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)

Integrated test plan for directional boring

International Nuclear Information System (INIS)

Volk, B.W.

1993-01-01

This integrated test plan describes the field testing of the DITCH WITCH Directional Boring System. DITCH WITCH is a registered trademark of The Charles Machine Works, Inc., Perry, Oklahoma. The test is being conducted as a coordinated effort between Charles Machine Works (CMW), Sandia National Laboratories (SNL), and the Westinghouse Hanford Company (WHC). Funding for the WHC portion of the project is through the Volatile Organic Compound-Arid Integrated Demonstration (VOC-Arid ID). The purpose of the test is to evaluate the performance of the directional boring system for possible future use on environmental restoration projects at Hanford and other Department of Energy (DOE) sites. The test will be conducted near the 200 Areas Fire Station located between the 200 East and 200 West Area of the Hanford Site. The directional boring system will be used to drill and complete (with fiberglass casing) two horizontal boreholes. A third borehole will be drilled to test sampling equipment but will not be completed with casing

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

Research on the Reliability Testing of Electrical Automation Control Equipment

OpenAIRE

Yongjie Luo

2014-01-01

According to the author’s many years’ work experience, this paper first discusses the concepts of electrical automation control equipment reliability testing, and then analyzes the test method of electrical automation control equipment reliability testing, finally, on this basis, this article discusses how to determine the reliability test method of electrical automation control equipment. Results of this study will provide a useful reference for electrical automation control equipment reliab...

Research on Integrated Analysis Method for Equipment and Tactics Based on Intervention Strategy Discussion

Institute of Scientific and Technical Information of China (English)

陈超; 张迎新; 毛赤龙

2012-01-01

As the increase of the complexity of the information warfare,its intervention strategy needs to be designed in an integrated environment.However,the current research always breaks the internal relation between equipment and tactics,and it is difficult to meet the requirements of their integrated analysis.In this paper,the research status quo of the integrated analysis about equipment and tactics is discussed first,some shortages of the current methods are summarized then,and an evolvement mechanism of the integrated analysis for equipment and tactics is given finally.Based on these,a framework of integrated analysis is proposed.This method＇s effectiveness is validated by an example.

Measurements of integrated components' parameters versus irradiation doses gamma radiation (60Co) dosimetry-methodology-tests

International Nuclear Information System (INIS)

Fuan, J.

1991-01-01

This paper describes the methodology used for the irradiation of the integrated components and the measurements of their parameters, using Quality Insurance of dosimetry: - Measurement of the integrated dose using the competences of the Laboratoire Central des Industries Electriques (LCIE): - Measurement of irradiation dose versus source/component distance, using a calibrated equipment. - Use of ALANINE dosimeters, placed on the support of the irradiated components. - Assembly and polarization of components during the irradiations. Selection of the irradiator. - Measurement of the irradiated components's parameters, using the competences of the societies: - GenRad: GR130 tests equipement placed in the DEIN/SIR-CEN SACLAY. - Laboratoire Central des Industries Electriques (LCIE): GR125 tests equipment and this associated programmes test [fr

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.

Suitability of Strain Gage Sensors for Integration into Smart Sport Equipment: A Golf Club Example.

Science.gov (United States)

Umek, Anton; Zhang, Yuan; Tomažič, Sašo; Kos, Anton

2017-04-21

Wearable devices and smart sport equipment are being increasingly used in amateur and professional sports. Smart sport equipment employs various sensors for detecting its state and actions. The correct choice of the most appropriate sensor(s) is of paramount importance for efficient and successful operation of sport equipment. When integrated into the sport equipment, ideal sensors are unobstructive, and do not change the functionality of the equipment. The article focuses on experiments for identification and selection of sensors that are suitable for the integration into a golf club with the final goal of their use in real time biofeedback applications. We tested two orthogonally affixed strain gage (SG) sensors, a 3-axis accelerometer, and a 3-axis gyroscope. The strain gage sensors are calibrated and validated in the laboratory environment by a highly accurate Qualisys Track Manager (QTM) optical tracking system. Field test results show that different types of golf swing and improper movement in early phases of golf swing can be detected with strain gage sensors attached to the shaft of the golf club. Thus they are suitable for biofeedback applications to help golfers to learn repetitive golf swings. It is suggested that the use of strain gage sensors can improve the golf swing technical error detection accuracy and that strain gage sensors alone are enough for basic golf swing analysis. Our final goal is to be able to acquire and analyze as many parameters of a smart golf club in real time during the entire duration of the swing. This would give us the ability to design mobile and cloud biofeedback applications with terminal or concurrent feedback that will enable us to speed-up motor skill learning in golf.

Vitrification Facility integrated system performance testing report

International Nuclear Information System (INIS)

Elliott, D.

1997-01-01

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

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

Test processing integrated system (S.I.D.E.X.)

International Nuclear Information System (INIS)

Sabas, M.; Oules, H.; Badel, D.

1969-01-01

The Test Processing Integrated System is mostly composed of a CAE 9080 (equiv. S. D. S. 9300) computer which is equipped of a 100 000 samples/sec acquisition system. The System is designed for high speed data acquisition and data processing on environment tests, and also calculation of structural models. Such a digital appliance on data processing has many advantages compared to the conventional methods based on analog instruments. (author) [fr

Infrastructure for Integration of Legacy Electrical Equipment into a Smart-Grid Using Wireless Sensor Networks.

Science.gov (United States)

de Araújo, Paulo Régis C; Filho, Raimir Holanda; Rodrigues, Joel J P C; Oliveira, João P C M; Braga, Stephanie A

2018-04-24

At present, the standardisation of electrical equipment communications is on the rise. In particular, manufacturers are releasing equipment for the smart grid endowed with communication protocols such as DNP3, IEC 61850, and MODBUS. However, there are legacy equipment operating in the electricity distribution network that cannot communicate using any of these protocols. Thus, we propose an infrastructure to allow the integration of legacy electrical equipment to smart grids by using wireless sensor networks (WSNs). In this infrastructure, each legacy electrical device is connected to a sensor node, and the sink node runs a middleware that enables the integration of this device into a smart grid based on suitable communication protocols. This middleware performs tasks such as the translation of messages between the power substation control centre (PSCC) and electrical equipment in the smart grid. Moreover, the infrastructure satisfies certain requirements for communication between the electrical equipment and the PSCC, such as enhanced security, short response time, and automatic configuration. The paper’s contributions include a solution that enables electrical companies to integrate their legacy equipment into smart-grid networks relying on any of the above mentioned communication protocols. This integration will reduce the costs related to the modernisation of power substations.

Infrastructure for Integration of Legacy Electrical Equipment into a Smart-Grid Using Wireless Sensor Networks

Directory of Open Access Journals (Sweden)

Paulo Régis C. de Araújo

2018-04-01

Full Text Available At present, the standardisation of electrical equipment communications is on the rise. In particular, manufacturers are releasing equipment for the smart grid endowed with communication protocols such as DNP3, IEC 61850, and MODBUS. However, there are legacy equipment operating in the electricity distribution network that cannot communicate using any of these protocols. Thus, we propose an infrastructure to allow the integration of legacy electrical equipment to smart grids by using wireless sensor networks (WSNs. In this infrastructure, each legacy electrical device is connected to a sensor node, and the sink node runs a middleware that enables the integration of this device into a smart grid based on suitable communication protocols. This middleware performs tasks such as the translation of messages between the power substation control centre (PSCC and electrical equipment in the smart grid. Moreover, the infrastructure satisfies certain requirements for communication between the electrical equipment and the PSCC, such as enhanced security, short response time, and automatic configuration. The paper’s contributions include a solution that enables electrical companies to integrate their legacy equipment into smart-grid networks relying on any of the above mentioned communication protocols. This integration will reduce the costs related to the modernisation of power substations.

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

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.

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.

Testing of FFTF fuel handling equipment

International Nuclear Information System (INIS)

Coleman, D.W.; Grazzini, E.D.; Hill, L.F.

1977-07-01

The Fast Flux Test Facility has several manual/computer controlled fuel handling machines which are exposed to severe environments during plant operation but still must operate reliably when called upon for reactor refueling. The test programs for two such machines--the Closed Loop Ex-Vessel Machine and the In-Vessel Handling Machine--are described. The discussion centers on those areas where design corrections or equipment repairs substantiated the benefits of a test program prior to plant operation

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

Comparative tests of bench equipment for fuel control system testing of gas-turbine engine

Science.gov (United States)

Shendaleva, E. V.

2018-04-01

The relevance of interlaboratory comparative researches is confirmed by attention of world metrological community to this field of activity. Use of the interlaboratory comparative research methodology not only for single gages collation, but also for bench equipment complexes, such as modeling stands for fuel control system testing of gas-turbine engine, is offered. In this case a comparative measure of different bench equipment will be the control fuel pump. Ensuring traceability of measuring result received at test benches of various air enterprises, development and introduction of national standards to practice of bench tests and, eventually, improvement of quality and safety of a aircraft equipment is result of this approach.

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

Test of remote control cutting equipment by Nd:YAG laser

Energy Technology Data Exchange (ETDEWEB)

Shimizu, Akio [Fuji Electric Corp. Research and Development Ltd., Yokosuka, Kanagawa (Japan); Hosoda, Hiroshi

1997-11-01

Technology of remote controlled cutting and reduction of generative secondary products have been required to the cutting system for decommissioning nuclear equipments. At a point of view that laser cutting technology by use of a Nd:YAG laser is effective, we have developed the laser cutting machine and carried out cutting tests for several stainless steel plates. This report is described the result of experiment by test equipment, about element technology of remote controlled cutting nuclear equipments. (author)

Test of remote control cutting equipment by Nd:YAG laser

International Nuclear Information System (INIS)

Shimizu, Akio; Hosoda, Hiroshi.

1997-01-01

Technology of remote controlled cutting and reduction of generative secondary products have been required to the cutting system for decommissioning nuclear equipments. At a point of view that laser cutting technology by use of a Nd:YAG laser is effective, we have developed the laser cutting machine and carried out cutting tests for several stainless steel plates. This report is described the result of experiment by test equipment, about element technology of remote controlled cutting nuclear equipments. (author)

Integration of transport and handling equipment at CERN criteria to satisfy operational needs and safety aspects

CERN Document Server

Bertone, C; CERN. Geneva. TS Department

2004-01-01

Within the last 4 years TS-IC-HM (former ST-HM group) integrated about 150 transport and handling supplies including 29 cranes, 20 fork lift trucks, 60 tunnel vehicles. Most of these are standardised supplies, but very often special functionality has been implemented and the complexity of the equipment has been increased. With the Rocla cryo-dipol transporters even prototype equipment was integrated that had been specially designed for CERN. This paper discusses the differences regarding the actions that have to be performed when the different kind of equipment have to be integrated.

Functional integration of digital radiologic equipment

International Nuclear Information System (INIS)

Agnifili, A.; DiStefano, G.; Salcito, G.; Passariello, R.

1989-01-01

This paper reports on a pilot project for the functional integration of digital radiologic equipment. Four different systems (a digital subtraction angiography unit, a DF unit, a computer radiography prototype, and a film digitizer) were connected with a link in an Ethernet LAN.ACR-NEMA standards were used to process the images of the different units in the same way. The central computer manages the long-term optical archive and the film laser printer. Some graphic workstations are connected to the picture archiving and communications system, which allows fast retrieval and processing of the images. Patients; data are acquired through the RIS and stored together with the images

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

Boosting program integrity and effectiveness of the cognitive behavioral program EQUIP for incarcerated youth in The Netherlands

NARCIS (Netherlands)

Helmond, P.; Overbeek, G.; Brugman, D.

2014-01-01

This study examined whether a "program integrity booster" could improve the low to moderate program integrity and effectiveness of the EQUIP program for incarcerated youth as practiced in The Netherlands. Program integrity was assessed in EQUIP groups before and after the booster. Youth residing in

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

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

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

International Nuclear Information System (INIS)

Lewis, B.E.; Jubin, R.T.

1987-03-01

This report summarizes the findings from three sets of experiments on iodine and NO/sub x/ removal performance using dual downdraft condensers in the dissolver off-gas line. The initial experiments were conducted in the laboratory using glassware in proof-of-principle tests. Two additional sets of condenser experiments were conducted using equipment prototyical for a 0.5-t/d plant in the Integrated Equipment Test (IET) facility at the Oak Ridge National Laboratory. This report also describes the NO/sub x/ removal performance of a packed scrubber in the IET during the dissolution of depleted uranium oxides. The overall iodine pass-through efficiency of the condensers in the IET was high as desired. Removal efficiencies ranged from only 0.35 to 6.29%, indicating that the bulk of the iodine in the off-gas will be transferred on through the condensers to the iodox process for final disposal rather than recycled to the dissolver. The optimum operating temperature for the first condenser was in the range of 50 to 70 0 C, with the temperature of the second condenser held near 20 0 C. The NO/sub x/ removal performance of the combined dual condensers and packed scrubber resulted in effluent off-gas stream NO/sub x/ compositions of ∼0.4 to 1.0%, which are acceptable levels for the iodox process. The NO/sub x/ removal efficiency of the condensers ranged from ∼5 to 58%, but was generally around 20%. The removal efficiency of the packed tower scrubber was observed to be in the range of 40 to 60%. The NO/sub x/ removal performance of the condensers tended to complement the performance of the scrubber in that the condenser removal afficiency was high when the scrubber efficiency was low and vice versa

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

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

Sensor integration and testing in an airborne environment

Science.gov (United States)

Ricks, Timothy P.; Streling, Julie T.; Williams, Kirk W.

2005-11-01

The U.S. Army Redstone Technical Test Center (RTTC) has been supporting captive flight testing of missile sensors and seekers since the 1980's. Successful integration and test of sensors in an airborne environment requires attention to a broad range of disciplines. Data collection requirements drive instrumentation and flight profile configurations, which along with cost and airframe performance factors influence the choice of test aircraft. Installation methods used for instrumentation must take into consideration environmental and airworthiness factors. In addition, integration of test equipment into the aircraft will require an airworthiness release; procedures vary between the government for military aircraft, and the Federal Aviation Administration (FAA) for the use of private, commercial, or experimental aircraft. Sensor mounting methods will depend on the type of sensor being used, both for sensor performance and crew safety concerns. Pilots will require navigation input to permit the execution of accurate and repeatable flight profiles. Some tests may require profiles that are not supported by standard navigation displays, requiring the use of custom hardware/software. Test locations must also be considered in their effect on successful data collection. Restricted airspace may also be required, depending on sensor emissions and flight profiles.

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

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

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

Integrated software system for improving medical equipment management.

Science.gov (United States)

Bliznakov, Z; Pappous, G; Bliznakova, K; Pallikarakis, N

2003-01-01

The evolution of biomedical technology has led to an extraordinary use of medical devices in health care delivery. During the last decade, clinical engineering departments (CEDs) turned toward computerization and application of specific software systems for medical equipment management in order to improve their services and monitor outcomes. Recently, much emphasis has been given to patient safety. Through its Medical Device Directives, the European Union has required all member nations to use a vigilance system to prevent the reoccurrence of adverse events that could lead to injuries or death of patients or personnel as a result of equipment malfunction or improper use. The World Health Organization also has made this issue a high priority and has prepared a number of actions and recommendations. In the present workplace, a new integrated, Windows-oriented system is proposed, addressing all tasks of CEDs but also offering a global approach to their management needs, including vigilance. The system architecture is based on a star model, consisting of a central core module and peripheral units. Its development has been based on the integration of 3 software modules, each one addressing specific predefined tasks. The main features of this system include equipment acquisition and replacement management, inventory archiving and monitoring, follow up on scheduled maintenance, corrective maintenance, user training, data analysis, and reports. It also incorporates vigilance monitoring and information exchange for adverse events, together with a specific application for quality-control procedures. The system offers clinical engineers the ability to monitor and evaluate the quality and cost-effectiveness of the service provided by means of quality and cost indicators. Particular emphasis has been placed on the use of harmonized standards with regard to medical device nomenclature and classification. The system's practical applications have been demonstrated through a pilot

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

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

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.

Safeguards equipment of the future: Integrated monitoring systems and remote monitoring

International Nuclear Information System (INIS)

Sonnier, C.S.; Johnson, C.S.

1994-01-01

From the beginning, equipment to support IAEA Safeguards could be characterized as that which is used to measure nuclear material, Destructive Assay (DA) and Non Destructive Assay (NDA), and that which is used to provide continuity of knowledge between inspection intervals, Containment ampersand Surveillance (C/S). C/S equipment has often been thought of as Cameras and Seals, with a limited number of monitors being employed as they became available. In recent years, technology has advanced at an extremely rapid rate, and continues to do so. The traditional film cameras are being replaced by video equipment, and fiber optic and electronic seals have come into rather widespread use. Perhaps the most interesting aspect of this evolution, and that which indicates the wave of the future without much question, is the integration of video surveillance and electronic seals with a variety of monitors. This is demonstrated by safeguards systems which are installed in several nuclear facilities in France, Germany, Japan, the UK, the USA, and elsewhere. The terminology of Integrated Monitoring Systems (IMS) has emerged, with the employment of network technology capable of interconnecting all desired elements in a very flexible manner. Also, the technology for transmission of a wide variety of information to off-site locations, termed Remote Monitoring, is in widespread industrial use, requiring very little adaptation for safeguards use. This paper examines the future of the Integrated Monitoring Systems and Remote Monitoring in International Safeguards, including technical and other related factors

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

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)

Integrated inventory ranking system for oilfield equipment industry

Directory of Open Access Journals (Sweden)

Jalel Ben Hmida

2014-01-01

Full Text Available Purpose: This case study is motivated by the subcontracting problem in an oilfield equipment and service company where the management needs to decide which parts to manufacture in-house when the capacity is not enough to make all required parts. Currently the company is making subcontracting decisions based on management’s experience. Design/methodology/approach: Working with the management, a decision support system (DSS is developed to rank parts by integrating three inventory classification methods considering both quantitative factors such as cost and demand, and qualitative factors such as functionality, efficiency, and quality. The proposed integrated inventory ranking procedure will make use of three classification methods: ABC, FSN, and VED. Findings: An integration mechanism using weights is developed to rank the parts based on the total priority scores. The ranked list generated by the system helps management to identify about 50 critical parts to manufacture in-house. Originality/value: The integration of all three inventory classification techniques into a single system is a unique feature of this research. This is important as it provides a more inclusive, big picture view of the DSS for management’s use in making business decisions.

Electrical Integrity Tests during Production of the LHC Dipoles

CERN Document Server

de Rijk, G; Cornelis, M; Fessia, P; Miles, J; Modena, M; Molinari, G; Rinn, J; Savary, F; Vlogaert, J

2006-01-01

For the LHC dipoles, mandatory electrical integrity tests are performed to qualify the cold mass (CM) at four production stages: individual pole, collared coil, CM before end cover welding and final CM. A description of the measurement equipment and its recent development are presented. After passing the demands set out in the specification, the results of the tests are transmitted to CERN where they are further analyzed. The paper presents the most important results of these measurements. We also report a review of the electrical non-conformities encountered e.g. interturn shorts and quench heater failure, their diagnostic and the cures.

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.)

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

Model-based integration and testing : bridging the gap between academic theory and industrial practice

NARCIS (Netherlands)

Braspenning, N.C.W.M.

2008-01-01

For manufacturers of high-tech multi-disciplinary systems such as semiconductor equipment, the effort required for integration and system testing is ever increasing, while customers demand a shorter time-to-market.This book describes how executable models can replace unavailable component

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...

M109 Family of Vehicles, Paladin Integrated Management (PIM): Operational Assessment of the Initial Operational Test and Evaluation (IOT and E)

Science.gov (United States)

2017-01-01

Director, Operational Test and Evaluation M109 Family of Vehicles, Paladin Integrated Management (PIM) Operational Assessment of the... operational suitability, test adequacy, and survivability of the M109 Family of Vehicles (FoV), known as Paladin Integrated Management (PIM) Self...prevent the M109A7 SPH-equipped unit from completing its mission. The Paladin Integrated Management (PIM) Initial Operational Test and Evaluation

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

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

Acceptance test procedure for the master equipment list (MEL)database system -- phase I

International Nuclear Information System (INIS)

Jech, J.B.

1997-01-01

The Waste Remediation System/.../Facilities Configuration Management Integration group has requested development of a system to help resolve many of the difficulties associated with management of master equipment list information. This project has been identified as Master Equipment List (MEL) database system. Further definition is contained in the system requirements specification (SRS), reference 7

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

Smart integrated containment leakage rate test system using wireless communication

Energy Technology Data Exchange (ETDEWEB)

Lee, Dong Hwan; Lee, Sang Yong; Kim, Jung Sun; Kim, Gun Soo; Kim, Jong Myeong; Ahn, Jong Han [Research and Development Center, Ulsan (Korea, Republic of)

2012-10-15

Integrated Leakage Rate Test (ILRT) is the important test the confidentiality and integrity of the containment building, which is the last barrier when Design basis accidents (DBA) of Nuclear Power plant occur. Since the result of this test is the basis to guarantee the safety of nuclear power plants, the test process, test procedure, and the test equipment are required to have high reliability. The test devices previously used have been products of VOLUMERTRICS and GRAFTEL of USA. These devices have been inconvenient to calibrate and use. Thus improved devices needed to be developed to remove the inconveniences, to verify the safety of Korean nuclear power plants with Korea's own technology, and to secure core technology. A new leak test system was developed by domestic technology for that purpose and needed to be verified. In this paper, technical details of the newly developed easy to use and highly reliable measuring test device, which is in operation at the nuclear power plant sites, will be introduced. State of art technology was applied to the device to address the shortcomings of previous US made devices and the difficulties to use on site.

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).

SAP crm integration testing

OpenAIRE

Černiavskaitė, Marija

2017-01-01

This Bachelor's thesis presents SAP CRM and integration systems testing analysis: investigation in SAP CRM and SAP PO systems, presentation of relationship between systems, introduction to third-party system (non-SAP) – Network Informational System (NIS) which has integration with SAP, presentation of best CRM testing practises, analysis and recommendation of integration testing. Practical integration testing is done in accordance to recommendations.

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)

Australian national networked tele-test facility for integrated systems

Science.gov (United States)

Eshraghian, Kamran; Lachowicz, Stefan W.; Eshraghian, Sholeh

2001-11-01

The Australian Commonwealth government recently announced a grant of 4.75 million as part of a 13.5 million program to establish a world class networked IC tele-test facility in Australia. The facility will be based on a state-of-the-art semiconductor tester located at Edith Cowan University in Perth that will operate as a virtual centre spanning Australia. Satellite nodes will be located at the University of Western Australia, Griffith University, Macquarie University, Victoria University and the University of Adelaide. The facility will provide vital equipment to take Australia to the frontier of critically important and expanding fields in microelectronics research and development. The tele-test network will provide state of the art environment for the electronics and microelectronics research and the industry community around Australia to test and prototype Very Large Scale Integrated (VLSI) circuits and other System On a Chip (SOC) devices, prior to moving to the manufacturing stage. Such testing is absolutely essential to ensure that the device performs to specification. This paper presents the current context in which the testing facility is being established, the methodologies behind the integration of design and test strategies and the target shape of the tele-testing Facility.

Inspector training for VIFM equipment - An integrated approach

International Nuclear Information System (INIS)

Truong, Q.S. Bob; Keeffe, R.; Ellacott, T.; Desson, K.; Herber, N.

2001-01-01

Full text: The VXI Integrated Fuel Monitor (VIFM) was developed by the Canadian Safeguards Support Program (CSSP) as a generic radiation monitor for safeguards applications. The VIFM equipment features a modular design, where a single cabinet can house several instruments such as bundle counters, core discharge monitors, Yes/No monitors, and other devices. VIFM can also be used in a stand-alone, transportable mode, with a detector connected to a single VIFM module linked to a laptop computer. VIFM equipment is currently in use at CANDU nuclear generating stations in several countries. Because each facility may have a different combination of detectors, the training program has been designed to reflect the modular nature of VIFM. Introductory material is generic and applies to any facility. More advanced material is carefully compartmentalized to allow IAEA Inspectors to concentrate their efforts in areas that concern them. Advanced material is available in a just-in-time reference format that simplifies rapid access to detailed information. A number of training resources have been developed, including multimedia and video material on CD-ROMs. This material has been designed to operate on a laptop computer, allowing inspectors to review and refresh their knowledge at any time - for example, during inspection trips. Although each of these resources is useful in its own right, the CSSP is developing an integrated approach to inspector training that combines all of these elements in a new way calculated to produce better training results than in the past. This new training approach features a two-day workshop preceded by a period of CD-ROM-based self-paced study. After the workshop, participants are able to make use of printed and CD-ROM-based reference materials for just-in-time 'refreshers'. Each step in this integrated approach to training will be described in the presentation. Briefly, the steps are as follows. A multimedia computer-based training package is made

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

International Nuclear Information System (INIS)

Birdwell, J.F.

1990-01-01

This paper describes the most recent in a series of experiments evaluating the behavior of iodine and NO x in the Integrated Equipment Test (IET) Dissolver Off-Gas (DOG) System. This work was performed as part of a joint collaborative program between the US Department of Energy and the Power and Nuclear Fuel Development Corporation of Japan. The DOG system consists of two shell-and-tube heat exchangers in which water and nitric acid are removed from the dissolver off-gas by condensation, followed by a packed tower in which NO x is removed by absorption into a dilute nitric acid solution. The paper also describes the results of the operation of the Iodine Oxidation (IODOX) System. This system serves to remove iodine from the DOG system effluent by absorption into hyperazeotropic nitric acid. 7 refs., 11 figs., 10 tabs

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

Integrated leak rate testing of the fast flux test facility reactor containment building

International Nuclear Information System (INIS)

James, E.B.; Farabee, O.A.; Bliss, R.J.

1978-01-01

The initial Integrated Leak Rate Test (ILRT) of the Fast Flux Test Facility containment building was performed from May 27 to June 2, 1978. The test was conducted in air with systems vented and with the containment recirculating coolers in operation. 10 psig and 5 psig tests were run using the absolute pressure test method. The measured leakage rates were .033% Vol/24 hr. and -.0015% Vol/24 hrs. respectively. Subsequent verification tests at both 10 psig and 5 psig proved that the test equipment was operating properly and it was sensitive enough to detect leaks at low pressures. This ILRT was performed at a lower pressure than any previous ILRT on a reactor containment structure in the United States. While the initial design requirements for ice condenser containments called for a part pressure test at 6 psig, the tests were waived due to the apparent statistical problems of data analysis and the repeatability of the data itself at such low pressure. In contrast to this belief, both the 5 and 10 psig ILRT's were performed in a successful manner at FFTF

Construction of a test platform for Test Blanket Module (TBM) systems integration and maintenance in ITER Port Cell #16

Energy Technology Data Exchange (ETDEWEB)

Vála, Ladislav, E-mail: ladislav.vala@cvrez.cz [Centrum výzkumu Řež, Hlavní 130, 250 68 Husinec-Řež (Czech Republic); Reungoat, Mathieu, E-mail: mathieu.reungoat@cvrez.cz [Centrum výzkumu Řež, Hlavní 130, 250 68 Husinec-Řež (Czech Republic); Vician, Martin [Centrum výzkumu Řež, Hlavní 130, 250 68 Husinec-Řež (Czech Republic); Poitevin, Yves; Ricapito, Italo; Zmitko, Milan; Panayotov, Dobromir [Fusion for Energy, Josep Pla 2, Torres Diagonal Litoral B3, 08019 Barcelona (Spain)

2015-10-15

Highlights: • A non-nuclear, full size facility – TBM platform – is under construction in CVR. • It is designed for tests, optimization and validation of TBS maintenance operations. • It will allow testing and validation of specific maintenance tools and RH equipment. • It reproduces ITER Port Cell #16, as well as the TBS interfaces and main equipment. • The TBM platform will be available for full operation in the first half of 2016. - Abstract: This paper describes a project of a non-nuclear, 1:1 scale testing platform dedicated to tests, optimization and validation of integration and maintenance operations for the European TBM systems in the ITER Port Cell #16. This TBM platform is currently under construction in Centrum výzkumu Řež, Czech Republic. The facility is realized within the scope of the SUSEN project and its full operation is foreseen in the first half of 2016.

