15 CFR 740.10 - Servicing and replacement of parts and equipment (RPL).

Science.gov (United States)

2010-01-01

... REGULATIONS LICENSE EXCEPTIONS § 740.10 Servicing and replacement of parts and equipment (RPL). This License... replacement of equipment. (a) Parts—(1) Scope. The provisions of this paragraph (a) authorize the export and reexport of one-for-one replacement parts for previously exported equipment. (2) One-for-one replacement of...

Maintenance or replacement of primary equipments

International Nuclear Information System (INIS)

Branchu, J.

1995-01-01

The principal materials, such as the primary equipments of a PWR type steam generator, have a finite service life. Framatome, builder of steam generators and maintenance contractor of Electricite de France has developed a methodology for the maintenance or the replacement of primary equipments. The paper describes the methodology followed by Framatome to identify and localize the wear mode and to treat or repair the component. Four failure modes have been considered: crack propagation, rubbing/vibration wear, neutron irradiation and corrosion propagation under permanent stress. A kinetic modelling of wear propagation has been computerized and validated using mechanical tests on Inconel 600 mockups. These analyses have allow to determine the strategy of repair or replacement of vessel heads for each unit. The method is evaluated taking into account the risk assessment, cost, dosimetry, efficiency and time delay involved. (J.S.). 1 fig., 3 photos

Optimization on replacement and inspection period of plant equipment

International Nuclear Information System (INIS)

Takase, Kentaro; Kasai, Masao

2004-01-01

Rationalization of the plant maintenance is one of the main topics being investigated in Japanese nuclear power industries. Optimization of the inspection and replacement period of equipments is effective for the maintenance cost reduction. The more realistic model of the replacement policy is proposed in this study. It is based on the classical replacement policy model and its cost is estimated. Then, to consider the inspection for the maintenance, the formulation that includes the risk concept is discussed. Based on it, two variations of the combination of the inspection and the replacement are discussed and the costs are estimated. In this study the effect of the degradation of the equipment is important. The optimized maintenance policy depends on the existence of significant degradation. (author)

Decommissioning and equipment replacement of nuclear power plants under uncertainty

International Nuclear Information System (INIS)

Takashima, Ryuta; Naito, Yuta; Kimura, Hiroshi; Madarame, Haruki

2007-01-01

This study examines the optimal timing for the decommissioning and equipment replacement of nuclear power plants. We consider that the firm has two options of decommissioning and equipment replacement, and determines to exercise these options under electricity price uncertainty. This problem is formulated as two optimal stopping problems. The solution of this model provides the value of the nuclear power plant and the threshold values for decommissioning and replacement. The dependence of decommissioning and replacement strategies on uncertainty and each cost is shown. In order to investigate the probability of events for decommissioning and replacement, Monte Carlo calculations are performed. We also show the probability distribution and the conditional expected time for each event. (author)

40 CFR 261.35 - Deletion of certain hazardous waste codes following equipment cleaning and replacement.

Science.gov (United States)

2010-07-01

... codes following equipment cleaning and replacement. 261.35 Section 261.35 Protection of Environment... equipment in accordance with this section; (ii) Prepare and follow an equipment replacement plan and replace equipment in accordance with this section; or (iii) Document cleaning and replacement in accordance with...

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

International Nuclear Information System (INIS)

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

1984-01-01

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

Simulation Gaming in Construction: ER, The Equipment Replacement Game.

Science.gov (United States)

Nassar, Khaled

2002-01-01

The Equipment Replacement simulation game can be used to explain the different effects of various equipment buy/sell strategies on the economic performance of construction companies. The probabilistic aspect of demand in the construction market is incorporated. The game is implemented using Excel and Visual Basic for Applications. (Author/SK)

34 CFR 395.10 - The maintenance and replacement of vending facility equipment.

Science.gov (United States)

2010-07-01

... and replacement of vending facility equipment. The State licensing agency shall maintain (or cause to... 34 Education 2 2010-07-01 2010-07-01 false The maintenance and replacement of vending facility equipment. 395.10 Section 395.10 Education Regulations of the Offices of the Department of Education...

OPTIMIZATION MODEL FOR VEHICLE ROUTING AND EQUIPMENT REPLACEMENT IN FARM MACHINERY

OpenAIRE

Grano, Carolina; Abensur, Eder

2017-01-01

ABSTRACT: An equipment replacement decision takes into account economic engineering models based on discounted cash flow (DCF) such as the Annual Equivalent Cost (AEC). Despite a large number of researches on industrial assets replacement, there is a lack of studies applied to farm goods. This study aimed at assessing an alternative model for economic decision analysis on farm machinery replacement, with no restrictions on the number of replacements and assessed goods during a defined timelin...

38 CFR 17.351 - Grants for the replacement and upgrading of equipment at Veterans Memorial Medical Center.

Science.gov (United States)

2010-07-01

... replacement and upgrading of equipment at Veterans Memorial Medical Center. 17.351 Section 17.351 Pensions... Philippines § 17.351 Grants for the replacement and upgrading of equipment at Veterans Memorial Medical Center. Grants to assist the Republic of the Philippines in the replacement and upgrading of equipment and in...

38 CFR 17.352 - Amounts and use of grant funds for the replacement and upgrading of equipment.

Science.gov (United States)

2010-07-01

... funds for the replacement and upgrading of equipment. 17.352 Section 17.352 Pensions, Bonuses, and... Amounts and use of grant funds for the replacement and upgrading of equipment. Grants awarded under § 17... States for the purpose. Funds appropriated for the upgrading and replacement of equipment at the Veterans...

Financial Analysis for Replacement of Construction Equipment in Saudi Arabia

Directory of Open Access Journals (Sweden)

Ali Shash

2012-11-01

Full Text Available This study report results of a survey conducted in the EasternProvince of Saudi Arabia to explore the procedures and financialtechniques that large-size contractors utilise in replacingequipment. The results indicated that contractors set severalreplacement alternatives that they evaluate by using a set ofvarious qualitative and quantitative factors. The contractors’business objectives, employee safety and morale, and, contractors’image in the industry were found to be the most influentialqualitative factors affecting the decision of equipment replacement.Inflation, downtime, obsolescence, salvage value, and depreciationare among the top quantitative factors that contractors considerwhile making a decision to replace equipment. Because of theirsimplicity and practicality, the net present value, payback period,and the economic life are the most popular techniques that areutilised for analysing the financial issues of proposed replacementalternatives.

Maintainability design criteria for packaging of spacecraft replaceable electronic equipment.

Science.gov (United States)

Kappler, J. R.; Folsom, A. B.

1972-01-01

Maintainability must be designed into long-duration spacecraft and equipment to provide the required high probability of mission success with the least cost and weight. The ability to perform repairs quickly and easily in a space environment can be achieved by imposing specific maintainability design criteria on spacecraft equipment design and installation. A study was funded to investigate and define design criteria for electronic equipment that would permit rapid removal and replacement in a space environment. The results of the study are discussed together with subsequent simulated zero-g demonstration tests of a mockup with new concepts for packaging.

23 CFR 661.19 - When is a bridge eligible for replacement?

Science.gov (United States)

2010-04-01

... 23 Highways 1 2010-04-01 2010-04-01 false When is a bridge eligible for replacement? 661.19... replacement? To be eligible for replacement, the bridge must be considered structurally deficient or functionally obsolete and must be in accordance with 23 CFR part 650.409(a) for bridge replacement. After an...

Replacement strategy for obsolete plant computers

International Nuclear Information System (INIS)

Schaefer, J.P.

1985-01-01

The plant computers of the first generation of larger nuclear power plants are reaching the end of their useful life time with respect to the hardware. The software would be no reason for a system exchange but new tasks for the supervisory computer system, availability questions of maintenance personnel and spare parts and the demand for improved operating procedures for the computer users have stimulated the considerations on how to exchange a computer system in a nuclear power plant without extending plant outage times due to exchange works. In the Federal Republic of Germany the planning phase of such backfitting projects is well under way, some projects are about to be implemented. The base for these backfitting projects is a modular supervisory computer concept which has been designated for the new line of KWU PWR's. The main characteristic of this computer system is the splitting of the system into a data acquisition level and a data processing level. This principle allows an extension of the processing level or even repeated replacements of the processing computers. With the existing computer system still in operation the new system can be installed in a step-by-step procedure. As soon as the first of the redundant process computers of the data processing level is in operation and the data link to the data acquisition computers is established the old computer system can be taken out of service. Then the back-up processing computer can be commissioned to complete the new system. (author)

Setting the optimal type of equipment to be adopted and the optimal time to replace it

OpenAIRE

Albici, Mihaela

2009-01-01

The mathematical models of equipment’s wear and tear, and replacement theory aim at deciding on the purchase selection of a certain equipment type, the optimal exploitation time of the equipment, the time and ways to replace or repair it, or to ensure its spare parts, the equipment’s performance in the technical progress context, the opportunities to modernize it etc.

Development of an approach to facilitate optimal equipment replacement : technical summary.

Science.gov (United States)

1999-10-01

The objective of the study was to determine a way or ways to assign an urgency rating to equipment that was currently in service but in need of replacement. This urgency rating must in some manner took into account the various costs associated with r...

New technology for optimized I and C maintenance and management of ageing of critical equipment in nuclear power plants

International Nuclear Information System (INIS)

Hashemian, H.M.

2000-01-01

Advanced sensors and new testing and maintenance technologies have become available over the last ten years for nuclear power plants (NPPs) to replace outdated, obsolete, and troublesome instruments, provide for management of ageing of critical plant equipment, optimize maintenance activities, reduce maintenance costs and personnel radiation exposure, and at the same time, improve plant safety and availability. These new developments are reviewed in this TECDOC. The material covered here has been summarized from NUREG/CR-5501, a 1998 report written by H.M. Hashemian and his co-authors for the US Nuclear Regulatory Commission. (author)

Cost analysis of hash collisions : will quantum computers make SHARCS obsolete?

NARCIS (Netherlands)

Bernstein, D.J.

2009-01-01

Current proposals for special-purpose factorization hardware will become obsolete if large quantum computers are built: the number-field sieve scales much more poorly than Shor's quantum algorithm for factorization. Will all special-purpose cryptanalytic hardware become obsolete in a post-quantum

3-D modeling and motion simulation of fuel rod-replacing equipment

International Nuclear Information System (INIS)

Ding Jie; Zhu Libing

2010-01-01

In this paper, the process of 3-D modeling and motion simulation of fuel rod-replacing equipment using SolidWorks is described, and the application of SolidWorks in manufacturing and design improvement is discussed. Complexity of the manufacturing is reduced and reliability of the design is improved. (authors)

9 CFR 355.36 - Obsolete labels.

Science.gov (United States)

2010-01-01

... CERTIFICATION CERTIFIED PRODUCTS FOR DOGS, CATS, AND OTHER CARNIVORA; INSPECTION, CERTIFICATION, AND... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Obsolete labels. 355.36 Section 355.36 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY...

Financing New Technologies, Equipment/Furniture Replacement, and Building Renovation: A Survey Report.

Science.gov (United States)

Shirk, Gary M.

1984-01-01

Reports results of survey of methods used by 77 North American academic and public libraries to finance implementation of new technologies, replace equipment and furniture, and renovate buildings. Financing methods used, frequency of use, choice, and range of methods are discussed. Eight references and list of survey participants are appended.…

Use of seismic experience data for replacement and new equipment

International Nuclear Information System (INIS)

Johnson, H.W.; Hardy, G.S.; Horstman, N.G.; Baughman, P.D.

1990-01-01

Over the past seven years the use of seismic experience data to address seismic concerns has received a great deal of attention, particularly regarding the NRC Unresolved Safety Issue (USI) A-46. The Seismic Qualification Utility Group (SQUG) was formed in January 1982 to develop a practical alternative to the rigorous seismic qualification of equipment for resolution of USI A-46. The alternative method chosen is seismic experience technology. The purpose of this paper is to explore two additional potential applications of seismic experience technology: Replacement parts and New equipment/design change process. The need for, and benefits of, these applications are summarized. The available technology and the methodologies proposed are described. The methodology descriptions include a summary of the requirements for the seismic evaluations, an outline of the method, and the documentation requirements. (orig./HP)

9 CFR 590.502 - Equipment and utensils; PCB-containing equipment.

Science.gov (United States)

2010-01-01

... Sanitary Standards and accepted practices currently in effect for such equipment. (c) New or replacement equipment or machinery (including any replacement parts) brought onto the premises of any official plant... equipment and machinery, and any replacement parts for such equipment and machinery. Totally enclosed...

Refurbishment programs

International Nuclear Information System (INIS)

Irish, C.S.

2004-01-01

As nuclear plants age, equipment becomes obsolete, outdated or just simply unreliable. This puts a lot of emphasis on replacement of the subject equipment. This can be an expensive proposition for safety related equipment due to design changes, requalification charges and the cost of the new equipment, specifically when the original component is obsolete. The presentation will explain how comprehensive refurbishment programs on many different types of equipment can alleviate this situation. The refurbishment program is a systematic refurbishment of equipment to an as new condition by replacing all of the age sensitive components within the equipment. This is carried out on all of the same type of equipment in a scheduled program. For example the plant may to decide to refurbish all of their Lambda LME-24 power supplies, or all of their Bailey modules, or all of their Agastat DSC Series relays. Independent of the item the process is the same. Refurbish each piece of equipment to an as new condition by replacing all of the age sensitive equipment. The equipment is then returned to the client as safety related, existing qualification maintained and with a new service life/warranty. This is not a simple repair. It is a planned refurbishment to an as new condition of certain equipment types throughout the plant and then carried out from equipment piece to equipment piece. The refurbishment program may even include introducing new spares into the plant. This is normally performed by upgrading (dedicating for safety related use and refurbishing to an 'as new' condition) surplus equipment and using these equipment pieces in the rotation of the plant equipment to refurbish the entire population of a selected piece of equipment at the plant. This process can be performed on many equipment types including power supplies, circuit boards, modules, relays, motors, breakers, and many more. The refurbishment program greatly increases the reliability of the equipment without the

Choice of optimal replacement of equipment in the warehouse of the company

Science.gov (United States)

Baeva, Silvia; Tomov, Kiril

2016-12-01

The aim of this paper is to find an optimal replacement of equipment in the warehouse of the company. Real data for the machines are used and are processed with appropriate software. The mathematical model is made for this problem as problem for the shortest path from graph theory. The solution is made by Bellman's principle.

CANDU Digital Control Computer upgrade options

International Nuclear Information System (INIS)

De Jong, M.S.; De Grosbois, J.; Qian, T.

1997-01-01

This paper reviews the evolution of Digital Control Computers (DCC) in CANDU power plants to the present day. Much of this evolution has been to meeting changing control or display requirements as well as the replacement of obsolete, or old and less reliable technology with better equipment that is now available. The current work at AECL and Canadian utilities to investigate DCC upgrade options, alternatives, and strategies are examined. The dependence of a particular upgrade strategy on the overall plant refurbishment plans are also discussed. Presently, the upgrade options range from replacement of individual obsolete system components, to replacement of the entire DCC hardware without changing the software, to complete replacement of the DCCs with a functionally equivalent system using new control computer equipment and software. Key issues, constraints and objectives associated with these DCC upgrade options are highlighted. (author)

Refurbishment and replacement efforts to mitigate ageing at Tarapur Atomic Power Station - an overview

International Nuclear Information System (INIS)

Katiyar, S.C.; Thattey, V.; Das, P.K.

2006-01-01

Tarapur Atomic Power Station (TAPS) - a twin Boiling Water Reactor unit and India's first Atomic Power Station was commissioned in April 1969, and was declared commercial in November 1969. Since then the light water moderated, low enriched uranium BWR with its demonstrated reliability and favourable economics is playing a vital role as a reliable source of power for the states of Maharashtra and Gujarat. The Power Station played a key role as a technology demonstrator validating the nuclear energy as safe and environmentally benign and economically viable alternate source of power generation in India. Built in the late sixties with state-of-the-art safety features prevailing then, TAPS has further evolved to be a safe plant with renovation and refurbishment efforts. Ageing Management Programme is in place at TAPS. Identification of systems, structures and components (SSCs) important to safety and availability, assessment of ageing degradation of these SSCs and mitigation through repair, replacement and refurbishment based on the investigations have enhanced the plant safety and reliability. The station's operating experience and feedback from BWRs operating abroad have also given inputs to Ageing Management Programme. A good number of major equipment have been replaced to mitigate ageing. Primary system piping, process heat exchangers, feed water heaters, turbine extraction system piping, turbine blades, emergency condenser tube bundles, various pumps, station batteries, electrical cables, circuit breakers etc. are some of them. Obsolescence is another aspect of ageing of a plant. Replacement of obsolete equipment and components particularly in C and I is another area where much headway has been made. Replacement and refurbishment of equipment have been done after detailed study and analysis so that current standards are met. Retrofitting the indigenously developed and fabricated equipment in a compact plant like TAPS was a difficult task and required lot of

X-ray pelvimetry in a resource poor environment. Obsolete ...

African Journals Online (AJOL)

-pelvic disproportion; a risk factor associated with dystocia and obstructed labor. Computed tomography pelvimetry has rendered traditional radiographic assessment obsolete and makes radiography useful probably only in the rural health ...

29 CFR 97.32 - Equipment.

Science.gov (United States)

2010-07-01

...) When acquiring replacement equipment, the grantee or subgrantee may use the equipment to be replaced as... equipment (including replacement equipment), whether acquired in whole or in part with grant funds, until... established to ensure the highest possible return. (e) Disposition. When original or replacement equipment...

44 CFR 13.32 - Equipment.

Science.gov (United States)

2010-10-01

...) When acquiring replacement equipment, the grantee or subgrantee may use the equipment to be replaced as... equipment (including replacement equipment), whether acquired in whole or in part with grant funds, until... established to ensure the highest possible return. (e) Disposition. When original or replacement equipment...

24 CFR 85.32 - Equipment.

Science.gov (United States)

2010-04-01

...) When acquiring replacement equipment, the grantee or subgrantee may use the equipment to be replaced as... equipment (including replacement equipment), whether acquired in whole or in part with grant funds, until... established to ensure the highest possible return. (e) Disposition. When original or replacement equipment...

43 CFR 12.72 - Equipment.

Science.gov (United States)

2010-10-01

...) When acquiring replacement equipment, the grantee or subgrantee may use the equipment to be replaced as... equipment (including replacement equipment), whether acquired in whole or in part with grant funds, until... established to ensure the highest possible return. (e) Disposition. When original or replacement equipment...

45 CFR 2541.320 - Equipment.

Science.gov (United States)

2010-10-01

... replacement equipment, the grantee or subgrantee may use the equipment to be replaced as a trade-in or sell... replacement equipment), whether acquired in whole or in part with grant funds, until disposition takes place... ensure the highest possible return. (e) Disposition. When original or replacement equipment acquired...

Optimal replacement of residential air conditioning equipment to minimize energy, greenhouse gas emissions, and consumer cost in the US

International Nuclear Information System (INIS)

De Kleine, Robert D.; Keoleian, Gregory A.; Kelly, Jarod C.

2011-01-01

A life cycle optimization of the replacement of residential central air conditioners (CACs) was conducted in order to identify replacement schedules that minimized three separate objectives: life cycle energy consumption, greenhouse gas (GHG) emissions, and consumer cost. The analysis was conducted for the time period of 1985-2025 for Ann Arbor, MI and San Antonio, TX. Using annual sales-weighted efficiencies of residential CAC equipment, the tradeoff between potential operational savings and the burdens of producing new, more efficient equipment was evaluated. The optimal replacement schedule for each objective was identified for each location and service scenario. In general, minimizing energy consumption required frequent replacement (4-12 replacements), minimizing GHG required fewer replacements (2-5 replacements), and minimizing cost required the fewest replacements (1-3 replacements) over the time horizon. Scenario analysis of different federal efficiency standards, regional standards, and Energy Star purchases were conducted to quantify each policy's impact. For example, a 16 SEER regional standard in Texas was shown to either reduce primary energy consumption 13%, GHGs emissions by 11%, or cost by 6-7% when performing optimal replacement of CACs from 2005 or before. The results also indicate that proper servicing should be a higher priority than optimal replacement to minimize environmental burdens. - Highlights: → Optimal replacement schedules for residential central air conditioners were found. → Minimizing energy required more frequent replacement than minimizing consumer cost. → Significant variation in optimal replacement was observed for Michigan and Texas. → Rebates for altering replacement patterns are not cost effective for GHG abatement. → Maintenance levels were significant in determining the energy and GHG impacts.

The analytical determination of useful life and replacement intervals for equipment located in a non-harsh environment

International Nuclear Information System (INIS)

Glazman, J.S.; Ahluwalia, J.S.; Kneppel, D.S.; Harter, T.G.

1985-01-01

In order to establish useful life and replacement intervals for equipment located in a non-harsh environment, an analysis can be performed to show that either the thermal degradation of the equipment is insignificant over the life of the plant or that certain components must be replaced periodically. In these analyses it is necessary to calculate the thermal lives of the components based on their actual operating temperatures rather than at a single cabinet temperature. The Infrared Thermal Imaging Measurement System is a rapid technique for measuring the temperatures of all points on a board or cabinet side simultaneously. The infrared scan of the operating equipment is displayed on a monitor, analyzed and stored on videotape for future reference. This paper presents an approach to performing such an analysis using the example of a process analysis and display system. The equilibrium operating temperatures of the individual components in the above system were measured by the Infrared Thermal Imaging Measurement System and compared to a calculated maximum permitted service temperature determined by the Arrhenius methodology. Examples will be shown where it was possible to exempt entire assemblies from replacement by showing that no point on the assembly exceeds the calculated maximum permitted temperature

22 CFR 135.32 - Equipment.

Science.gov (United States)

2010-04-01

... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

21 CFR 1403.32 - Equipment.

Science.gov (United States)

2010-04-01

... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

45 CFR 602.32 - Equipment.

Science.gov (United States)

2010-10-01

... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

49 CFR 18.32 - Equipment.

Science.gov (United States)

2010-10-01

... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

34 CFR 80.32 - Equipment.

Science.gov (United States)

2010-07-01

... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

10 CFR 600.232 - Equipment.

Science.gov (United States)

2010-01-01

... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

45 CFR 1183.32 - Equipment.

Science.gov (United States)

2010-10-01

... specifically permitted or contemplated by Federal statute. (4) When acquiring replacement equipment, the...) Management requirements. Procedures for managing equipment (including replacement equipment), whether... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no...

Obsolete pesticide storage sites and their POP release into the environment-an Armenian case study

Czech Academy of Sciences Publication Activity Database

Dvorská, Alice; Šír, M.; Honzajková, Z.; Komprda, J.; Čupr, P.; Petrlík, J.; Anakhasyan, E.; Simonyan, L.; Kubal, M.

2012-01-01

Roč. 19, č. 6 (2012), s. 1944-1952 ISSN 0944-1344 Institutional research plan: CEZ:AV0Z60870520 Keywords : Obsolete organochlorinated pesticides * Obsolete organochlorinated pesticides * Gradient sampling * Emissions * Diffusivity-based calculations * Health risks * Stockholm Convention Subject RIV: DI - Air Pollution ; Quality Impact factor: 2.618, year: 2012

45 CFR 1174.32 - Equipment.

Science.gov (United States)

2010-10-01

... contemplated by Federal statute. (4) When acquiring replacement equipment, the grantee or subgrantee may use... requirements. Procedures for managing equipment (including replacement equipment), whether acquired in whole or... original or replacement equipment acquired under a grant or subgrant is no longer needed for the original...

45 CFR 1157.32 - Equipment.

Science.gov (United States)

2010-10-01

... contemplated by Federal statute. (4) When acquiring replacement equipment, the grantee or subgrantee may use... requirements. Procedures for managing equipment (including replacement equipment), whether acquired in whole or... original or replacement equipment acquired under a grant or subgrant is no longer needed for the original...

Remotely operated replaceable process equipment

International Nuclear Information System (INIS)

Westendorf, H.

1987-01-01

The coupling process of pneumatic and electrical auxiliary lines of a pneumatic control pressure line in a large cell of the reprocessing plant is carried out, together with the coupling process of the connecting flange of the process equipment. The coupling places of the auxiliary lines, such as control or supply lines, are laid in the flange parts of the flanges to be connected. The pipe flange on the frame side remains flush with the connecting flange of the process equipment. (DG) [de

Handbook for replacement of process control systems in thermal power plants; Handbok - Utbytesbehov i kontrollsystem foer vaermekraftverk

Energy Technology Data Exchange (ETDEWEB)

Tuszynski, J. [Sydkraft Konsult AB, Malmoe (Sweden); Eriksson, Tage [Vattenfall Energisystem AB, Stockholm (Sweden)

1996-12-01

Modernization of control equipment in more complex power plants, such as thermal power plants, requires special attention due to the almost complete change-over to new computerised technology. The introduction of new technology gives rise to great changes in both the process control systems and in operation and maintenance routines. The change-over to computerised technology also causes lack of spare parts and service for older equipment. The older technology becomes obsolete due to the great advantages that comes with new technology. Therefore, the lifetime of control equipment is not only coupled to traditional ageing and wear, such as oxidation and fatigue of material, but also to the fact that the old equipment is getting out of date. It becomes more and more common that this out-of-date factor, rather than ageing, sets the limit for the useful life of the equipment. The Handbook for replacement of process control systems in thermal power plants is thought to be a first help for engineers and managers who has the responsibility for process control modernization. The Handbook points out the factors that determines the service life of the control equipment. It also suggests what information is required in order to take a decision on modernization. The Handbook at its present form constitutes a first approach that leaves room for an extension later on. Any request to expand the Handbook should be put forward to Vaermeforsk or its partners

Microcomputer-based equipment-control and data-acquisition system for fission-reactor reactivity-worth measurements

International Nuclear Information System (INIS)

McDowell, W.P.; Bucher, R.G.

1980-01-01

Material reactivity-worth measurements are one of the major classes of experiments conducted on the Zero Power research reactors (ZPR) at Argonne National Laboratory. These measurements require the monitoring of the position of a servo control element as a sample material is positioned at various locations in a critical reactor configuration. In order to guarantee operational reliability and increase experimental flexibility for these measurements, the obsolete hardware-based control unit has been replaced with a microcomputer based equipment control and data acquisition system. This system is based on an S-100 bus, dual floppy disk computer with custom built cards to interface with the experimental system. To measure reactivity worths, the system accurately positions samples in the reactor core and acquires data on the position of the servo control element. The data are then analyzed to determine statistical adequacy. The paper covers both the hardware and software aspects of the design

Microcomputer-based equipment-control and data-acquisition system for fission-reactor reactivity-worth measurements

Energy Technology Data Exchange (ETDEWEB)

McDowell, W.P.; Bucher, R.G.

1980-01-01

Material reactivity-worth measurements are one of the major classes of experiments conducted on the Zero Power research reactors (ZPR) at Argonne National Laboratory. These measurements require the monitoring of the position of a servo control element as a sample material is positioned at various locations in a critical reactor configuration. In order to guarantee operational reliability and increase experimental flexibility for these measurements, the obsolete hardware-based control unit has been replaced with a microcomputer based equipment control and data acquisition system. This system is based on an S-100 bus, dual floppy disk computer with custom built cards to interface with the experimental system. To measure reactivity worths, the system accurately positions samples in the reactor core and acquires data on the position of the servo control element. The data are then analyzed to determine statistical adequacy. The paper covers both the hardware and software aspects of the design.

20 CFR 437.32 - Equipment.

Science.gov (United States)

2010-04-01

... contemplated by Federal statute. (4) When acquiring replacement equipment, the grantee or subgrantee may use.... Procedures for managing equipment (including replacement equipment), whether acquired in whole or in part... 20 Employees' Benefits 2 2010-04-01 2010-04-01 false Equipment. 437.32 Section 437.32 Employees...

High flux testing reactor Petten. Replacement of the reactor vessel and connected components. Overall report

International Nuclear Information System (INIS)

Chrysochoides, N.G.; Cundy, M.R.; Von der Hardt, P.; Husmann, K.; Swanenburg de Veye, R.J.; Tas, A.

1985-01-01

The project of replacing the HFR originated in 1974 when results of several research programmes confirmed severe neutron embrittlement of aluminium alloys suggesting a limited life of the existing facility. This report contains the detailed chronology of events concerning preparation and execution of the replacement. After a 14 months' outage the reactor resumed routine operation on 14th February, 1985. At the end of several years of planning and preparation the reconstruction proceded in the following steps: unloading of the old core, decay of short-lived radioactivity in December 1983, removal of the old tank and of its peripheral equipment in January-February 1984, segmentation and waste disposal of the removed components in March-April, decontamination of the pools, bottom penetration overhauling in May-June, installation of the new tank and other new components in July-September, testing and commissioning, including minor modifications in October-December, and, trials runs and start-up preparation in January-February 1985. The new HFR Petten features increased and improved experimental facilities. Among others the obsolete thermal columns was replaced by two high flux beam tubes. Moreover the new plant has been designed for future increases of reactor power and neutron fluxes. For the next three to four years the reactor has to cope with a large irradiation programme, claiming its capacity to nearly 100%

34 CFR 74.34 - Equipment.

Science.gov (United States)

2010-07-01

... as program income. (e) When acquiring replacement equipment, the recipient may use the equipment to... replacement equipment subject to the approval of the Secretary. (f) The recipient's property management... 34 Education 1 2010-07-01 2010-07-01 false Equipment. 74.34 Section 74.34 Education Office of the...

41 CFR 105-71.132 - Equipment.

Science.gov (United States)

2010-07-01

.... (4) When acquiring replacement equipment, the grantee or subgrantee may use the equipment to be... managing equipment (including replacement equipment), whether acquired in whole or in part with grant funds... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Equipment. 105-71.132...

40 CFR 31.32 - Equipment.

Science.gov (United States)

2010-07-01

... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Equipment. 31.32 Section 31.32...

14 CFR 1273.32 - Equipment.

Science.gov (United States)

2010-01-01

... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 14 Aeronautics and Space 5 2010-01-01 2010-01-01 false Equipment. 1273.32 Section 1273.32...

29 CFR 1470.32 - Equipment.

Science.gov (United States)

2010-07-01

... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 29 Labor 4 2010-07-01 2010-07-01 false Equipment. 1470.32 Section 1470.32 Labor Regulations...

38 CFR 43.32 - Equipment.

Science.gov (United States)

2010-07-01

... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 38 Pensions, Bonuses, and Veterans' Relief 2 2010-07-01 2010-07-01 false Equipment. 43.32 Section...

75 FR 17857 - Removal of Obsolete References to Herbicides Containing Dioxin

Science.gov (United States)

2010-04-08

... Herbicides Containing Dioxin AGENCY: Department of Veterans Affairs. ACTION: Final rule. SUMMARY: The... health effects of exposure to herbicides containing dioxin and radiation to remove the obsolete references to herbicides containing dioxin. This final rule reflects changes made by the Agent Orange Act of...

13 CFR 143.32 - Equipment.

Science.gov (United States)

2010-01-01

... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Equipment. 143.32 Section 143.32...

32 CFR 33.32 - Equipment.

Science.gov (United States)

2010-07-01

... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 32 National Defense 1 2010-07-01 2010-07-01 false Equipment. 33.32 Section 33.32 National Defense...

45 CFR 92.32 - Equipment.

Science.gov (United States)

2010-10-01

... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 45 Public Welfare 1 2010-10-01 2010-10-01 false Equipment. 92.32 Section 92.32 Public Welfare...

15 CFR 24.32 - Equipment.

Science.gov (United States)

2010-01-01

... awarding agency. (d) Management requirements. Procedures for managing equipment (including replacement... return. (e) Disposition. When original or replacement equipment acquired under a grant or subgrant is no... 15 Commerce and Foreign Trade 1 2010-01-01 2010-01-01 false Equipment. 24.32 Section 24.32...

10 CFR 830 Major Modification Determination for Emergency Firewater Injection System Replacement

International Nuclear Information System (INIS)

Duckwitz, Noel

2011-01-01

The continued safe and reliable operation of the ATR is critical to the Department of Energy (DOE) Office of Nuclear Energy (NE) mission. While ATR is safely fulfilling current mission requirements, a variety of aging and obsolescence issues challenge ATR engineering and maintenance personnel's capability to sustain ATR over the long term. First documented in a series of independent assessments, beginning with an OA Environmental Safety and Health Assessment conducted in 2003, the issues were validated in a detailed Material Condition Assessment (MCA) conducted as a part of the ATR Life Extension Program in 2007. Accordingly, near term replacement of aging and obsolescent original ATR equipment has become important to ensure ATR capability in support of NE's long term national missions. To that end, a mission needs statement has been prepared for a non-major system acquisition which is comprised of three interdependent sub-projects. The first project will replace the existent diesel-electrical bus (E-3), switchgear, and the fifty year old antiquated marine diesels with commercial power that is backed with safety-related emergency diesel generators (EDGs), switchgear, and uninterruptible power supply. The second project will replace the four, obsolete, original primary coolant pumps and motors. The third project, the subject of this major modification determination, will replace the current emergency firewater injection system (EFIS). The replacement water injection system will function as the primary emergency water injection system with the EFIS being retained as a defense-in-depth backup. Completion of this and the two other age-related projects (replacement of the ATR diesel bus (E-3) and switchgear and replacement of the existent aged primary coolant pumps and motors) will resolve major age-related operational issues plus make a significant contribution in sustaining the ATR safety and reliability profile. The major modification criteria evaluation of the

7 CFR 3015.169 - Equipment management requirements.

Science.gov (United States)

2010-01-01

... following requirements (including replacement equipment) until such actions as transfer, replacement or... transfer, replacement, or disposal of the equipment. (b) Every two years, at a minimum, a physical... 7 Agriculture 15 2010-01-01 2010-01-01 false Equipment management requirements. 3015.169 Section...

The influence of residents' behaviour on waste electrical and electronic equipment collection effectiveness.

Science.gov (United States)

Nowakowski, Piotr

2016-11-01

Government agencies have implemented regulations to reduce the volume of waste electrical and electronic equipment to protect the environment and encourage recycling. The effectiveness of systems through which waste electrical and electronic equipment is collected and recycled depends on (a) the development and operation of new programmes to process this material and (b) on information dissemination programmes aimed at manufacturers, retail sellers, and the consuming public. This study analyses these two elements. The main focus is to better understand household residents' behaviour in regards to the proper methods of handling waste electrical and electronic equipment and possible storage of the obsolete equipment that brings disturbances with collection of the waste equipment. The study explores these issues depending on size of municipality and the household residents' knowledge about legal methods of post-consumer management of waste electrical and electronic equipment in Poland, where the collection rate of that type of waste is about 40% of the total mass of waste electrical and electronic equipment appearing in the market.The research was informed by various sources of information, including non-government organisations, Inspectorate of Environmental Protection and Central Statistics Office in Poland, questionnaires, and interviews with the household residents. The questionnaires were distributed to daytime and vocational students from different universities and the customers of an electronic equipment superstore. The results show that a resident's behaviour in regards to the handling of obsolete waste electrical and electronic equipment can significantly reduce the collection rate, especially when the waste is discarded improperly - mixed with municipal waste or sold in scrapyards. It is possible to identify points that are necessary to be improved to achieve a higher collection rate. © The Author(s) 2016.

The replace repair decision for heavy equipment.

Science.gov (United States)

2004-01-01

The fleet of equipment operated by the Virginia Department of Transportation (VDOT) constitutes a large investment, on the order of half a billion dollars. A means of identifying earlier and more accurately those pieces of equipment whose timely repl...

Will technology make shelters obsolete

International Nuclear Information System (INIS)

Haaland, C.M.; Chester, C.V.

1981-01-01

The fears and hopes that shelters for civil defense might be made obsolete by technology fall along diametrically opposed paths. Along the pessimistic direction is the fear that strategic offensive weapons have become so numerous and terrible that no shelter program is worthwhile. This fear has been nurtured by the US deterrence policy of Mutual Assured Destruction (MAD), about which we will say more in the first part of this article. In the opposite direction along the optimistic path is the hope that active defensive technology will become so good that shelters will be unnecessary. Very few hold this viewpoint today, although there was a time during the development of antiballistic missiles (ABM) when such a hope was common. The recent emphasis on research and development of laser- and particle-beam weapons has again raised some hopes that defense against strategic missiles may become effective. Researchers will discuss the impact of defensive technology on shelters in Part II of this article

Adaptive Control System of Hydraulic Pressure Based on The Mathematical Modeling

Science.gov (United States)

Pilipenko, A. V.; Pilipenko, A. P.; Kanatnikov, N. V.

2016-04-01

In this paper, the authors highlight the problem of replacing an old heavy industrial equipment, and offer the replacement of obsolete control systems on the modern adaptive control system, which takes into account changes in the hydraulic system of the press and compensates them with a corrective action. The proposed system can reduce a water hammer and thereby increase the durability of the hydraulic system and tools.

The cost function for the preventive - maintenance replacement problem

OpenAIRE

Vilaplana, Jose Perez

1994-01-01

Let a discounted continuous review preventive-maintenance replacement model be such that its total discounted cost is given by means of two functional equations. We assume that downtime is caused by equipment breakdowns, and the length of a given downtime is the time necessary to repair the equipment and set it back in operation. The periodic preventive replacement policy is to replace the equipment by a new identical equipment when service age X is reached, or when the equipment ...

Strategic provisioning of replacement parts for CANDU power plants

International Nuclear Information System (INIS)

Mizuno, G.; Tume, P.; Prentice, J.

2000-01-01

Provisioning of replacement parts and management of critical spares are key factors in optimizing maintenance programs for CANDU power plants. With a view to supply assurance, Atomic Energy Canada Limited (AECL) has created a Spare Parts Branch (SPB) to provide a clear pipeline from the client to the delivered replacement part(s). SPB provides the client with assured access to a qualified supplier database, computer aided design, engineering and manufacturing services and material upgrades and design registration through the authorized inspection agency. The AECL spare parts strategic provisioning service plan that has four thrusts: 1) the efficient delivery of cost-effective replacement parts; 2) obsolete parts resolution; 3) a website that will provide our clients with real-time access to replacement part data; and 4) inventory recovery opportunities. Thrusts one and two are actively ensuring plant maintenance for on-shore and off-shore CANDU clients. Thrusts three and four are longer-term commitments. This paper will explore these thrusts in the context of our CANDU business practices. (author)

Changing nature of equipment and parts qualification

International Nuclear Information System (INIS)

Bucci, R.M.

1988-01-01

Ideally, the original supplier of a piece of nuclear safety-related equipment has performed a qualification program and will continue to support that equipment throughout the lifetime of the nuclear power plants in which in equipment is installed. The supplier's nuclear quality assurance program will be maintained and he will continue to offer all necessary replacement parts. These parts will be identical to the original parts, certified to the original purchase order requirements, and the parts will be offered at competitive prices. Due to the changing nature of the nuclear plant equipment market, however, one or more of those ideal features are frequently unavailable when safety-related replacement equipment or parts are required. Thus, the process of equipment and parts qualification has had to adjust in order to ensure obtaining qualified replacements when needed. This paper presents some new directions taken in the qualification of replacement equipment and parts to meet changes in the marketplace

ISS qualified thermal carrier equipment

Science.gov (United States)

Deuser, Mark S.; Vellinger, John C.; Jennings, Wm. M.

2000-01-01

Biotechnology is undergoing a period of rapid and sustained growth, a trend which is expected to continue as the general population ages and as new medical treatments and products are conceived. As pharmaceutical and biomedical companies continue to search for improved methods of production and, for answers to basic research questions, they will seek out new avenues of research. Space processing on the International Space Station (ISS) offers such an opportunity! Space is rapidly becoming an industrial laboratory for biotechnology research and processing. Space bioprocessing offers exciting possibilities for developing new pharmaceuticals and medical treatments, which can be used to benefit mankind on Earth. It also represents a new economic frontier for the private sector. For over eight years, the thermal carrier development team at SHOT has been working with government and commercial sector scientists who are conducting microgravity experiments that require thermal control. SHOT realized several years ago that the hardware currently being used for microgravity thermal control was becoming obsolete. It is likely that the government, academic, and industrial bioscience community members could utilize SHOT's hardware as a replacement to their current microgravity thermal carrier equipment. Moreover, SHOT is aware of several international scientists interested in utilizing our space qualified thermal carrier. SHOT's economic financing concept could be extremely beneficial to the international participant, while providing a source of geographic return for their particular region. Beginning in 2000, flight qualified thermal carriers are expected to be available to both the private and government sectors. .

75 FR 16001 - New Animal Drugs; Removal of Obsolete and Redundant Regulations

Science.gov (United States)

2010-03-31

... drug-resistant bacteria associated with these animals, was obsolete as FDA had a new strategy and... on any approved new animal drugs, or to cause any approved new animal drug to lose its marketing ability or experience a loss of sales. C. Regulatory Flexibility Analysis The Regulatory Flexibility Act...

40 CFR 63.1363 - Standards for equipment leaks.

Science.gov (United States)

2010-07-01

... the replacement equipment and the actual date of delivery of the replacement equipment. (E) The date... heavy liquid service. Information, data, and analysis used to determine that a piece of equipment or... 40 Protection of Environment 11 2010-07-01 2010-07-01 true Standards for equipment leaks. 63.1363...

A Low-Cost Vehicle Anti-Theft System Using Obsolete Smartphone

OpenAIRE

Liu, Bang; Liu, Nianbo; Chen, Guihai; Dai, Xili; Liu, Ming

2018-01-01

In modern society, vehicle theft has become an increasing problem to the general public. Deploying onboard anti-theft systems could relieve this problem, but it often requires extra investment for vehicle owners. In this paper, we propose the idea of PhoneInside, which does not need a special device but leverages an obsolete smartphone to build a low-cost vehicle anti-theft system. After being fixed in the vehicle body with a car charger, the smartphone can detect vehicle movement and adaptiv...

UK survey of occupational therapist's and physiotherapist's experiences and attitudes towards hip replacement precautions and equipment.

Science.gov (United States)

Smith, T O; Sackley, C M

2016-05-25

Total hip replacement (THR) is one of the most common orthopaedic procedures in the United Kingdom (UK). Historically, people following THR have been provided with hip precautions and equipment such as: raised toilet seats and furniture rises, in order to reduce the risks of dislocation post-operation. The purpose of this study was to determine current practices in the provision of these interventions in the UK for people following primary THR. A 27-question, self-administered online survey was developed and distributed to UK physiotherapists and occupational therapists involved in the management of people following primary THR (target respondents). The survey included questions regarding the current practices in the provision of equipment and hip precautions for THR patients, and physiotherapist's and occupational therapist's attitudes towards these practices. The survey was disseminated through print and web-based/social media channels. 170 health professionals (87 physiotherapists and 83 occupational therapists), responded to the survey. Commonly prescribed equipment in respondent's health trusts were raised toilet seats (95 %), toilet frames and rails (88 %), furniture raises (79 %), helping hands/grabbers (77 %), perching stools (75 %) and long-handled shoe horns (75 %). Hip precautions were routinely prescribed by 97 % of respondents. Hip precautions were most frequently taught in a pre-operative group (52 % of respondents). Similarly equipment was most frequently provided pre-operatively (61 % respondents), and most commonly by occupational therapists (74 % respondents). There was variability in the advice provided on the duration of hip precautions and equipment from up to 6 weeks post-operatively to life-time usage. Current practice on hip precautions and provision of equipment is not full representative of clinician's perceptions of best care after THR. Future research is warranted to determine whether and to whom hip precautions and equipment

32 CFR 34.21 - Real property and equipment.

Science.gov (United States)

2010-07-01

... original equipment as trade-in or sell it and use the proceeds to offset the costs of the replacement... request approval to use equipment as trade-in or offset for replacement equipment (see paragraph (e)(1)(i... 32 National Defense 1 2010-07-01 2010-07-01 false Real property and equipment. 34.21 Section 34.21...

Is CALL Obsolete? Language Acquisition and Language Learning Revisited in a Digital Age

Science.gov (United States)

Jarvis, Huw; Krashen, Stephen

2014-01-01

In this article, Huw Jarvis and Stephen Krashen ask "Is CALL Obsolete?" When the term CALL (Computer-Assisted Language Learning) was introduced in the 1960s, the language education profession knew only about language learning, not language acquisition, and assumed the computer's primary contribution to second language acquisition…

A single - item replacement decision model for repairable spare ...

African Journals Online (AJOL)

In this paper, we present an analytical method for determining spare parts replacement over an infinite planning horizon. (The objective is to minimize the total system cost). We develop an exact and simple method for determining the time for equipment replacement or making decision about when to replace equipments, ...

7 CFR 3015.172 - Federal share of real property, equipment, and supplies.

Science.gov (United States)

2010-01-01

... equipment. To calculate the Federal share of replacement equipment the following procedures shall be...: Determine the percentage of the replacement equipment's costs that was covered by the amount received for... the step 2 percentage. (4) Step 4: If an additional outlay for the replacement equipment was charged...

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

International Nuclear Information System (INIS)

Nordling, Anna; Haakansson, Goeran

2012-01-01

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

Remotely operated replaceable process equipment. Fernbedient austauschbare Prozessapparatur

Energy Technology Data Exchange (ETDEWEB)

Westendorf, H.

1987-07-23

The coupling process of pneumatic and electrical auxiliary lines of a pneumatic control pressure line in a large cell of the reprocessing plant is carried out, together with the coupling process of the connecting flange of the process equipment. The coupling places of the auxiliary lines, such as control or supply lines, are laid in the flange parts of the flanges to be connected. The pipe flange on the frame side remains flush with the connecting flange of the process equipment.

Study Of Robotic Replacement Of Equipment Modules

Science.gov (United States)

Backes, Paul G.; Tso, Kam S.

1992-01-01

Report discusses issues pertaining to control of single-arm robotic manipulator to remove and install interchangeable equipment modules. Presents preliminary control strategy intended to guide development of control algorithms, along with analyses of problems arising in implementing strategy.

