preset code and records information in the buffer storage module. The considered controllers employ integral microcircuits of the K 155 series. At present the controllers are under experimental operation. Their utilization would permit to adopt new arrangement of data acquisition from experimental facilities in the nearest future and essentially increase the operating efficiency of these facilities.

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

Photovoltaic System Equipped with Digital Command Control and Acquisition

Directory of Open Access Journals (Sweden)

Khalil Kassmi

2013-07-01

Full Text Available In this paper, we present results concerning the design, the realization and the characterization of a photovoltaic system (PV, equipped with a digital controls: Power Point Tracking (MPPT, charge/discharge lead acid batteries, sun tracker and supervision. These different functions are performed with a microcontroller that has capabilities and functions to the reliability of PV systems (signal generation Pulses Width Modulation (PWM, speed etc.. Concerning the MPPT control operation, we improved the accuracy and reliability of research by improving the search algorithm “Hill Climbing” taking into account the optimal operation of PV panels depending on weather conditions (temperature and light.The experiment of each block shows that the MPPT control converges instantly the operating point of the PV panels around the maximum power point, independently of sudden changes of the illumination or the load. The control blocks charge/discharge battery and sun tracking show good control of charge/discharge lead acid batteries and the need of sun tracker to increase the power supplied by the PV panel. By using the improved MPPT control, loss of power supplied by the PV panels are very low (below 5%.

Mounted Smartphones as Measurement and Control Platforms for Motor-Based Laboratory Test-Beds

Directory of Open Access Journals (Sweden)

Jared A. Frank

2016-08-01

Full Text Available Laboratory education in science and engineering often entails the use of test-beds equipped with costly peripherals for sensing, acquisition, storage, processing, and control of physical behavior. However, costly peripherals are no longer necessary to obtain precise measurements and achieve stable feedback control of test-beds. With smartphones performing diverse sensing and processing tasks, this study examines the feasibility of mounting smartphones directly to test-beds to exploit their embedded hardware and software in the measurement and control of the test-beds. This approach is a first step towards replacing laboratory-grade peripherals with more compact and affordable smartphone-based platforms, whose interactive user interfaces can engender wider participation and engagement from learners. Demonstrative cases are presented in which the sensing, computation, control, and user interaction with three motor-based test-beds are handled by a mounted smartphone. Results of experiments and simulations are used to validate the feasibility of mounted smartphones as measurement and feedback control platforms for motor-based laboratory test-beds, report the measurement precision and closed-loop performance achieved with such platforms, and address challenges in the development of platforms to maintain system stability.

Mounted Smartphones as Measurement and Control Platforms for Motor-Based Laboratory Test-Beds.

Science.gov (United States)

Frank, Jared A; Brill, Anthony; Kapila, Vikram

2016-08-20

Laboratory education in science and engineering often entails the use of test-beds equipped with costly peripherals for sensing, acquisition, storage, processing, and control of physical behavior. However, costly peripherals are no longer necessary to obtain precise measurements and achieve stable feedback control of test-beds. With smartphones performing diverse sensing and processing tasks, this study examines the feasibility of mounting smartphones directly to test-beds to exploit their embedded hardware and software in the measurement and control of the test-beds. This approach is a first step towards replacing laboratory-grade peripherals with more compact and affordable smartphone-based platforms, whose interactive user interfaces can engender wider participation and engagement from learners. Demonstrative cases are presented in which the sensing, computation, control, and user interaction with three motor-based test-beds are handled by a mounted smartphone. Results of experiments and simulations are used to validate the feasibility of mounted smartphones as measurement and feedback control platforms for motor-based laboratory test-beds, report the measurement precision and closed-loop performance achieved with such platforms, and address challenges in the development of platforms to maintain system stability.

Interfacing the septa movement (DC motor) equipment to the PS control system and the MIL1553 bus

CERN Document Server

Dehavay, Claude

1993-01-01

Continuing the rejuvenation of the PS Control system , it is planned to replace the Single Transceiver Hybrid used to interface the Septa Movement Equipment by a G64 system connected to the VME crate via the MIL1553 bus. This note explains the G64 hardware interface and details the standard message as defined in the Control Protocole for Power Converter, RF and Stepping Motor equipment.

Experience of Implementing a Distributed Control System for Thermal and Mechanical and Electrical Equipment at the South-West CHP

Energy Technology Data Exchange (ETDEWEB)

Babkin, K. V., E-mail: babkin@uztec.ru; Tsvetkov, M. S.; Kostyuk, R. I.; Chugin, A. V. [SC “South-West CHP” (Russian Federation); Bilenko, V. A.; Molchanov, K. A.; Fedunov, V. V. [JSC “Interautomatika” (Russian Federation)

2015-01-15

Results of implementing an SPPA-T3000-based unified distributed control system for thermal and mechanical and electrical equipment at the South-West CHP are discussed. Hardware solutions for integration with local control systems, control of electrical equipment in compliance with the standards IEC 61850, Modbus RTU, and communication between the plant control system and the System Operator of the Unified Power System are described.

Experience of Implementing a Distributed Control System for Thermal and Mechanical and Electrical Equipment at the South-West CHP

International Nuclear Information System (INIS)

Babkin, K. V.; Tsvetkov, M. S.; Kostyuk, R. I.; Chugin, A. V.; Bilenko, V. A.; Molchanov, K. A.; Fedunov, V. V.

2015-01-01

Results of implementing an SPPA-T3000-based unified distributed control system for thermal and mechanical and electrical equipment at the South-West CHP are discussed. Hardware solutions for integration with local control systems, control of electrical equipment in compliance with the standards IEC 61850, Modbus RTU, and communication between the plant control system and the System Operator of the Unified Power System are described

Design and construction rules for electrical equipments of nuclear islands. 3. ed.

International Nuclear Information System (INIS)

1993-01-01

The French design and construction for electrical equipments of nuclear islands (RCC-E) deals with equipments of which the failure may have consequences on the safety of persons or appreciable effects on the availability of the power plant. This book presents the rules concerning (1) qualification procedure, (2) the design of functional units, (3) the installation (environmental conditions, protection rules), (4) the constituent elements of equipments, (5) the control and testing methods

CONTROL DE MALEZA EN DISTRITOS DE RIEGO CON EQUIPOS LIGEROS WEED CONTROL IN IRRIGATION DISTRICTS WITH LIGHT WEIGHT EQUIPMENT

Directory of Open Access Journals (Sweden)

José Ramón Lomelí Villanueva

2010-12-01

Full Text Available En México el control mecánico de maleza, tradicionalmente se realizaba con maquinaria inadecuada lo cual provocaba daños en los taludes y modificaciones de la sección hidráulica. Para resolver este problema, actualmente se utilizan los equipos ligeros que permiten el desarrollo de una cubierta vegetal, que no interfiere con el flujo del agua y su sistema radical retiene el suelo, lo cual reduce la erosión y mantiene en condiciones estables los taludes. El presente trabajo aborda los aspectos relativos a características y criterios para la selección de los implementos y la secuencia para su utilización. El costo de las operaciones para el control de maleza en canales, drenes y caminos se ha reducido un 39,21% con respecto a utilizar maquinaria inadecuada. La versatilidad de los equipos ligeros permite emplear el implemento más adecuado para cada tipo de maleza. En México, el inventario actual es de 263 equipos ligeros que tienen un potencial de aplicación para el control de la maleza, en la totalidad de los caminos, el 90% de canales y el 70% de drenes de los Distritos de Riego.In Mexico, the mechanical weed control was traditionally carried out with inadequate equipment which caused damage to the slopes and changes in the hydraulic section. In order to solve this problem, light weight equipment is currently being used to allow the development of a vegetation cover to retain soil with no interference with water flow, reducing erosion and maintaining stable conditions in the slopes. This paper addresses aspects related to characteristics and criteria for selecting and sequencing tools for use. The costs of weed control in irrigation channels, drains and roads have been reduced 39.21% compared to using inadequate equipment. The versatility of light weight equipment allows the use of the most appropriate implement for each weed. In Mexico, the current inventory includes 263 light weight devices with which a potential weed control of 90

Validation Testing for Automated Solubility Measurement Equipment Final Report

Energy Technology Data Exchange (ETDEWEB)

Lachut, J. S. [Washington River Protection Solutions LLC, Richland, WA (United States)

2016-01-11

Laboratory tests have been completed to test the validity of automated solubility measurement equipment using sodium nitrate and sodium chloride solutions (see test plan WRPS-1404441, “Validation Testing for Automated Solubility Measurement Equipment”). The sodium nitrate solution results were within 2-3% of the reference values, so the experiment is considered successful using the turbidity meter. The sodium chloride test was done by sight, as the turbidity meter did not work well using sodium chloride. For example, the “clear” turbidity reading was 53 FNU at 80 °C, 107 FNU at 55 °C, and 151 FNU at 20 °C. The sodium chloride did not work because it is granular and large; as the solution was stirred, the granules stayed to the outside of the reactor and just above the stir bar level, having little impact on the turbidity meter readings as the meter was aimed at the center of the solution. Also, the turbidity meter depth has an impact. The salt tends to remain near the stir bar level. If the meter is deeper in the slurry, it will read higher turbidity, and if the meter is raised higher in the slurry, it will read lower turbidity (possibly near zero) because it reads the “clear” part of the slurry. The sodium chloride solution results, as measured by sight rather than by turbidity instrument readings, were within 5-6% of the reference values.