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)

Reliability of nondestructive testing of metal strength properties for power equipment

International Nuclear Information System (INIS)

Bugaj, N.V.; Lebedev, A.A.; Sharko, A.V.

1985-01-01

Ultrasonic control which is a constituent part of a complex control system which includes specimen-free (by hardness) tests, random breaking tests and acoustic measurements is stUdied for its reliability with respect to strength properties of power-equipment metal. Quantitative and alternative criteria are developed to estimate quality of elements for power-equipment according to results of metal strength properties. Acoustic control results are presented for ultimate strength in 12Kh1MF-steel

Operational Overview for UAS Integration in the NAS Project Flight Test Series 3

Science.gov (United States)

Valkov, Steffi B.; Sternberg, Daniel; Marston, Michael

2018-01-01

The National Aeronautics and Space Administration Unmanned Aircraft Systems Integration in the National Airspace System Project has conducted a series of flight tests intended to support the reduction of barriers that prevent unmanned aircraft from flying without the required waivers from the Federal Aviation Administration. The 2015 Flight Test Series 3, supported two separate test configurations. The first configuration investigated the timing of Detect and Avoid alerting thresholds using a radar equipped unmanned vehicle and multiple live intruders flown at varying encounter geometries.

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

Integrating HIV care and treatment into primary healthcare: Are clinics equipped?

Directory of Open Access Journals (Sweden)

Talitha Crowley

2014-01-01

Full Text Available Background: The demand for HIV care and treatment services is increasing rapidly and strategies to sustain long-term care should be employed. The decentralisation and integration of HIV care and treatment services into primary healthcare (PHC is vitally important in order to ensure optimal access to life-saving antiretroviral therapy and ongoing chronic care. Conversely, the PHC system is fraught with the current burden of disease. Setting: The study was conducted in PHC clinics in the uMgungundlovu district, Kwa-Zulu Natal.Aim: The objectives of the study were to assess whether PHC clinics were equipped to deliver integrated HIV services and to evaluate the availability of resources as well as support systems for HIV care and treatment in PHC clinics.Methods: A quantitative, cross-sectional descriptive study was undertaken in 20 randomly-selected, eligible clinics in the uMgungundlovu district, KwaZulu-Natal, South Africa. An evaluation instrument was completed through observations and review of the clinic data records. Criteria were based on the World Health Organization’s guide to indicators for antiretroviral programmes as well as South African HIV standards for PHC facilities.Results: None of the clinics were equipped adequately. Clinics with a higher patient load had poorer scores, whilst clinics providing antiretroviral therapy were better equipped in terms of human resources and infrastructure.Conclusion: HIV services are an essential part of primary healthcare and clinics need to be equipped adequately in order to render this service. It is unlikely that the over-burdened health system would be able to cope with an increased number of patients on antiretroviral therapy in the long term, whilst maintaining quality of services, without support being given to PHC clinics.

Integrating HIV care and treatment into primary healthcare: Are clinics equipped?

Directory of Open Access Journals (Sweden)

Talitha Crowley

2014-08-01

Full Text Available Background: The demand for HIV care and treatment services is increasing rapidly and strategies to sustain long-term care should be employed. The decentralisation and integration of HIV care and treatment services into primary healthcare (PHC is vitally important in order to ensure optimal access to life-saving antiretroviral therapy and ongoing chronic care. Conversely, the PHC system is fraught with the current burden of disease. Setting: The study was conducted in PHC clinics in the uMgungundlovu district, Kwa-Zulu Natal. Aim: The objectives of the study were to assess whether PHC clinics were equipped to deliver integrated HIV services and to evaluate the availability of resources as well as support systems for HIV care and treatment in PHC clinics. Methods: A quantitative, cross-sectional descriptive study was undertaken in 20 randomly-selected, eligible clinics in the uMgungundlovu district, KwaZulu-Natal, South Africa. An evaluation instrument was completed through observations and review of the clinic data records. Criteria were based on the World Health Organization’s guide to indicators for antiretroviral programmes as well as South African HIV standards for PHC facilities. Results: None of the clinics were equipped adequately. Clinics with a higher patient load had poorer scores, whilst clinics providing antiretroviral therapy were better equipped in terms of human resources and infrastructure. Conclusion: HIV services are an essential part of primary healthcare and clinics need to be equipped adequately in order to render this service. It is unlikely that the over-burdened health system would be able to cope with an increased number of patients on antiretroviral therapy in the long term, whilst maintaining quality of services, without support being given to PHC clinics.

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

Development of automatic ultrasonic testing equipment for reactor pressure vessel

Energy Technology Data Exchange (ETDEWEB)

Jang, Kee Ok; Park, Dae Yung; Park, Moon Hoh; Koo, Kil Mo; Park, Kwang Heui; Kang, Sang Sin; Bang, Heui Song; Noh, Heui Choong; Kong, Woon Sik [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1994-08-01

The selected weld areas of reactor pressure vessel and adjacent piping are examined by remote mechanized ultrasonic testing(MUT) equipment. Since the MUT equipment was purchased from Southwest Research Institute (SwRI) in April 1985, we have performed 15 inservice inspections and 5 preservice inspections. However, the reliability of examination was recently decreased rapidly as the problems which results from the old age of equipment and the frequent movement to plant site to site have occurred frequently. Therefore, the 3-axis control system hardware in occurring many problems among the equipments of mechanized ultrasonic testing (MUT) was designed and developed to cover the examination areas of nozzle-shell weld as specified in ASME Code Section XI and to improve the examination reliability. The new 3-axis control system hardware with the performance of this project was developed to be compatible with the old one and it was used as dual system or spare parts of the old system. Furthermore, the established technologies are expected to be applied to the similar control systems in nuclear power plant. 17 figs, 2 pix, 2 tabs, 10 refs. (Author).

Development of automatic ultrasonic testing equipment for reactor pressure vessel

International Nuclear Information System (INIS)

Jang, Kee Ok; Park, Dae Yung; Park, Moon Hoh; Koo, Kil Mo; Park, Kwang Heui; Kang, Sang Sin; Bang, Heui Song; Noh, Heui Choong; Kong, Woon Sik

1994-08-01

The selected weld areas of reactor pressure vessel and adjacent piping are examined by remote mechanized ultrasonic testing(MUT) equipment. Since the MUT equipment was purchased from Southwest Research Institute (SwRI) in April 1985, we have performed 15 inservice inspections and 5 preservice inspections. However, the reliability of examination was recently decreased rapidly as the problems which results from the old age of equipment and the frequent movement to plant site to site have occurred frequently. Therefore, the 3-axis control system hardware in occurring many problems among the equipments of mechanized ultrasonic testing (MUT) was designed and developed to cover the examination areas of nozzle-shell weld as specified in ASME Code Section XI and to improve the examination reliability. The new 3-axis control system hardware with the performance of this project was developed to be compatible with the old one and it was used as dual system or spare parts of the old system. Furthermore, the established technologies are expected to be applied to the similar control systems in nuclear power plant. 17 figs, 2 pix, 2 tabs, 10 refs. (Author)

Application of advanced non-destructive testing for testing the integrity of concrete foundations

International Nuclear Information System (INIS)

Nguyen Le Son; Nguyen Phuoc Lan; Pham The Hung; Vu Huy Thuc

2004-01-01

Solid foundations are integral important part of any structures. Obtaining accurate and timely information on the integrity of structural foundations is essential for project progress and success. Cross-hole sonic method has been widely accepted for quality assurance and quality control on projects with deep foundations, and to assess the integrity of other civil engineering structures. Under the framework of the basic VAEC project (2003) and project VIE/8/013, the Cross-hole sonic method (CHM) was evaluated at Center for Nuclear Techniques, Hochiminh City (CNT). Background information on principle and general description of the method as is typically applied in the evaluation of deep foundations are also summarized. A suitable experimental model of the shaft foundations was prepared, where the artificial defects can be controlled for the Cross-hole sonic logging was conducted by measuring the propagation time of ultrasonic signals between two probes in vertical holes in a shaft. The purpose of the test program is to evaluate the ability of the cross-hole sonic method to identify the defects present in the experimental model, to evaluate the capabilities of the method and the equipped system Cs-97, to improve the presentation of test results to meet requirements for interpreting the quality of drilled shafts by processing the data of Cs-97. The cross-hole sonic testing program is describe. Summarizes the results and analysis of the cross-hole sonic logging are presented to highlight both the applicability and limitations of the method. The cross-hole sonic logging evaluation is a valuable non-destructive method in assessing the integrity of deep foundations. The cross-hole sonic logging tests successfully determined the location and extent of the built-in defects on experimental model shaft. Minimum sizes of defects can be detected were about ≥ 10 cm Cs-97. Effects of the directions, detectable sizes and natures of defects were studied. The apparent velocities

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

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.)

Demonstration of the iodine and NO/sub x/ removal systems in the Oak Ridge National Laboratory (ORNL) Integrated Equipment Test (IET) facility

International Nuclear Information System (INIS)

Jubin, R.T.; Lewis, B.E.

1986-01-01

The overall iodine removal performance of the condensers during phase-two experiments was good (i.e., very small amounts of iodine were recycled), with removal efficiency for both condensers ranging from 0.35 to 6.29%. The removal efficiency for the first condenser ranged from 0.03 to 5.78%, and the second condenser, from 0.02 to 3.42%. In all the cases studied, the overall iodine removal efficiency appeared to be smallest, with the first condenser operating near 50 0 C. While the 50 0 C operating temperature is not necessarily the optimum temperature, the data appear to indicate that the optimum is bounded by 50 and 70 0 C. Phase three of the Integrated Equipment Test dissolver off-gas (DOG) system tests verified the operation of the dual condensers and the NO/sub x/ scrubber column under a variety of operating conditions. The removal efficiencies of the condensers were higher than anticipated, generally approx.20% in these tests. The scrubber provided an NO/sub x/ effluent of approx.0.4 to 1.0% during the entire campaign, which is consistent with the acceptable NO/sub x/ levels in the off-gas to Iodox. In addition, this 0.4-to-1.0% NO/sub x/ level in the scrubber effluent confirms the BRET design decision to omit the NO/sub x/ scrubber in a system with a DOG NO/sub x/ concentration of approx.1.0%

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.

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)

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

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

INTEGRATED MANAGEMENT SYSTEM FOR A SOCIETY FROM INDUSTRY OF MACHINERY AND EQUIPMENT

Directory of Open Access Journals (Sweden)

Constanţa RĂDULESCU

2014-05-01

Full Text Available In this paper shows the importance that it has SMI in a society of the industry of machinery and equipment. An integrated management system is the mode to design, implement and certify two or more management systems: Quality - Environment, Quality -Environment - Safety and Occupational Health. By implementing the system, the society themselves hires in the development and continuous improvement of the system in accordance with the ones three standards and with objective of activity of the society. Also, in the paper themselves presents the advantages and disadvantages of implementing this integrated system.

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.

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)

Cloud-based shaft torque estimation for electric vehicle equipped with integrated motor-transmission system

Science.gov (United States)

Zhu, Xiaoyuan; Zhang, Hui; Yang, Bo; Zhang, Guichen

2018-01-01

In order to improve oscillation damping control performance as well as gear shift quality of electric vehicle equipped with integrated motor-transmission system, a cloud-based shaft torque estimation scheme is proposed in this paper by using measurable motor and wheel speed signals transmitted by wireless network. It can help reduce computational burden of onboard controllers and also relief network bandwidth requirement of individual vehicle. Considering possible delays during signal wireless transmission, delay-dependent full-order observer design is proposed to estimate the shaft torque in cloud server. With these random delays modeled by using homogenous Markov chain, robust H∞ performance is adopted to minimize the effect of wireless network-induced delays, signal measurement noise as well as system modeling uncertainties on shaft torque estimation error. Observer parameters are derived by solving linear matrix inequalities, and simulation results using acceleration test and tip-in, tip-out test demonstrate the effectiveness of proposed shaft torque observer design.

Integrated Test and Evaluation Flight Test 3 Flight Test Plan

Science.gov (United States)

Marston, Michael Lawrence

2015-01-01

The desire and ability to fly Unmanned Aircraft Systems (UAS) in the National Airspace System (NAS) is of increasing urgency. The application of unmanned aircraft to perform national security, defense, scientific, and emergency management are driving the critical need for less restrictive access by UAS to the NAS. UAS represent a new capability that will provide a variety of services in the government (public) and commercial (civil) aviation sectors. The growth of this potential industry has not yet been realized due to the lack of a common understanding of what is required to safely operate UAS in the NAS. NASA's UAS Integration into the NAS Project is conducting research in the areas of Separation Assurance/Sense and Avoid Interoperability, Human Systems Integration (HSI), and Communication to support reducing the barriers of UAS access to the NAS. This research is broken into two research themes namely, UAS Integration and Test Infrastructure. UAS Integration focuses on airspace integration procedures and performance standards to enable UAS integration in the air transportation system, covering Sense and Avoid (SAA) performance standards, command and control performance standards, and human systems integration. The focus of Test Infrastructure is to enable development and validation of airspace integration procedures and performance standards, including the integrated test and evaluation. In support of the integrated test and evaluation efforts, the Project will develop an adaptable, scalable, and schedulable relevant test environment capable of evaluating concepts and technologies for unmanned aircraft systems to safely operate in the NAS. To accomplish this task, the Project will conduct a series of Human-in-the-Loop and Flight Test activities that integrate key concepts, technologies and/or procedures in a relevant air traffic environment. Each of the integrated events will build on the technical achievements, fidelity and complexity of the previous tests and

METHODOLOGICAL PROBLEMS AND WAYS OF CREATION OF THE AIRCRAFT EQUIPMENT TEST AUTOMATED MANAGEMENT SYSTEM

Directory of Open Access Journals (Sweden)

Vladimir Michailovich Vetoshkin

2017-01-01

Full Text Available The development of new and modernization of existing aviation equipment specimens of different classes are ac- companied and completed by the complex process of ground and flight tests. This phase of aviation equipment life cycle is implemented by means of organizational and technical systems - running centers. The latter include various proving grounds, measuring complex and systems, aircraft, ships, security and flight control offices, information processing laborato- ries and many other elements. The system analysis results of development challenges of the automated control systems of aviation equipment tests operations are presented. The automated control systems are in essence an automated data bank. The key role of development of flight tests automated control system in the process of creation of the automated control sys- tems of aviation equipment tests operations is substantiated. The way of the mobile modular measuring complexes integra- tion and the need for national methodologies and technological standards for database systems design concepts are grounded. Database system, as a central element in this scheme, provides collection, storing and updating of values of the elements described above in pace and the required frequency of the controlled object state monitoring. It is database system that pro- vides the supervisory unit with actual data corresponding to specific moments of time, which concern the state processes, assessments of the progress and results of flight experiments, creating the necessary environment for aviation equipment managing and testing as a whole. The basis for development of subsystems of automated control systems of aviation equip- ment tests operations are conceptual design processes of the respective database system, the implementation effectiveness of which largely determines the level of success and ability to develop the systems being created. Introduced conclusions and suggestions can be used in the

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...

Integrated test plan ResonantSonic drilling system technology demonstration-1995, at the Hanford Site: Revision 1

International Nuclear Information System (INIS)

McLellan, G.W.

1994-01-01

This integrated test plan describes the demonstration test of the ResonantSonic drilling system. This demonstration is part of the Office of Technology Development's Volatile Organic Compound Arid Integrated Demonstration (VOC-Arid ID). Two main purposes of this demonstration are (1) to continue testing the ResonantSonic drilling system compatibility with the Hanford Site waste characterization programs, and (2) to transfer this method for use at the Hanford Site, other government sites, and the private sector. The ResonantSonic method is a dry drilling technique. Field testing of this method began in July 1993. During the next four months, nine holes were drilled, and continuous core samples were retrieved. Penetration rates were 2 to 3 times the baseline, and the operational downtime rate was less than 10%. Successfully demonstrated equipment refinements included a prototype 300 series ResonantSonic head, a new drill rod design for 18-centimeter diameter pipe, and an automated pipe handling system. Various configurations of sampling equipment and drill bits were tested, depending on geologic conditions. The principal objective of the VOC-Arid ID is to determine the viability of emerging technologies that can be used to characterize, remediate, and/or monitor arid or semiarid sites containing VOCs (e.g., carbon tetrachloride) with or without associated metal and radionuclide contamination

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)

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

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)

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

Science.gov (United States)

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

2016-01-01

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

Non-destructive vacuum decay method for pre-filled syringe closure integrity testing compared with dye ingress testing and high-voltage leak detection.

Science.gov (United States)

Simonetti, Andrea; Amari, Filippo

2015-01-01

In reaction to the limitations of the traditional sterility test methods, in 2008, the U.S. Food and Drug Administration issued the guidance "Container and Closure System Integrity Testing in Lieu of Sterility Testing as a Component of the Stability Protocol for Sterile Products" encouraging sterile drug manufacturers to use properly validated physical methods, apart from conventional microbial challenge testing, to confirm container closure integrity as part of the stability protocol. The case study presented in this article investigated the capability of four container closure integrity testing methods to detect simulated defects of different sizes and types on glass syringes, prefilled both with drug product intended for parenteral administration and sterile water. The drug product was a flu vaccine (Agrippal, Novartis Vaccines, Siena, Italy). Vacuum decay, pharmacopoeial dye ingress test, Novartis specific dye ingress test, and high-voltage leak detection were, in succession, the methods involved in the comparative studies. The case study execution was preceded by the preparation of two independent sets of reference prefilled syringes, classified, respectively, as examples of conforming to closure integrity requirements (negative controls) and as defective (positive controls). Positive controls were, in turn, split in six groups, three of with holes laser-drilled through the prefilled syringe glass barrel, while the other three with capillary tubes embedded in the prefilled syringe plunger. These reference populations were then investigated by means of validated equipment used for container closure integrity testing of prefilled syringe commercial production; data were collected and analyzed to determine the detection rate and the percentage of false results. Results showed that the vacuum decay method had the highest performance in terms of detection sensitivity and also ensured the best reliability and repeatability of measurements. An innovative technical

Test and verification of a reactor protection system application-specific integrated circuit

International Nuclear Information System (INIS)

Battle, R.E.; Turner, G.W.; Vandermolen, R.I.; Vitalbo, C.

1997-01-01

Application-specific integrated circuits (ASICs) were utilized in the design of nuclear plant safety systems because they have certain advantages over software-based systems and analog-based systems. An advantage they have over software-based systems is that an ASIC design can be simple enough to not include branch statements and also can be thoroughly tested. A circuit card on which an ASIC is mounted can be configured to replace various versions of older analog equipment with fewer design types required. The approach to design and testing of ASICs for safety system applications is discussed in this paper. Included are discussions of the ASIC architecture, how it is structured to assist testing, and of the functional and enhanced circuit testing

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)

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

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...

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.

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...

Integrated test schedule for buried waste integrated demonstration

International Nuclear Information System (INIS)

Brown, J.T.; McDonald, J.K.

1992-05-01

The Integrated Test Schedule incorporates the various schedules the Buried Waste Integrated Demonstration (BWID) supports into one document. This document contains the Federal Facilities Agreement and Consent Order schedules for the Idaho National Engineering Laboratory, Hanford Reservation, Oak Ridge Reservation, and Fernald Environmental Materials Center. Included in the Integrated Test Schedule is the Buried Waste Integrated Demonstration ''windows of opportunity'' schedule. The ''windows of opportunity'' schedule shows periods of time in which Buried Waste Integrated Demonstration Program-sponsored technology demonstrations could support key decisions in the Federal Facilities Agreement and Consent Order. Schedules for the Buried Waste Integrated Demonstration-sponsored technology task plans are categorized by technology area and divided by current fiscal year and out-year. Total estimated costs for Buried Waste Integrated Demonstration-sponsored Technology Task Plans for FY-92 through FY-97 are $74.756M

Integrated Instrumentation and Sensor Systems Enabling Condition-Based Maintenance of Aerospace Equipment

Directory of Open Access Journals (Sweden)

Richard C. Millar

2012-01-01

Full Text Available The objective of the work reported herein was to use a systems engineering approach to guide development of integrated instrumentation/sensor systems (IISS incorporating communications, interconnections, and signal acquisition. These require enhanced suitability and effectiveness for diagnostics and health management of aerospace equipment governed by the principles of Condition-based maintenance (CBM. It is concluded that the systems engineering approach to IISS definition provided clear benefits in identifying overall system requirements and an architectural framework for categorizing and evaluating alternative architectures, relative to a bottom up focus on sensor technology blind to system level user needs. CBM IISS imperatives identified include factors such as tolerance of the bulk of aerospace equipment operational environments, low intrusiveness, rapid reconfiguration, and affordable life cycle costs. The functional features identified include interrogation of the variety of sensor types and interfaces common in aerospace equipment applications over multiplexed communication media with flexibility to allow rapid system reconfiguration to adapt to evolving sensor needs. This implies standardized interfaces at the sensor location (preferably to open standards, reduced wire/connector pin count in harnesses (or their elimination through use of wireless communications.

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

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

C.O.D. toughness testing of medium strength steel as a preliminary development for single specimen J integral toughness tests of SA533-B steel

International Nuclear Information System (INIS)

Dean, P.; Tait, R.B.; Garrett, G.G.

1981-10-01

The primary purpose of this project is to set up a test facility and to develop the necessary expertise to enable reliable elasto-plastic fracture toughness tests to be performed. Initially, tests are to be conducted on material similar to that used in the Koeberg pressure vessel walls, with the ultimate goal of performing single specimen J integral tests on the pressure vessel steel itself to determine through-thickness toughness variations. The project will comprise a number of stages, each one necessary for the development of the techniques used in J integral testing. These include: (i) development of an appropriate specimen design, of suitable size and shape that is applicable to both crack opening displacement (C.O.D.) and J integral tests; (ii) development, testing and calibration of the necessary associated mechanical and electrical equipment (e.g. clip gauge, amplifiers, interface unit, etc.), with (iii) an estimation of the probable errors and noise levels with a view to their elimantion, leading to (iv) perfection of the sensitivity and reproducibility of, firstly, the multiple specimen C.O.D. technique and, secondly, the multiple specimen J integral techniques. (v) Based on the above techniques, development of the single specimen J integral test method incorporating development of a computerised testing procedure. All the above procedure is to be conducted on similar, but non-Koeberg pressure vessel material ('ROQ Tough'). (vi) Finally, development and testing of both multiple specimen and single specimen J integral tests on actual SA533B material and an investigation of the through thickness toughness and fatigue crack propagation behaviour

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

General arrangement and systems integration of the BPX

International Nuclear Information System (INIS)

Brown, T.G.; Mueller, J.P.; Shampinato, P.T.

1992-01-01

This paper reports on the integration of Burning Plasma Experiment (BPX) tokamak components, peripheral equipment, service lines, and the test cell facility which are being carried out to satisfy the functional requirements of all systems, maximize hands-on maintenance of peripheral equipment, and maximize access space around the machine for remote maintenance. The test cell configuration provides a center cell to house the tokamak device, close-in North and South Cells for locating peripheral equipment for hands-on maintenance and trenches are located in the test cell floor to carry away service lines to East, West, and South Diagnostic Areas. Equipment lines that service the device core components have been integrated in the design of the cryostat and locally arranged to maximize remote maintenance access to the device core and center cell peripheral equipment. a circular pipe corridor has been located in the basement to localize floor penetrations, prevent activation of the basement, and provide support structure directly under the machine. These and other configurational design details have been developed in the process of fully integrating all BPX systems and subsystems

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...

Integration of the PHIN RF Gun into the CLIC Test Facility

CERN Document Server

Döbert, Steffen

2006-01-01

CERN is a collaborator within the European PHIN project, a joint research activity for Photo injectors within the CARE program. A deliverable of this project is an rf Gun equipped with high quantum efficiency Cs2Te cathodes and a laser to produce the nominal beam for the CLIC Test Facility (CTF3). The nominal beam for CTF3 has an average current of 3.5 A, 1.5 GHz bunch repetition frequency and a pulse length of 1.5 ìs (2332 bunches) with quite tight stability requirements. In addition a phase shift of 180 deg is needed after each train of 140 ns for the special CLIC combination scheme. This rf Gun will be tested at CERN in fall 2006 and shall be integrated as a new injector into the CTF3 linac, replacing the existing injector consisting of a thermionic gun and a subharmonic bunching system. The paper studies the optimal integration into the machine trying to optimize transverse and longitudinal phase space of the beam while respecting the numerous constraints of the existing accelerator. The presented scheme...

Maintenance of electronic equipment at the Saclay Nuclear Research Centre

International Nuclear Information System (INIS)

Chicheportiche, Armand; Raoult, Norbert.

1975-06-01

The Test-Repair Group of the Saclay Electronics Services ensures the maintenance of electronic equipment available to users of the Saclay site. The more and more frequent use of microelectronics in these instruments increases the electronic operator density and the working and data transmission sequences are becoming difficult to understand. This leads to complications in the adjustment, testing and repairs. Ways and means are studied to facilitate maintenance while reducing the immobilization time of the equipment and the repair costs. The Saclay Electronics Services have developed a method of systematic test sequence formulation and breakdown diagnosis based on the properties of binary analysis. This method is used by a supplier of the CEA which has built the corresponding test equipment. Owing to the test programmmes established for each component of an apparatus it is possible for example to locate a faulty element on a plan including more than 100 integrated circuits and to replace it in no more than 10 minutes [fr

Medical equipment management

CERN Document Server

Willson, Keith; Tabakov, Slavik

2013-01-01

Know What to Expect When Managing Medical Equipment and Healthcare Technology in Your Organization As medical technology in clinical care becomes more complex, clinical professionals and support staff must know how to keep patients safe and equipment working in the clinical environment. Accessible to all healthcare professionals and managers, Medical Equipment Management presents an integrated approach to managing medical equipment in healthcare organizations. The book explains the underlying principles and requirements and raises awareness of what needs to be done and what questions to ask. I

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...

Effects of earthquake induced rock shear on containment system integrity. Laboratory testing plan development

International Nuclear Information System (INIS)

Read, Rodney S.