77 FR 60619 - Removal of Obsolete Regulation: Use of the Centennial of Flight Commission Name

Science.gov (United States)

2012-10-04

... Removal of Obsolete Regulation: Use of the Centennial of Flight Commission Name AGENCY: National... section 1204. 506 entitled ``Delegation of Authority to License the Use of the Centennial of Flight Commission Name.'' Section 506, Delegation of Authority to License the Use of the Centennial of Flight...

Equipment Obsolescence Management Program

Energy Technology Data Exchange (ETDEWEB)

Redmond, J.

2014-07-01

Nuclear Power Plant (NPP) Operators are challenged with securing reliable supply channels for safety related equipment due to equipment obsolescence. Many Original Equipment Manufacturers (OEMs) have terminated production of spare parts and product life-cycle support. The average component life cycles are much shorter than the NPP design life, which means that replacement components and parts for the original NPP systems are not available for the complete design life of the NPPs. The lack or scarcity of replacement parts adversely affects plant reliability and ultimately the profitability of the affected NPPs. This problem is further compounded when NPPs pursue license renewal and approval for plant-life extension. A reliable and predictable supply of replacement co components is necessary for NPPs to remain economically competitive and meet regulatory requirements and guidelines. Electrical and I and C components, in particular, have short product life cycles and obsolescence issues must be managed pro actively and not reactively in order to mitigate the risk to the NPP to ensure reliable and economic NPP operation. (Author)

Replacement Saltwell Pumping System Document Bibliography

International Nuclear Information System (INIS)

BELLOMY, J.R.

2000-01-01

This document bibliography is prepared to identify engineering documentation developed during the design of the Replacement Saltwell Pumping System. The bibliography includes all engineering supporting documents and correspondence prepared prior to the deployment of the system in the field. All documents referenced are available electronically through the Records Management Information System (RMIS). Major components of the Replacement Saltwell Pumping System include the Sundyne Canned Motor Pump, the Water Filter Skid, the Injection Water Skid and the Backflow Preventer Assembly. Drawing H-14-104498 provides an index of drawings (fabrication details, PandIDs, etc.) prepared to support development of the Replacement Saltwell Pumping System. Specific information pertaining to new equipment can be found in Certified Vendor Information (CVI) File 50124. This CVI file has been established specifically for new equipment associated with the Replacement Saltwell Pumping System

30 CFR 75.504 - Permissibility of new, replacement, used, reconditioned, additional, and rebuilt electric face...

Science.gov (United States)

2010-07-01

... STANDARDS-UNDERGROUND COAL MINES Electrical Equipment-General § 75.504 Permissibility of new, replacement... new, replacement, used, reconditioned, and additional electric face equipment used in any mine..., unless in the opinion of the Secretary, such equipment or necessary replacement parts are not available...

7 CFR 550.38 - Equipment.

Science.gov (United States)

2010-01-01

... Regulations of the Department of Agriculture (Continued) AGRICULTURAL RESEARCH SERVICE, DEPARTMENT OF AGRICULTURE GENERAL ADMINISTRATIVE POLICY FOR NON-ASSISTANCE COOPERATIVE AGREEMENTS Management of Agreements... Agency, the Cooperator shall use the equipment to be replaced as trade-in or sell the equipment and use...

Recycling-oriented characterization of small waste electrical and electronic equipment

International Nuclear Information System (INIS)

Chancerel, Perrine; Rotter, Susanne

2009-01-01

As a result of the continuous change in the design and function of consumer electrical and electronic products, the mechanical and material properties of the obsolete products, called waste electric and electronic equipment (WEEE), are highly variable. The variability within WEEE is explained by the number of different appliances, and the heterogeneity in composition of any given appliance. This paper reports on an extended investigation of the properties of WEEE, in particular small appliances. The investigation focuses on the analysis of the composition of about 700 single appliances. Firstly, analytical methods to characterize the waste equipment are described. The results of the experimental analyses show that the mechanical properties, the material composition, the polymer composition and the chemical composition of WEEE vary not only between equipment types with different functions, but also between single appliances within one equipment type. Data on hazardous and valuable substances in selected equipment types are presented. Using detailed data on the composition of individual appliances to calculate rates of recovery for assumed recycling processes demonstrates that the performance of recycling processes depends strongly on the composition of WEEE. Recycling-oriented characterization is, therefore, a systematic approach to support the design and the operation of recycling processes.

Fleet replacement modeling : final report, July 2009.

Science.gov (United States)

2009-07-01

This project focused on two interrelated areas in equipment replacement modeling for fleets. The first area was research-oriented and addressed a fundamental assumption in engineering economic replacement modeling that all assets providing a similar ...

Replacement of the Advanced Test Reactor control room

International Nuclear Information System (INIS)

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

1989-01-01

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

Replacement of the Advanced Test Reactor control room

International Nuclear Information System (INIS)

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

1990-01-01

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

Plant process computer replacements - techniques to limit installation schedules and costs

International Nuclear Information System (INIS)

Baker, M.D.; Olson, J.L.

1992-01-01

Plant process computer systems, a standard fixture in all nuclear power plants, are used to monitor and display important plant process parameters. Scanning thousands of field sensors and alarming out-of-limit values, these computer systems are heavily relied on by control room operators. The original nuclear steam supply system (NSSS) vendor for the power plant often supplied the plant process computer. Designed using sixties and seventies technology, a plant's original process computer has been obsolete for some time. Driven by increased maintenance costs and new US Nuclear Regulatory Commission regulations such as NUREG-0737, Suppl. 1, many utilities have replaced their process computers with more modern computer systems. Given that computer systems are by their nature prone to rapid obsolescence, this replacement cycle will likely repeat. A process computer replacement project can be a significant capital expenditure and must be performed during a scheduled refueling outage. The object of the installation process is to install a working system on schedule. Experience gained by supervising several computer replacement installations has taught lessons that, if applied, will shorten the schedule and limit the risk of costly delays. Examples illustrating this technique are given. This paper and these examples deal only with the installation process and assume that the replacement computer system has been adequately designed, and development and factory tested

Beyond the glitz of new equipment

International Nuclear Information System (INIS)

Stolberg, H.O.; Nahmias, C.

2001-01-01

Canadian radiologists were informed by the press on Mar. 17, 2001, about an important initiative of their national organization. The CAR had commissioned a Montreal law firm to provide a legal opinion about the use of 'obsolete equipment'. The lawyer of the law firm opined that 'it is imperative that the patient be advised and understand the risks and uncertainties associated with the reliability of such an examination'. The 5-page legal opinion (available at www.car.ca) also recommended that radiologists inform patients that they should consider shopping around for a hospital or clinic with newer machines, even if it means travelling out of the country. When summarizing the legal advice for the media, the Chief Executive Officer of the CAR said radiologists should advise patients if better equipment is available in other facilities, including 'private facilities', or in other jurisdictions, such as the United States. These developments should be of great concern to Canadian radiologists who are well aware of the problems associated with aging equipment and the lack of and limited access to newer imaging modalities. The legal initiative of the CAR, however, makes it imperative for individual radiologists to provide comments and for the CAR executive to answer a number of questions and address a number of priorities, including the following. (author)

B Plant process piping replacement feasibility study

International Nuclear Information System (INIS)

Howden, G.F.

1996-01-01

Reports on the feasibility of replacing existing embedded process piping with new more corrosion resistant piping between cells and between cells and a hot pipe trench of a Hanford Site style canyon facility. Provides concepts for replacement piping installation, and use of robotics to replace the use of the canyon crane as the primary means of performing/supporting facility modifications (eg, cell lining, pipe replacement, equipment reinstallation) and operational maintenenace

Large-component handling equipment and its use

International Nuclear Information System (INIS)

Krieg, S.A.; Swannack, D.L.

1983-01-01

The Fast Flux Test Facility (FFTF) reactor systems have special requirements for component replacements during maintenance servicing. Replacement operations must address handling of equipment within shielded metal containers while maintaining an inert atmosphere to prevent reaction of sodium with air. Plant identification of a failed component results in selecting and assembling the maintenance cask and equipment transport system for transfer from the storage facility to the Reactor Containment Building (RCB). This includes a proper diameter and length cask, inert atmosphere control consoles, component lift fixture and support structure for interface with the facility area surrounding the component. This equipment is staged in modular groups in the Reactor Service Building for transfer through the equipment airlock to the containment interior. The failed component is generally prepared for replacement by installation of the special lifting fixture attachment. Assembly of the cask support structure is performed over the component position on the containment building operating floor. The cask and shroud from the reactor interface are inerted after all manual service connections and handling attachments are completed. The component is lifted from the reactor and into the cask interior through a floor valve which is then closed to isolate the component reactor port. The cask with sodium wetted component is transferred to a service/repair location, either within containment or outside, to the Maintenance Facility cleaning and repair area. The complete equipment and handling operations for replacement of a large reactor component are described

Unique aspects of downhill ski injuries part 1: epidemiology and equipment.

Science.gov (United States)

Buck, P G; Sophocles, A M; Beckenbauch, R D

1982-03-01

Skiing is an exciting sport with a significant potential /or serious injury. This potential for injury can be minimized but never entirely eliminated by modern safety equipment.Upper extremity injuries have become relatively more common as the incidence of lower extremity injuries has decreased. Ankle and foot injuries have become infrequent since the advent of the rigid plastic boot, while the incidence of knee injuries has remained essentially constant.Three major mechanisms of injury to the lower extremity include external rotation and abduction, forward fall, and internal rotation. Each mechanism can produce a distinctive set of injured structures.The "skier at risk" is characterized by a lower level of ability, lighter weight, and extremes of age. Injuries can be minimized by purchasing good quality equipment and maintaining it properly; discarding obsolete equipment; using ski brakes, antifriction devices and pistol grip poles; using multirelease bindings for beginners or intermediates; good physical conditioning; taking ski lessons and coupling this with skiing experience; and skiing in control and using common sense on the slopes.Areas which need the most improvement in equipment design include multi-release bindings suitable for all skiers and children's boots. Copyright 2013, SLACK Incorporated.

Choledochoduodenostomy in the Management of Common Duct Stones or Associated Pathology – An Obsolete Method?

Directory of Open Access Journals (Sweden)

António Castro Mendes de Almeida

1996-01-01

Full Text Available Choledochoduodenostomy (CDD has been reported as a more effective treatment of CBD stones than T-tube drainage but it is regarded as a last resort or obsolete therapeutic method due to fears of higher mobidity, cholangitis, “sump” syndrome and liver dysfunction. We aimed to assess the aforementioned issues analyzing prospectively our experience from 1976 through Dec.92.

Renewal of radiological equipment.

Science.gov (United States)

2014-10-01

In this century, medical imaging is at the heart of medical practice. Besides providing fast and accurate diagnosis, advances in radiology equipment offer new and previously non-existing options for treatment guidance with quite low morbidity, resulting in the improvement of health outcomes and quality of life for the patients. Although rapid technological development created new medical imaging modalities and methods, the same progress speed resulted in accelerated technical and functional obsolescence of the same medical imaging equipment, consequently creating a need for renewal. Older equipment has a high risk of failures and breakdowns, which might cause delays in diagnosis and treatment of the patient, and safety problems both for the patient and the medical staff. The European Society of Radiology is promoting the use of up-to-date equipment, especially in the context of the EuroSafe Imaging Campaign, as the use of up-to-date equipment will improve quality and safety in medical imaging. Every healthcare institution or authority should have a plan for medical imaging equipment upgrade or renewal. This plan should look forward a minimum of 5 years, with annual updates. Teaching points • Radiological equipment has a definite life cycle span, resulting in unavoidable breakdown and decrease or loss of image quality which renders equipment useless after a certain time period.• Equipment older than 10 years is no longer state-of-the art equipment and replacement is essential. Operating costs of older equipment will be high when compared with new equipment, and sometimes maintenance will be impossible if no spare parts are available.• Older equipment has a high risk of failure and breakdown, causing delays in diagnosis and treatment of the patient and safety problems both for the patient and the medical staff.• Every healthcare institution or authority should have a plan for medical imaging equipment upgrade or replacement. This plan should look forward a

45 CFR 95.707 - Equipment management and disposition.

Science.gov (United States)

2010-10-01

... participation in the costs of replacement equipment shall be limited to the additional outlay. (4) If the... 45 Public Welfare 1 2010-10-01 2010-10-01 false Equipment management and disposition. 95.707... PROGRAMS) Equipment Acquired Under Public Assistance Programs § 95.707 Equipment management and disposition...

7 CFR 3015.168 - Disposal of equipment.

Science.gov (United States)

2010-01-01

..., DEPARTMENT OF AGRICULTURE UNIFORM FEDERAL ASSISTANCE REGULATIONS Property § 3015.168 Disposal of equipment. When original or replacement equipment is no longer to be used in projects or programs currently or... 7 Agriculture 15 2010-01-01 2010-01-01 false Disposal of equipment. 3015.168 Section 3015.168...

40 CFR 63.424 - Standards: Equipment leaks.

Science.gov (United States)

2010-07-01

....424 Standards: Equipment leaks. (a) Each owner or operator of a bulk gasoline terminal or pipeline... location of all equipment in gasoline service at the facility. (c) Each detection of a liquid or vapor leak... replacement of leaking equipment shall be completed within 15 calendar days after detection of each leak...

Clarification of radiation-control regulations for diagnostic x-ray equipment

International Nuclear Information System (INIS)

1989-03-01

The Office of Compliance and Surveillance of the Center for Devices and Radiological Health (CDRH) has received many requests for interpretation of the Federal regulations that relate to diagnostic x-ray equipment. Responses to these requests were originally issued as FDA Compliance Policy Guides, industry-wide letters, and letters to individuals. The document is a compilation of those responses that remain applicable. Guides or opinions that have been withdrawn or are now obsolete because they have been incorporated into the regulations are not included. The document consists of two sections: the General section, which contains information of a general nature; and the Specific section, which contains information specific to particular sections of the Federal Performance Standard for Diagnostic X-ray Equipment (21 CFR 1020.30-32). When the term 'Revised Language' appears in an item heading, it indicates English grammar correction; the term 'Revised' indicates an updated version of the original clarification

Development of an approach to facilitate optimal equipment replacement.

Science.gov (United States)

1999-10-01

The principle objective of this study was to develop a procedure using available departmental data on operation, maintenance and replacement costs to provide the Louisiana Department of Transportation and Development with guidelines for the identific...

24 CFR 965.306 - Energy conservation equipment and practices.

Science.gov (United States)

2010-04-01

... Measures § 965.306 Energy conservation equipment and practices. In purchasing original or, when needed, replacement equipment, PHAs shall acquire only equipment that meets or exceeds the minimum efficiency... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Energy conservation equipment and...

Optimal replacement time estimation for machines and equipment based on cost function

Directory of Open Access Journals (Sweden)

J. Šebo

2013-01-01

Full Text Available The article deals with a multidisciplinary issue of estimating the optimal replacement time for the machines. Considered categories of machines, for which the optimization method is usable, are of the metallurgical and engineering production. Different models of cost function are considered (both with one and two variables. Parameters of the models were calculated through the least squares method. Models testing show that all are good enough, so for estimation of optimal replacement time is sufficient to use simpler models. In addition to the testing of models we developed the method (tested on selected simple model which enable us in actual real time (with limited data set to indicate the optimal replacement time. The indicated time moment is close enough to the optimal replacement time t*.

30 CFR 57.4203 - Extinguisher recharging or replacement.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Extinguisher recharging or replacement. 57.4203 Section 57.4203 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND... Prevention and Control Firefighting Equipment § 57.4203 Extinguisher recharging or replacement. Fire...

30 CFR 56.4203 - Extinguisher recharging or replacement.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Extinguisher recharging or replacement. 56.4203 Section 56.4203 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND... Prevention and Control Firefighting Equipment § 56.4203 Extinguisher recharging or replacement. Fire...

Fission chamber assembly and matching preamplifier

International Nuclear Information System (INIS)

DeLorenzo, J.T.

1982-12-01

The preamplifier for the wide-range counting channel at the High Flux Isotope Reactor was redesigned. This new design incorporates current state-of-the-art components as replacements for the obsolete components of the earlier design. To accommodate the new design, a test and maintenance manual was prepared for use by qualified technicians and field engineers. The test procedures described herein do not require special test equipment and have been successfully applied to the prototype design

Equipment improvements for performance enhancement

International Nuclear Information System (INIS)

Gaestel, P.; Guesnon, H.; Sauze, G.

1994-01-01

In order to enhance the reactor availability, several improvements on reactor equipment have been developed: design optimization for stator maintenance replacement in the main alternator; adjustment modification of stator coils in the main alternator for an easier maintenance; improvement of the fuel handling line (pole crane, transfer equipment, loading machine); development of a loose part trapping system in the steam generator secondary circuit. 1 tab

Measurement of secondary emissions during laser cutting of steel equipments

Energy Technology Data Exchange (ETDEWEB)

Pilot, Guy [Institut de Radioprotection et de Surete Nucleaire, BP 68, 91192 Gif-sur-Yvette Cedex (France)], E-mail: guy.pilot@irsn.fr; Fauvel, Sylvain [Institut de Radioprotection et de Surete Nucleaire, BP 68, 91192 Gif-sur-Yvette Cedex (France); Gosse, Xavier [AREVA NC, Centre de Marcoule, 30200 Bagnols-sur-Ceze Cedex (France); Dinechin, Guillaume de [Commissariat a l' Energie Atomique, DEN/DM2S/SEMT, Saclay, Bat. 611, 91191 Gif-sur-Yvette Cedex (France); Vernhet, Didier [Commissariat a l' Energie Atomique, DEN/VRH/UMODD, Centre de Valrho, BP 17171, 20207 Bagnols-sur-Ceze Cedex (France)

2008-08-15

In order to dismantle some equipments of an obsolete reprocessing plant in Marcoule, studies were carried out by IRSN (Institut de Radioprotection et de Surete Nucleaire)/DSU/SERAC in cooperation with CEA (power laser group) on the laser cutting of steel structures, on the request of AREVA NC/Marcoule (UP1 dismantling project manager) and CEA/UMODD (UP1 dismantling owner). These studies were aimed at: {center_dot}quantifying and characterizing the secondary emissions produced by Nd-YAG laser cutting of Uranus 65 steel pieces and examining the influence of different parameters, {center_dot}qualifying a prefiltration technique and particularly an electrostatic precipitator, {center_dot}comparing the Nd-YAG laser used with other cutting tools previously studied especially on aerosol production and aerosol size distribution.

The New START Treaty: a necessary or obsolete treaty?

International Nuclear Information System (INIS)

Ekovich, Steven

2012-01-01

In a first part, the author evokes the discussions between the Republicans and the Democrats about the fact that President Obama said to President Medvedev he would have more flexibility to negotiate with Russia after the elections of 2012, whereas there is some controversy about the importance of US antimissile defence in terms of national security when Russia keeps on supporting dangerous states like Syria, North Korea and Iran. In a second part, he briefly recalls the objectives and content of the previous START treaties, outlines that START II is already obsolete, that which lead to a new approach called New START by the White House. Then, while noticing critics and evoking other treaties, he discusses the arguments for or against such a new treaty which is perceived as either only cosmetic or decisive. He comments ambiguities, ulterior motives, perceptions and strategic approaches of the different actors whether they are Russians or Americans. He finally outlines some measures of this New Treaty which may jeopardize positive expectations regarding the reduction of strategic weapons and the antimissile defence

Guideline for the seismic technical evaluation of replacement items for nuclear power plants

International Nuclear Information System (INIS)

Harris, S.P.; Cushing, R.W.; Johnson, H.W.; Abeles, J.M.

1993-02-01

Seismic qualification for equipment originally installed in nuclear power plants was typically performed by the original equipment suppliers or manufactures (OES/OEM). Many of the OES/OEM no longer maintain quality assurance programs with adequate controls for supplying nuclear equipment. Utilities themselves must provide reasonable assurance in the continued seismic adequacy of such replacement items. This guideline provides practical, cost-effective techniques which can be used to provide reasonable assurance that replacement items will meet seismic performance requirements necessary to maintain the seismic design basis of commercial nuclear power plants. It also provides a method for determining when a seismic technical evaluation of replacement items (STERI) is required as part of the procurement process for spare and replacement items. Guidance on supplier program requirements necessary to maintain continued seismic adequacy and on documentation of maintaining required seismic adequacy is also included

Rapid breeding and varietal replacement are critical to adaptation of cropping systems in the developing world to climate change.

Science.gov (United States)

Atlin, Gary N; Cairns, Jill E; Das, Biswanath

2017-03-01

Plant breeding is a key mechanism for adaptation of cropping systems to climate change. Much discussion of breeding for climate change focuses on genes with large effects on heat and drought tolerance, but phenology and stress tolerance are highly polygenic. Adaptation will therefore mainly result from continually adjusting allele frequencies at many loci through rapid-cycle breeding that delivers a steady stream of incrementally improved cultivars. This will require access to elite germplasm from other regions, shortened breeding cycles, and multi-location testing systems that adequately sample the target population of environments. The objective of breeding and seed systems serving smallholder farmers should be to ensure that they use varieties developed in the last 10 years. Rapid varietal turnover must be supported by active dissemination of new varieties, and active withdrawal of obsolete ones. Commercial seed systems in temperate regions achieve this through competitive seed markets, but in the developing world, most crops are not served by competitive commercial seed systems, and many varieties date from the end of the Green Revolution (the late 1970s, when the second generation of modern rice and wheat varieties had been widely adopted). These obsolete varieties were developed in a climate different than today's, placing farmers at risk. To reduce this risk, a strengthened breeding system is needed, with freer international exchange of elite varieties, short breeding cycles, high selection intensity, wide-scale phenotyping, and accurate selection supported by genomic technology. Governments need to incentivize varietal release and dissemination systems to continuously replace obsolete varieties.

Determining Optimal Replacement Policy with an Availability Constraint via Genetic Algorithms

Directory of Open Access Journals (Sweden)

Shengliang Zong

2017-01-01

Full Text Available We develop a model and a genetic algorithm for determining an optimal replacement policy for power equipment subject to Poisson shocks. If the time interval of two consecutive shocks is less than a threshold value, the failed equipment can be repaired. We assume that the operating time after repair is stochastically nonincreasing and the repair time is exponentially distributed with a geometric increasing mean. Our objective is to minimize the expected average cost under an availability requirement. Based on this average cost function, we propose the genetic algorithm to locate the optimal replacement policy N to minimize the average cost rate. The results show that the GA is effective and efficient in finding the optimal solutions. The availability of equipment has significance effect on the optimal replacement policy. Many practical systems fit the model developed in this paper.

Software and man-machine interface considerations for a nuclear plant computer replacement and upgrade project

International Nuclear Information System (INIS)

Diamond, G.; Robinson, E.

1984-01-01

Some of the key software functions and Man-Machine Interface considerations in a computer replacement and upgrade project for a nuclear power plant are described. The project involves the installation of two separate computer systems: an Emergency Response Facilities Computer System (ERFCS) and a Plant Process Computer System (PPCS). These systems employ state-of-the-art computer hardware and software. The ERFCS is a new system intended to provide enhanced functions to meet NRC post-TMI guidelines. The PPCS is intended to replace and upgrade an existing obsolete plant computer system. A general overview of the hardware and software aspects of the replacement and upgrade is presented. The work done to develop the upgraded Man-Machine Interface is described. For the ERFCS, a detailed discussion is presented of the work done to develop logic to evaluate the readiness and performance of safety systems and their supporting functions. The Man-Machine Interface considerations of reporting readiness and performance to the operator are discussed. Finally, the considerations involved in the implementation of this logic in real-time software are discussed.. For the PPCS, a detailed discussion is presented of some new features

Insurance for replacement power costs

International Nuclear Information System (INIS)

Cleaver, A.

1980-01-01

Although careful consideration is given to insurance against physical damage to plant and equipment, little thought is given to the costs that will be incurred in replacing the power that is lost while a relatively efficient system is out of action. The results of an investigation carried out for a generating authority with an installed capacity of about 3000 MW is given. Replacement power costs for different cases of severity of damage range from Pound1.17m per month for damage to central services taking out all four units. (author)

An evaluation on the environmental consequences of residual CFCs from obsolete household refrigerators in China

International Nuclear Information System (INIS)

Zhao Xiangyang; Duan Huabo; Li Jinhui

2011-01-01

Chlorofluorocarbons (CFCs) contained in household refrigerators consist mainly of CFC-11 and CFC-12, which will be eventually released into the environment. Consequentially, environmental releases of these refrigerants will lead to ozone depletion and contribute significantly to the greenhouse effect, if waste refrigerators are not disposed of properly. In the present paper, the potential release of residual CFCs and their substitutes from obsolete household refrigerators in China is examined, and their contributions to ozone depletion and greenhouse effect are compared with those of other recognized ozone-depleting substances (ODS) and greenhouse gases (GHGs). The results imply that annual potential amounts of released residual CFC-11 and CFC-12 will reach their maximums at 4600 and 2300 tons, respectively in 2011, and then decrease gradually to zero until 2020. Meanwhile, the amounts of their most widely used substitutes HCFC-141b and HFC-134a will keep increasing. Subsequently, the contribution ratio of these CFCs and their substitutes to ozone depletion will remain at 25% through 2011, and reach its peak value of 34% by 2018. The contribution to greenhouse effect will reach its peak value of 0.57% by 2010. Moreover, the contribution ratio of these CFCs to the total global release of CFCs will steadily increase, reaching its peak of 15% by 2018. Thus, this period from 2010 to 2018 is a crucial time during which residual CFCs and their substitutes from obsolete household refrigerators in China will contribute significantly to ozone depletion.

Improved servicing equipment for steam generators

International Nuclear Information System (INIS)

Hedtke, James C.

1998-01-01

To help keep personnel exposure as low as reasonably achievable and reduce critical path outage time, most nuclear plants of PWR design in the USA are now using improved equipment to service their steam generators (SGs) during outages. Because of the success of this equipment in the USA, two Belgian plants and one English plant have purchased this equipment, and other nuclear plants in Europe are also considering procurement. The improved SG servicing equipment discussed in this paper discusses consists of nozzle dams, segmented multi-stud tensioner, primary manway cover handling tool set, shield door and fastener cleaner. This equipment is specifically designed for the individual plant application and can also be specified for replacement SG projects. All of the equipment can be used without modification of the existing SGs. (author)

Optimal replacement time estimation for machines and equipment based on cost function

OpenAIRE

J. Šebo; J. Buša; P. Demeč; J. Svetlík

2013-01-01

The article deals with a multidisciplinary issue of estimating the optimal replacement time for the machines. Considered categories of machines, for which the optimization method is usable, are of the metallurgical and engineering production. Different models of cost function are considered (both with one and two variables). Parameters of the models were calculated through the least squares method. Models testing show that all are good enough, so for estimation of optimal replacement time is ...

Step by step replacement of aging electronic equipment: a way to maintain high capacity factors

International Nuclear Information System (INIS)

Wilder, O.

1990-01-01

The paper discusses the following topics: replacement concept, aging, replacement, strategy and the Swedish situation. The replacement of important central systems started already 1986 in Oskarshamn 1

Restoration to serviceability of Bruce 'A' heat transfer equipment

International Nuclear Information System (INIS)

Gammage, D.; Machowski, C.; McGillivray, R.; Durance, D.; Kazimer, D.; Werner, K.

2009-01-01

Bruce Units 1 to 4 were shut down during the 1990s by the former Ontario Hydro, due in part to a long list of system and equipment deficiencies and concerns, including steam generator tube degradation as a consequence of the then-existing steam generator secondary side water chemistry conditions. Upon its creation in 2001, and following a program of condition assessment, Bruce Power was able to determine that Units 3 and 4 could return to service; but that Units 1 and 2 would require refurbishment. That Refurbishment Program, which is currently well advanced, included the re-assessment of the condition of equipment throughout the plant including the heat transfer equipment; and determination item-by-item as to what inspection, cleaning, repair, or even replacement would be required to put the equipment into a condition where it could be expected to operate reliably for the additional 30 years expected from the plant. Clearly the objective is to suitably restore the equipment to serviceability without doing more refurbishment work than is warranted - without replacing equipment except where absolutely necessary. The first task in such a program is determination of its scope - i.e. a listing of all heat exchangers. That list included everything from the steam generators (which required replacement, now completed), to much smaller heat exchangers in the heavy water upgrader systems (which were found to be in very good overall condition). There is also a very large number of other so-called 'balance-of-plant' heat exchangers; these include the maintenance coolers, moderator heat exchangers, shutdown coolers and a whole raft of smaller coolers - many of which are cooled directly by lake water with its potential for bio-fouling and 'BIC' (Biologically Induced Corrosion). This paper focuses primarily on the engineering assessment, inspection, repair and general refurbishment of the balance-of-plant heat exchangers. As will be discussed in the paper, the assessment of the

Backfitting of research reactors

International Nuclear Information System (INIS)

Delrue, R.; Noesen, T.

1985-01-01

The backfitting of research reactors covers a variety of activities. 1. Instrumentation and control: Control systems have developed rapidly and many reactor operators wish to replace obsolete equipment by new systems. 2. Pool liners: Some pools are lined internally with ceramic tiles. These may become pervious with time necessitating replacement, e.g. by a new stainless steel liner. 3. Heat removal system: Deficiencies can occur in one or more of the cooling system components. Upgrading may require modifications of the system such as addition of primary loops, introduction of deactivation tanks, pump replacement. Recent experience in such work has shown that renewal, backfitting and upgrading of an existing reactor is economically attractive since the related costs and delivery times are substantially lower than those required to install a new research reactor

The suitability and installation of technological equipment when upgrading existing facilities

Directory of Open Access Journals (Sweden)

Ladnushkin A. A.

2016-03-01

Full Text Available to date, a large number of Russian companies in diverse and various industries, has old equipment and requires modernization of the technological process due to the growth of scientific and technological progress. In order to achieve goals when upgrading is considered such an important aspect as the readiness of the new equipment installation. Mounting hardware suitability describes the suitability and readiness of equipment for efficient Assembly at the user. Replacement of technological equipment requires large volumes of works on installation and dismantling, in the absence of the building has its own lifting mechanisms require large financial and labor costs. One of possible methods for replacement of process equipment is the technology of without crane installation allows us to carry out work in existing space planning. Today is the question of the necessity of development and introduction of new technological production methods and fixtures tooling in which it is possible to conduct installation and dismantling of technological equipment in the operating production process.

Human Health Safety Evaluation of Halon Replacement Candidates

National Research Council Canada - National Science Library

Dodd, D. E; Jepson, G. W; Macko, Jr, J. A

2000-01-01

.... The services within the Department of Defense (DoD) are directed to determine and evaluate suitable halon replacement candidates that will optimize performance of mission-essential equipment and operations...

Structural considerations in steam generator replacement

International Nuclear Information System (INIS)

Bertheau, S.R.; Gazda, P.A.

1991-01-01

Corrosion of the tubes and tube-support structures inside pressurized water reactor (PWR) steam generators has led many utilities to consider a replacement of the generators. Such a project is a major undertaking for a utility and must be well planned to ensure an efficient and cost-effective effort. This paper discusses various structural aspects of replacement options, such as total or partial generator replacement, along with their associated pipe cuts; major structural aspects associated with removal paths through the equipment hatch or through an opening in the containment wall, along with the related removal processes; onsite movement and storage of the generators; and the advantages and disadvantages of the removal alternatives. This paper addresses the major structural considerations associated with a steam generator replacement project. Other important considerations (e.g., licensing, radiological concerns, electrical requirements, facilities for management and onsite administrative activities, storage and fabrication activities, and offsite transportation) are not discussed in this paper, but should be carefully considered when undertaking a replacement project

Upgrade programs. Status and prospective

International Nuclear Information System (INIS)

Loyer, F.

1998-01-01

Arguments for launching a renovation program for GANIL system, taking into account aging and wear, are analyzed. A statistics of failures related to vacuum systems, power supplies, electronics, cooling systems, beam dumps and other equipment is given. The renovation program is targeted to: replacement of obsolete components, introduction of advanced systems of failure diagnosis, augmentation of performances of the new regulating and control system and improvement in the performance characteristics of certain fundamental equipment. The first results and to date status of the program development is reported. Mentioned are the works related to control of HF cavities and the associated amplifiers, electronics, the system of cavity synchronization, power supply, RMN, system commutation grid, pumping equipment, etc. Also, improvements concerning the machine data acquisition and online processing are referred to as well as program cost estimations

Making petroleum equipment safe, a priority

International Nuclear Information System (INIS)

1999-01-01

Changes to the 'Act respecting the use of petroleum products' have been announced effective May 1, 1999. The changes have been made to reduce problems which can be attributed to petroleum product leaks. The new regulations will make owners and users of petroleum equipment, including underground and above-ground storage equipment and commercial storage tanks, more accountable for the use of their own equipment. The emphasis in the new regulations is based upon the storage capacity of petroleum equipment and the risks associated with this equipment, rather than the on the activities of the owners concerned. Accordingly, the new regulations call for stricter requirements for high-risk equipment, a private equipment inspection plan, a two-year operating permit, replacing the current permits and certificates, a tariff structure based on the risks associated with the equipment, and deregulation of commercial activities involving petroleum products that require no equipment. Additionally, the amendments to the Act transfer responsibility for administration to the Regie du batiment and to the Ministere des Transports. Details of each of these changes are explained

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

Energy Technology Data Exchange (ETDEWEB)

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

1982-01-01

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

'Consolidation' of HVAC and cooling systems at CERN

CERN Document Server

Inigo-Golfin, J; Pepinster, P; CERN. Geneva. TS Department

2008-01-01

A â€ﾜconsolidation” of installations after they have reached the end of their predetermined life-time is part of the life cycle of industrial installations, regardless how well maintained they are. The â€ﾜconsolidation” plan might cover the replacement of obsolete equipment, partial refurbishment, the work requested to comply with new standards and applicable rules (environmental aspects) until the complete replacement of the whole installation. This â€ﾜconsolidation” process is all the more critical since the installation dates of the existing cooling and HVAC equipment at CERN spans over a period of 50 years and â€ﾜconsolidation” in the past has been not been systematic, being most of the time associated with new projects. This paper describes the reasons behind the recent â€ﾜconsolidation” requests for cooling and HVAC equipment both for the accelerators backbone and in tertiary buildings. A criticality analysis is given, based on the criteria laid down in the p...

Plant equipment services with laser metrology

International Nuclear Information System (INIS)

Hayes, J.H.; Kreitman, P.J.

1995-01-01

A new industrial metrology process is now being applied to support PWR Nuclear Plant Steam Generator Replacement Projects. The method uses laser tracking interferometry to perform as built surveys of existing and replacement plant equipment. This method provides precision data with a minimum of setup when compared to alternative methods available. In addition there is no post processing required to ascertain validity. The data is obtained quickly, processed in real time and displayed during the survey in the desired coordinate system. These capabilities make this method of industrial measure ideal for various data acquisition needs throughout the power industry, from internal/external equipment templating to area mapping. Laser tracking interferometry is an improvement on the present use of optical instruments and surveying technique. In order to describe the laser tracking interferometry measurement process, previous methods of templating and surveying are first reviewed

Case Based Asset Maintenance for the Electric Equipment

International Nuclear Information System (INIS)

Kim, Ji-Hyeon; Jung, Jae-Cheon; Chang, Young-Woo; Chang, Hoon-Seon; Kim, Jae-Cheol; Kim, Hang-Bae; Kim, Kyu-Ho; Hur, Yong; Lee, Dong-Chul

2006-01-01

The electric equipment maintenance strategies are changing from PM(Preventive Maintenance) or CM(Corrective Maintenance) to CBM(Condition Based Maintenance). The main benefits of CBM are reduced possibility of service failures of critical equipment and reduced costs or maintenance work. In CBM, the equipment status need to be monitored continuously and a decision should be made whether an equipment need to be repaired or replaced. For the maintenance decision making, the CBR(Case Base Reasoning) system is introduced. The CBR system receives the current equipment status and retrieves the case based historic database to determine any possible equipment failure under current conditions. In retrieving the case based historic data, the suggested DSS(Decision Support System) uses a reasoning engine with an equipment/asset ontology that describes the equipment subsumption relationships

5/8'' baffle bolt replacement

International Nuclear Information System (INIS)

Pinaud, T.; Grypczynski, D.

1999-01-01

Both Framatome Nuclear Services in France and its U.S. arm, FT1, are now equipped with baffle bolt inspection and replacement packages. These packages allow them to tackle baffle bold degradation on both two- and three-loop nuclear power plants. Framatome and FT1 together are world leaders in addressing reactor vessel internal bolting concerns

The capacity of sugar beet farms’ machinery and equipment

Directory of Open Access Journals (Sweden)

Małgorzata BZOWSKA – BAKALARZ

2012-12-01

Full Text Available The survey investigates into equipment of sugar beet farms of the Lublin region, Poland, with machinery – with reference to plantation size and yields. To assess the production potential of the farms, the authors determined the age structure of the machinery owned by the farmers and established the scale of investment in new equipment. The machinery most important for sugar beet production are pre-sowing and post-harvest tillage units, sprayers, seed drills, combine harvesters and self-unloading trailers. In most cases, the surveyed farmers own most of these machines, but they are often obsolete: 37% of them is in operation for more than 15 years. As for the machines dedicated solely to sugar beet growing (harvesters and seeders, their age structure is most unfavourable – 70% of them have been used for over 15 years. A trend towards increasing plantation sizes provides incentives for introducing innovation to cultivation methods. However, the scale of investment in new machinery is small, especially in the case of small and medium-sized farms that dominate in the region. The authors surveyed also the scale of using professional services in the field of tillage processes to determine changes in farming practices.

Application of deterministic and probabilistic methods in replacement of nuclear systems

International Nuclear Information System (INIS)

Vianna Filho, Alfredo Marques

2007-01-01

The economic equipment replacement problem is one of the oldest questions in Production Engineering. On the one hand, new equipment are more attractive given their best performance, better reliability, lower maintenance cost, etc. New equipment, however, require a higher initial investment and thus a higher opportunity cost, and impose special training of the labor force. On the other hand, old equipment represent the other way around, with lower performance, lower reliability and specially higher maintenance costs but in contrast having lower financial, insurance, and opportunity costs. The weighting of all these costs can be made with the various methods presented. The aim of this paper is to discuss deterministic and probabilistic methods applied to the study of equipment replacement. Two types of distinct problems will be examined, substitution imposed by the wearing and substitution imposed by the failures. In order to solve the problem of nuclear system substitution imposed by wearing, deterministic methods are discussed. In order to solve the problem of nuclear system substitution imposed by failures, probabilistic methods are discussed. (author)

Optimization of station battery replacement

International Nuclear Information System (INIS)

Jancauskas, J.R.; Shook, D.A.

1994-01-01

During a loss of ac power at a nuclear generating station (including diesel generators), batteries provide the source of power which is required to operate safety-related components. Because traditional lead-acid batteries have a qualified life of 20 years, the batteries must be replaced a minimum of once during a station's lifetime, twice if license extension is pursued, and more often depending on actual in-service dates and the results of surveillance tests. Replacement of batteries often occurs prior to 20 years as a result of systems changes caused by factors such as Station Blackout Regulations, control system upgrades, incremental load growth, and changes in the operating times of existing equipment. Many of these replacement decisions are based on the predictive capabilities of manual design basis calculations. The inherent conservatism of manual calculations may result in battery replacements occurring before actually required. Computerized analysis of batteries can aid in optimizing the timing of replacements as well as in interpreting service test data. Computerized analysis also provides large benefits in maintaining the as-configured load profile and corresponding design margins, while also providing the capability of quickly analyze proposed modifications and response to internal and external audits

Remote handling demonstration of ITER blanket module replacement

International Nuclear Information System (INIS)

Kakudate, S.; Nakahira, M.; Oka, K.; Taguchi, K.; Obara, K.; Tada, E.; Shibanuma, K.; Tesini, A.; Haange, R.; Maisonnier, D.

2001-01-01

In ITER, the in-vessel components such as blanket are to be maintained or replaced remotely since they will be activated by 14 MeV neutrons, and a complete exchange of shielding blanket with breeding blanket is foreseen after the Basic Performance Phase. The blanket is segmented into about seven hundred modules to facilitate remote maintainability and allow individual module replacement. For this, the remote handing equipment for blanket maintenance is required to handle a module with a dead weight of about 4 tonne within a positioning accuracy of a few mm under intense gamma radiation. According to the ITER R and D program, a rail-mounted vehicle manipulator system was developed and the basic feasibility of this system was verified through prototype testing. Following this, development of full-scale remote handling equipment has been conducted as one of the ITER Seven R and D Projects aiming at a remote handling demonstration of the ITER blanket. As a result, the Blanket Test Platform (BTP) composed of the full-scale remote handling equipment has been completed and the first integrated performance test in March 1998 has shown that the fabricate remote handling equipment satisfies the main requirements of ITER blanket maintenance. (author)

Replacement of core components in the Advanced Test Reactor

International Nuclear Information System (INIS)

Durney, J.L.; Croucher, D.W.

1990-01-01

The core internals of the Advanced Test Reactor are subjected to very high neutron fluences resulting in significant aging. The most irradiated components have been replaced on several occasions as a result of the neutron damage. The surveillance program to monitor the aging developed the needed criteria to establish replacement schedules and maximize the use of the reactor. The methods to complete the replacements with minimum radiation exposures to workers have been developed using the experience gained from each replacement. The original design of the reactor core and associated components allows replacements to be completed without special equipment. The plant has operated for about 20 years and is expected to continue operation for at least and additional 25 years. Aging evaluations are in progress to address additional replacements that may be needed during this period

Replacement of core components in the Advanced Test Reactor

International Nuclear Information System (INIS)

Durney, J.L.; Croucher, D.W.

1989-01-01

The core internals of the Advanced Test Reactor are subjected to very high neutron fluences resulting in significant aging. The most irradiated components have been replaced on several occasions as a result of the neutron damage. The surveillance program to monitor the aging developed the needed criteria to establish replacement schedules and maximize the use of the reactor. Methods to complete the replacements with minimum radiation exposures to workers have been developed using the experience gained from each replacement. The original design of the reactor core and associated components allows replacements to be completed without special equipment. The plant has operated for about 20 years and will continue operation for perhaps another 20 years. Aging evaluations are in program to address additional replacements that may be needed during this extended time period. 3 figs

New instrument calibration facility for the DOE Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Wilkie, W.H.; Polz, E.J. [Westinghouse Savannah River Company, Aiken, SC (United States)

1993-12-31

A new laboratory facility is being designed, constructed, and equipped at the Savannah River Site (SRS) as a fiscal year 1992 line item project. This facility will provide space and equipment for test, evaluation, repair, maintenance, and calibration of radiation monitoring instrumentation. The project will replace an obsolete facility and will allow implementation of program upgrades necessary to meet ANSI N323 requirements and National Voluntary Laboratory Accreditation Program (NVLAP) criteria for accreditation of federally owned secondary calibration laboratories. An outline of the project is presented including description, scope, cost, management organization, chronology, and current status. Selected design criteria and their impacts on the project are discussed. The upgraded SRS calibration program is described, and important features of the new facility and equipment that will accommodate this program are listed. The floor plan for the facility is shown, and equipment summaries and functional descriptions for each area are provided.

New instrument calibration facility for the DOE Savannah River Site

International Nuclear Information System (INIS)

Wilkie, W.H.; Polz, E.J.

1993-01-01

A new laboratory facility is being designed, constructed, and equipped at the Savannah River Site (SRS) as a fiscal year 1992 line item project. This facility will provide space and equipment for test, evaluation, repair, maintenance, and calibration of radiation monitoring instrumentation. The project will replace an obsolete facility and will allow implementation of program upgrades necessary to meet ANSI N323 requirements and National Voluntary Laboratory Accreditation Program (NVLAP) criteria for accreditation of federally owned secondary calibration laboratories. An outline of the project is presented including description, scope, cost, management organization, chronology, and current status. Selected design criteria and their impacts on the project are discussed. The upgraded SRS calibration program is described, and important features of the new facility and equipment that will accommodate this program are listed. The floor plan for the facility is shown, and equipment summaries and functional descriptions for each area are provided

Air Traffic Control: Status of FAA's Implementation of the Display System Replacement Project

National Research Council Canada - National Science Library

1999-01-01

...) implementation of the Display System Replacement (DSR) project. DSR, which replaces the controllers' workstations and other equipment in the nation's en route centers, is one of FAA's major projects under the air traffic control modernization program...

10 CFR 34.27 - Leak testing and replacement of sealed sources.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Leak testing and replacement of sealed sources. 34.27... SAFETY REQUIREMENTS FOR INDUSTRIAL RADIOGRAPHIC OPERATIONS Equipment § 34.27 Leak testing and replacement... radiographic exposure device and leak testing of any sealed source must be performed by persons authorized to...

Hardware replacements and software tools for digital control computers

International Nuclear Information System (INIS)

Walker, R.A.P.; Wang, B-C.; Fung, J.

1996-01-01

Technological obsolescence is an on-going challenge for all computer use. By design, and to some extent good fortune, AECL has had a good track record with respect to the march of obsolescence in CANDU digital control computer technology. Recognizing obsolescence as a fact of life, AECL has undertaken a program of supporting the digital control technology of existing CANDU plants. Other AECL groups are developing complete replacement systems for the digital control computers, and more advanced systems for the digital control computers of the future CANDU reactors. This paper presents the results of the efforts of AECL's DCC service support group to replace obsolete digital control computer and related components and to provide friendlier software technology related to the maintenance and use of digital control computers in CANDU. These efforts are expected to extend the current lifespan of existing digital control computers through their mandated life. This group applied two simple rules; the product, whether new or replacement should have a generic basis, and the products should be applicable to both existing CANDU plants and to 'repeat' plant designs built using current design guidelines. While some exceptions do apply, the rules have been met. The generic requirement dictates that the product should not be dependent on any brand technology, and should back-fit to and interface with any such technology which remains in the control design. The application requirement dictates that the product should have universal use and be user friendly to the greatest extent possible. Furthermore, both requirements were designed to anticipate user involvement, modifications and alternate user defined applications. The replacements for hardware components such as paper tape reader/punch, moving arm disk, contact scanner and Ramtek are discussed. The development of these hardware replacements coincide with the development of a gateway system for selected CANDU digital control

Investment, replacement and scrapping in a vintage capital model with embodied technological change

OpenAIRE

Bitros, George C.; Hritonenko, Natali; Yatsenko, Yuri

2007-01-01

This paper analyzes and compares two alternative policies of determining the service life and replacement demand for vintage equipment under embodied technological change. The policies are the infinite-horizon replacement and the transitory replacement ending with scrapping. The corresponding vintage capital models are formulated in the dynamic optimization framework. These two approaches lead to different estimates of the duration of replacements and the impact of technological change on the...