Verification of BGA type FPGA logic applied to a control equipment with Safety Class using the special socket

International Nuclear Information System (INIS)

Chung, YounHu; Yoo, Kwanwoo; Lee, Myeongkyun; Yun, Donghwa

2015-01-01

This article aims to provide the verification method for BGA-type FPGA of Programmable Logic Controller (PLC) developed as Safety Class. The logic of FPGA in the control device with Safety Class is the circuit to control overall logic of PLC. This device converts to the different module from the input signals for both digital and analogue of the equipment in the field and outputs their data. In addition, it should perform the logical controls such as backplane communication control and data communication. We suggest acquiring method of the data signal with efficient logic using the socket in this article. Proposed test socket is made by simpler process than former one, and the process is done in batches by which cost can be reduces, and the test socket can be quickly produced in response to any request. Also, it is possible to reduce the wear by reducing the contact force of the ball phenomenon. The structure on the basis of silicon can be reduced the modification, and it has excellent linearity. At the logic verification, the operation that state data block is designed in the FPGA could be easily confirmed by using a socket

Radon removal equipment based on aeration: A literature study of tests performed in Sweden between 1981 and 1996

International Nuclear Information System (INIS)

Mjoenes, L.

2000-02-01

In Sweden some principles to reduce the radon concentration in drinking water were tested in the beginning of the 1980s. Spray aeration under atmospheric pressure, diffused bubble aeration, aeration in the pressure tank and different combinations of these principles were studied. Aeration in the drill hole and adsorption on granulated activated char-coal were also tested. The best results, about 70 % reduction, were obtained with aeration in the pressure tank with a spray system combined with diffused air bubbling. The Oerebro project in the beginning of the 1990s included on site testing of five different aeration solutions: Aeration in the drill hole, aeration in the storage tank, ejector aeration, shallow tray aeration and packed column aeration. The radon removal efficiency varied between 20 % and 99 %. In 1994 a study intended to test the radon removal capacity of different water treatment equipment was performed. Six units of radon separators were included but most of the tested equipment was installed for other water treatment purposes. The performed measurements showed that the only types of equipment that reduce the radon concentration efficiently are radon separators and reverse osmosis filters. The radon removal capacity of the radon separators varied between 23 % and 97 %. In 1996 the nine most common radon separators on the Swedish market were tested. The results showed that the tested radon removal equipment worked well, although the technical quality and chosen technical solutions were not always the best. The radon removal capacity of the units participating in this test was in most cases between 96 and 99 %. In some cases the capacity exceeded 99 %. In order to reach this radon removal capacity the water must be recirculated in a storage tank under atmospheric pressure

Radon removal equipment based on aeration: A literature study of tests performed in Sweden between 1981 and 1996

Energy Technology Data Exchange (ETDEWEB)

Mjoenes, L

2000-02-01

In Sweden some principles to reduce the radon concentration in drinking water were tested in the beginning of the 1980s. Spray aeration under atmospheric pressure, diffused bubble aeration, aeration in the pressure tank and different combinations of these principles were studied. Aeration in the drill hole and adsorption on granulated activated char-coal were also tested. The best results, about 70 % reduction, were obtained with aeration in the pressure tank with a spray system combined with diffused air bubbling. The Oerebro project in the beginning of the 1990s included on site testing of five different aeration solutions: Aeration in the drill hole, aeration in the storage tank, ejector aeration, shallow tray aeration and packed column aeration. The radon removal efficiency varied between 20 % and 99 %. In 1994 a study intended to test the radon removal capacity of different water treatment equipment was performed. Six units of radon separators were included but most of the tested equipment was installed for other water treatment purposes. The performed measurements showed that the only types of equipment that reduce the radon concentration efficiently are radon separators and reverse osmosis filters. The radon removal capacity of the radon separators varied between 23 % and 97 %. In 1996 the nine most common radon separators on the Swedish market were tested. The results showed that the tested radon removal equipment worked well, although the technical quality and chosen technical solutions were not always the best. The radon removal capacity of the units participating in this test was in most cases between 96 and 99 %. In some cases the capacity exceeded 99 %. In order to reach this radon removal capacity the water must be recirculated in a storage tank under atmospheric pressure.

Results from Operational Testing of the Siemens Smart Grid-Capable Electric Vehicle Supply Equipment

Energy Technology Data Exchange (ETDEWEB)

Bennett, Brion [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-05-01

The Idaho National Laboratory conducted testing and analysis of the Siemens smart grid capable electric vehicle supply equipment (EVSE), which was a deliverable from Siemens for the U.S. Department of Energy FOA-554. The Idaho National Laboratory has extensive knowledge and experience in testing advanced conductive and wireless charging systems though INL’s support of the U.S. Department of Energy’s Advanced Vehicle Testing Activity. This document details the findings from the EVSE operational testing conducted at the Idaho National Laboratory on the Siemens smart grid capable EVSE. The testing conducted on the EVSE included energy efficiency testing, SAE J1772 functionality testing, abnormal conditions testing, and charging of a plug-in vehicle.

Improvement of remote control system of automatic ultrasonic equipment for inspection of reactor pressure vessel

International Nuclear Information System (INIS)

Cheong, Yong Moo; Jung, H. K.; Joo, Y. S.; Koo, K. M.; Hyung, H.; Sim, C. M.; Gong, U. S.; Kim, S. H.; Lee, J. P.; Rhoo, H. C.; Kim, M. S.; Ryoo, S. K.; Choi, C. H.; Oh, K. I.

1999-12-01

One of the important issues related to the nuclear safety is in-service inspection of reactor pressure vessel (RPV). A remote controlled automatic ultrasonic method is applied to the inspection. At present the automatic ultrasonic inspection system owned by KAERI is interrupted due to degradation of parts. In order to resume field inspection new remote control system for the equipment was designed and installed to the existing equipment. New ultrasonic sensors and their modules for RPV inspection were designed and fabricated in accordance with the new requirements of the inspection codes. Ultrasonic sensors were verified for the use in the RPV inspection. (author)

Lighting Control System for Premises with Display Screen Equipment

Science.gov (United States)

Kudryashov, A. V.

2017-11-01

The use of Display Screen Equipment (DSE) at enterprises allows one to increase the productivity and safety of production, minimize the number of personnel and leads to the simplification of the work of specialists, but on the other side, changes usual working conditions. If the personnel works with displays, visual fatigue develops more quickly which contributes to the emergence of nervous tension, stress and possible erroneous actions. Low interest of the lighting control system developers towards the rooms with displays is dictated by special requirements for coverage by sanitary and hygienic standards (limiting excess workplace illumination). We decided to create a combined lighting system which works considering daylight illumination and artificial light sources. The brightness adjustment of the LED lamps is carried out according to the DALI protocol, adjustment of the natural illumination by means of smart glasses. The technical requirements for a lighting control system, the structural-functional scheme and the algorithm for controlling the operation of the system have been developed. The elements of control units, sensors and actuators have been selected.

40 CFR 63.2994 - How do I verify the performance of monitoring equipment?

Science.gov (United States)

2010-07-01

... equipment? (a) Before conducting the performance test, you must take the steps listed in paragraphs (a)(1) and (2) of this section: (1) Install and calibrate all process equipment, control devices, and... evaluation results. (b) If you use a thermal oxidizer, the temperature monitoring device must meet the...

Electrical and control equipment in nuclear power plants. Problems when replacing aging equipment

International Nuclear Information System (INIS)

Nordling, Anna; Haakansson, Goeran

2012-01-01

Interoperability between different technical systems is more complicated when old and new technology meet, such as between analog and digital technology. New electrical and I and C equipment is selected with consideration to simplify and improve the compatibility and interoperability. The original construction of nuclear power plants with electricity and I and C equipment had more natural interfaces. Generally experienced guidance, to the management of interoperability and interfaces, feels insufficient. Skills transfer programs are identified as a major need, as more and more important personnel are retiring and important information is lost with them. Lack of appropriate skills directly affects the ability to produce accurate and complete requirements specification. Failure modes of newer electrical and I and C equipment are perceived as more complex than the older equipment. When choosing equipment, attempts are made to minimize unnecessary features, to reduce the number of potential failure modes. There is a lack of consistent understanding of the meaning of robustness in electrical technology and I and C technology, in the nuclear plant engineering departments. The overall picture is that the robustness has worsened since the facilities were built. The Swedish nuclear power plants have an internal organizational structure with separated client and support organization. This splits the nuclear organization into two distinct parts which threaten to separate the two entities focus. Engineering departments at the Swedish nuclear power plants express a need for increased expertise in the client organization (blocks). Competence requested is for example, system knowledge to facilitate and enhance the quality of the initial analysis performed in the blocks. Suppliers receive more recently larger turnkey projects, both to minimize costs but also to minimize the interfaces and co-function problems. This, however, heightens demands for knowledge transfer between

CONTROL SYSTEM FOR UNMANNED AIRCRAFT EQUIPPED WITH ROBOTICS ARM

Directory of Open Access Journals (Sweden)

Alexei A. Margun

2014-11-01

Full Text Available The paper deals with the problem of control system synthesis for multi rotational UAV equipped with robotics arm. Control algorithm is proposed based on the method of feedback linearization and synthesis of proportional-differential controller with the real time computation of the inertia tensor and center of mass changes and compensation of the reactive torque generated by the dynamics of the manipulator. Quadrocopter with attached articulated manipulator is selected as a model of the control object. Systems of equations describing the behavior of considered dynamical system are obtained according to the Newton and Euler-Lagrange laws. Expressions are offered, defining the inertia tensor and the position of the system center of mass depending on the current position of the manipulator, and the torque acting on the quadrocopter from the manipulator. Feedback linearization with arm influence compensation on quadrocopter is applied for the resulting nonlinear coupled system. As a result, robot dynamics equations have been converted to a linear stationary system. Converted system control is achieved by a proportional-differential controller. Examined system simulation is done with control method described in the paper and the classical method based on a proportional-differential controller. Simulation results confirm the effectiveness of the proposed approach and demonstrate that the proposed approach provides higher accuracy of the tracking error, than control method by means of proportional-differential regulator.