2011-07-01

This report describes a laboratory-scale testing program plan to address the issue of earthquake induced rock shear effects on containment system integrity. The document contains a review of relevant literature from SKB covering laboratory testing of bentonite clay buffer material, scaled analogue tests, and the development of related material models to simulate rock shear effects. The proposed testing program includes standard single component tests, new two-component constant volume tests, and new scaled analogue tests. Conceptual drawings of equipment required to undertake these tests are presented along with a schedule of tests. The information in this document is considered sufficient to engage qualified testing facilities, and to guide implementation of laboratory testing of rock shear effects. This document was completed as part of a collaborative agreement between SKB and Nuclear Waste Management Organization (NWMO) in Canada

Effects of earthquake induced rock shear on containment system integrity. Laboratory testing plan development

Energy Technology Data Exchange (ETDEWEB)

Read, Rodney S. (RSRead Consulting Inc. (Canada))

2011-07-15

This report describes a laboratory-scale testing program plan to address the issue of earthquake induced rock shear effects on containment system integrity. The document contains a review of relevant literature from SKB covering laboratory testing of bentonite clay buffer material, scaled analogue tests, and the development of related material models to simulate rock shear effects. The proposed testing program includes standard single component tests, new two-component constant volume tests, and new scaled analogue tests. Conceptual drawings of equipment required to undertake these tests are presented along with a schedule of tests. The information in this document is considered sufficient to engage qualified testing facilities, and to guide implementation of laboratory testing of rock shear effects. This document was completed as part of a collaborative agreement between SKB and Nuclear Waste Management Organization (NWMO) in Canada

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

A new method to determine J0-integral values (ASTM E 813) without any auxiliary equipment

International Nuclear Information System (INIS)

Ullrich, G.; Krompholz, K.

1987-01-01

In this contribution the path independent J-integral according to J.R. Rice, respective J.D. Landes and J.A. Begley due to ASTME 813 is calculated by the product J pl = d v J el for 3 point bend type specimen. Here d v is the load point displacement up to the point of the onset of stable crack growth V, which is taken from the load versus load point displacement diagram and J el a value which is equivalent to K 2 /E, where K is the stress intensity factor (ASTME 399) and E is Young's modulus. The advantage of the new procedure is the simplicity of the test arrangement and of the evaluation with the determination of initiation point V without computer or other auxiliary equipment. (orig.) [de

Design and testing of integrated circuits for reactor protection channels

International Nuclear Information System (INIS)

Battle, R.E.; Vandermolen, R.I.; Jagadish, U.; Swail, B.K.; Naser, J.; Rana, I.

1995-01-01

Custom and semicustom application-specific integrated circuit design and testing methods are investigated for use in research and commercial nuclear reactor safety systems. The Electric Power Research Institute and Oak Ridge National Laboratory are working together through a cooperative research and development agreement to apply modern technology to a nuclear reactor protection system. Purpose of this project is to demonstrate to the nuclear industry an alternative approach for new or upgrade reactor protection and safety system signal processing and voting logic. Motivation for this project stems from (1) the difficulty of proving that software-based protection systems are adequately reliable, (2) the obsolescence of the original equipment, and (3) the improved performance of digital processing

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).

An integrated approach to calculate life cycle costs of arms and military equipment

Directory of Open Access Journals (Sweden)

Vlada S. Sokolović

2013-12-01

, costs are one of the most dominant parameters in decision-making. Modern trends in this area comprehensively perceive all costs during the life cycle of assets.In general, in the analysis of costs in the life cycle of AME there are two sets of costs: visible and invisible (hidden costs. The visible part of the costs is mainly present in decision-making and usually includes the cost of equipping units or purchase of assets. The invisible part of the costs is far more significant. Although it is larger than the visible part and covers more groups of costs, decision-makers often do not take it into account. The hidden costs include: distribution costs, operating costs, maintenance costs, training costs, inventory costs, information systems costs, the cost of disposal and write-offs, etc. The decision making problem about investment in the AME purchase and equipping is obviously of  multicriteria nature, whether an optimum combination of costs for one  technical system (AME is in question, or whether it is a choice of a system of AME among many offered. COST ANALYSIS OF A PARTICULAR  ASSET For the illustration of an integrated approach to the analysis of the cost of assets in their life-cycle, a model from the US Naval Postgraduate School, was adjusted and applied on an example of a real asset. The model is applied to the case of two  squadrons of identical aircraft based at different airports. With regard to the availability, confidentiality, and the variability of costs and reliability of the elements of AME, the calculations in the model are implemented on the basis of the estimated or orientation parameters. Essentially, the goal is to demonstrate the interdependence, mutual relations and influences of parameters and their ultimate impact on the overall cost of military assets. Applying the model to a particular example points to the fact that, in the first years of asset life, the dominant cost is that of asset procurement (cost of acquisition, cost of assets

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)

UAS Integration in the NAS Project: Integrated Test and Evaluation (IT&E) Flight Test 3. Revision E

Science.gov (United States)

Marston, Michael

2015-01-01

The desire and ability to fly Unmanned Aircraft Systems (UAS) in the National Airspace System (NAS) is of increasing urgency. The application of unmanned aircraft to perform national security, defense, scientific, and emergency management are driving the critical need for less restrictive access by UAS to the NAS. UAS represent a new capability that will provide a variety of services in the government (public) and commercial (civil) aviation sectors. The growth of this potential industry has not yet been realized due to the lack of a common understanding of what is required to safely operate UAS in the NAS. NASA's UAS Integration into the NAS Project is conducting research in the areas of Separation Assurance/Sense and Avoid Interoperability, Human Systems Integration (HSI), and Communication to support reducing the barriers of UAS access to the NAS. This research is broken into two research themes namely, UAS Integration and Test Infrastructure. UAS Integration focuses on airspace integration procedures and performance standards to enable UAS integration in the air transportation system, covering Sense and Avoid (SAA) performance standards, command and control performance standards, and human systems integration. The focus of Test Infrastructure is to enable development and validation of airspace integration procedures and performance standards, including the integrated test and evaluation. In support of the integrated test and evaluation efforts, the Project will develop an adaptable, scalable, and schedulable relevant test environment capable of evaluating concepts and technologies for unmanned aircraft systems to safely operate in the NAS. To accomplish this task, the Project will conduct a series of Human-in-the-Loop and Flight Test activities that integrate key concepts, technologies and/or procedures in a relevant air traffic environment. Each of the integrated events will build on the technical achievements, fidelity and complexity of the previous tests and

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)

Test Procedure - pumping system for caustic addition project

International Nuclear Information System (INIS)

Leshikar, G.A.

1994-01-01

This test procedure provides the requirements for sub-system testing and integrated operational testing of the submersible mixer pump and caustic addition equipment by WHC and Kaiser personnel at the Rotating Equipment Shop run-in pit (Bldg. 272E)

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

Assessment of electrical equipment aging for nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

The electrical and instrumentation equipments, especially whose parts are made of polymer material, are gradually degraded by thermal and radiation environment in the normal operation, and the degradation is thought to progress rapidly when they are exposed to the environment of the design basis event (DBE). The integrity of the equipments is evaluated by the environmental qualification (EQ) test simulating the environment of the normal operation and the DBE. The project of 'Assessment of Cable Aging for Nuclear Power Plants' (ACA, 2002-2008) indicated the importance of applying simultaneous thermal and radiation aging for simulating the aging in normal operation. The project of 'Assessment of Electrical Equipment Aging for Nuclear Power Plants' (AEA) was initiated in FY2008 to apply the outcome of ACA to the other electrical and instrumentation equipment and to establish an advanced EQ test method that can appropriately simulate the environment in actual plants. In FY2012, aging characteristics of thermal aging and simultaneous aging were obtained for the epoxy resin of electrical penetrations and the O-ring of connectors. Physical property measurement was carried out for epoxy resin of electrical penetration subject to the type testing in FY2010. (author)

Assessment of electrical equipment aging for nuclear power plant

International Nuclear Information System (INIS)

2013-01-01

The electrical and instrumentation equipments, especially whose parts are made of polymer material, are gradually degraded by thermal and radiation environment in the normal operation, and the degradation is thought to progress rapidly when they are exposed to the environment of the design basis event (DBE). The integrity of the equipments is evaluated by the environmental qualification (EQ) test simulating the environment of the normal operation and the DBE. The project of 'Assessment of Cable Aging for Nuclear Power Plants' (ACA, 2002-2008) indicated the importance of applying simultaneous thermal and radiation aging for simulating the aging in normal operation. The project of 'Assessment of Electrical Equipment Aging for Nuclear Power Plants' (AEA) was initiated in FY2008 to apply the outcome of ACA to the other electrical and instrumentation equipment and to establish an advanced EQ test method that can appropriately simulate the environment in actual plants. In FY2012, aging characteristics of thermal aging and simultaneous aging were obtained for the epoxy resin of electrical penetrations and the O-ring of connectors. Physical property measurement was carried out for epoxy resin of electrical penetration subject to the type testing in FY2010. (author)

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

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.

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)

Cryogenic Fiber Optic Assemblies for Spaceflight Environments: Design, Manufacturing, Testing, and Integration

Science.gov (United States)

Thomes, W. Joe; Ott, Melanie N.; Chuska, Richard; Switzer, Robert; Onuma, Eleanya; Blair, Diana; Frese, Erich; Matyseck, Marc

2016-01-01

Fiber optic assemblies have been used on spaceflight missions for many years as an enabling technology for routing, transmitting, and detecting optical signals. Due to the overwhelming success of NASA in implementing fiber optic assemblies on spaceflight science-based instruments, system scientists increasingly request fibers that perform in extreme environments while still maintaining very high optical transmission, stability, and reliability. Many new applications require fiber optic assemblies that will operate down to cryogenic temperatures as low as 20 Kelvin. In order for the fiber assemblies to operate with little loss in optical throughput at these extreme temperatures requires a system level approach all the way from how the fiber assembly is manufactured to how it is held, routed, and integrated. The NASA Goddard Code 562 Photonics Group has been designing, manufacturing, testing, and integrating fiber optics for spaceflight and other high reliability applications for nearly 20 years. Design techniques and lessons learned over the years are consistently applied to developing new fiber optic assemblies that meet these demanding environments. System level trades, fiber assembly design methods, manufacturing, testing, and integration will be discussed. Specific recent examples of ground support equipment for the James Webb Space Telescope (JWST); the Ice, Cloud and Land Elevation Satellite-2 (ICESat-2); and others will be included.

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.

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.

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

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

Development of remote handling tools and equipment

International Nuclear Information System (INIS)

Nakahira, Masataka; Oka, Kiyoshi; Taguchi, Kou; Ito, Akira; Fukatsu, Seiichi; Oda, Yasushi; Kajiura, Soji; Yamazaki, Seiichiro; Aoyama, Kazuo.

1997-01-01

The remote handling (RH) tools and equipment development in ITER focuses mainly on the welding and cutting technique, weld inspection and double-seal door which are essential factors in the replacement of in-vessel components such as divertor and blanket. The conceptual design of these RH tools and equipment has been defined through ITER engineering design activity (EDA). Similarly, elementary R and D of the RH tools and equipment have been extensively performed to accumulate a technological data base for process and performance qualification. Based on this data, fabrications of full-scale RH tools and equipment are under progress. A prototypical bore tool for pipe welding and cutting has already been fabricated and is currently undergoing integrated performance tests. This paper describes the design outline of the RH tools and equipment related to in-vessel components maintenance, and highlights the current status of RH tools and equipment development by the Japan Home Team as an ITER R and D program. This paper also includes an outline of insulation joint and quick-pipe connector development, which has also been conducted through the ITER R and D program in order to standardize RH operations and components. (author)

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.)

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.

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.

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.

Electronic equipment packaging technology

CERN Document Server

Ginsberg, Gerald L

1992-01-01

The last twenty years have seen major advances in the electronics industry. Perhaps the most significant aspect of these advances has been the significant role that electronic equipment plays in almost all product markets. Even though electronic equipment is used in a broad base of applications, many future applications have yet to be conceived. This versatility of electron­ ics has been brought about primarily by the significant advances that have been made in integrated circuit technology. The electronic product user is rarely aware of the integrated circuits within the equipment. However, the user is often very aware of the size, weight, mod­ ularity, maintainability, aesthetics, and human interface features of the product. In fact, these are aspects of the products that often are instrumental in deter­ mining its success or failure in the marketplace. Optimizing these and other product features is the primary role of Electronic Equipment Packaging Technology. As the electronics industry continues to pr...

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...

Phase III Simplified Integrated Test (SIT) results - Space Station ECLSS testing

Science.gov (United States)

Roberts, Barry C.; Carrasquillo, Robyn L.; Dubiel, Melissa Y.; Ogle, Kathryn Y.; Perry, Jay L.; Whitley, Ken M.

1990-01-01

During 1989, phase III testing of Space Station Freedom Environmental Control and Life Support Systems (ECLSS) began at Marshall Space Flight Center (MSFC) with the Simplified Integrated Test. This test, conducted at the MSFC Core Module Integration Facility (CMIF), was the first time the four baseline air revitalization subsystems were integrated together. This paper details the results and lessons learned from the phase III SIT. Future plans for testing at the MSFC CMIF are also discussed.

Performance evaluation of the quarter-scale Russian retrieval equipment for the removal of hazardous waste

International Nuclear Information System (INIS)

Enderlin, C.W.; Mullen, O.D.; Terrones, G.

1997-09-01

This report describes the test program for evaluating the Russian Retrieval Equipment fabricated by the Integrated Mining Chemical Company (IMCC) and delivered to the US by Radiochem Services Company (RCSC), both of Russia. The testing and fabrication of this equipment were sponsored by the US Department of Energy (DOE). The tests described in this report were conducted at the Pacific Northwest National Laboratory (PNNL) at the DOE Hanford Site by the Retrieval Process Development and Enhancement (RPD and E) team of the Tank Focus Area program (TFA). Tests were carried out jointly by Russian and US personnel for the purpose of evaluating the Russian Retrieval Equipment for potential deployment within the DOE complex. Section 1.0 of this report presents the objectives and a brief background for the test program. The Russian Equipment is described in Section 2.0. Section 3.0 describes the approach taken for testing the equipment. The results of the tests and an analysis of the data are described in Section 4.0. The results and observations obtained from the tests are discussed in Section 5.0. Recommendations and conclusions are presented in Section 6.0

On line ultrasonic integrated backscatter

International Nuclear Information System (INIS)

Landini, L.; Picano, E.; Mazzarisi, A.; Santarelli, F.; Benassi, A.; De Pieri, G.

1988-01-01

A new equipment for on-line evaluation of index based on two-dimensional integrated backscatter from ultrasonic images is described. The new equipment is fully integrated into a B-mode ultrasonic apparatus which provides a simultaneous display of conventional information together with parameters of tissue characterization. The system has been tested with a backscattering model of microbubbles in polysaccharide solution, characterized by a physiological exponential time decay. An exponential fitting to the experimental data was performed which yielded r=0.95

Integrated Ground Operations Demonstration Units Testing Plans and Status

Science.gov (United States)

Johnson, Robert G.; Notardonato, William U.; Currin, Kelly M.; Orozco-Smith, Evelyn M.

2012-01-01

Cryogenic propellant loading operations with their associated flight and ground systems are some of the most complex, critical activities in launch operations. Consequently, these systems and operations account for a sizeable portion of the life cycle costs of any launch program. NASA operations for handling cryogens in ground support equipment have not changed substantially in 50 years, despite advances in cryogenics, system health management and command and control technologies. This project was developed to mature, integrate and demonstrate advancement in the current state of the art in these areas using two distinct integrated ground operations demonstration units (GODU): GODU Integrated Refrigeration and Storage (IRAS) and GODU Autonomous Control

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.

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

Design and testing of integrated circuits for reactor protection channels

International Nuclear Information System (INIS)

Battle, R.E.; Vandermolen, R.I.; Jagadish, U.; Swail, B.K.; Naser, J.

1995-01-01

Custom and semicustom application-specific integrated circuit design and testing methods are investigated for use in research and commercial nuclear reactor safety systems. The Electric Power Research Institute and Oak Ridge National Laboratory are working together through a cooperative research and development agreement to apply modern technology to a nuclear reactor protection system. The purpose of this project is to demonstrate to the nuclear industry an alternative approach for new or upgrade reactor protection and safety system signal processing and voting logic. Motivation for this project stems from (1) the difficulty of proving that software-based protection systems are adequately reliable, (2) the obsolescence of the original equipment, and (3) the improved performance of digital processing. A demonstration model for protection system of PWR reactor has been designed and built

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

Evaluation of Design Models of Process Equipment for Use in PRIDE: Remote Operability and Maintainability

International Nuclear Information System (INIS)

Kim, Ki Ho; Kim, Sung Hyun; Yu, Seung Nam; Lee, Jong Kwang; Park, Byung Suk; Han, Jong Hui; Cho, Il Je; Lee, Han Soo

2012-01-01

Process equipment for pyroprocessing are being developed at KAERI (Korea Atomic Energy Research Institute). Those equipment should be operated and maintained in a fully remote manner in the argon gas filled cell of PRIDE (PyRoprocess Integrated inactive DEmonstration facility) at KAERI because direct human access to the in-cell is not possible during an operation due to the high toxicity of the argon gas. To make such process equipment remotely operable and maintainable, their design developments have been tested and evaluated in a simulator before they are constructed. A simulator as a means of evaluating the remote operability and maintainability of the design models of process equipment for pyroprocessing is described, and results of the design models tested and evaluated in a simulator are presented

Integration testing through reusing representative unit test cases for high-confidence medical software.

Science.gov (United States)

Shin, Youngsul; Choi, Yunja; Lee, Woo Jin

2013-06-01

As medical software is getting larger-sized, complex, and connected with other devices, finding faults in integrated software modules gets more difficult and time consuming. Existing integration testing typically takes a black-box approach, which treats the target software as a black box and selects test cases without considering internal behavior of each software module. Though it could be cost-effective, this black-box approach cannot thoroughly test interaction behavior among integrated modules and might leave critical faults undetected, which should not happen in safety-critical systems such as medical software. This work anticipates that information on internal behavior is necessary even for integration testing to define thorough test cases for critical software and proposes a new integration testing method by reusing test cases used for unit testing. The goal is to provide a cost-effective method to detect subtle interaction faults at the integration testing phase by reusing the knowledge obtained from unit testing phase. The suggested approach notes that the test cases for the unit testing include knowledge on internal behavior of each unit and extracts test cases for the integration testing from the test cases for the unit testing for a given test criteria. The extracted representative test cases are connected with functions under test using the state domain and a single test sequence to cover the test cases is produced. By means of reusing unit test cases, the tester has effective test cases to examine diverse execution paths and find interaction faults without analyzing complex modules. The produced test sequence can have test coverage as high as the unit testing coverage and its length is close to the length of optimal test sequences. Copyright © 2013 Elsevier Ltd. All rights reserved.

Overview of Power Quality and Integrated Testing at JSC

Science.gov (United States)

Davies, Francis

2018-01-01

This presentation describes the basic philosophy behind integrated testing and partially integrated testing. It lists some well known errors in space systems that were or could have been caught during integrated testing. Two examples of integrated testing at the Johnson Space Center (JSC) are mentioned, and then an overview of two test facilities that do power testing (partially integrated testing) at JSC are presented, with information on the capabilities of each. Finally a list of three projects that has problems caught during power quality or Electromagnetic Interference (EMI) testing is presented.

ITER diagnostics: Maintenance and commissioning in the hot cell test bed

International Nuclear Information System (INIS)

Walker, C.I.; Barnsley, R.; Costley, A.E.; Gottfried, R.; Haist, B.; Itami, K.; Kondoh, T.; Loesser, G.D.; Palmer, J.; Sugie, T.; Tesini, A.; Vayakis, G.

2005-01-01

In-vessel diagnostic equipment in ITER integrated in six equatorial and 12 upper ports, 16 divertor cassettes and five lower ports is designed to be removed in modules and then repaired, tested and commissioned in the same location at the ITER hot cell. The repair requirements and tests on these components are described along with design features that facilitate repair. The testing establishes the repair strategy, qualifies the refurbishment work and finally checks the mechanical and diagnostic function before the return of the modules. At the hot cell, a dummy port is provided for tests of mechanical and vacuum integrity as well as commissioning of the diagnostic equipment. The scope of the hot cell maintenance and commissioning activities is summarised and an overview of the integration of the diagnostic equipment is given

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)

Integration and test planning patterns in different organizations

NARCIS (Netherlands)

Jong, de I.S.M.; Boumen, R.; Mortel - Fronczak, van de J.M.; Rooda, J.E.; Tretmans, J.

2007-01-01

Planning an integration and test phase is often done by experts in the visited organizations. These experts have a thorough knowledge about the system, integration and testing and the business drivers of an organization. An integration and test plan developedfor an airplane is different than the

Actinide integral measurements in the CFRMF and integral tests for ENDF/B-V

International Nuclear Information System (INIS)

Anderl, R.A.

1982-01-01

Integral capture and/or fission rates have been reported earlier for several actinides irradiated in the fast neutron field of the Coupled Fast Reactivity Measurements Facility (CFRMF). These nuclides include 232 Th, 233 U, 235 U, 238 U, 237 Np, 239 Pu, 240 Pu, 242 Pu, 241 Am and 243 Am. This paper forucses on the utilization of these integral data for testing the respective cross sections on ENDF/B-V. Integral cross sections derived from the measured reaction rates are tabulated. Results are presented for cross-section data testing which includes integral testing based on a comparison of calculated and measured integral cross sections and testing based on least-squares-adjustment analyses

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.

Technical Report on Preliminary Methodology for Enhancing Risk Monitors with Integrated Equipment Condition Assessment

Energy Technology Data Exchange (ETDEWEB)

Ramuhalli, Pradeep; Coles, Garill A.; Coble, Jamie B.; Hirt, Evelyn H.

2013-09-17

Small modular reactors (SMRs) generally include reactors with electric output of ~350 MWe or less (this cutoff varies somewhat but is substantially less than full-size plant output of 700 MWe or more). Advanced SMRs (AdvSMRs) refer to a specific class of SMRs and are based on modularization of advanced reactor concepts. AdvSMRs may provide a longer-term alternative to traditional light-water reactors (LWRs) and SMRs based on integral pressurized water reactor concepts currently being considered. Enhancing affordability of AdvSMRs will be critical to ensuring wider deployment. AdvSMRs suffer from loss of economies of scale inherent in small reactors when compared to large (~greater than 600 MWe output) reactors. Some of this loss can be recovered through reduced capital costs through smaller size, fewer components, modular fabrication processes, and the opportunity for modular construction. However, the controllable day-to-day costs of AdvSMRs will be dominated by operation and maintenance (O&M) costs. Technologies that help characterize real-time risk are important for controlling O&M costs. Risk monitors are used in current nuclear power plants to provide a point-in-time estimate of the system risk given the current plant configuration (e.g., equipment availability, operational regime, and environmental conditions). However, current risk monitors are unable to support the capability requirements listed above as they do not take into account plant-specific normal, abnormal, and deteriorating states of active components and systems. This report documents technology developments that are a step towards enhancing risk monitors that, if integrated with supervisory plant control systems, can provide the capability requirements listed and meet the goals of controlling O&M costs. The report describes research results from an initial methodology for enhanced risk monitors by integrating real-time information about equipment condition and POF into risk monitors.

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

Preliminary piping layout and integration of European test blanket modules subsystems in ITER CVCS area

Energy Technology Data Exchange (ETDEWEB)

Tarallo, Andrea, E-mail: andrea.tarallo@unina.it [CREATE, University of Naples Federico II, DII, P.le Tecchio, 80, 80125 Naples (Italy); Mozzillo, Rocco; Di Gironimo, Giuseppe [CREATE, University of Naples Federico II, DII, P.le Tecchio, 80, 80125 Naples (Italy); Aiello, Antonio; Utili, Marco [ENEA UTIS, C.R. Brasimone, Bacino del Brasimone, I-40032 Camugnano, BO (Italy); Ricapito, Italo [TBM& MD Project, Fusion for Energy, EU Commission, Carrer J. Pla, 2, Building B3, 08019 Barcelona (Spain)

2015-04-15

Highlights: • The use of human modeling tools for piping design in view of maintenance is discussed. • A possible preliminary layout for TBM subsystems in CVCS area has been designed with CATIA. • A DHM-based method to quickly check for maintainability of piping systems is suggested. - Abstract: This paper explores a possible integration of some ancillary systems of helium-cooled lithium lead (HCLL) and helium-cooled pebble-bed (HCPB) test blanket modules in ITER CVCS area. Computer-aided design and ergonomics simulation tools have been fundamental not only to define suitable routes for pipes, but also to quickly check for maintainability of equipment and in-line components. In particular, accessibility of equipment and systems has been investigated from the very first stages of the design using digital human models. In some cases, the digital simulations have resulted in changes in the initial space reservations.

The Bosnian Train and Equip Program: A Lesson in Interagency Integration of Hard and Soft Power

Science.gov (United States)

2014-03-01

even before Bos- nia officially declared independence. Most of the weaponry and commanders from the former Yugoslav People’s Army in Bosnia, which was...ability, and disposition.” 505 It covers characteristics that research indicates affect team performance including attitudinal, de- mographic, and...The Train and Equip Program reduced foreign influence in the Federation, which helped remove impediments to reconciliation and integration in Bos- nia

Ares I Integrated Test Approach

Science.gov (United States)

Taylor, Jim

2008-01-01

This slide presentation reviews the testing approach that NASA is developing for the Ares I launch vehicle. NASA is planning a complete series of development, qualification and verification tests. These include: (1) Upper stage engine sea-level and altitude testing (2) First stage development and qualification motors (3) Upper stage structural and thermal development and qualification test articles (4) Main Propulsion Test Article (MPTA) (5) Upper stage green run testing (6) Integrated Vehicle Ground Vibration Testing (IVGVT) and (7) Aerodynamic characterization testing.

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.

Radiation protection instrumentation. Monitoring equipment. Radioactive aerosols in the environment

International Nuclear Information System (INIS)

1996-01-01

This international standard applies to portable or installed equipment for continuous monitoring of radioactive aerosols in the environment in normal and emergency conditions. Monitoring involves continuous sampling and, where desirable, automatic start of sampling. The document applies particularly to the following assignments: (i) determination of the volume activity of radionuclides in the form of aerosols, either per time unit, along with its time changes, or in the integral form over a longer time period such as 24 h, and measurement of the volume sampled; (ii) triggering a warning alarm signal if the preset volume activity or time integral of the volume activity of aerosols has been exceeded. The document deals with radioactive aerosol monitor design, testing procedures, and documentation. Appended tables refer to the reference and normal testing conditions, tests in normal testing conditions, tests during changes of the affecting quantities, and tests of the air circuit. (P.A.)

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

Comprehensive analysis and evaluation of big data for main transformer equipment based on PCA and Apriority

Science.gov (United States)

Guo, Lijuan; Yan, Haijun; Hao, Yongqi; Chen, Yun

2018-01-01

With the power supply level of urban power grid toward high reliability development, it is necessary to adopt appropriate methods for comprehensive evaluation of existing equipment. Considering the wide and multi-dimensional power system data, the method of large data mining is used to explore the potential law and value of power system equipment. Based on the monitoring data of main transformer and the records of defects and faults, this paper integrates the data of power grid equipment environment. Apriori is used as an association identification algorithm to extract the frequent correlation factors of the main transformer, and the potential dependence of the big data is analyzed by the support and confidence. Then, the integrated data is analyzed by PCA, and the integrated quantitative scoring model is constructed. It is proved to be effective by using the test set to validate the evaluation algorithm and scheme. This paper provides a new idea for data fusion of smart grid, and provides a reference for further evaluation of big data of power grid equipment.

Wafer-level testing and test during burn-in for integrated circuits

CERN Document Server

Bahukudumbi, Sudarshan

2010-01-01

Wafer-level testing refers to a critical process of subjecting integrated circuits and semiconductor devices to electrical testing while they are still in wafer form. Burn-in is a temperature/bias reliability stress test used in detecting and screening out potential early life device failures. This hands-on resource provides a comprehensive analysis of these methods, showing how wafer-level testing during burn-in (WLTBI) helps lower product cost in semiconductor manufacturing.Engineers learn how to implement the testing of integrated circuits at the wafer-level under various resource constrain

Operational test report, integrated system test (ventilation upgrade)

International Nuclear Information System (INIS)

HARTY, W.M.