Overview of statistical methods, models and analysis for predicting equipment end of life

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-07-01

Utility equipment can be operated and maintained for many years following installation. However, as the equipment ages, utility operators must decide whether to extend the service life or replace the equipment. Condition assessment modelling is used by many utilities to determine the condition of equipment and to prioritize the maintenance or repair. Several factors are weighted and combined in assessment modelling, which gives a single index number to rate the equipment. There is speculation that this index alone may not be adequate for a business case to rework or replace an asset because it only ranks an asset into a particular category. For that reason, a new methodology was developed to determine the economic end of life of an asset. This paper described the different statistical methods available and their use in determining the remaining service life of electrical equipment. A newly developed Excel-based demonstration computer tool is also an integral part of the deliverables of this project.

The lost constellations a history of obsolete, extinct, or forgotten star lore

CERN Document Server

Barentine, John C

2016-01-01

Casual stargazers are familiar with many classical figures and asterisms composed of bright stars (e.g., Orion and the Plough), but this book reveals not just the constellations of today but those of yesteryear. The history of the human identification of constellations among the stars is explored through the stories of some influential celestial cartographers whose works determined whether new inventions survived. The history of how the modern set of 88 constellations was defined by the professional astronomy community is recounted, explaining how the constellations described in the book became permanently “extinct.”  Dr. Barentine addresses why some figures were tried and discarded, and also directs observers to how those figures can still be picked out on a clear night if one knows where to look. These lost constellations are described in great detail using historical references, ennabling observers to rediscover them on their own surveys of the sky. Treatment of the obsolete constellations as ...

Fuzzy logic application for extruders replacement problem

Directory of Open Access Journals (Sweden)

Edison Conde Perez dos Santos

2017-03-01

Full Text Available In a scenario of uncertainty and imprecision, before taking the replacement analysis, a manager needs to consider the uncertain reality of a problem. In this scenario, the fuzzy logic makes an excellent option. Therefore, it is necessary to make a decision based on the fuzzy model. This study is based on the comparison of two methodologies used in the problem of asset replacement. The study, thus, was based on a comparison between two extruders for polypropylene yarn bibliopegy, comparing mainly the costs involved in maintaining the equipment.

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

International Nuclear Information System (INIS)

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

1987-08-01

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

Green and economic fleet replacement modeling : part I.

Science.gov (United States)

2011-10-01

"The purpose of this study was to gain a better understanding of how equipment replacement decisions are supported with data collection and : quantitative models at state DOTs, and to determine if models found in the research literature offer any bet...

Market Potential for Residential Biomass Heating Equipment: Stochastic and Econometric Assessments

OpenAIRE

Adee Athiyaman

2015-01-01

This paper provides estimates of market potential for biomass-residential-heating equipment in the US: that is, the greatest amount of biomass-residential-heating equipment that can be sold by the industry. The author's analysis is limited to biomass equipment used most to heat the housing unit. Assuming that households equipped with 10+ year old primary heating devices will replace rather than repair the devices he predicts that approximately 1.4 million units of residential home heating equ...

Technical development and its application on steam generator replacement

International Nuclear Information System (INIS)

Morita, Sadahiko; Hanzawa, Katsumi; Sato, Hajime; Kannoto, Yasuo.

1995-01-01

Twenty-two PWR nuclear power plants are now under commercial operation in Japan. Eight of these plants are scheduled to have their steam generators replaced by up-graded units as a social responsibility for improved reliability, economy and easier maintenance. To carry out steam generator replacement, main coolant pipe cutting and restoration techniques, remote controlled welding machines and other remote controlled equipment, templating techniques with which the new steam generator primary nozzles will fit the existing primary pipes correctly were developed. An adequate training program was carried out to establish these techniques and they were then applied in replacement work on site. The steam generators of the three plants were replaced completely in 1994. These newly developed techniques are to be applied in upcoming plants and replaced plants will be much reliable. (author)

EG and G electron linac modifications

International Nuclear Information System (INIS)

Norris, N.J.; Detch, J.L.; Kocimski, S.M.; Sawyer, C.R.; Hudson, C.L.

1986-01-01

A three-year modification of the EG and G electron linac has been performed to replace obsolete equipment and bring all subsystems up to the current state of the art. Components and subsystems were designed, constructed, and tested off-line to minimize interruption of experiments. The configuration of the modified linac is shown schematically, and performance characteristics are give. Each subsystem is described, including: the electron gun; solenoid focusing system; subharmonic bunchers; accelerating system; RF system; klystron modulators and power supplies; control system; beam handling system; vacuum system; and beam current monitors. 7 refs., 4 figs., 2 tabs

EG and G electron linac modifications

International Nuclear Information System (INIS)

Norris, N.J.; Detch, J.L.; Kocimski, S.M.; Sawyer, C.R.; Hudson, C.L.

1986-01-01

The electron linear accelerator at EG and G/EM, Santa Barbara Operations, installed in 1963, has been subsequently modified to produce short, intense beam pulses used in the test, calibration and development of many types of fast radiation detectors and systems. The first practical use of the single RF pulse operation, now used in many accelerators, was demonstrated on this accelerator in the late 60s. A major three-year modification, to replace obsolete equipment and bring all the subsystems up to the current state of the art, has increased the beam intensity, stability and reliability. These modifications are discussed

The use of MRI in the investigation of lateral meniscal tear post medial unicompartmental knee replacement

Directory of Open Access Journals (Sweden)

Sanil H. Ajwani, MBChB, BSc (Hons, MRCS

2015-06-01

Full Text Available The evaluation of lateral knee pain in patients with a medial unicompartmental knee replacement (UKR is complex. The native lateral compartment structures are prone to the same injuries as patients with normal knees. Historical reports of lateral meniscal injury post medial UKR have argued MRI evaluation is obsolete due to artefact caused by the prosthesis. We report a case of lateral meniscal injury in a patient two years after successful medial UKR. We identified the offending pathology via utilization of MRI scanners adopting metal artefact reduction sequences (MARS. The MARS MRI protocol helps clinicians accurately and non-invasively evaluate soft tissue structures in knees with metal prostheses. It also allows surgeons to accurately counsel patients and provides a higher degree of certainty in treating the pathology.

Evaluation of Bluetooth as a replacement for cables in intensive care and surgery.

Science.gov (United States)

Wallin, Mats K E B; Wajntraub, Samson

2004-03-01

In today's intensive care and surgery, a great number of cables are attached to patients. These cables can make the care and nursing of the patient difficult. Replacing them with wireless communications technology would facilitate patient care. Bluetooth is a modern radio technology developed specifically to replace cables between different pieces of communications equipment. In this study we sought to determine whether Bluetooth is a suitable replacement for cables in intensive care and during surgery with respect to electromagnetic compatibility. The following questions were addressed: Does Bluetooth interfere with medical equipment? And does the medical equipment decrease the quality of the Bluetooth communication? A Bluetooth link, simulating a patient monitoring system, was constructed with two laptops. The prototype was then used in laboratory and clinical tests according to American standards at the Karolinska Hospital in Stockholm. The tests, which included 44 different pieces of medical equipment, indicated that Bluetooth does not cause any interference. The tests also showed that the hospital environment does not affect the Bluetooth communication negatively. Bluetooth, a new radio technology transmitting at 2.4 GHz, was tested in a clinical setting. The study showed that a single Bluetooth link was robust and electromagnetically compatible with the tested electronic medical devices.

Research on Application of FMECA in Missile Equipment Maintenance Decision

Science.gov (United States)

Kun, Wang

2018-03-01

Fault mode effects and criticality analysis (FMECA) is a method widely used in engineering. Studying the application of FMEA technology in military equipment maintenance decision-making, can help us build a better equipment maintenance support system, and increase the using efficiency of weapons and equipment. Through Failure Modes, Effects and Criticality Analysis (FMECA) of equipment, known and potential failure modes and their causes are found out, and the influence on the equipment performance, operation success, personnel security are determined. Furthermore, according to the synthetical effects of the severity of effects and the failure probability, possible measures for prevention and correction are put forward. Through replacing or adjusting the corresponding parts, corresponding maintenance strategy is decided for preventive maintenance of equipment, which helps improve the equipment reliability.

Remote mechanized equipment for the repair and replacement of boiling water reactor recirculation loop piping

International Nuclear Information System (INIS)

Mauser, D.; Busch, D.F.

1983-01-01

Equipment has been assembled for the remote repair or replacement of boiling water reactor nuclear plant piping in the diameter range of 4 to 28 inches (10-71 cm). The objectives of this program were to produce high-quality pipe welds, reduce plant downtime, and reduce man-rem exposure. The repair strategy was to permit repair personnel to install and check out the repair subsystems and then leave the radiation zone allowing the operations to be conducted at a distance of up to 300 feet (91 m) from the operator. The complete repair system comprises subsystems for pipe severing, dimensional gaging, joint preparation, counterboring, welding, postweld nondestructive inspection (conceptual design), and audio, electronic, and visual monitoring of all operations. Components for all subsystems, excluding those for postweld nondestructive inspection, were purchased and modified as needed for integration into the repair system. Subsystems were designed for two sizes of Type 304 stainless steelpipe. For smaller, 12-inch-diameter (30.5 cm) pipe, severing is accomplished by a power hack saw and joint preparation and counterboring by an internally mounted lathe. The 22-inch-diameter (56 cm) pipe is severed, prepared, and counterbored using an externally mounted, single-point machining device. Dimensional gaging is performed to characterize the pipe geometry relative to a fixed external reference surface, allowing the placement of the joint preparation and the counterbore to be optimized. For both pipe sizes, a track-mounted gas tungsten-arc welding head with filler wire feed is used

Equipment and performance upgrade of compact nuclear simulator

International Nuclear Information System (INIS)

Park, J. C.; Kwon, K. C.; Lee, D. Y.; Hwang, I. K.; Park, W. M.; Cha, K. H.; Song, S. J.; Lee, J. W.; Kim, B. G.; Kim, H. J.

1999-01-01

The simulator at Nuclear Training Center in KAERI became old and has not been used effectively for nuclear-related training and researches due to the problems such as aging of the equipment, difficulties in obtaining consumables and their high cost, and less personnel available who can handle the old equipment. To solve the problems, this study was performed for recovering the functions of the simulator through the technical design and replacement of components with new ones. As results of this study, our test after the replacement showed the same simulation status as the previous one, and new graphic displays added to the simulator was effective for the training and easy for maintenance. This study is meaningful as demonstrating the way of upgrading nuclear training simulators that lost their functioning due to the obsolescence of simulators and the unavailability of components

Life Cycle Management for Equipments in Nuclear Plants Based on Reliability

International Nuclear Information System (INIS)

Wang Dalin; Sun Jinlong

2012-01-01

Majority of equipments in nuclear power stations are not un-repairable, but repaired after failures or maintained periodically and then returned to running. Along with aging or fatigue causes, duration between failures may be variable such as larger or shorter. Equipments failure occurrences are consistent with non-homogeneous Poisson process (NHPP), in which their failure rates are variable. We chose Weibull process to simplify the actual circumstances to obtain the optimal life cycle management plans approximately. In application we need to estimate parameters of Weibull process with existing data. Before that, trend test is necessary. Total time test (TTT) is an alternative. Trend test can determine whether the failure rate changes along operating time and whether the devices operated under imperfect or minimal repair. Parameters of Weibull process λ, β can be estimated by maximum likelihood estimation method. LCM model is designed to found an optimizing model for those aging equipments under minimal repair or imperfect maintenance with maximum economic or availability as objective function. The purpose is to establish the optimal replacement strategies. Periodical replacement is the most regular choice and so LCM model aims to calculate the optimal replacement periodical duration.

Development of the New Kibou® Equipment for Continuous Renal Replacement Therapy from Scratch to the Final Configuration.

Science.gov (United States)

Neri, Mauro; Lorenzin, Anna; Brendolan, Alessandra; Garzotto, Francesco; Ferrari, Fiorenza; De Rosa, Silvia; Bonato, Raffaele; Villa, Gianluca; Bazzano, Simona; D''Ippoliti, Fiorella; Ricci, Zaccaria; La Manna, Gaetano; Ronco, Claudio

2017-01-01

A new technology has recently appeared in the area of extracorporeal therapies for critically ill patients with acute kidney injury. The International Renal Research Institute of Vicenza was involved from the beginning in the development of a new continuous renal replacement therapy (CRRT) equipment with peculiar characteristics. We report the overall experience from design of the new machine to its in vitro and in vivo testing. Kibou® (Asahi Kasei Kuraray Medical Co., Ltd., Tokyo, Japan) is a new multifunctional machine designed for delivering RRT. Kibou® carries out many features of the fourth generation CRRT machines including the possibility of a dynamic prescription and reduction of nursing workload. We describe our first experience with this new device, focusing on several usability and performance parameters. A specific in vitro protocol was designed to analyze the various characteristics and accuracy of performance of the machine. Furthermore, a preliminary in vivo alpha trial with 12 CRRT sessions was performed to test, characterize and evaluate the machine in terms of usability, flexibility and reliability. The in vitro evaluation confirmed an adequate design and a good usability of the machine with accurate delivery of prescribed parameters. No adverse events were observed during the in vivo test that confirmed usability and safety together with accuracy of treatment delivery in different modalities. In general, the machine was rated by physicians and nurses involved in the evaluation as practical and easy to use, although a specific training is required to familiarize with the equipment. A large-scale multicenter beta trial is required to confirm the results reported in this preliminary evaluation in terms of safety, accuracy and performance of Kibou®. © 2017 S. Karger AG, Basel.

NPP I and C system modernizations in the Czech Republic. The NPP Dukovany example

International Nuclear Information System (INIS)

Krs, P.

1998-01-01

There are four units of WWER 440/213 type reactors under operation at Nuclear Power Plant Dukovany site in the Czech Republic. The EEZ utility has decided to include upgrade of existing Instrumentation and Control (I and C) systems as one of the most significant parts of a larger scale modernization project. The original I and C systems designed in the late 70's and early 80's with analogue equipment and relays will be subjected to an integrated modernization programme developed to replace obsolete equipment, to balance operational and maintenance costs, to improve performance and to enhance plant safety. To achieve this objective within next decade, the utility has already started preparatory phase of the overall modernization project, including analytical and planning activities related to the I and C part. (author)

Procurement and control of spare and replacement parts - a regulatory perspective

International Nuclear Information System (INIS)

Baker, E.T.; Grimes, B.K.; Merschoff, E.W.

1987-01-01

As the nuclear industry shifts from a construction to an operations orientation, a number of fundamental changes have occurred in the type of safety-related procurements and the manner in which the utilities accomplish these procurements. Specifically, procurements have shifted from the purchase of large systems and components by architect-engineers, and nuclear steam supply system (NSSS) suppliers to the procurement by utilities of subassemblies, individual pieces of equipment (e.g., breakers, relays), and small parts for repairing individual pieces of equipment. To ensure that equipment will continue to perform its intended function and to satisfy regulatory requirements utilities must consider several things: (1) does the equipment perform a safety function; (2) does the replacement part affect the safety function; and (3) does the replacement part affect the seismic or environmental qualification. If the answer to any of these questions is yes, the purchaser has two alternatives. He may procure the item as safety-related and require the supplier or manufacturer to comply with all the applicable technical and quality requirements or he may purchase the item commercial grade and perform the necessary inspections and tests to ensure the item meets the requirements, i.e., dedicate the item

Ingledow 500 kV substation : using mixed technology switchgear solutions for replacement

Energy Technology Data Exchange (ETDEWEB)

Wallner, C.; Glaubitz, P. [Siemens AG, Munich (Germany); Messinger, T. [British Columbia Transmission Corp., Vancouver, BC (Canada)

2008-07-01

The reliability of the 500 kV equipment at the Ingledow substation operated by BC Hydro Transmission System is of critical importance due to the energy interchange with the Bonneville Power Authority in the United States and the major role of the substation in serving the energy needs of British Columbia's densely populated Lower Mainland. Presently, the 500 kV switchyard includes 10 airblast circuit breakers and the associated current transformers which are all approaching their end of service-life. In response to environmental and safety concerns, the British Columbia Transmission Corporation adopted a policy whereby new oil-filled transformers are no longer acceptable, and the replacement of existing oil-filled transformers must be oil-free. The result is that the current transformers must be either bushing-type or sulphur-hexafluoride (SF6) type. The replacement strategies for the substation equipment consider economical, environmental and seismic issues. They have just as strong an influence on the decision process as the technical, operational and reliability aspects for the particular case or switchgear replacement in the transmission system. The Ingledow case demonstrates the advantages of using mixed technology switchgear, with its compact design flowing from gas insulated switchgear (GIS) for replacement of equipment in an outdoor switchyard. The advantages of the MTS in this case offer the possibility of future reconfiguration to improve the system reliability within the existing switchyard space. 3 refs., 5 figs.

The reduction of noise from hydraulic equipments; La reduction du bruit provenant des equipements hydrauliques

Energy Technology Data Exchange (ETDEWEB)

Gential, R.

1996-09-01

Noise pollution from hydraulic equipments (bath filling, toilets taps, waste waters flow, vibrations, knocks in water pipes, dilatation clattering in heating pipes, hissing of heater taps etc..) are one of the principal causes of nuisance inside residential buildings. Solutions exist and consist in the replacement of old cocks and fittings, the use of soundproof clamps for pipes and noise absorbing supports for baths etc.. This paper summarizes the available modern equipments with a low-noise warranty (cocks and fittings, noise dampers, anti-backflow valves, pressure reducers) and the practical solutions for the modification of existing installations (increase of pipe diameters, reduction of pipe lengths, use of flexible fittings, hydraulic counterbalancing of water flows in heaters etc..). (J.S.)

Consolidating a Distributed Compound Management Capability into a Single Installation: The Application of Overall Equipment Effectiveness to Determine Capacity Utilization.

Science.gov (United States)

Green, Clive; Taylor, Daniel

2016-12-01

Compound management (CM) is a critical discipline enabling hit discovery through the production of assay-ready compound plates for screening. CM in pharma requires significant investments in manpower, capital equipment, repairs and maintenance, and information technology. These investments are at risk from external factors, for example, new technology rendering existing equipment obsolete and strategic site closures. At AstraZeneca, we faced the challenge of evaluating the number of CM sites required to support hit discovery in response to site closures and pressure on our operating budget. We reasoned that overall equipment effectiveness, a tool used extensively in the manufacturing sector, could determine the equipment capacity and appropriate number of sites. We identified automation downtime as the critical component governing capacity, and a connection between automation downtime and the availability of skilled staff. We demonstrated that sufficient production capacity existed in two sites to meet hit discovery demand without the requirement for an additional investment of $7 million in new facilities. In addition, we developed an automated capacity model that incorporated an extended working-day pattern as a solution for reducing automation downtime. The application of this solution enabled the transition to a single site, with an annual cost saving of $2.1 million. © 2015 Society for Laboratory Automation and Screening.

Establishing benchmarks and metrics for disruptive technologies, inappropriate and obsolete tests in the clinical laboratory.

Science.gov (United States)

Kiechle, Frederick L; Arcenas, Rodney C; Rogers, Linda C

2014-01-01

Benchmarks and metrics related to laboratory test utilization are based on evidence-based medical literature that may suffer from a positive publication bias. Guidelines are only as good as the data reviewed to create them. Disruptive technologies require time for appropriate use to be established before utilization review will be meaningful. Metrics include monitoring the use of obsolete tests and the inappropriate use of lab tests. Test utilization by clients in a hospital outreach program can be used to monitor the impact of new clients on lab workload. A multi-disciplinary laboratory utilization committee is the most effective tool for modifying bad habits, and reviewing and approving new tests for the lab formulary or by sending them out to a reference lab. Copyright © 2013 Elsevier B.V. All rights reserved.

Study on compact design of remote handling equipment for ITER blanket maintenance

International Nuclear Information System (INIS)

Takeda, Nobukazu; Kakudate, Satoshi; Nakahira, Masataka; Shibanuma, Kiyoshi

2006-03-01

In the ITER, the neutrons created by D-T reactions activate structural materials, and thereby, the circumstance in the vacuum vessel is under intense gamma radiation field. Thus, the in-vessel components such as blanket are handled and replaced by remote handling equipment. The objective of this report is to study the compactness of the remote handling equipment (a vehicle/manipulator) for the ITER blanket maintenance. In order to avoid the interferences between the blanket and the equipment during blanket replacement in the restricted vacuum vessel, a compact design of the equipment is required. Therefore, the compact design is performed, including kinematic analyses aiming at the reduction of the sizes of the vehicle equipped with a manipulator handling the blanket and the rail for the vehicle traveling in the vacuum vessel. Major results are as follows: 1. The compact vehicle/manipulator is designed concentration on the reduction of the rail size and simplification of the guide roller mechanism as well as the reduction of the gear diameter for vehicle rotation around the rail. Height of the rail is reduced from 500 mm to 400 mm by a parameter survey for weight, stiffness and stress of the rail. The roller mechanism is divided into two simple functional mechanisms composed of rollers and a pad, that is, the rollers support relatively light loads during rail deployment and vehicle traveling while a pad supports heavy loads during blanket replacement. Regarding the rotation mechanism, the double helical gear is adopted, because it has higher contact ratio than the normal spur gear and consequently can transfer higher force. The smaller double helical gear, 996 mm in diameter, can achieve 26% higher output torque, 123.5 kN·m, than that of the original spur gear of 1,460 mm in diameter, 98 kN·m. As a result, the manipulator becomes about 30% lighter, 8 tons, than the original weight, 11.2 tons. 2. Based on the compact design of the vehicle/manipulator, the

Liquid Metal Fast Breeder Reactor plant maintenance and equipment design

International Nuclear Information System (INIS)

Swannack, D.L.

1982-01-01

This paper provides a summary of maintenance equipment considerations and actual plant handling experiences from operation of a sodium-cooled reactor, the Fast Flux Test Facility (FFTF). Equipment areas relating to design, repair techniques, in-cell handling, logistics and facility services are discussed. Plant design must make provisions for handling and replacement of components within containment or allow for transport to an ex-containment area for repair. The modular cask assemblies and transporter systems developed for FFTF can service major plant components as well as smaller units. The plant and equipment designs for the Clinch River Breeder Reactor (CRBR) plant have been patterned after successful FFTF equipment

Optimising Age-Replacement and Extended Non-Renewing Warranty Policies in Lifecycle Costing

OpenAIRE

Wu, Shaomin; Longhurst, Phil

2011-01-01

This paper analyses the life cycle cost of equipment protected by both base and extended warranty policies from a consumer's perspective. We assume that the equipment has two types of failure: minor and catastrophic. A minor failure can be corrected with minimal repair whereas a catastrophic failure can only be removed by a replacement. It is assumed that equipment is maintained at no charge to the consumer during the warranty period, whereas the consumer is fully charged for any maintenance ...

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

The manager and equipment decisions: is that in the capital budget?

Science.gov (United States)

McConnell, C R

2001-06-01

Although any decision to purchase a piece of capital equipment involves a number of the organization's functions, the department manager has some significant responsibilities in the selection and acquisition of capital equipment. Except for unavoidable replacement of essential equipment that fails unexpectedly, capital purchases must ordinarily be planned in advance through the annual budgeting process. The department manager is ordinarily the organization's primary source of information in major capital expenditure projects; therefore, it is essential that the manager follow a logical process for identifying and evaluating alternative equipment choices and perform a consistent economic analysis of the alternatives.

Renewal of handling and storage equipment in wholesale company

Directory of Open Access Journals (Sweden)

Tânia Brasileiro Azevedo Teixeira

2015-06-01

Full Text Available This paper presents a use of methodology for renewing handling and storage equipment in a wholesale company. It is based on equipment maintenance, downtime and possession costs. With the analysis performed,, it was possible to make some suggestions for an optimal economic point for pallets replacement. The methodology is based on mathematical and economic principles in order to provide the organization with an increase in productivity and costs reduction for handling and storage equipment. As a result of the use of methodology, the conclusion that it was possible to consider that this point is obtained when the total annual cost is equal to the average total cost was reached. Therefore, the equilibrium point is achieved when the equipment usage time is six years.

Hoisting appliances and fuel handling equipment at nuclear facilities

International Nuclear Information System (INIS)

1987-01-01

The guide is followed by the Finnish Centre for Radiation and Nuclear Safety (STUK) in regulating hoisting and handling equipment Class 3 at nuclear facilities. The guide is applied e.g. to the following equipment: reactor building overhead cranes, hoisting appliances at nuclear fuel storages, fuel handling machines, other hoisting appliances, which because of nuclear safety aspects are classified in Safety Class 3, and load-bearing devices connected with the above equipment, such as replaceable hoisting tools and auxiliary lifting devices. The regulating of hoisting and handling equipment comprises the following stages: handling of preliminary and final safety analysis reports, inspection of the construction plan, supervision of fabrication and construction inspection, and supervision of initial start-up and commissioning inspection

40 CFR 35.2035 - Rotating biological contractor (RBC) replacement grants.

Science.gov (United States)

2010-07-01

... treatment works owner, the applicant, its engineers, contractors, equipment manufacturers or suppliers; (b) The RBC failure has significantly increased the project's capital or operation and maintenance costs; (c) The modification/replacement project meets all requirements of EPA's construction grant and other...

Small Scale Manufacture of Replacement Crankshaft | Nyang'aya ...

African Journals Online (AJOL)

Local production of spares has been recognised to have direct economic advantage for the national economy in which the equipment operates. The crankshaft of a single cylinder diesel engine for which the approximate cost of a replacement is a third of the cost of a new engine was considered a prime product for local ...

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)

Essential Specification Elements for Heat Exchanger Replacement

Energy Technology Data Exchange (ETDEWEB)

Bower, L.

2015-07-01

Performance upgrade and equipment degradation are the primary impetuses for a nuclear power plant to engage in the large capital cost project of heat exchanger replacement. Along with attention to these issues, consideration of heat exchanger Codes and Standards, material improvements, thermal redesign, and configuration are essential for developing User’s Design Specifications for successful replacement projects. The User’s Design Specification is the central document in procuring ASME heat exchangers. Properly stated objectives for the heat exchanger replacement are essential for obtaining the materials, configurations and thermal designs best suited for the nuclear power plant. Additionally, the code of construction required and the applied manufacturing standard (TEMA or HEI) affects how the heat exchanger may be designed or configured to meet the replacement goals. Knowledge of how Codes and Standards affect design and configuration details will aid in writing the User’s Design Specification. Joseph Oat Corporation has designed and fabricated many replacement heat exchangers for the nuclear power industry. These heat exchangers have been constructed per ASME Section III to various Code-Years or ASME Section VIII-1 to the current Code-Year also in accordance with TEMA and HEI. These heat exchangers have been a range of like-for-like replacement to complete thermal, material and configuration redesigns. Several examples of these heat exchangers with their Code, Standard and specification implications are presented. (Author.

A Low-Cost Vehicle Anti-Theft System Using Obsolete Smartphone

Directory of Open Access Journals (Sweden)

Bang Liu

2018-01-01

Full Text Available In modern society, vehicle theft has become an increasing problem to the general public. Deploying onboard anti-theft systems could relieve this problem, but it often requires extra investment for vehicle owners. In this paper, we propose the idea of PhoneInside, which does not need a special device but leverages an obsolete smartphone to build a low-cost vehicle anti-theft system. After being fixed in the vehicle body with a car charger, the smartphone can detect vehicle movement and adaptively use GPS, cellular/WiFi localization, and dead reckoning to locate the vehicle during driving. Especially, a novel Velocity-Aware Dead Reckoning (VA-DR method is presented, which utilizes map knowledge and vehicle’s turns at road curves and intersections to estimate velocity for trajectory computation. Compared to traditional dead reckoning, it reduces accumulated errors and achieves great improvement in localization accuracy. Furthermore, based on the learning of the driving history, our system can establish individual mobility model for a vehicle and distinguish abnormal driving behaviors by a Long Short Term Memory (LSTM network. With the help of ad hoc authentication, the system can identify vehicle theft and send out timely alarming and tracking messages for rapid recovery. The realistic experiments running on Android smartphones prove that our system can detect vehicle theft effectively and locate a stolen vehicle accurately, with average errors less than the sight range.

Fiscal 1999 report on basic research for promotion of joint implementation programs. Research on potential for higher energy efficiency through instrumentation, control, and energy saving equipment (Research report); 1999 nendo keisoku seigyo oyobi sho energy kiki ni yoru sho energy potential chosa hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-03-01

As part of the 'clean development mechanism (CDM)' activities to be conducted by advanced nations jointly with developing nations, a survey is conducted of potential for higher energy efficiency, the effect of greenhouse gas reduction, and the effect of related investments in Egypt's textile (dyeing) industry. As the result, it is found that the Egyptian textile (dyeing) industry is rich in potential for higher energy efficiency and that intensification of energy management with importance attached to instrumentation will be quite effective. Private plants, though small in scale, enjoy a high operating rate and are full of life. As for their energy management, however, though management oriented instrumentation is found to stay without being scattered or lost in case of newly introduced equipment, normal operation is impeded by damaged parts which are not duly repaired or replaced. As for state operated plants, they are large in scale and are provided with some leading-edge facilities. Many of them are obsolete, however, and a privatization plan is under consideration, these discouraging investors and reducing vitality. Operation control or quality control are not sufficiently practiced in the administration of plants, and they need improvement. (NEDO)

Fast Flux Test Facility replacement of a primary sodium pump

International Nuclear Information System (INIS)

Krieg, S.A.; Thomson, J.D.

1985-01-01

The Fast Flux Test Facility is a 400 MW Thermal Sodium Cooled Fast Reactor operated by Westinghouse Hanford Company for the US Department of Energy. During startup testing in 1979, the sodium level in one of the primary sodium pumps was inadvertently raised above the normal height. This resulted in distortion of the pump shaft. Pump replacement was carried out using special maintenance equipment. Nuclear radiation and contamination were not significant problems since replacement operations were carried out shortly after startup of the Fast Flux Test Facility

Development of an automated system for the operation of an electron beam accelerator

International Nuclear Information System (INIS)

Somessari, Samir L.; Moura, João A.; Calvo, Wilson Ap. Parejo

2017-01-01

Electron beam accelerators are used in many applications, such as basic physical research, chemistry, medicine, molecular biology, microelectronics, agriculture and industry, among others. The majority of the accelerators have electrons from a hot tungsten filament and their energy is increased as it passes through an electric field in the vacuum chamber. For industrial purposes, the most common model is Dynamitrons®. At IPEN-CNEN/SP, there is an electron beam accelerator Dynamitron® Type (Manufactured by RDI- Radiation Dynamics Inc., 1978) model DC1500/25/4. The technology applied was available in the 60's and 70's, but, nowadays is obsolete. Moreover, there are not original spare parts for this equipment any longer. The aim of this work is to develop a nationalized automated operation system for the accelerator, to replace the old equipment. (author)

Development of an automated system for the operation of an electron beam accelerator

Energy Technology Data Exchange (ETDEWEB)

Somessari, Samir L.; Moura, João A.; Calvo, Wilson Ap. Parejo, E-mail: somessar@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2017-11-01

Electron beam accelerators are used in many applications, such as basic physical research, chemistry, medicine, molecular biology, microelectronics, agriculture and industry, among others. The majority of the accelerators have electrons from a hot tungsten filament and their energy is increased as it passes through an electric field in the vacuum chamber. For industrial purposes, the most common model is Dynamitrons®. At IPEN-CNEN/SP, there is an electron beam accelerator Dynamitron® Type (Manufactured by RDI- Radiation Dynamics Inc., 1978) model DC1500/25/4. The technology applied was available in the 60's and 70's, but, nowadays is obsolete. Moreover, there are not original spare parts for this equipment any longer. The aim of this work is to develop a nationalized automated operation system for the accelerator, to replace the old equipment. (author)

Solid-State Thyratron Replacement. Final Report

Energy Technology Data Exchange (ETDEWEB)

Roth, Ian [Diversified Technologies, Inc., Bedford, MA

2017-12-12

Under this SBIR, DTI developed a solid-state switch as an alternative to legacy thyratron equipment. Our Phase II objective was to make a solid-state thyratron replacement that would provide equivalent or better performance, much higher reliability (at least a 20 year lifetime, compared to a thyratron’s two-year lifetime) and would sell for ~3x the cost of a thyratron, or less than $40k. We were successful in building a solid-state switch which could reliably function as a thyratron replacement. The unit was designed to directly replace the thyratrons currently being used at SLAC’s Linac Coherent Light Source (LCLS), and was built in a tank that was small enough to fit into the existing thyratron cabinet, providing a true form-fit-function replacement path. We tested the switch at the full operating specifications: 48 kV, 6.3 kA, and 1 µs risetime. We also demonstrated a peak-to-peak pulse jitter of 1.5 ns, which is five times shorter than is typical for thyratrons. This lower jitter would improve the performance of the LCLS beam. The predicted reliability is more than 80 years, which is 40 times greater than a thyratron.

A methodological framework applied to the choice of the best method in replacement of nuclear systems

International Nuclear Information System (INIS)

Vianna Filho, Alfredo Marques

2009-01-01

The economic equipment replacement problem is a central question in Nuclear Engineering. On the one hand, new equipment are more attractive given their best performance, better reliability, lower maintenance cost etc. New equipment, however, require a higher initial investment. On the other hand, old equipment represent the other way around, with lower performance, lower reliability and specially higher maintenance costs, but in contrast having lower financial and insurance costs. The weighting of all these costs can be made with deterministic and probabilistic methods applied to the study of equipment replacement. Two types of distinct problems will be examined, substitution imposed by the wearing and substitution imposed by the failures. In order to solve the problem of nuclear system substitution imposed by wearing, deterministic methods are discussed. In order to solve the problem of nuclear system substitution imposed by failures, probabilistic methods are discussed. The aim of this paper is to present a methodological framework to the choice of the most useful method applied in the problem of nuclear system substitution.(author)

Determining Optimal Replacement Policy with an Availability Constraint via Genetic Algorithms

OpenAIRE

Zong, Shengliang; Chai, Guorong; Su, Yana

2017-01-01

We develop a model and a genetic algorithm for determining an optimal replacement policy for power equipment subject to Poisson shocks. If the time interval of two consecutive shocks is less than a threshold value, the failed equipment can be repaired. We assume that the operating time after repair is stochastically nonincreasing and the repair time is exponentially distributed with a geometric increasing mean. Our objective is to minimize the expected average cost under an availability requi...

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.

Development Of Remote Hanford Connector Gasket Replacement Tooling For DWPF

International Nuclear Information System (INIS)

Krementz, D.; Coughlin, Jeffrey

2009-01-01

The Defense Waste Processing Facility (DWPF) requested the Savannah River National Laboratory (SRNL) to develop tooling and equipment to remotely replace gaskets in mechanical Hanford connectors to reduce personnel radiation exposure as compared to the current hands-on method. It is also expected that radiation levels will continually increase with future waste streams. The equipment is operated in the Remote Equipment Decontamination Cell (REDC), which is equipped with compressed air, two master-slave manipulators (MSM's) and an electro-mechanical manipulator (EMM) arm for operation of the remote tools. The REDC does not provide access to electrical power, so the equipment must be manually or pneumatically operated. The MSM's have a load limit at full extension of ten pounds, which limited the weight of the installation tool. In order to remotely replace Hanford connector gaskets several operations must be performed remotely, these include: removal of the spent gasket and retaining ring (retaining ring is also called snap ring), loading the new snap ring and gasket into the installation tool and installation of the new gasket into the Hanford connector. SRNL developed and tested tools that successfully perform all of the necessary tasks. Removal of snap rings from horizontal and vertical connectors is performed by separate air actuated retaining ring removal tools and is manipulated in the cell by the MSM. In order install a new gasket, the snap ring loader is used to load a new snap ring into a groove in the gasket installation tool. A new gasket is placed on the installation tool and retained by custom springs. An MSM lifts the installation tool and presses the mounted gasket against the connector block. Once the installation tool is in position, the gasket and snap ring are installed onto the connector by pneumatic actuation. All of the tools are located on a custom work table with a pneumatic valve station that directs compressed air to the desired tool and

Measurement and control system for ITER remote maintenance equipment

Energy Technology Data Exchange (ETDEWEB)

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

1998-04-01

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

Measurement and control system for ITER remote maintenance equipment

International Nuclear Information System (INIS)

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

1998-01-01

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

Reduction rules-based search algorithm for opportunistic replacement strategy of multiple life-limited parts

Directory of Open Access Journals (Sweden)

Xuyun FU

2018-01-01

Full Text Available The opportunistic replacement of multiple Life-Limited Parts (LLPs is a problem widely existing in industry. The replacement strategy of LLPs has a great impact on the total maintenance cost to a lot of equipment. This article focuses on finding a quick and effective algorithm for this problem. To improve the algorithm efficiency, six reduction rules are suggested from the perspectives of solution feasibility, determination of the replacement of LLPs, determination of the maintenance occasion and solution optimality. Based on these six reduction rules, a search algorithm is proposed. This search algorithm can identify one or several optimal solutions. A numerical experiment shows that these six reduction rules are effective, and the time consumed by the algorithm is less than 38 s if the total life of equipment is shorter than 55000 and the number of LLPs is less than 11. A specific case shows that the algorithm can obtain optimal solutions which are much better than the result of the traditional method in 10 s, and it can provide support for determining to-be-replaced LLPs when determining the maintenance workscope of an aircraft engine. Therefore, the algorithm is applicable to engineering applications concerning opportunistic replacement of multiple LLPs in aircraft engines.

Life Cycle Management for Equipments in Nuclear Plants Based on Reliability

International Nuclear Information System (INIS)

Wang Dalin; Sun Jinlong

2012-01-01

Life cycle management model based on reliability includes two parts: obtaining failure rate function and founding cost-oriented model to solve. It is actually a single objective programming whose optimal solution is the most economical replacement period. Parameters of failure rate function are estimated by Weibull process fitting with the method of maximum likelihood. The objective function of the model is life-cost function where the dependent variable is replacement period T, with the constraints of failure rate or availability. After foundation of LCM model, we solve it to find the optimal replacement period for the equipments. (author)

Supporting management of medical equipment for inpatient service in public hospitals: a case study.

Science.gov (United States)

Figueroa, Rosa L; Vallejos, Guido E

2013-01-01

This work presents a study of medical equipment availability in the short and long term. The work is divided in two parts. The first part is an analysis of the medical equipment inventory for the institution of study. We consider the replacement, maintenance, and reinforcement of the available medical equipment by considering local guidelines and surveying clinical personnel appreciation. The resulting recommendation is to upgrade the current equipment inventory if necessary. The second part considered a demand analysis in the short and medium term. We predicted the future demand with a 5-year horizon using Holt-Winters models. Inventory analysis showed that 27% of the medical equipment in stock was not functional. Due to this poor performance result we suggested that the hospital gradually addresses this situation by replacing 29 non-functional equipment items, reinforcing stock with 40 new items, and adding 11 items not available in the inventory but suggested by the national guidelines. The results suggest that general medicine inpatient demand has a tendency to increase within the time e.g. for general medicine inpatient service the highest increment is obtained by respiratory (12%, RMSE=8%) and genitourinary diseases (20%, RMSE=9%). This increment did not involve any further upgrading of the proposed inventory.

A typewriting system operated by head movements, based on home-computer equipment.

Science.gov (United States)

Heuvelmans, A M; Mélotte, H E; Neve, J J

1990-06-01

For persons who cannot move their hands and legs we have designed a relatively inexpensive typewriting system which can be operated by movements of the head. The typewriter is made up of commercially available home computer equipment - i e, a computer including monitor and printer and a headset replacing the mouse. A user-friendly software program has been designed to replace the mouse button and to make this equipment act as a typewriter with simple text-editing features. Some ergonomics aspects of the typewriter set-up and the results of an evaluation of the typewriter by two patients suffering from amyotrophic lateral sclerosis (ALS) are given. Several factors relevant to the design, construction, evaluation and application of the typewriter are discussed.

EPERC: The European Pressure Equipment Research Council

International Nuclear Information System (INIS)

Darlaston, J.; McAllister, S.

1998-01-01

The European Pressure Equipment Research Council (EPERC) is a European Network of industries, research laboratories, inspection bodies and governmental institutions set up to foster co-operative research for the greater benefit of the European industry. The concept of a European Research Council originated at the PVRC meeting in Cannes in 1989 and since this time volunteers from the industry, research laboratories and of the European Commission Joint Research Centre, Petten have worked together to create a Statute for EPERC. In the context of the pressure equipment industry, the creation of EPERC is extremely pertinent, since in the near future, a Council directive on pressure equipment will replace the existing national regulations. In parallel to this, work is in progress for the elaboration of European Standards. It is useful to recall that ''Harmonised Standards'' will be the privileged means of complying with the Essential Safety Requirements of the directive. (author)

Capital renewal as a real option

NARCIS (Netherlands)

Reindorp, M.J.; Fu, M.C.

2011-01-01

We consider the timing of replacement of obsolete subsystems within an extensive, complex infrastructure. Such replacement action, known as capital renewal, must balance uncertainty about future profitability against uncertainty about future renewal costs. Treating renewal investments as real

The tendency of medical electrical equipment - IEC 60601-2-54: Particular requirements for the basic safety and essential performance of x-ray equipment for radiography and radioscopy

International Nuclear Information System (INIS)

Roh, Young Hoon; Kim, Jung Min

2015-01-01

Medical electrical equipment - Part 1: General requirement for basic safety and essential performance of MFDS was revised as 3th edition and Medical electrical equipment Part 2-54: Particular requirements for the basic safety and essential performance of X-ray equipment will be expected to be announced as notification. Therefore this technical report was written to introduce provision of the particular requirements, replacement, addition, amendment. The purpose of this particular requirements is to secure requirements for basic safety and essential performance of X-ray equipment for radiography and radioscopy. X-ray high voltage generator, mechanical protective device, protection against radiation is included in this particular requirements. Medical electrical equipment - Part 1, Part 1-2, Part 1-3 is applied to this particular requirements. If the requirements is announced as notification, It is expected to widen understanding for basic safety and essential performance of X-ray equipment for radiography and radioscopy and play a part to internationalize of medical equipment

Equipment for maintenance and repair of 900 MW PWR units in France

International Nuclear Information System (INIS)

Blary, F.; Castaing, C.; Haessig, M.

1984-01-01

As of March 1984, Electricite de France has been operating twenty-seven 900 MW PWR power units. To cut down unit unavailability and reduce the dosimetric requirements of maintenance staff, a wide range of special devices for inspecting and repairing equipment has been designed; details of 64 operational devices and a further 18 still being developed are given in a maintenance catalogue. This special equipment, together with maintenance and repair procedures, has been devised in collaboration with Framatome, the constructor of the nuclear island. One particular problem resolved was that of replacing the pins of the upper internals (UI) of 21 operational units, preventive measures having been taken at the other units. The strategy adopted consisted, first, in setting up a pin-changing workshop to enable the pins and guide tubes to be replaced separately and, second, in devising and applying wherever possible a method for partially replacing the guide tubes outside the critical path of the outage by means of a mobile pool known as the 'Aquarium'. (author)

Department of Energy: Opportunities Exist to Improve Los Alamos' Equipment Purchasing Practices

National Research Council Canada - National Science Library

2001-01-01

In fiscal year 2000, the Department of Energy (DOE) received $13.2 million in supplemental funding to replace equipment lost in the May 2000 Cerro Grande fire that damaged the Los Alamos National Laboratory...

Hoisting appliances and fuel handling equipment at nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-12-31

The guide is followed by the Finnish Centre for Radiation and Nuclear Safety (STUK) in regulating hoisting and handling equipment Class 3 at nuclear facilities. The guide is applied e.g. to the following equipment: reactor building overhead cranes, hoisting appliances at nuclear fuel storages, fuel handling machines, other hoisting appliances, which because of nuclear safety aspects are classified in Safety Class 3, and load-bearing devices connected with the above equipment, such as replaceable hoisting tools and auxiliary lifting devices. The regulating of hoisting and handling equipment comprises the following stages: handling of preliminary and final safety analysis reports, inspection of the construction plan, supervision of fabrication and construction inspection, and supervision of initial start-up and commissioning inspection. 36 refs. Translation. The original text is published under the same guide number. The guide is valid from 5 January 1987 and will be in force until further notice.

Upgrade of the computer-based information systems on USNRC simulators

International Nuclear Information System (INIS)

Griffin, J.I.

1998-01-01

In late 1995, the U.S. Nuclear Regulatory Commission (USNRC) began a project to upgrade the computer-based information systems on its BWR/6 and BandW Simulators. The existing display generation hardware was very old and in need of replacement due to difficulty in obtaining spare parts and technical support. In addition, the display systems used currently each require a SEL 32/55 computer system, which is also obsolete, running the Real Time Monitor (RTM) operating system. An upgrade of the display hardware and display generation systems not only solves the problem of obsolescence of that equipment but also allows removal of the 32/55 systems. These computers are used only to support the existing display generation systems. Shortly after purchase of the replacement equipment, it was learned that the vendor was no longer going to support the methodology. Instead of implementing an unsupported concept, it was decided to implement the display systems upgrades using the Picasso-3 UIMS (User Interface Management System) and the purchased hardware. This paper describes the upgraded display systems for the BWR/6 and BandW Simulators, including the design concept, display development, hardware requirements, the simulator interface software, and problems encountered. (author)

Nuclear equipment recalsification based on the service experience

International Nuclear Information System (INIS)

Geambasu, A.; Segarceanu, D.