Retrieval of buried waste using conventional equipment

International Nuclear Information System (INIS)

Valentich, D.J.

1994-01-01

A field test was conducted to determine the effectiveness of using conventional type construction equipment for the retrieval of buried transuranic (TRU) waste. A cold (nonhazardous and nonradioactive test pit 841 m 3 in volume) was constructed with boxes and drums filled with simulated waste materials, such as metal, plastic, wood, concrete, and sludge. Large objects, including truck beds, vessels, vaults, pipes, and beams were also placed in the pit. These materials were intended to simulate the type of waste found in existing TRU buried waste pits and trenches. A series of commercially available equipment items, such as excavators and tracked loaders outfitted with different end effectors, were used to remove the simulated waste. Work was performed from both the abovegrade and belowgrade positions. During the demonstration, a number of observations, measurements, and analyses were performed to determine which equipment was the most effective in removing the waste. The retrieval rates for the various excavation techniques were recorded. The inherent dust control capabilities of the excavation methods used were also observed

Development of hot test equipment for advanced nuclear fuel cycle development in JNC

International Nuclear Information System (INIS)

Nomura, K.; Shibata, A.; Nemoto, S.; Aoshima, A.; Funasaka, H.

2001-01-01

JNC (Japan nuclear fuel cycle development institute) has been developing a mini centrifugal contactor. JNC has experience of the development of the RETF (Recycle equipment test facility; under construction at Tokai-works) type centrifugal contactor and the mini centrifugal contactor is designed on the basis of this knowledge. The followings were carried out in order to estimate the performance of the mini centrifugal contactor: functional test for evaluating basic performance of this extractor, acid-solvent test and uranium test for confirming that sufficient performance is attained. The results showed wide performance in comparison with the mini mixer settler used so far and it is expected that shortening in operating time and higher efficiency of extracting tests will be achieved. (author)

Investigation and realization of an automatic device for the control and test of a photon tagging system

International Nuclear Information System (INIS)

Fallou, J.L.

1987-12-01

An intelligent control/test equipment for a monoenergetic photon production system was developed. The device enables simulations to be done outside experimental runs. Operation can be entirely automatic, or controlled by the experimenters. The device is modular and conforms to CAMAC standards. The architecture of the system is based around a local bus which comprises a central unit and its memory; a programmable pulse generator; a switching circuit to test and control the various paths; and a unit to communicate with the acquisition system [fr

Data acquisition, remote control and equipment monitoring for ISOLDE RILIS

CERN Document Server

Rossel, R E; Richter, D; Wendt, K D A; Rothe, S; Marsh, B A

2013-01-01

With a steadily increasing on-line operation time up to a record 3000 h in the year 2012, the Resonance Ionization Laser Ion Source (RILIS) is one of the key components of the ISOLDE on-line isotope user facility at CERN. Ion beam production using the RILIS is essential for many experiments due to the unmatched combination of ionization efficiency and selectivity. To meet the reliability requirements the RILIS is currently operated in shift duty for continuous maintenance of crucial laser parameters such as wavelength, power, beam position and timing, as well as ensuring swift intervention in case of an equipment malfunction. A recent overhaul of the RILIS included the installation of new pump lasers, commercial dye lasers and a complementary, fully solid-state titanium:sapphire laser system. The framework of the upgrade also required the setup of a network-extended, LabVIEW-based system for data acquisition, remote control and equipment monitoring, to support RILIS operators as well as ISOLDE users. The syst...

Process equipment data organisation in CERN PS controls

International Nuclear Information System (INIS)

Casalegno, L.; Cuperus, J.; Sicard, C.H.

1990-01-01

The CERN PS control system has a widely distributed architecture, mainly for fast response in a real-time environment. The organisation of the data for equipment access must be compatible with this architecture and give efficient program access to the data. Moreover, it must also offer managerial features such as data integrity, easy backup and restoration, adaptibility to changes in data structure, initialisation, data-entry facilities and automatic documentation. This paper shows how one can take advantage of a commercial data-base management system with its associated tools, adding to it some object-oriented programming concepts to meet the objectives of a manageable distributed data organisation having good run-time performance features and using a reasonable manpower investment. (orig.)

Test equipment used for radiation protection type testing of aerosol filters at the National Board of Nuclear Safety and Radiation Protection (SAAS)

International Nuclear Information System (INIS)

Ullmann, W.; Przyborowski, S.

1977-01-01

Following a description of the overall design of test equipment developed in the SAAS for radiation protection type testing of aerosol filters, the most important physical and technical details concerning the preparation and measurement of test aerosols as well as the sampling procedure upstream and downstream of the filter to the tested, are comprehensively discussed. Furthermore, experiences gained during several years with different devices for mixing and diluting the aerosols are reported. (author)

Non-destructive testing: magnetizing equipment for magnetic particle inspection

International Nuclear Information System (INIS)

1975-07-01

Magnetizing equipment for magnetic particle inspection serves to produce a magnetic field of suitable size and direction in a workpiece under examination. The characteristic parameters of this equipment are given in this standard along with their method of determination if this is necessary. (orig./AK) [de

Equipment for functional testing of the ALADIN TXA pulsed laser head

Science.gov (United States)

Emanuele, Stucchi; Franco, Trespidi; Enzo, Nava

2017-11-01

It is described a measurement instrument, used as Optical Ground Support Equipment, capable of performing the characterization of a pulsed laser beam. The instrument was developed for the functional testing of the EQM and FMs of the ALADIN laser transmitter (TXA). The performed measurements are: beam shaping, M2 measurement, beam angular stability, energy and wavelength measurements, pulse duration, polarization, pulse shape and spectral characterization, optical frequency stability measurement. The measurement system can work in automatic mode performing several measurements and providing automatic report generation.

Equipment design guidance document for flammable gas waste storage tank new equipment

International Nuclear Information System (INIS)

Smet, D.B.

1996-01-01

This document is intended to be used as guidance for design engineers who are involved in design of new equipment slated for use in Flammable Gas Waste Storage Tanks. The purpose of this document is to provide design guidance for all new equipment intended for application into those Hanford storage tanks in which flammable gas controls are required to be addressed as part of the equipment design. These design criteria are to be used as guidance. The design of each specific piece of new equipment shall be required, as a minimum to be reviewed by qualified Unreviewed Safety Question evaluators as an integral part of the final design approval. Further Safety Assessment may be also needed. This guidance is intended to be used in conjunction with the Operating Specifications Documents (OSDs) established for defining work controls in the waste storage tanks. The criteria set forth should be reviewed for applicability if the equipment will be required to operate in locations containing unacceptable concentrations of flammable gas

Multi-parameter decoupling and slope tracking control strategy of a large-scale high altitude environment simulation test cabin

Directory of Open Access Journals (Sweden)

Li Ke

2014-12-01

Full Text Available A large-scale high altitude environment simulation test cabin was developed to accurately control temperatures and pressures encountered at high altitudes. The system was developed to provide slope-tracking dynamic control of the temperature–pressure two-parameter and overcome the control difficulties inherent to a large inertia lag link with a complex control system which is composed of turbine refrigeration device, vacuum device and liquid nitrogen cooling device. The system includes multi-parameter decoupling of the cabin itself to avoid equipment damage of air refrigeration turbine caused by improper operation. Based on analysis of the dynamic characteristics and modeling for variations in temperature, pressure and rotation speed, an intelligent controller was implemented that includes decoupling and fuzzy arithmetic combined with an expert PID controller to control test parameters by decoupling and slope tracking control strategy. The control system employed centralized management in an open industrial ethernet architecture with an industrial computer at the core. The simulation and field debugging and running results show that this method can solve the problems of a poor anti-interference performance typical for a conventional PID and overshooting that can readily damage equipment. The steady-state characteristics meet the system requirements.

Nondestructive control of materials by ultrasonic tests

International Nuclear Information System (INIS)

Mercier, Noelle.