1999-01-01

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

Operational test report integrated system test (ventilation upgrade)

Energy Technology Data Exchange (ETDEWEB)

HARTY, W.M.

1999-10-05

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

Handling equipment Selection in open pit mines by using an integrated model based on group decision making

Directory of Open Access Journals (Sweden)

Abdolreza Yazdani-Chamzini

2012-10-01

Full Text Available Process of handling equipment selection is one of the most important and basic parts in the project planning, particularly mining projects due to holding a high charge of the total project's cost. Different criteria impact on the handling equipment selection, while these criteria often are in conflicting with each other. Therefore, the process of handling equipment selection is a complex and multi criteria decision making problem. There are a variety of methods for selecting the most appropriate equipment among a set of alternatives. Likewise, according to the sophisticated structure of the problem, imprecise data, less of information, and inherent uncertainty, the usage of the fuzzy sets can be useful. In this study a new integrated model based on fuzzy analytic hierarchy process (FAHP and fuzzy technique for order preference by similarity to ideal solution (FTOPSIS is proposed, which uses group decision making to reduce individual errors. In order to calculate the weights of the evaluation criteria, FAHP is utilized in the process of handling equipment selection, and then these weights are inserted to the FTOPSIS computations to select the most appropriate handling system among a pool of alternatives. The results of this study demonstrate the potential application and effectiveness of the proposed model, which can be applied to different types of sophisticated problems in real problems.

Passive BWR integral LOCA testing at the Karlstein test facility INKA

Energy Technology Data Exchange (ETDEWEB)

Drescher, Robert [AREVA GmbH, Erlangen (Germany); Wagner, Thomas [AREVA GmbH, Karlstein am Main (Germany); Leyer, Stephan [TH University of Applied Sciences, Deggendorf (Germany)

2014-05-15

KERENA is an innovative AREVA GmbH boiling water reactor (BWR) with passive safety systems (Generation III+). In order to verify the functionality of the reactor design an experimental validation program was executed. Therefore the INKA (Integral Teststand Karlstein) test facility was designed and erected. It is a mockup of the BWR containment, with integrated pressure suppression system. While the scaling of the passive components and the levels match the original values, the volume scaling of the containment compartments is approximately 1:24. The storage capacity of the test facility pressure vessel corresponds to approximately 1/6 of the KERENA RPV and is supplied by a benson boiler with a thermal power of 22 MW. In March 2013 the first integral test - Main Steam Line Break (MSLB) - was executed. The test measured the combined response of the passive safety systems to the postulated initiating event. The main goal was to demonstrate the ability of the passive systems to ensure core coverage, decay heat removal and to maintain the containment within defined limits. The results of the test showed that the passive safety systems are capable to bring the plant to stable conditions meeting all required safety targets with sufficient margins. Therefore the test verified the function of those components and the interplay between them. The test proved that INKA is an unique test facility, capable to perform integral tests of passive safety concepts under plant-like conditions. (orig.)

Multisignal detecting system of pile integrity testing

Science.gov (United States)

Liu, Zuting; Luo, Ying; Yu, Shihai

2002-05-01

The low strain reflection wave method plays a principal rule in the integrating detection of base piles. However, there are some deficiencies with this method. For example, there is a blind area of detection on top of the tested pile; it is difficult to recognize the defects at deep-seated parts of the pile; there is still the planar of 3D domino effect, etc. It is very difficult to solve these problems only with the single-transducer pile integrity testing system. A new multi-signal piles integrity testing system is proposed in this paper, which is able to impulse and collect signals on multiple points on top of the pile. By using the multiple superposition data processing method, the detecting system can effectively restrain the interference and elevate the precision and SNR of pile integrity testing. The system can also be applied to the evaluation of engineering structure health.

Multiloop integral system test (MIST)

International Nuclear Information System (INIS)

Gloudemans, J.R.

1989-07-01

The multiloop integral system test (MIST) was part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock and Wilcox-designed plants. MIST was sponsored by the US Nuclear Regulatory Commission, the Babcock and Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock and Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral system facilities to address the thermal-hydraulic SBLOCA questions. MIST and two other supporting facilities were specifically designed and constructed for this program, and an existing facility -- the once-through integral system (OTIS) -- was also used. Data from MIST and the other facilities will be used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The individual tests are described in detail in Volumes 2 through 8 and Volume 11, and are summarized in Volume 1. Inter-group comparisons are addressed in this document, Volume 9. These comparisons are grouped as follows: mapping versus SBLOCA transients, SBLOCA, pump effects, and the effects of noncondensible gases. Appendix A provides an index and description of the microfiched plots for each test, which are enclosed with the corresponding Volumes 2 through 8. 147 figs., 5 tabs

Structural integration of separation and reaction systems: I. Integration of stage-wise processes

Directory of Open Access Journals (Sweden)

Mitrović Milan

2002-01-01

Full Text Available The structural integration of separation processes, using multifunctional equipment, has been studied on four stage-wise liquid-liquid separations extraction, absorption, distillation, adsorption and on some combinations of these processes. It was shown for stage - wise processes that the ultimate aim of equipment integration is 3-way integration (by components by steps and by stages and that membrane multiphase contactors present concerning the equipment optimal solutions in many cases. First, by using partially integrated equipment and, later by developing fully integrated systems it was experimentally confirmed that structural 3-way integration produces much higher degrees of component separations and component enrichments in compact and safe equipment.

Design considerations, tooling and equipment for remote in-service inspection of radioactive piping and pressure vessel systems

International Nuclear Information System (INIS)

Schmoker, D.S.; Swannack, D.L.

1983-01-01

In-Service Inspection programs are performed to monitor and verify the integrity of a nuclear power plant's primary pressure boundaries. Early detection of abnormal structural or material degradation could preclude serious damage to plant systems. This paper summarizes results obtained in use of remotely-operated nondestructive testing (NDT) equipment for inspection of reactor system components. Experience obtained in operating the Fast Flux Test Facility (FFTF) has provided a basis for field verification of remote NDT equipment designs and has suggested development improvements. Remote Viewing and data gathering systems used include periscopes, borescopes, fiberscopes, hybrid borescopes/fiberscopes, and closed circuit television. A summary of design consideration for inspection equipment and power plant design is presented to achieve improved equipment operation and reduction of plant maintenance downtime

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)

Electric vehicle station equipment for grid-integrated vehicles

Science.gov (United States)

Kempton, Willett; Kiamilev, Fouad; McGee, Rodney; Waite, Nick

2017-09-05

Methods, systems, and apparatus transferring power between the grid and an electric vehicle are disclosed. The apparatus may include at least one vehicle communication port for interfacing with electric vehicle equipment (EVE) and a processor coupled to the at least one vehicle communication port to establish communication with the EVE, receive EVE attributes from the EVE, and transmit electric vehicle station equipment (EVSE) attributes to the EVE. Power may be transferred between the grid and the electric vehicle by maintaining EVSE attributes, establishing communication with the EVE, and transmitting the EVSE maintained attributes to the EVE.

Performance test of nutrient control equipment for hydroponic plants

Science.gov (United States)

Rahman, Nurhaidar; Kuala, S. I.; Tribowo, R. I.; Anggara, C. E. W.; Susanti, N. D.

2017-11-01

Automatic control equipment has been made for the nutrient content in irrigation water for hydroponic plants. Automatic control equipment with CCT53200E conductivity controller to nutrient content in irrigation water for hydroponic plants, can be used to control the amount of TDS of nutrient solution in the range of TDS numbers that can be set according to the range of TDS requirements for the growth of hydroponically cultivated crops. This equipment can minimize the work time of hydroponic crop cultivators. The equipment measurement range is set between 1260 ppm up to 1610 ppm for spinach plants. Caisim plants were included in this experiment along with spinach plants with a spinach plants TDS range. The average of TDS device is 1450 ppm, while manual (conventional) is 1610 ppm. Nutrient solution in TDS controller has pH 5,5 and temperature 29,2 °C, while manual is pH 5,6 and temperature 31,3 °C. Manually treatment to hydroponic plant crop, yields in an average of 39.6 grams/plant, greater than the yield of spinach plants with TDS control equipment, which is in an average of 24.6 grams / plant. The yield of caisim plants by manual treatment is in an average of 32.3 grams/crop, less than caisim crop yields with TDS control equipment, which is in an average of 49.4 grams/plant.

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

The Integral Test Facility Karlstein

Directory of Open Access Journals (Sweden)

Stephan Leyer

2012-01-01

Full Text Available The Integral Test Facility Karlstein (INKA test facility was designed and erected to test the performance of the passive safety systems of KERENA, the new AREVA Boiling Water Reactor design. The experimental program included single component/system tests of the Emergency Condenser, the Containment Cooling Condenser and the Passive Core Flooding System. Integral system tests, including also the Passive Pressure Pulse Transmitter, will be performed to simulate transients and Loss of Coolant Accident scenarios at the test facility. The INKA test facility represents the KERENA Containment with a volume scaling of 1 : 24. Component heights and levels are in full scale. The reactor pressure vessel is simulated by the accumulator vessel of the large valve test facility of Karlstein—a vessel with a design pressure of 11 MPa and a storage capacity of 125 m3. The vessel is fed by a benson boiler with a maximum power supply of 22 MW. The INKA multi compartment pressure suppression Containment meets the requirements of modern and existing BWR designs. As a result of the large power supply at the facility, INKA is capable of simulating various accident scenarios, including a full train of passive systems, starting with the initiating event—for example pipe rupture.

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)

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

TFTR neutral-beam test facility

International Nuclear Information System (INIS)

Turitzin, N.M.; Newman, R.A.

1981-11-01

TFTR Neutral Beam System will have thirteen discharge ion sources, each with its own power supply. Twelve of these will be utilized for supplemental heating of the TFTR tokamak plasma, while the thirteenth will be dedicated to an off-machine test chamber for source development and/or conditioning. A test installation for one source was set up using prototype equipment to discover and correct possible deficiencies, and to properly coordinate the equipment. This test facility represents the first opportunity for assembling an integrated system of hardware supplied by diverse vendors, each of whom designed and built his equipment to performance specifications. For the installation and coordination of the different portions of the total system, particular attention was given to personnel safety and safe equipment operation. This paper discusses various system components, their characteristics, interconnection and control. Results of the recently initiated test phase will be reported at a later date

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

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

International Nuclear Information System (INIS)

Galioto, T.M.

1994-01-01

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

Wireless sensors for predictive maintenance of rotating equipment in research reactors

International Nuclear Information System (INIS)

Hashemian, H.M.

2011-01-01

In 2008-2009, the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) tested the potential of predictive or condition-based maintenance techniques to reduce maintenance costs, minimize the risk of catastrophic failures, and maximize system availability by attaching wireless-based sensors to selected rotating equipment at HFIR. Rotating equipment is an ideal 'test case' for the viability of integrated, online predictive maintenance strategies because motors, bearings, and shafts are ubiquitous in nuclear power plants and because the maintenance methods typically performed on rotating equipment today (such as portable or handheld vibration data collection equipment) are highly labor-intensive. The HFIR project achieved all five of its objectives: (1) to identify rotating machinery of the types used in research reactors and determine their operational characteristics, degradation mechanisms, and failure modes, (2) to establish a predictive maintenance program for rotating equipment in research reactors, (3) to identify wireless sensors that are suitable for predictive maintenance of rotating machinery and test them in a laboratory setting, (4) to establish the requirements and procedures to be followed when implementing wireless sensors for predictive maintenance in research reactors, and (5) to develop a conceptual design for a predictive maintenance system for research reactors based on wireless sensors. The project demonstrated that wireless sensors offer an effective method for monitoring key process conditions continuously and remotely, thereby enhancing the safety, reliability, and efficiency of the aging research reactor fleet.

Automated Quality Assurance of Medical Digital X-Ray Equipment

International Nuclear Information System (INIS)

Zelikman, Mikhail; Kruchinin, Sergey

2013-06-01

Quality assurance of the x-ray equipment includes a set of various tests among which are installation and periodic exams performed by qualified engineers as well as daily routine tests carried out by the medical staff of the Radiology Department. As a rule, the decision concerning the applicability of the x-ray equipment for using in clinical studies is made on the basis of the routine tests results. The presented method is based on the detector's output signals, Signal-to-Noise Ratio and Modulation Transfer Function evaluation in automated way using the simple test-object's digital image registered with given geometry and x-ray exposure parameters settings. Rectangular 20 mm thick aluminum plate with fixed 1 mm thick well-finished steel edge (for general x-ray radiography/fluoroscopy systems) or 2 mm thick aluminum plate with fixed 1 mm thick aluminum well-finished edge (for digital x-ray mammography systems) can be used as a test equipment. Relevant to the decision concerning the x-ray device operation status are the parameters: deviations from the reference levels of the tube voltage and mAs as well as internal detector's noise variance and detector's gain deviations. Everyday testing procedure includes the following steps. On the first step the roentgenographer places the test-object at the center of the detector's surface, makes an exposure with specified parameters setting and geometry and after this, test results are displayed on the work station monitor or console screen in automatic way. In order to provide an automated regime of the presenting algorithm, the software must be integrated with the program module intended for the x-ray device control. The use of the presented method in clinical practice provides the reliable daily monitoring of the x-ray equipment operation status prior to its utilizing for patient diagnostic process. As a rule, it will take not more than 3-5 minutes for the roentgenographer to complete the routine

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

An Updated Methodology for Enhancing Risk Monitors with Integrated Equipment Condition Assessment

Energy Technology Data Exchange (ETDEWEB)

Ramuhalli, Pradeep [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hirt, Evelyn H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Coles, Garill A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bonebrake, Christopher A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ivans, William J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wootan, David W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Mitchell, Mark R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-07-18

Small modular reactors (SMRs) generally include reactors with electric output of ~350 MWe or less (this cutoff varies somewhat but is substantially less than full-size plant output of 700 MWe or more). Advanced SMRs (AdvSMRs) refer to a specific class of SMRs and are based on modularization of advanced reactor concepts. Enhancing affordability of AdvSMRs will be critical to ensuring wider deployment, as AdvSMRs suffer from loss of economies of scale inherent in small reactors when compared to large (~greater than 600 MWe output) reactors and the controllable day-to-day costs of AdvSMRs will be dominated by operation and maintenance (O&M) costs. Technologies that help characterize real-time risk are important for controlling O&M costs. Risk monitors are used in current nuclear power plants to provide a point-in-time estimate of the system risk given the current plant configuration (e.g., equipment availability, operational regime, and environmental conditions). However, current risk monitors are unable to support the capability requirements listed above as they do not take into account plant-specific normal, abnormal, and deteriorating states of active components and systems. This report documents technology developments towards enhancing risk monitors that, if integrated with supervisory plant control systems, can provide the capability requirements listed and meet the goals of controlling O&M costs. The report describes research results on augmenting an initial methodology for enhanced risk monitors that integrate real-time information about equipment condition and POF into risk monitors. Methods to propagate uncertainty through the enhanced risk monitor are evaluated. Available data to quantify the level of uncertainty and the POF of key components are examined for their relevance, and a status update of this data evaluation is described. Finally, we describe potential targets for developing new risk metrics that may be useful for studying trade-offs for economic

The pharmaceutical vial capping process: Container closure systems, capping equipment, regulatory framework, and seal quality tests.

Science.gov (United States)

Mathaes, Roman; Mahler, Hanns-Christian; Buettiker, Jean-Pierre; Roehl, Holger; Lam, Philippe; Brown, Helen; Luemkemann, Joerg; Adler, Michael; Huwyler, Joerg; Streubel, Alexander; Mohl, Silke

2016-02-01

Parenteral drug products are protected by appropriate primary packaging to protect against environmental factors, including potential microbial contamination during shelf life duration. The most commonly used CCS configuration for parenteral drug products is the glass vial, sealed with a rubber stopper and an aluminum crimp cap. In combination with an adequately designed and controlled aseptic fill/finish processes, a well-designed and characterized capping process is indispensable to ensure product quality and integrity and to minimize rejections during the manufacturing process. In this review, the health authority requirements and expectations related to container closure system quality and container closure integrity are summarized. The pharmaceutical vial, the rubber stopper, and the crimp cap are described. Different capping techniques are critically compared: The most common capping equipment with a rotating capping plate produces the lowest amount of particle. The strength and challenges of methods to control the capping process are discussed. The residual seal force method can characterize the capping process independent of the used capping equipment or CCS. We analyze the root causes of several cosmetic defects associated with the vial capping process. Copyright © 2015 Elsevier B.V. All rights reserved.

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.

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.

Ion chamber-electrometer measurement system for radiation protection tests in X-ray equipment for interventional procedures

International Nuclear Information System (INIS)

Bottaro, Marcio

2012-01-01

A new parallel plate ionization chamber with volume of 500 cc and an electrometer with digital interface for data acquisition, configuring an ion chamber electrometer measurement system, were developed to comply with specific requirements for compulsory radiation protection tests in interventional X-ray equipment. The ion chamber has as main characteristics: low cost, mechanical strength and response variation with beam energy of less than 5% in the 40 kV to 150 kV range. The electrometer has a high gain (5x10 8 V/A) transimpedance amplifier circuit and a data acquisition and control system developed in LabVIEW ® platform, including an integrated power supply for the ion chamber bias with adjustable DC voltage output from O to 1000 V and an air density correction system. Electric field calculations, laboratory measurements in standard beams and computational simulations of radiation interactions in chamber volume with Monte Carlo Method were employed in the elaborated methodology of the ion chamber development, which was tested and validated. It was also developed a simplified methodology for electrometer calibration that assures metrological trustworthiness of the measurement system. Tests for the system performance evaluation as environmental influence response, energy response, angular dependency, linearity and air kerma and air kerma rate dependency were performed according to international standards and requirements. Additionally, for a detailed evaluation of the developed ion chamber, simulations with various scattered radiation spectra were performed. The system was applied in leakage radiation, residual radiation and scattered radiation tests, being compared with other reference systems and validated for laboratorial test routine. (author)

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.

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

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)

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

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

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.

Advanced Stirling Convertor Dual Convertor Controller Testing at NASA Glenn Research Center in the Radioisotope Power Systems System Integration Laboratory

Science.gov (United States)

Dugala, Gina M.; Taylor, Linda M.; Bell, Mark E.; Dolce, James L.; Fraeman, Martin; Frankford, David P.

2015-01-01

NASA Glenn Research Center developed a nonnuclear representation of a Radioisotope Power System (RPS) consisting of a pair of Advanced Stirling Convertors (ASCs), Dual Convertor Controller (DCC) EMs (engineering models) 2 and 3, and associated support equipment, which were tested in the Radioisotope Power Systems System Integration Laboratory (RSIL). The DCC was designed by the Johns Hopkins University Applied Physics Laboratory (JHU/APL) to actively control a pair of ASCs. The first phase of testing included a Dual Advanced Stirling Convertor Simulator (DASCS), which was developed by JHU/APL and simulates the operation and electrical behavior of a pair of ASCs in real time via a combination of hardware and software. RSIL provides insight into the electrical interactions between a representative radioisotope power generator, its associated control schemes, and realistic electric system loads. The first phase of integration testing included the following spacecraft bus configurations: capacitive, battery, and super-capacitor. A load profile, created based on data from several missions, tested the RPS's and RSIL's ability to maintain operation during load demands above and below the power provided by the RPS. The integration testing also confirmed the DCC's ability to disconnect from the spacecraft when the bus voltage dipped below 22 volts or exceeded 36 volts. Once operation was verified with the DASCS, the tests were repeated with actual operating ASCs. The goal of this integration testing was to verify operation of the DCC when connected to a spacecraft and to verify the functionality of the newly designed RSIL. The results of these tests are presented in this paper.

Response to waste electrical and electronic equipments in China: legislation, recycling system, and advanced integrated process.

Science.gov (United States)

Zhou, Lei; Xu, Zhenming

2012-05-01

Over the past 30 years, China has been suffering from negative environmental impacts from distempered waste electrical and electronic equipments (WEEE) recycling activities. For the purpose of environmental protection and resource reusing, China made a great effort to improve WEEE recycling. This article reviews progresses of three major fields in the development of China's WEEE recycling industry: legal system, formal recycling system, and advanced integrated process. Related laws concerning electronic waste (e-waste) management and renewable resource recycling are analyzed from aspects of improvements and loopholes. The outcomes and challenges for existing formal recycling systems are also discussed. The advantage and deficiency related to advanced integrated recycling processes for typical e-wastes are evaluated respectively. Finally, in order to achieve high disposal rates of WEEE, high-quantify separation of different materials in WEEE and high added value final products produced by separated materials from WEEE, an idea of integrated WEEE recycling system is proposed to point future development of WEEE recycling industry. © 2012 American Chemical Society

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

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.

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.

Application of wireless LAN technology to remote monitoring for inspection equipment

International Nuclear Information System (INIS)

Ishiyama, Koichi; Kimura, Takashi; Miura, Yasushi; Yamaguchi, Katsuhiro; Kabuki, Toshihide

2011-01-01

To support inspections under an Integrated Safeguards regime into Tokai Reprocessing Plant (TRP), the IAEA suggested making use of Remote Monitoring (RM) capabilities to the inspection equipment (surveillance camera and NDA systems) installed in the spent fuel storage area at TRP. Since TRP had no pre-prepared cabling infrastructure for data transmission in the spent fuel storage area, the option of wireless LAN was chosen over the telephone line due to its lower installation costs. Feasibility studies and tests were performed by TRP on communication and particularly on long-term continuous communication using wireless LAN equipment composed of APs (AP: Access Point) and the external antennas for introducing wireless LAN technology to RM. As a result it was recognized that wireless LAN has enough ability to communicate for long periods of time and consequently the IAEA installed the AP and the external antenna to each inspection equipment and the wireless LAN technology was applied for RM. In this paper, the summary of each test and the results are reported. (author)

Equipment line-up developed for structuring programmed digital systems important to safety

International Nuclear Information System (INIS)

Remus, L.; Colling, J.M.; Buisson, J.

1986-01-01

The use of the programmed digital techniques in systems important to safety led to developing equipment line-ups which allow to procedure, through using a restricted number of sub-assemblies, a variety of facilities capable of performing diversified functions. Upon remembering the requirements that such equipment are required to meet (quality assurance both at the design and production stages, qualification, testing opportunities, etc.) the equipments produced by MERLIN GERIN are described in this paper. Such equipments include a whole set of printed circuit boards, plug-in units with self-engaging connectors and the related cabinets to accomodate them. The following systems are made up of such equipments: Digital integrated protection system; Rod control and monitoring system; Reactor power distribution monitoring equipment. This equipment line-up has been gradually complemented and is still further expanding both as a result of the component further development or for the purpose of meeting new requirements or applications (new digital neutron instrumentation, local area networks). Experience gained thus far provides us with the capability of working out in a short time programmed systems for further applications in the nuclear power field

Characterization of a clay-rich rock through development and installation of specific hydrogeological and diffusion test equipment in deep boreholes

Science.gov (United States)

Delay, Jacques; Distinguin, Marc; Dewonck, Sarah

Andra (Agence Nationale pour la Gestion des Déchets Radioactifs - National Radioactive Waste Management Agency) has developed specific tools and methodologies to evaluate and understand the main transport mechanisms of solute species in an argillaceous rock in the framework of the scientific program of the Meuse/Haute-Marne Underground Research Laboratory. This paper focuses on three specific equipments already installed in boreholes for the determination of convection and diffusion parameters in a very low permeability environment. The first one is a specific borehole completion for head and permeability measurements with an integrated wireless telemetry device. In 1995, Andra devised a probe equipped with a pressure sensor to monitor the long-term evolution of electro-magnetically transmitted pore pressures. The data gathered by this first device, and a second one installed in 2001, have shown the occurrence of overpressures in very low permeability formations. The second device is derived from the multipacker system used for monitoring the drainage of the Oxfordian limestone due to the sinking of the shaft above the Callovo-Oxfordian. It is used for obtaining from a single borehole, a pressure profile of the argillaceous formation and its encasing units. To date, the major information obtained with these two borehole equipments is the existence of a 25-35 m anomalous excess hydraulic head in the 130 m thick Callovo-Oxfordian argillaceous formation. Head values in the argillaceous rock exceed those in the overlying Oxfordian limestone by 25-35 m, and those in the underlying Dogger by over 45 m. The third equipment described in the paper, is derived from the experiment carried out at the Mont Terri rock laboratory since 1996 for the characterization of diffusion and retention processes. The system is adapted for a borehole drilled from the surface. The objectives of this experiment are as follows: Verification of the predominant role played by molecular diffusion

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

Overview of containment integrity test at NUPEC

International Nuclear Information System (INIS)

Takumi, K.; Yamada, T.

2004-01-01

NUPEC has started NUPEC Containment Integrity project entitled 'Proving Test on the Reliability for Reactor Containment Vessel' since June 1987. This is the project for the term of twelve years sponsored by MITI (Ministry of International Trade and Industry, Japanese Government). The test items are (1) Hydrogen mixing and distribution test, (2) Hydrogen Burning Test, (3) Iodine trapping characteristics test, and (4) Structural behavior test. Based on the test results, computer codes are verified and as the results of analysis and evaluation by the computer codes, containment integrity is to be confirmed. This paper indicates the results of hydrogen mixing and distribution test and hydrogen burning test. The NUPEC tests conducted so far suggest that hydrogen will be well mixed in the model containment vessel and the prediction by the computer code is in excellent agreement with the data. The NUPEC hydrogen burning test data is in good agreement with the FITS data at SNL that were obtained at the lower hydrogen concentration condition. (author)

Humidity Testing for Human Rated Spacecraft

Science.gov (United States)

Johnson, Gary B.

2009-01-01

Determination that equipment can operate in and survive exposure to the humidity environments unique to human rated spacecraft presents widely varying challenges. Equipment may need to operate in habitable volumes where the atmosphere contains perspiration, exhalation, and residual moisture. Equipment located outside the pressurized volumes may be exposed to repetitive diurnal cycles that may result in moisture absorption and/or condensation. Equipment may be thermally affected by conduction to coldplate or structure, by forced or ambient air convection (hot/cold or wet/dry), or by radiation to space through windows or hatches. The equipment s on/off state also contributes to the equipment s susceptibility to humidity. Like-equipment is sometimes used in more than one location and under varying operational modes. Due to these challenges, developing a test scenario that bounds all physical, environmental and operational modes for both pressurized and unpressurized volumes requires an integrated assessment to determine the "worst-case combined conditions." Such an assessment was performed for the Constellation program, considering all of the aforementioned variables; and a test profile was developed based on approximately 300 variable combinations. The test profile has been vetted by several subject matter experts and partially validated by testing. Final testing to determine the efficacy of the test profile on actual space hardware is in the planning stages. When validation is completed, the test profile will be formally incorporated into NASA document CxP 30036, "Constellation Environmental Qualification and Acceptance Testing Requirements (CEQATR)."

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)

Radiological equipment analyzed by specific developed phantoms and software

International Nuclear Information System (INIS)

Soto, M.; Campayo, J. M.; Mayo, P.; Verdu, G.; Rodenas, F.