2000-01-01

The paper presents some considerations concerning the need of comparison between equipment performance proven by test and the service experience in Cernavoda Nuclear Plant. Service performance dana obtain partly from service failures (failures times) and partly from service experience without failure (running times) can be statistically analyzed to obtain predictions of the number of failures of unfailed units in specified period of time, means time to first failure, means time of median failure, a.s.o. These informations can be used during the operation of Nuclear Power Plant to estimate when a equipment should be replaced with a new one in order to prevent getting to the life end point. (author)

Remotely replaceable fuel and feed nozzles for the NWCF calciner vessel

International Nuclear Information System (INIS)

Fletcher, R.D.; Carter, J.A.; May, K.W.

1978-01-01

The development and testing of remotely replaceable fuel and feed nozzles for calcination of liquid radioactive wastes in the calciner vessel of the New Waste Calcining Facility (NWCF) being built at the Idaho National Engineering Laboratory are described. A complete fuel nozzle assembly was fabricated and tested at the Remote Maintenance Development Facility to evolve design refinements, identify required support equipment, and develop handling techniques. The design also provided for remote replacement of the nozzle support carriage and adjacent feed and fuel pipe loops using two pairs of master-slave manipulators

Replacement of the computerized control system at NPP under operation

International Nuclear Information System (INIS)

Ermolaev, A.D.; Rakitin, I.D.

1985-01-01

Reasons and preconditions for replacement of the computerized control systems (CCS) at NPP under operation are consi-- dered. Problems dealing with management of CCS replacement, maintenance of a new CCS as well as NPP personnel training for the new system maintenance are discussed. A necessity of NPP personnel participation in these works in order to adapt CCS to requirements of NPP operation personnel and to initiate the training process is underlined. Replacement of CCS at NPP under operation is associated, as a rule, with obsolescence of old systems not ensuring growing requirements to NPP workability and safety. Principles observed at CCS replacement are reduced, mainly, to the following; maximum utilizatian of existing equipment, metal strUctures, cables, instruments, power supplies, ventilation system minimum of construction works and new communications; the least change of acting panels and boxes; changes in control desks should be introduced on the basis of the analysis of operator actions '

Safety Review related to Commercial Grade Digital Equipment in Safety System

International Nuclear Information System (INIS)

Yu, Yeongjin; Park, Hyunshin; Yu, Yeongjin; Lee, Jaeheung

2013-01-01

The upgrades or replacement of I and C systems on safety system typically involve digital equipment developed in accordance with non-nuclear standards. However, the use of commercial grade digital equipment could include the vulnerability for software common-mode failure, electromagnetic interference and unanticipated problems. Although guidelines and standards for dedication methods of commercial grade digital equipment are provided, there are some difficulties to apply the methods to commercial grade digital equipment for safety system. This paper focuses on regulatory guidelines and relevant documents for commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. This paper focuses on KINS regulatory guides and relevant documents for dedication of commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. Dedication including critical characteristics is required to use the commercial grade digital equipment on safety system in accordance with KEPIC ENB 6370 and EPRI TR-106439. The dedication process should be controlled in a configuration management process. Appropriate methods, criteria and evaluation result should be provided to verify acceptability of the commercial digital equipment used for safety function

Electrical and control equipment in nuclear power plants. Problems when replacing aging equipment; El och kontrollutrustning i kaernkraftverk - Problematik vid utbyte av aaldrad utrustning

Energy Technology Data Exchange (ETDEWEB)

Nordling, Anna; Haakansson, Goeran

2012-11-01

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

Development of support system for maintenance and administration of reprocessing plant equipment

International Nuclear Information System (INIS)

Iwasaki, Syogo; Taniguchi, Takayuki; Shiraishi, Yoshihiko; Isaka, Kazuo

1998-01-01

Each year, maintenance work is carried out for about 10,000 pieces of equipment, including mechanical devices, electric equipment and instruments, at the Tokai Reprocessing Plant. Ninety percent of such maintenance work is preventive maintenance. In order to manage the information about the maintenance work, a computer support system was developed between 1985 and 1992. Twenty-seven thousand pieces of equipment and 180,000 maintenance histories have already been registered in the system. The system has been used for planning inspections and replacement of equipment as well as checking their maintenance histories. Actual usage of the system has shown that some auxiliary functions need to be added. The system will therefore be improved and extended. (author)

Guideline for design and construction radiation monitoring equipments for Tokai reprocessing plant

International Nuclear Information System (INIS)

Miyabe, Kenjiro; Ninomiya, Kazushige; Jin, Kazumi; Morifuji, Masayuki; Nemoto, Kazuhiko; Sato, Akira; Kawai, Keiichi

1999-12-01

Various kind of radiation monitoring equipment are used in radiation controlled area at each facility of Tokai reprocessing plant. These equipments have been designed and constructed based on the users requirements, and permitted by governmental regulation office. And, design has been carried out in consideration of the adoption of the new technology and our operational experience. Then, it has been used effectively for the radiation control of the facilities. This report summarizes the technical requirements that should be taken into consideration in the design and installation of radiation monitoring equipments. These requirements are fundamentally applicable when the equipments of the new facilities will be designed or the present instruments will be replaced. (author)

Proposed replacement and operation of the anhydrous hydrogen fluoride supply and fluidized-bed chemical processing systems at Building 9212, Y-12 Plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1995-09-01

The US Department of Energy (DOE) proposes to replace the existing anhydrous hydrogen fluoride (AHF) supply and fluidized-bed reactor systems for the Weapons Grade Highly Enriched Uranium Chemical Recovery and Recycle Facility, Building 9212, which is located within the Y-12 Plant on DOE's Oak Ridge Reservation in Oak Ridge, Tennessee. The proposed replacement system would be based upon modern design criteria and safety analyses. The replacement AHF supply and distribution system equipment would be located on the existing Dock 8/8A at Building 9212. Utilities would be extended to the dock to service the process equipment. The following process equipment modules would be prefabricated for installation at the modified dock: an AHF cylinder enclosure, an AHF supply manifold and vaporizer module, an AHF sump tank and transfer skid, and an AHF supply off-gas scrubber assembly module. The fluidized-bed reactor system would be constructed in an area adjacent to the existing system in Building 9212. The replacement equipment would consist of a new reduction fluidized-bed reactor, a hydrofluorination fluidized-bed reactor, and associated air emission control equipment. The no-action alternative, which is the continued operation of the existing AHF supply and fluidized-bed reactor systems, was also evaluated

Organochlorine pesticides in surface soils from obsolete pesticide dumping ground in Hyderabad City, Pakistan: contamination levels and their potential for air-soil exchange.

Science.gov (United States)

Alamdar, Ambreen; Syed, Jabir Hussain; Malik, Riffat Naseem; Katsoyiannis, Athanasios; Liu, Junwen; Li, Jun; Zhang, Gan; Jones, Kevin C

2014-02-01

This study was conducted to examine organochlorine pesticides (OCPs) contamination levels in the surface soil and air samples together with air-soil exchange fluxes at an obsolete pesticide dumping ground and the associated areas from Hyderabad City, Pakistan. Among all the sampling sites, concentrations of OCPs in the soil and air samples were found highest in obsolete pesticide dumping ground, whereas dominant contaminants were dichlorodiphenyltrichloroethane (DDTs) (soil: 77-212,200 ng g(-1); air: 90,700 pg m(-3)) and hexachlorocyclohexane (HCHs) (soil: 43-4,090 ng g(-1); air: 97,400 pg m(-3)) followed by chlordane, heptachlor and hexachlorobenzene (HCB). OCPs diagnostic indicative ratios reflect historical use as well as fresh input in the study area. Moreover, the air and soil fugacity ratios (0.9-1.0) at the dumping ground reflecting a tendency towards net volatilization of OCPs, while at the other sampling sites, the fugacity ratios indicate in some cases deposition and in other cases volatilization. Elevated concentrations of DDTs and HCHs at pesticide dumping ground and its surroundings pose potential exposure risk to biological organisms, to the safety of agricultural products and to the human health. Our study thus emphasizes the need of spatio-temporal monitoring of OCPs at local and regional scale to assess and remediate the future adverse implications. © 2013.

Optimising reverse logistics network to support policy-making in the case of Electrical and Electronic Equipment.

Science.gov (United States)

Achillas, Ch; Vlachokostas, Ch; Aidonis, D; Moussiopoulos, N; Iakovou, E; Banias, G

2010-12-01

Due to the rapid growth of Waste Electrical and Electronic Equipment (WEEE) volumes, as well as the hazardousness of obsolete electr(on)ic goods, this type of waste is now recognised as a priority stream in the developed countries. Policy-making related to the development of the necessary infrastructure and the coordination of all relevant stakeholders is crucial for the efficient management and viability of individually collected waste. This paper presents a decision support tool for policy-makers and regulators to optimise electr(on)ic products' reverse logistics network. To that effect, a Mixed Integer Linear Programming mathematical model is formulated taking into account existing infrastructure of collection points and recycling facilities. The applicability of the developed model is demonstrated employing a real-world case study for the Region of Central Macedonia, Greece. The paper concludes with presenting relevant obtained managerial insights. Copyright © 2010 Elsevier Ltd. All rights reserved.

Benefits Of Vibration Analysis For Development Of Equipment In HLW Tanks - 12341

International Nuclear Information System (INIS)

Stefanko, D.; Herbert, J.

2012-01-01

Vibration analyses of equipment intended for use in the Savannah River Site (SRS) radioactive liquid waste storage tanks are performed during pre-deployment testing and has been demonstrated to be effective in reducing the life-cycle costs of the equipment. Benefits of using vibration analysis to identify rotating machinery problems prior to deployment in radioactive service will be presented in this paper. Problems encountered at SRS and actions to correct or lessen the severity of the problem are discussed. In short, multi-million dollar cost saving have been realized at SRS as a direct result of vibration analysis on existing equipment. Vibration analysis of equipment prior to installation can potentially reduce inservice failures, and increases reliability. High-level radioactive waste is currently stored in underground carbon steel waste tanks at the United States Department of Energy (DOE) Savannah River Site and at the Hanford Site, WA. Various types of rotating machinery (pumps and separations equipment) are used to manage and retrieve the tank contents. Installation, maintenance, and repair of these pumps and other equipment are expensive. In fact, costs to remove and replace a single pump can be as high as a half million dollars due to requirements for radioactive containment. Problems that lead to in-service maintenance and/or equipment replacement can quickly exceed the initial investment, increase radiological exposure, generate additional waste, and risk contamination of personnel and the work environment. Several different types of equipment are considered in this paper, but pumps provide an initial example for the use of vibration analysis. Long-shaft (45 foot long) and short-shaft (5-10 feet long) equipment arrangements are used for 25-350 horsepower slurry mixing and transfer pumps in the SRS HLW tanks. Each pump has a unique design, operating characteristics and associated costs, sometimes exceeding a million dollars. Vibration data are routinely

BENEFITS OF VIBRATION ANALYSIS FOR DEVELOPMENT OF EQUIPMENT IN HLW TANKS - 12341

Energy Technology Data Exchange (ETDEWEB)

Stefanko, D.; Herbert, J.

2012-01-10

Vibration analyses of equipment intended for use in the Savannah River Site (SRS) radioactive liquid waste storage tanks are performed during pre-deployment testing and has been demonstrated to be effective in reducing the life-cycle costs of the equipment. Benefits of using vibration analysis to identify rotating machinery problems prior to deployment in radioactive service will be presented in this paper. Problems encountered at SRS and actions to correct or lessen the severity of the problem are discussed. In short, multi-million dollar cost saving have been realized at SRS as a direct result of vibration analysis on existing equipment. Vibration analysis of equipment prior to installation can potentially reduce inservice failures, and increases reliability. High-level radioactive waste is currently stored in underground carbon steel waste tanks at the United States Department of Energy (DOE) Savannah River Site and at the Hanford Site, WA. Various types of rotating machinery (pumps and separations equipment) are used to manage and retrieve the tank contents. Installation, maintenance, and repair of these pumps and other equipment are expensive. In fact, costs to remove and replace a single pump can be as high as a half million dollars due to requirements for radioactive containment. Problems that lead to in-service maintenance and/or equipment replacement can quickly exceed the initial investment, increase radiological exposure, generate additional waste, and risk contamination of personnel and the work environment. Several different types of equipment are considered in this paper, but pumps provide an initial example for the use of vibration analysis. Long-shaft (45 foot long) and short-shaft (5-10 feet long) equipment arrangements are used for 25-350 horsepower slurry mixing and transfer pumps in the SRS HLW tanks. Each pump has a unique design, operating characteristics and associated costs, sometimes exceeding a million dollars. Vibration data are routinely

Practices of prolongation of the I and C equipment lifetime

International Nuclear Information System (INIS)

Samoylov, O.B.; Pronin, V.S.; Savelov, I.D.; Bogomazov, V.A.; Drumov, V.V.; Chudin, A.G.

2000-01-01

The lifetime of nuclear power plants (NPP) always exceeds the operational time of Instrumentation and Control (I and C) systems. Ageing of I and C equipment in NPPs have many aspects. Research of these aspects is being performed in OKB Mechanical Engineering. Under condition of fast development of I and C systems and applying more stringent safety requirements, modernization of the equipment irrespective of its operational condition is getting important. However, an equipment of I and C systems operated in Russia was designed and manufactured applying highest requirements for a reliability of their work during its whole operational time. Therefore, in many cases it is not necessary to replace them in spite of expiration of their specified lifetime. During operation this equipment is maintained in a proper operation condition by a special service procedures stipulated by its development. When the equipment lifetime approaches to its end, lifetime extension for the certain period should be considered. (author)

Incidence and Trends of Six Types of Cancer in Populations Environmentally Exposed to Obsolete Pesticides in the Colombian State of Cesar

International Nuclear Information System (INIS)

Rojas H, Martha P

2009-01-01

Objective: To determine incidence and trends related to the appearance of bladder, kidney, non melanoma skin (except head and neck),lung, liver and colon cancer in the State of Cesar and in the entirety of its municipalities from January 1, 1998-December 31, 2006. Methods: A descriptive, transverse epidemiologic study carried out in the municipalities of the State of Cesar where environmental exposure to obsolete or near obsolete pesticides had occurred. Census of secondary information sources was conducted at main geographical points where state residents sought medical care. Active data collection (at the source) was employed in accordance with Population Cancer Registry. Results: In the State of Cesar, between 1998-2006, average annual percentage and statistically significant changes occurred in the incidence of lung, colon, and rectal cancers for both sexes, and of non melanoma skin cancer for men. The municipalities of Agustin Codazzi and El Copey revealed age standard rates (ASR) above the state average for liver cancer in both sexes, and for bladder cancer in women. Gender related multiple ASR for the municipalities of Valledupar, Aguachica, Pailitas and La Paz stood out with respectively higher ASR than that for the entire State of Cesar. Conclusions: It is possible that there is a statistical and geospatial association between the incidence of the following cancers and the environmental exposure to PLADES: (a) bladder cancer in women, in Agustin Codazzi and El Copey; (b) bladder cancer in men, only in El Copey, and (c) non melanoma skin cancer in men, only in Agustin Codazzi.

With the Advent of Tomosynthesis in the Workup of Mammographic Abnormality, is Spot Compression Mammography Now Obsolete? An Initial Clinical Experience.

Science.gov (United States)

Ni Mhuircheartaigh, Neasa; Coffey, Louise; Fleming, Hannah; O' Doherty, Ann; McNally, Sorcha

2017-09-01

To determine if the routine use of spot compression mammography is now obsolete in the assessment of screen detected masses, asymmetries and architectural distortion since the availability of digital breast tomosynthesis. We introduced breast tomosynthesis in the workup of screen detected abnormalities in our screening center in January 2015. During an initial learning period with tomosynthesis standard spot compression views were also performed. Three consultant breast radiologists retrospectively reviewed all screening mammograms recalled for assessment over the first 6-month period. We assessed retrospectively whether there was any additional diagnostic information obtained from spot compression views not already apparent on tomography. All cases were also reviewed for any additional lesions detected by tomosynthesis, not detected on routine 2-view screening mammography. 548 women screened with standard 2-view digital screening mammography were recalled for assessment in the selected period and a total of 565 lesions were assessed. 341 lesions were assessed by both tomosynthesis and routine spot compression mammography. The spot compression view was considered more helpful than tomosynthesis in only one patient. This was because the breast was inadequately positioned for tomosynthesis and the area in question was not adequately imaged. Apart from this technical error there was no asymmetry, distortion or mass where spot compression provided more diagnostic information than tomosynthesis alone. We detected three additional cancers on tomosynthesis, not detected by routine screening mammography. From our initial experience with tomosynthesis we conclude that spot compression mammography is now obsolete in the assessment of screen detected masses, asymmetries and distortions where tomosynthesis is available. © 2017 Wiley Periodicals, Inc.

Steam generator replacement at Surry Power Station

International Nuclear Information System (INIS)

McKay, H.S.

1982-01-01

The purposes of the steam generator repair program at Surry Power Station were to repair the tube degradation caused by corrosion-related phenomena and to restore the integrity of the steam generators to a level equivalent to new equipment. The repair program consisted of (1) replacing the existing lower-shell assemblies with new ones and (2) adding new moisture separation equipment to the upper-shell assemblies. These tasks required that several pieces of reactor coolant piping, feedwater piping, main steam piping, and the steam generator be cut and refurbished for reinstallation after the new lower shell was in place. The safety implications and other potential effects of the repair program both during the repair work and after the unit was returned to power were part of the design basis of the repair program. The repair program has been completed on Unit 2 without any adverse effects on the health and safety of the general public or to the personnel engaged in the repair work. Before the Unit 1 repair program began, a review of work procedures and field changes for the Unit 2 repair was conducted. Several major changes were made to avoid recurrence of problems and to streamline procedures. Steam generator replacements was completed on June 1, 1981, and the unit is presently in the startup phase of the outrage

The development of techniques for determining the residual life time prediction on NPP equipment

International Nuclear Information System (INIS)

Antonov, Alexander V.; Dagaev, Alexander V.; Volnikov, Ivan S.

1999-01-01

The problem of determining the residual life prediction of NPP equipment is presently highly pressing. NPP residual life resources are 30 years, but for particular equipment it is much less. Thus, residual life resource for equipment of control and protection system of NPP unit is 5-10 years. The NPP equipment is expensive and its replacing requires much expense. Hence an urgent problem is to study residual life resources of equipment on the basis of statistic information obtained during operation. Deterministic approach of determining residual life resources for particular equipment is widely known in the literature. Physical and statistical models are also being developed for determining the residual life, e.g. the model (loading-bearing capability). The present work offers the techniques of the residual life determination reasoning from statistic information of functioning objects in the process of operation. To put the techniques into effect it is necessary to have information about the time of operation of a group of objects of the same type, the number of failures; it is desirable to know failure operating time, order of the object replacement and the reason which caused the replacement (failure or planned preventive maintenance). Metrics is based on studying the parameters for the series of failures resulted from real statistic data. Then we can proceed to distribution density of the failure working time. For this purpose the Voltarra's equation of the second order is solved f(t) = ω(t) + ∫ 0 t f(t - τ)ω(τ)dτ. Since statistics of data sampling related to failure is small due to difficulties in solution of Voltaire's equation, the authors offer moderate method of solution for the above equation. After distribution density of the failure working time is determined the calculation of equipment residual life is made by the following formula: T τ (t) 1/P(τ)∫ 0 ∞ P(t)dt. The proposed techniques are realised as the software. In the course of working

Safety benefits from CANDU reactor replacement - a case study

International Nuclear Information System (INIS)

Mottram, R.; Millard, J.W.F.; Purdy, P.

2011-01-01

Both total core replacement and core retubing have been used in the CANDU industry. For future plant refurbishments, based on experience both in new construction and in recent refurbishments, the concept of total core replacement has been revisited. This builds on practices for replacement of other large plant equipment like boilers. The Bruce CANDU reactors, with their local shield tanks built around the Calandria and containment closely located around that Calandria Shield Tank Assembly (CSTA), are believed to be good candidates for core replacement. A structured process was used to design a replacement CSTA suitable for Bruce A use. The work started with a study of opportunities for safety enhancements in the core. This progressed into design studies and related design assist safety analysis on the reactor. A key element of the work involved consideration of how verified features from later CANDU designs, and from our new reactor design work, could be tailored to fit this replacement core. The replacement reactor core brings in structural improvements in both calandria and end shield, and safety improvements like the natural circulation enhancing moderator cooling layout and further optimized reactivity layouts to improve shutdown system performance. Bruce Power are currently studying the business implications of this and retube techniques as part of preparation for future refurbishments. The work explained in this paper is in the context of the safety related changes and the work to choose and quantify them. (author)

Safety benefits from CANDU reactor replacement. A case study

International Nuclear Information System (INIS)

Mottram, R.; Millard, J.W.F.; Purdy, P.

2011-01-01

Both total core replacement and core retubing have been used in the CANDU industry. For future plant refurbishments, based on experience both in new construction and in recent refurbishments, the concept of total core replacement has been revisited. This builds on practices for replacement of other large plant equipment like boilers. The Bruce CANDU reactors, with their local shield tanks built around the Calandria and containment closely located around that Calandria Shield Tank Assembly (CSTA), are believed to be good candidates for core replacement. A structured process was used to design a replacement CSTA suitable for Bruce A use. The work started with a study of opportunities for safety enhancements in the core. This progressed into design studies and related design assist safety analysis on the reactor. A key element of the work involved consideration of how verified features from later CANDU designs, and from our new reactor design work, could be tailored to fit this replacement core. The replacement reactor core brings in structural improvements in both calandria and end shield, and safety improvements like the natural circulation enhancing moderator cooling layout and further optimized reactivity layouts to improve shutdown system performance. Bruce Power are currently studying the business implications of this and retube techniques as part of preparation for future refurbishments. The work explained in this paper is in the context of the safety related changes and the work to choose and quantify them. (author)

Experience acquired by Turboatom in the modernization of hydraulic turbines and associated equipment; Experiencia en la modernizacion de turbinas hidraulicas y equipos asociados acumulada por Turboatom

Energy Technology Data Exchange (ETDEWEB)

Veremeyenko, Igor S. [Turboatom, Jarkov (Ukraine)]. E-mail: office@turboatom.kharkov.ua; Kukalev, Viacheslav M. [Energomashexport, Moscow (Russian Federation)]. E-mail: nb_kuk@energomashexport. ru

2000-07-01

This work describes the experience acquired by TURBOATOM with hydroelectric turbines and related equipment modernization during the last years. The best parameters of the modernized equipment are obtained due to the replacement of the directional blades by the new ones with improved design, or replacement of the weared out parts.

Steam generator replacement at the Obrigheim nuclear power station

International Nuclear Information System (INIS)

Pickel, E.; Schenk, H.; Huemmler, A.

1984-01-01

The Obrigheim Nuclear Power Station (KWO) is equipped with a dual-loop pressurized water reactor of 345 MW electric power; it was built by Siemens in the period 1965 to 1968. By the end of 1983, KWO had produced some 35 billion kWh in 109,000 hours of operation. Repeated leaks in the heater tubes of the two steam generators had occurred since 1971. Both steam generators were replaced in the course of the 1983 annual revision. Kraftwerk Union AG (KWU) was commissioned to plant and carry out the replacement work. Despite the leakages the steam generators had been run safely and reliably over a period of 14 years until their replacement. Replacing the steam generators was completed within twelve weeks. In addition to the KWO staff and the supervising crew of KWU, some 400 external fitters were employed on the job at peak work-load periods. For the revision of the whole plant, work on the emergency systems and replacement of the steam generators a maximum number of approx. 900 external fitters were employed in the plant in addition to some 250 members of the plant crew. The exposure dose of the personnel sustained in the course of the steam generator replacement was 690 man-rem, which was clearly below previous estimates. (orig.) [de

Installation equipment for a glove box

International Nuclear Information System (INIS)

Loriot, P.

1993-01-01

The equipment uses a hollow support on which the glove to be replaced is mounted. It carries two grooves to ensure that the edges of the new and used glove are securely held in position. The new glove is temporarily fitted to a mounting ring using a mounting jig which stretches the edge of the new glove around its rim. The mounting ring is then positioned over the hollow support and the edge of the glove transferred onto it. (author)

Use of seismic experience data for technical evaluation of commercial grade replacement items

International Nuclear Information System (INIS)

Cushing, R.W.; Campbell, R.D.

1991-01-01

This paper reports that the purchase of commercial grade replacement items which are dedicated for use in nuclear safety related systems requires a technical evaluation for those items which cannot be purchased as like-for-like replacements. One of the requirements for performing a technical evaluation is verification of seismic adequacy. Studying the performance and failure modes of equipment which has been subjected to strong motion earthquakes has provided the industry with the ability to predict the behavior characteristics of many types of commonly replaced components and parts. The use of Seismic Experience Data has developed into an efficient means of satisfying the seismic adequacy requirement

Reactor console replacement at Washington State University

International Nuclear Information System (INIS)

Lovas, Thomas A.

1978-01-01

A replacement reactor console was installed in 1977 at the W.S.U. 1 MW TRIGA-fueled reactor as the final step in an instrumentation upgrade program. The program was begun circa 1972 with the design, construction and installation of various systems and equipment. Major instruments were installed in the existing console and tested in the course of reactor operation. The culmination of the program was the installation of a cubicle designed and constructed to house the updated instrumentation. (author)

Underground coal mining - methods, equipment developments and trends

Energy Technology Data Exchange (ETDEWEB)

Singhal, R

1988-12-01

Underground mines are truly beginning to accept the so-called 'high tech' technology evident in other industries. Automation, remote control and robotics have taken an added significance. Wireless communication, mine-wide equipment health and performance monitoring, and transmission of data from deeper levels to surface is moving towards becoming the norm. There is emphasis on developing and applying continuous mining systems, as well as on modifying cyclical discontinuous methods to continuous systems. Multi-purpose equipment is also being developed. Technology transfer is playing its role - equipment and systems from surface coal mining are being applied to underground mining and vice-versa. At the American Mining Congress Exhibition held in Chicago in April 1988, a variety of equipment for underground mining was displayed including coal face equipment such as shearer loaders, conveyors and powered supports, and equipment for room-and-pillar coal mining. The trend continues to be towards high power machines equipped with a variety of electronics and sensors, safety devices, and alarm systems. Ancillary equipment on display covered a variety of cutting drums, cutting tools, conveying equipment and so on. In room-and-pillar mining, the overall emphasis was on moving away from the cyclical nature of the work. Transportation by shuttle cars must be replaced by continuous transport systems such as conveyors. Experience from Australia has shown that the application of continuous haulage and breaker line supports has permitted a doubling of production from room-and-pillar systems. Production levels of 3,000tpd have already been achieved, and 4,000tpd is considered achievable.

10 CFR 830 Major Modification Determination for Advanced Test Reactor RDAS and LPCIS Replacement

Energy Technology Data Exchange (ETDEWEB)

David E. Korns

2012-05-01

The replacement of the ATR Control Complex's obsolete computer based Reactor Data Acquisition System (RDAS) and its safety-related Lobe Power Calculation and Indication System (LPCIS) software application is vitally important to ensure the ATR remains available to support this national mission. The RDAS supports safe operation of the reactor by providing 'real-time' plant status information (indications and alarms) for use by the reactor operators via the Console Display System (CDS). The RDAS is a computer support system that acquires analog and digital information from various reactor and reactor support systems. The RDAS information is used to display quadrant and lobe powers via a display interface more user friendly than that provided by the recorders and the Control Room upright panels. RDAS provides input to the Nuclear Engineering ATR Surveillance Data System (ASUDAS) for fuel burn-up analysis and the production of cycle data for experiment sponsors and the generation of the Core Safety Assurance Package (CSAP). RDAS also archives and provides for retrieval of historical plant data which may be used for event reconstruction, data analysis, training and safety analysis. The RDAS, LPCIS and ASUDAS need to be replaced with state-of-the-art technology in order to eliminate problems of aged computer systems, and difficulty in obtaining software upgrades, spare parts, and technical support. The major modification criteria evaluation of the project design did not lead to the conclusion that the project is a major modification. The negative major modification determination is driven by the fact that the project requires a one-for-one equivalent replacement of existing systems that protects and maintains functional and operational requirements as credited in the safety basis.

DEVELOPMENT OF OPERATING DRIVE SYSTEMS IN ENGINEERING EQUIPMENT

Directory of Open Access Journals (Sweden)

A. A. Kotlobai

2015-01-01

Full Text Available Engineering machines being in operational service with military units of  engineer troops are fit to their purpose and their application is relevant in modern conditions. Maintenance of operating conditions in engineering equipment which was produced earlier by the USSR enterprises is considered as a rather complicated task due to lack of spare parts because their production has been discontinued.One of the approaches used for maintenance of engineering equipment combat capabilities is modernization of operating drive systems that presupposes replacement of mechanical systems in working element drives by hydrostatic drives which are realized while using modern element base. Usage of hydraulic units in drive systems being in mass production for replacement of mechanical systems manufactured earlier in small batches makes it possible to reduce labour inputs for maintenance and repair of machines. The paper presents some possibilities for development of operating drive systems in engineering equipment. The proposed approach is given through an example of  engineering obstacle-clearing vehicle (IMR-2M and excavation machines (MDK-3 and MDK-2M.Application of a hydraulic drive in working elements of the excavation machines permits to withdraw from cardan  shafts, a gear box, a rotary gear and an overload clutch. A hydraulic motor of the cutter and thrower drive is mounted  on a working element gearbox. While executing modernization of hydraulic systems in excavation machines a pump unit has been proposed for the cutter and thrower drive which consists of a controlled pump and a system for automatic maintenance of the pump operational parameters. While developing the operating drive systems in engineering equipment in accordance with the proposed requirements it is possible to simplify drive systems of working elements and  ensure reliable machinery operation in the units of engineer troops. 

Cost justification of chiller replacement

International Nuclear Information System (INIS)

Baker, T.J.; Baumer, R.A.

1993-01-01

We often hear of products with paybacks that are too good to be true. Just a few weeks ago,a client received a recommendation from a national service company's local office. In the letter the company recommended that open-quotes due to the age and condition of the boiler ... that the school consider replacing the boiler... The cost for the new boiler can usually be recovered by lower fuel bills in 2 to 3 yearsclose quotes. This was for an installation in Southeast Texas where the boiler is only used 4 to 5 months per year. Analysis show the above claims to be nonsense. A new boiler would cost about $47,000 installed. Current total gas bills for the facility are $15,630 per year. They would have to shutoff the gas to the facility to have a three year payback. In fact, only two-thirds of the gas is used to heat the facility so we have only $10, 000 to write off against the new boiler. How much will the greater efficiency save? A 30% savings due to greater efficiency produces $3,000 per year in gas savings to offset the $47,000 cost, a 16 year payback. And much of the efficiency savings can be realized by adjusting the existing boiler. In another care a client wanted to investigate replacement of a twenty year old chiller plant with more efficient equipment. We investigated the project and determined that the payback would be greater than ten years. They did not operate the equipment during the summer and at less than 50% of capacity the balance of the year

Measure Guideline: Air Conditioner Diagnostics, Maintenance, and Replacement

Energy Technology Data Exchange (ETDEWEB)

Springer, D.; Dakin, B.

2013-03-01

This guideline responds to the need for an efficient means of identifying, diagnosing, and repairing faults in air conditioning systems in existing homes that are undergoing energy upgrades. Inadequate airflow due to constricted ducts or undersized filters, improper refrigerant charge, and other system defects can be corrected at a fraction of the cost of equipment replacement and can yield significant savings. The guideline presents a two-step approach to diagnostics and repair.

Measure Guideline. Air Conditioner Diagnostics, Maintenance, and Replacement

Energy Technology Data Exchange (ETDEWEB)

Springer, David [Alliance for Residential Building Innovation (ARBI), Davis, CA (United States); Dakin, Bill [Alliance for Residential Building Innovation (ARBI), Davis, CA (United States)

2013-03-01

This guideline responds to the need for an efficient means of identifying, diagnosing, and repairing faults in air conditioning systems in existing homes that are undergoing energy upgrades. Inadequate airflow due to constricted ducts or undersized filters, improper refrigerant charge, and other system defects can be corrected at a fraction of the cost of equipment replacement and can yield significant savings. The guideline presents a two-step approach to diagnostics and repair.

Ageing management and equipment qualification

International Nuclear Information System (INIS)

Stahl, Gunnar

2014-01-01

The knowledge of how the environment and load of organic material in general and especially polymers and lubricants, is affecting the degradation of important properties, have increased during the last decade. However the restrictions using established additives like some color pigments due to their poisonousness e.g. pigments based at cadmium, lead, mercury etc. have caused problems when replacing additives to polymers. The replacement additives have often been used in new design without going through the required material qualification procedure. There have also been observed that some non-qualified and non-approved materials have been installed in some power plants due to false documentation. There are also a lot of new manufacturers, of materials similar to the previously qualified materials, active at the market. This increases the difficulty to ensure that the required material quality is used. New materials, new additives and new manufacturers makes if more and more difficult to assure that the expected material is present. This causes more strict demands of how the new materials often used in equipment at type-testing and in replacement materials are analyzed and documented. By implementing new steps for chemical, mechanical and electrical analysis and increase the general quality assurance content this issue can be managed. (authors)

E-waste management and sustainability: a case study in Brazil.

Science.gov (United States)

Azevedo, Luís Peres; da Silva Araújo, Fernando Gabriel; Lagarinhos, Carlos Alberto Ferreira; Tenório, Jorge Alberto Soares; Espinosa, Denise Crocce Romano

2017-11-01

The advancement of technology and development of new electronic and electrical equipment with a reduced life cycle has increased the need for the disposal of them (called Waste of Electric and Electronic Equipment or simply e-waste) due to defects presented during use, replacement of obsolete equipment, and ease of acquisition of new equipment. There is a lack of consumer awareness regarding the use, handling storage, and disposal of this equipment. In Brazil, the disposal of post-consumer waste is regulated by the National Solid Waste Policy, established by Law No. 12305 and regulated on the 23rd December 2010. Under this legislation, manufacturers and importers are required to perform a project for the Reverse Logistics of e-waste, though its implementation is not well defined. This work focuses on the verification of the sustainability of reverse logistics suggested by the legislation and the mandatory points, evaluating its costs and the possible financial gain with recycling of the waste. The management of reverse logistics and recycling of waste electrical and electronic equipment, or simply recycling of e-waste, as suggested by the government, will be the responsibility of the managing organization to be formed by the manufacturers/importers in Brazil.

Standard Measurement & Verification Plan for Lighting Equipment Retrofit or Replacement Projects

Energy Technology Data Exchange (ETDEWEB)

Richman, Eric E.

2009-11-04

This document provides a framework for a standard Measurement and Verification (M&V) plan for lighting projects. It was developed to support cost-effective retrofits (partial and complete replacements) of lighting systems and is intended to provide a foundation for an M&V plan for a lighting retrofit utilizing a "best practice" approach, and to provide guidance to site owners, contractors, and other involved organizations on what is essential for a robust M&V plan for lighting projects. This document provides examples of appropriate elements of an M&V plan, including the calculation of expected energy savings. The standard M&V plan, as provided, also allows for consistent comparison with other similar lighting projects. Although intended for lighting retrofit applications, M&V plans developed per this framework document may also be used for other non-lighting technology retrofits and new installations.

Laboratory equipment maintenance: a critical bottleneck for strengthening health systems in sub-Saharan Africa?

Science.gov (United States)

Fonjungo, Peter N; Kebede, Yenew; Messele, Tsehaynesh; Ayana, Gonfa; Tibesso, Gudeta; Abebe, Almaz; Nkengasong, John N; Kenyon, Thomas

2012-02-01

Properly functioning laboratory equipment is a critical component for strengthening health systems in developing countries. The laboratory can be an entry point to improve population health and care of individuals for targeted diseases - prevention, care, and treatment of TB, HIV/AIDS, and malaria, plus maternal and neonatal health - as well as those lacking specific attention and funding. We review the benefits and persistent challenges associated with sustaining laboratory equipment maintenance. We propose equipment management policies as well as a comprehensive equipment maintenance strategy that would involve equipment manufacturers and strengthen local capacity through pre-service training of biomedical engineers. Strong country leadership and commitment are needed to assure development and sustained implementation of policies and strategies for standardization of equipment, and regulation of its procurement, donation, disposal, and replacement.

Reactor vessel closure head replacements in 1997

International Nuclear Information System (INIS)

Anon.

1997-01-01

The Framatome-Jeumont Industrie consortium have completed in 1997 28 reactor vessel (RV) closure head replacements, including five on 1300 MWe class PWR units. Framatome manages the operations and handles removal and reinstallation of equipment (not including the control rod drive mechanisms (CRDM)) and the requalification tests, while JI, which manufactures the CRDMs, is involved in the CRDM cutting, re-machining and welding operations, using tools of original design, in order to optimize the RV closure head operation in terms of costs, schedule and dosage

Technology management: a perspective on system support, procurement, and replacement planning.

Science.gov (United States)

Dickerson, M L; Jackson, M E

1992-01-01

The escalating costs associated with medical technology present a host of challenges for the hospital clinical engineering department. As service and support costs comprise ever larger portions of a system's life cycle cost, innovative management of service provider mix and mechanisms can provide substantial savings in operating expenses. In addition to full-service contracts, the use of demand service and independents has become commonplace. Medical equipment maintenance insurance programs provide yet another service alternative, combining the flexibility of demand service with the safety of a capped budget. These programs have gained acceptance among hospitals as their providers have become more focused on the healthcare market and its many needs. In view of the long-term cost impact surrounding technology procurement, the authors recommend that hospitals refine system evaluation methodologies and develop more comprehensive techniques directed at capital equipment replacement planning. One replacement planning approach, based on an estimation of system value changes, is described and illustrated using data collected through client consultations. Although the validity of this method has not been demonstrated, it represents a simplified approach to life cycle cost analysis and is intended to provide a standard method by which system replacement planning may be quantified. As a departure from system devaluation based solely on depreciation, this method estimates prospective system values derived from anticipated operations and maintenance costs, projected revenue, and the availability of new technology.

Replacing the Engine In Your Car While You Are Still Driving It

Energy Technology Data Exchange (ETDEWEB)

Bjorklund, Eric A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-11-04

Replacing your accelerator’s timing system with a completely different architecture is not something that happens very often. Perhaps even rarer is the requirement that the replacement not interfere with the accelerator’s normal operational cycle. In 2011, The Los Alamos Neutron Science Center (LANSCE) began the purchasing and installation phase of a nine-year rolling upgrade project which will eventually result in the complete replacement of the low-level RF system, the timing system, the industrial I/O system, the beam-synchronized data acquisition system, the fastprotect reporting system, and much of the diagnostic equipment. These projects are mostly independent of each other, with their own installation schedules, priorities, and time-lines. All of them, however, must interface with the timing system.

Modern approach to the problem of fossil gas fuels replacement by alternative fuels

Energy Technology Data Exchange (ETDEWEB)

Soroka, Boris [Gas Institute, National Academy of Sciences, Kiev (Ukraine)

2013-07-01

New scientific and engineering fundamentals of fuels substitution have been developed instead of obsolete methodology “Interchangeability of Fuel Gases” developed in USA and existing from the middle of XX{sup th} century. To perform the complex prediction of total or partial substitution of given flow rate of natural gas NG for alternative gases AG the following parameters are to be predicted: plant utilization efficiencies – regarding fuel and energy utilization, the last in form of heat Ș{sub H} and exergy Ș{sub eff} efficiencies, saving or overexpenditure of the NG flow rate in the gas mixture with AG, specific fuel consumption b f and specific issue of harmful substances C{sub t} – pollutants in the combustion products (C{sub NO{sub x}} ) and greenhouse gases (C {sub CO{sub 2}} ). Certification of alternative gas fuels and fuel mixtures as a commodity products is carried out in frame of our approach with necessary set of characteristics, similar to those accepted in the world practice. Key words: alternative fuel, fuel replacement (substitution), natural gas, process gases, theoretical combustion temperature, thermodynamic equilibrium computations, total enthalpy.

Reliability tests for reactor internals replacement technology

International Nuclear Information System (INIS)

Fujimaki, K.; Uchiyama, J.; Ohtsubo, T.

2000-01-01

Structural damage due to aging degradation of LWR reactor internals has been reported in several nuclear plants. NUPEC has started a project to test the reliability of the technology for replacing reactor internals, which was directed at preventive maintenance before damage and repair after damage for the aging degradation. The project has been funded by the Ministry of International Trade and Industry (MITI) of Japan since 1995, and it follows the policy of a report that the MITI has formally issued in April 1996 summarizing the countermeasures to be considered for aging nuclear plants and equipment. This paper gives an outline of the whole test plans and the test results for the BWR reactor internals replacement methods; core shroud, ICM housing, and CRD Housing and stub tube. The test results have shown that the methods were reliable and the structural integrity was appropriate based on the evaluation. (author)

Environmental and ventilation benefits for underground mining operations using fuel cell powered production equipment

International Nuclear Information System (INIS)

Kocsis, C.; Hardcastle, S.

2007-01-01

The benefits of replacing diesel engines with fuel cells in mine production equipment were discussed. The paper was part of a multi-year feasibility study conducted to evaluate the use of hydrogen fuel cell-powered equipment to replace diesel engine powered equipment in underground mining operations. The feasibility study demonstrated that fuel cells are capable of eliminating the unwanted by-products of combustion engines. However, the use of fuel cells also reduced the amount of ventilation that mines needed to supply, thereby further reducing energy consumption. This study examined the benefits of replacing diesel engines with fuel cells, and discussed the mitigating qualifiers that may limit ventilation energy savings. Solutions to retaining and maintaining additional ventilation in the event of hydrogen leaks from fuel cell stacks were also investigated. The analyses were conducted on 6 operating mines. Current operating costs were compared with future operating conditions using fuel cell powered production vehicles. Operating costs of the primary ventilation system were established with a mine ventilation simulator. The analysis considered exhaust shaft velocities, heating system air velocities, and levels of silica exposure. Canadian mine design criteria were reviewed. It was concluded that appropriate safeguards are needed along hydrogen distribution lines to lower the impacts of hydrogen leaks. Large financial commitments may also be required to ensure a spark-free environment. 20 refs., 6 tabs., 3 figs

Safety measures for the main control board replacement project at Ikata units 1 and 2

International Nuclear Information System (INIS)

Hashimoto, Nozomu; Tada, Kenji

2013-01-01

When Units 1 and 2 of the Ikata Power Station underwent replacement of their main control boards, control cabinets, and associated equipment, it was necessary to remove all the control boards, cabinets, and cables from the control building including from the main control room. This meant the loss of operation and monitoring functions in the main control room and functions of control cabinets. To maintain the operation and monitoring functions required under plant shutdown conditions, temporary operation and monitoring equipment (i.e., temporary main control board) was installed in the temporary main control room. The advance preparations included a trial switching from the permanent to the temporary main control board to identify and address potential problems in advance. When the replacement work was underway, a work schedule sheet posted in the temporary and the permanent control rooms was used to prevent human errors caused by operators’ recognition errors. Monitoring and control signals were switched from the old boards to the temporary boards and from the temporary boards to the new boards at appropriate timings to ensure plant safety during the replacement operation. (author)

Fuel element replacement and cooling water radioactivity at the Musashi reactor

International Nuclear Information System (INIS)

Nozaki, T.; Honda, T.; Horiuchi, N.; Aizawa, O.; Sato, T.

1988-01-01

The Musashi reactor (TRIGA-II, 100kW) has been operated without any serious troubles since 1963. In 1985 the old Al-cladded fuel elements were replaced with new stainless cladded ones in order to insure a long and safe operation. By using a semi-automatic equipment the old fuel elements have been transferred into the bulk-shielding experimental pool, which was remodelled for the spent-fuel storage. In order to reduce the exposure during the transfer work, the old fuel elements were cooled in the core tank for 3 months. After the replacement, the radioactivities in the cooling water have been drastically changed. The activity of Na-24 decreased about one decade, and the activities of Cr-51, Mn-54, Mn-56, Co-58 and Co-60 increased about two decades. At this conference we will report on the following points: (1) semi-automatic equipment for the transportation of the Al-cladded spent fuel, (2) structure of spent-fuel storage pool, and (3) radioactivity change in the cooling water. (author)

Rationalizing method of replacement intervals by using Bayesian statistics

International Nuclear Information System (INIS)

Kasai, Masao; Notoya, Junichi; Kusakari, Yoshiyuki

2007-01-01

This study represents the formulations for rationalizing the replacement intervals of equipments and/or parts taking into account the probability density functions (PDF) of the parameters of failure distribution functions (FDF) and compares the optimized intervals by our formulations with those by conventional formulations which uses only representative values of the parameters of FDF instead of using these PDFs. The failure data are generated by Monte Carlo simulations since the real failure data can not be available for us. The PDF of PDF parameters are obtained by Bayesian method and the representative values are obtained by likelihood estimation and Bayesian method. We found that the method using PDF by Bayesian method brings longer replacement intervals than one using the representative of the parameters. (author)

Optimal Replacement Policy of Jet Engine Modules from the Aircarrier's Point of View

Directory of Open Access Journals (Sweden)

Anita Domitrović

2008-01-01

Full Text Available A mathematical model for optimising preventive maintenanceof aircraft jet engine was developed by dynamic programming.Replacement planning for jet engine modules is regardedas a multistage decision process, while optimum modulereplacement is considered as a problem of equipment replacement.The goal of the optimal replacement policy of jet enginemodules is a defined series of decisions resulting in minimummaintenance costs. The model was programmed inC++ programming language and tested by using CFM56 jetengine data. The optimum maintenance strategy costs werecompared to costs of simpler experience-based maintenancestrategies. The results of the comparison j usti.JY further developmentand usage of the model in order to achieve significant costreduction for airline carriers.

A new machine for continuous renal replacement therapy: from development to clinical testing.