1974-01-01

A bibliographic study of nondestructive control methods of solids by ultrasonic tests, and of the ultrasonic emission of a transducer of finite dimension, is first presented. The principle of two of these methods is verified experimentally; they should permit the measurement of various physical parameters of solids, and the detection of local inhomogeneities. The first method calls upon the analysis of the ultrasonic signal (amplitude and phase), after it has crossed a constant thickness of a metallic specimen. This analysis reveals variations of attenuation and of ultrasonic propagation velocity within the specimen. A good spatial resolution is obtained by using 1mm-diameter probes. The second method leads, thanks to a test rig equipped with broad frequency band electrostatic transducers, to the knowledge of the attenuation law of the specimens as a function of frequency (present range: 5 to 15MHz); from this a classification of these specimens as regards their granulometry is deduced [fr

Hot roller embossing system equipped with a temperature margin-based controller

Energy Technology Data Exchange (ETDEWEB)

Kim, Seyoung, E-mail: seyoungkim@kimm.re.kr; Son, Youngsu; Lee, Sunghee; Ham, Sangyong; Kim, Byungin [Department of Robotics and Mechatronics, Korea Institute of Machinery and Materials (KIMM), Daejeon (Korea, Republic of)

2014-08-15

A temperature control system was proposed for hot roller embossing. The roll surface was heated using induction coils and cooled with a circulating chilled water system. The temperature of the roll surface was precisely controlled by a temperature margin-based control algorithm that we developed. Implementation of the control system reduced deviations in the roll surface temperature to less than ±2 °C. The tight temperature control and the ability to rapidly increase and decrease the roll temperature will allow optimum operating parameters to be developed quickly. The temperature margin-based controller could also be used to optimize the time course of electrical power and shorten the cooling time by choosing an appropriate temperature margin, possibly for limited power consumption. The chiller-equipped heating roll with the proposed control algorithm is expected to decrease the time needed to determine the optimal embossing process.

Hot roller embossing system equipped with a temperature margin-based controller

International Nuclear Information System (INIS)

Kim, Seyoung; Son, Youngsu; Lee, Sunghee; Ham, Sangyong; Kim, Byungin

2014-01-01

A temperature control system was proposed for hot roller embossing. The roll surface was heated using induction coils and cooled with a circulating chilled water system. The temperature of the roll surface was precisely controlled by a temperature margin-based control algorithm that we developed. Implementation of the control system reduced deviations in the roll surface temperature to less than ±2 °C. The tight temperature control and the ability to rapidly increase and decrease the roll temperature will allow optimum operating parameters to be developed quickly. The temperature margin-based controller could also be used to optimize the time course of electrical power and shorten the cooling time by choosing an appropriate temperature margin, possibly for limited power consumption. The chiller-equipped heating roll with the proposed control algorithm is expected to decrease the time needed to determine the optimal embossing process

Development of In situ Geological Investigation and Test Equipment in KURT

Energy Technology Data Exchange (ETDEWEB)

Koh, Yong Kweon; Kim, Kyung Su; Park, Kyung Woo; Koh, Yong Kweon; Choi, Jong Won [KAERI, Daejeon (Korea, Republic of)

2010-12-15

For establishment of the advanced infrastructures of KURT, geological investigation and in situ test equipment were installed. The optical sensor technique could be applicable to monitoring system for the safe operation of various kinds of facilities having static and/or dynamic characteristics, such as chemical plant, pipeline, rail, huge building, long and slim structures, bridge, subway and marine vessel. etc. The micro-seismic monitoring system is able to predict the location and timing of fracturing of rock mass and rock fall around an underground openings as well as analysis on safety of various kinds of engineering structures such as nuclear facilities and other structures. The straddle packer system for hydro-testing in a deep borehole will lead to not only improve current technical level in the field of hydraulic testing but also provide important information to radioactive waste disposal technology development and site characterization project

Experimental Issues in Testing a Semiactive Technique to Control Earthquake Induced Vibration

Directory of Open Access Journals (Sweden)

Nicola Caterino

2014-01-01

Full Text Available This work focuses on the issues to deal with when approaching experimental testing of structures equipped with semiactive control (SA systems. It starts from practical experience authors gained in a recent wide campaign on a large scale steel frame structure provided with a control system based on magnetorheological dampers. The latter are special devices able to achieve a wide range of physical behaviours using low-power electrical currents. Experimental activities involving the use of controllable devices require special attention in solving specific aspects that characterize each of the three phases of the SA control loop: acquisition, processing, and command. Most of them are uncommon to any other type of structural testing. This paper emphasizes the importance of the experimental assessment of SA systems and shows how many problematic issues likely to happen in real applications are also present when testing these systems experimentally. This paper highlights several problematic aspects and illustrates how they can be addressed in order to achieve a more realistic evaluation of the effectiveness of SA control solutions. Undesired and unavoidable effects like delays and control malfunction are also remarked. A discussion on the way to reduce their incidence is also offered.

40 CFR 85.2231 - On-board diagnostic test equipment requirements.

Science.gov (United States)

2010-07-01

... PROGRAMS (CONTINUED) CONTROL OF AIR POLLUTION FROM MOBILE SOURCES Emission Control System Performance... evaluation status of supported monitors (test complete/test not complete) in Mode $01 PID $01, as well as be... have the capability to include bi-directional communication for control of the evaporative canister...

First test of a CMS DT chamber equipped with full electronics in a muon beam

CERN Multimedia

Jesus Puerta-Pelayo

2003-01-01

A CMS DT chamber of MB3 type, equipped with the final version of a minicrate (containing all on-chamber trigger and readout electronics), was tested in a muon beam for the first time. The beam was bunched in 25 ns spills, allowing an LHC-like response of the chamber trigger. This test confirmed the excellent performance of the trigger design.

Development of a system for monitoring and diagnosis using Fuzzy logic in control valves of laboratory test equipment of Experimental Center Aramar

International Nuclear Information System (INIS)

Porto Junior, Almir Carlos Soares

2014-01-01

The question of components reliability, specifically process control valves, has become an important issue to be investigated in nuclear power plants and other areas such as refinery or offshore oil rig, considering the safety and life extension of the plant. The development of non intrusive monitoring and diagnostic method allows the identification of defects in components of the plant during normal operation. The objective of this dissertation is to present an analysis and diagnosis of control valves of a steam plant part that simulates the secondary circuit of a pressurized water reactor. This installation is part of propulsion equipment testing laboratory of the Brazilian Navy, at Ipero-SP. The methodology for design is based on graphical analysis of two parameters, the valve air pressure actuator and the displacement of the valve plug. These data are extracted by a smart positioner, part of Delta V™ Automation System. An analysis is implemented in detecting anomalies by an approach using Expert Systems by the technique of fuzzy logic. Once the basic measures of control valves are taken, it is possible to detect symptoms of failure, leakage, friction, damage, etc. The monitoring and diagnostic system has been designed in MATLAB® version 2009 th by the complement 'Fuzzy Logic Toolbox'. It is a noninvasive technique. Thus, it is possible to know what is happening with the chosen components, just analyzing the parameters of the valve. The software called ValveLink® (developed by Emerson) receives signals from hardware component (intelligent positioner) installed next to the control valve. These signals (electrical current) are transformed into information which are used input parameters: air pressure valve actuator and valve plug displacement. With the use of fuzzy logic, these parameters are interpreted. They suffer inferences by rules written by experts in valves. After these inferences, the information is processed and sent as output signals

Contact Dermatitis to Personal Sporting Equipment in Youth.

Science.gov (United States)

Marzario, Barbara; Burrows, Dianne; Skotnicki, Sandy

2016-07-01

Contact dermatitis to personal sporting equipment in youth is poorly studied. To review the results of patch testing 6 youth to their sporting equipment in a dermatology general private practice from 2006 to 2011. A retrospective analysis of 6 youth aged 11 to 14 who were evaluated for chronic and persistent dermatitis occurring in relation to sports equipment was conducted. All patients were subjected to epicutaneous (patch) testing, which included some or all of the following: North American Contact Dermatitis Group (NACGD) series, textile series, rubber series, corticosteroid series, and raw material from the patients' own personal equipment. All cases had 1 or more positive patch test reactions to an allergen within the aforementioned series, and 3 subjects tested positive to their personal equipment in raw form. Allergic contact dermatitis, not irritant, was deemed the relevant cause of chronic dermatitis in 4 of the 6 patients due to positive reactions to epicutaneous tests and/or personal equipment. The utility of testing to patients' own sporting equipment was shown to be of additional value and should be considered when patch testing for contact allergy to sporting equipment. © The Author(s) 2015.

INCREASING OF ECOLOGICAL EFFICIENCY OF WORN EQUIPMENT BY PARTIAL UPDATES. ANALYTICAL AND CONTROL ASPECT

Directory of Open Access Journals (Sweden)

S. Voinova

2017-12-01

Full Text Available The current state of worn industrial equipment and the resulting low performance indicators of its functioning, in particular, low environmental friendliness, are considered. It is shown that the normalization of the complex situation that has developed in production is an acute problem, the solution of which should begin with the implementation of a program for the partial renewal of worn equipment. It is pointed out that there is a high potential for improving the technological, including ecological, efficiency of functioning of the upgraded equipment. It is pointed out that the partial renewal is highly efficient, because of the small specific investments in it. The significant influence of the quality of control of the setting and implementation of the renewal program on its effectiveness was noted. It is shown that the process of renewal of worn-out equipment, ultimately, has an environmental focus, increases the environmental friendliness of the updated technical facility.