2010-10-01

The use of radiographic phantoms specifically designed to evaluate the operation of the radiographic equipment lets the study of the image quality obtained by this equipment in an objective way. In digital radiographic equipment, the analysis of the image quality can be computerized because the acquisition of the image is possible in different technologies that are, computerized radiography or phosphor plate and direct radiography or detector. In case of film-screen equipment s this analysis could be applied digitalising the image in a professional scanner. In this work we have shown an application to assess automatically the constancy quality image in the image chain of the radiographic equipment s. This application is integrated by designed radiographic phantoms which are adapted to conventional, dental equipment s and specific developed software for the automatic evaluation of the phantom image quality. The software is based on digital image processing techniques that let the automatic detection of the different phantom tests by edge detector, morphological operators, threshold histogram techniques... etc. The utility developed is enough sensitive to the radiographic equipment of operating conditions of voltage (kV) and charge (m As). It is a friendly user programme connected with a data base of the hospital or clinic where it has been used. After the phantom image processing the user can obtain an inform with a resume of the imaging system state with accepting and constancy results. (Author)

Radiological equipment analyzed by specific developed phantoms and software

Energy Technology Data Exchange (ETDEWEB)

Soto, M.; Campayo, J. M. [Logistica y Acondicionamientos Industriales SAU, Sorolla Center, Local 10, Av. de las Cortes Valencianas No. 58, 46015 Valencia (Spain); Mayo, P. [TITANIA Servicios Tecnologicos SL, Sorolla Center, Local 10, Av. de las Cortes Valencianas No. 58, 46015 Valencia (Spain); Verdu, G.; Rodenas, F., E-mail: m.soto@lainsa.co [ISIRYIM Universidad Politecnica de Valencia, Camino de Vera s/n, Valencia (Spain)

2010-10-15

The use of radiographic phantoms specifically designed to evaluate the operation of the radiographic equipment lets the study of the image quality obtained by this equipment in an objective way. In digital radiographic equipment, the analysis of the image quality can be computerized because the acquisition of the image is possible in different technologies that are, computerized radiography or phosphor plate and direct radiography or detector. In case of film-screen equipment s this analysis could be applied digitalising the image in a professional scanner. In this work we have shown an application to assess automatically the constancy quality image in the image chain of the radiographic equipment s. This application is integrated by designed radiographic phantoms which are adapted to conventional, dental equipment s and specific developed software for the automatic evaluation of the phantom image quality. The software is based on digital image processing techniques that let the automatic detection of the different phantom tests by edge detector, morphological operators, threshold histogram techniques... etc. The utility developed is enough sensitive to the radiographic equipment of operating conditions of voltage (kV) and charge (m As). It is a friendly user programme connected with a data base of the hospital or clinic where it has been used. After the phantom image processing the user can obtain an inform with a resume of the imaging system state with accepting and constancy results. (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 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)

Standard Test Methods for Wet Insulation Integrity Testing of Photovoltaic Modules

CERN Document Server

American Society for Testing and Materials. Philadelphia

2007-01-01

1.1 These test methods provide procedures to determine the insulation resistance of a photovoltaic (PV) module, i.e. the electrical resistance between the module's internal electrical components and its exposed, electrically conductive, non-current carrying parts and surfaces. 1.2 The insulation integrity procedures are a combination of wet insulation resistance and wet dielectric voltage withstand test procedures. 1.3 These procedures are similar to and reference the insulation integrity test procedures described in Test Methods E 1462, with the difference being that the photovoltaic module under test is immersed in a wetting solution during the procedures. 1.4 These test methods do not establish pass or fail levels. The determination of acceptable or unacceptable results is beyond the scope of these test methods. 1.5 The values stated in SI units are to be regarded as the standard. 1.6 There is no similar or equivalent ISO standard. 1.7 This standard does not purport to address all of the safety conce...

The Architecture Design of Detection and Calibration System for High-voltage Electrical Equipment

Science.gov (United States)

Ma, Y.; Lin, Y.; Yang, Y.; Gu, Ch; Yang, F.; Zou, L. D.

2018-01-01

With the construction of Material Quality Inspection Center of Shandong electric power company, Electric Power Research Institute takes on more jobs on quality analysis and laboratory calibration for high-voltage electrical equipment, and informationization construction becomes urgent. In the paper we design a consolidated system, which implements the electronic management and online automation process for material sampling, test apparatus detection and field test. In the three jobs we use QR code scanning, online Word editing and electronic signature. These techniques simplify the complex process of warehouse management and testing report transferring, and largely reduce the manual procedure. The construction of the standardized detection information platform realizes the integrated management of high-voltage electrical equipment from their networking, running to periodic detection. According to system operation evaluation, the speed of transferring report is doubled, and querying data is also easier and faster.

Start up testing for the secure automated fabrication line

International Nuclear Information System (INIS)

Gerber, E.W.; Benson, E.M.; Dahl, R.E.

1987-01-01

The secure automated fabrication (SAF) line is a remotely operated, liquid metal reactor fuel fabrication process being built by Westinghouse Hanford Company for the Department of Energy. All process and control equipment is installed and start up testing has been initiated. Start up testing is comprised of five phases, each incorporating higher degrees of equipment integration, automation, and remote control. Testing methodology for SAF line start up is described in this report

History and development of the tennis equipment

OpenAIRE

Horáková, Kateřina

2007-01-01

Title: History and development of the tennis equipment. Aim of the work: Process an integral, tabular and synoptic historical development overview of the tennis equipment. This owerview will cover the period since the early beginnings of the game to present days. Methods: Advance work has historical charakter therefore used methods are historiogaphical methods such as chronological method and historical method. Results: Produce tabular description of the tennis equipment by means of reading a...

Thermal Hydraulic Integral Effect Tests for Pressurized Water Reactors

Energy Technology Data Exchange (ETDEWEB)

Baek, W. P.; Song, C. H.; Kim, Y. S. and others

2005-02-15

The objectives of the project are to construct a thermal-hydraulic integral effect test facility and to perform various integral effect tests for design, operation, and safety regulation of pressurized water reactors. During the first phase of this project (1997.8{approx}2002.3), the basic technology for thermal-hydraulic integral effect tests was established and the basic design of the test facility was accomplished: a full-height, 1/300-volume-scaled full pressure facility for APR1400, an evolutionary pressurized water reactor that was developed by Korean industry. Main objectives of the present phase (2002.4{approx}2005.2), was to optimize the facility design and to construct the experimental facility. We have performed following researches: 1) Optimization of the basic design of the thermal-hydraulic integral effect test facility for PWRs - ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation) - Reduced height design for APR1400 (+ specific design features of KSNP safety injection systems) - Thermal-hydraulic scaling based on three-level scaling methodology by Ishii et al. 2) Construction of the ATLAS facility - Detailed design of the test facility - Manufacturing and procurement of components - Installation of the facility 3) Development of supporting technology for integral effect tests - Development and application of advanced instrumentation technology - Preliminary analysis of test scenarios - Development of experimental procedures - Establishment and implementation of QA system/procedure.

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

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.

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.

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

Test Structures For Bumpy Integrated Circuits

Science.gov (United States)

Buehler, Martin G.; Sayah, Hoshyar R.

1989-01-01

Cross-bridge resistors added to comb and serpentine patterns. Improved combination of test structures built into integrated circuit used to evaluate design rules, fabrication processes, and quality of interconnections. Consist of meshing serpentines and combs, and cross bridge. Structures used to make electrical measurements revealing defects in design or fabrication. Combination of test structures includes three comb arrays, two serpentine arrays, and cross bridge. Made of aluminum or polycrystalline silicon, depending on material in integrated-circuit layers evaluated. Aluminum combs and serpentine arrays deposited over steps made by polycrystalline silicon and diffusion layers, while polycrystalline silicon versions of these structures used to cross over steps made by thick oxide layer.

Development of an EVA systems cost model. Volume 2: Shuttle orbiter crew and equipment translation concepts and EVA workstation concept development and integration

Science.gov (United States)

1975-01-01

EVA crewman/equipment translational concepts are developed for a shuttle orbiter payload application. Also considered are EVA workstation systems to meet orbiter and payload requirements for integration of workstations into candidate orbiter payload worksites.

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

Structural integrity evaluation of FTL in-pool piping

Energy Technology Data Exchange (ETDEWEB)

Kim, J. Y

1998-05-01

HANARO fuel test loop will be equipped in HANARO to obtain the development betterment of advanced fuel and materials through the irradiation test. The object of this study is to evaluate the structural integrity of FTL in-pool piping by investigating a dynamic analysis of the loop containing a postulated rupture section. The method to perform the dynamic analysis and structural integrity evaluation caused by the pipe whip in water environment can be a reference for a similar structural integrity evaluation. (author). 7 refs., 39 tabs., 34 figs.

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...

Specific developed phantoms and software to assess radiological equipment image quality

International Nuclear Information System (INIS)

Verdu, G.; Rodenas, F.

2011-01-01

The use of radiographic phantoms specifically designed to evaluate the operation of the radiographic equipment lets the study of the image quality obtained by this equipment in an objective way. In digital radiographic equipment, the analysis of the image quality can be automatized because the acquisition of the image is possible in different technologies that are, computerized radiography or phosphor plate and direct radiography or detector. In this work we have shown an application to assess automatically the constancy quality image in the image chain of the radiographic equipment. This application is integrated by designed radiographic phantoms which are adapted to conventional, dental equipment and specific developed software for the automatic evaluation of the phantom image quality. The software is based on digital image processing techniques that let the automatic detection of the different phantom tests by edge detector, morphological operators, threshold histogram techniques, etc. The utility developed is enough sensitive to the radiographic equipment of operating conditions of voltage (kV) and charge (mAs). It is a friendly user programme connected with a data base of the hospital or clinic where it has been used. After the phantom image processing the user can obtain an inform with a resume of the imaging system state with accepting and constancy results. (author)

Specific developed phantoms and software to assess radiological equipment image quality

Energy Technology Data Exchange (ETDEWEB)

Verdu, G., E-mail: gverdu@iqn.upv.es [Universidad Politecnica de Valencia (Spain). Dept. de Ingenieria Quimica y Nuclear; Mayo, P., E-mail: p.mayo@titaniast.com [TITANIA Servicios Teconologicos, Valencia (Spain); Rodenas, F., E-mail: frodenas@mat.upv.es [Universidad Politecnica de Valencia (Spain). Dept. de Matematica Aplicada; Campayo, J.M., E-mail: j.campayo@lainsa.com [Logistica y Acondicionamientos Industriales S.A.U (LAINSA), Valencia (Spain)

2011-07-01

The use of radiographic phantoms specifically designed to evaluate the operation of the radiographic equipment lets the study of the image quality obtained by this equipment in an objective way. In digital radiographic equipment, the analysis of the image quality can be automatized because the acquisition of the image is possible in different technologies that are, computerized radiography or phosphor plate and direct radiography or detector. In this work we have shown an application to assess automatically the constancy quality image in the image chain of the radiographic equipment. This application is integrated by designed radiographic phantoms which are adapted to conventional, dental equipment and specific developed software for the automatic evaluation of the phantom image quality. The software is based on digital image processing techniques that let the automatic detection of the different phantom tests by edge detector, morphological operators, threshold histogram techniques, etc. The utility developed is enough sensitive to the radiographic equipment of operating conditions of voltage (kV) and charge (mAs). It is a friendly user programme connected with a data base of the hospital or clinic where it has been used. After the phantom image processing the user can obtain an inform with a resume of the imaging system state with accepting and constancy results. (author)

UAS-NAS Integrated Human in the Loop: Test Environment Report

Science.gov (United States)

Murphy, Jim; Otto, Neil; Jovic, Srba

2015-01-01

The desire and ability to fly Unmanned Aircraft Systems (UAS) in the National Airspace System (NAS) is of increasing urgency. The application of unmanned aircraft to perform national security, defense, scientific, and emergency management are driving the critical need for less restrictive access by UAS to the NAS. UAS represent a new capability that will provide a variety of services in the government (public) and commercial (civil) aviation sectors. The growth of this potential industry has not yet been realized due to the lack of a common understanding of what is required to safely operate UAS in the NAS. NASA's UAS Integration in the NAS Project is conducting research in the areas of Separation Assurance/Sense and Avoid Interoperability (SSI), Human Systems Integration (HSI), and Communication to support reducing the barriers of UAS access to the NAS. This research was broken into two research themes namely, UAS Integration and Test Infrastructure. UAS Integration focuses on airspace integration procedures and performance standards to enable UAS integration in the air transportation system, covering Sense and Avoid (SAA) performance standards, command and control performance standards, and human systems integration. The focus of the Test Infrastructure theme was to enable development and validation of airspace integration procedures and performance standards, including the execution of integrated test and evaluation. In support of the integrated test and evaluation efforts, the Project developed an adaptable, scalable, and schedulable relevant test environment incorporating live, virtual, and constructive elements capable of validating concepts and technologies for unmanned aircraft systems to safely operate in the NAS. To accomplish this task, the Project planned to conduct three integrated events: a Human-in-the-Loop simulation and two Flight Test series that integrated key concepts, technologies and/or procedures in a relevant air traffic environment. Each of

Methodology development for availability improvement of standby equipment

International Nuclear Information System (INIS)

Shin, Sung Min; Jeon, In Seop; Kang, Hyun Gook

2014-01-01

The core damage frequency (CDF) of operating and constructing pressurized nuclear plants are ranging on the order of 10 -5 and 10 -6 per year. The target CDF of new NPP design has been set at 10 -7 . In this context, although various systems are currently studied, availability improvement of standby equipment will be more efficient than the additional application of safety systems. It is obvious in every aspect, such as management and cost efficiency. Here, soundness can affect equipment unavailability, and the soundness degrades because of aging. However, some studies did not consider aging when calculating the unavailability. Standby equipment can age because of two important factors: standby stress which accumulates over time, and test stress which accumulates with the number of tests (or operations). Both factors should be considered together when aging is considered. However, some studies only considered standby stress or test stress. There are some previous studies which considered both factors. Besides equipment soundness related to aging effect, some process like bypass during test also can affect equipment unavailability because the original function of equipment cannot be performed immediately during this process. However, there are seldom studies dealing with above factors as a whole problem. This study investigated a general approach to calculate the unavailability of standby equipment which considers aging caused by standby and test stresses and bypass process. Based on this general approach, we propose two maintenance strategies which aim to reduce standby equipment unavailability. In section 2, the general approach is presented. As one of the strategies, the changing test interval method (CIM) is introduced in section 3, and its effectiveness is also analyzed. The online monitoring method (OMM) is investigated in section 4 as another method to reduce equipment unavailability. In section 5, a combination of these two methods is analyzed. A general

EQUIPMENT FOR NONDESTRUCTIVE TESTING OF SILICON WAFERS SUBMICRON TOPOLOGY DURING THE FABRICATION OF INTEGRATED CIRCUITS

Directory of Open Access Journals (Sweden)

S. A. Chizhik

2013-01-01

Full Text Available The advantages of using an atomic force microscopy in manufacturing of submicron integrated circuits are described. The possibilities of characterizing the surface morphology and the etching profile for silicon substrate and bus lines, estimation of the periodicity and size of bus lines, geometrical stability for elementary bus line are shown. Methods of optical and atomic force microcopies are combined in one diagnostic unit. Scanning  probe  microscope  (SPM  200  is  designed  and  produced.  Complex  SPM  200  realizes  nondestructive control of microelectronics elements made on silicon wafers up to 200 mm in diameter and it is introduced by JSC «Integral» for the purpose of operational control, metrology and acceptance of the final product.

Optimal integration and test plans for software releases of lithographic systems

NARCIS (Netherlands)

Boumen, R.; Jong, de I.S.M.; Mortel - Fronczak, van de J.M.; Rooda, J.E.

2007-01-01

This paper describes a method to determine the optimal integration and test plan for embedded systems software releases. The method consists of four steps: 1)describe the integration and test problem in an integration and test model which is introduced in this paper, 2) determine possible test

An overview of equipment survivability studies at Sandia National Laboratories (SNL)

International Nuclear Information System (INIS)

Bonzon, L.L.; Craft, Ch.M.; McCulloch, W.H.; Sebrell, W.A.

1983-01-01

The USNRC sponsors a number of programs at Sandia National Laboratories (SNL) specifically addressing safety-related equipment survivability. The major thrust of these programs has been the physical testing of equipment. Test results illustrate the importance of a dedicated equipment design effort giving particular attention to the safety implications of the equipment operation. Several equipment survivability tests here have revealed equipment design and test-related deficiencies

Field vibration test of principal equipment of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Shiraki, Kazuhiro; Fujita, Katsuhisa; Kajimura, Motohiko; Ikegami, Yasuhiko; Hanzawa, Katsumi; Sakai, Yoshiyuki; Kokubo, Eiji; Igarashi, Shigeru

1984-09-01

Japan is one of the most earthquake-stricken countries in the world, and demands for aseismic design have become severer recently. In a nuclear power plant in particular, consisting of a reactor vessel and other facilities dealing with a radioactive substance in some form or other, it is essential from the standpoint of safety to eliminate any possibility of radioactive hazards for the local public, and the employees at the plant as well, if these facilities are struck by an earthquake. This paper is related to the reactor vessel, reactor primary cooling equipment and piping system and important general piping as examples of important facilities of a nuclear power plant, and discusses vibration tests of an actual plant in the field from the standpoint of enhancing the aseismic safety of the Mitsubishi PWR nuclear power plant. Especially concerning vibration test technology, the effects in the evaluation of aseismic safety and its limits are studied to prove how it contributes to the enhancement of the reliability of aseismic design of nuclear power plants.

The Ural Electrochemical Integrated Plant Process for Managing Equipment Intended for Nuclear Material Protection, Control and Accounting System Upgrades

International Nuclear Information System (INIS)

Yuldashev, Rashid; Nosov, Andrei; Carroll, Michael F.; Garrett, Albert G.; Dabbs, Richard D.; Ku, Esther M.

2008-01-01

Since 1996, the Ural Electrochemical Integrated Plant (UEIP) located in the town of Novouralsk, Russia, (previously known as Sverdlovsk-44) and the United States Department of Energy (U.S. DOE) have been cooperating under the Nuclear Material Protection, Control and Accounting (MPC and A) Program. Because UEIP is involved in the processing of highly enriched uranium (HEU) into low enriched uranium (LEU), and there are highly enriched nuclear materials on its territory, the main goal of the MPC and A cooperation is to upgrade those systems that ensure secure storage, processing and transportation of nuclear materials at the plant. UEIP has completed key upgrades (equipment procurement and installation) aimed at improving MPC and A systems through significant investments made by both the U.S. DOE and UEIP. These joint cooperative efforts resulted in bringing MPC and A systems into compliance with current regulations, which led to nuclear material (NM) theft risk reduction and prevention from other unlawful actions with respect to them. Upon the U.S. MPC and A project team's suggestion, UEIP has developed an equipment inventory control process to track all the property provided through the MPC and A Program. The UEIP process and system for managing equipment provides many benefits including: greater ease and efficiency in determining the quantities, location, maintenance and repair schedule for equipment; greater assurance that MPC and A equipment is in continued satisfactory operation; and improved control in the development of a site sustainability program. While emphasizing UEIP's equipment inventory control processes, this paper will present process requirements and a methodology that may have practical and helpful applications at other sites.

Full scaled tests of the KERENA trademark containment cooling condenser at the INKA test facility

International Nuclear Information System (INIS)

Leyer, Stephan; Maisberger, Fabian; Lineva, Natalia; Wagner, Thomas; Doll, Mathias; Herbst, Vasilli; Wich, Michael

2010-01-01

KERENA trademark is a medium-capacity boiling water reactor. It combines passive safety systems with active safety equipment of service-proven design. The passive systems utilize basic laws of physics, such as gravity and natural convection, enabling them to function without any power supply or actuation by instrumentation and control (I and C) equipment. They are designed to bring the plant to a safe and stable condition without the aid of active systems. Furthermore, the passive safety features partially replace the active systems, which reduces costs significantly and provides a safe, reliable and economically competitive plant design. At the new test facility at Karlstein called INKA (Integral Test Stand Karlstein), the key components of the KERENA trademark passive safety concept - the Emergency Condenser (EC), the Containment Cooling Condenser (CCC) and the passive core flooding system (PCFS) - are presently under full-scale testing,. Integral system tests will also be performed to show how the passive safety systems interact under various anticipated accident conditions and to demonstrate the ability of the passive systems to bring the plant to a safe and stable condition without the aid of active systems or actuation by I and C signals. The passive pressure pulse transmitter (PPPT) will be included in these integral tests. In this report the experimental setup and the first test results with the full scaled Containment Cooling Condenser will be described. (orig.)

Measuring and test equipment control through bar-code technology

International Nuclear Information System (INIS)

Crockett, J.D.; Carr, C.C.

1993-01-01

Over the past several years, the use, tracking, and documentation of measuring and test equipment (M ampersand TE) has become a major issue. New regulations are forcing companies to develop new policies for providing use history, traceability, and accountability of M ampersand TE. This paper discusses how the Fast Flux Test Facility (FFTF), operated by Westinghouse Hanford Company and located at the Hanford site in Rich- land, Washington, overcame these obstacles by using a computerized system exercising bar-code technology. A data base was developed to identify M ampersand TE containing 33 separate fields, such as manufacturer, model, range, bar-code number, and other pertinent information. A bar-code label was attached to each piece of M ampersand TE. A second data base was created to identify the employee using the M ampersand TE. The fields contained pertinent user information such as name, location, and payroll number. Each employee's payroll number was bar coded and attached to the back of their identification badge. A computer program was developed to automate certain tasks previously performed and tracked by hand. Bar-code technology was combined with this computer program to control the input and distribution of information, eliminate common mistakes, electronically store information, and reduce the time required to check out the M ampersand TE for use

Electronic equipment for spectrometric data processing

International Nuclear Information System (INIS)

Antonov, L.J.; Trenev, A.M.; Todorova, E.I.; Dimitrov, V.D.

1978-01-01

Electronic equipment carrying out logical operations and a full set of the arithmetic operations was developed for spectrometric data processing. The flowsheet of the computing part of the device, made on the basis of a specialized integral circuit, is given. The device includes input registers, multiplexor, matrix commutator, arithmetic unit and indication unit. The equipment is rated to carry out calculations according to comparatively complex formulae in several seconds

Design of a compact low-power human-computer interaction equipment for hand motion

Science.gov (United States)

Wu, Xianwei; Jin, Wenguang

2017-01-01

Human-Computer Interaction (HCI) raises demand of convenience, endurance, responsiveness and naturalness. This paper describes a design of a compact wearable low-power HCI equipment applied to gesture recognition. System combines multi-mode sense signals: the vision sense signal and the motion sense signal, and the equipment is equipped with the depth camera and the motion sensor. The dimension (40 mm × 30 mm) and structure is compact and portable after tight integration. System is built on a module layered framework, which contributes to real-time collection (60 fps), process and transmission via synchronous confusion with asynchronous concurrent collection and wireless Blue 4.0 transmission. To minimize equipment's energy consumption, system makes use of low-power components, managing peripheral state dynamically, switching into idle mode intelligently, pulse-width modulation (PWM) of the NIR LEDs of the depth camera and algorithm optimization by the motion sensor. To test this equipment's function and performance, a gesture recognition algorithm is applied to system. As the result presents, general energy consumption could be as low as 0.5 W.

Eddy-Current Testing of Welded Stainless Steel Storage Containers to Verify Integrity and Identity

International Nuclear Information System (INIS)

Tolk, Keith M.; Stoker, Gerald C.

1999-01-01

An eddy-current scanning system is being developed to allow the International Atomic Energy Agency (IAEA) to verify the integrity of nuclear material storage containers. Such a system is necessary to detect attempts to remove material from the containers in facilities where continuous surveillance of the containers is not practical. Initial tests have shown that the eddy-current system is also capable of verifying the identity of each container using the electromagnetic signature of its welds. The DOE-3013 containers proposed for use in some US facilities are made of an austenitic stainless steel alloy, which is nonmagnetic in its normal condition. When the material is cold worked by forming or by local stresses experienced in welding, it loses its austenitic grain structure and its magnetic permeability increases. This change in magnetic permeability can be measured using an eddy-current probe specifically designed for this purpose. Initial tests have shown that variations of magnetic permeability and material conductivity in and around welds can be detected, and form a pattern unique to the container. The changes in conductivity that are present around a mechanically inserted plug can also be detected. Further development of the system is currently underway to adapt the system to verifying the integrity and identity of sealable, tamper-indicating enclosures designed to prevent unauthorized access to measurement equipment used to verify international agreements

West Valley Demonstration Project vitrification process equipment Functional and Checkout Testing of Systems (FACTS)

International Nuclear Information System (INIS)

Carl, D.E.; Paul, J.; Foran, J.M.; Brooks, R.

1990-01-01

The Vitrification Facility (VF) at the West Valley Demonstration Project was designed to convert stored radioactive waste into a stable glass for disposal in a federal repository. The Functional and Checkout Testing of Systems (FACTS) program was conducted from 1984 to 1989. During this time new equipment and processes were developed, installed, and implemented. Thirty-seven FACTS tests were conducted, and approximately 150,000 kg of glass were made by using nonradioactive materials to simulate the radioactive waste. By contrast, the planned radioactive operation is expected to produce approximately 500,000 kg of glass. The FACTS program demonstrated the effectiveness of equipment and procedures in the vitrification system, and the ability of the VF to produce quality glass on schedule. FACTS testing also provided data to validate the WVNS waste glass qualification method and verify that the product glass would meet federal repository acceptance requirements. The system was built and performed to standards which would have enabled it to be used in radioactive service. As a result, much of the VF tested, such as the civil construction, feed mixing and holding vessels, and the off-gas scrubber, will be converted for radioactive operation. The melter was still in good condition after being at temperature for fifty-eight of the sixty months of FACTS. However, the melter exceeded its recommended design life and will be replaced with a similar melter. Components that were not designed for remote operation and maintenance will be replaced with remote-use items. The FACTS testing was accomplished with no significant worker injury or environmental releases. During the last FACTS run, the VF processes approximated the remote-handling system that will be used in radioactive operations. Following this run the VF was disassembled for conversion to a radioactive process. Functional and checkout testing of new components will be performed prior to radioactive operation

Open manufacturing system using MMS service and object oriented manufacturing equipment

International Nuclear Information System (INIS)

Kim, Dong Hoon; Song, Jun Yeob; Kim, Sun Ho

2007-01-01

Manufacturing equipment should be integrated to construct CIM (Computer Integrated Manufacturing) environment, but several economical and technological difficulties may be arisen in case heterogeneous systems are integrated into each other. MMS (Manufacturing Message Specification) can be effective in such a case, but the problem is that MMS-related products are comparatively expensive and the existing manufacturing equipment mostly do not support MMS. This study was focused on developing a gateway suitable to a non-MMS-compatible CNC machine-tool, and on implementing OSI (Open System Interconnection) upper layer on TCP/IP. The development system was applied to a cell controller by means of heterogeneous equipment under CIM environment, and to evaluate interoperability and portability

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.

Approach to the assessment of the performance of nondestructive test methods in the manufacture of nuclear power station equipment

International Nuclear Information System (INIS)

Michaut, J.P.

1996-01-01

The safety of a nuclear power station lies largely in the possibility of ensuring, at the time of in service inspections on major equipment, that the extent of faults which may appear or develop is not greater than that of faults detrimental to behavior in service. This assurance is based on performance demonstration of the nondestructive test methods used for inspecting the equipment in service. This is the subject of numerous studies in various countries. To ensure that manufacturing faults likely to downgrade the safety of the equipment are not discovered in service, it seems desirable to make sure that the performance of the nondestructive test (NDT) methods which are going to be used in manufacture will be at least as high as those used in service and that they are therefore capable of guaranteeing detection of faults clearly less important than really harmful faults. The performance of NDT methods and their consistency with those which can be used in service is evaluated before the start of manufacture on a mock-up representative of the equipment itself. Information is given on research in progress on the bimetal welding of a pressurizer spray nozzle

46 CFR 133.45 - Tests and inspections of lifesaving equipment and arrangements.

Science.gov (United States)

2010-10-01

... of flotation equipment such as lifebuoys, lifejackets, immersion suits, work vests, lifefloats... mechanisms; (3) The proper condition of flotation equipment such as lifebuoys, lifejackets, immersion suits, work vests, lifefloats, buoyant apparatus, and associated equipment; (4) That each inflatable liferaft...