Science.gov (United States)

Ricci, Zaccaria; Salvatori, Gabriella; Bonello, Monica; Ratanarat, Ranistha; Andrikos, Emilios; Dan, Maurizio; Piccinni, Pasquale; Ronco, Claudio

2005-01-01

A new continuous renal replacement therapy machine has been designed to fulfill the expectations of nephrologists and intensivists operating in the common ground of critical care nephrology. The new equipment is called Prismaflex and it is the natural evolution of the PRISMA machine that has been utilized worldwide for continuous renal replacement therapy in the last 10 years. The authors performed a preliminary alpha-trial to establish the usability, flexibility and reliability of the new device. Accuracy was also tested by recording various operational parameters during different intermittent and continuous renal replacement modalities during 62 treatments. This article will describe our first experience with this new device and touch upon the historic and technologic background leading to its development.

Complex of the equipment for instrumental element analysis

International Nuclear Information System (INIS)

Borisov, G.I.; Komkov, M.M.; Kuz'michev, V.A.

1986-01-01

Complex of the equipment for instrumental element analysis at the IR-8 reactor is designed, fabricated and taken into operation. The complex is provided with a multichannel system of vacuum pneumatic transport with radiation positions in the reactor horizontal tangential channel for neutron-activation analysis by short-lived isotopes; specialized dry vertical channels in a beryllium reflector of the reactor and remote system of radioactive sample replacement for neutron-activation analysis by long-lived isotopes; a specialized horizontal tangential channel for neutron beam extraction by means of a beryllium converter and remote device for studied sample replacement under radiation and measurement of prompt γ-radiation for neutron-radiation analysis; a measuring center using minicomputers for experimental data accumulation and processing and analysis control

Upgrading the TFTR Transrex Power Supplies

International Nuclear Information System (INIS)

Lawson, J.E.; Marsala, R; Ramakrishnan, S.; Zhao, X.; Sichta, P.

2009-01-01

In order to provide improved and expanded experimental capabilities, the existing Transrex power supplies at PPPL are to be upgraded and modernized. Each of the 39 power supplies consists of two six pulse silicon controlled rectifier sections forming a twelve pulse power supply. The first modification is to split each supply into two independent six pulse supplies by replacing the existing obsolete twelve pulse firing generator with two commercially available six pulse firing generators. The second change replaces the existing control link with a faster system, with greater capacity, which will allow for independent control of all 78 power supply sections. The third change replaces the existing Computer Automated Measurement and Control (CAMAC) based fault detector with an Experimental Physics and Industrial Control System (EPICS) compatible unit, eliminating the obsolete CAMAC modules. Finally the remaining relay logic and interfaces to the 'Hardwired Control System' will be replaces with a Programmable Logic Controller (PLC)

The Need for Strategic Planning for Nuclear Power Plant I and C Upgrades

International Nuclear Information System (INIS)

Hill, J. Douglas; Moore, Paul

2002-01-01

Nuclear power plants rely on Instrumentation and Control (I and C) systems for control, monitoring and protection of the plant. The original, analog designs used in most nuclear plants have become or soon will be obsolete, forcing plants to turn to digital technology. Many factors affect the design of replacement equipment, including long-term and short-term economics, regulatory issues, and the way the plant operates on a day-to-day basis. The first step to all modernization projects should involve strategic planning, to ensure that the overall long and short-term goals of the plant are met. Strategic planning starts with a thorough evaluation of the existing plant control systems, the available options, and the benefits and consequences of these options. (authors)

Life cycle management for equipments in nuclear plants based on reliability and actual conditions

International Nuclear Information System (INIS)

Dalin, Wang; Jingquan, Liu; Peng, Liu

2010-01-01

Life cycle management model based on reliability includes two parts: obtaining failure rate function and founding cost-oriented model to solve. It is actually a single objective programming whose optimal solution is the most economical replacement period. Parameters of failure rate function are estimated by Weibull process fitting with the method of maximum likelihood. The objective function of the model is life-cost function where the dependent variable is replacement period T, with the constraints of failure rate or availability. After foundation of LCM model, we solve it to find the optimal replacement period for the equipments. (authors)

Cache Management of Big Data in Equipment Condition Assessment

Directory of Open Access Journals (Sweden)

Ma Yan

2016-01-01

Full Text Available Big data platform for equipment condition assessment is built for comprehensive analysis. The platform has various application demands. According to its response time, its application can be divided into offline, interactive and real-time types. For real-time application, its data processing efficiency is important. In general, data cache is one of the most efficient ways to improve query time. However, big data caching is different from the traditional data caching. In the paper we propose a distributed cache management framework of big data for equipment condition assessment. It consists of three parts: cache structure, cache replacement algorithm and cache placement algorithm. Cache structure is the basis of the latter two algorithms. Based on the framework and algorithms, we make full use of the characteristics of just accessing some valuable data during a period of time, and put relevant data on the neighborhood nodes, which largely reduce network transmission cost. We also validate the performance of our proposed approaches through extensive experiments. It demonstrates that the proposed cache replacement algorithm and cache management framework has higher hit rate or lower query time than LRU algorithm and round-robin algorithm.

Maintenance service for major component of PWR plant. Replacement of pressurizer safe end weld

International Nuclear Information System (INIS)

Miyoshi, Yoshiyuki; Kobayashi, Yuki; Yamamoto, Kazuhide; Ueda, Takeshi; Suda, Naoki; Shintani, Takashi

2017-01-01

In October 2016, MHI completed the replacement of safe end weld of pressurizer (Pz) of Ringhals unit 3, which was the first maintenance work for main component of pressurized water reactor (PWR) plant in Europe. For higher reliability and longer lifetime of PWR plant, MHI has conducted many kinds of maintenance works of main components of PWR plants in Japan against stress corrosion cracking due to aging degradation. Technical process for replacement of Pz safe end weld were established by MHI. MHI has experienced the work for 21 PWR units in Japan. That of Ringhals unit 3 was planned and conducted based on the experiences. In this work, Alloy 600 used for welds of nozzles of Pz was replaced with Alloy 690. Alloy 690 is more corrosive-resistant than Alloy 600. Specially designed equipment and technical process were developed and established by MHI to replace safe end weld of Pz and applied for the Ringhals unit 3 as a first application in Europe. The application had been performed in success and achieved the planned replacement work duration and total radiation dose by using sophisticated machining and welding equipment designed to meet the requirements to be small, lightweight and remote-controlled and operating by well skilled MHI personnel experienced in maintenance activities for major components of PWR plant in Japan. The success shows that the experience, activities and technology developed in Japan for main components of PWR plant shall be applicable to contribute reliable operations of nuclear power plants in Europe and other countries. (author)

Replacement of the glove box panel in nuclear fuel reprocessing facility

International Nuclear Information System (INIS)

Yamamoto, Masahiko; Shirouzu, Hidetomo; Mori, Eito; Surugaya, Naoki

2016-05-01

The panels for visual confirmation of glove box installed at Operation Testing Laboratory in Tokai Reprocessing Plant have been deteriorated and transparencies have been decreased due to the long-term use. Therefore, the glove box panels have been replaced from the view point of preventive maintenance. In the new regulation formulated since the accident at Tokyo Electric Power Company's Fukushima Daiichi Nuclear Power Station, it is demanded that the glove box consists of incombustible or noncombustible materials. In this replacement, the new panels have been manufactured with the polycarbonate which satisfied the UL94 V-0 incombustible class. The glove box has been in service for 40 years and its inside is contaminated with radioactive materials. Thus, the contaminations have been investigated and decontaminated before the replacement work. Then, operator's exposure and radiation protection equipment have been estimated. Also, it is necessary to replace the panels with maintaining the glove box's enclosure function. The replacement has been conducted in closed space covering the opening parts with vinyl sheets. The enclosure function has been verified by the inspection of the new panels and glove box. (author)

Central alarm system replacement in NPP Krsko

International Nuclear Information System (INIS)

Cicvaric, D.; Susnic, M.; Djetelic, N.

2004-01-01

Current NPP Krsko central alarm system consists of three main segments. Main Control Board alarm system (BETA 1000), Ventilation Control Board alarm system (BETA 1000) and Electrical Control Board alarm system (BETA 1100). All sections are equipped with specific BetaTone audible alarms and silence, acknowledge as well as test push buttons. The main reason for central alarm system replacement is system obsolescence and problems with maintenance, due to lack of spare parts. Other issue is lack of system redundancy, which could lead to loss of several Alarm Light Boxes in the event of particular power supply failure. Current central alarm system does not provide means of alarm optimization, grouping or prioritization. There are three main options for central alarm system replacement: Conventional annunciator system, hybrid annunciator system and advanced alarm system. Advanced alarm system implementation requires Main Control Board upgrade, integration of process instrumentation and plant process computer as well as long time for replacement. NPP Krsko has decided to implement hybrid alarm system with patchwork approach. The new central alarm system will be stand alone, digital, with advanced filtering and alarm grouping options. Sequence of event recorder will be linked with plant process computer and time synchronized with redundant GPS signal. Advanced functions such as link to plant procedures will be implemented with plant process computer upgrade in outage 2006. Central alarm system replacement is due in outage 2004.(author)

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.

LS1 Report: Replacing an antique

CERN Multimedia

CERN Bulletin

2013-01-01

At the PS Booster, the old beam dump and the shielding blocks surrounding it have been removed (see here). Installation of the new beam dump is now under way (see video).   The new PSB beam dump during its installation. At the PS, replacement of the old cooling and ventilation system, which dated back to 1957, is progressing well. The dismantling phase has just been completed and the tunnel is being prepared to receive a brand new ventilation system offering more efficient aeration of radioactive areas. At the same time, testing of the newly installed access system is under way. At the SPS, all the equipment of the Long Straight Section 1 (LSS1) has been removed to make way for the campaign to replace the irradiated cables, which started this week. In the LHC, the Radiation to Electronics (R2E) campaign is still progressing at a good clip, especially at Point 1, where the teams are two and a half months ahead of schedule. The Superconducting Magnets and Circuits Consolidation (SMACC) proje...

Replacement of low pressure reheater and performance evaluation on domestic NPP moisture separator reheater

International Nuclear Information System (INIS)

Choi, Y. S.; Jeong, W. T.; Shon, S. Y.; Kim, M. H.

2003-01-01

Moisture Separator Reheater is one of the most important equipment for the integrity of low pressure turbine and the total efficiency of the nuclear power plant, It supplies the dry steam to low pressure turbine after separation of moisture and reheating the wet steam out of high pressure turbine. This equipment is always operated under severe conditions, therefore it should be carefully maintained for safe operation and operating confidence. After replacement low pressure reheater of moister separator reheater on domestic nuclear power plant, there was MSR performance degradation and vibration of condensate drain line. So I found out root cause and commented a solution, site people modified the equipment. Finally I concluded the performanc of MSR was good condition, after I inspected the equipment and evaluated the performance of MSR

Primary Total Knee Replacement: Is Suction a Portal of Infection?

Science.gov (United States)

Budnar, Vijaya M; Amirfeyz, Rouin; Ng, Michael; Bannister, Gordon C; Blom, Ashley W

2009-01-01

INTRODUCTION Pulsed lavage during a total knee replacement usually leaves a pool of fluid on the surgical drapes. It is common practice to suck away this fluid using the same suction device used intra-operatively. This could be a cause of direct wound contamination. We hypothesised that bacteria contaminate fluid that collects around the foot in total knee replacement surgery and that suction equipment could be a portal of contamination. We also hypothesised that bacterial count in the fluid is lower if chlorhexidine, rather than saline, is used in the pulsed lavage. PATIENTS AND METHODS Forty patients undergoing primary total knee replacement were divided into two groups. The first group had pulsed lavage with normal saline and the second with 0.05% chlorhexidine. RESULTS At the end of the operation, 20 ml of fluid, pooled on the surgical drapes was aspirated and cultured for bacterial growth. None of the fluid samples showed bacterial growth. CONCLUSIONS Suction device used peri-operatively during knee replacement is unlikely to be a cause of wound contamination. Pulsed lavage with normal saline is as effective as lavage with chlorhexidine. PMID:19335972

Stability analysis of multipoint tool equipped with metal cutting ceramics

Science.gov (United States)

Maksarov, V. V.; Khalimonenko, A. D.; Matrenichev, K. G.

2017-10-01

The article highlights the issues of determining the stability of the cutting process by a multipoint cutting tool equipped with cutting ceramics. There were some recommendations offered on the choice of parameters of replaceable cutting ceramic plates for milling based of the conducted researches. Ceramic plates for milling are proposed to be selected on the basis of value of their electrical volume resistivity.

Remotely replaceable fuel and feed nozzles for the new waste calcining facility calciner vessel

International Nuclear Information System (INIS)

Fletcher, R.D.; Carter, J.A.; May, K.W.

1978-01-01

The development and testing of remotely replaceable fuel and feed nozzles for calcination of liquid radioactive wastes in the calciner vessel of the New Waste Calcining Facility being built at the Idaho National Engineering Laboratory is described. A complete fuel nozzle assembly was fabricated and tested at the Remote Maintenance Development Facility to evolve design refinements, identify required support equipment, and develop handling techniques. The design also provided for remote replacement of the nozzle support carriage and adjacent feed and fuel pipe loops using two pairs of master-slave manipulators

Primary separator replacement for Bruce Unit 8 steam generators

International Nuclear Information System (INIS)

Roy, S.B.; Mewdell, C.G.; Schneider, W.G.

2000-01-01

During a scheduled maintenance outage of Bruce Unit 8 in 1998, it was discovered that the majority of the original primary steam separators were damaged in two steam generators. The Bruce B steam generators are equipped with GXP type primary cyclone separators of B and W supply. There were localized perforations in the upper part of the separators and large areas of generalized wall thinning. The degradation was indicative of a flow related erosion corrosion mechanism. Although the unit- restart was justified, it was obvious that corrective actions would be necessary because of the number of separators affected and the extent of the degradation. Repair was not considered to be a practical option and it was decided to replace the separators, as required, in Unit 8 steam generators during an advanced scheduled outage. GXP separators were selected for replacement to minimize the impact on steam generator operating characteristics and analysis. The material of construction was upgraded from the original carbon steel to stainless steel to maximize the assurance of full life. The replacement of the separators was a first of a kind operation not only for Ontario Power Generation and B and W but also for all CANDU plants. The paper describes the degradations observed and the assessments, the operating experience, manufacture and installation of the replacement separators. During routine inspection in 1998, many of the primary steam separators in two of steam generators at Bruce Nuclear Division B Unit 8 were observed to have through wall perforations. This paper describes assessment of this condition. It also discusses the manufacture and testing of replacement primary steam separators and the development and execution of the replacement separator installation program. (author)

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

CERN Document Server

Dehavay, Claude

1993-01-01

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

Applying of neural networks in determination of replacement cycle of spare parts

International Nuclear Information System (INIS)

Saric, Tomislav; Majdandzic; Niko; Lujic, Roberto

2003-01-01

The article shows neural networks applicability to determine expected working time of equipment components before the damage. The results based on measure - simulated values of suggested model have been presented. Advantages of suggested model have been analyzed compared to traditional way of replacement of spare parts and components. Implementation possibility of suggested model in Management Information Maintenance System has been described. (author)

Interrupting a multi-species bioinvasion vector: the efficacy of in-water cleaning for removing biofouling on obsolete vessels.

Science.gov (United States)

Davidson, Ian C; McCann, Linda D; Sytsma, Mark D; Ruiz, Gregory M

2008-09-01

Vector management is the primary method for reducing and preventing nonindigenous species (NIS) invasions and their ecological and economic consequences. This study was the first to examine the efficacy of in-water scrubbing using a submersible cleaning and maintenance platform (SCAMP) to prevent invertebrate species transfers from a heavily fouled obsolete vessel. Initially, prior to treatment, 37 species were recorded in a biofouling matrix that reached 30cm depth in some locations. The bryozoan Conopeum chesapeakensis, and bivalves Mytilopsis leucophaeata and Ischadium recurvum, were dominant sessile species that created structure, supporting mobile biota that included crabs and the associated parasitic barnacle Loxothylacus panopae. Scrubbing had the effect of significantly reducing organism extent and the number of species per sample, but a substantial and diverse (30 species) residual fouling community remained across the entire vessel. Further assessments of management options are needed to prevent potentially damaging NIS transfers. Additional measures taken within an integrated vector management (IVM) strategy may further improve invasion prevention measures.

High harmonic distortion in a new building due to a multitude of electronic equipment

NARCIS (Netherlands)

Timens, R.B.; Buesink, Frederik Johannes Karel; Cuk, V.; Cobben, J.F.G.; Kling, W.L.; Leferink, Frank Bernardus Johannes

2011-01-01

In modern buildings virtually all electric loads are non-linear. Neither the applicable standards for supply of electrical energy nor those for consumption of electrical energy take into account the replacement of linear loads by non-linear loads. Low power equipment is exempted in standards

Using Survival Analysis to Evaluate Medical Equipment Battery Life.

Science.gov (United States)

Kuhajda, David

2016-01-01

As hospital medical device managers obtain more data, opportunities exist for using the data to improve medical device management, enhance patient safety, and evaluate costs of decisions. As a demonstration of the ability to use data analytics, this article applies survival analysis statistical techniques to assist in making decisions on medical equipment maintenance. The analysis was performed on a large amount of data related to failures of an infusion pump manufacturer's lithium battery and two aftermarket replacement lithium batteries from one hospital facility. The survival analysis resulted in statistical evidence showing that one of the third-party batteries had a lower survival curve than the infusion pump manufacturer's battery. This lower survival curve translates to a shorter expected life before replacement is needed. The data suggested that to limit unexpected failures, replacing batteries at a two-year interval, rather than the current industry recommendation of three years, may be warranted. For less than $5,400 in additional annual cost, the risk of unexpected battery failures can be reduced from an estimated 28% to an estimated 7%.

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

International Nuclear Information System (INIS)

Dong Shengguo; Ma Hongsheng; Zhao Lixia

2008-01-01

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

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

Application of Shuttle Remote Manipulator System technology to the replacement of fuel channels in the Pickering CANDU reactor

International Nuclear Information System (INIS)

Stratton, D.; Butt, C.

1982-04-01

Spar Aerospace Limited of Toronto was the prime contractor to the National Research Council of Canada for the design and development of the Shuttle Remote Manipulator (SRMS). Spar is presently under contract to Ontario Hydro to design and build a Remote Manipulation Control System to replace the fuel channels in the Pickering A Nuclear Generating Station. The equipment may be used to replace the fuel channels in six other early generation CANDU reactors

Designing a power supply for Nim-bin formatted equipment

International Nuclear Information System (INIS)

Banuelos G, L. E.; Hernandez D, V. M.; Vega C, H. R.

2016-09-01

From an old Nuclear Chicago power supply that was practically in the trash, was able to recover the 19 inches casing, rear connectors and the housing where the circuits were. From here all mechanical parts were cleaned and the electronic design was started to replace the original voltage and current functions of this equipment. The cards for the ±6, ±12 and ±24 voltages were designed, simulated and tested with circuitry that does not rely on specialized components or that is sold only by the equipment manufacturer. In the handling of the current by each voltage to operate, was possible to tie with the specifications of the manufacturers like Ortec or Canberra where a model of power supply gives a power of 160 Watts. Basic tests were performed to show that the behavior is very similar to commercial equipment; such as the full load regulation index and the noise level in the supply voltages. So our Nim-bin voltage source is viable for use in our institution laboratories. (Author)

Report for fiscal 1998 on the international joint research project of medical welfare equipment; Iryo fukushi kiki kokusai kyodo kenkyu jigyo 1998 nendo chosa hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

In connection with the international joint research project of medical welfare, a report was made on the results of the investigation conducted in 1998 concerning the technology of overseas medical welfare equipment. In the investigation of china, observation was made on the actual state of the representative medial institutions, with opinions exchanged. Obsolete equipment and old technology are the present state in China, which is strongly desirous of exchanging information with Japan. In Taiwan, being full of venture spirit, an ultrasonic thermal treatment apparatus and an ultrasonic echo device have been produced for example. In Europe, an observation tour was conducted on a German manipulator and process robot while an investigative visit and exchange of opinions were made on the living environment and facilities in Italian training center for physically handicapped persons. Japan's self-supporting and assisting system for excretion attracted many questions and comments. In the investigation in the U.S., views were exchanged concerning '{sup 13}C-MRS device for non-invasion brain metabolic measurement' in research institutions such as universities. A machine developed in Japan received a high evaluation in that {sup 13}C spectrum was obtained from a substantial depth. (NEDO)

Configuration control during maintenance of safety related equipment

International Nuclear Information System (INIS)

Irish, C.S.

2001-01-01

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

Configuration control during maintenance of safety related equipment

International Nuclear Information System (INIS)

Irish, C.S.

2003-01-01

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

Remote replacement of TF [toroidal field] and PF [poloidal field] coils for the compact ignition tokamak

International Nuclear Information System (INIS)

Macdonald, D.; Watkin, D.C.; Hollis, M.J.; DePew, R.E.; Kuban, D.P.

1990-01-01

The use of deuterium-tritium fuel in the Compact Ignition Tokamak will require applying remote handling technology for ex-vessel maintenance and replacement of machine components. Highly activated and contaminated components of the fusion devices auxiliary systems, such as diagnostics and RF heating, must be replaced using remotely operated maintenance equipment in the test cell. In-vessel remote maintenance included replacement of divertor and first wall hardware, faraday shields, and for an in-vessel inspection system. Provision for remote replacement of a vacuum vessel sector, toroidal field coil or poloidal field ring coil was not included in the project baseline. As a result of recent coil failures experienced at a number of facilities, the CIT project decided to reconsider the question of remote recovery from a coil failure and, in January of 1990, initiated a coil replacement study. This study focused on the technical requirements and impact on fusion machine design associated with remote recovery from any coil failure

Equipment for capping drums, especially with radioactive waste

International Nuclear Information System (INIS)

Bednarik, F.

1987-01-01

The equipment consists of a pneumatic cylinder, lever systems with jaws, guide bars, and of securing pins. The top cylinder lid and the bottom cylinder lid provided with openings are slidably attached to a shaft firmly connected to a piston and a support plate. Firmly attached to the bottom lid using brackets are pins holding connecting rods controlling the double-arm levers pivoted on pins, featuring jaws pivoted on forks firmly attached to the support plate and provided with a replaceable spacer insert. The guide bars are firmly attached to the support plate via braces and stiffeners. The securing pins are loaded with springs seated in the braces. The benefits of the equipment include that the lid closing levers with jaws, mechanically controlled using one pneumatic cylinder, thanks to their number and configuration, close the lid around the drum border provided with small recesses which do not reach above the circumference of the drum being closed. The equipment can also be used for carrying closed drums, this also during compressed air failures because the levers with jaws are secured in position with the pneumatic cylinder leg. (J.B.). 1 fig

Fermilab 200 MeV linac control system hardware

Energy Technology Data Exchange (ETDEWEB)

Shea, M.F.

1984-01-01

This report is a description of the present Linac distributed control system that replaces the original Xerox computer and interface electronics with a network of 68000-based stations. In addition to replacing the obsolete Xerox equipment, goals set for the new system were to retain the fast response and interactive nature of the original system, to improve reliability, to ease maintenance, and to provide 15 Hz monitoring of all Linac parameters. Our previous experience with microcomputer installations showed that small, stand-alone control systems are rather straightforward to implement and have been proven to be reliable in operation, even in the severe environment of the 750-keV preaccelerator. The overall design of the Linac system incorporates the concept of many relatively small, stand-alone control systems networked together using an intercomputer communication network. Each station retains its local control system character but takes advantage of the network to allow an operator to interact with the entire Linac from any local console. At the same time, a link to the central computer system allows Host computers to also access parameters in the Linac.

Fermilab 200 MeV linac control system hardware

International Nuclear Information System (INIS)

Shea, M.F.

1984-01-01

This report is a description of the present Linac distributed control system that replaces the original Xerox computer and interface electronics with a network of 68000-based stations. In addition to replacing the obsolete Xerox equipment, goals set for the new system were to retain the fast response and interactive nature of the original system, to improve reliability, to ease maintenance, and to provide 15 Hz monitoring of all Linac parameters. Our previous experience with microcomputer installations showed that small, stand-alone control systems are rather straightforward to implement and have been proven to be reliable in operation, even in the severe environment of the 750-keV preaccelerator. The overall design of the Linac system incorporates the concept of many relatively small, stand-alone control systems networked together using an intercomputer communication network. Each station retains its local control system character but takes advantage of the network to allow an operator to interact with the entire Linac from any local console. At the same time, a link to the central computer system allows Host computers to also access parameters in the Linac

Planning of maintenance of electrical equipment in nuclear plants/laboratories [Paper No.: VB-3

International Nuclear Information System (INIS)

Narasinga Rao, S.N.; Bhattacharyya, A.K.

1981-01-01

Satisfactory operating performance of electrical systems ensures continuous availability of power to the various plants and machinery in nuclear plant and laboratories. For effective optimal functioning of the electrical equipment and to reduce their down time, scheduled planning of maintenance to the equipment is essential. Maintenance of power plant, nuclear or fossil, and industrial plant and research laboratories demands essential ingredients such as right type of trained and motivated technical personnel, adoption of standard procedures for maintenance, adequate safety and protection for equipment, safety procedures adopted in the installation to prevent hazards to the workers, provision of adequate stores and inventories, facilities for quick repairs and testing of equipment and effective planning of procedures for their maintenance. While breakdown maintenance allows equipment to operate before it is repaired or replaced, preventive maintenance makes use of scheduled inspection and periodical equipment overhaul and has little value for predicting future continuous performances of equipment. The engineered maintenance is most advantageous and offers maximum operating time to reduce down time of the equipment while adding predictive testing technique to aid in determining the frequency of overhaul of equipment. The important checks to be conducted and preventive maintenance programme to be scheduled are discussed in this paper. The safety and reliable functioning of the electrical equipment depend on proper optimal design, selection of equipment, their installation, subsequent maintenance and strict compliance with safety regulations. (author)

Purex: process and equipment performance

International Nuclear Information System (INIS)

Orth, D.A.

1986-01-01

The Purex process is the solvent extraction system that uses tributyl phosphate as the extractant for separating uranium and plutonium from irradiated reactor fuels. Since the first flowsheet was proposed at Oak Ridge National Laboratory in 1950, the process has endured for over 30 years with only minor modifications. The spread of the technology was rapid, and worldwide use or research on Purex-type processes was reported by the time of the 1955 Geneva Conference. The overall performance of the process has been so good that there are no serious contenders for replacing it soon. This paper presents: process description; equipment performance (mixer-settlers, pulse columns, rapid contactors); fission product decontamination; solvent effects (solvent degradation products); and partitioning of uranium and plutonium

1998 investigation report. Basic investigation for promotion of joint projects, 'Investigation on Russian CO2 reduction conditions'; 1998 nendo Roshiakoku CO{sub 2} sakugen anken chosa hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

A feasibility study was conducted for a project assuming modernization of a manufacturing plant and improvement of power generation facilities in Russia, with the aim of 'joint implementation' in reducing the greenhouse effect gas by utilizing technologies mutually between advanced nations. The project is to replace obsolete an open hearth furnace and cupola with electric furnaces in connection with the cast steel and forged steel production facilities of Uralmash, a largest-scale Russian heavy machinery manufacturer, to change surface hardening equipment for rolling roll products from a combustion method to a low frequency induction heating method, and to enhance efficiency of the power generation equipment of a public corporation which supplies electric power to Uralmash. Through a field study and a technological investigation, the social background of the project was examined such as the situation of the Russian Federation, its environment and the present state of Sveldorv province; then, examined were the specifications of the facilities, project cost, cost performance, CO2 reduction expected, environmental influence, etc., in the case where the modernization project of Uralmash was implemented. (NEDO)

NASA Ames Research Center 60 MW Power Supply Modernization

Science.gov (United States)

Choy, Yuen Ching; Ilinets, Boris V.; Miller, Ted; Nagel, Kirsten (Technical Monitor)

2001-01-01

The NASA Ames Research Center 60 MW DC Power Supply was built in 1974 to provide controlled DC power for the Thermophysics Facility Arc Jet Laboratory. The Power Supply has gradually losing reliability due to outdated technology and component life limitation. NASA has decided to upgrade the existing rectifier modules with contemporary high-power electronics and control equipment. NASA plans to complete this project in 2001. This project includes a complete replacement of obsolete thyristor stacks in all six rectifier modules and rectifier bridge control system. High power water-cooled thyristors and freewheeling diodes will be used. The rating of each of the six modules will be 4000 A at 5500 V. The control firing angle signal will be sent from the Facility Control System to six modules via fiberoptic cable. The Power Supply control and monitoring system will include a Master PLC in the Facility building and a Slave PLC in each rectifier module. This system will also monitor each thyristor level in each stack and the auxiliary equipment.

DSM [demand-side management] financing: Risks and incentives

International Nuclear Information System (INIS)

Dayton, D.S.

1992-01-01

Opportunities to make investments in demand side management (DSM) are widespread, especially among large, complex, energy-intensive customers. Acceptable economics are found for energy efficiency improvements, new construction or renovation, replacement of failing or obsolete equipment, and retrofit of existing facilities with more efficient equipment and operations. Market imperfections and technical limitations intrude on the DSM investment process. These intrusions are examined from a financial viewpoint by considering the return on investment and risks faced by the three potential investors in DSM opportunities: the customer, the utility, and the third party contractor or financier. These risks are illustrated by examining the cash flow of a typical project depicting a comprehensive energy efficiency installation in a medium to large industrial or institutional facility. The spread between the customer's risk/return ratio and that of the other two investors is shown to be surprisingly large. A utility role in marketing and financing, as opposed to direct subsidizing of customers or direct purchase of DSM resources from third parties, is explored as an efficient response to these realities. 2 figs., 3 tabs

Regenerative Medicine Will Make Orthopaedic Implants Obsolete In Our Time Orthopaedic Research Society First Annual Meeting Debate, San Diego, March 21st , 2017.

Science.gov (United States)

Johnstone, Brian; Jacobs, Joshua J; Sandell, Linda J; Wilkinson, J Mark

2018-05-10

The mission of the Orthopaedic Research Society is to promote and advance musculoskeletal research worldwide. With this in mind, the Annual Meeting Program Committee sought to establish a debate as a key component of the meeting. Our purpose was to provoke discussion on topics that are core to our mission and to engage all constituencies within the society by examining questions of broad relevance. To this end, the topic "Regenerative medicine will make orthopaedic implants obsolete in our time" was selected as the title of the inaugural debate. The arguments for and against the motion are presented in this perspectives article. This article is protected by copyright. All rights reserved. This article is protected by copyright. All rights reserved.

Replacement of fish meal by protein soybean concentrate in practical diets for Pacific white shrimp

Directory of Open Access Journals (Sweden)

Mariana Soares

2015-10-01

Full Text Available ABSTRACTThe objective of this work was to evaluate the performance of Litopenaeus vannameifed different levels (0, 25, 50, 75, and 100% of soybean protein concentrate (63.07% crude protein, CP to replace fish meal-by product (61.24% CP. The study was conducted in clear water in fifteen 800 L tanks equipped with aeration systems, constant heating (29 ºC, and daily water exchange (30%. Each tank was stocked with 37.5 shrimp/m3 (3.03±0.14 g. Feed was supplied four times a day, at 6% of the initial biomass, adjusted daily. After 42 days, the weight gain of shrimp fed diets with 0 and 25% protein replacement was higher than that observed in shrimp fed 100% replacement, and there were no differences among those fed the other diets. Feed efficiency and survival did not differ among shrimp fed different protein replacements. There was a negative linear trend for growth parameters and feed intake as protein replacement with soybean protein concentrate increased. Fish meal by-product can be replaced by up to 75% of soybean protein concentrate, with no harm to the growth of Pacific white shrimp.

Economic analysis for upgrade decision-making using a control system replacement example

International Nuclear Information System (INIS)

De Grosbois, J.; Wichman, R.; Hepburn, G.A.; Basso, R.; Kumar, V.; Deregowska, D.

2006-01-01

This paper (3rd in a CNS series) provides insight on how nuclear power plants can achieve better efficiencies and reduced operations and maintenance (O and M) costs by making well-informed equipment upgrade decisions. An investment decision in a plant system upgrade will have various technical options and associated performance outcomes. These can be modelled and evaluated using economic and financial analysis methods. The economic analysis usually involves a comparison of an investment scenario versus a no-investment scenario called difference case analysis. The investment may include several scenarios due to the existence of various options, different investment timings, or desired performance results. Classical approaches, using financial tools such as net present value and internal rate of return calculations, may be used to quantify the financial benefits of the difference cases when certainty about the outcomes is assumed. When making decisions under risk, the classical approaches may be augmented with methods that consider life-cycle costs and benefits, the cost consequences of and probability of equipment failure, the timing of the replacement, and the uncertainties in estimating costs and benefits. The use of expected value and Monte Carlo simulation, among others, allow the incorporation of financial and technical uncertainty into the analysis. Finally, sensitivity analysis enables better understanding of the problem and may improve the decision and clarify the level of confidence that should be put in the outcomes. This paper illustrates the use of financial decision analysis methods for equipment replacements using a control system upgrade example. These methods may easily be generalized for other types of plant upgrades. (author)

Image quality analysis of digital mammographic equipments

Energy Technology Data Exchange (ETDEWEB)

Mayo, P.; Pascual, A.; Verdu, G. [Valencia Univ. Politecnica, Chemical and Nuclear Engineering Dept. (Spain); Rodenas, F. [Valencia Univ. Politecnica, Applied Mathematical Dept. (Spain); Campayo, J.M. [Valencia Univ. Hospital Clinico, Servicio de Radiofisica y Proteccion Radiologica (Spain); Villaescusa, J.I. [Hospital Clinico La Fe, Servicio de Proteccion Radiologica, Valencia (Spain)

2006-07-01

The image quality assessment of a radiographic phantom image is one of the fundamental points in a complete quality control programme. The good functioning result of all the process must be an image with an appropriate quality to carry out a suitable diagnostic. Nowadays, the digital radiographic equipments are replacing the traditional film-screen equipments and it is necessary to update the parameters to guarantee the quality of the process. Contrast-detail phantoms are applied to digital radiography to study the threshold contrast detail sensitivity at operation conditions of the equipment. The phantom that is studied in this work is C.D.M.A.M. 3.4, which facilitates the evaluation of image contrast and detail resolution. One of the most extended indexes to measure the image quality in an objective way is the Image Quality Figure (I.Q.F.). This parameter is useful to calculate the image quality taking into account the contrast and detail resolution of the image analysed. The contrast-detail curve is useful as a measure of the image quality too, because it is a graphical representation in which the hole thickness and diameter are plotted for each contrast-detail combination detected in the radiographic image of the phantom. It is useful for the comparison of the functioning of different radiographic image systems, for phantom images under the same exposition conditions. The aim of this work is to study the image quality of different images contrast-detail phantom C.D.M.A.M. 3.4, carrying out the automatic detection of the contrast-detail combination and to establish a parameter which characterize in an objective way the mammographic image quality. This is useful to compare images obtained at different digital mammographic equipments to study the functioning of the equipments. (authors)

Image quality analysis of digital mammographic equipments

International Nuclear Information System (INIS)

Mayo, P.; Pascual, A.; Verdu, G.; Rodenas, F.; Campayo, J.M.; Villaescusa, J.I.

2006-01-01

The image quality assessment of a radiographic phantom image is one of the fundamental points in a complete quality control programme. The good functioning result of all the process must be an image with an appropriate quality to carry out a suitable diagnostic. Nowadays, the digital radiographic equipments are replacing the traditional film-screen equipments and it is necessary to update the parameters to guarantee the quality of the process. Contrast-detail phantoms are applied to digital radiography to study the threshold contrast detail sensitivity at operation conditions of the equipment. The phantom that is studied in this work is C.D.M.A.M. 3.4, which facilitates the evaluation of image contrast and detail resolution. One of the most extended indexes to measure the image quality in an objective way is the Image Quality Figure (I.Q.F.). This parameter is useful to calculate the image quality taking into account the contrast and detail resolution of the image analysed. The contrast-detail curve is useful as a measure of the image quality too, because it is a graphical representation in which the hole thickness and diameter are plotted for each contrast-detail combination detected in the radiographic image of the phantom. It is useful for the comparison of the functioning of different radiographic image systems, for phantom images under the same exposition conditions. The aim of this work is to study the image quality of different images contrast-detail phantom C.D.M.A.M. 3.4, carrying out the automatic detection of the contrast-detail combination and to establish a parameter which characterize in an objective way the mammographic image quality. This is useful to compare images obtained at different digital mammographic equipments to study the functioning of the equipments. (authors)

An optimal inspection strategy for randomly failing equipment

International Nuclear Information System (INIS)

Chelbi, Anis; Ait-Kadi, Daoud

1999-01-01

This paper addresses the problem of generating optimal inspection strategies for randomly failing equipment where imminent failure is not obvious and can only be detected through inspection. Inspections are carried out following a condition-based procedure. The equipment is replaced if it has failed or if it shows imminent signs of failure. The latter state is indicated by measuring certain predetermined control parameters during inspection. Costs are associated with inspection, idle time and preventive or corrective actions. An optimal inspection strategy is defined as the inspection sequence minimizing the expected total cost per time unit over an infinite span. A mathematical model and a numerical algorithm are developed to generate an optimal inspection sequence. As a practical example, the model is applied to provide a machine tool operator with a time sequence for inspecting the cutting tool. The tool life time distribution and the trend of one control parameter defining its actual condition are supposed to be known

Hip joint replacement

Science.gov (United States)

Hip arthroplasty; Total hip replacement; Hip hemiarthroplasty; Arthritis - hip replacement; Osteoarthritis - hip replacement ... Your hip joint is made up of 2 major parts. One or both parts may be replaced during surgery: ...

Regulatory requirements for replacement of analog systems with digital upgrades

International Nuclear Information System (INIS)

Loeser, P.J.

1993-01-01

This paper reviews briefly the regulatory guidelines which must be met in order to replace analog systems in nuclear power plants with digital systems. There is a move to do such replacements for a number of reasons: analog systems are aging, and showing considerable drift; few vendors manufacture analog systems today; support and parts are hard to get; digital systems provide flexibility. There is a safety concern however about undesirable and unpredictable effects to digital safety equipment due to plant transients, accidents, post-accident condition, and EMI/RF environmental interferences. License holders must comply with the requirements of 10 C.F.R. 50.59, which deals with safety concerns with respect to any changes to operating plants which may have an impact on the safety of the plant. NRC staff is taking the position that all digital upgrades will require an evaluation under this regulation

Selection of equipment for equipment qualification

International Nuclear Information System (INIS)

Torr, K.G.

1989-01-01

This report describes the methodology applied in selecting equipment in the special safety systems for equipment qualification in the CANDU 600 MW nuclear generating stations at Gentilly 2 and Point Lepreau. Included is an explanation of the selection procedure adopted and the rationale behind the criteria used in identifying the equipment. The equipment items on the list have been grouped into three priority categories as a planning aid to AECB staff for a review of the qualification status of the special safety systems

75 FR 6865 - Airworthiness Directives; The Boeing Company Model 737-700 (IGW) Series Airplanes Equipped With...

Science.gov (United States)

2010-02-12

... replacing aging float level switch conduit assemblies, periodically inspecting the external dry bay system... Model 737-700 (IGW) Series Airplanes Equipped With Auxiliary Fuel Tanks Installed in Accordance With... airworthiness directive (AD) for certain Model 737-700 (IGW) series airplanes. This proposed AD would require...

Developing a Logistics Data Process for Support Equipment for NASA Ground Operations

Science.gov (United States)

Chakrabarti, Suman

2010-01-01

The United States NASA Space Shuttle has long been considered an extremely capable yet relatively expensive rocket. A great part of the roughly US $500 million per launch expense was the support footprint: refurbishment and maintenance of the space shuttle system, together with the long list of resources required to support it, including personnel, tools, facilities, transport and support equipment. NASA determined to make its next rocket system with a smaller logistics footprint, and thereby more cost-effective and quicker turnaround. The logical solution was to adopt a standard Logistics Support Analysis (LSA) process based on GEIA-STD-0007 http://www.logisticsengineers.org/may09pres/GEIASTD0007DEXShortIntro.pdf which is the successor of MIL-STD-1388-2B widely used by U.S., NATO, and other world military services and industries. This approach is unprecedented at NASA: it is the first time a major program of programs, Project Constellation, is factoring logistics and supportability into design at many levels. This paper will focus on one of those levels NASA ground support equipment for the next generation of NASA rockets and on building a Logistics Support Analysis Record (LSAR) for developing and documenting a support solution and inventory of resources for. This LSAR is actually a standards-based database, containing analyses of the time and tools, personnel, facilities and support equipment required to assemble and integrate the stages and umbilicals of a rocket. This paper will cover building this database from scratch: including creating and importing a hierarchical bill of materials (BOM) from legacy data; identifying line-replaceable units (LRUs) of a given piece of equipment; analyzing reliability and maintainability of said LRUs; and therefore making an assessment back to design whether the support solution for a piece of equipment is too much work, i.e., too resource-intensive. If one must replace or inspect an LRU too much, perhaps a modification of

Tritium Facilities Modernization and Consolidation Project Process Waste Assessment (Project S-7726)

Energy Technology Data Exchange (ETDEWEB)

Hsu, R.H. [Westinghouse Savannah River Company, AIKEN, SC (United States); Oji, L.N.

1997-11-14

Under the Tritium Facility Modernization {ampersand} Consolidation (TFM{ampersand}C) Project (S-7726) at the Savannah River Site (SS), all tritium processing operations in Building 232-H, with the exception of extraction and obsolete/abandoned systems, will be reestablished in Building 233-H. These operations include hydrogen isotopic separation, loading and unloading of tritium shipping and storage containers, tritium recovery from zeolite beds, and stripping of nitrogen flush gas to remove tritium prior to stack discharge. The scope of the TFM{ampersand}C Project also provides for a new replacement R&D tritium test manifold in 233-H, upgrading of the 233- H Purge Stripper and 233-H/234-H building HVAC, a new 234-H motor control center equipment building and relocating 232-H Materials Test Facility metallurgical laboratories (met labs), flow tester and life storage program environment chambers to 234-H.

An overview of new video techniques

CERN Document Server

Parker, R

1999-01-01

Current video transmission and distribution systems at CERN use a variety of analogue techniques which are several decades old. It will soon be necessary to replace this obsolete equipment, and the opportunity therefore exists to rationalize the diverse systems now in place. New standards for digital transmission and distribution are now emerging. This paper gives an overview of these new standards and of the underlying technology common to many of them. The paper reviews Digital Video Broadcasting (DVB), the Motion Picture Experts Group specifications (MPEG1, MPEG2, MPEG4, and MPEG7), videoconferencing standards (H.261 etc.), and packet video systems, together with predictions of the penetration of these standards into the consumer market. The digital transport mechanisms now available (IP, SDH, ATM) are also reviewed, and the implication of widespread adoption of these systems on video transmission and distribution is analysed.

Human engineering considerations in designing a computerized controlled access security system

International Nuclear Information System (INIS)

Moore, J.W.; Banks, W.W.

1988-01-01

This paper describes a human engineering effort in the design of a major security system upgrade at Lawrence Livermore National Laboratory. This upgrade was to be accomplished by replacing obsolete and difficult-to-man (i.e., multiple operator task actions required) security equipment and systems with a new, automated, computer-based access control system. The initial task was to assist the electronic and mechanical engineering staff in designing a computerized security access system too functionally and ergonomically accommodate 100% of the Laboratory user population. The new computerized access system was intended to control entry into sensitive exclusion areas by requiring personnel to use an entry booth-based system and/or a remote access control panel system. The primary user interface with the system was through a control panel containing a magnetic card reader, function buttons, LCD display, and push-button keypad

Noninvasive studies of peripheral vascular disease

International Nuclear Information System (INIS)

Yao, J.S.T.

1987-01-01

Plethysmography probably is the oldest method for measuring blood flow. In this method, measurements are made of changes in volume of an organ or region of tissue. In the modern practice of vascular surgery, the use of plethysmography has been expanded to include detection of not only arterial occlusive disease but also carotid artery disease and venous problems. Several types of plethysmographs are now available for clinical use in the evaluation of arterial occlusions. These are volume, strain-gauge, and photoelectric plethysmographs. The water-filled volume recorder, popular in the early use of plethysmography, is now obsolete and has been replaced by the air-filled volume plethysmograph, notably, the pulse-volume recorder. For clinical application, the newer plethysmographs, such as the strain-gauge, photopletyhsmograph, and pulse-volume recorder, are now standard equipment in many vascular laboratories. They are discussed in this article

Activities at the electric power research institute to support the modernization of instrumentation and control systems in nuclear power plants in the United States of America

International Nuclear Information System (INIS)

Naser, J.

1998-01-01

Most nuclear power plants in the United States are operating with a vast majority of their original analog instrumentation and control (I and C) equipment. Many of the I and C systems in the plants need to be modernized in a reliable and cost-effective manner to replace obsolete equipment, to reduce operating and maintenance (O and M) costs, to improve plant performance, and to maintain safety. The major drivers for the replacement of the safety, control, and information systems in nuclear power plants are the obsolescence of the existing hardware and the need for more cost-effective power production. Competition between power producers is dictating the need for more cost-effective power production. The increasing O and M costs to maintain systems experiencing obsolescence problems is counter to the needs for more cost-effective power production and improved competitiveness. Modern technology, especially digital systems, offers improved functionality, performance, and reliability; solutions to obsolescence of equipment; reduction in O and M costs, and the potential to enhance safety. Digital I and C systems with their inherent advantages will be implemented only if reliable and cost-effective implementation and licensing acceptance is achieved and if the modernized system supports reduced power production costs. Increasing competition will continue to be a major factor in the operation of nuclear power plants. I will continue to dictate the need for improved productivity and cost-effectiveness. EPRI and its members utilities are working together on an industry-wide Instrumentation and Control Program to address I and C issues and to develop cost-effective solutions. (author)

A case study in the use of cancelled plant equipment in nuclear plant modifications

International Nuclear Information System (INIS)

Anders, D.A.