Charging equipment. Ladegeraet

Energy Technology Data Exchange (ETDEWEB)

Neumann, E

1981-09-17

The invention refers to a charging equipment, particularly on board charging equipment for charging traction batteries of an electric vehicle from the AC mains supply, consisting of a DC converter, which contains a controlled power transistor, a switching off unloading circuit and a power transmitter, where the secondary winding is connected in series with a rectifier diode, and a smoothing capacitor is connected in parallel with this series circuit. A converter module is provided, which consists of two DC voltage converters, whose power transistors are controlled by a control circuit in opposition with a phase displacement of 180/sup 0/.

Design and adjustment on test bed of replacing subassembly machine control system for China experimental fast reactor

International Nuclear Information System (INIS)

Dong Shengguo; Ma Hongsheng; Zhao Lixia

2008-01-01

The present research concerns in the design and adjustment of replacing sub- assembly machine control system of China Experimental Fast Reactor. The design of replacing subassembly machine control system adopts some electric equipments, such as programmable controllers, digital DC drivers. The designed control system was adjusted on the test bed. The results indicate that the operation of the control system is steady and reliable, and designed control system can meet the needs of the design specification. (authors)

Improvement of remote control system of automatic ultrasonic equipment for inspection of reactor pressure vessel

Energy Technology Data Exchange (ETDEWEB)

Cheong, Yong Moo; Jung, H. K.; Joo, Y. S.; Koo, K. M.; Hyung, H.; Sim, C. M.; Gong, U. S.; Kim, S. H.; Lee, J. P.; Rhoo, H. C.; Kim, M. S.; Ryoo, S. K.; Choi, C. H.; Oh, K. I

1999-12-01

One of the important issues related to the nuclear safety is in-service inspection of reactor pressure vessel (RPV). A remote controlled automatic ultrasonic method is applied to the inspection. At present the automatic ultrasonic inspection system owned by KAERI is interrupted due to degradation of parts. In order to resume field inspection new remote control system for the equipment was designed and installed to the existing equipment. New ultrasonic sensors and their modules for RPV inspection were designed and fabricated in accordance with the new requirements of the inspection codes. Ultrasonic sensors were verified for the use in the RPV inspection. (autho0008.

The effect of smoke from plastics on digital communications equipment

International Nuclear Information System (INIS)

Tanaka, T.J.; Chapin, J.T.

1998-01-01

Smoke from plastics can cause immediate problems in electrical equipment in the form of shorting and increased leakage currents, as well as long-term corrosion (metal loss). The short-term problems can be especially serious for critical control instrumentation such as that found in nuclear reactors or telecommunications systems. The US Nuclear Regulatory Commission and Sandia National Laboratories are sponsoring a program to determine the modes and probabilities of digital equipment failure during exposure to smoke and up to 24 hours after the exposure. Early tests on computer systems have shown that the most common immediate problems are temporary and are likely to be caused by increased leakage currents. High-voltage circuits are especially vulnerable since the charged particles in smoke are drawn to those surfaces. To study failure probabilities, smoke exposure tests with real-time measurements will be carried out to determine how the electrical properties of the environment are affected by smoke concentration and content. Digital communication cable will be included in the tests because temporary shorts that cannot be detected through dc measurements may cause interruptions in communications between computers. The reaction of the equipment to changed electrical properties of the environment will be modeled. Equipment that can be used for testing and modeling is being solicited

Mounted Smartphones as Measurement and Control Platforms for Motor-Based Laboratory Test-Beds †

Science.gov (United States)

Frank, Jared A.; Brill, Anthony; Kapila, Vikram

2016-01-01

Laboratory education in science and engineering often entails the use of test-beds equipped with costly peripherals for sensing, acquisition, storage, processing, and control of physical behavior. However, costly peripherals are no longer necessary to obtain precise measurements and achieve stable feedback control of test-beds. With smartphones performing diverse sensing and processing tasks, this study examines the feasibility of mounting smartphones directly to test-beds to exploit their embedded hardware and software in the measurement and control of the test-beds. This approach is a first step towards replacing laboratory-grade peripherals with more compact and affordable smartphone-based platforms, whose interactive user interfaces can engender wider participation and engagement from learners. Demonstrative cases are presented in which the sensing, computation, control, and user interaction with three motor-based test-beds are handled by a mounted smartphone. Results of experiments and simulations are used to validate the feasibility of mounted smartphones as measurement and feedback control platforms for motor-based laboratory test-beds, report the measurement precision and closed-loop performance achieved with such platforms, and address challenges in the development of platforms to maintain system stability. PMID:27556464

Management of radiodiagnostic equipment: Implementation of self-maintenance project of the conventional x-ray equipment of Hospital Universitario Clementino Fraga Filho - HUCFF-UFRJ

International Nuclear Information System (INIS)

Couto, N.F. do; Azevedo, A.C.P.; Koch, H.A.

2001-01-01

The project aims the implantation of a management program, for the maintenance of the conventional X-ray equipment at HUCFF. It has been implemented through the training of the electronic technicians who work at the Hospital. Essential courses were organized such as: Basics of Radioprotection, Radiographs Techniques, and Maintenance of equipment of X-Rays. Equipment: a library with the schemes of the equipment is being assembled in collaboration with UNICAMP. In order to manage the process, a software was created using the tools of the total quality for control of the maintenance. Preliminary tests: the equipment and their working conditions were evaluated, as well as the level of the employees' satisfaction with their use. The creation of a new routine for maintenance seeks to assist the demands of the new legislation in Brazil 5, and also reduce the costs to improve the quality of the images in the Radiodiagnostic Service. (author)

Evaluation of cold testing for Tokai Vitrification Facility

International Nuclear Information System (INIS)

Yoshioka, Masahiro; Inada, Eiichi

1994-01-01

The cold testing of the Tokai Vitrification Facility (TVF) was completed at the end of March, 1994 through the tests of nearly two years since May in 1992. The cold testing was carried out in order to evaluate the process equipment, product quality control, remote maintenance capability. The test results shown that TVF has enough performance with safety to treat the liquid waste in each process, and to control the product quality. For the remote maintenance of process equipment in the vitrification cell, the remote maintenance capability was confirmed for all remote equipment in the cell. The improvements were taken for some equipment with problem from the point of the operability and maintenance. It was confirmed by these test results that the TVF can go forward to the hot test operation using actual waste. (author)

Seismic qualification of non-safety class equipment whose failure would damage safety class equipment

International Nuclear Information System (INIS)

LaSalle, F.R.

1991-01-01

Both Code of Federal Regulations, Title 10, Part 50, and US Department of Energy Order 6340.1A have requirements to assess the interaction of non-safety and safety class structures and equipment during a seismic event to maintain the safety function. At the Hanford Site, a cost effective program has been developed to perform the evaluation of non-safety class equipment. Seismic qualification is performed by analysis, test, or upgrading of the equipment to ensure the integrity of safety class structures and equipment. This paper gives a brief overview and synopsis that address design analysis guidelines including applied loading, damping values, component anchorage, allowable loads, and stresses. Test qualification of equipment and walkdown acceptance criteria for heating ampersand ventilation (H ampersand V) ducting, conduit, cable tray, missile zone of influence, as well as energy criteria are presented

Proposed limiting values for performance criteria in acceptance testing of diagnostic X-ray equipment in the Federal Republic of Germany

International Nuclear Information System (INIS)

Baeuml, A.

1989-01-01

In the Federal Republic of Germany a new X-ray ordinance came into force in 1988 containing a specific paragraph on quality assurance for all medical X-ray units stipulating acceptance tests, regular checks and supervision by medical bodies and the competent authorities. Acceptance testing is to be performed by engineers from equipment suppliers of manufacturers in new and existing installations. It is expected that the service engineers will adjust the equipment in such a way as to obtain optimal performance before measurements are made, the results of which are to be stated in a certificate describing quality status of the equipment. A working group has developed guidelines for these acceptance tests. Items to be measured are reported and proposed limiting values and their tolerances are discussed. (author)

Proposed limiting values for performance criteria in acceptance testing of diagnostic X-ray equipment in the Federal Republic of Germany

International Nuclear Information System (INIS)

Baeuml, A.

1989-01-01

In the Federal Republic of Germany a new X-ray ordinance came into force in 1988 containing a specific paragraph on quality assurance for all medical X-ray units stipulating acceptance tests, regular checks and supervision by medical bodies and the competent authorities. Acceptance testing is to be performed by engineers from the equipment suppliers or manufacturers in new and also existing installations. It is expected that the service engineers will adjust the equipment in such a way as to obtain optimal performance before measurements are made, the results of which are to be stated in a certificate describing the quality status of the equipment. A working group has developed guidelines for these acceptance tests. The items to be measured are reported and the proposed limiting values and their tolerances are discussed. (author)

Investigation of potential fire-related damage to safety-related equipment in nuclear power plants

International Nuclear Information System (INIS)

Wanless, J.