Airside HVAC BESTEST. Adaptation of ASHRAE RP 865 Airside HVAC Equipment Modeling Test Cases for ASHRAE Standard 140. Volume 1, Cases AE101-AE445

Energy Technology Data Exchange (ETDEWEB)

Neymark, J. [J. Neymark & Associates, Golden, CO (United States); Kennedy, M. [Mike D. Kennedy, Inc., Townsend, WA (United States); Judkoff, R. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Gall, J. [AAON, Inc., Tulsa, OK (United States); Knebel, D. [AAON, Inc., Tulsa, OK (United States); Henninger, R. [GARD Analytics, Inc., Arlington Heights, IL (United States); Witte, M. [GARD Analytics, Inc., Arlington Heights, IL (United States); Hong, T. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); McDowell, T. [Thermal Energy System Specialists, Madison, WI (United States); Yan, D. [Tsinghua Univ., Beijing (China); Zhou, X. [Tsinghua Univ., Beijing (China)

2016-03-01

This report documents a set of diagnostic analytical verification cases for testing the ability of whole building simulation software to model the air distribution side of typical heating, ventilating and air conditioning (HVAC) equipment. These cases complement the unitary equipment cases included in American National Standards Institute (ANSI)/American Society of Heating, Refrigerating, and Air-Conditioning Engineers (ASHRAE) Standard 140, Standard Method of Test for the Evaluation of Building Energy Analysis Computer Programs, which test the ability to model the heat-transfer fluid side of HVAC equipment.

Equipment Reliability Process in Krsko NPP

International Nuclear Information System (INIS)

Gluhak, M.

2016-01-01

To ensure long-term safe and reliable plant operation, equipment operability and availability must also be ensured by setting a group of processes to be established within the nuclear power plant. Equipment reliability process represents the integration and coordination of important equipment reliability activities into one process, which enables equipment performance and condition monitoring, preventive maintenance activities development, implementation and optimization, continuous improvement of the processes and long term planning. The initiative for introducing systematic approach for equipment reliability assuring came from US nuclear industry guided by INPO (Institute of Nuclear Power Operations) and by participation of several US nuclear utilities. As a result of the initiative, first edition of INPO document AP-913, 'Equipment Reliability Process Description' was issued and it became a basic document for implementation of equipment reliability process for the whole nuclear industry. The scope of equipment reliability process in Krsko NPP consists of following programs: equipment criticality classification, preventive maintenance program, corrective action program, system health reports and long-term investment plan. By implementation, supervision and continuous improvement of those programs, guided by more than thirty years of operating experience, Krsko NPP will continue to be on a track of safe and reliable operation until the end of prolonged life time. (author).

Best Practices: Power Quality and Integrated Testing at JSC

Science.gov (United States)

Davis, Lydia

2018-01-01

This presentation discusses Best Practices for Power Quality and Integrated Testing at JSC in regards to electrical systems. These high-level charts include mostly generic information; however, a specific issue is discussed involving flight hardware that could have been discovered prior to flight with an integrated test.

Integration of Diagnostics into Ground Equipment Study. Volume 1

National Research Council Canada - National Science Library

Kumara, Soundar; Gautam, N; Hall, Dave; Purao, Sandeep; Garga, Amulya; Grimes, Barney

2004-01-01

...) for Ground Equipment used by the U.S. Marine Corps. The study reviewed the sources of Autonomic Logistics data, the data requirements, the timeliness or required "pull" of such data, its transmission means...

Nuclear Technology. Course 32: Nondestructive Examination (NDE) Techniques II. Module 32-4, Operation of Magnetic Particle Test Equipment.

Science.gov (United States)

Groseclose, Richard

This fourth in a series of six modules for a course titled Nondestructive Examination (NDE) Techniques II describes the specific technique variables and options which are available to the test technician, provides instructions for selecting and operating the appropriate test equipment, describes physical criteria for detectable discontinuities,…

The study of human bodies' impedance networks in testing leakage currents of electrical equipments

Science.gov (United States)

Zhang, Zhaohui; Wang, Xiaofei

2006-11-01

In the testing of electrical equipments' leakage currents, impedance networks of human bodies are used to simulate the current's effect on human bodies, and they are key to the preciseness of the testing result. This paper analyses and calculates three human bodies' impedance networks of measuring electric burn current, perception or reaction current, let-go current in IEC60990, by using Matlab, compares the research result of current effect thresholds' change with sine wave's frequency published in IEC479-2, and amends parameters of measuring networks. It also analyses the change of perception or reaction current with waveform by Multisim.

Use of commercial grade equipment and industrial standards for equipment qualification

International Nuclear Information System (INIS)

Gradin, L.P.; Muller, E.S.

1984-01-01

One of the most controversial issues is the proper application of Arrhenius aging methodology. Naturally and artificially aged equipment used in type test programs are often costly and burdensome tasks. Appropriate use of non-nuclear industrial standards and comparison to past history can demonstrate, with reasonable assurance, that equipment is qualified with proper consideration of aging. Specific review of the industrial standards available and application examples are provided

W-026, acceptance test report manipulator system

International Nuclear Information System (INIS)

Watson, T.L.

1997-01-01

The purpose of the WRAP Manipulator System Acceptance Test Plan (ATP) is to verify that the 4 glovebox sets of WRAP manipulator components, including rail/carriage, slave arm, master controller and auxiliary equipment, meets the requirements of the functional segments of 14590 specification. The demonstration of performance elements of the ATP are performed as a part of the Assembly specifications. Manipulator integration is integrated in the performance testing of the gloveboxes. Each requirement of the Assembly specification will be carried out in conjunction with glovebox performance tests

Remote maintenance ''lessons learned'' on prototypical reprocessing equipment

International Nuclear Information System (INIS)

Kring, C.T.; Schrock, S.L.

1990-01-01

Hardware representative of essentially every major equipment item necessary for reprocessing breeder reactor nuclear fuel has been installed and tested for remote maintainability. This testing took place in a cold mock-up of a remotely maintained hot cell operated by the Consolidated Fuel Reprocessing Program (CFRP) within the Fuel Recycle Division at Oak Ridge National Laboratory (ORNL). The reprocessing equipment tested included a Disassembly System, a Shear System, a Dissolver System, an Automated Sampler System, removable Equipment Racks on which various chemical process equipment items were mounted, and an advanced servomanipulator (ASM). These equipment items were disassembled and reassembled remotely by using the remote handling systems that are available within the cold mock-up area. This paper summarizes the ''lessons learned'' as a result of the numerous maintenance activities associated with each of these equipment items. 4 refs., 3 figs., 1 tab

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

30 CFR 250.517 - Tubing and wellhead equipment.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Tubing and wellhead equipment. 250.517 Section... Tubing and wellhead equipment. (a) No tubing string shall be placed in service or continue to be used unless such tubing string has the necessary strength and pressure integrity and is otherwise suitable for...

BWR Full Integral Simulation Test (FIST). Phase I test results

International Nuclear Information System (INIS)

Hwang, W.S.; Alamgir, M.; Sutherland, W.A.

1984-09-01

A new full height BWR system simulator has been built under the Full-Integral-Simulation-Test (FIST) program to investigate the system responses to various transients. The test program consists of two test phases. This report provides a summary, discussions, highlights and conclusions of the FIST Phase I tests. Eight matrix tests were conducted in the FIST Phase I. These tests have investigated the large break, small break and steamline break LOCA's, as well as natural circulation and power transients. Results and governing phenomena of each test have been evaluated and discussed in detail in this report. One of the FIST program objectives is to assess the TRAC code by comparisons with test data. Two pretest predictions made with TRACB02 are presented and compared with test data in this report

Silicon integrated circuit process

International Nuclear Information System (INIS)

Lee, Jong Duck

1985-12-01

This book introduces the process of silicon integrated circuit. It is composed of seven parts, which are oxidation process, diffusion process, ion implantation process such as ion implantation equipment, damage, annealing and influence on manufacture of integrated circuit and device, chemical vapor deposition process like silicon Epitaxy LPCVD and PECVD, photolithography process, including a sensitizer, spin, harden bake, reflection of light and problems related process, infrared light bake, wet-etch, dry etch, special etch and problems of etching, metal process like metal process like metal-silicon connection, aluminum process, credibility of aluminum and test process.

Silicon integrated circuit process

Energy Technology Data Exchange (ETDEWEB)

Lee, Jong Duck

1985-12-15

This book introduces the process of silicon integrated circuit. It is composed of seven parts, which are oxidation process, diffusion process, ion implantation process such as ion implantation equipment, damage, annealing and influence on manufacture of integrated circuit and device, chemical vapor deposition process like silicon Epitaxy LPCVD and PECVD, photolithography process, including a sensitizer, spin, harden bake, reflection of light and problems related process, infrared light bake, wet-etch, dry etch, special etch and problems of etching, metal process like metal process like metal-silicon connection, aluminum process, credibility of aluminum and test process.

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

Aviation Systems Test and Integration Lab (AvSTIL)

Data.gov (United States)

Federal Laboratory Consortium — The Aviation Systems Test and Integration Laboratory offers an innovative approach to aviation system and subsystem testing by fully immersing aviation platforms in...

The Predominance Of Integrative Tests Over Discrete Point Tests In Evaluating The Medical Students' General English Knowledge

Directory of Open Access Journals (Sweden)

maryam Heydarpour Meymeh

2009-03-01

Full Text Available Background and purpose: Multiple choice tests are the most common type of tests used in evaluating the general English knowledge of the students in most medical universities, however the efficacy of these tests are not examined precisely. Wecompare and examine the integrative tests and discrete point tests as measures of the English language knowledge of medical students.Methods: Three tests were given to 60 undergraduate physiotherapy and Audiology students in their second year of study (after passing their general English course. They were divided into 2 groups.The first test for both groups was an integrative test, writing. The second test was a multiple - choice test 0.(prepositions for group one and a multiple - choice test of tensesfor group two. The same items which were mostfi-equently used wrongly in thefirst test were used in the items of the second test. A third test, a TOEFL, was given to the subjects in order to estimate the correlation between this test and tests one and two.Results: The students performed better in the second test, discrete point test rather than the first which was an integrative test. The same grammatical mistakes in the composition were used correctly in the multiple choice tests by the students.Conclusion:Our findings show that student perform better in non-productive rather than productive test. Since being competent English language user is an expected outcome of university language courses it seems warranted to switch to integrative tests as a measure of English language competency.Keywords: INTEGRATIVE TESTS, ENGLISH LANGUAGE FOR MEDICINE, ACADEMIC ENGLISH

Discrete-continuous analysis of optimal equipment replacement

OpenAIRE

YATSENKO, Yuri; HRITONENKO, Natali

2008-01-01

In Operations Research, the equipment replacement process is usually modeled in discrete time. The optimal replacement strategies are found from discrete (or integer) programming problems, well known for their analytic and computational complexity. An alternative approach is represented by continuous-time vintage capital models that explicitly involve the equipment lifetime and are described by nonlinear integral equations. Then the optimal replacement is determined via the opt...

Equipment reliability improvement process; implementation in Almaraz NPP and Trillo NPP

International Nuclear Information System (INIS)

Risquez Bailon, Aranzazu; Gutierrez Fernandez, Eduardo

2010-01-01

The Equipment Reliability Improvement Process (INPO AP-913) is a non-regulatory process developed by the US Nuclear Industry for improving Plants Availability. This Process integrates and coordinates a broad range of equipment reliability activities into one process, performed by the Plant in a non-centralized way. The integration and coordination of these activities will allow plant personnel to evaluate the trends of important station equipment, develop and implement long-term equipment health plans, monitor equipment performance and condition, and make adjustments to preventive maintenance tasks and frequencies based on equipment operating experience, if necessary, arbitrating operational and design improvements, to reach a Failure-free Operation. This paper describes the methodology of Equipment Reliability Improvement Process, being focused on main aspects of the implementation process, relating to the scope and establishment of an Equipment Reliability Monitoring Plan, which should include and complement the existing mechanisms and organizations in the Plant to monitor the condition and performance of the equipments, with the common aim of achieving an operation free of failures. The paper will describe the tools that Iberdrola Ingenieria has developed to support the implementation and monitoring of the Equipment Reliability Improvement Process, as well as the results and lessons learned from its implementation in Almaraz NPP and Trillo NPP. (authors)

Vibrodynamical tests of RP equipment with application of imitation area of WWER-1000 reactor

International Nuclear Information System (INIS)

Khajretdinov, V.U.; Tarkhanov, V.V.; Rodionova, I.N.

2015-01-01

Performance of preoperational tests and measurements with application of imitation area of the reactor is a distinctive characteristic of putting into operation of NPP Units with WWER-1000/1200. The imitation area consists of 163 full-scale FA models, where fuel matrixes made of nuclear-fissionable material, are replaced by leaden simulators. Vibrodynamic tests involve inspection of hydrodynamic disturbances in the primary circuit (dynamic impact on the inspected elements), characteristics of vibration response of the main equipment stress-deformed state of bearing structure, and also parameters of moving and geometry of the inspected objects (boundary conditions at process simulation). Preoperational tests and measurements on the simulated area of WWER-1000/1200 are obligatory and performed at every unit of NPP of this type [ru

Test requirements for the integral effect test to simulate Korean PWR plants

Energy Technology Data Exchange (ETDEWEB)

Song, Chul Hwa; Park, C. K.; Lee, S. J.; Kwon, T. S.; Yun, B. J.; Chung, M. K

2001-02-01

In this report, the test requirements are described for the design of the integral effect test facility to simulate Korean PWR plants. Since the integral effect test facility should be designed so as to simulate various thermal hydraulic phenomena, as closely as possible, to be occurred in real plants during operation or anticipated transients, the design and operational characteristics of the reference plants (Korean Standard Nuclear Plant and Korean Next Generation Reactor)were analyzed in order to draw major components, systems, and functions to be satisfied or simulated in the test facility. The test matrix is set up by considering major safety concerns of interest and the test objectives to confirm and enhance the safety of the plants. And the analysis and prioritization of the test matrix leads to the general design requirements of the test facility. Based on the general design requirements, the design criteria is set up for the basic and detailed design of the test facility. And finally it is drawn the design requirements specific to the fluid system and measurement system of the test facility. The test requirements in this report will be used as a guideline to the scaling analysis and basic design of the test facility. The test matrix specified in this report can be modified in the stage of main testing by considering the needs of experiments and circumstances at that time.

Test requirements for the integral effect test to simulate Korean PWR plants

International Nuclear Information System (INIS)

Song, Chul Hwa; Park, C. K.; Lee, S. J.; Kwon, T. S.; Yun, B. J.; Chung, M. K.

2001-02-01

In this report, the test requirements are described for the design of the integral effect test facility to simulate Korean PWR plants. Since the integral effect test facility should be designed so as to simulate various thermal hydraulic phenomena, as closely as possible, to be occurred in real plants during operation or anticipated transients, the design and operational characteristics of the reference plants (Korean Standard Nuclear Plant and Korean Next Generation Reactor)were analyzed in order to draw major components, systems, and functions to be satisfied or simulated in the test facility. The test matrix is set up by considering major safety concerns of interest and the test objectives to confirm and enhance the safety of the plants. And the analysis and prioritization of the test matrix leads to the general design requirements of the test facility. Based on the general design requirements, the design criteria is set up for the basic and detailed design of the test facility. And finally it is drawn the design requirements specific to the fluid system and measurement system of the test facility. The test requirements in this report will be used as a guideline to the scaling analysis and basic design of the test facility. The test matrix specified in this report can be modified in the stage of main testing by considering the needs of experiments and circumstances at that time

Benefits of Digital Equipment Generic Qualification Activities

International Nuclear Information System (INIS)

Thomas, James E.; Steiman, Samuel C.

2002-01-01

As a result of nuclear power plant instrumentation and control obsolescence issues, there have been numerous activities during recent years relating to the qualification of digital equipment. Some of these activities have been 'generic' in nature in that the qualification was not limited to plant specific applications, but was intended to cover a broad base of potential applications of the digital equipment. These generic qualifications have been funded by equipment manufacturers and by utility groups and organizations. The generic activities sponsored by the Electric Power Research Institute (EPRI) have been pilot projects for an overall generic qualification approach. The primary benefit resulting from the generic qualification work to date is that a number of digital platforms and digital devices are now available for use in various nuclear safety-related applications. Many of the tests and evaluations necessary to support plant specific applications have been completed. The amount of data and documentation that each utility must develop on a case by case basis has been significantly reduced. There are also a number of additional benefits resulting from these industry efforts. The challenges and difficulties in qualifying digital equipment for safety-related applications are now more clearly understood. EPRI has published a lessons learned document (EPRI Report 1001452, Generic Qualification of Commercial Grade Digital Devices: Lessons Learned from Initial Pilots, which covers several different qualification areas, including device selection, project planning, vendor surveys and design reviews, and electromagnetic compatibility (EMC) qualification. Application of the experience and lessons learned from the EPRI pilot activities should help reduce the effort and cost required for future qualification work. Most generic qualification activities for commercial equipment have been conducted using the approach of EPRI TR-106439, Guideline on Evaluation and Acceptance

Design of the Nonlinear Pin Rubber Forming Equipment Integrating the Functions of Extruding, Dewatering, Drying & Expanding

Directory of Open Access Journals (Sweden)

Yuefeng Yuan

2014-12-01

Full Text Available The top priority of car-tire suppliers is to improve wetland grip force of the using tires, reduce the rolling resistance and the rolling noise of tires. It is urgent for the tire industry to research and develop high-performance tires to solve the above problems. They must use the high- performance synthetic rubber and auxiliary rubber to develop the most advanced manufacturing technologies and equipment. Silica, a kind of important tire auxiliary rubber, can significantly reduce the rolling resistance of tires, improve the grip force and properties resistant to ice, wetness or slippery of tires. In this paper, based on the conventional tire rubber forming technologies of extrusion, dewatering, drying and expanding, a study is made on the conical screw, the dewatering barrel, the drying barrel, the pin layout scheme, the expanding die head, cutter and the control system. The nonlinear pin rubber forming equipment integrating the functions of extrusion, dewatering, drying and expanding is designed and applied to tire auxiliary rubber forming. The experiment shows that the forming device can realize the one-step forming, with high forming efficiency, low cost and less labor.

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

Status of NRC approval of EPRI electromagnetic interference susceptibility testing guidelines for digital equipment

International Nuclear Information System (INIS)

James, R.W.; Shank, J.W.; Yoder, C.

1996-01-01

Historically, nuclear power plants installing digital equipment have been required to conduct expensive, site-specific electromagnetic interference (EMI) surveys to demonstrate that EMI will not affect the operation of sensitive electronic equipment. Consequently, EPRI formed a Utility Working Group which developed a set of generic EMI susceptibility testing guidelines, which were published as an EPRI report in September 1994. These guidelines are based upon EMI survey data obtained from several different plants and include criteria for determining their applicability. The Working Group interacted with NRC staff to obtain NRC approval. In April 1996, the NRC issued a Safety Evaluation Report (SER) endorsing the guidelines as a valid means of demonstrating EMI compatibility. The issuance of this SER was conditional on issuing a revision to the EPRI EMI Guidelines. This paper summarizes the guidelines, the NRC SER, and the current status of Revision 1 to the report

Task force for integral test of High Energy nuclear data

Energy Technology Data Exchange (ETDEWEB)

Oyama, Yukio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-11-01

According to completion of the JENDL-High Energy file for neutron nuclear cross sections up to 50 MeV, a task force for integral test of high energy nuclear data was organized to discuss a guide line for integral test activities. A status of existing differential and integral experiments and how to perform such a test were discussed in the task force. Here the purpose and outline of the task force is explained with some future problems raised in discussion among the task member. (author)

Radiation therapy sources, equipment and installations

International Nuclear Information System (INIS)

2011-03-01

The safety code for Telegamma Therapy Equipment and Installations, (AERB/SC/MED-1) and safety code for Brachytherapy Sources, Equipment and Installations, (AERB/SC/MED-3) were issued by AERB in 1986 and 1988 respectively. These codes specified mandatory requirements for radiation therapy facilities, covering the entire spectrum of operations ranging from the setting up of a facility to its ultimate decommissioning, including procedures to be followed during emergency situations. The codes also stipulated requirements of personnel and their responsibilities. With the advent of new techniques and equipment such as 3D-conformal radiation therapy, intensity modulated radiation therapy, image guided radiation therapy, treatment planning system, stereotactic radiosurgery, stereotactic radiotherapy, portal imaging, integrated brachytherapy and endovascular brachytherapy during the last two decades, AERB desires that these codes be revised and merged into a single code titled Radiation Therapy Sources, Equipment, and Installations

Development of Wireless System for Containment Integrated Leakage Rate Test

International Nuclear Information System (INIS)

Lee, Kwang-Dae; Oh, Eung-Se; Yang, Seung-Ok

2006-01-01

The containment system leakage rate should be estimated periodically with reliable test equipment. In light-water reactor nuclear power plants, ANSI/ANS- 56.8 is a basis for determining leakage rates. Two types of data acquisition system, centralized type and networked type, has been used. In centralized type, all sensors are connected directly from sensors in the containment to the measuring equipment outside the building. The other hand, the networked type has several branch chains which connect one group of the network-sensors together. To test leakage rate, more than 20 temperature sensors and 6 humidity sensors, which are different for each plant, should be installed on a specific level in the containment. A wireless technology gives the benefits such as reducing installation efforts, making pretest easy, so it is widely used more and more in the plant monitoring. As the containment system has many kinds of complex barriers to the radio frequency, the radio power and frequency band for better transmission rate as well as the interference by the radio frequency should be considered. The overview of the wireless sensor system for the containment leakage rate test is described here and the test results on Yonggwang unit 4 PWR plant is presented

Electronic detecting equipment in the Camac standard

International Nuclear Information System (INIS)

Basiladze, S.G.

1981-01-01

Basic tends of development of electron detecting equipment of modern facilities for experiments in nuclear physics are considered. Special attention is paid to developments of specialized hybrid integrated circuits, specialized processors for selection of events, usage of integrated circuits of memories in detecting units as well as to prospects of developing nuclear electronics standards [ru

The NIRspec assembly integration and test status

Science.gov (United States)

Wettemann, Thomas; Ehrenwinkler, Ralf; Johnson, Thomas E.; Maschmann, Marc; Mosner, Peter; te Plate, Maurice; Rödel, Andreas

2017-11-01

The Near-Infrared Spectrograph (NIRSpec) is one of the four instruments on the James Webb Space Telescope (JWST) scheduled for launch in 2018. NIRSpec has been manufactured and tested by an European industrial consortium led by Airbus Defence and Space and delivered to the European Space Agency (ESA) and NASA in September 2013. Since then it has successfully been integrated into the JWST Integrated Science Instrument Module (ISIM) and is currently in ISIM Cryo-Vacuum Test#2. Since however two of its most important assemblies, the Focal Plane Assembly (FPA) and the Micro-Shutter Assembly (MSA) need to be replaced by new units we will present the status of the instrument, the status of its new flight assemblies in manufacturing and testing and give an outlook on the planned exchange activities and the following instrument re-verification.

Integral leakage rate tests of containments

International Nuclear Information System (INIS)

Engel, M.; Siefart, E.; Walter, R.

1978-01-01

A method is presented for the integral leakage rate tests of containments. This method, used in conjunction with statistical methods, provides reliable information on the tightness of the containment. This method forms the basis of DIN 25436/KTA 3405. (orig.) [de

Development of nuclear equipment qualification technology

Energy Technology Data Exchange (ETDEWEB)

Choi, Heon O; Kim, Wu Hyun; Kim, Jin Wuk; Kim, Jeong Hyun; Lee, Jeong Kyu; Kim, Yong Han; Jeong, Hang Keun [Korea Institute of Machinery and Materials, Taejon (Korea)

1999-03-01

In order to enhance testing and evaluation technologies, which is one of the main works of the Chanwon branch of KIMM(Korea Institute of Machinery and Materials), in addition to the present work scope of the testing and evaluation in the industrial facilities such as petroleum and chemical, plants, the qualification technologies of the equipments important to safety used in the key industrial facilities such as nuclear power plants should be localized: Equipments for testing and evaluation is to be set up and the related technologies must be developed. In the first year of this study, of vibration aging qualification technologies of equipments important to safety used in nuclear power plants have been performed. (author). 27 refs., 81 figs., 17 tabs.

Integrated Test and Evaluation (ITE) Flight Test Series 4

Science.gov (United States)

Marston, Michael

2016-01-01

The integrated Flight Test 4 (FT4) will gather data for the UAS researchers Sense and Avoid systems (referred to as Detect and Avoid in the RTCA SC 228 ToR) algorithms and pilot displays for candidate UAS systems in a relevant environment. The technical goals of FT4 are to: 1) perform end-to-end traffic encounter test of pilot guidance generated by DAA algorithms; 2) collect data to inform the initial Minimum Operational Performance Standards (MOPS) for Detect and Avoid systems. FT4 objectives and test infrastructure builds from previous UAS project simulations and flight tests. NASA Ames (ARC), NASA Armstrong (AFRC), and NASA Langley (LaRC) Research Centers will share responsibility for conducting the tests, each providing a test lab and critical functionality. UAS-NAS project support and participation on the 2014 flight test of ACAS Xu and DAA Self Separation (SS) significantly contributed to building up infrastructure and procedures for FT3 as well. The DAA Scripted flight test (FT4) will be conducted out of NASA Armstrong over an eight-week period beginning in April 2016.

Thermal Hydraulic Integral Effect Tests for Pressurized Water Reactors

International Nuclear Information System (INIS)

Baek, Won Pil; Song, C. H.; Kim, Y. S.

2007-02-01

The objectives of the project are to construct a thermal-hydraulic integral effect test facility and to perform the tests for design, operation, and safety regulation of pressurized water reactors. In the first phase of this project (1997.8∼2002.3), the basic technology for thermal-hydraulic integral effect tests was established and the basic design of the test facility was accomplished. In the second phase (2002.4∼2005.2), an optimized design of the ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation) was established and the construction of the facility was almost completed. In the third phase (2005.3∼2007.2), the construction and commission tests of the ATLAS are to be completed and some first-phase tests are to be conducted

National Ignition Facility sub-system design requirements integrated timing system SSDR 1.5.3

International Nuclear Information System (INIS)

Wiedwald, J.; Van Aersau, P.; Bliss, E.

1996-01-01

This System Design Requirement document establishes the performance, design, development, and test requirements for the Integrated Timing System, WBS 1.5.3 which is part of the NIF Integrated Computer Control System (ICCS). The Integrated Timing System provides all temporally-critical hardware triggers to components and equipment in other NIF systems

Generic testability and test methods guidelines for ASIC devices

International Nuclear Information System (INIS)

Puri, K.; Takeda, H.