1986-01-01

The nuclear industry has suffered several blows in the recent past in the form of generating plant cancellations. Upon cancellation, the utility must find a way of minimizing its loss on investment already incurred - consisting of purchased property, partially completed plant, and unused equipment. In many cases, the utility has no practical choice but to dispose of its unused equipment at extremely low prices. While this certainly represents an unfortunate situation for the seller, it does present a significant opportunity for other utilities to procure equipment to use in modifications to their own plants. This paper presents a case study in the use of such cancelled plant equipment in modifications at two nuclear generating facilities. In particular, modifications to replace the refueling platforms at each of the two units at Philadelphia Electric Company's (PECo) Peach Bottom Atomic Power Station and Installation of additional Standby Liquid Control equipment at Limerick Generating Station will be examined. The purpose of the paper is to show the applicability of this information to other utilities

Steam generator replacement in Bruce A Unit 1 and Unit 2

International Nuclear Information System (INIS)

Hart, R.S.

2006-01-01

The Bruce A Generating Station consists of four 900 MW class CANDU units. The reactor and Primary Heat Transport System for each Unit are housed within a reinforced concrete reactor vault. A large duct running below the reactor vaults accommodates the shared fuel handling system, and connects the four reactor vaults to the vacuum building. The reactor vaults, fuelling system duct and the vacuum building constitute the station vacuum containment system. Bruce A Unit 2 was shut down in 1995 and Bruce A Units 1, 3 and 4 were shutdown in 1997. Bruce A Units 3 and 4 were returned to service in late 2003 and are currently operating. Units 1 and 2 remain out of service. Bruce Power is currently undertaking a major rehabilitation of Bruce A Unit 1 and Units 2 that will extend the in-service life of these units by at least 25 years. Replacement of the Steam Generators (eight in each unit) is required; this work was awarded to SNC-Lavalin Nuclear (SLN). The existing steam drums (which house the steam separation and drying equipment) will be retained. Unit 2 is scheduled to be synchronized with the grid in 2009, followed by Unit 1 in 2009. Each Bruce A unit has two steam generating assemblies, one located above and to each end of the reactor. Each steam generating assembly consists of a horizontal cylindrical steam drum and four vertical Steam Generators. The vertical Steam Generators connect to individual nozzles that are located on the underside of the Steam Drum (SD). The steam drums are located in concrete shielding structures (steam drum enclosures). The lower sections of the Steam Generators penetrate the top of the reactor vaults: the containment pressure boundary is established by bellows assemblies that connect between the reactor vault roof slab and the Steam Generators. Each Steam Generators is supported from the bottom by a trapeze that is suspended from the reactor vault top structure. The Steam Generator Replacement (SGR) methodology developed by SLN for Unit 1

10 CFR 830 Major Modification Determination for the ATR Diesel Bus (E-3) and Switchgear Replacement

International Nuclear Information System (INIS)

Duckwitz, Noel

2011-01-01

Near term replacement of aging and obsolescent original ATR equipment has become important to ensure ATR capability in support of NE's long term national missions. To that end, a mission needs statement has been prepared for a non-major system acquisition which is comprised of three interdependent subprojects. The first project, subject of this determination, will replace the existent diesel-electrical bus (E-3) and associated switchgear. More specifically, INL proposes transitioning ATR to 100% commercial power with appropriate emergency backup to include: (1) Provide commercial power as the normal source of power to the ATR loads currently supplied by diesel-electric power. (2) Provide backup power to the critical ATR loads in the event of a loss of commercial power. (3) Replace obsolescent critical ATR power distribution equipment, e.g., switchgear, transformers, motor control centers, distribution panels. Completion of this and two other age-related projects (primary coolant pump and motor replacement and emergency firewater injection system replacement) will resolve major age related operational issues plus make a significant contribution in sustaining the ATR safety and reliability profile. The major modification criteria evaluation of the project pre-conceptual design identified several issues make the project a major modification: (1) Evaluation Criteria No.2 (Footprint change). The addition of a new PC-4 structure to the ATR Facility to house safety-related SSCs requires careful attention to maintaining adherence to applicable engineering and nuclear safety design criteria (e.g., structural qualification, fire suppression) to ensure no adverse impacts to the safety-related functions of the housed equipment. (2) Evaluation Criteria No.3 (Change of existing process). The change to the strategy for providing continuous reliable power to the safety-related emergency coolant pumps requires careful attention and analysis to ensure it meets a project primary

77 FR 53962 - Technical Standard Order (TSO)-C68a, Airborne Automatic Dead Reckoning Computer Equipment...

Science.gov (United States)

2012-09-04

... CONTACT: Mr. Albert Sayadian, AIR-130, Federal Aviation Administration, 470 L'Enfant Plaza, Suite 4102... Positioning System (GPS) has rendered TSO-C68a systems obsolete. The FAA has no record of any applications for...

77 FR 37733 - Technical Standard Order (TSO)-C68a, Airborne Automatic Dead Reckoning Computer Equipment...

Science.gov (United States)

2012-06-22

... Sayadian, AIR-130, Federal Aviation Administration, 470 L'Enfant Plaza, Suite 4102, Washington, DC 20024... Positioning System (GPS) has rendered TSO-C68a systems obsolete. The FAA has no record of any applications for...

The JET experience with remote handling equipment and future prospects

International Nuclear Information System (INIS)

Raimondi, T.

1989-01-01

The commissioning and testing of numerous pieces of equipment are now in progress at JET. Two microprocessor controlled force feedback MASCOT IV servomanipulators have shown comparable characteristics to those of the previous analogue types. Teach and repeat software permits precision welding and repetitive operations in a robotics mode. Other computer aids are planned to improve the man-machine interface: Tool-weight compensation, constraints along preferred lines or planes, automatic tracking of the TV cameras. The in-vessel transporter, provided with 5 vertical hinges, a pan-tilt-roll extension and special purpose end effectors, has been used under direct visual control to install 32 toroidal limiters and 8 radio frequency antennae. Test of remote installation in teach and repeat were done, using the JET spare octant as a mock-up, achieving repeatability of better than 5 mm. A considerable number of special remote handling tools were used inside the vessel hands-on to align, cut and weld diagnostics ports and water pipes. The cutting and welding trolleys were used hands-on, on a total of 250 m of lip joints. The ex-vessel transporter, a crane-mounted vertical telescope, 17 m high with a 10 m horizontal arm, is being manufactured. It will be equipped with manipulator and TV systems and controlled via joystick or keyboard or in teach and repeat. Image processing for collision avoidance is being studied. A low level transporter was used for turbo-pump replacement and is now being equipped with remote control. Mock-up work has started on the replacement of the Neutral Injector sources. Bench tests on flanges, heating jackets and connectors are being done to identify refinements needed. The in-vessel inspection system has been used at high temperature in vacuum. (orig.)

The Jet experience with remote handling equipment and future prospects

International Nuclear Information System (INIS)

Raimondi, T.

1989-01-01

The commissioning and testing of numerous pieces of equipment are now in progress at JET. Two microprocessor controlled force feedback MASCOT IV servomanipulators have shown comparable characteristics to those of the previous analogue types. Teach and repeat software permits precision welding and repetitive operations in a robotics mode. Other computer aids are planned to improve the man-machine interface: tool-weight compensation, constraints along preferred lines or planes, automatic tracking of the TV cameras. The in-vessel transporter, provided with 5 vertical hinges, a pan-tilt-roll extension and special purpose end effectors, has been used under direct visual control to install 32 toroidal limiters and 8 radio frequency antennae. Tests of remote installation in teach and repeat were done, using the JET spare octant as a mock-up, achieving repeatability of better than 5mm. A considerable number of special remote handling tools were used inside the vessel hands-on to align, cut and weld diagnostics ports and water pipes. The cutting and welding trolleys were used hands-on, on a total of 250m of lip joints. The ex-vessel transporter, a crane-mounted vertical telescope, 17m high with a 10m horizontal arm, is being manufactured. It will be equipped with manipulator and TV systems and controlled via joystick or keyboard or in teach and repeat. Image processing for collision avoidance is being studied. A low level transporter was used for turbo-pump replacement and is now being equipped with remote control. Mock-up work has started on the replacement of the Neutral Injector sources. Bench tests on flanges, heating jackets and connectors are being done to identify refinements needed. The in-vessel inspection system has been used at high temperature in vacuum

The JET experience with remote handling equipment and future prospects

International Nuclear Information System (INIS)

Raimondi, T.

1989-01-01

The commissioning and testing of numerous pieces of equipment are now in progress at JET. Two microprocessor controlled force feedback MASCOT IV servomanipulators have shown comparable characteristics to those of the previous analogue types. Teach and repeat software permits precision welding and repetitive operations in a robotics mode. Other computer aids are planned to improve the man-machine interface: tool-weigth compensation, constraints along preferred lines or planes, automatic tracking of the TV cameras. The in-vessel transporter, provided with 5 vertical hinges, a pan-tilt-roll extension and special purpose end effectors, has been used under direct visual control to install 32 toroidal limiters and 8 radio frequency antennae. Tests of remote installation in teach and repeat were done, using the JET spare octant as a mock-up, achieving repeatability of better than 5 mm. A considerable number of special remote handling tools were used inside the vessel hands-on to align, cut and weld diagnostics ports and water pipes. The cutting and welding trolleys were used hands-on, on a total of 250 m of lip joints. The ex-vessel transporter, a crane-mounted vertical telescope, 17 m high with a 10 m horizontal arm, is being manufactured. it will be equipped with manipulator and TV systems and controlled via joystick or keyboard or in teach and repeat. image processing for collision avoidance is being studied. A low level transporter was used for turbo-pump replacement and is now being equipped with remote control. Mock-up work has started on the replacement of the Neutral Injector sources. Bench tests on flanges, heating jackets and connectors are being done to identify refinements needed. The in-vessel inspection system has been used at high temperature in vacuum. (author). 14 refs.; 12 figs

Acceptance test for 900 MWe PWR unit replacement steam generators

International Nuclear Information System (INIS)

Gourguechon, B.

1993-01-01

During the first half of 1994, the Gravelines 1 steam generators will be replaced (SG replacement procedure). The new SG's differ from the former components notably by the alloy used for the tube bundle, in this case, the high chromium content Inconel 690. So, from this standpoint, they are to be considered as PWR 900 replacement SG first models and their thermal efficiency has consequently to be assessed. This will provide an opportunity of ensuring that the performance of the components delivered is in compliance with requirements and of making the necessary provisions if significant deviations are observed. The EFMT branch, which has been in charge of the instrumentation and acceptance of the different SG first models since the first PWR plants were commissioned, will be responsible for the acceptance tests and the ultimate validation of a performance assessment procedure applicable to the future replacement steam generators. The methods and tests proposed for SG expert appraisal are based on consideration of the importance of primary measurement quality for satisfactory SG assessment and of the new test facilities with which the 900 and 1 300 PWR plants are gradually being equipped. These facilities provide an on-site computer environment for tests compatible with the tools (PATTERN, etc.) used at EFMT and in other departments. This test is the first of this kind performed by EFMT and the test facility of a nuclear power plant. (author). 6 figs

Shoulder replacement - discharge

Science.gov (United States)

Total shoulder arthroplasty - discharge; Endoprosthetic shoulder replacement - discharge; Partial shoulder replacement - discharge; Partial shoulder arthroplasty - discharge; Replacement - shoulder - discharge; Arthroplasty - shoulder - discharge

Replacing penalties

Directory of Open Access Journals (Sweden)

Vitaly Stepashin

2017-01-01

Full Text Available УДК 343.24The subject. The article deals with the problem of the use of "substitute" penalties.The purpose of the article is to identify criminal and legal criteria for: selecting the replacement punishment; proportionality replacement leave punishment to others (the formalization of replacement; actually increasing the punishment (worsening of legal situation of the convicted.Methodology.The author uses the method of analysis and synthesis, formal legal method.Results. Replacing the punishment more severe as a result of malicious evasion from serving accused designated penalty requires the optimization of the following areas: 1 the selection of a substitute punishment; 2 replacement of proportionality is serving a sentence other (formalization of replacement; 3 ensuring the actual toughening penalties (deterioration of the legal status of the convict. It is important that the first two requirements pro-vide savings of repression in the implementation of the replacement of one form of punishment to others.Replacement of punishment on their own do not have any specifics. However, it is necessary to compare them with the contents of the punishment, which the convict from serving maliciously evaded. First, substitute the punishment should assume a more significant range of restrictions and deprivation of certain rights of the convict. Second, the perfor-mance characteristics of order substitute the punishment should assume guarantee imple-mentation of the new measures.With regard to replacing all forms of punishment are set significant limitations in the application that, in some cases, eliminates the possibility of replacement of the sentence, from serving where there has been willful evasion, a stricter measure of state coercion. It is important in the context of the topic and the possibility of a sentence of imprisonment as a substitute punishment in cases where the original purpose of the strict measures excluded. It is noteworthy that the

77 FR 38173 - TRICARE Reimbursement Revisions

Science.gov (United States)

2012-06-27

... specific numeric diagnosis-related group values and replacing them with their narrative description. DATES... reference to specific DRG numbers and descriptions became obsolete, so we are removing the numeric... follows: Sec. 199.14 Provider reimbursement methods. * * * * * (a) * * * (1) * * * (ii) * * * (C) * * * (3...

Measuring the Cost of Obsolescence

International Nuclear Information System (INIS)

White, Mark

2006-01-01

The Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) has provided the capability for irradiation testing of nuclear fuels and materials since 1967, and is expected to operate for several more years. Within the scope of extending the life of a nuclear plant is dealing with aging and obsolescence issues. A component can be considered obsolete if the manufacturer no longer supports the component, or if the manufacturer does not even exist anymore. Though these components can be considered obsolete, the cost of obsolescence may or may not be significant; it may be more cost-effective to leave and/or repair the component rather than to replace it. The project at hand is to develop a tool that will not only identify these components, series of components, or entire systems that are obsolete, but to quantify the cost of obsolescence. This engineering tool will be based on empirical formulas created from data collected from factors that deal with obsolescence. These factors are primarily, the cost of item replacement, current cost of maintenance, cost of maintenance of the replacement, cost of failure, risk of failure, safety, increase in performance/efficiency, length of manufacturer's support, and so forth. The objective is to be able to look at the outcome of this engineering tool and clearly see what needs to be replaced, be it a component, series of components, or an entire system. If there are several such replacements needed, which one(s) have the greatest priority for replacement. Therefore the engineering tool will identify, quantify, and prioritize the cost of obsolescence in the plant. An engineering tool of this type should find application in a number of nuclear and non-nuclear facilities. While the engineering tool is being developed, the first stage of development will be on system components. Once the foundation is set it will be used to evaluate other systems and eventually expand and develop the engineering tool for the entire plant

Analysis of Technical State of Thermal and Mechanical Equipment of Thermal Power Stations in the Republic of Belarus under Conditions of Investment Deficit

Directory of Open Access Journals (Sweden)

S. N. Shichko

2004-01-01

Full Text Available The paper contains an analysis of the equipment state at a number of thermal power stations. This analysis is made on the basis of indifferent curves. Relationship of two factors is taken as a criterion for estimation of the equipment state. These factors are faultiness (parameter of failure fi"equency and operating time from the moment when the equipment was put into operation. It is noted that operation of the equipment in excess of specified life without replacement of so-called «weab> elements and estimation of metal state will lead to conditions of high risk in opieration of such equipment.

Dr. med. – obsolet? Eine Querschnittserhebung zur Wahrnehmung und Akzeptanz der medizinischen Doktorarbeit

Directory of Open Access Journals (Sweden)

Heun, Xenia

2014-08-01

Full Text Available [english] Purpose: To obtain the German Medical Degree “Dr.med.” candidates are required to write a scientific thesis which is usually accomplished during Medical school education. This extra work load for the students amongst a lack of standardization and an M.D. awarded upon graduation in other European and Anglo-Saxon countries leads repeatedly to criticism of the German system. However, a systematic survey on the perception and acceptance of the German doctoral thesis among those affected is overdue.Methods: Using an online questionnaire, medical students as well as licensed doctors were asked for the status of their medical degree, their motivation, personal benefit, time and effort, scientific output, its meaningfulness and alternatives concerning their thesis. Patients were asked, how important they value their general practitioner’s title “Dr. med.”. The resulting data were evaluated performing basic statistic analyses.Results and Conclusions: The title “Dr. med.“ does not seem to be obsolete, but there is room for improvement. The scientific output is good and only a mere 15.1% of the candidates do not publish their results at all. Moreover, while at an early stage motivation, appreciation and recognition of personal benefits from the medical degree are considered as independent aspects, they merge to a general view at later stages. The current practice is considered most meaningful by the ones who have already finished their thesis. However, there are discrepancies between the expected and the actual length as well as the type of the thesis indicating that mentoring and educational advertising need improvement. As for the patients, their educational level seems to correlate with the significance attributed to the title “Dr. med.” held by their physician.

A safety equipment list for rotary mode core sampling systems operation in single shell flammable gas tanks

International Nuclear Information System (INIS)

SMALLEY, J.L.

1999-01-01

This document identifies all interim safety equipment to be used for rotary mode core sampling of single-shell flammable gas tanks utilizing Rotary Mode Core Sampling systems (RMCS). This document provides the safety equipment for RMCS trucks HO-68K-4600, HO-68K-4647, trucks three and four respectively, and associated equipment. It is not intended to replace or supersede WHC-SD-WM-SEL-023, (Kelly 1991), or WHC-SD-WM-SEL-032, (Corbett 1994), which classifies 80-68K-4344 and HO-68K-4345 respectively. The term ''safety equipment'' refers to safety class (SC) and safety significant (SS) equipment, where equipment refers to structures, systems and components (SSC's). The identification of safety equipment in this document is based on the credited design safety features and analysis contained in the Authorization Basis (AB) for rotary mode core sampling operations in single-shell flammable gas tanks. This is an interim safety classification since the AB is interim. This document will be updated to reflect the final RMCS equipment safety classification designations upon completion of a final AB which will be implemented with the release of the Final Safety Analysis Report (FSAR)

Notice to exporters on products prohibited from export (nuclear material, equipment and large nuclear units)

International Nuclear Information System (INIS)

1988-01-01

In order to ensure that the policy to avoid the proliferation of nuclear weapons is complied with, the French Administration applies stricter controls over the export of certain sensitive products, materials and equipment. To this effect, lists of such products, materials and equipment are published in the form of Notices to exporters and periodically revised. This Notice repeals and replaces the previous Notice published in the Official Gazette of 21 January 1986. Annex I contains the list of materials whose export is subject to nuclear non-proliferation controls. Annex II lists the equipment whose export is subject to the same controls. Annex III includes the list of large nuclear units for which an application for prior approval of export must be submitted to the Administrations concerned. (NEA) [fr

Dismantling of alpha contaminated obsolete installations and glove boxes on the IRMM site in Geel (Belgium)

International Nuclear Information System (INIS)

Cretskens, Pieter; Lenie, Koen; Melis, Gustaaf

2007-01-01

At the Institute for Reference Materials and Measurements (European commission, Joint Research Centre, IRMM) a dismantling campaign of obsolete installations and glove boxes has been carried out in 2005. There were various reasons for their removal. Some large installations did not meet modern safety standards, other installations were worn out and expected to cause a radioactive contamination risk in the future. The main goal was to create as less waste as possible by extensive contamination checks and by decontamination if necessary. For the glove boxes, decontamination was not possible. A controlled area was set up around the installation to be dismantled in order to prevent spreading of contamination from dust and dirt. This was only possible for the 'minor' contaminated installations. The dismantling campaign of the glove boxes was carried out by using tents of two types depending the contamination inside the glove boxes. The most common glove boxes were dismantled in a tent constructed with hard surfaced polycarbonate plates (ventilated cell). For glove boxes with higher contamination, the same principle was used but with a second 'glove box tent' inside (ventilated glove tent). The purpose of this project was to learn from the experience of this campaign which gave the ability to make estimates of future radioactive waste or classic waste that could be expected from dismantled installations. (authors)

Ankle replacement

Science.gov (United States)

Ankle arthroplasty - total; Total ankle arthroplasty; Endoprosthetic ankle replacement; Ankle surgery ... Ankle replacement surgery is most often done while you are under general anesthesia. This means you will ...

78 FR 37696 - Federal Acquisition Regulation; Updated Postretirement Benefit (PRB) References

Science.gov (United States)

2013-06-21

... that were deleted in the Financial Accounting Standards Board's (FASB's) Accounting Standards Codification (ASC) of Generally Accepted Accounting Principles (GAAP). The references no longer exist in the..., 2012, to replace the obsolete references to paragraphs 110, 112, and 113 of Financial Accounting...

Radiometer evaluation of X-rays equipment in the region of Aracatuba, Sao Paulo, Brazil

International Nuclear Information System (INIS)

Fernandes, Marco A.R.

2009-01-01

This paper presents the basic concepts of radiation protection to guide the health care professionals who use equipment emitting ionizing radiation on the correct handling of the beams of radiation. Radiometric evaluations were conducted in 1665 in X-ray equipment, installed in dental surgeries and clinics, hospitals and radiology services, during the years 1996 to 2003 in the region of Aracatuba. Tests of radiometry are presented as a technical report where the parameters are quantified physical and radiological verifying its compliance with the established by legislation. The distribution of reports by type of unit shows that the vast majority of equipment is of periapical dental x-rays (72%), 25% of equipment is medical equipment for radiology and 3% is dental equipment panoramic model (orthodontic documentation). Among the physical parameters analyzed, the length of the browser was showing more variance compared to the required by law, this fact may also contribute to gaps in the rate of the radiation dose and the size of field in the skin of the patient, the that can easily be resolved simply to replace the piece at the outlet of the head. During the completion of visits to services, it also noted a gap in the training of professionals who operate this equipment emitting radiation, warning of the need for specific training in the area. (author)

Nicotine replacement therapy

Science.gov (United States)

Smoking cessation - nicotine replacement; Tobacco - nicotine replacement therapy ... Before you start using a nicotine replacement product, here are some things to know: The more cigarettes you smoke, the higher the dose you may need to ...

Enhancing reactor availability factor by diagnostic monitoring and data acquisition of electrical equipments

International Nuclear Information System (INIS)

Singh, G.

2006-01-01

Electrical energy has made significant contribution to rapid growth of industrial activity in the country. Development and improvement of energy conversion devices or electrical apparatus have supported the growth. Reliability is probably the most important factor in electrical supply system, not only to give uninterrupted service but to provide an economic supply. Regular diagnostic testing of electrical equipments will make a significant contribution to the reliability of electrical supply. The purpose of diagnostic monitoring is to recognize the development of faults at an early stage, which consequently allows greater freedom to schedule the outages resulting in lower downtime and lower capitalized losses. The insulation constitutes the heart of any electrical/power equipment. The insulation in power equipment in normal condition undergoes certain changes in the physical, chemical, electrical and mechanical properties. The change with respect to time in the presence of an influencing factor, more often a stress (electrical) is referred to as ageing. The deterioration of insulating material plays an important role in the assessing the condition of electrical equipments. The systematic diagnostic tests are also part of the maintenance program to ensure the continued serviceability of electrical equipments, by replacing or repairing the components likely to fail, as revealed by the test. Diagnostic tests are carried out on various electrical equipments for detection of incipient fault, location and judging their severity. (author)

Hip Replacement Surgery

Science.gov (United States)

... Outreach Initiative Breadcrumb Home Health Topics English Español Hip Replacement Surgery Basics In-Depth Download Download EPUB ... PDF What is it? Points To Remember About Hip Replacement Surgery Hip replacement surgery removes damaged or ...

Optimization of inspection and replacement period by using Bayesian statistics

International Nuclear Information System (INIS)

Kasai, Masao; Watanabe, Yasushi; Kusakari, Yoshiyuki; Notoya, Junichi

2006-01-01

This study describes the formulations to optimize the time interval of inspections and/or replacements of equipment/parts taking into account the probability density functions (PDF) for failure rates and parameters of failure distribution functions (FDF) and evaluates the optimized results of these time intervals using our formulations by comparing with those using only representative values of failure rates and the parameters of FDF instead of using these PDFs. The PDFs are obtained with Bayesian method and the representative values are obtained with likelihood estimation method. However, any significant difference is not observed between both optimized results within our preliminary calculations. (author)

Using PHM to measure equipment usable life on the Air Force's next generation reusable space booster

Science.gov (United States)

Blasdel, A.

The U.S. Air Force procures many launch vehicles and launch vehicle services to place their satellites at their desired location in space. The equipment on-board these satellite and launch vehicle often suffer from premature failures that result in the total loss of the satellite or a shortened mission life sometimes requiring the purchase of a replacement satellite and launch vehicle. The Air Force uses its EELV to launch its high priority satellites. Due to a rise in the cost of purchasing a launch using the Air Force's EELV from 72M in 1997 to as high as 475M per launch today, the Air Force is working to replace the EELV with a reusable space booster (RSB). The RSB will be similar in design and operations to the recently cancelled NASA reusable space booster known as the Space Shuttle. If the Air Force uses the same process that procures the EELV and other launch vehicles and satellites, the RSB will also suffer from premature equipment failures thus putting the payloads at a similar high risk of mission failure. The RSB is expected to lower each launch cost by 50% compared to the EELV. The development of the RSB offers the Air Force an opportunity to use a new reliability paradigm that includes a prognostic and health management program and a condition-based maintenance program. These both require using intelligent, decision making self-prognostic equipment The prognostic and health management program and its condition-based maintenance program allows increases in RSB equipment usable life, lower logistics and maintenance costs, while increasing safety and mission assurance. The PHM removes many decisions from personnel that, in the past resulted in catastrophic failures and loss of life. Adding intelligent, decision-making self-prognostic equipment to the RSB will further decrease launch costs while decreasing risk and increasing safety and mission assurance.

Cadaveric Temporal Bone Dissection: Is It Obsolete Today?

Directory of Open Access Journals (Sweden)

Naik, Sulabha M.

2014-01-01

Full Text Available Introduction Traditionally, surgical training in otology, is imparted by dissecting harvested human cadaveric temporal bones. However, maintenance of a cadaveric temporal bone laboratory is expensive and carries risk of exposure to infection. In recent times, other modalities of training are gaining ground and are likely to eventually replace cadaveric temporal bone dissection altogether. Objectives Other alternative methods of training are emerging. New technology like simulation and virtual reality as high-fidelity, safer alternatives, are making rapid strides as teaching tools. Other options are the use of animal temporal bones as teaching tools. The advantages of these are compared. Data Synthesis None of these modalities can replicate the innumerable anatomical variations which are a characteristic feature of the human temporal bone. A novice surgeon not only needs exposure to surgical anatomy and it's variations but also needs to develop hand-eye coordination skills to gain expertise. Conclusion Deliberate practice on human cadaveric temporal bones only, will confer both mastery in anatomy and surgical technique. The human cadaveric temporal bone is ideal simulator for training in otology.

Nuestra obsoleta mentalidad de mercado Our obsolete market mentality

Directory of Open Access Journals (Sweden)

Polanyi Karl

1994-06-01

rights and would like to see governments behaving responsibly towards society, without
relying uncritically on market forces. Liberal tradition is not enough, either there or here. Indi vidual freedoms cannot be abandoned: they must be re-created. An obsolete social sys tem , whose evils were hidden by the fog of ideology, cannot be brought back. Society must rebuild itself, learning such lessons as we are able to learn: for example, the fact that human motivation does not revolve around a single institution
the self-regulating market where hunger and profitare the apparent motives for men to work and be efficient. It is ingenuous, and deceitfully and harmfully so, to believe that world peace and progress will be achieved by trade. Neither a national nor an international system can rely on self-regulation. Balanced budgets, free enterprise and flexible exchange rates will not secure international order: only
society can achieve this, and international society must also be re-created, with the appropriate regulatory institutions.

Regulatory issues on using programmable logic device in nuclear power plants

International Nuclear Information System (INIS)

Park, G. Y.; Yu, Y. J.; Kim, H. T.; Kwon, Y. I.; Park, H. S.; Jeong, C. H.

2012-01-01

For replacing obsolete analog equipment in nuclear power plant, the Programmable Logic Devices (PLDs) using Hardware Description Language (HDL) have been widely adopted in digitalized Instrumentation and Control (I and C) systems because of its flexibility. For safety reviews on Nuclear Power Plants (NPPs,) qualifying digitalized safety I and C system using PLDs is an important issue. As an effort to provide regulatory position on using PLDs in safety I and C system, there is a research project to provide the regulatory positions against emerging issues involved with digitalisation of I and C system including using PLDs. Therefore, this paper addresses the important considerations for using PLDs in safety I and C systems such as diversity, independence and qualification, etc. In this point, this study focuses on technical reports for Field Programmable Gate Array (FPGA) from EPRI,. U.S. NRC, and relevant technical standards

Regulatory issues on using programmable logic device in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Park, G. Y.; Yu, Y. J.; Kim, H. T.; Kwon, Y. I.; Park, H. S.; Jeong, C. H. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2012-10-15

For replacing obsolete analog equipment in nuclear power plant, the Programmable Logic Devices (PLDs) using Hardware Description Language (HDL) have been widely adopted in digitalized Instrumentation and Control (I and C) systems because of its flexibility. For safety reviews on Nuclear Power Plants (NPPs,) qualifying digitalized safety I and C system using PLDs is an important issue. As an effort to provide regulatory position on using PLDs in safety I and C system, there is a research project to provide the regulatory positions against emerging issues involved with digitalisation of I and C system including using PLDs. Therefore, this paper addresses the important considerations for using PLDs in safety I and C systems such as diversity, independence and qualification, etc. In this point, this study focuses on technical reports for Field Programmable Gate Array (FPGA) from EPRI,. U.S. NRC, and relevant technical standards.

Tritium Facilities Modernization and Consolidation Project Process Waste Assessment (Project S-7726)

International Nuclear Information System (INIS)

Hsu, R.H.; Oji, L.N.

1997-01-01

Under the Tritium Facility Modernization ampersand Consolidation (TFM ampersand C) Project (S-7726) at the Savannah River Site (SS), all tritium processing operations in Building 232-H, with the exception of extraction and obsolete/abandoned systems, will be reestablished in Building 233-H. These operations include hydrogen isotopic separation, loading and unloading of tritium shipping and storage containers, tritium recovery from zeolite beds, and stripping of nitrogen flush gas to remove tritium prior to stack discharge. The scope of the TFM ampersand C Project also provides for a new replacement R ampersand D tritium test manifold in 233-H, upgrading of the 233- H Purge Stripper and 233-H/234-H building HVAC, a new 234-H motor control center equipment building and relocating 232-H Materials Test Facility metallurgical laboratories (met labs), flow tester and life storage program environment chambers to 234-H

A safety equipment list for rotary mode core sampling systems operation in single shell flammable gas tanks; TOPICAL

International Nuclear Information System (INIS)

SMALLEY, J.L.

1999-01-01

This document identifies all interim safety equipment to be used for rotary mode core sampling of single-shell flammable gas tanks utilizing Rotary Mode Core Sampling systems (RMCS). This document provides the safety equipment for RMCS trucks HO-68K-4600, HO-68K-4647, trucks three and four respectively, and associated equipment. It is not intended to replace or supersede WHC-SD-WM-SEL-023, (Kelly 1991), or WHC-SD-WM-SEL-032, (Corbett 1994), which classifies 80-68K-4344 and HO-68K-4345 respectively. The term ''safety equipment'' refers to safety class (SC) and safety significant (SS) equipment, where equipment refers to structures, systems and components (SSC's). The identification of safety equipment in this document is based on the credited design safety features and analysis contained in the Authorization Basis (AB) for rotary mode core sampling operations in single-shell flammable gas tanks. This is an interim safety classification since the AB is interim. This document will be updated to reflect the final RMCS equipment safety classification designations upon completion of a final AB which will be implemented with the release of the Final Safety Analysis Report (FSAR)

Knee Replacement

Science.gov (United States)

Knee replacement is surgery for people with severe knee damage. Knee replacement can relieve pain and allow you to ... Your doctor may recommend it if you have knee pain and medicine and other treatments are not ...

Astronaut Anna Fisher Suits Up for NBS Training

Science.gov (United States)

1980-01-01

The Hubble Space Telescope (HST) is a cooperative program of the European Space Agency (ESA) and the National Aeronautical and Space Administration (NASA) to operate a long-lived space-based observatory. It was the flagship mission of NASA's Great Observatories program. The HST program began as an astronomical dream in the 1940s. During the 1970s and 1980s, the HST was finally designed and built becoming operational in the 1990s. The HST was deployed into a low-Earth orbit on April 25, 1990 from the cargo bay of the Space Shuttle Discovery (STS-31). The design of the HST took into consideration its length of service and the necessity of repairs and equipment replacement by making the body modular. In doing so, subsequent shuttle missions could recover the HST, replace faulty or obsolete parts and be re-released. Marshall Space Flight Center's (MSFC's) Neutral Buoyancy Simulator (NBS) served as the test center for shuttle astronauts training for Hubble related missions. Shown is astronaut Anna Fisher suiting up for training on a mockup of a modular section of the HST for an axial scientific instrument change out.

Astronaut Anna Fisher Suiting Up For NBS Training

Science.gov (United States)

1980-01-01

The Hubble Space Telescope (HST) is a cooperative program of the European Space Agency (ESA) and the National Aeronautical and Space Administration (NASA) to operate a long-lived space-based observatory. It was the flagship mission of NASA's Great Observatories program. The HST program began as an astronomical dream in the 1940s. During the 1970s and 1980s, the HST was finally designed and built becoming operational in the 1990s. The HST was deployed into a low-Earth orbit on April 25, 1990 from the cargo bay of the Space Shuttle Discovery (STS-31). The design of the HST took into consideration its length of service and the necessity of repairs and equipment replacement by making the body modular. In doing so, subsequent shuttle missions could recover the HST, replace faulty or obsolete parts and be re-released. Marshall Space Flight Center's (MSFC's) Neutral Buoyancy Simulator (NBS) served as the test center for shuttle astronauts training for Hubble related missions. Shown is astronaut Anna Fisher suiting up for training on a mockup of a modular section of the HST for an axial scientific instrument change out.

Astronaut Anna Fisher Suited Up For NBS Training

Science.gov (United States)

1980-01-01

The Hubble Space Telescope (HST) is a cooperative program of the European Space Agency (ESA) and the National Aeronautical and Space Administration (NASA) to operate a long-lived space-based observatory. It was the flagship mission of NASA's Great Observatories program. The HST program began as an astronomical dream in the 1940s. During the 1970s and 1980s, the HST was finally designed and built becoming operational in the 1990s. The HST was deployed into a low-Earth orbit on April 25, 1990 from the cargo bay of the Space Shuttle Discovery (STS-31). The design of the HST took into consideration its length of service and the necessity of repairs and equipment replacement by making the body modular. In doing so, subsequent shuttle missions could recover the HST, replace faulty or obsolete parts and be re-released. Marshall Space Flight Center's (MSFC's) Neutral Buoyancy Simulator (NBS) served as the test center for shuttle astronauts training for Hubble related missions. Shown is astronaut Anna Fisher suited up for training on a mockup of a modular section of the HST for an axial scientific instrument change out.

Astronaut Anna Fisher in NBS Training For Hubble Space Telescope

Science.gov (United States)

1980-01-01

The Hubble Space Telescope (HST) is a cooperative program of the European Space Agency (ESA) and the National Aeronautical and Space Administration (NASA) to operate a long-lived space-based observatory. It was the flagship mission of NASA's Great Observatories program. The HST program began as an astronomical dream in the 1940s. During the 1970s and 1980s, the HST was finally designed and built becoming operational in the 1990s. The HST was deployed into a low-Earth orbit on April 25, 1990 from the cargo bay of the Space Shuttle Discovery (STS-31). The design of the HST took into consideration its length of service and the necessity of repairs and equipment replacement by making the body modular. In doing so, subsequent shuttle missions could recover the HST, replace faulty or obsolete parts and be re-released. Marshall Space Flight Center's (MSFC's) Neutral Buoyancy Simulator (NBS) served as the test center for shuttle astronauts training for Hubble related missions. Shown is astronaut Anna Fisher training on a mock-up of a modular section of the HST for an axial scientific instrument change out.

Hygiene of work in main shops of modern coking by-product industry. [USSR

Energy Technology Data Exchange (ETDEWEB)

Kapitul' skii, V B

1984-07-01

The hygiene of working conditions is evaluated and compared for coking by-product industry shops using modern technology and machines with those using obsolete equipment and methods. Most basic factors in contamination of atmosphere of coking, pitch-coking and metal-refining shops are coal and coke dust, carbon monoxide and polycyclic aromatic hydrocarbons, especially carcinogenic benzpyrene. Contamination of air of working zone is determined by details of technology: periodicity or continuity of industrial processes, use of improved equipment for smokeless injection of charge into stoves and of hermetic pipes to remove gas with hydraulically operated caps, position of machines in shops and in coal tar distillation removal of carcinogenic benzpyrene by sulfonation and aeration. In modernized shops of coking by-product industry, illness and loss of work capacity are significantly lower than in plants using obsolete methods and equipment. Measures are presented for hygienic improvement of working conditions; both methods to further increase efficiency of technological processes and methods to protect individual worker on job such as use of respirators, protective clothing, plexiglass shields, shampoos and skin creams. 14 references.

Simplified method to evaluate seismic nozzle loads on mechanical equipment connected to unbraced piping

International Nuclear Information System (INIS)

Detroux, P.; Lafaille, J.P.

1991-01-01

After ten years of operation, the Belgian Nuclear Power Plants had to be seismically reassessed; especially, new requirements were imposed to the oldest units. The method, presented in this paper, is based on the principle that all the piping connected to the equipment is replaced by a clamped-hinged beam with or without concentrated mass and of a characteristic length depending on the diameter, schedule, mass per length of the connected piping and on the floor response spectra applicable at the location of the equipment. A theoretical justification of the method is presented for the simplest cases. The case of added concentrated mass is investigated. Finally, several comparisons with a full modal spectral analysis are presented

Contribution to optimization of preventive replacement

International Nuclear Information System (INIS)

Legat, V.; Zaludova, A.H.; Cervenka, V.; Jurca, V.

1996-01-01

The paper presents a method for determining the optimal interval for preventive maintenance/replacement using either an age-based or diagnostic-based renewal strategy. For the case of a finite-time horizon, for which the computations are complicated, a simple formula is proposed for modifying the commonly used inifinite-time solution so that it gives a good approximation to the exact finite-time solution. Examples demonstrate that the method is sufficiently accurate and simple in practice for typical engineering components with Weibull life distributions and for a reasonable range of the cost factor (ratio of unit corrective to unit preventive maintenance costs). This paper investigates the problem of the accuracy of the results compared to the exact, finite-time solution for a selected matrix of time-to failure Weibull shape parameters and cost factors commonly occurring in technical practice. Applications offer substantial benefits to both manufacturer and user of technical equipment

Neutron beam facilities at the Replacement Research Reactor, ANSTO

International Nuclear Information System (INIS)

Kim, S.

2003-01-01

The exciting development for Australia is the construction of a modern state-of-the-art 20-MW Replacement Research Reactor which is currently under construction to replace the aging reactor (HIFAR) at ANSTO in 2006. To cater for advanced scientific applications, the replacement reactor will provide not only thermal neutron beams but also a modern cold-neutron source moderated by liquid deuterium at approximately -250 deg C, complete with provision for installation of a hot-neutron source at a later stage. The latest 'supermirror' guides will be used to transport the neutrons to the Reactor Hall and its adjoining Neutron Guide Hall where a suite of neutron beam instruments will be installed. These new facilities will expand and enhance ANSTO's capabilities and performance in neutron beam science compared with what is possible with the existing HIFAR facilities, and will make ANSTO/Australia competitive with the best neutron facilities in the world. Eight 'leading-edge' neutron beam instruments are planned for the Replacement Research Reactor when it goes critical in 2006, followed by more instruments by 2010 and beyond. Up to 18 neutron beam instruments can be accommodated at the Replacement Research Reactor, however, it has the capacity for further expansion, including potential for a second Neutron Guide Hall. The first batch of eight instruments has been carefully selected in conjunction with a user group representing various scientific interests in Australia. A team of scientists, engineers, drafting officers and technicians has been assembled to carry out the Neutron Beam Instrument Project to successful completion. Today, most of the planned instruments have conceptual designs and are now being engineered in detail prior to construction and procurement. A suite of ancillary equipment will also be provided to enable scientific experiments at different temperatures, pressures and magnetic fields. This paper describes the Neutron Beam Instrument Project and gives

Inspection and replacement of baffle assembly screws inside American reactor vessels

International Nuclear Information System (INIS)

Neal, K.; Chaumont, J.C.

1999-01-01

The baffle assembly inside the vessel of a 900 MWe reactor designed by Framatome, is made up of 44 plates fixed on 8 horizontal supports by a system of about 1000 screws. These plates undergo high neutron flux and the problem of screw cracking appeared at the end of the eighties in the first-generation reactors. The first operation on a large scale concerning the screws of a Westinghouse type reactor, was performed on the Tihange-1 power plant where Framatome controlled 960 screws and replaced 91. In 1997 as a consequence of the Belgian and French feedback experience, American plant operators launched a vast program of preventive actions: material analysis, inspection of baffle plate screws and replacement of defective screws. This program was held in cooperation with EPRI (electric power research institute) and under the control of NRC (nuclear regulatory commission). Framatome Technologies Inc (FTI) was in charge of the in-situ inspection and replacement of the screws. FTI designed special tools and equipment adapted to the 2-loop American reactors but the basis ideas were those applied on the Tihange reactor. The successful experience of FTI has allowed the firm to be commissioned for 6 2-loops American reactors. (A.C.)

Fiscal 1999 research report. Basic research for promotion of joint implementation programs (Energy efficiency survey at Noboil Refinery of Ufa City); 1999 nendo Ufa shi Noboil seiyusho ni kansuru sho energy chosa hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-03-01

The aim is to explore projects that will lead to joint implementations for greenhouse gas emission reduction, and a survey was conducted at the Bashneftechim Refineries, Ufa City, Bashkir Republic, Russian Federation. A feasibility study was carried out involving energy efficiency improvement for oil refining related units such as atmospheric and vacuum distillators. In the energy efficiency survey, studies covered energy efficiency improvement in the existing equipment through the modification of the normal and vacuum distillators, visbreaker, vacuum desulfurizer for light oil, and the process heating furnace of the catalytic cracking equipment, for a reduction in fuel consumption by realizing combustion excess air ratio control; the installation of an air preheater or a waste heater boiler for the collection of heat from combustion exhaust gas; the addition of heat exchangers and the optimization of their arrangement for an increase in the amount of heat recoverable from hot oil; the replacement of obsolete instruments and controllers with state-of-the-art types for higher energy efficiency in the control of distillation tower operation, etc. It is desired that this energy saving project will be embodied for a reduction in CO2 emissions. (NEDO)

Changing emphasis at the NRC's Office of Nuclear Regulatory Research

International Nuclear Information System (INIS)

Remick, F.J.

1994-01-01

One of the major objectives of the Office of Research is to ensure availability of sound technical information for timely decision making in support of the NRC's safety mission. The Office of Research is changing some of its emphasis to better meet the expected needs of the NRC's regulatory offices. Long-standing programs in support of operating reactors are nearing completion. These programs include plant aging and severe accident research for currently operating plants. This meeting will also address the new challenges faced by the NRC in its review of the advanced light water and non-light water reactors. As plant aging and severe accident research programs are nearing completion, the research activities are coming to focus on the emerging technologies, for example, digital instrumentation and control systems, both as replacement equipment for operating plants and as the technology of choice and necessity for the advanced reactors. Necessity, because analog equipment is becoming obsolete. Other examples include the use of new materials in operating plants, human factors considerations in the design and operation of the advanced plants, thermal-hydraulic characteristics of the advanced reactors, and new construction techniques

LDRD report: Smoke effects on electrical equipment

International Nuclear Information System (INIS)

TANAKA, TINA J.; BAYNES, EDWARD E. JR.; NOWLEN, STEVEN P.; BROCKMANN, JOHN E.; GRITZO, LOUIS A.; SHADDIX, Christopher R.

2000-01-01

Smoke is known to cause electrical equipment failure, but the likelihood of immediate failure during a fire is unknown. Traditional failure assessment techniques measure the density of ionic contaminants deposited on surfaces to determine the need for cleaning or replacement of electronic equipment exposed to smoke. Such techniques focus on long-term effects, such as corrosion, but do not address the immediate effects of the fire. This document reports the results of tests on the immediate effects of smoke on electronic equipment. Various circuits and components were exposed to smoke from different fields in a static smoke exposure chamber and were monitored throughout the exposure. Electrically, the loss of insulation resistance was the most important change caused by smoke. For direct current circuits, soot collected on high-voltage surfaces sometimes formed semi-conductive soot bridges that shorted the circuit. For high voltage alternating current circuits, the smoke also tended to increase the likelihood of arcing, but did not accumulate on the surfaces. Static random access memory chips failed for high levels of smoke, but hard disk drives did not. High humidity increased the conductive properties of the smoke. The conductivity does not increase linearly with smoke density as first proposed; however, it does increase with quantity. The data can be used to give a rough estimate of the amount of smoke that will cause failures in CMOS memory chips, dc and ac circuits. Comparisons of this data to other fire tests can be made through the optical and mass density measurements of the smoke

Replacement of CFCs in thermodynamical systems; Remplacement des C.F.C. dans les systemes thermodynamiques

Energy Technology Data Exchange (ETDEWEB)

Fleurance, M.

1996-12-31

Following the Montreal protocol and the withdrawal of the CFC-type refrigerating fluids, York France company has developed and adapted its equipments to new refrigerants. Each user will have to know how to define the best option for his installation: opting for or ignoring the withdrawal of CFCs, confining the installations, changing for new intermediate substitutes (HCFC-type), or changing or replacing with new long term substitutes (HFCs). (J.S.)

Foaming of waste cathode ray tube panel glass via CaCO3

DEFF Research Database (Denmark)

König, Jakob; Petersen, Rasmus Rosenlund; Yue, Yuanzheng

The disposal of obsolete electrical and electronic equipment has become a global environmental problem. However, with responsible collecting, dismantling and materials separation, majority of materials can be recycled. Cathode ray tube (CRT) glass represents as much as two-thirds of the weight...