1985-11-01

Based on a review of vendor information, fire damage reports, equipment qualification and hydrogen burn test results, and material properties, thirty-three types of equipment found in nuclear power plants were ranked in terms of their potential sensitivity to fire environments. The ranking considered both the functional requirements and damage proneness of each component. A further review of the seven top-ranked components was performed, considering the relative prevalence and potential safety significance of each. From this, relays and hand switches dominate as first choices for fire damage testing with logic equipment, power supplies, transmitters, and motor control centers as future candidates

Quality control of repair of equipment for coal preparation plants. Upravlenie kachestvom remonta oborudovaniya ugleobogatitel'nykh fabrik

Energy Technology Data Exchange (ETDEWEB)

Okonishnikov, A I; Neskoromnykh, V M; Surzhenko, V S; Sirichenko, R P; Pavlyuchenko, S G; Lesikov, A V

1984-01-01

The Ukrniiugleobogashchenie, Kalininsk and Sukhodol'sk coal preparation plants have developed the SUKRO system for control of repair quality of coal preparation equipment in the USSR. The system is based on a system of standards used in coal preparation plants. The following systems of standards used by the SUKRO system are analyzed: organization standards (order of repair in a coal preparation plant, repair planning, spare part systems, methods for determining equipment wear, analysis of equipment failures), standards for maintenance and repair (methods for equipment maintenance, service life of each equipment component or system, structure of preventive repair or repair, organizational models of repair operations, lubrication systems), standards for assessment of labor quality during repair operations. Use of the SUKRO system in the Sukhodol'sk coal preparation plant is evaluated. The SUKRO forms a system of standards for repair and maintenance of equipment considering operation conditions in coal preparation plants, requirements for equipment reliability and service life. (4 refs.)

Characterization of particle bound organic carbon from diesel vehicles equipped with advanced emission control technologies.

Science.gov (United States)

Pakbin, Payam; Ning, Zhi; Schauer, James J; Sioutas, Constantinos

2009-07-01

A chassis dynamometer study was carried out by the University of Southern California in collaboration with the Air Resources Board (CARB) to investigate the physical, chemical, and toxicological characteristics of diesel emissions of particulate matter (PM) from heavy-duty vehicles. These heavy-duty diesel vehicles (HDDV) were equipped with advanced emission control technologies, designed to meet CARB retrofit regulations. A HDDV without any emission control devices was used as the baseline vehicle. Three advanced emission control technologies; continuously regenerating technology (CRT), zeolite- and vanadium-based selective catalytic reduction technologies (Z-SCRT and V-SCRT), were tested under transient (UDDS) (1) and cruise (80 kmph) driving cycles to simulate real-world driving conditions. This paper focuses on the characterization of the particle bound organic species from the vehicle exhaust. Physical and chemical properties of PM emissions have been reported by Biswas et al. Atmos. Environ. 2008, 42, 5622-5634) and Hu et al. (Atmos. Environ. 2008, submitted) Significant reductions in the emission factors (microg/mile) of particle bound organic compounds were observed in HDDV equipped with advanced emission control technologies. V-SCRT and Z-SCRT effectively reduced PAHs, hopanes and steranes, n-alkanes and acids by more than 99%, and often to levels below detection limits for both cruise and UDDS cycles. The CRT technology also showed similar reductions with SCRT for medium and high molecular weight PAHs, acids, but with slightly lower removal efficiencies for other organic compounds. Ratios of particle bound organics-to-OC mass (microg/g) from the baseline exhaust were compared with their respective ratios in diesel fuel and lubricating oil, which revealed that hopanes and steranes originate from lubricating oil, whereas PAHs can either form during the combustion process or originate from diesel fuel itself. With the introduction of emission control

Exercise Equipment: Neutral Buoyancy

Science.gov (United States)

Shackelford, Linda; Valle, Paul

2016-01-01

Load Bearing Equipment for Neutral Buoyancy (LBE-NB) is an exercise frame that holds two exercising subjects in position as they apply counter forces to each other for lower extremity and spine loading resistance exercises. Resistance exercise prevents bone loss on ISS, but the ISS equipment is too massive for use in exploration craft. Integrating the human into the load directing, load generating, and motion control functions of the exercise equipment generates safe exercise loads with less equipment mass and volume.

Computer aided process control equipment at the Karlsruhe reprocessing pilot plant, WAK

International Nuclear Information System (INIS)

Winter, R.; Finsterwalder, L.; Gutzeit, G.; Reif, J.; Stollenwerk, A.H.; Weinbrecht, E.; Weishaupt, M.

1991-01-01

A computer aided process control system has been installed at the Karlsruhe Spent Fuel Reprocessing Plant, WAK. All necessary process control data of the first extraction cycle is collected via a data collection system and is displayed in suitable ways on a screen for the operator in charge of the unit. To aid verification of displayed data, various measurements are associated to each other using balance type process modeling. Thus, deviation of flowsheet conditions and malfunctioning of measuring equipment are easily detected. (orig.) [de

48 CFR 870.115 - Food service equipment.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Food service equipment... DEPARTMENT SUPPLEMENTARY REGULATIONS SPECIAL PROCUREMENT CONTROLS Controls 870.115 Food service equipment. (a) All new food service equipment purchased for Dietetic Service through other than Defense General...

Process plant equipment operation, control, and reliability

CERN Document Server

Holloway, Michael D; Onyewuenyi, Oliver A

2012-01-01

"Process Plant Equipment Book is another great publication from Wiley as a reference book for final year students as well as those who will work or are working in chemical production plants and refinery…" -Associate Prof. Dr. Ramli Mat, Deputy Dean (Academic), Faculty of Chemical Engineering, Universiti Teknologi Malaysia "…give[s] readers access to both fundamental information on process plant equipment and to practical ideas, best practices and experiences of highly successful engineers from around the world… The book is illustrated throughout with numerous black & white p

Annual report of the group for maintenance of electronic equipment

International Nuclear Information System (INIS)

Popovic, B.

1965-01-01

Maintenance and repair of the RA reactor control and safety systems were uniformly distributed during the whole year and were done according to the annual plan. A series of repairs of he electronic equipment as well as exchange of electronic components and elec tonic tubes. The testing and calibration of control and protection circuits were done regularly according to the needs and operation state of the reactor and according to the instructions. Inspections, repairs and reconstructions well as operating characteristics of individual elements as well as complete electronic circuits during 1965 have shown da the systems of control and safety are still in good condition. Somewhat higher number of failures due to aging of electronic tubes is a regular consequence of equipment and instrumentation aging [sr

Preventive maintenance prioritization index of medical equipment using quality function deployment.

Science.gov (United States)

Saleh, Neven; Sharawi, Amr A; Elwahed, Manal Abd; Petti, Alberto; Puppato, Daniele; Balestra, Gabriella

2015-05-01

Preventive maintenance is a core function of clinical engineering, and it is essential to guarantee the correct functioning of the equipment. The management and control of maintenance activities are equally important to perform maintenance. As the variety of medical equipment increases, accordingly the size of maintenance activities increases, the need for better management and control become essential. This paper aims to develop a new model for preventive maintenance priority of medical equipment using quality function deployment as a new concept in maintenance of medical equipment. We developed a three-domain framework model consisting of requirement, function, and concept. The requirement domain is the house of quality matrix. The second domain is the design matrix. Finally, the concept domain generates a prioritization index for preventive maintenance considering the weights of critical criteria. According to the final scores of those criteria, the prioritization action of medical equipment is carried out. Our model proposes five levels of priority for preventive maintenance. The model was tested on 200 pieces of medical equipment belonging to 17 different departments of two hospitals in Piedmont province, Italy. The dataset includes 70 different types of equipment. The results show a high correlation between risk-based criteria and the prioritization list.

Evaluation of protection factor of respiratory protective equipment using indigenously developed protection factor test facility

International Nuclear Information System (INIS)

Patkulkar, D.S.; Ganesh, G.; Tripathi, R.M.

2018-01-01

Assigned protection factor (APF) is an indicator representing effectiveness of a respirator and it provides workplace level of respiratory protection for workers in providing protection against exposure to airborne contaminants Occupational Safety and Health Administration (OSHA) specifies 'Respirator APF' and 'Maximum Use Concentration' (MUC - a term derived using APF) shall be an integral part of Respirator Protection Standard. MUC establishes the maximum airborne concentration of a contaminant in which a respirator with a given APF may be used. The use of particulate respirators such as half face mask, full face mask and powered air purifying respirators is essential for radioactive jobs in nuclear facilities to prevent any intake of radionuclide. With this impetus, the Protection Factor Test Facility (PFTF) for testing and evaluation of respiratory protective equipment meeting relevant applicable standards was designed, fabricated and installed in Respiratory Protective Equipment Laboratory of Health Physics Division

W-026 acceptance test report system integration equipment (SIE)(submittal {number_sign} 018.6.A)

Energy Technology Data Exchange (ETDEWEB)

Watson, T.L.

1997-01-27

Acceptance testing of the System Integration Equipment (SIE) at Hanford was performed in two stages. The first was inconclusive, and resulted in a number of findings. These finding. are summarized as part of this report. The second stage of testing addressed these findings, and performed full system testing per the approved test procedure. This report includes summaries of all testing, results and finding.. Although the SIE did not in some cases perform as required for plant operations, it did perform per the system specification. (These discrepancies were noted and are addressed elsewhere.) Following testing, the system was formaLLy accepted. Documentation of this acceptance is incLuded in this report.