1996-04-01

Many industries are switching from analog equipment to digital equipment. This change has become desirable because digital devices have become cost-effective, easily available, highly reliable, easy to qualify and easy to test and replace when needed. The nuclear power industry is beginning to upgrade some of its instrumentation and control equipment from an analog design to digital design. A digital application specific integrated circuit (ASIC) device can be designed to perform the same functions as performed by analog modules. However, the ASIC must be designed for cost-effective testability and qualification. This report provides generic guidelines for designing cost-effective methods for testing and characterizing ASIC devices to accomplish qualification

Progress in the integration of Test Blanket Systems in ITER equatorial port cells and in the interfaces definition

Energy Technology Data Exchange (ETDEWEB)

Pascal, R., E-mail: romain.pascal@iter.org [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Beloglazov, S.; Bonagiri, S. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Commin, L. [CEA, IRFM, Cadarache (France); Cortes, P.; Giancarli, L.M.; Gliss, C.; Iseli, M.; Lanza, R.; Levesy, B.; Martins, J.-P. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Neviere, J.-C. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Comex-Nucleaire, 13115 Saint Paul Lez Durance (France); Patisson, L.; Plutino, D.; Shu, W. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Swami, H.L. [Institute for Plasma Research, Bhat, Gandhinagar 382428 (India)

2012-08-15

Highlights: Black-Right-Pointing-Pointer The design integration of two test blanket systems in ITER port cell is addressed. Black-Right-Pointing-Pointer Definition of interfaces of TBSs with building and other ITER systems is done. Black-Right-Pointing-Pointer Designs of pipe forest, bioshield plug and ancillary equipment unit are described. Black-Right-Pointing-Pointer The maintenance of the two test blanket systems in ITER port cell is considered. Black-Right-Pointing-Pointer The management of the heat and tritium releases in the TBM port cell is described. - Abstract: In the framework of the TBM Program, three ITER vacuum vessel equatorial ports (no. 16, no. 18 and no. 02) have been allocated for the testing of up to six mock-ups of six different DEMO tritium breeding blankets. Each one is called a Test Blanket System (TBS). A TBS consists mainly of the Test Blanket Module (TBM), the in-vessel component facing the plasma, and several ancillary systems, in particular the cooling system and the tritium extraction system. Each port accommodates two TBMs and therefore the two TBSs have to share the corresponding port cell. This paper deals with the design integration aspects of the two TBSs in each port cell performed at ITER Organization (IO) with the corresponding definition of interfaces with other ITER systems. The performed activities have raised several issues that are discussed in the paper and for which design solutions are proposed.

Testing can counteract proactive interference by integrating competing information

Science.gov (United States)

Wahlheim, Christopher N.

2015-01-01

Testing initially learned information before presenting new information has been shown to counteract the deleterious effects of proactive interference by segregating competing sources of information. The present experiments were conducted to demonstrate that testing can also have its effects in part by integrating competing information. Variations of classic A–B, A–D paired-associate learning paradigms were employed that included two lists of word pairs and a cued-recall test. Repeated pairs appeared in both lists (A–B, A–B), control pairs appeared in List 2 only (A–B, C–D), and changed pairs appeared with the same cue in both lists but with different responses (A–B, A–D). The critical manipulation was whether pairs were tested or restudied in an interpolated phase that occurred between Lists 1 and 2. On a final cued-recall test, participants recalled List 2 responses and then indicated when they recollected that responses had earlier changed between lists. The change recollection measure indexed the extent to which competing responses were integrated during List 2. Change was recollected more often for tested than for restudied pairs. Proactive facilitation was obtained in cued recall when change was recollected, whereas proactive interference was obtained when change was not recollected. These results provide evidence that testing counteracted proactive interference in part by making List 1 responses more accessible during List 2, thus promoting integration and increasing later recollection of change. These results have theoretical implications because they show that testing can counteract proactive interference by integrating or segregating competing information. PMID:25120241

Testing can counteract proactive interference by integrating competing information.

Science.gov (United States)

Wahlheim, Christopher N

2015-01-01

Testing initially learned information before presenting new information has been shown to counteract the deleterious effects of proactive interference by segregating competing sources of information. The present experiments were conducted to demonstrate that testing can also have its effects in part by integrating competing information. Variations of classic A-B, A-D paired-associate learning paradigms were employed that included two lists of word pairs and a cued-recall test. Repeated pairs appeared in both lists (A-B, A-B), control pairs appeared in List 2 only (A-B, C-D), and changed pairs appeared with the same cue in both lists but with different responses (A-B, A-D). The critical manipulation was whether pairs were tested or restudied in an interpolated phase that occurred between Lists 1 and 2. On a final cued-recall test, participants recalled List 2 responses and then indicated when they recollected that responses had earlier changed between lists. The change recollection measure indexed the extent to which competing responses were integrated during List 2. Change was recollected more often for tested than for restudied pairs. Proactive facilitation was obtained in cued recall when change was recollected, whereas proactive interference was obtained when change was not recollected. These results provide evidence that testing counteracted proactive interference in part by making List 1 responses more accessible during List 2, thus promoting integration and increasing later recollection of change. These results have theoretical implications because they show that testing can counteract proactive interference by integrating or segregating competing information.

Solid secondary waste testing for maintenance of the Hanford Integrated Disposal Facility Performance Assessment - FY 2017

Energy Technology Data Exchange (ETDEWEB)

Nichols, Ralph L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Seitz, Roger R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, Kenneth L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-08-01

The Waste Treatment and Immobilization Plant (WTP) at Hanford is being constructed to treat 56 million gallons of radioactive waste currently stored in underground tanks at the Hanford site. Operation of the WTP will generate several solid secondary waste (SSW) streams including used process equipment, contaminated tools and instruments, decontamination wastes, high-efficiency particulate air filters (HEPA), carbon adsorption beds, silver mordenite iodine sorbent beds, and spent ion exchange resins (IXr) all of which are to be disposed in the Integrated Disposal Facility (IDF). An applied research and development program was developed using a phased approach to incrementally develop the information necessary to support the IDF PA with each phase of the testing building on results from the previous set of tests and considering new information from the IDF PA calculations. This report contains the results from the exploratory phase, Phase 1 and preliminary results from Phase 2. Phase 3 is expected to begin in the fourth quarter of FY17.

Integrated Vehicle Ground Vibration Testing of Manned Spacecraft: Historical Precedent

Science.gov (United States)

Lemke, Paul R.; Tuma, Margaret L.; Askins, Bruce R.

2008-01-01

For the first time in nearly 30 years, NASA is developing a new manned space flight launch system. The Ares I will carry crew and cargo to not only the International Space Station, but onward for the future exploration of the Moon and Mars. The Ares I control system and structural designs use complex computer models for their development. An Integrated Vehicle Ground Vibration Test (IVGVT) will validate the efficacy of these computer models. The IVGVT will reduce the technical risk of unexpected conditions that could place the vehicle or crew in jeopardy. The Ares Project Office's Flight and Integrated Test Office commissioned a study to determine how historical programs, such as Saturn and Space Shuttle, validated the structural dynamics of an integrated flight vehicle. The study methodology was to examine the historical record and seek out members of the engineering community who recall the development of historic manned launch vehicles. These records and interviews provided insight into the best practices and lessons learned from these historic development programs. The information that was gathered allowed the creation of timelines of the historic development programs. The timelines trace the programs from the development of test articles through test preparation, test operations, and test data reduction efforts. These timelines also demonstrate how the historical tests fit within their overall vehicle development programs. Finally, the study was able to quantify approximate staffing levels during historic development programs. Using this study, the Flight and Integrated Test Office was able to evaluate the Ares I Integrated Vehicle Ground Vibration Test schedule and workforce budgets in light of the historical precedents to determine if the test had schedule or cost risks associated with it.

Results from the Operational Testing of the General Electric Smart Grid Capable Electric Vehicle Supply Equipment (EVSE)

Energy Technology Data Exchange (ETDEWEB)

Carlson, Richard Barney [Idaho National Lab. (INL), Idaho Falls, ID (United States); Scoffield, Don [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bennett, Brion [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2013-12-01

The Idaho National Laboratory conducted testing and analysis of the General Electric (GE) smart grid capable electric vehicle supply equipment (EVSE), which was a deliverable from GE 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 GE 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.

Evaluation of Maxim Module-Integrated Electronics at the DOE Regional Test Centers: Preprint

Energy Technology Data Exchange (ETDEWEB)

Deline, C.; Sekulic, B.; Stein, J.; Barkaszi, S.; Yang, J.; Kahn, S.

2014-07-01

Module-embedded power electronics developed by Maxim Integrated are under evaluation through a partnership with the Department of Energy's Regional Test Center (RTC) program. Field deployments of both conventional modules and electronics-enhanced modules are designed to quantify the performance advantage of Maxim's products under different amounts of inter-row shading, and their ability to be deployed at a greater ground-coverage-ratio than conventional modules. Simulations in PVSYST have quantified the predicted performance difference between conventional modules and Maxim's modules from inter-row shading. Initial performance results have identified diffuse irradiance losses at tighter row spacing for both the Maxim and conventional modules. Comparisons with published models show good agreement with models predicting the greatest diffuse irradiance losses. At tighter row spacing, all of the strings equipped with embedded power electronics outperformed their conventional peers. An even greater performance advantage is predicted to occur in the winter months when the amount of inter-row shading mismatch is at a maximum.

A method for performance assessment of medical radioisotope equipment

International Nuclear Information System (INIS)

Kerin, T.; Slavtchev, Ath.; Nedeltchev, M.; Kjurktchiev, T.

1984-01-01

A variety of tests and procedures exist for the performance assessment of radioisotope diagnostic equipment. The complex performance index which has been introduced to date is based on an heuristic approach. The present work tries to interconnect algorithmically the most important factors as the influence of the measurement geometry, the statistic peculiarities for lower activities and the information loss at high count rates. All this is reflected in a criterion which integrates the spatial resolution, the effective detector's field of vision, the radionuclide's sensitivity, the background count rate and the effective dead-time of the system under investigation. (Auth.)

An overview of equipment survivability studies at Sandia National Labs. (SNL): Chapter 3

International Nuclear Information System (INIS)

Bonzon, L.L.; Craft, C.M.; McCulloch, W.H.; Sebrell, W.A.

1983-01-01

The USNRC sponsors a number of programs at Sandia National Laboratories (SNL) specifically addressing safety-related equipment survivability. The major thrust of these programs has been the physical testing of equipment. Test results illustrate the importance of a dedicated equipment design effort giving particular attention to the safety implications of the equipment operation. Several equipment survivability tests here have revealed equipment design and test-related deficiencies

Opportunities for the Reduction of Substances and Equipment Impact on Personnel in Penetrant and Magnetic Particles Testing

OpenAIRE

Yaremenko, Yuriy

2015-01-01

Penetrant testing (PT) and magnetic particles inspection (MPI) are widespread methods of non-destructive testing which are not required a lot of investments for manual application and are simple in terms of discontinuous interpretation. On the other hand, work with chemicals requires special precautions, safety instructions and disposal limitations. Growing demand among customers to decrease impact of consumables and equipment on personnel and environment, shift producers’ priorities to devel...

Major Achievements and Prospect of the ATLAS Integral Effect Tests

International Nuclear Information System (INIS)

Choi, K.; Kim, Y.; Song, C.; Baek, W.

2012-01-01

A large-scale thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been operated by KAERI. The reference plant of ATLAS is the APR1400 (Advanced Power Reactor, 1400 MWe). Since 2007, an extensive series of experimental works were successfully carried out, including large break loss of coolant accident tests, small break loss of coolant accident tests at various break locations, steam generator tube rupture tests, feed line break tests, and steam line break tests. These tests contributed toward an understanding of the unique thermal-hydraulic behavior, resolving the safety-related concerns and providing validation data for evaluation of the safety analysis codes and methodology for the advanced pressurized water reactor, APR1400. Major discoveries and lessons found in the past integral effect tests are summarized in this paper. As the demand for integral effect tests is on the rise due to the active national nuclear R and D program in Korea, the future prospects of the application of the ATLAS facility are also discussed.

Economic testing of large integrated switching circuits - a challenge to the test engineer

International Nuclear Information System (INIS)

Kreinberg, W.

1978-01-01

With reference to large integrated switching circuits, one can use an incoming standard programme test or the customer's switching circuits. The author describes the development of suitable, extensive and economical test programmes. (orig.) [de

Minimizing time for test in integrated circuit

OpenAIRE

Andonova, A. S.; Dimitrov, D. G.; Atanasova, N. G.

2004-01-01

The cost for testing integrated circuits represents a growing percentage of the total cost for their production. The former strictly depends on the length of the test session, and its reduction has been the target of many efforts in the past. This paper proposes a new method for reducing the test length by adopting a new architecture and exploiting an evolutionary optimisation algorithm. A prototype of the proposed approach was tested on 1SCAS standard benchmarks and theexperimental results s...

CopperCore Service Integration, Integrating IMS Learning Design and IMS Question and Test Interoperability

NARCIS (Netherlands)

Vogten, Hubert; Martens, Harrie; Nadolski, Rob; Tattersall, Colin; Van Rosmalen, Peter; Koper, Rob

2006-01-01

Vogten, H., Martens, H., Nadolski, R., Tattersall, C., Rosmalen, van, P., Koper, R., (2006). CopperCore Service Integration, Integrating IMS Learning Design and IMS Question and Test Interoperability. Proceedings of the 6th IEEE International Conference on Advanced Learning Technologies (pp.

Power, Avionics and Software - Phase 1.0:. [Subsystem Integration Test Report

Science.gov (United States)

Ivancic, William D.; Sands, Obed S.; Bakula, Casey J.; Oldham, Daniel R.; Wright, Ted; Bradish, Martin A.; Klebau, Joseph M.

2014-01-01

This report describes Power, Avionics and Software (PAS) 1.0 subsystem integration testing and test results that occurred in August and September of 2013. This report covers the capabilities of each PAS assembly to meet integration test objectives for non-safety critical, non-flight, non-human-rated hardware and software development. This test report is the outcome of the first integration of the PAS subsystem and is meant to provide data for subsequent designs, development and testing of the future PAS subsystems. The two main objectives were to assess the ability of the PAS assemblies to exchange messages and to perform audio testing of both inbound and outbound channels. This report describes each test performed, defines the test, the data, and provides conclusions and recommendations.

Integration and test of the ATLAS Semiconductor Tracker

CERN Document Server

Pernegger, H

2007-01-01

The ATLAS Semiconductor Tracker (SCT) will be a central part of the tracking system of the ATLAS experiment and is one of the major new silicon detector systems for LHC. The paper summarizes the system integration of the SCT from individual components to the completed tracker barrel and endcaps ready for installation in the pit. Particular attention will be given to the test results obtained during the different integration steps: from single barrels and disks to the final tests inside the ID before installation in the pit. The tests provided us with operational experience for a significant fraction of the full detector system and showed the very good performance of the final assembled detector.

SOCIAL INTEGRATION: TESTING ANTECEDENTS OF TIME SPENT ONLINE

Directory of Open Access Journals (Sweden)

Lily Suriani Mohd Arif

2013-07-01

Full Text Available The literature on the relationship of social integration and time spent onlineprovides conflicting evidence of the relationship of social integration with timespent online. The study identifies and highlightsthe controversy and attempts toclarify the relationship of social integration withtime spent online bydecomposing the construct social integration into its affective and behavioraldimensions . Thestudy tests antecedents and effects of time spent online in arandom sample of senior level undergraduate students at a public university inMalaysia. The findings indicated that while self-report measures of behavioralsocial integration did not predict time spent online, and, the affective socialintegration had an inverse relationship with time spent online.

Progress on EPRI electrical equipment qualification research

International Nuclear Information System (INIS)

Sliter, G.E.

1983-01-01

The objective of EPRI's electrical equipment qualification research program is to provide technical assistance to utilities in meeting nuclear plant safety requirements in a manner consistent with the state of the art. This paper reports progress on several research projects including: radiation effects studies, which compile data on degradation of organic materials in electrical equipment exposed to operational and accident radiation doses; the Equipment Qualification Data Bank, which is a remotely accessible computer system for disseminating qualification information on in-plant equipment, seismic data, and materials data; an aging/seismic correlation program, which is providing test data showing that, in many cases, age degradation has a negligibly small effect on the performance of electrical components under seismic excitation; a review of condition monitoring techniques, which has identified surveillance methods for measuring key performance parameters that have the potential for predicting remaining equipment life; and large-scale hydrogen burn equipment response tests, which are providing data to assess the ability of equipment to remain functional during and after hydrogen burning in postulated degraded core accidents

Development of the US Military Equipment Testing Range and It's Enlightenment%美军装备试验靶场建设发展及其启示

Institute of Scientific and Technical Information of China (English)

崔侃; 曹裕华

2013-01-01

Based on the review of the development of the US military equipment testing range and on the analysis of the programs ,such as“major range and test facility base” ,“joint test and training range” ,“joint mission environment test capability”and“national cyber range”,adopted by the US to develop its test capability ,this paper proposes that the construction of modern testing range with the direction of facility informationalization ,joint range ,integrated function and system-of-systems tes-ting range is a major tendency under the background of the development of information-dominated military equipment .%回顾美军装备试验靶场建设发展主要历程，叙述美军在靶场信息化改造与建设中推行的“重点靶场”“联合试验训练靶场”“联合任务环境试验能力”以及“国家网络靶场”等建设项目，分析上述项目的实施对提升美军靶场试验能力的意义；提出以设施信息化、靶场联合化、功能综合化、试验体系化为方向的现代装备试验靶场建设，是当前以信息技术为主导的武器装备发展背景下靶场建设发展的重要趋势。

Acoustic Camera as a Fool for Identifying Machinery and Equipment Failures

Directory of Open Access Journals (Sweden)

Ľudmila Pavlikova

2018-03-01

Full Text Available Sound and noise are as old as humanity itself. They have accompanied civilization, evolution, and development for centuries. Music and speech represent not only the key elements of human life but also unpleasant feelings of noise that have always been an integral part of human existence. As industrial development has required more energy, powerful machinery, and equipment, there have been still noisier machines. Traffic has grown quickly due to the number and speed of vehicles. For that reason, an acoustic camera is used for the dynamic visualization of machinery and equipment noise as it analyses the sources of noise in details. Subsequently, qualified measures are introduced based on the results of the analysis. The paper considers launching another application. According to the proposed methodology, its use in identifying machinery and equipment failures and their maintenance is proved. The experiment was performed on a four-wheel lawn mower. The primary focus was on the identification of failures using an acoustic camera. The previous method allowed to quickly, precisely and efficiently identifying the failures in two out of five tested machines.

Integrity assessment of research reactor fuel cladding and material testing using eddy current inspection

International Nuclear Information System (INIS)

Alencar, Donizete Anderson de

2004-01-01

A methodology to perform the integrity assessment of research reactors nuclear fuels cladding, such as those installed in IPR-Rl (TRIGA) and IEA-R1 (MTR), using nondestructive electromagnetic inspection (eddy current) is presented. This methodology is constituted by: the development of calibration reference standards, specific for each type of fuel; the development of special test probes; the recommendations for the inspection equipment calibration; the construction of voltage based evaluation curves and the inspection procedures developed for the characterization of detected flaws. The test probes development, specially those designed for the inspection of MTR fuels cladding, which present access difficulties due to the narrow gap between fuel plates (2,89 mm for IEAR-R1), constituted a challenge that demanded the introduction of unusual materials and constructive techniques. The operational performance of the developed resources, as well as the special operative characteristics of the test probes, such as their immunity to adjacent fuel plates interference and electrical resistivity changes of the fuels meat are experimentally demonstrated. The practical applicability of the developed methodology is verified in non radioactive environment, using a dummy MTR fuel element model, similar to an IEA-R1 reactor fuel element, produced and installed in IPEN, Sao Paulo. The efficacy of the proposed methodology was verified by the achieved results. (author)

Re-qualification of switchgear equipment following field modification

International Nuclear Information System (INIS)

Tulk, J.D.; El Bestawi, M.A.

1984-01-01

A set of 4.16 kV switchgear was seismically qualified by shaker table test for use in a nuclear power plant. Later, the equipment was modified by the addition of two extra switches and enclosures. This paper describes the methods used to extend the qualification achieved in the original proof test to the new configuration. Qualification of the modified switchgear depended on demonstrating that the intensity of the shaking that would be experienced by equipment mounted in the extended enclosure during a design basis earthquake (DBE) would be no stronger than the shaking that occurred during the original qualification testing. This was accomplished by a combination of analysis and experiment. Natural frequencies and mode-shapes of the original and extended enclosure structures were determined through in-situ modal tests on the equipment. Mathematical models based on the experimental results were then used for dynamic analyses which generated two sets of in-equipment response spectra: one set representing the original qualification test; and one set representing the response of the modified equipment to a hypothetical DBE. Qualification was confirmed by demonstrating that the test-based response spectra for the original configuration exceeded the response spectra developed for the extended structure subjected to DBE level excitation

The Mirror Fusion Test Facility cryogenic system: Performance, management approach, and present equipment status

International Nuclear Information System (INIS)

Slack, D.S.; Chronis, W.C.

1987-01-01

The cryogenic system for the Mirror Fusion Test Facility (MFTF) is a 14-kW, 4.35-K helium refrigeration system that proved to be highly successful and cost-effective. All operating objectives were met, while remaining within a few percent of initial cost and schedule plans. The management approach used in MFTF allowed decisions to be made quickly and effectively, and it helped keep costs down. Manpower levels, extent and type of industrial participation, key aspects of subcontractor specifications, and subcontractor interactions are reviewed, as well as highlights of the system tests, operation, and present equipment status. Organizations planning large, high-technology systems may benefit from this experience with the MFTF cryogenic system

Testing integrated sensors for cooperative remote monitoring

International Nuclear Information System (INIS)

Filby, E.E.; Smith, T.E.; Albano, R.K.; Andersen, M.K.; Lucero, R.L.; Tolk, K.M.; Andrews, N.S.

1996-01-01

The Modular Integrated Monitoring System (MIMS) program, with Sandia National Laboratory (SNL) as the lead lab, was devised to furnish sensors and integrated multi-sensor systems for cooperative remote monitoring. The Idaho National Engineering Laboratory (INEL), via the Center for Integrated Monitoring and Control (CIMC), provides realistic field tests of the sensors and sensor-integration approach for the MIMS, and for other similar programs. This has two important goals: it helps insure that these systems are truly read for use, and provides a platform so they can be demonstrated for potential users. A remote monitoring test/demonstration has been initiated at the Idaho Chemical Processing Plant (ICPP) to track the movement of spent nuclear fuel from one storage location to another, using a straddle carrier and shielded cask combination. Radiation monitors, motion sensors, videocameras, and other devices from several US Department of Energy (DOE) labs and commercial vendors were linked on the network. Currently, project personnel are collecting raw data from this large array of sensors, without trying to program any special network activities or other responses. These data will be used to determine which devices can actually provide useful information for a cooperative monitoring situation, versus those that may be redundant

High-speed railway signal trackside equipment patrol inspection system

Science.gov (United States)

Wu, Nan

2018-03-01

High-speed railway signal trackside equipment patrol inspection system comprehensively applies TDI (time delay integration), high-speed and highly responsive CMOS architecture, low illumination photosensitive technique, image data compression technique, machine vision technique and so on, installed on high-speed railway inspection train, and achieves the collection, management and analysis of the images of signal trackside equipment appearance while the train is running. The system will automatically filter out the signal trackside equipment images from a large number of the background image, and identify of the equipment changes by comparing the original image data. Combining with ledger data and train location information, the system accurately locate the trackside equipment, conscientiously guiding maintenance.

Study to Analyze the Acquisition of Automatic Test Equipment (ATE) Systems. Data Sequence Number A003

Science.gov (United States)

1973-12-27

Systems Test Equipment Comparator, ASTEC ) at NAEC can provide a very accurate Ion a pin by pin basis) match between the UUT and ATE in their data bank...In addition, abbreviated summary data on the ATE is also available to users. ASTEC will also file the UUT data as part of its data bank so that

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

Zirconium Recycle Test Equipment for Hot Cell Operations

International Nuclear Information System (INIS)

Collins, Emory D.; DelCul, Guillermo Daniel; Spencer, Barry B.; Bradley, Eric Craig; Brunson, Ronald Ray

2015-01-01

The equipment components and assembly support work were modified for optimized, remote hot cell operations to complete this milestone. The modifications include installation of a charging door, Swagelok connector for the off-gas line between the reactor and condenser, and slide valve installation to permit attachment/replacement of the product salt collector bottle.

Uncertainty and sensitivity analyses for age-dependent unavailability model integrating test and maintenance

International Nuclear Information System (INIS)

Kančev, Duško; Čepin, Marko

2012-01-01

Highlights: ► Application of analytical unavailability model integrating T and M, ageing, and test strategy. ► Ageing data uncertainty propagation on system level assessed via Monte Carlo simulation. ► Uncertainty impact is growing with the extension of the surveillance test interval. ► Calculated system unavailability dependence on two different sensitivity study ageing databases. ► System unavailability sensitivity insights regarding specific groups of BEs as test intervals extend. - Abstract: The interest in operational lifetime extension of the existing nuclear power plants is growing. Consequently, plants life management programs, considering safety components ageing, are being developed and employed. Ageing represents a gradual degradation of the physical properties and functional performance of different components consequently implying their reduced availability. Analyses, which are being made in the direction of nuclear power plants lifetime extension are based upon components ageing management programs. On the other side, the large uncertainties of the ageing parameters as well as the uncertainties associated with most of the reliability data collections are widely acknowledged. This paper addresses the uncertainty and sensitivity analyses conducted utilizing a previously developed age-dependent unavailability model, integrating effects of test and maintenance activities, for a selected stand-by safety system in a nuclear power plant. The most important problem is the lack of data concerning the effects of ageing as well as the relatively high uncertainty associated to these data, which would correspond to more detailed modelling of ageing. A standard Monte Carlo simulation was coded for the purpose of this paper and utilized in the process of assessment of the component ageing parameters uncertainty propagation on system level. The obtained results from the uncertainty analysis indicate the extent to which the uncertainty of the selected

APR1400 Fluidic Device Sensitivity Test

International Nuclear Information System (INIS)

Choi, Nam Hyun; Chu, In Cheol; Min, Kyong Ho; Song, Chul Hwa

2005-12-01

In the safety injection tank at the emergency core cooling system of APR1400, a new safety design feature, passive fluidic device is equipped which includes no active driving system. It is essential to evaluate the new design feature with various experiments. For this reason, three categories of sensitivity tests have been performed in the present study. As the first sensitivity experiment, the effect of the height of the stand pipe was investigated. The second sensitivity test was conducted with removing the insert plate gasket to examine its effect. The effect of the expansion of the control nozzle width was ascertained from the third sensitivity test. The results of each test showed that the passive fluidic device which will be equipped in the SIT tank of APR1400 has great integrity and repeatability

Topical Knowledge in L2 Speaking Assessment: Comparing Independent and Integrated Speaking Test Tasks

Science.gov (United States)

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

2018-01-01

Integrated speaking test tasks (integrated tasks) provide reading and/or listening input to serve as the basis for test-takers to formulate their oral responses. This study examined the influence of topical knowledge on integrated speaking test performance and compared independent speaking test performance and integrated speaking test performance…

Delivering on Industry Equipment Reliability Goals By Leveraging an Integration Platform and Decision Support Environment

International Nuclear Information System (INIS)

Coveney, Maureen K.; Bailey, W. Henry; Parkinson, William

2004-01-01

Utilities have invested in many costly enterprise systems - computerized maintenance management systems, document management systems, enterprise grade portals, to name but a few - and often very specialized systems, like data historians, high end diagnostic systems, and other focused and point solutions. From recent industry reports, we now know that the average nuclear power utilizes on average 1900 systems to perform daily work, of which 250 might facilitate the equipment reliability decision-making process. The time has come to leverage the investment in these systems by providing a common platform for integration and decision-making that will further the collective industry aim of enhancing the reliability of our nuclear generation assets to maintain high plant availability and to deliver on plant life extension goals without requiring additional large scale investment in IT infrastructure. (authors)

Fuel Cell Development and Test Laboratory | Energy Systems Integration

Science.gov (United States)

Facility | NREL Fuel Cell Development and Test Laboratory Fuel Cell Development and Test Laboratory The Energy System Integration Facility's Fuel Cell Development and Test Laboratory supports fuel cell research and development projects through in-situ fuel cell testing. Photo of a researcher running

Energy Systems High-Pressure Test Laboratory | Energy Systems Integration

Science.gov (United States)

Facility | NREL Energy Systems High-Pressure Test Laboratory Energy Systems High-Pressure Test Laboratory In the Energy Systems Integration Facility's High-Pressure Test Laboratory, researchers can safely test high-pressure hydrogen components. Photo of researchers running an experiment with a hydrogen fuel

W-087 Operational test report. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Joshi, A.W.