Czech, Slovak science ten years after split

CERN Multimedia

2003-01-01

Ten years after the split of Czechoslovakia Czech and Slovak science are facing the same difficulties: shortage of money for research, poor salaries, obsolete equipment and brain drain, especially of the young, according to a feature in the Daily Lidove Noviny (1 page).

Switchgear obsolescence

International Nuclear Information System (INIS)

Irish, C.S.

2004-01-01

As discussed in many forums, the global nuclear industry is struggling with many equipment issues, the foremost being obsolescence. The electrical distribution of a nuclear power plant is vital to plant safety and obviously to generation of electricity. Low and medium voltage breakers independent of OEM are becoming or are already obsolete in very large and alarming numbers. The obsolescence of the breakers causes the routine maintenance and overhauls to become very expensive and time consuming or not even possible at all. This is caused by the parts needed for the maintenance and overhauls to either not be available or to have very expensive prices and long lead times. The end result is that the overall switchgear reliability is greatly reduced due to nuisance trips, increased maintenance surveillance and breakers not being maintained with the frequency as needed. A lot of pressure is put on plant personnel to increase the reliability of the switchgear in the most cost effective manner. This paper will discuss using switchgear breaker replacements to improve the overall switchgear reliability. Whether the switchgear is 'safety related' or 'non-safety related' there is significant incentive to make as little field changes as necessary to improve the reliability. Replacement breakers achieve this goal. Replacement breakers are installed into the existing switchgear with little to no field changes. 600V, 5kV and 15kV breaker replacements are discussed with examples. (author)

Root cause analysis underscores the importance of understanding, addressing, and communicating cold chain equipment failures to improve equipment performance.

Science.gov (United States)

Lennon, Pat; Atuhaire, Brian; Yavari, Shahrzad; Sampath, Vidya; Mvundura, Mercy; Ramanathan, Nithya; Robertson, Joanie

2017-04-19

Vaccine cold chain equipment (CCE) in developing countries is often exposed to harsh environmental conditions, such as extreme temperatures and humidity, and is subject to many additional challenges, including intermittent power supply, insufficient maintenance capacity, and a scarcity of replacement parts. Together, these challenges lead to high failure rates for refrigerators, potentially damaging vaccines and adversely affecting immunization coverage. Providing a sustainable solution for improving CCE performance requires an understanding of the root causes of failure. Project teams conducted small-scale studies to determine the root causes of CCE failure in selected locations in Uganda and Mozambique. The evaluations covered 59 failed refrigerators and freezers in Uganda and 27 refrigerators in Mozambique. In Uganda, the vast majority of failures were due to a cooling unit fault in one widely used refrigerator model. In Mozambique, 11 of the 27 problems were attributable to solar refrigerators with batteries that were unable to hold a charge, and another eight problems were associated with a need to adjust thermostat settings. The studies showed that tracking and evaluation of equipment performance and failure can yield important, actionable information for a range of stakeholders, including local CCE technicians, the ministry of health, equipment manufacturers, and international partners such as the United Nations Children's Fund, World Health Organization, and Gavi, the Vaccine Alliance. Collaborative efforts to systematically collect and communicate data on CCE performance and causes of failure will help to improve the efficiency and reach of immunization programs in low- and middle-income countries. Copyright © 2016 The Author(s). Published by Elsevier Ltd.. All rights reserved.

Defining line replaceable units

NARCIS (Netherlands)

Parada Puig, J. E.; Basten, R. J I

2015-01-01

Defective capital assets may be quickly restored to their operational condition by replacing the item that has failed. The item that is replaced is called the Line Replaceable Unit (LRU), and the so-called LRU definition problem is the problem of deciding on which item to replace upon each type of

Steam generator replacement in Bruce A Unit 1 and Unit 2

International Nuclear Information System (INIS)

Hart, R.S.

2007-01-01

The Bruce A Generating Station consists of four 900 MW class CANDU units. The reactor and Primary Heat Transport System for each Unit are housed within a reinforced concrete reactor vault. A large duct running below the reactor vaults accommodates the shared fuel handling system, and connects the four reactor vaults to the vacuum building. The reactor vaults, fuelling system duct and the vacuum building constitute the station vacuum containment system. Bruce A Unit 2 was shut down in 1995 and Bruce A Units 1, 3 and 4 were shutdown in 1997. Bruce A Units 3 and 4 were returned to service in late 2003 and are currently operating. Units 1 and 2 remain out of service. Bruce Power is currently undertaking a major rehabilitation of Bruce A Unit 1 and Unit 2 that will extend the in-service tile of these units by at least 25 years. Replacement of the Steam Generators (eight in each unit) is required; this work was awarded to SNC-Lavalin Nuclear (SLN). The existing steam drums (which house the steam separation and drying equipment) will be retained. Unit 2 is scheduled to be synchronized with the grid in 2009, followed by Unit 1 in 2009. Each Bruce A unit has two steam generating assemblies, one located above and to each end of the reactor. Each steam generating assembly consists of a horizontal cylindrical steam drum and four vertical Steam Generators. The vertical Steam Generators connect to individual nozzles that are located on the underside of the Steam Drum (SD). The steam drums are located in concrete shielding structures (steam drum enclosures). The lower sections of the Steam Generators penetrate the top of the reactor vaults: the containment pressure boundary is established by bellows assemblies that connect between the reactor vault roof slab and the Steam Generators. Each Steam Generators is supported from he bottom by a trapeze that is suspended from the reactor vault top structure. The Steam Generator Replacement (SGR) methodology developed by SLN for Unit 1

Fact sheet on nuclear power plant instrumentation and control technologies

International Nuclear Information System (INIS)

2006-01-01

Nuclear power plants (NPPs) are facing challenges in several instrumentation and control (I and C) areas with ageing and obsolete components and equipment. With license renewals and power uprates, the long-term operation and maintenance of obsolete I and C systems may not be a cost-effective and reliable option. The effort needed to maintain or increase the reliability and useful life of existing I and C systems may be greater in the long run than modernizing I and C systems or replacing them completely with new digital systems. The increased functionality of the new I and C systems can also open up new possibilities to better support the operation and maintenance activities in the plant. The IAEA recognizes the importance of the profound role the I and C systems play in the reliable, safe, efficient, and cost-effective operations of NPPs by supporting the activities of the Department of Nuclear Energy's Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI). The group was established in March 1970. Its membership currently includes thirty Member States and three international organizations. The most recent meeting of the TWG-NPPCI was held in May 2005 in Vienna. The meeting report is available at http://www.iaea.org/OurWork/ST/NE/NENP/twg_nppc.html. The next meeting of the TWGNPPCI will be the 21st meeting of the advisory body, and it will be held in May 2007

Generation of equipment response spectrum considering equipment-structure interaction

International Nuclear Information System (INIS)

Lee, Sang Hoon; Yoo, Kwang Hoon

2005-01-01

Floor response spectra for dynamic response of subsystem such as equipment, or piping in nuclear power plant are usually generated without considering dynamic interaction between main structure and subsystem. Since the dynamic structural response generally has the narrow-banded shapes, the resulting floor response spectra developed for various locations in the structure usually have high spectral peak amplitudes in the narrow frequency bands corresponding to the natural frequencies of the structural system. The application of such spectra for design of subsystems often leads to excessive design conservatisms, especially when the equipment frequency and structure are at resonance condition. Thus, in order to provide a rational and realistic design input for dynamic analysis and design of equipment, dynamic equipment-structure interaction (ESI) should be considered in developing equipment response spectrum which is particularly important for equipment at the resonance condition. Many analytical methods have been proposed in the past for developing equipment response spectra considering ESI. However, most of these methods have not been adapted to the practical applications because of either the complexities or the lack of rigorousness of the methods. At one hand, mass ratio among the equipment and structure was used as an important parameter to obtain equipment response spectra. Similarly, Tseng has also proposed the analytical method for developing equipment response spectra using mass ratio in the frequency domain. This method is analytically rigorous and can be easily validated. It is based on the dynamic substructuring method as applied to the dynamic soil-structure interaction (SSI) analysis, and can relatively easily be implemented for practical applications without to change the current dynamic analysis and design practice for subsystems. The equipment response spectra derived in this study are also based on Tseng's proposed method

Nuclear waste inventory characterization for mixer pumps and long length equipment removed from Hanford waste tanks

International Nuclear Information System (INIS)

Troyer, G.L.

1998-01-01

The removal and disposition of contaminated equipment from Hanford high-level nuclear waste tanks presents many challenges. One of which is the characterization of radioactive contaminants on components after removal. A defensible assessment of the radionuclide inventory of the components is required for disposal packaging and classification. As examples of this process, this paper discusses two projects: the withdrawal of thermocouple instrument tubes from Tank 101-AZ, and preparation for eventual replacement of the hydrogen mitigation mixer pump in Tank 101-SY. Emphasis is on the shielding analysis that supported the design of radiation detection systems and the interpolation of data recorded during the equipment retrieval operations

Maintenance cost control at the Pacific Missile Test Center.

OpenAIRE

Jenson, Richard J.

1980-01-01

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

Flash-Aware Page Replacement Algorithm

Directory of Open Access Journals (Sweden)

Guangxia Xu

2014-01-01

Full Text Available Due to the limited main memory resource of consumer electronics equipped with NAND flash memory as storage device, an efficient page replacement algorithm called FAPRA is proposed for NAND flash memory in the light of its inherent characteristics. FAPRA introduces an efficient victim page selection scheme taking into account the benefit-to-cost ratio for evicting each victim page candidate and the combined recency and frequency value, as well as the erase count of the block to which each page belongs. Since the dirty victim page often contains clean data that exist in both the main memory and the NAND flash memory based storage device, FAPRA only writes the dirty data within the victim page back to the NAND flash memory based storage device in order to reduce the redundant write operations. We conduct a series of trace-driven simulations and experimental results show that our proposed FAPRA algorithm outperforms the state-of-the-art algorithms in terms of page hit ratio, the number of write operations, runtime, and the degree of wear leveling.

A Centrifugal Contactor Design to Facilitate Remote Replacement

International Nuclear Information System (INIS)

Meikrantz, David H.; Law, Jack D.; Garn, Troy G.; Macaluso, Lawrence L.

2011-01-01

Advanced designs of nuclear fuel recycling and radioactive waste treatment plants are expected to include more ambitious goals for solvent extraction based separations including; higher separations efficiency, high-level waste minimization, and a greater focus on continuous processes to minimize cost and footprint. Therefore, Annular Centrifugal Contactors (ACCs) are destined to play a more important role for such future processing schemes. This work continues the development of remote designs for ACCs that can process the large throughputs needed for future nuclear fuel recycling and radioactive waste treatment plants. A three stage, 12.5 cm diameter rotor module has been constructed and is being evaluated for use in highly radioactive environments. This prototype assembly employs three standard CINC V-05 clean-in-place (CIP) units modified for remote service and replacement via new methods of connection for solution inlets, outlets, drain and CIP. Hydraulic testing and functional checks were successfully conducted and then the prototype was evaluated for remote handling and maintenance. Removal and replacement of the center position V-05R contactor in the three stage assembly was demonstrated using an overhead rail mounted PaR manipulator. Initial evaluation indicates a viable new design for interconnecting and cleaning individual stages while retaining the benefits of commercially reliable ACC equipment. Replacement of a single stage via remote manipulators and tools is estimated to take about 30 minutes, perhaps fast enough to support a contactor change without loss of process equilibrium. The design presented in this work is scalable to commercial ACC models from V-05 to V-20 with total throughput rates ranging from 20 to 650 liters per minute.

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

Because there is a difference depending on the environment as for an inspection equipment the important part of bone density scan and the precision/accuracy of a tester, the management of quality must be made systematically. The equipment failure caused by overload effect due to the aged equipment and the increase of a patient was made frequently. Thus, the replacement of equipment and additional purchases of new bone density equipment caused a compatibility problem in tracking patients. This study wants to know whether the clinical changes of patient's bone density can be accurately and precisely reflected when used it compatibility like the existing equipment after equipment replacement and expansion. Two equipment of GE Lunar Prodigy Advance(P1 and P2) and the Phantom HOLOGIC Spine Road(HSP) were used to measure equipment precision. Each device scans 20 times so that precision data was acquired from the phantom(Group 1). The precision of a tester was measured by shooting twice the same patient, every 15 members from each of the target equipment in 120 women(average age 48.78, 20-60 years old)(Group 2). In addition, the measurement of the precision of a tester and the cross-calibration data were made by scanning 20 times in each of the equipment using HSP, based on the data obtained from the management of quality using phantom(ASP) every morning (Group 3). The same patient was shot only once in one equipment alternately to make the measurement of the precision of a tester and the cross-calibration data in 120 women(average age 48.78, 20-60 years old)(Group 4). It is steady equipment according to daily Q.C Data with 0.996 g/cm 2 , change value(%CV) 0.08. The meanSD and a %CV price are ALP in Group 1(P1 : , , P2 : , %CV=0.192). The mean±SD and a %CV price are P1 : 1.064±0.002 g/cm 2 , %CV=0.190 g/cm 2 , P2 : 1.061±0.003 g/cm 3 , %CV=0.163 in Group 2. The average error±2SD and %CV are P1 - (spine: 0.001±0.013 g/cm 2 , %CV=0.94, Femur: 0.001±0.019 g/cm 2 , %CV

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

Because there is a difference depending on the environment as for an inspection equipment the important part of bone density scan and the precision/accuracy of a tester, the management of quality must be made systematically. The equipment failure caused by overload effect due to the aged equipment and the increase of a patient was made frequently. Thus, the replacement of equipment and additional purchases of new bone density equipment caused a compatibility problem in tracking patients. This study wants to know whether the clinical changes of patient's bone density can be accurately and precisely reflected when used it compatibility like the existing equipment after equipment replacement and expansion. Two equipment of GE Lunar Prodigy Advance(P1 and P2) and the Phantom HOLOGIC Spine Road(HSP) were used to measure equipment precision. Each device scans 20 times so that precision data was acquired from the phantom(Group 1). The precision of a tester was measured by shooting twice the same patient, every 15 members from each of the target equipment in 120 women(average age 48.78, 20-60 years old)(Group 2). In addition, the measurement of the precision of a tester and the cross-calibration data were made by scanning 20 times in each of the equipment using HSP, based on the data obtained from the management of quality using phantom(ASP) every morning (Group 3). The same patient was shot only once in one equipment alternately to make the measurement of the precision of a tester and the cross-calibration data in 120 women(average age 48.78, 20-60 years old)(Group 4). It is steady equipment according to daily Q.C Data with 0.996 g/cm{sup 2}, change value(%CV) 0.08. The meanSD and a %CV price are ALP in Group 1(P1 : , , P2 : , %CV=0.192). The mean{+-}SD and a %CV price are P1 : 1.064{+-}0.002 g/cm{sup 2}, %CV=0.190 g/cm{sup 2}, P2 : 1.061{+-}0.003 g/cm{sup 3}, %CV=0.163 in Group 2. The average error{+-}2SD and %CV are P1 - (spine: 0.001{+-}0.013 g/cm{sup 2}, %CV=0

Equipment considerations

International Nuclear Information System (INIS)

Anon.

1992-01-01

Trace or ultratrace analyses require that the HPLC equipment used, including the detector, be optimal for such determinations. HPLC detectors are discussed at length in Chapter 4; discussion here is limited to the rest of the equipment. In general, commercial equipment is adequate for trace analysis; however, as the authors approach ultratrace analysis, it becomes very important to examine the equipment thoroughly and optimize it, where possible. For this reason they will review the equipment commonly used in HPLC and discuss the optimization steps. Detectability in HPLC is influenced by two factors (1): (a) baseline noise or other interferences that lead to errors in assigning the baseline absorbance; (b) peak width. 87 refs

Willingness to pay for replacing traditional energies with renewable energy in South Korea

International Nuclear Information System (INIS)

Lee, Chul-Yong; Lee, Min-Kyu; Yoo, Seung-Hoon

2017-01-01

This study aims to estimate consumers' willingness to pay (WTP) for replacing traditional energy generated from nuclear and coal sources with renewable energy, using a contingent valuation (CV) model. To this end, it reports the results from a CV survey of 1000 respondents and a spike model. The estimate obtained shows that consumers are willing to pay an additional USD 3.3 per month to replace nuclear power and USD 3.0 per month to replace coal energy. The total WTPs for the substitution of nuclear power and coal-fired power with renewable energy sources are calculated as USD 722 million and USD 659 million, respectively. When such a WTP is provided for installing photovoltaic equipment, the photovoltaic capacity of 372 MW for nuclear power substitution and 339 MW for coal-fired power substitution can be built every year, taking into consideration the backup cost and opportunity cost. Given that the WTP means the level of public acceptability of a rising energy bill, Korean consumers would accept an increase in their electricity bills caused by solar photovoltaic energy equivalent to 31–32 GW in the medium and long term. - Highlights: • There is a growing need to replace traditional energies with renewable energy. • We estimate consumers' willingness to pay (WTP) for the replacement. • To this end, a contingent valuation survey of 1000 households was conducted. • Monthly WTPs are USD 3.3 and 3.0 for nuclear power and coal, respectively. • These values amount to solar photovoltaic energy equivalent to 31–32 GW.

Medical Issues: Equipment

Science.gov (United States)

... Information Packets Equipment Pool Living With SMA Medical Issues Palliative Breathing Orthopedics Nutrition Equipment Daily Life At ... curesma.org > support & care > living with sma > medical issues > equipment Equipment Individuals with SMA often require a ...

Transcatheter aortic valve replacement

Science.gov (United States)

... gov/ency/article/007684.htm Transcatheter aortic valve replacement To use the sharing features on this page, please enable JavaScript. Transcatheter aortic valve replacement (TAVR) is surgery to replace the aortic valve. ...

Energy saving by means of air conditioning equipment replacement and the household application of thermal insulation; Ahorro de energia electrica por reemplazo de equipos de aire acondicionado y aplicacion de aislamiento termico en viviendas

Energy Technology Data Exchange (ETDEWEB)

Peralta Solorio, Jose Luis [Fideicomiso para el Ahorro de la Energia (Mexico)

2005-07-15

An extension study of the Financing Program for Energy Saving looked for the evaluation of the electric energy saving potential obtained by the replacement of air conditioning equipment and the application of thermal insulation in 30 houses of two Mexican cities with warmth climate. In a joint effort with Comision Federal de Electricidad the consumption files of the users were analyzed and field measurements of electric demand and of refrigeration were made. As a following step the change of the refrigeration necessities derived from the application of thermal insulation were evaluated as well as the energy efficiency improvement obtained by the substitution of the air conditioning equipment and the favorable results obtained by the implementation of both measures - thermal insulation and change of air conditioning equipment in a joint form. This way, as a conclusion, the optimum sequence of application of these measures is revealed. [Spanish] Un estudio extension del Programa de Financiamiento para el Ahorro de Energia Electrica busco evaluar el potencial de ahorro de energia electrica alcanzado por el reemplazo de equipos de aire acondicionado y la aplicacion de aislamiento termico en 30 viviendas de dos ciudades mexicanas con clima calido. En un esfuerzo conjunto con la Comision Federal de Electricidad se analizaron los historiales de consumo de los usuarios y se efectuaron las mediciones de campo de demanda electrica y de refrigeracion. Como paso siguiente se valoro el cambio en las necesidades de refrigeracion derivado de la aplicacion de aislamiento termico al igual que la mejora en eficiencia energetica obtenida por la sustitucion de aire acondicionado y se identificaron los resultados favorecedores arrojados por la implementacion de ambas medidas -aislamiento termico y cambio de equipo de aire acondicionado- en forma conjunta. De esta manera, como conclusion, se devela la mas optima secuencia de aplicacion de estas medidas.

Film replacement by digital x-ray detectors - the correct procedure and equipment

International Nuclear Information System (INIS)

Ewert, U.; Zscherpel, U.; Bavendiek, K.

2004-01-01

New digital detectors were developed for medical applications, which have the potential to substitute the X-ray film and revolutionise the radiological technique. Digital Detector Arrays (DDA: Flat Panel Detectors, Line Detectors) and Imaging Plates (Computed Radiography) allow a fast detection of radiographic images in a shorter time and with higher dynamic than film applications. Companies report about a reduction of exposure time down to 5 - 25% in comparison to NDT film exposures. This provides together with the reduction of consumables economical (and also ecological) benefits and short amortisation periods. But this does not always provide the same image quality as NDT film. The requirements of the European and USA standards for film radiography are analysed to derive correct requirements for the digital image quality and procedures for prediction and measurement of image quality. Basically the USA standards seem to be more tolerant for these new innovative technologies. New standard proposals use signal/noise ratio and unsharpness as dominant parameters for image quality. Specialised measurement procedures are described. The properties of the new detectors can be controlled by electronics and exposure conditions. New names appear in literature like 'direct radiography' and 'film replacement techniques'. The basic advantage of the new digital techniques is the possibility to use numeric procedures for image interpretation. Industrial radiology can be optimised for crack detection as well as for analysis of flaw depth and shape measurement. Automated flaw detection, measurement of part dimensions and detection of completeness are used for serial part inspection devices. Parallel to the development of DDA's, an extraordinary increase of Computed Tomography (CT) applications can be observed. (author)

Modelling and design of undercarriage components of large-scale earthmoving equipment in tar sand operations

Energy Technology Data Exchange (ETDEWEB)

Szymanski, J.; Frimpong, S.; Sobieski, R. [Alberta Univ., Edmonton, AB (Canada). Centre for Advanced Energy and Minerals Research

2004-07-01

This presentation described the fundamental and applied research work which has been carried out at the University of Alberta's Centre for Advanced Energy and Minerals Research to improve the undercarriage elements of large scale earthmoving equipment used in oil sands mining operations. A new method has been developed to predict the optimum curvature and blade geometry of earth moving equipment such as bulldozers and motor graders. A mathematical relationship has been found to approximate the optimum blade shape for reducing cutting resistance and fill resistance. The equation is a function of blade geometry and soil properties. It is the first model that can mathematically optimize the shape of a blade on earth moving equipment. A significant saving in undercarriage components can be achieved from reducing the amount of cutting and filling resistance for this type of equipment working on different soils. A Sprocket Carrier Roller for a Tracked Vehicle was also invented to replace the conventional cylindrical carrier roller. The new sprocket type carrier roller offers greater support for the drive track and other components of the undercarriage assembly. A unique retaining pin assembly has also been designed to detach connecting disposable wear parts from earthmoving equipment. The retaining pin assembly is easy to assemble and disassemble and includes reusable parts. 13 figs.

Digital Signal Processing Applied to the Modernization Of Polish Navy Sonars

Directory of Open Access Journals (Sweden)

Marszal Jacek

2014-04-01

Full Text Available The article presents the equipment and digital signal processing methods used for modernizing the Polish Navy’s sonars. With the rapid advancement of electronic technologies and digital signal processing methods, electronic systems, including sonars, become obsolete very quickly. In the late 1990s a team of researchers of the Department of Marine Electronics Systems, Faculty of Electronics, Telecommunications and Informatics, Gdansk University of Technology, began work on modernizing existing sonar systems for the Polish Navy. As part of the effort, a methodology of sonar modernization was implemented involving a complete replacement of existing electronic components with newly designed ones by using bespoke systems and methods of digital signal processing. Large and expensive systems of ultrasound transducers and their dipping and stabilisation systems underwent necessary repairs but were otherwise left unchanged. As a result, between 2001 and 2014 the Gdansk University of Technology helped to modernize 30 sonars of different types.

Online data handling and storage at the CMS experiment

CERN Document Server

Andre, Jean-marc Olivier; Behrens, Ulf; Branson, James; Chaze, Olivier; Demiragli, Zeynep; Dobson, Marc; Dupont, Aymeric; Erhan, Samim; Gigi, Dominique; Glege, Frank; Gomez Ceballos, Guillelmo; Hegeman, Jeroen Guido; Holzner, Andre Georg; Jimenez Estupinan, Raul; Masetti, Lorenzo; Meijers, Franciscus; Meschi, Emilio; Mommsen, Remigius; Morovic, Srecko; Nunez Barranco Fernandez, Carlos; O'Dell, Vivian; Orsini, Luciano; Paus, Christoph Maria Ernst; Petrucci, Andrea; Pieri, Marco; Racz, Attila; Roberts, Penelope Amelia; Sakulin, Hannes; Schwick, Christoph; Stieger, Benjamin Bastian; Sumorok, Konstanty; Veverka, Jan; Zaza, Salvatore; Zejdl, Petr

2015-01-01

During the LHC Long Shutdown 1, the CMS Data Acquisition (DAQ) system underwent a partial redesign to replace obsolete network equipment, use more homogeneous switching technologies, and support new detector back-end electronics. The software and hardware infrastructure to provide input, execute the High Level Trigger (HLT) algorithms and deal with output data transport and storage has also been redesigned to be completely file- based. All the metadata needed for bookkeeping are stored in files as well, in the form of small 'documents' using the JSON encoding. The Storage and Transfer System (STS) is responsible for aggregating these files produced by the HLT, storing them temporarily and transferring them to the T0 facility at CERN for subsequent offline processing. The STS merger service aggregates the output files from the HLT from ~62 sources produced with an aggregate rate of ~2GB/s. An estimated bandwidth of 7GB/s in concurrent read/write mode is needed. Furthermore, the STS has to be able to store ...

Feasibility study on the modernization and expansion of the Tema Oil Refinery. Executive Summary. Export trade information

International Nuclear Information System (INIS)

Anon.

1992-04-01

The Tema Oil Refinery (TOR), which was commissioned in 1963, is a simple hydro-skimming plant which processes crude oil into LPG, gasoline, kerosene, gasoil, and fuel oil. It is the only petroleum refinery in Ghana. Over the years some of the equipment in the refinery has deteriorated or become obsolete necessitating major rehabilitation. A study of the refinery expansion project takes into consideration earlier studies and, equally important, recognizes the extensive work done by TOR in rehabilitating the refinery. The program, carried out in phases because of funding limitations, has addressed the critical repairs and replacements in the process units and utilities necessary to prolong the life of the refinery and assure reliability and safe operation. It undertook the task of investigating the feasibility of modernizing and expanding the refinery at Tema, Ghana to meet projected market demands until the year 2005. A process planning study was conducted to select the optimal process and utility configuration which would result in economic benefits to Ghana

Dismantling an alpha-contaminated facility

International Nuclear Information System (INIS)

Caldwell, R.D.; Harper, R.M.

1975-01-01

The difficult task of removing large pieces of highly contaminated equipment from an obsolete plutonium-239 facility was completed in a seven-month operation that included structural alteration of the process building. Detailed job planning, job execution and contamination control were major factors in accomplishing the task

Virtual Bridge Design Challenge

Science.gov (United States)

Mitts, Charles R.

2013-01-01

This design/problem-solving activity challenges students to design a replacement bridge for one that has been designated as either structurally deficient or functionally obsolete. The Aycock MS Technology/STEM Magnet Program Virtual Bridge Design Challenge is an authentic introduction to the engineering design process. It is a socially relevant…

Special equipment for processing can-rupture measurements; Equipement specialise de traitement des mesures de rupture de gaines

Energy Technology Data Exchange (ETDEWEB)

Kaiser, J.; Phalippou, J.; Dumont, D.; Viellard, R. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1969-07-01

Recent installations for detecting can-rupture in nuclear reactors use, in the measurement processing section, a digital computer, either completely or partially. The reliability of the system is limited by that of the computer, which represents a common point for the processing of data from the detector. In order to satisfy the demands imposed by safety considerations for the operation of the equipment it is necessary to consider the possibility of installing a second computer in certain cases. The use of a computer involves the presence as interface between the detection equipment and the computer itself, of sealers operating as integrators for the pulses produced by the detector. By adding a certain number of circuits to these sealers, it is possible to carry out the work now demanded of the computer, as far as the calculation is concerned. This reasoning has led us to a so-called 'decentralized' solution involving the construction of specialized equipment in the region of the prospector itself. We believe that this solution, apart from the reliability point of view, has definite economic advantages. In our solution, the common point in the processing of the data is now situated not in the zone of the production of results but further down, in the printing out of these results. Even in the case of an incident at the common point, the results are produced, exposed and compared to the alarm thresholds. In the case of a breakdown of the specialized equipment, the results from this prospector are no longer available but the others continue to operate. It seems that this solution is more reliable than that employing universal computers. By using an interchangeable drawer system (MULTIBLOC) it is possible to replace rapidly any of the specialized equipment which breaks down. The systematic use of integrated circuits (TTL) ensures an increased reliability of the equipment. (author) [French] Les installations recentes de detection de rupture de gaines

Ankle replacement - discharge

Science.gov (United States)

... total - discharge; Total ankle arthroplasty - discharge; Endoprosthetic ankle replacement - discharge; Osteoarthritis - ankle ... You had an ankle replacement. Your surgeon removed and reshaped ... an artificial ankle joint. You received pain medicine and were ...

The Mexican market for electrical equipment and services

International Nuclear Information System (INIS)

Robinson, J.

1994-05-01

Most of Mexico's electric power needs are supplied by the Comision Federal de Electricidad (CFE). Total installed capacity is ca 33,000 MW, of which ca 42% comes from oil-fired generation and 26% hydroelectric. Electricity consumption is expected to grow at ca 6%/y between 1993 and 2000; to meet this demand, CFE plans to build nearly 14,000 MW of additional generating capacity to cost ca $34 billion. A new law governing the electric power sector recently privatized electrical project construction and provided for private financing. Construction of all larger generation and transmission projects has been privatized, thereby deregulating and simplifying the bidding process for Canadian firms wishing to bid, subcontract, or supply equipment or materials. The most notable opportunities for Canadian firms are in transmission projects. The Mexican electrical manufacturing industry comprises ca 2,000 firms employing 150,000 people. Branch plants of global firms plus domestic companies supply over 70% of market demand. Production of equipment and materials for the electrical sector is well integrated with suppliers and customers, and manufacturers are seeking imports to replace abandoned product lines as the industry rationalizes. These, along with more sophisticated equipment not made in Mexico, provide opportunities for Canadian suppliers. The North American Free Trade Agreement gives preference to Canadians over offshore competitors, and eliminates many barriers to exports. Canada's Export Development Corporation provides financing with a line of credit for the electrical sector. Marketing in Mexico is best done through personal visits and capable local representation. A directory of Mexican electrical manufacturers who import is appended. 1 tab

Semiconductor Manufacturing equipment introduction

International Nuclear Information System (INIS)

Im, Jong Sun

2001-02-01

This book deals with semiconductor manufacturing equipment. It is comprised of nine chapters, which are manufacturing process of semiconductor device, history of semiconductor manufacturing equipment, kinds and role of semiconductor manufacturing equipment, construction and method of semiconductor manufacturing equipment, introduction of various semiconductor manufacturing equipment, spots of semiconductor manufacturing, technical elements of semiconductor manufacturing equipment, road map of technology of semiconductor manufacturing equipment and semiconductor manufacturing equipment in the 21st century.

REPLACEMENT SPARE PART INVENTORY MONITORING USING ADAPTIVE NEURO FUZZY INFERENCE SYSTEM

Directory of Open Access Journals (Sweden)

Hartono Hartono

2016-01-01

Full Text Available Abstract   The amount of inventory is determined on the basis of the demand. So that users can know the demand forecasts need to be done on the request. This study uses the data to implement a replacement parts on the electronic module production equipment in the telecommunications transmission systems, switching, access and power, ie by replacing the electronic module in the system is trouble  or damaged parts of a good electronic module spare parts inventory, while the faulty electronic modules shipped to the Repair Center for repaired again, so that the results of these improvements can replenish spare part  inventory. Parameters speed on improvement process of electronic module broken (repaired, in the form of an average repair time at the repair centers, in order to get back into the electronic module that is ready for used as spare parts in compliance with the safe supply inventory  warehouse.  This research using the method  of  Adaptive Neuro Fuzzy Inference System (ANFIS in developing a decision support system for inventory control of spare parts available in Warehouse Inventory taking into account several parameters supporters, namely demand, improvement and fulfillment of spare parts and repair time. This study uses a recycling input parameter repair faulty electronic module of the customer to immediately replace the module in inventory warehouse,  do improvements in the Repair Center. So the acceleration restoration factor is very influential as the input spare parts inventory supply in the warehouse and using the Adaptive Neuro-Fuzzy Inference System (ANFIS method.   Keywords: ANFIS, inventory control, replacement

Patients Unicondylar Knee Replacement vs. Total Knee Replacement

OpenAIRE

Hedra Eskander

2017-01-01

The aim of this review article is to analyse the clinical effectiveness of total knee replacement (TKR) compared to unicondylar knee replacement (UKR) on patients. In terms of survival rates, revision rates and postoperative complications. The keywords used were: knee arthroplasty. Nearly three thousand articles were found on 25 August 2016. Of those, only twenty-five were selected and reviewed because they were strictly focused on the topic of this article. Compared with those who have TKR, ...

Artificial Disc Replacement

Science.gov (United States)

... Spondylolisthesis BLOG FIND A SPECIALIST Treatments Artificial Disc Replacement (ADR) Patient Education Committee Jamie Baisden The disc ... Disc An artificial disc (also called a disc replacement, disc prosthesis or spine arthroplasty device) is a ...

Product Platform Replacements

DEFF Research Database (Denmark)

Sköld, Martin; Karlsson, Christer

2012-01-01

. To shed light on this unexplored and growing managerial concern, the purpose of this explorative study is to identify operational challenges to management when product platforms are replaced. Design/methodology/approach – The study uses a longitudinal field-study approach. Two companies, Gamma and Omega...... replacement was chosen in each company. Findings – The study shows that platform replacements primarily challenge managers' existing knowledge about platform architectures. A distinction can be made between “width” and “height” in platform replacements, and it is crucial that managers observe this in order...... to challenge their existing knowledge about platform architectures. Issues on technologies, architectures, components and processes as well as on segments, applications and functions are identified. Practical implications – Practical implications are summarized and discussed in relation to a framework...

15 years steam generator experience in German PWR power plants; part II: replacement of two completely assembled steam generators within ten weeks

International Nuclear Information System (INIS)

Scheuktanz, G.; Bouecker, R.; Riess, R.; Soellner, P.; Stieding, L.; Termeuhlen, H.

1984-01-01

This paper reports on the replacement of two steam generators at the Obrigheim power plant during a 10-week period, including a description of the methods and equipment used to do so. It is concluded that the method should be used only if transportation conditions within the reactor building preclude a complete system exchange and that one of the main reasons for the success of this operation was the very close relationship established between plant personnel and the equipment supplier and contractor, a relationship which began when the project was in the planning stage

Radiographic inspection. Film replacement with digital detector arrays in aerospace applications

International Nuclear Information System (INIS)

Schulte, Frank; Bavendiek, Klaus

2016-01-01

The new Digital Radiographic Inspection method replace more and more the conventional Film technique. For DDA (Digital Detector Array) systems it is currently necessary to use automated or semi-automated systems. For CR (Computer Radiography) Systems the conventional Film Systems may be used. For this CR technique operators can use same X-Ray Units (Bunker) and same X-Ray equipment. But on CR technique we have basically the same settings like the Film-based technique. More or less same exposure times and for aerospace application long scanning times for the CR foils. In fact there is no big benefit in capacity or in economical view. Regarding this issue we thought about the option to use a DDA System instead of a Film or CR System to use the current Film Equipment (Bunker, Generator, Tube.) and replace this 1:1 by a manual system. In this time only small detectors with fine pixel pitch was available on the market. With this type of DDA's is was absolutely uneconomical to inspect parts in serial inspection. Therefore a new generation of DDA's were developed, which is able to replace Film or CR System 1:1 with adequate economical properties for specific applications. The new PerkinElmer XRD 1611 Panel has a size of 40 x 40 cm and a pixel pitch of 100 μm. The baseline for the new DDA Panel was the most used X-Ray Film in size 30 x 40 cm. The Pixel Pitch and requirements for Bad Pixel based on the requirements for spatial resolution of the applicable ASTM standards and different customer specifications for castings. With this new DDA System is it possible to inspect small and medium castings in very short time with excellent image quality. The System is able to process images under 1 minute include averaging. Images will be transferred by a specific software tool to an offline reading station where certified Level 2 operator can inspect the images. Images will be archived as 16bit DICONDE File. All relevant images information are included in DICONDE File

Replacement

Directory of Open Access Journals (Sweden)

S. Radhakrishnan

2014-03-01

Full Text Available The fishmeal replaced with Spirulina platensis, Chlorella vulgaris and Azolla pinnata and the formulated diet fed to Macrobrachium rosenbergii postlarvae to assess the enhancement ability of non-enzymatic antioxidants (vitamin C and E, enzymatic antioxidants (superoxide dismutase (SOD and catalase (CAT and lipid peroxidation (LPx were analysed. In the present study, the S. platensis, C. vulgaris and A. pinnata inclusion diet fed groups had significant (P < 0.05 improvement in the levels of vitamins C and E in the hepatopancreas and muscle tissue. Among all the diets, the replacement materials in 50% incorporated feed fed groups showed better performance when compared with the control group in non-enzymatic antioxidant activity. The 50% fishmeal replacement (best performance diet fed groups taken for enzymatic antioxidant study, in SOD, CAT and LPx showed no significant increases when compared with the control group. Hence, the present results revealed that the formulated feed enhanced the vitamins C and E, the result of decreased level of enzymatic antioxidants (SOD, CAT and LPx revealed that these feeds are non-toxic and do not produce any stress to postlarvae. These ingredients can be used as an alternative protein source for sustainable Macrobrachium culture.

Medicare program; replacement of reasonable charge methodology by fee schedules for parenteral and enteral nutrients, equipment, and supplies. Final rule.

Science.gov (United States)

2001-08-28

This final rule implements fee schedules for payment of parenteral and enteral nutrition (PEN) items and services furnished under the prosthetic device benefit, defined in section 1861(s)(8) of the Social Security Act. The authority for establishing these fee schedules is provided by the Balanced Budget Act of 1997, which amended the Social Security Act at section 1842(s). Section 1842(s) of the Social Security Act specifies that statewide or other area wide fee schedules may be implemented for the following items and services still subject to the reasonable charge payment methodology: medical supplies; home dialysis supplies and equipment; therapeutic shoes; parenteral and enteral nutrients, equipment, and supplies; electromyogram devices; salivation devices; blood products; and transfusion medicine. This final rule describes changes made to the proposed fee schedule payment methodology for these items and services and provides that the fee schedules for PEN items and services are effective for all covered items and services furnished on or after January 1, 2002. Fee schedules will not be implemented for electromyogram devices and salivation devices at this time since these items are not covered by Medicare. In addition, fee schedules will not be implemented for medical supplies, home dialysis supplies and equipment, therapeutic shoes, blood products, and transfusion medicine at this time since the data required to establish these fee schedules are inadequate.

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

Space Heating Equipment

Energy Technology Data Exchange (ETDEWEB)

Rafferty, Kevin D.

1998-01-01

The performance evaluation of space heating equipment for a geothermal application is generally considered from either of two perspectives: (a) selecting equipment for installation in new construction, or (b) evaluating the performance and retrofit requirements of an existing system. With regard to new construction, the procedure is relatively straightforward. Once the heating requirements are determined, the process need only involve the selection of appropriately sized hot water heating equipment based on the available water temperature. It is important to remember that space heating equipment for geothermal applications is the same equipment used in non-geothermal applications. What makes geothermal applications unique is that the equipment is generally applied at temperatures and flow rates that depart significantly from traditional heating system design. This chapter presents general considerations for the performance of heating equipment at non-standard temperature and flow conditions, retrofit of existing systems, and aspects of domestic hot water heating.

Control rod upper pin and roller removal and replacement

International Nuclear Information System (INIS)

Giordano, B.

1995-01-01

There has been increasing utility interest in removing cobalt sources as a means to minimize dose rates and shipping costs associated with operations, maintenance, shipping and radioactive waste disposal. This activation product accounts for approximately 80% of the dose rates at a plant. Estimates suggest that older (original equipment) control rod blades (CRBs) using stellite rollers and Haynes Alloy 25 pins can contribute as much as 43% of the cobalt in the plant. Since CRBs are the most concentrated source of cobalt in the reactor vessel, pin and roller (P ampersand R) replacement will provide significant reductions in cobalt-60 levels. The reductions will be measurable within 2 years, and should plateau within 5 to 6 years. This paper described a new, simple, cost effective, field proven in-situ method to replace these high source term contributing components and return the CRB to the reactor core for continued service. The paper also briefly describes a methodology that has been developed to estimate the labor and material costs along with a man-rem dollar savings for removal of the upper P ampersand Rs from in-service CRBs purchased prior to 1982. This method permits comparison to the cost of early replacement of CRBs. The result of this study is an EXCEL spreadsheet cost/benefit analysis that can be made plant specific by incorporation of plant data. The Analysis shows that the removal of P ampersand Rs can be beneficial for a Co-60 contribution as low as 5-10%. Recent interest by non-utility radioactive material users in obtaining the removed P ampersand Rs may further increase the benefit and reduce the cost associated with in-situ removal

Integration technique of digital I and C replacement and its Critical Digital Review procedure

International Nuclear Information System (INIS)

Huang, Hui-Wen; Yang, Wen-Long

2013-01-01

Highlights: ► A digital I and C replacement integration technique have been developed. ► Establishment of Nuclear Power Plant Digital Replacement Integration Guideline. ► Preliminary Investigation on I and C System Digitalization. ► Evaluation on I and C System Digitalization. ► Establishment of I and C System Digitalization Architectures. -- Abstract: Institute of Nuclear Energy Research (INER) developed a digital Instrumentation and Control (I and C) replacement integration technique on the basis of requirement of the three existing nuclear power plants (NPPs), which are Chin–Shan (CS) NPP, Kuo–Sheng (KS) NPP, and Maanshan (MS) NPP, in Taiwan, and also developed the related Critical Digital Review (CDR) procedure. The digital I and C replacement integration technique includes: (1) Establishment of Nuclear Power Plant Digital Replacement Integration Guideline, (2) Preliminary Investigation on I and C System Digitalization, (3) Evaluation on I and C System Digitalization, and (4) Establishment of I and C System Digitalization Architectures. These works can be a reference for performing I and C system digital replacement integration of the three existing NPPs of Taiwan Power Company (TPC). A CDR is the review for a critical system digital I and C replacement. The major reference of this procedure is EPRI TR-1011710 (2005) “Handbook for Evaluating Critical Digital Equipment and Systems” which was published by the Electric Power Research Institute (EPRI). With this document, INER developed a TPC-specific CDR procedure. Currently, CDR becomes one of the policies for digital I and C replacement in TPC. The contents of this CDR procedure include: Scope, Responsibility, Operation Procedure, Operation Flow Chart, CDR review items. The CDR review items include the comparison of the design change, Software Verification and Validation (SV and V), Failure Mode and Effects Analysis (FMEA), Evaluation of Diversity and Defense-in-depth (D3), Evaluation of

Advanced concepts and solutions for geothermal heating applied in Oradea, Romania

Science.gov (United States)

Antal, C.; Popa, F.; Mos, M.; Tigan, D.; Popa, B.; Muresan, V.

2017-01-01

Approximately 70% of the total population of Oradea benefits from centralized heating, about 55,000 apartments and 159,000 inhabitants are connected. The heating system of Oradea consists of: sources of thermal energy production (Combined heat and power (CHP) I Oradea and geothermal water heating plants); a transport network of heat; heat distribution network for heating and domestic hot water; substations, most of them equipped with worn and obsolete equipment. Recently, only a few heat exchangers were rehabilitated and electric valves were installed to control the water flow. After heat extraction, geothermal chilled waters from the Oradea area are: discharged into the sewer system of the city, paying a fee to the local water company which manages the city’s sewers; discharged into the small river Peta; or re-injected into the reservoir. In order to ensure environmental protection and a sustainable energy development in Oradea, renewable sources of energy have been promoted in recent years. In this respect, the creation of a new well for geothermal water re-injection into the reservoir limits any accidental thermal pollution of the environment, while ensuring the conservation properties of the aquifer by recharging with geothermal chilled water. The paper presents the achievements of such a project whose aim is to replace thermal energy obtained from coal with geothermal heating. The novelty consists in the fact that within the substation we will replace old heat exchangers, circulation pumps and valves with fully automated substations operating in parallel on both a geothermal system and on a primary heating system of a thermal plant.

Noise control of radiological monitoring equipment

International Nuclear Information System (INIS)

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

1998-01-01

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

Replacing lactose from calf milk replacers : effects on digestion and post-absorptive metabolism

NARCIS (Netherlands)

Gilbert, M.S.

2015-01-01

Summary PhD thesis Myrthe S. Gilbert

Replacing lactose from calf milk replacers – Effects on digestion and post-absorptive metabolism

Veal calves are fed milk replacer (MR) and solid feed. The largest part of the energy provided to veal calves

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

CERN Document Server

Dehavay, Claude

1995-01-01

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

Flued head replacement alternatives

International Nuclear Information System (INIS)

Smetters, J.L.

1987-01-01

This paper discusses flued head replacement options. Section 2 discusses complete flued head replacement with a design that eliminates the inaccessible welds. Section 3 discusses alternate flued head support designs that can drastically reduce flued head installation costs. Section 4 describes partial flued head replacement designs. Finally, Section 5 discusses flued head analysis methods. (orig./GL)

Improvement of the reactivity computer using windows for HANARO research reactor

International Nuclear Information System (INIS)

Park, S. Z.; Kim, M. J.; Seo, C. K.; Kim, H. N.