Results from the Operational Testing of the Eaton Smart Grid Capable Electric Vehicle Supply Equipment

Energy Technology Data Exchange (ETDEWEB)

Bennett, Brion [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-10-01

The Idaho National Laboratory conducted testing and analysis of the Eaton smart grid capable electric vehicle supply equipment (EVSE), which was a deliverable from Eaton for the U.S. Department of Energy FOA-554. The Idaho National Laboratory has extensive knowledge and experience in testing advanced conductive and wireless charging systems though INL’s support of the U.S. Department of Energy’s Advanced Vehicle Testing Activity. This document details the findings from the EVSE operational testing conducted at the Idaho National Laboratory on the Eaton smart grid capable EVSE. The testing conducted on the EVSE included energy efficiency testing, SAE J1772 functionality testing, abnormal conditions testing, and charging of a plug-in vehicle.

The application of nuclear equipment to measurement and control in the steel industry

International Nuclear Information System (INIS)

Van Schalkwyk, J.

1976-01-01

In this paper, some of the reasons for utilising equipment which makes use of nuclear radiation for the control of processes in the steel industry will be discussed. Two applications will be analysed to demonstrate the reasoning and to highlight some of the factors and principles [af

Equipment support for the implementation of safeguards

International Nuclear Information System (INIS)

Arlt, R.; Bosler, G.; Goldfarb, M.; Schanfein, M.; Whichello, J.

2001-01-01

Full text: The provision of effective, reliable, and user-friendly equipment needed for the implementation of safeguards is one of the main objectives of the Division of Technical Services (SOTS) in the Department of Safeguards. As an outcome of a review by an independent external consultant firm, the instrumentation sections of the SGTS were reorganized in January 2001 into two new sections, the Section for NDA Systems and Seals (TNS) and Section for Installed Systems (TIE). Each section has 'cradle-to-grave' responsibilities for development, implementation, maintenance, and decommissioning of safeguards instruments and measurement systems. Unattended assay, monitoring and surveillance instruments are the responsibility of TIE while attended nondestructive assay (NDA) instruments and seals are handled by TNS. The principal goals of both sections are to define equipment requirements based on Departmental needs, to coordinate Support Programme tasks concerning development and implementation activities, to provide system engineering of commercial components, manage laboratory and to do field testing and prove system suitability for defined safeguards applications. In addition both sections coordinate equipment and supply needs for the Department, including acquisition, preparation, servicing, installation, commissioning, troubleshooting, maintenance and repair, ensuring their availability when needed. As required, TIE and TNS provide specialized field support to the Operations Divisions. Each section is working to standardize equipment as much as possible and reduce the number of instruments performing the same function. This reduces both inspector and technician training, required parts inventories, and overall life-cycle costs. Development based on User Needs from the Operations Divisions follows a strict quality control program that includes a thorough qualification testing procedure with the last phase being field-testing under actual facility conditions. A

Design of electronic measurement and quench detection equipment for the Current Lead Test facility Karlsruhe (CuLTKa)

International Nuclear Information System (INIS)

Hollik, Markus; Fietz, Walter H.; Fink, Stefan; Gehrlein, Mirko; Heller, Reinhard; Lange, Christian; Möhring, Tobias

2013-01-01

The Current Lead Test facility Karlsruhe (CuLTKa) is under construction at the Karlsruhe Institute of Technology (KIT) to perform acceptance tests of high temperature superconductor (HTS) current leads (CL). CuLTKa is in progress and present planning expects the completion in 2013. The data acquisition system is based on a modular design with electronic measurement and monitoring equipment covering a test voltage of 50 kV DC against ground. It provides plug-in units which enable temperature and voltage measurement at high voltage potential and in addition quench detection units which detect a loss of superconductivity reliably and quickly to avoid damage of the superconducting device under test. Prototype units for quench detection, temperature and voltage measurement have been successfully tested. Six temperature measurement units are already in use in the KIT test facility TOSKA and operated reliably during the acceptance tests of the HTS current leads for Wendelstein 7-X (W7-X) in 2011/2012. CuLTKa will be used first for 26 current leads which will be built in KIT for the fusion experiment JT-60SA. The present paper gives an overview of the design of the electronic measurement and quench detection equipment

Manufacture research of the test equipment to measure the dose rate in high radiation medium

International Nuclear Information System (INIS)

Phan Luong Tuan; Nguyen Van Sy; Nguyen Xuan Vinh; Dang Quang Bao; Nguyen Thanh Hung; Pham Minh Duc; Nguyen Xuan Truong

2017-01-01

Photodiode BPW34 is operated as a low voltage counter tubes. When the radiation rays go into the BPW34,they will create a pairs of electron and hole. If setting the reverse bias in to the BPW34, a pulse is achieved and it can be amplified and processed. The STM32 is the microcontroller family which is developed base on ARM processors. The STM32 incorporated many new features such as ADC, I2C, etc. With the connectional ability to other devices, the STM32 is proving its advantages in the development of equipment.The application of irradiation technology in the economy-society increases widespread as food irradiation, mutant irradiation, etc. Until now the calculation the high dose rate at Hanoi Irradiation Center is identified by the Fricke, ECB dosimeters. The dosimeters must be destroyed in order to serve for dose rate determination. Manufacture research the equipment for dose rate calculation support to determine dose rate directly through the equipment’s signal and this equipment can be used multiple. This equipment can be connected to other devices to control the irradiation process better via signals. (author)

RETRIEVAL EQUIPMENT DESCRIPTIONS

International Nuclear Information System (INIS)

J. Steinhoff

1997-01-01

The objective and the scope of this document are to list and briefly describe the major mobile equipment necessary for waste package (WP) retrieval from the proposed subsurface nuclear waste repository at Yucca Mountain. Primary performance characteristics and some specialized design features of the equipment are explained and summarized in the individual subsections of this document. There are no quality assurance requirements or QA controls in this document. Retrieval under normal conditions is accomplished with the same fleet of equipment as is used for emplacement. Descriptions of equipment used for retrieval under normal conditions is found in Emplacement Equipment Descriptions, DI: BCAF00000-01717-5705-00002 (a document in progress). Equipment used for retrieval under abnormal conditions is addressed in this document and consists of the following: (1) Inclined Plane Hauler; (2) Bottom Lift Transporter; (3) Load Haul Dump (LHD) Loader; (4) Heavy Duty Forklift for Emplacement Drifts; (5) Covered Shuttle Car; (6) Multipurpose Vehicle; and (7) Scaler

Calibration of laboratory equipment and its intermediate verification

International Nuclear Information System (INIS)

Remedi, Jorge O.

2011-01-01

When a laboratory wants to prove that he has technical competence to carry out tests or calibrations must demonstrate that it has complied with certain requirements that establish , among others, the mandatory : calibrate or verify equipment before putting it into service in order to ensure that it meets to the specifications of laboratory equipment to keep records evidencing the checks that equipment complies with the specification ; perform intermediate checks for maintain confidence in the calibration status of the equipment , ensure that the operation is checked and calibration status of equipment when the equipment goes outside the direct control of the laboratory , before be returned to service, establish a program and procedure for the calibration of equipment; show how determined the calibration periods of their equipment as well as evidence that intermediate checks are suitable for the calibration periods. However, some confusion is observed as to the meaning of the terms 'calibration' and 'verification' of a computer. This paper analyzes applicable documentation and suggests that the differences are generated in part by translations and by characterization concepts upon its usage, that is, if it is legal metrology or assessment conformity. Therefore, this study aims to characterize both concepts , fundamentals to zoom distinguish , outline appropriate strategies for calibration and verification activities to ensure the compliance with regulatory requirements [es

Eddy Current, Magnetic Particle and Hardness Testing, Aviation Quality Control (Advanced): 9227.04.

Science.gov (United States)

Dade County Public Schools, Miami, FL.

This unit of instruction includes the principles of eddy current, magnetic particle and hardness testing; standards used for analyzing test results; techniques of operating equipment; interpretation of indications; advantages and limitations of these methods of testing; care and calibration of equipment; and safety and work precautions. Motion…

Three-dimensional triaxial testing of marine sediments

International Nuclear Information System (INIS)

Nelson, J.D.; Thompson, E.G.

1981-01-01

The purpose of this investigation has been to develop testing methods and upgrade equipment for the determination of shear strength of and constitutive relationships for ocean bottom sediments under true three dimensional triaxial states of stress. The research to date has utilized existing 3-D triaxial equipment capable of controlling the three principal stresses independently of each other. Experiments are currently concerned with up-grading the equipment for use with ocean bottom cohesive soils. In addition, stage triaxial tests using conventional laboratory test equipment are being performed

Ten years of sodium cooled steam generator tests on the C.G.V.S. Synthesis of the results obtained on these equipments and operation experiments of an industrial size test facility

International Nuclear Information System (INIS)

Fontaine, J.P.; Llory, M.; Quinet, J.L.

1984-04-01

From 1970 to 1980, Electricite de France carried out tests on four steam generators of the fast neutron reactor series on an industrial size testing equipment, the C.G.V.S. (large power testing Circuit for Steam Generators heated by Sodium). After a presentation of the testing installation, types of tests carried out and tested apparatus, a balance of lessons drawn from the circuit exploitation, and from the main results obtained on the tested equipments and on the means of calculation COPI and SICLE codes developed or adopted to simulate steam generator operation. 33 figs., 50 refs [fr

Reduction of patient doses in X-ray diagnosis using quality control tests on image and equipment

International Nuclear Information System (INIS)

Milu, C.; Tomulescu, V.; Sorescu, Anca; Vladareanu, M.; Olteanu, B.; Enachescu, B.; Zaharia, N.; Lesaru, M.