1997-06-10

This Acceptance Test Procedure/Operational Test Procedure (ATP/OTP) has been prepared to demonstrate that the Electrical/Instrumentation and Mechanical systems function as required by project criteria and to verify proper operation of the integrated system including the interlocks. The equipment to be tested includes the following: a. Leak detection system operation and controls. b. Electrical interlocks.- C. Transfer pump oper ation. d. Vacuum breaker system interlocks.

Site characterization and validation - equipment design and techniques used in single borehole hydraulic testing, simulated drift experiment and crosshole testing

International Nuclear Information System (INIS)

Holmes, D.C.; Sehlstedt, M.

1991-10-01

This report describes the equipment and techniques used to investigate the variation of hydrogeological parameters within a fractured crystalline rock mass. The testing program was performed during stage 3 of the site characterization and validation programme at the Stripa mine in Sweden. This programme used a multidisciplinary approach, combining geophysical, geological and hydrogeological methods, to determine how groundwater moved through the rock mass. The hydrogeological work package involved three components. Firstly, novel single borehole techniques (focused packer testing) were used to determine the distribution of hydraulic conductivity and head along individual boreholes. Secondly, water was abstracted from boreholes which were drilled to simulate a tunnel (simulated drift experiment). Locations and magnitudes of flows were measured together with pressure responses at various points in the SCV rock mass. Thirdly, small scale crosshole tests, involving detailed interference testing, were used to determine the variability of hydrogeological parameters within previously identified, significant flow zones. (au)

Integrated Virtual Environment Test Concepts and Objectives

National Research Council Canada - National Science Library

Tackett, Gregory

2001-01-01

...), a series of integration and verification tests were conducted to provide development milestones for the simulation architecture and tools that would be needed for the full-up live/virtual field experiment...

FFTF integrated leak rate computer system

International Nuclear Information System (INIS)

Hubbard, J.A.

1987-01-01

The Fast Flux Test Facility (FFTF) is a liquid-metal-cooled test reactor located on the Hanford site. The FFTF is the only reactor of this type designed and operated to meet the licensing requirements of the Nuclear Regulatory Commission. Unique characteristics of the FFTF that present special challenges related to leak rate testing include thin wall containment vessel construction, cover gas systems that penetrate containment, and a low-pressure design basis accident. The successful completion of the third FFTF integrated leak rate test 5 days ahead of schedule and 10% under budget was a major achievement for the Westinghouse Hanford Company. The success of this operational safety test was due in large part to a special network (LAN) of three IBM PC/XT computers, which monitored the sensor data, calculated the containment vessel leak rate, and displayed test results. The equipment configuration allowed continuous monitoring of the progress of the test independent of the data acquisition and analysis functions, and it also provided overall improved system reliability by permitting immediate switching to backup computers in the event of equipment failure

Development of Turbulence-Measuring Equipment

Science.gov (United States)

Kovasznay, Leslie S G

1954-01-01

Hot wire turbulence-measuring equipment has been developed to meet the more stringent requirements involved in the measurement of fluctuations in flow parameters at supersonic velocities. The higher mean speed necessitates the resolution of higher frequency components than at low speed, and the relatively low turbulence level present at supersonic speed makes necessary an improved noise level for the equipment. The equipment covers the frequency range from 2 to about 70,000 cycles per second. Constant-current operation is employed. Compensation for hot-wire lag is adjusted manually using square-wave testing to indicate proper setting. These and other features make the equipment adaptable to all-purpose turbulence work with improved utility and accuracy over that of older types of equipment. Sample measurements are given to demonstrate the performance.

Assessing the Impact of Clothing and Individual Equipment (CIE) on Soldier Physical, Biomechanical, and Cognitive Performance Part 1: Test Methodology

Science.gov (United States)

2018-02-01

29 during Soldier Equipment Configuration Impact on Performance: Establishing a Test Methodology for the...during ACSM’S resource manual for exercise testing and prescription Human Movement Science, 31(2), Proceedings of the 2016 American Biomechanics...Performance of Medium Rucksack Prototypes An investigation: Comparison of live-fire and weapon simulator test methodologies and the of three extremity armor

Melcor benchmarking against integral severe fuel damage tests

Energy Technology Data Exchange (ETDEWEB)

Madni, I.K. [Brookhaven National Lab., Upton, NY (United States)

1995-09-01

MELCOR is a fully integrated computer code that models all phases of the progression of severe accidents in light water reactor nuclear power plants, and is being developed for the U.S. Nuclear Regulatory Commission (NRC) by Sandia National Laboratories (SNL). Brookhaven National Laboratory (BNL) has a program with the NRC to provide independent assessment of MELCOR, and a very important part of this program is to benchmark MELCOR against experimental data from integral severe fuel damage tests and predictions of that data from more mechanistic codes such as SCDAP or SCDAP/RELAP5. Benchmarking analyses with MELCOR have been carried out at BNL for five integral severe fuel damage tests, namely, PBF SFD 1-1, SFD 14, and NRU FLHT-2, analyses, and their role in identifying areas of modeling strengths and weaknesses in MELCOR.

46 CFR 71.25-25 - Hull equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 3 2010-10-01 2010-10-01 false Hull equipment. 71.25-25 Section 71.25-25 Shipping COAST... Inspection § 71.25-25 Hull equipment. (a) At each annual inspection, the inspector shall conduct the following tests and inspections of hull equipment: (1) All subdivision bulkheads shall be examined to...

14 CFR Appendix E to Part 43 - Altimeter System Test and Inspection

Science.gov (United States)

2010-01-01

... associated computing systems, or which incorporate air data correction internally, may be tested in a manner...) Automatic Pressure Altitude Reporting Equipment and ATC Transponder System Integration Test. The test must...). Measure the automatic pressure altitude at the output of the installed ATC transponder when interrogated...

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.

Dynamic behavior and functional integrity tests on RC shear walls

International Nuclear Information System (INIS)

Akino, Kinji; Nasuda, Toshiaki; Shibata, Akenori.

1991-01-01

A project consisting of seven subprojects has been conducted to study the dynamic behavior and functional integrity of reinforced concrete (RC) shear walls in reactor buildings. The objective of this project is to obtain the data to improve and prepare the seismic analysis code regarding the nonlinear structural behavior and integrity of reactor buildings during and after earthquakes. The project started in April, 1986, and will end in March, 1994. Seven subprojects are strain rate test, damping characteristic test, ultimate state response test and the verification test for the test of restoring force characteristics regarding dynamic restoring force characteristics and damping performance; the restoring force characteristic test on the shear walls with openings; and pull-out strength test and the test on air leakage through concrete cracks regarding the functional integrity. The objectives of respective subprojects, the test models and the interim results are reported. Three subprojects have been completed by March, 1990. The results of these projects will be used for the overall evaluation. The strain rate test showed that the ultimate strength of shear walls increased with strain rate. A formula for estimating air flow through the cracks in walls was given by the leakage test. (K.I.)

Qualification test for the flexible receiver

International Nuclear Information System (INIS)

Keller, C.M.

1994-01-01

This document provides the test plan and procedures to certify and design verify the 42 inch and 4--6 inch Flexible Receiver (FR) is a safety class 3 system. Verification of the design will be handled in two parts. The first part will be to show that it meets design requirements set forth by documents and the second part will perform test(s) to verify its operational aspects. To qualify the design of the FR systems for field use this test will demonstrate environmentally safe removal of a Tank Farm pump mock-up from a Tank Farm riser mock-up. Testing will also demonstrate the performance of supporting equipment. The FR and the Secondary Bagging (SB) equipment shall be tested to verify successful operation of the equipment to the following criteria: The FR can be placed on a riser and connections made to the supporting equipment; The FR bag can accept equipment and be successfully sealed; The SB system encases the seal of the primary FR bag; The flexible bag(s) do not tear and maintain integrity during the entire test; The FR control system operates in the fail safe forced sequence mode; The FR control system will operate in the manual override mode (out of sequence operations); The CCTV Video system monitors and records the removal of the test item; The spray wash system operates without leaks and effectively provides coverage; The item being removed can be reinserted to a depth of 8 feet and the bag reinstalled onto the vertical bag supports; and The system prohibits momentary mechanical fluctuations due to the application of system power, including power interruptions

Developing equipment for AGR remote visual inspection

International Nuclear Information System (INIS)

James, P.W.; Walton, P.J.

1985-01-01

The Remote Inspection Group is part of the CEGB's Generation Development and Construction Division, and has responsibility for the design, development, procurement, testing and setting to work of the equipment provided to carry out routine remote visual inspections of its AGRs. This equipment includes both the viewing devices and the necessary placement equipment. (author)

Design Study and Optimization of Irradiation Facilities for Detector and Accelerator Equipment Testing in the SPS North Area at CERN

CERN Document Server

AUTHOR|(CDS)2079748; Stekl, Ivan

Due to increasing performance of LHC during the last years, the strong need of new detector and electronic equipment test areas at CERN appeared from user communities. This thesis reports on two test facilities: GIF++ and H4IRRAD. GIF++, an upgrade of GIF facility, is a combined high-intensity gamma and particle beam irradiation facility for testing detectors for LHC. It combines a high-rate 137Cs source, providing photons with energy of 662 keV, together with the high-energy secondary particle beam from SPS. H4IRRAD is a new mixed-field irradiation area, designed for testing LHC electronic equipment for radiation damage effects. In particular, large volume assemblies such as full electronic racks of high current power converters can be tested. The area uses alternatively an attenuated primary 400 GeV/c proton beam from SPS, or a secondary, mainly proton, beam of 280 GeV/c directed towards a copper target. Different shielding layers are used to reproduce a radiation field similar to the LHC “tunnel” and �...

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

Test plan: Brayton Isotope Power System Ground Demonstration System (BIPS-GDS)

International Nuclear Information System (INIS)

1976-01-01

The purpose of this test plan is to provide an overall outline of all testing to be accomplished on the GDS. Included in this test plan are administrative requirements, instrumentation accuracies, instrumentation, equipment definitions, system test setup, and facility installation. The test program will enable collection of sufficient data to establish material, component, and system design integrity. The data will also be used to establish and evaluate component and system performance and reliability characteristics, verification of proper system component integration prior to initiation of Phase II, and flight system (FS) development

Testing Fixture For Microwave Integrated Circuits

Science.gov (United States)

Romanofsky, Robert; Shalkhauser, Kurt

1989-01-01

Testing fixture facilitates radio-frequency characterization of microwave and millimeter-wave integrated circuits. Includes base onto which two cosine-tapered ridge waveguide-to-microstrip transitions fastened. Length and profile of taper determined analytically to provide maximum bandwidth and minimum insertion loss. Each cosine taper provides transformation from high impedance of waveguide to characteristic impedance of microstrip. Used in conjunction with automatic network analyzer to provide user with deembedded scattering parameters of device under test. Operates from 26.5 to 40.0 GHz, but operation extends to much higher frequencies.

Prototype testing and analysis of a novel internal combustion linear generator integrated power system

Energy Technology Data Exchange (ETDEWEB)

Xu, Zhaoping; Chang, Siqin [School of Mechanical Engineering, Nanjing University of Science and Technology, Nanjing 210094 (China)

2010-04-15

A novel four-stroke free-piston engine equipped with a linear electric generator (namely internal combustion linear generator integrated power system) is proposed in this paper to achieve efficient energy conversion from fuel to electricity. Unique features of the novel power system are presented and their effects on the continuous running are discussed, along with potential advantages and disadvantages compared to conventional engines. A single cylinder, gasoline and spark ignition prototype is fabricated with reference to the geometric and control parameters of an existing conventional four-stroke engine. Stable running of the prototype is realized, and a 2.2 kW average output power with the generating efficiency of 32% has been obtained up to now. The feasibility and performance of the proposed design are verified. Detailed testing results from the continuous running prototype are analyzed in this paper for giving insight into the performance and dynamic behaviors of the novel power system. (author)

Integrating IMS Learning Design and IMS Question and Test Interoperability using CopperCore Service Integration

NARCIS (Netherlands)

Vogten, Hubert; Martens, Harrie; Nadolski, Rob; Tattersall, Colin; Van Rosmalen, Peter; Koper, Rob

2006-01-01

Please, cite this publication as: Vogten, H., Martens, H., Nadolski, R., Tattersall, C., van Rosmalen, P., & Koper, R. (2006). Integrating IMS Learning Design and IMS Question and Test Interoperability using CopperCore Service Integration. Proceedings of International Workshop in Learning Networks

Performance results from the first integrated NDA VXI safeguards system

International Nuclear Information System (INIS)

Bot, D.; Messner, R.

1999-01-01

The VIFM system is the first integrated safeguard system to be developed and deployed by the IAEA. The system is also noteworthy in that it is the most versatile of any NDA system thus far deployed. Due to the high level of functionality, the VIFM is probably the most 'tested' of all IAEA systems. This paper discusses the results obtained from detailed in field and laboratory testing of a variety of VIFM configurations ranging from simple single systems to highly integrated system implementations. A total of 4 sites have had VIFM equipment installed. Data collected from these sites have been of very high quality and consistency despite the failure of commercial hard disk drive equipment. The systematic failure of these drives have been corrected using a variety of methods and performance since those corrections have been excellent with no equipment failures. The tests carried out also included the test of a twisted pair to coaxial cable interface. This interface was required in order to allow installation even with a significant facility cabling limitation. The performance obtained from the system utilizing this device showed no degradation as compared to that of systems utilizing direct coaxial cable connections. To conclude, the VIFM system, has been reliable even after partial failure of commercial off-the-shelf components which required the systems to operate on full fail-safe backup. These tests have thus shown both the reliable operation of the VIFM in normal operating conditions as well as the most adverse

An integral effect test facility of the SMART, SMART ITL

Energy Technology Data Exchange (ETDEWEB)

Park, Hyun Sik; Moon, Sang Ki; Kim, Yeon Sik; Cho, Seok; Choi, Ki Yong; Bae, Hwang; Kim, Dong Eok; Choi, Nam Hyun; Min, Kyoung Ho; Ko, Yung Joo; Shin, Yong Cheol; Park, Rae Joon; Lee, Won Jae; Song, Chul Hwa; Yi, Sung Jae [KAERI, Daejeon (Korea, Republic of)

2012-10-15

SMART (System integrated Modular Advanced ReacTor) is a 330 MWth integral pressurized water reactor (iPWR) developed by KAERI and had obtained standard design approval (SDA) from Korean regulatory authority on July 2012. In this SMART design main components including a pressurizer, reactor coolant pumps and steam generators are installed in a reactor pressure vessel without any large connecting pipes. As the LBLOCA scenario is inherently excluded, its safety systems could be simplified only to ensure the safety during the SBLOCA scenarios and the other system transients. An integral effect test loop for the SMART (SMART ITL), or called as FESTA, had been designed to simulate the integral thermal hydraulic behavior of the SMART. The objectives of the SMART ITL are to investigate and understand the integral performance of reactor systems and components and the thermal hydraulic phenomena occurred in the system during normal, abnormal and emergency conditions, and to verify the system safety during various design basis events of the SMART. The integral effect test data will also be used to validate the related thermal hydraulic models of the safety analysis code such as TASS/SMR S, which is used for performance and accident analysis of the SMART design. This paper introduces the scaling analysis and scientific design of the integral test facility of the SMART, SMART ITL and its scaling analysis results.

Plasma and process characterization of high power magnetron physical vapor deposition with integrated plasma equipment--feature profile model

International Nuclear Information System (INIS)

Zhang Da; Stout, Phillip J.; Ventzek, Peter L.G.

2003-01-01

High power magnetron physical vapor deposition (HPM-PVD) has recently emerged for metal deposition into deep submicron features in state of the art integrated circuit fabrication. However, the plasma characteristics and process mechanism are not well known. An integrated plasma equipment-feature profile modeling infrastructure has therefore been developed for HPM-PVD deposition, and it has been applied to simulating copper seed deposition with an Ar background gas for damascene metalization. The equipment scale model is based on the hybrid plasma equipment model [M. Grapperhaus et al., J. Appl. Phys. 83, 35 (1998); J. Lu and M. J. Kushner, ibid., 89, 878 (2001)], which couples a three-dimensional Monte Carlo sputtering module within a two-dimensional fluid model. The plasma kinetics of thermalized, athermal, and ionized metals and the contributions of these species in feature deposition are resolved. A Monte Carlo technique is used to derive the angular distribution of athermal metals. Simulations show that in typical HPM-PVD processing, Ar + is the dominant ionized species driving sputtering. Athermal metal neutrals are the dominant deposition precursors due to the operation at high target power and low pressure. The angular distribution of athermals is off axis and more focused than thermal neutrals. The athermal characteristics favor sufficient and uniform deposition on the sidewall of the feature, which is the critical area in small feature filling. In addition, athermals lead to a thick bottom coverage. An appreciable fraction (∼10%) of the metals incident to the wafer are ionized. The ionized metals also contribute to bottom deposition in the absence of sputtering. We have studied the impact of process and equipment parameters on HPM-PVD. Simulations show that target power impacts both plasma ionization and target sputtering. The Ar + ion density increases nearly linearly with target power, different from the behavior of typical ionized PVD processing. The

Using Gaming Equipment to Teach

Science.gov (United States)

Curriculum Review, 2009

2009-01-01

Gaming equipment (such as Nintendo's Wii[TM]) is making its way to schools and classrooms. However, most of the discussion regarding how to use this technology and integrate it into lesson plans is happening in blogs on the Internet. An advocate of interactive media in the classroom, Dr. Dawn Hawkins, a faculty member for the Art Institute of…

Preparation and Integration of ALHAT Precision Landing Technology for Morpheus Flight Testing

Science.gov (United States)

Carson, John M., III; Robertson, Edward A.; Pierrottet, Diego F.; Roback, Vincent E.; Trawny, Nikolas; Devolites, Jennifer L.; Hart, Jeremy J.; Estes, Jay N.; Gaddis, Gregory S.

2014-01-01

The Autonomous precision Landing and Hazard Avoidance Technology (ALHAT) project has developed a suite of prototype sensors for enabling autonomous and safe precision land- ing of robotic or crewed vehicles on solid solar bodies under varying terrain lighting condi- tions. The sensors include a Lidar-based Hazard Detection System (HDS), a multipurpose Navigation Doppler Lidar (NDL), and a long-range Laser Altimeter (LAlt). Preparation for terrestrial ight testing of ALHAT onboard the Morpheus free- ying, rocket-propelled ight test vehicle has been in progress since 2012, with ight tests over a lunar-like ter- rain eld occurring in Spring 2014. Signi cant work e orts within both the ALHAT and Morpheus projects has been required in the preparation of the sensors, vehicle, and test facilities for interfacing, integrating and verifying overall system performance to ensure readiness for ight testing. The ALHAT sensors have undergone numerous stand-alone sensor tests, simulations, and calibrations, along with integrated-system tests in special- ized gantries, trucks, helicopters and xed-wing aircraft. A lunar-like terrain environment was constructed for ALHAT system testing during Morpheus ights, and vibration and thermal testing of the ALHAT sensors was performed based on Morpheus ights prior to ALHAT integration. High- delity simulations were implemented to gain insight into integrated ALHAT sensors and Morpheus GN&C system performance, and command and telemetry interfacing and functional testing was conducted once the ALHAT sensors and electronics were integrated onto Morpheus. This paper captures some of the details and lessons learned in the planning, preparation and integration of the individual ALHAT sen- sors, the vehicle, and the test environment that led up to the joint ight tests.

An integrated artificial neural networks approach for predicting global radiation

International Nuclear Information System (INIS)

Azadeh, A.; Maghsoudi, A.; Sohrabkhani, S.

2009-01-01

This article presents an integrated artificial neural network (ANN) approach for predicting solar global radiation by climatological variables. The integrated ANN trains and tests data with multi layer perceptron (MLP) approach which has the lowest mean absolute percentage error (MAPE). The proposed approach is particularly useful for locations where no available measurement equipment. Also, it considers all related climatological and meteorological parameters as input variables. To show the applicability and superiority of the integrated ANN approach, monthly data were collected for 6 years (1995-2000) in six nominal cities in Iran. Separate model for each city is considered and the quantity of solar global radiation in each city is calculated. Furthermore an integrated ANN model has been introduced for prediction of solar global radiation. The acquired results of the integrated model have shown high accuracy of about 94%. The results of the integrated model have been compared with traditional angstrom's model to show its considerable accuracy. Therefore, the proposed approach can be used as an efficient tool for prediction of solar radiation in the remote and rural locations with no direct measurement equipment.

Fiscal 1997 research report on the survey on public test and evaluation organizations for development of welfare equipment; 1997 nendo fukushi kiki kaihatsu ni kakawaru koteki shiken hyoka kikan chosa hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-03-01

This research studies the construction policy of public test and evaluation systems for future development and practical use of welfare equipment, through survey on the current methods for development, practical test and evaluation of welfare equipment in countries advanced in welfare, and preparation of basic data for promoting establishment of public test and evaluation functions in Japan. Infrastructure preparation for standards and public test and evaluation organizations for developing welfare equipment is being promoted by Technical Laboratory of Bicycle Industry Promotion Association and some national organizations such as Product Evaluation Technical Center, Mechanical Engineering Laboratory, National Institute of Bioscience and Human Technology, and Living and JIS Center. However, preparation of objective and across test and evaluation systems for developing welfare equipment is still insufficient. Product Evaluation Technical Center is now approaching to evaluation and standardization of welfare equipment. Public test and evaluation organizations of the UK, Sweden and Denmark are presented. (NEDO)

Alternative containment integrity test methods, an overview of possible techniques

International Nuclear Information System (INIS)

Spletzer, B.L.

1986-01-01

A study is being conducted to develop and analyze alternative methods for testing of containment integrity. The study is focused on techniques for continuously monitoring containment integrity to provide rapid detection of existing leaks, thus providing greater certainty of the integrity of the containment at any time. The study is also intended to develop techniques applicable to the currently required Type A integrated leakage rate tests. A brief discussion of the range of alternative methods currently being considered is presented. The methods include applicability to all major containment types, operating and shutdown plant conditions, and quantitative and qualitative leakage measurements. The techniques are analyzed in accordance with the current state of knowledge of each method. The bulk of the techniques discussed are in the conceptual stage, have not been tested in actual plant conditions, and are presented here as a possible future direction for evaluating containment integrity. Of the methods considered, no single method provides optimum performance for all containment types. Several methods are limited in the types of containment for which they are applicable. The results of the study to date indicate that techniques for continuous monitoring of containment integrity exist for many plants and may be implemented at modest cost

Tracking Unmanned Aerial Vehicle CTU FTS - Application of equipment

Directory of Open Access Journals (Sweden)

David Hůlek

2015-10-01

Full Text Available Article which is about the Tracking Unmanned Aerial Vehicle continues in the description of the project development dealing with the utilization of the UAV (unmanned aerial vehicle. Documentation of the project progresses builds on the previous article. In that article the selection of observation and transmission equipment was summarized. In the article, the reader learns about an installation of the equipment on the UAV (helicopter, about an interconnection of the equipment to create complete and functional system, about testing of the UAV, about the solutions of the problems which came into being during testing and about protection of the equipment against unfavourable effects. The location of equipment on the unmanned vehicle was chosen after a considering of several parameters. These parameters are preservation of the functionality or an influence to the balance. To find out how the added equipment affect the centre of gravity of the UAV the tabular method of the centre of gravity calculation was used. The results of the existing work on the project are location and attaching of the equipment to the unmanned vehicle, balance of the unmanned vehicle, solutions of the problems coming into being during the testing and design of the equipment protection against unfavourable effects.

7 CFR 1436.6 - Eligible storage or handling equipment.

Science.gov (United States)

2010-01-01

...) Electrical equipment, including labor and materials for installation, such as lighting, motors, and wiring... installation, such as lighting, motors, and wiring integral to the proper operation of the sugar storage and... materials for installation, such as lighting, motors, and wiring integral to the proper operation of a cold...

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.

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

Integration test of ITER full-scale vacuum vessel sector

International Nuclear Information System (INIS)

Nakahira, M.; Koizumi, K.; Oka, K.

2001-01-01

The full-scale Sector Model Project, which was initiated in 1995 as one of the Large Seven R and D Projects, completed all R and D activities planned in the ITER-EDA period with the joint effort of the ITER Joint Central Team (JCT), the Japanese, the Russian Federation (RF) and the United States (US) Home Teams. The fabrication of a full-scale 18 toroidal sector, which is composed of two 9 sectors spliced at the port center, was successfully completed in September 1997 with the dimensional accuracy of ± 3 mm for the total height and total width. Both sectors were shipped to the test site in JAERI and the integration test was begun in October 1997. The integration test involves the adjustment of field joints, automatic Narrow Gap Tungsten Inert Gas (NG-TIG) welding of field joints with splice plates, and inspection of the joint by ultrasonic testing (UT), which are required for the initial assembly of ITER vacuum vessel. This first demonstration of field joint welding and performance test on the mechanical characteristics were completed in May 1998 and the all results obtained have satisfied the ITER design. In addition to these tests, the integration with the mid plane port extension fabricated by the Russian Home Team, and the cutting and re-welding test of field joints by using full-remotized welding and cutting system developed by the US Home Team, are planned as post EDA activities. (author)

Integration test of ITER full-scale vacuum vessel sector

International Nuclear Information System (INIS)

Nakahira, M.; Koizumi, K.; Oka, K.

1999-01-01

The full-scale Sector Model Project, which was initiated in 1995 as one of the Large Seven ITER R and D Projects, completed all R and D activities planned in the ITER-EDA period with the joint effort of the ITER Joint Central Team (JCT), the Japanese, the Russian Federation (RF) and the United States (US) Home Teams. The fabrication of a full-scale 18 toroidal sector, which is composed of two 9 sectors spliced at the port center, was successfully completed in September 1997 with the dimensional accuracy of - 3 mm for the total height and total width. Both sectors were shipped to the test site in JAERI and the integration test was begun in October 1997. The integration test involves the adjustment of field joints, automatic Narrow Gap Tungsten Inert Gas (NG-TIG) welding of field joints with splice plates, and inspection of the joint by ultrasonic testing (UT), which are required for the initial assembly of ITER vacuum vessel. This first demonstration of field joint welding and performance test on the mechanical characteristics were completed in May 1998 and the all results obtained have satisfied the ITER design. In addition to these tests, the integration with the mid plane port extension fabricated by the Russian Home Team, and the cutting and re-welding test of field joints by using full-remotized welding and cutting system developed by the US Home Team, are planned as post EDA activities. (author)

Electric vehicle equipment for grid-integrated vehicles