1997-01-01

In the frame of a research program under the contract with the International Atomic Energy Agency (IAEA), several patient dose measurements were performed using thermoluminescent dosemeters (TLDs) before and after application of Quality Control tests and patient dose reduction methods. The paper evidenced the practical influence factors (like the need of use of high voltage technique) and possibilities for dose reduction keeping the image quality. (authors)

Bacteriological research for the contamination of equipment in chest radiography

International Nuclear Information System (INIS)

Choi, Seung Gu; Song, Woon Heung; Kweon, Dae Cheol

2015-01-01

The purpose is to determine the degree of contamination of the equipment for infection control in chest radiography of the radiology department. We confirmed by chemical and bacterial identification of bacteria of the equipment and established a preventive maintenance plan. Chest X-ray radiography contact area on the instrument patients shoulder, hand, chin, chest lateral radiography patient contact areas with a 70% isopropyl alcohol cotton swab were compared to identify the bacteria before and after sterilization on the patient contact area in the chest radiography equipment of the department. The gram positive Staphylococcus was isolated from side shoots handle before disinfection in the chest radiography equipment. For the final identification of antibiotic tested that it was determined by performing the nobobiocin to the sensitive Staphylococcus epidermidis. Chest radiography equipment before disinfecting the handle side of Staphylococcus epidermidis bacteria were detected using a disinfectant should be to prevent hospital infections

Bacteriological research for the contamination of equipment in chest radiography

Energy Technology Data Exchange (ETDEWEB)

Choi, Seung Gu; Song, Woon Heung; Kweon, Dae Cheol [Shinhan University, Uijeongbu (Korea, Republic of)

2015-12-15

The purpose is to determine the degree of contamination of the equipment for infection control in chest radiography of the radiology department. We confirmed by chemical and bacterial identification of bacteria of the equipment and established a preventive maintenance plan. Chest X-ray radiography contact area on the instrument patients shoulder, hand, chin, chest lateral radiography patient contact areas with a 70% isopropyl alcohol cotton swab were compared to identify the bacteria before and after sterilization on the patient contact area in the chest radiography equipment of the department. The gram positive Staphylococcus was isolated from side shoots handle before disinfection in the chest radiography equipment. For the final identification of antibiotic tested that it was determined by performing the nobobiocin to the sensitive Staphylococcus epidermidis. Chest radiography equipment before disinfecting the handle side of Staphylococcus epidermidis bacteria were detected using a disinfectant should be to prevent hospital infections.

76 FR 77914 - Energy Conservation Program for Certain Commercial and Industrial Equipment: Test Procedures for...

Science.gov (United States)

2011-12-15

... lifetime. Correlated color temperature (CCT) and color rendering index (CRI) would also be measured as potential means to delineate equipment classes for HID lamps. This notice of proposed rulemaking (NOPR) also... Conditions a. Ambient Conditions i. Ambient Test Temperature ii. Air Speed b. Power Supply Characteristics i...

Initial virtual flight test for a dynamically similar aircraft model with control augmentation system

Directory of Open Access Journals (Sweden)

Linliang Guo

2017-04-01

Full Text Available To satisfy the validation requirements of flight control law for advanced aircraft, a wind tunnel based virtual flight testing has been implemented in a low speed wind tunnel. A 3-degree-of-freedom gimbal, ventrally installed in the model, was used in conjunction with an actively controlled dynamically similar model of aircraft, which was equipped with the inertial measurement unit, attitude and heading reference system, embedded computer and servo-actuators. The model, which could be rotated around its center of gravity freely by the aerodynamic moments, together with the flow field, operator and real time control system made up the closed-loop testing circuit. The model is statically unstable in longitudinal direction, and it can fly stably in wind tunnel with the function of control augmentation of the flight control laws. The experimental results indicate that the model responds well to the operator’s instructions. The response of the model in the tests shows reasonable agreement with the simulation results. The difference of response of angle of attack is less than 0.5°. The effect of stability augmentation and attitude control law was validated in the test, meanwhile the feasibility of virtual flight test technique treated as preliminary evaluation tool for advanced flight vehicle configuration research was also verified.

Development of a handmade device for collimation and central ray alignment tests in medical X-ray equipment; Desenvolvimento de um dispositivo artesanal para os testes de colimação e alinhamento do raio central em equipamentos médicos de raios X

Energy Technology Data Exchange (ETDEWEB)

Cruz, B.L. da; Brito, E.B.; Gomes, A.S., E-mail: elizabethberbr@live.com [Universidade José de Souza Herdy (UNINGRANRIO), Nova Iguaçu, RJ (Brazil)

2017-07-01

Ordinance 453/98 of the Ministry of Health establishes that medical X-ray equipment should be monitored by tests that prove its efficiency. This practice is called quality control (QC), and two important tests jointly evaluate the operation of the collimation and alignment systems of the central axis of the X-ray beam. The low supply and the high cost generate allegations of difficulties in the periodic realization of the tests. The aim of this work is to design, make and evaluate the performance of a handmade device for the mentioned tests, using low cost materials. Once built, the device had its performance evaluated and compared with the traditionally marketed device. The handmade device proved to be fit in its functions. It is possible to make a device that tests X-ray medical equipment, using the radiology technologist himself as the test runner. Radiation protection is promoted and legislation with no real financial burden.

Control protocol: the proposed new CERN standard access procedure to accelerator equipment

International Nuclear Information System (INIS)

Baribaud, G.; Barnett, I.; Benincasa, G.

1992-01-01

Control protocol provides a normalized access procedure for equipment of the same kind from a control system. Modelisation and the subsequent identification of functionalities with their parameters, variables and attributes have now been carried out at CERN for representative families of devices. ISO specifications, such as the ASN.1 metalanguage for data structure representation and MMS definitions and services have, to some extent, been introduced in the design for generality and compatibility with external world. The final product of this design is totally independent of the control systems and permits object oriented implementations in any controls frame. The present paper describes the different phases of the project with a short overview of the various implementations under development at CERN. (author)

Equipment Obsolescence Analysis and Management Software

Energy Technology Data Exchange (ETDEWEB)

Redmond, J.; Carret, L.; Shaon, S.; Schultz, C.

2015-07-01

The procurement engineering resources at Nuclear Power Plants (NPPs) are experiencing increasing backlog for procurement items primarily due to the inability to order the original replacement parts. The level of effort and time required to prepare procurement packages is increasing since the number of obsolete parts are increasing exponentially. Procurement packages for obsolete components and parts are much more complex and take more time to prepare because of the need to perform equivalency evaluations, testing requirements and test acceptance criteria development, commercial grade dedication or equipment qualification, and increasing efforts to verify that no fraudulent or counterfeit parts are procured. This problem will be further compounded when NPPs pursue license renewal and approval for plant-life extension. Advanced planning and advanced knowledge of equipment obsolescence is required to allow for sufficient time to properly procure replacement parts for obsolete items. The uncertain supply chain capability due to obsolescence is a real problem and can cause a risk to reliable plant operations due to the potential for a lack of available spare parts and replacement components to support outages and unplanned component failures. Advanced notification of obsolescence is increasingly more important to ensure that adequate time and planning is scheduled to procure the proper replacement parts. A thorough analysis of Original Equipment Manufacturer (OEM) availability and inventory as well as an analysis of failure rates and usage rates is required to predict critical part needs to allow for early identification of obsolescence issues so that a planned and controlled strategy to qualify replacement equipment can be implemented. (Author)

Instrument Control (iC) – An Open-Source Software to Automate Test Equipment

Science.gov (United States)

Pernstich, K. P.

2012-01-01

It has become common practice to automate data acquisition from programmable instrumentation, and a range of different software solutions fulfill this task. Many routine measurements require sequential processing of certain tasks, for instance to adjust the temperature of a sample stage, take a measurement, and repeat that cycle for other temperatures. This paper introduces an open-source Java program that processes a series of text-based commands that define the measurement sequence. These commands are in an intuitive format which provides great flexibility and allows quick and easy adaptation to various measurement needs. For each of these commands, the iC-framework calls a corresponding Java method that addresses the specified instrument to perform the desired task. The functionality of iC can be extended with minimal programming effort in Java or Python, and new measurement equipment can be addressed by defining new commands in a text file without any programming. PMID:26900522

Inquiry about the uses of special equipment (CT equipment, angiography systems, mammography devices, screens)

International Nuclear Information System (INIS)

Schwager, P.; Stieve, F.E.

1986-01-01

There are at least 1100 special devices in medical establishment in Bavaria which require special inspection and surveillance with regard to quality of equipment and radiation protection. In addition, there are at least 53 tomographs available for operation, and at least 120 installed X-ray screens. These devices need special approval testing and quality control services as they contribute a very significant amount of the medically indicated radiation exposure of the population. Appropriate measures are explained that can be applied in order to reduce the medical radiation exposure to an optimum. (orig.) [de

Methodology development for availability improvement of standby equipment