2001-01-01

A multi-channel wide range digital reactivity computer, which was developed by KAERI, has been used for HANARO research reactor since its fuel loading. It was based on the PC (personal computer) system equipped with an ADC (analog to digital converter), and the application program was developed in the MS-DOS envrionment. There exist some difficulties in upgrading the system through adding the necessary functions because not only DOS does not sure to presist in parallel with Windows, but also it has a drawback in supporting the advanced abilities of the innovatively developing PC. And it is very hard to change or replace some components, if needed, due to the strong dependence of the system on the PC hardware, which is fast obsolete. To solve these problems stemming from the MS-DOS envrionment, we replaced some parts of the existing system for neutron signal acquisition and completely upgraded on the Windows environment the application program including various helpful tools that are necessary for the reactivity measuring experiments. And to improve the processing features for the wide range neutron signal, we elaborated and implemented the new concept that a single channel of the neutron signal is renovated to multi ADC channels with different gains for the purpose of selectively utilizing a proper neutron signal

Design and implementation of equipment for monitoring the salinity in the subsoil

Directory of Open Access Journals (Sweden)

Mariano Norzagaray Campos

2012-09-01

Full Text Available Geochemical exploration equipments to explore the contaminants and structures geological in the subsoil come from abroad are expensive and sometimes parts for replacement are not available in the market. So it is necessary design apparatus that meet cover these needs. To the monitoring of variations in salinity there is semi-automatic equipment, but it always has difficult to manage. However, is not equipment for the indirect study of salinity in the subsoil. In this work was design equipment for measurement the apparent resistivity in the subsoil, at same time allow know the salinity, as well as the detection of any pollutant in groundwater. For make it, was selected a design of earthing systems, with electronic hardware which were jointed for apply to subsoil a direct current (DC through an array dipole-dipole and vertical electric sounding, with brass and stainless steel electrodes. In the earthing systems the electrodes were collocated in the equidistant line between the detectors of potential and current. A geometric factor (K, that depend on theelectrodes distance and direct current (I injected in the electrodes A and B, was used for measure the potential difference between the electrodes M and N; after was calculate the resistivity point to point for obtain a subsoil tomography geoelectrical. The equipment was calibrated with minimum error (rms < 2% whit respect to curves obtained in similar commercial equipment. On this situation, in this work was modernized and automated an equipment to determine thesalinity of the subsoil. The instrument was tasted in the micro basin Texcoco, State of Mexico, to define the environment geometry formed by alluvial or lake sediments from igneous rocks (andesites, rhyolites and tuffs vitreous or “tepetates” which by its mineralogical composition allowed to the lateral resistivity be associate with free components trace from the aquifer: Cd, Cu, Cr, Co, Ni, Pb or Zn and others. This method constitutes

Implementing Replacement Cost Accounting

Science.gov (United States)

1976-12-01

cost accounting Clickener, John Ross Monterey, California. Naval Postgraduate School http://hdl.handle.net/10945/17810 Downloaded from NPS Archive...Calhoun IMPLEMENTING REPLACEMENT COST ACCOUNTING John Ross CHckener NAVAL POSTGRADUATE SCHOOL Monterey, California THESIS IMPLEMENTING REPLACEMENT COST ...Implementing Replacement Cost Accounting 7. AUTHORS John Ross Clickener READ INSTRUCTIONS BEFORE COMPLETING FORM 3. RECIPIENT’S CATALOG NUMBER 9. TYRE OF

Influence of cable losses on the economic analysis of efficient and sustainable electrical equipment

International Nuclear Information System (INIS)

Lobão, J.A.; Devezas, T.; Catalão, J.P.S.

2014-01-01

Increasing energy needs are accompanied by environmental responsibilities, since nowadays electricity companies operate in a competitive and sustainable energy framework. In this context, any proposal for action on energy efficiency becomes important for consumers to minimize operational costs. In electrical installations, electricity consumption can be decreased by reducing losses in the cables, associated with the overall efficiency of the equipment, allowing a better use of the installed power. The losses must be analysed in conjunction with all loads that contribute to the currents in the sections of an electrical installation. When replacing equipment in output distribution boxes with more efficient ones, the current in those sections is reduced in association with the decrease in power losses. This decrease, often forgotten, is taken into account in this work for the economic analysis of efficiency and sustainable electrical equipment. This paper presents a new software application that compares and chooses the best investment in the acquisition of electrical equipment. Simulation results obtained with the new software application are provided and are then validated with experimental results from a real electrical installation. - Highlights: • Any proposal for action on energy efficiency is important for consumers. • Electricity consumption can be decreased by reducing losses in the cables. • A new software application that compares and chooses the best investment is provided. • The economic analysis of efficiency and sustainable electrical equipment is carried out. • Simulation results are validated with experimental results from a real electrical installation

The status of the LANSCE refurbishment project (LANSCE-R)

International Nuclear Information System (INIS)

Erickson, John Leonard; Jones, Kevin; Streve, Michael

2008-01-01

The Los Alamos Neutron Science Center (LANSCE) accelerator is an 800-MeV proton linac that drives user facilities for isotope production, proton radiography, ultra-cold neutrons, weapons neutron research and various sciences using neutron scattering. The LANSCE Refurbishment Project (LANSCE-R) is an ambitious project to refurbish key elements of the LANSCE accelerator that are becoming obsolete or nearing end-of-life. The conceptual design phase for the project is funded and underway. The 5 year, $170M (US) project will enable future decades of reliable, high-performance operation. It will replace a substantial fraction of the radio-frequency power systems (gridded tubes and klystrons) with modern systems, completely refurbish the original accelerator control and timing systems, replace obsolete diagnostic devices, and modernize other ancillary systems. An overview of the LANSCE-R project will be presented. The functional and operating requirements will be discussed, the proposed technical solutions presented, and the plan for successful project execution while meeting annual customer expectations for beam delivery will be reviewed.

The core pipeline equipment localization process and application prospects in China

Directory of Open Access Journals (Sweden)

Zejun Huang

2014-12-01

Full Text Available To improve the economic efficiency of gas pipelines, core equipment such as compressor sets and large-diameter valves must be localized. For this purpose, in alliance with other related enterprises, PetroChina Company Limited established an equipment localization R&D system and a new product testing system and successfully developed a 20 MW class motor-driven compressor set, a 30 MW-class gas turbine-driven compressor unit, and a high-pressure and large-diameter welded ball valve. First, the motor-driven compressor R&D focuses on three main units. The developed frequency-control device structure is a cascaded multilevel with a capacity of 25 MVA. The developed anti-explosion dynamo with a motor speed of 4800 rpm can produce a power of 22 MW. The developed compressor is PCL800 with features of a high efficiency and a wide flow-operating point-adjustment range. Second, there are two steps of the R&D of a GT-driven compressor unit (product A + product B: auxiliary supporting systems and control systems are developed for the imported GT25000 gas turbine, together with China-made compressors, to constitute product A; simultaneously, the R&D of product B of a gas turbine is carried out, which would replace the imported one. Third, aiming to solve the problems of sealing and welding, we developed the high-pressure and large-diameter all-welded ball valves in full replace of the same kind of imported products with three different sizes: NPS40 Class 600, NPS48 Class 600, and NPS48 Class 900.

Assessment of Eco-friendly Gases for Electrical Insulation to Replace the Most Potent Industrial Greenhouse Gas SF6.

Science.gov (United States)

Rabie, Mohamed; Franck, Christian M

2018-01-16

Gases for electrical insulation are essential for the operation of electric power equipment. This Review gives a brief history of gaseous insulation that involved the emergence of the most potent industrial greenhouse gas known today, namely sulfur hexafluoride. SF 6 paved the way to space-saving equipment for the transmission and distribution of electrical energy. Its ever-rising usage in the electrical grid also played a decisive role in the continuous increase of atmospheric SF 6 abundance over the last decades. This Review broadly covers the environmental concerns related to SF 6 emissions and assesses the latest generation of eco-friendly replacement gases. They offer great potential for reducing greenhouse gas emissions from electrical equipment but at the same time involve technical trade-offs. The rumors of one or the other being superior seem premature, in particular because of the lack of dielectric, environmental, and chemical information for these relatively novel compounds and their dissociation products during operation.

Pipe replacement in a water supply network: coordinated versus uncoordinated replacement and budget effects

NARCIS (Netherlands)

Dijk, van D.; Hendrix, E.M.T.

2016-01-01

Operators of underground water supply networks are challenged with pipe replacement
decisions, because pipes are subject to increased failure rates as they age and financial resources
are often limited.We study the optimal replacement time and optimal number of pipe replacements
such

RETRIEVAL EQUIPMENT DESCRIPTIONS

International Nuclear Information System (INIS)

J. Steinhoff

1997-01-01

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

Kindling: The Amazon e-Reader as an Educational Tool

Science.gov (United States)

Brezicki, Colin

2011-01-01

The revolutionary electronic reading device, Amazon's Kindle, is already obsolete. Such is the breakneck speed of technology that the machine touted to spell the death of printed books is already heading for the scrap heap, replaced by e-readers like the iPad that access the Internet, make phone calls, download movies, and connect users with all…

78 FR 66840 - Revocation of Certain Requirements Pertaining to Caps Intended for Use With Toy Guns and Toy Guns...

Science.gov (United States)

2013-11-07

... Certain Requirements Pertaining to Caps Intended for Use With Toy Guns and Toy Guns Not Intended for Use With Caps AGENCY: Consumer Product Safety Commission. ACTION: Final rule. SUMMARY: Section 106 of the... regulations pertaining to caps intended for use with toy guns refer to obsolete equipment, but the ASTM F963...

Fitness of equipment used for medical exposures to ionising radiation

International Nuclear Information System (INIS)

1998-01-01

The advice in this guidance note is aimed at employers in control of equipment used for medical exposures to ionising radiation and ancillary equipment. This includes NHS trusts, health authorities or boards, private hospitals, clinics, surgeries, medical X-ray facilities in industry, dentists and chiropractors. The guidance should also be useful to radiation protection advisers appointed by such employers. The guidance provides advice on the requirements of regulation 33 of the Ionising Radiations Regulations 1985 (IRR85). In particular, it covers: (a) the selection, installation, maintenance, calibration and replacement of equipment to ensure that it is capable of restricting, so far as reasonably practicable, the medical exposure of any person to the extent that this is compatible with the intended diagnostic or therapeutic purpose; (b) recommended procedures for the definitive calibration of radiotherapy treatment; and (c) the need to investigate incidents involving a malfunction or defect in any 'radiation equipment' which result in medical exposures much greater than intended and to notify the Health and Safety Executive (HSE). 'Medical exposure' is defined in IRR85 as exposure of a person to ionising radiation for the purpose of his or her medical or dental examination or treatment which is conducted under the direction of a suitably qualified person and includes any such examination or treatment conducted for the purposes of research. For convenience, people undergoing medical exposure will be referred to as 'patients' in this guidance. Nothing in this publication is intended to indicate whether or not patients should be informed of any incident resulting from malfunction or defect in equipment used for medical exposure and the possible consequences of that exposure. As stated above, this guidance concerns medical exposures much greater than intended and although exposures much lower than intended can also have serious consequences, the incident would not

Data communication equipment

International Nuclear Information System (INIS)

Kim, Hak Seon; Lee, Sang Mok

1998-02-01

The contents of this book are introduction of data communication on definition, purpose and history, information terminal about data communication system and data transmission system, data transmit equipment of summary, transmission cable, data port, concentrator and front-end processor, audio communication equipment like phones, radio communication equipment of summary on foundation of electromagnetic waves, AM transmitter, AM receiver, FM receiver and FM transmitter, a satellite and mobile communication equipment such as earth station, TT and C and Cellular phone, video telephone and new media apparatus.

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

Influence of Total Knee Arthroplasty on Gait Mechanics of the Replaced and Non-Replaced Limb During Stair Negotiation.

Science.gov (United States)

Standifird, Tyler W; Saxton, Arnold M; Coe, Dawn P; Cates, Harold E; Reinbolt, Jeffrey A; Zhang, Songning

2016-01-01

This study compared biomechanics during stair ascent in replaced and non-replaced limbs of total knee arthroplasty (TKA) patients with control limbs of healthy participants. Thirteen TKA patients and fifteen controls performed stair ascent. Replaced and non-replaced knees of TKA patients were less flexed at contact compared to controls. The loading response peak knee extension moment was greater in control and non-replaced knees compared with replaced. The push-off peak knee abduction moment was elevated in replaced limbs compared to controls. Loading and push-off peak hip abduction moments were greater in replaced limbs compared to controls. The push-off peak hip abduction moment was greater in non-replaced limbs compared to controls. Future rehabilitation protocols should consider the replaced knee and also the non-replaced knee and surrounding joints. Copyright © 2016 Elsevier Inc. All rights reserved.

Backbone upgrades and DEC equipment replacement

Science.gov (United States)

Vancamp, Warren

1991-01-01

The NASA Science Internet (NSI) dual protocol backbone is outlined. It includes DECnet link upgrades to match TCP/IP link performance. It also includes the integration of backbone resources and central management. The phase 1 transition process is outlined.

Hip Replacement: MedlinePlus Health Topic

Science.gov (United States)

... invasive hip replacement (Medical Encyclopedia) Also in Spanish Topic Image MedlinePlus Email Updates Get Hip Replacement updates ... replacement - precautions Minimally invasive hip replacement Related Health Topics Hip Injuries and Disorders National Institutes of Health ...

Aorto-right atrial fistula after ascending aortic replacement or aortic value replacement

International Nuclear Information System (INIS)

Zhi Aihua; Dai Ruping; Jiang Shiliang; Lu Bin

2012-01-01

Objective: To evaluate the CT features of aorto-right atrial fistula after aortic valve replacement (AVR) or ascending aortic replacement. Methods: Eighty-seven patients with aortic-right atrial fistula underwent CT after operation. The CT features were retrospectively analyzed. Fistula was measured according to maximum width of the shunt. Results: Aorto-right atrial fistula was detected in 87 patients after aortic valve replacement or ascending aortic replacement by CT scan. Among them, 25 patients were diagnosed as mild aorto-right atrial fistula, 47 patients as moderate, and 15 patients as severe. Thirty-seven patients underwent follow-up CT.Among them, 10 patients with mild to moderate aorto-right atrial fistula were considered to have complete regression, 8 patients with mild aorto-right atrial fistula considered to have incomplete regression, 14 patients with mild to moderate aorto-right atrial fistula considered to have stable condition, and 5 patients with moderate aorto-right atrial fistula considered to have progression at the 3-month follow-up. Conclusion: CT is a useful tool for defining aorto-right atrial fistula after AVR or ascending aortic replacement and for evaluating it in follow-up. (authors)

Obsolete treaties

International Nuclear Information System (INIS)

Rodionov, S.

1999-01-01

The proliferation of ballistic missile technologies (as opposed to nuclear ones) is not limited actually by any international treaty, there are no treaties of that kind. It is hardly imaginable that the international community could succeed in getting any agreements in the near future that would ban (or seriously limit) missile technology proliferation, similar to Non-proliferation Treaty or CTBT. An optimum option would permit the declared nuclear powers to have intercontinental ballistic missiles until the transition to a nuclear-weapon-free world, while any space activity would be under strict international control

Prevalence of patients receiving renal replacement therapy in El Salvador in 2014.

Science.gov (United States)

García-Trabanino, Ramón; Trujillo, Zulma; Colorado, Ana Verónica; Magaña Mercado, Salvador; Henríquez, Carlos Atilio

El Salvador has the highest renal failure mortality rate in the Americas. Five healthcare providers offer renal replacement therapy (RRT) in the country. The national RRT prevalence has never been reported. To determine the RRT prevalence in El Salvador and some basic characteristics. The association of nephrology coordinated a nationwide cross-sectional survey during the third quarter of 2014. 31 renal centres participated in the survey, covering 99.5% of patients. National RRT prevalence: 595 per million population (pmp), N=3807, average age 50.4 years, 67.5% male. By modality: peritoneal dialysis (PD) 289 pmp, haemodialysis (HD) 233 pmp, with functioning kidney transplantation 74 pmp (living donor only). Social security covers 25% of the population but treats 49.7% of RRT patients. Generally, higher prevalence was observed in municipalities with renal centres or located on the coast or lowlands. Ninety-five percent of HD patients receive fewer than 3 weekly sessions. Of PD patients, 59% do not belong to a continuous outpatient or automated programme, and 25% still use rigid catheter. Aetiology of chronic kidney disease: unavailable/undetermined 50%, hypertension 21.1%, diabetes 18.9%, glomerulonephritis 6.7%, obstructive causes 1.2%, tubulointerstitial 0.9%, polycystic 0.4% and other 0.7%. Despite the increase in RRT services, the prevalence is lower than the Latin American average (660 pmp). Three quarters of HD and PD patients are under-dialysed. Obsolete RRT techniques are still used. The presence of Mesoamerican nephropathy influences the demographic characteristics (many young patients, two-thirds male, high prevalence in lowlands and coastlands). Copyright © 2016 Sociedad Española de Nefrología. Published by Elsevier España, S.L.U. All rights reserved.

Design of EPON far-end equipment based on FTTH

Science.gov (United States)

Feng, Xiancheng; Yun, Xiang

2008-12-01

Now, most favors fiber access is mainly the EPON fiber access system. Inheriting from the low cost of Ethernet, usability and bandwidth of optical network, EPON technology is one of the best technologies in fiber access and is adopted by the carriers all over the world widely. According to the scheme analysis to FTTH fan-end equipment, hardware design of ONU is proposed in this paper. The FTTH far-end equipment software design deference modulation design concept, it divides the software designment into 5 function modules: the module of low-layer driver, the module of system management, the module of master/slave communication, and the module of main/Standby switch and the module of command line. The software flow of the host computer is also analyzed. Finally, test is made for Ethernet service performance of FTTH far-end equipment, E1 service performance and the optical path protection switching, and so on. The results of test indicates that all the items are accordance with technical request of far-end ONU equipment and possess good quality and fully reach the requirement of telecommunication level equipment. The far-end equipment of FTTH divides into several parts based on the function: the control module, the exchange module, the UNI interface module, the ONU module, the EPON interface module, the network management debugging module, the voice processing module, the circuit simulation module, the CATV module. In the downstream direction, under the protect condition, we design 2 optical modules. The system can set one group optical module working and another group optical module closure when it is initialized. When the optical fiber line is cut off, the LOS warning comes out. It will cause MUX to replace another group optical module, simultaneously will reset module 3701/3711 and will make it again test the distance, and will give the plug board MPC850 report through the GPIO port. During normal mode, the downstream optical signal is transformed into the

A Web portal for the Engineering and Equipment Data Management System at CERN

CERN Document Server

Tsyganov, A; Martel, P; Milenkovic, S; Suwalska, A; Delamare, Christophe; Widegren, David; Mallon Amerigo, S; Pettersson, Thomas Sven

2010-01-01

CERN, the European Laboratory for Particle Physics, located in Geneva – Switzerland, has recently started the Large Hadron Collider (LHC), a 27 km particle accelerator. The CERN Engineering and Equipment Data Management Service (EDMS) provides support for managing engineering and equipment information throughout the entire lifecycle of a project. Based on several both in-house developed and commercial data management systems, this service supports management and follow-up of different kinds of information throughout the lifecycle of the LHC project: design, manufacturing, installation, commissioning data, maintenance and more. The data collection phase, carried out by specialists, is now being replaced by a phase during which data will be consulted on an extensive basis by non-experts users. In order to address this change, a Web portal for the EDMS has been developed. It brings together in one space all the aspects covered by the EDMS: project and document management, asset tracking and safety follow-up. T...

Life extension of low and medium voltage equipment

International Nuclear Information System (INIS)

Bharteey, B.M.; Hart, T.J.

1990-01-01

Nuclear plant life extension is becoming a very important issue with the passing of each day. Within 3 to 10 years after the turn of the century, licenses of a number of nuclear power plants in the United States will expire. For the near future, new construction of nuclear power plants in the United States is expected to be inhibited, if the current economic and regulatory environment continues to persist. This situation, coupled with aging of utility equipment and the high cost of financing new construction is resulting in a growing emphasis on preserving and extending the capability of existing power plants. Until now, the utilities have placed more emphasis on high cost items, but experience shows that extending life of low cost of device/components in items like Motor Control Center Centers and switchgear pays big dividends. According to the current practice, devices of these items are replaced at the end of their assigned qualified life or attended to when there is a problem resulting in an unplanned outage. In this paper based on extensive experience in the field of motor control centers and medium switchgear, the authors proposed a cookbook methodology to determine the extent or absence of degradation and establish trends of the pertinent operational properties of devices of this type of equipment. The test results also provide satisfactory evidence of class 1E nuclear safety-related function

Minimally invasive aortic valve replacement

DEFF Research Database (Denmark)

Foghsgaard, Signe; Schmidt, Thomas Andersen; Kjaergard, Henrik K

2009-01-01

In this descriptive prospective study, we evaluate the outcomes of surgery in 98 patients who were scheduled to undergo minimally invasive aortic valve replacement. These patients were compared with a group of 50 patients who underwent scheduled aortic valve replacement through a full sternotomy...... operations were completed as mini-sternotomies, 4 died later of noncardiac causes. The aortic cross-clamp and perfusion times were significantly different across all groups (P replacement...... is an excellent operation in selected patients, but its true advantages over conventional aortic valve replacement (other than a smaller scar) await evaluation by means of randomized clinical trial. The "extended mini-aortic valve replacement" operation, on the other hand, is a risky procedure that should...

Impact of power uprate on environmental qualification of equipment in nuclear power plants

International Nuclear Information System (INIS)

Raheja, R.D.; Mohiuddin, A.; Alsammarae, A.

1996-01-01

Many nuclear power facilities are finding it economically beneficial to increase reactor output, from operating plants, by resorting to power uprates. A power uprate implies that a utility can increase the reactor output, or the megawatts generated, by increasing steam pressure without adding or changing any plant systems. This is perhaps one of the least expensive options for increasing the generating capacity of a power plant. However, a nuclear plant requires a comprehensive review of the plant systems, structures and components to assure their capability to withstand the resulting increased normal and accident plant conditions. A power uprate will typically result in a plant operating at higher than the originally designed environmental conditions. Safety related equipment in nuclear plants is presently qualified to the UFSAR Chapter 15 accident events and the resulting temperatures, pressures, radiation levels etc. These values will increase when the reactor is producing a higher MWe output. Components that are sensitive to the environment must be re-evaluated and assessed to determine their acceptability and operability under the revised environmental conditions. Most safety-related mechanical and electrical equipment will require an assessment from an environmental qualification standpoint. Utilities must perform this task in a systematic, auditable and cost effective manner to optimize their resources and minimize plant costs associated with modifications, replacements or equipment testing. This paper discusses various approaches and provides recommendations to achieve equipment qualification while satisfying the plant's objective of a power uprate

Life extension and replacement management for RAPS type steam generators

International Nuclear Information System (INIS)

Arya, R.C.; Rastogi, A.K.

1996-01-01

The steam generating equipment in first four units of Indian PHWRs Rajasthan Atomic Power Station (RAPS) 1-2 and Madras Atomic Power Station (MAPS) 1-2 are hairpin type and comprise of eight boiler assemblies. Each assembly consists of identical, single pass, inverted and vertical hairpin heat exchangers (10 for RAPS and 11 for MAPS) containing 195 monel-400 U tubes of 12.7 mm dia x 1.242 mm thick. The hot heavy water flows through these tubes and imparts heat to feed, light demineralized water entering the shell at the bottom of preheat leg. The heat is generated on the outer surface of the tubes. Details of studies carried out for life extension and replacement management for RAPS type steam generators are given. 1 fig., 5 tabs

FPGA Design Methodologies Applicable to Nuclear Power Plants

International Nuclear Information System (INIS)

Kwong, Yongil; Jeong, Choongheui

2013-01-01

In order to solve the above problem, NPPs in some countries such as the US, Canada and Japan have already applied FPGA-based equipment which has advantages as follows: It is easier to verify the performance because it needs only HDL code to configure logic circuits without other software, compared to microprocessor-based equipment, It is much cheaper than ASIC in a small quantity, Its logic circuits are re configurable, It has enough resources like logic blocks and memory blocks to implement I and C functions, Multiple functions can be implemented in a FPGA chip, It is stronger with respect to carboy security than microprocessor-based equipment because its configuration cannot be changed by external access, It is simple to replace it with new one when it is obsolete, Its power consumption is lower. However, FPGA-based equipment does not have only the merits. There are some issues on its application to NPPs. First of all, the experiences in applying it to NPPs are much less than to other industries, and international standards or guidelines are also very few. And there is the small number of FPGA platforms for I and C systems. Finally, the specific guidelines on FPGA design are required because the design has both hardware and software characteristics. In order to handle the above issues, KINS(Korea Institute of Nuclear Safety) built a test platform last year and have developed regulatory guidelines for FPGA-application in NPPs. I and C systems of NPPs have been increasingly using FPGA-based equipment as an alternative of microprocessor-based equipment which is not simple to be evaluated for safety due to its complexity. This paper explained the FPGA design flow and design guidelines. Those methodologies can be used as the guidelines on FPGA verification for safety of I and C systems

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

Partial knee replacement - slideshow

Science.gov (United States)

... page: //medlineplus.gov/ency/presentations/100225.htm Partial knee replacement - series—Normal anatomy To use the sharing ... A.M. Editorial team. Related MedlinePlus Health Topics Knee Replacement A.D.A.M., Inc. is accredited ...

24 CFR 891.405 - Replacement reserve.

Science.gov (United States)

2010-04-01

... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Replacement reserve. 891.405....405 Replacement reserve. (a) Establishment of reserve. The Owner shall establish and maintain a replacement reserve to aid in funding extraordinary maintenance and repair and replacement of capital items...

Acceptance test procedure for SY Tank Farm replacement exhauster unit

Energy Technology Data Exchange (ETDEWEB)

Becken, G.W.

1994-12-16

The proper functioning of a new 241-SY Tank Farm replacement exhauster will be acceptance tested, to establish operability and to provide an operational baseline for the equipment. During this test, a verification of all of the alarm and control circuits associated with the exhaust, which provide operating controls and/or signals to local and remote alarm/annunciator panels, shall be performed. Test signals for sensors that provide alarms, warnings, and/or interlocks will be applied to verify that alarm, warning, and interlock setpoints are correct. Alarm and warning lights, controls, and local and remote readouts for the exhauster will be verified to be adequate for proper operation of the exhauster. Testing per this procedure shall be conducted in two phases. The first phase of testing, to verify alarm, warning, and interlock setpoints primarily, will be performed in the MO-566 Fab Shop. The second phase of testing, to verify proper operation and acceptable interface with other tank farm systems, will be conducted after the exhauster and all associated support and monitoring equipment have been installed in the SY Tank Farm. The exhauster, which is mounted on a skid and which will eventually be located in the SY tank farm, receives input signals from a variety of sensors mounted on the skid and associated equipment. These sensors provide information such as: exhauster system inlet vacuum pressure; prefilter and HEPA filter differential pressures; exhaust stack sampler status; exhaust fan status; system status (running/shut down); and radiation monitoring systems status. The output of these sensors is transmitted to the exhauster annunciator panel where the signals are displayed and monitored for out-of-specification conditions.

24 CFR 880.602 - Replacement reserve.

Science.gov (United States)

2010-04-01

... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Replacement reserve. 880.602... Replacement reserve. (a) A replacement reserve must be established and maintained in an interest-bearing account to aid in funding extraordinary maintenance and repair and replacement of capital items. (1) Part...

24 CFR 891.855 - Replacement reserves.

Science.gov (United States)

2010-04-01

... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Replacement reserves. 891.855... § 891.855 Replacement reserves. (a) The mixed-finance owner shall establish and maintain a replacement... the funds will be used to pay for capital replacement costs for the Section 202 or 811 supportive...

Short communication: Bacterial counts in recycled manure solids bedding replaced daily or deep packed in freestalls.

Science.gov (United States)

Sorter, D E; Kester, H J; Hogan, J S

2014-05-01

An experiment was conducted to compare bacterial counts of mastitis pathogens in deep-packed manure solids bedding with those in manure solids bedding replaced daily from mattresses. Eighteen Holstein cows were housed in 1 pen with 18 stalls. One row of 9 stalls was equipped with mattresses topped with bedding. The back one-third of these stalls toward the alleyway was covered in 25 mm of recycled manure solids, which was removed daily for the next 6 d and replaced with bedding from the brisket board and lunge space areas of stalls. The second row of 9 stalls was bedded for 3 wk with 100 to 150 mm of deep-pack recycled manure bedding from which only fecal matter was removed daily. After 3 wk, bedding treatments were changed between rows in a switchback design. Mean total gram-negative bacterial counts did not differ between treatments throughout the experiment. Coliform and Klebsiella spp. bacterial counts were lower in daily replaced bedding compared with deep pack across the experiment and on each of d 0, 1, 2, and 6. Streptococcal counts were reduced in daily replacement stalls compared with deep-pack stalls on d 0 and greater in daily replacement stalls compared with deep-pack stalls on d 1, 2, and 6. Daily replacement of recycled manure bedding from the back one-third of the stalls appeared to be an effective approach to reducing exposure to coliforms, specifically Klebsiella, but not streptococci. However, bacterial counts in bedding from both treatments were elevated throughout the trial and resulted in considerable risk for exposure to teats and development of intramammary infections. Copyright © 2014 American Dairy Science Association. Published by Elsevier Inc. All rights reserved.

Future trends in metal forming—equipment, materials and processes in automotive applications

Science.gov (United States)

Hitz, D.; Duggirala, R.

1995-10-01

Global competition in the automotive market has made a significant impact in the materials, processes, tools, and equipment used to make components. Steels are being replaced by other materials, such as aluminum, composites, and plastics, that meet the demand for a higher performance per weight ratio. From a processing viewpoint, the customers demand production of parts to near-net shape with little or no machining. Competition in business depends on understanding the needs of the customer in the coming years in the area of metal forming. A workshop was conducted using a novel approach to address the above issue. This presentation describes the approach and the results of the study.

25 CFR 700.53 - Dwelling, replacement.

Science.gov (United States)

2010-04-01

... 25 Indians 2 2010-04-01 2010-04-01 false Dwelling, replacement. 700.53 Section 700.53 Indians THE... Policies and Instructions Definitions § 700.53 Dwelling, replacement. The term replacement dwelling means a dwelling selected by the head of a household as a replacement dwelling that meets the criteria of this...

Could wind replace nuclear?

International Nuclear Information System (INIS)

2017-01-01

This article aims at assessing the situation produced by a total replacement of nuclear energy by wind energy, while facing consumption demand at any moment, notably in December. The authors indicate the evolution of the French energy mix during December 2016, and the evolution of the rate between wind energy production and the sum of nuclear and wind energy production during the same month, and then give briefly some elements regarding necessary investments in wind energy to wholly replace nuclear energy. According to them, such a replacement would be ruinous

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

Design and production of a new surface mount charge-integrating amplifier for CDF

Energy Technology Data Exchange (ETDEWEB)

Nelson, C.; Drake, G.

1991-12-31

We present our experiences in designing and producing 26,000 new charge-integrating amplifiers for CDF, using surface-mount components. The new amplifiers were needed to instrument 920 new 24-channel CDF RABBIT boards, which are replacing an older design rendered obsolete by increases in the collision rate. Important design considerations were frequency response, physical size and cost. 5 refs.

Design and production of a new surface mount charge-integrating amplifier for CDF

International Nuclear Information System (INIS)

Nelson, C.; Drake, G.

1991-01-01

We present our experiences in designing and producing 26,000 new charge-integrating amplifiers for CDF, using surface-mount components. The new amplifiers were needed to instrument 920 new 24-channel CDF RABBIT boards, which are replacing an older design rendered obsolete by increases in the collision rate. Important design considerations were frequency response, physical size and cost. 5 refs

Operational Readiness Review: Savannah River Replacement Tritium Facility

International Nuclear Information System (INIS)

1993-02-01

The Operational Readiness Review (ORR) is one of several activities to be completed prior to introducing tritium into the Replacement Tritium Facility (RTF) at the Savannah River Site (SRS). The Secretary of Energy will rely in part on the results of this ORR in deciding whether the startup criteria for RTF have been met. The RTF is a new underground facility built to safely service the remaining nuclear weapons stockpile. At RTF, tritium will be unloaded from old components, purified and enriched, and loaded into new or reclaimed reservoirs. The RTF will replace an aging facility at SRS that has processed tritium for more than 35 years. RTF has completed construction and is undergoing facility startup testing. The final stages of this testing will require the introduction of limited amounts of tritium. The US Department of Energy (DOE) ORR was conducted January 19 to February 4, 1993, in accordance with an ORR review plan which was developed considering previous readiness reviews. The plan also considered the Defense Nuclear Facilities Safety Board (DNFSB) Recommendations 90-4 and 92-6, and the judgements of experienced senior experts. The review covered three major areas: (1) Plant and Equipment Readiness, (2) Personnel Readiness, and (3) Management Systems. The ORR Team was comprised of approximately 30 members consisting of a Team Leader, Senior Safety Experts, and Technical Experts. The ORR objectives and criteria were based on DOE Orders, industry standards, Institute of Nuclear Power Operations guidelines, recommendations of external oversight groups, and experience of the team members

Carbohydrates as Fat Replacers.

Science.gov (United States)

Peng, Xingyun; Yao, Yuan

2017-02-28

The overconsumption of dietary fat contributes to various chronic diseases, which encourages attempts to develop and consume low-fat foods. Simple fat reduction causes quality losses that impede the acceptance of foods. Fat replacers are utilized to minimize the quality deterioration after fat reduction or removal to achieve low-calorie, low-fat claims. In this review, the forms of fats and their functions in contributing to food textural and sensory qualities are discussed in various food systems. The connections between fat reduction and quality loss are described in order to clarify the rationales of fat replacement. Carbohydrate fat replacers usually have low calorie density and provide gelling, thickening, stabilizing, and other texture-modifying properties. In this review, carbohydrates, including starches, maltodextrins, polydextrose, gums, and fibers, are discussed with regard to their interactions with other components in foods as well as their performances as fat replacers in various systems.

IE Bulletin No. 79-01: Environmental qualification of Class IE equipment

International Nuclear Information System (INIS)

Anon.

1993-01-01

The intent of IE Circular 78-08 was to highlight to all licensees important lessons learned from environmental qualification deficiencies reported by individual licensees. In this regard, licensees were requested to examine installed safety-related electrical equipment and determine that proper documentation existed which provided assurance that this equipment would function under postulated accident conditions. The intent of this Bulletin is to raise the threshold of IE Circular 78-08 to the level of a Bulletin; i.e., action requiring a licensee response. Inspections conducted to date by the NRC of licensees' activities in response to IE Circular 78-08 have identified one component which licensees have found to be unqualified for service within the LOCA environment. Specifically, unqualified stem mounted limit switches (SMLS), other than those identified in previously issued IE Bulletin 78-04, were found to be installed on safety-related valves inside containment at both Duane Arnold and Quad Cities 1 and 2 Nuclear Generating Stations. According to the manufacturer, these switches are designed only for general purpose applications and are not considered suitable devices for service in the LOCA environment. Consequently, switches are being replaced at the above power plants with qualified components

Position controlled Knee Rehabilitation Orthotic Device for Patients after Total Knee Replacement Arthroplasty

Science.gov (United States)

Wannaphan, Patsiri; Chanthasopeephan, Teeranoot

2016-11-01

Knee rehabilitation after total knee replacement arthroplasty is essential for patients during their post-surgery recovery period. This study is about designing one degree of freedom knee rehabilitation equipment to assist patients for their post-surgery exercise. The equipment is designed to be used in sitting position with flexion/extension of knee in sagittal plane. The range of knee joint motion is starting from 0 to 90 degrees angle for knee rehabilitation motion. The feature includes adjustable link for different human proportions and the torque feedback control at knee joint during rehabilitation and the control of flexion/extension speed. The motion of the rehabilitation equipment was set to move at low speed (18 degrees/sec) for knee rehabilitation. The rehabilitation link without additional load took one second to move from vertical hanging up to 90° while the corresponding torque increased from 0 Nm to 2 Nm at 90°. When extra load is added, the link took 1.5 seconds to move to 90° The torque is then increased from 0 Nm to 4 Nm. After a period of time, the speed of the motion can be varied. User can adjust the motion to 40 degrees/sec during recovery activity of the knee and users can increase the level of exercise or motion up to 60 degrees/sec to strengthen the muscles during throughout their rehabilitation program depends on each patient. Torque control is included to prevent injury. Patients can use the equipment for home exercise to help reduce the number of hospital visit while the patients can receive an appropriate therapy for their knee recovery program.

Performance and equipments upgrade of compact nuclear simulator

Energy Technology Data Exchange (ETDEWEB)

Park, Jae Chang; Kwon, Kee Choon; Sim, Bong Shick; Kim, Jung Taek; Lee, Dong Young; Kim, Chang Hwoi; Park, Won Man; Song, Soon Ja; Yoo, Soon Duk; Yang, Kwang Nam

1997-12-01

The compact nuclear simulator (CNS) is installed in the Korea Atomic Energy Research Institute (KAERI) Nuclear Training Center in 1988. The CNS has been used for training of non-operator personnel such as NSSS design engineers, maintenance personnel, inspectors of regulatory body, etc. and for test facility of fuzzy control algorithm. The CNS was manufactured by KAERI and Studsvik (now Eurosim) joint project. The CNS mathematical modeling modeled a three loop Westinghouse Pressurizer Water Reactor (PWR), 993 MWe, mostly referred to as the Kori Unit 3 and 4 in Korea. But the main computer (Micro VAX II), a interface card between main computer and operator panel, and a graphic interface system are faced with frequent troubles by obsolescence and lack of spare parts. According to the above reasons, the CNS hardware should be replaced by state of the art equipment. It is planned to replace the main computer with HP workstation, a dedicated interface card with a PLC-based interface system, and a graphic interface system with an X-terminal based full graphics system. The software for a instructor console also will be modified text-based to Motif-based user interface. The Motif-based user interface provides more efficient and easy operation in a instructor console also will be modified text-based to Motif-based user interface. The Motif-based user interface provides more efficient and easy operation in a instructor console. (author). 124 refs., 2 tabs., 24 figs

High energy arcing fault fires in switchgear equipment : a literature review.

Energy Technology Data Exchange (ETDEWEB)

Nowlen, Steven Patrick; Brown, Jason W.; Wyant, Francis John

2008-10-01

In power generating plants, switchgear provide a means to isolate and de-energize specific electrical components and buses in order to clear downstream faults, perform routine maintenance, and replace necessary electrical equipment. These protective devices may be categorized by the insulating medium, such as air or oil, and are typically specified by voltage classes, i.e. low, medium, and high voltage. Given their high energy content, catastrophic failure of switchgear by means of a high energy arcing fault (HEAF) may occur. An incident such as this may lead to an explosion and fire within the switchgear, directly impact adjacent components, and possibly render dependent electrical equipment inoperable. Historically, HEAF events have been poorly documented and discussed in little detail. Recent incidents involving switchgear components at nuclear power plants, however, were scrupulously investigated. The phenomena itself is only understood on a very elementary level from preliminary experiments and theories; though many have argued that these early experiments were inaccurate due to primitive instrumentation or poorly justified methodologies and thus require re-evaluation. Within the past two decades, however, there has been a resurgence of research that analyzes previous work and modern technology. Developing a greater understanding of the HEAF phenomena, in particular the affects on switchgear equipment and other associated switching components, would allow power generating industries to minimize and possibly prevent future occurrences, thereby reducing costs associated with repair and downtime. This report presents the findings of a literature review focused on arc fault studies for electrical switching equipment. The specific objective of this review was to assess the availability of the types of information needed to support development of improved treatment methods in fire Probabilistic Risk Assessment (PRA) for nuclear power plant applications.

Radiation Source Replacement Workshop

Energy Technology Data Exchange (ETDEWEB)

Griffin, Jeffrey W.; Moran, Traci L.; Bond, Leonard J.

2010-12-01

This report summarizes a Radiation Source Replacement Workshop in Houston Texas on October 27-28, 2010, which provided a forum for industry and researchers to exchange information and to discuss the issues relating to replacement of AmBe, and potentially other isotope sources used in well logging.

Process and equipment for locating defective fuel rods of a reactor fuel element

International Nuclear Information System (INIS)

Jester, A.; Honig, H.

1977-01-01

By this equipment, well-known processes for determining defective fuel rods of a reactor fuel element are improved in such a fashion that defective fuel rods can be located individually, so that it is possible to replace them. The equipment consists of a cylindrical test vessel open above, which accommodates the element to be tested, so that an annular space is left between the latter's external circumference and the wall of the vessel, and so that the fuel rods project above the vessel. A bell in the shape of a frustrum of a cone is inverted over the test vessel, which has an infra-red measuring equipment at a certain distance above the tops of the fuel rods. The fuel element to be tested together with the test vessel and hood are immersed in a basin full of water, which displaces water by means of gas from the hood. The post-shutdown heat increases the temperature in the water space of the test vessel, which is stabilised at 100 0 C. In each defective fuel rod the water which has penetrated the defective fuel rod previously, or does so now, starts to boil. The steam rising in the fuel rod raises the temperature of the defective fuel rod compared to all the sound ones. The subsequent measurement easily determines this. Where one can expect interference with the measurement by appreciable amounts of gamma rays, the measuring equipment is removed from the path of radiation by mirror deflection in a suitably shaped measuring hood. (FW) [de

Remote handling equipment

International Nuclear Information System (INIS)

Clement, G.

1984-01-01

After a definition of intervention, problems encountered for working in an adverse environment are briefly analyzed for development of various remote handling equipments. Some examples of existing equipments are given [fr

Can photovoltaic replace nuclear?

International Nuclear Information System (INIS)

2017-01-01

As the French law on energy transition for a green growth predicts that one third of nuclear energy production is to be replaced by renewable energies (wind and solar) by 2025, and while the ADEME proposes a 100 per cent renewable scenario for 2050, this paper proposes a brief analysis of the replacement of nuclear energy by solar photovoltaic energy. It presents and discusses some characteristics of photovoltaic production: production level during a typical day for each month (a noticeable lower production in December), evolution of monthly production during a year, evolution of the rate between nuclear and photovoltaic production. A cost assessment is then proposed for energy storage and for energy production, and a minimum cost of replacement of nuclear by photovoltaic is assessed. The seasonal effect is outlined, as well as the latitude effect. Finally, the authors outline the huge cost of such a replacement, and consider that public support to new photovoltaic installations without an at least daily storage mean should be cancelled

Latest news from the YETS: On the home straight, handover to operations in sight

CERN Multimedia

Antonella Del Rosso

2016-01-01

With the PS Booster already in its hardware commissioning phase and the PS being handed over to the operations teams this week, the injector chain is almost ready for the restart of the LHC run, planned for the end of March.   After an intense maintenance campaign over the last few weeks, the PS is now being cleaned and prepared for commissioning. At the SPS, the last access for YETS activities is planned for Friday, 19 February. More than 560 interventions have taken place over the past eight weeks. Since the beginning of the technical stop, 14 magnets have been changed and three more will be replaced before commissioning starts. The campaign for identifying obsolete cables is progressing well and will be completed on schedule. The LHC operators are eager to restart the physics run around the end of March. For the time being, all maintenance operations are progressing according to schedule. In particular, all the repairs involving the cryogenic equipment have been completed but inspections are stil...

Evolution of the ReadOut System of the ATLAS experiment

CERN Document Server

Borga, A; The ATLAS collaboration; Green, B; Kugel, A; Joos, M; Panduro Vazquez, W; Schumacher, J; Teixeira-Dias, P; Tremblet, L; Vandelli, W; Vermeulen, J; Werner, P; Wickens, F

2014-01-01

The ReadOut System (ROS) is a central and essential part of the ATLAS DAQ system. It receives and buffers data of events accepted by the first-level trigger from all subdetectors and first-level trigger subsystems. Event data are subsequently forwarded to the High-Level Trigger system and Event Builder via a 1 GbE-based network. The ATLAS ROS is completely renewed in view of the demanding conditions expected during LHC Run 2 and Run 3, to replace obsolete technologies and space constraints require it to be compact. The new ROS will consist of roughly 100 Linux-based 2U high rack mounted server PCs, each equipped with 2 PCIe I/O cards and two four 10 GbE interfaces. The FPGA-based PCIe I/O cards, developed by the ALICE collaboration, will be configured with ATLAS-specific firmware, the so-called RobinNP firmware. They will provide the connectivity to about 2000 optical point-to-point links conveying the ATLAS event data. This dense configuration provides an excellent test bench for studying I/O efficiency and ...

Update on the TRIUMF Central Control System

International Nuclear Information System (INIS)

Mouat, M.M.; Diel, D.A.; Grant, P.A.; Klassen, E.; Lee, K.S.; Ludgate, G.A.; Richards, J.E.; Yogendran, P.J.; Kadantsev, S.G.

1994-01-01

The continuing evolution of the TRIUMF Central Control System is currently subject to three major influences. Most imperative is the need to replace the obsolete Nova computers that still handle much of the routine cyclotron operation. Smooth integration of a number of isolated control systems into the CCS is another focus. The third major force arises from the requirements of developing new projects in a system that has reached serious expansion constraints. The plan for phasing out the Novas, integrating the orphaned systems and allowing expansion of the CCS in a smooth fashion is discussed. This is a conservative approach, relying on the strengths of the present hardware configuration, the substantial financial investment in existing equipment, and the expertise of available personnel, while meeting the present and future requirements. Details of the modified and expanded hardware configuration are described. This review also briefly mentions new support for device access, X-window displays, database usage, and plans for one of the upcoming projects, namely an eye cancer proton therapy treatment facility. ((orig.))

Effects of replacing lactose from milk replacer by glucose, fructose, or glycerol on energy partitioning in veal calves

NARCIS (Netherlands)

Gilbert, M. S.; Pantophlet, A. J.; van den Borne, J. J. G. C.; Hendriks, W. H.; Schols, H. A.; Gerrits, W. J. J.

Calf milk replacers contain 40 to 50% lactose. Fluctuating dairy prices are a major economic incentive to replace lactose from milk replacers by alternative energy sources. Our objective was, therefore, to determine the effects of replacement of lactose with glucose, fructose, or glycerol on energy

Radiation control in the core shroud replacement project of Fukushima-Daiichi NPS Unit no.2

International Nuclear Information System (INIS)

Kokubun, Yasunori; Haraguchi, Kazuyuki; Yoshizawa, Yuji; Yamada, Yasuo

2000-01-01

In Fukushima-Daiichi NPS Unit no.2, the core shroud replacement was made following that of Unit no.3. This project involves replacement of wide-ranging equipment, with the project extending over a long period of time. This was expected to increase the dose equivalent of workers. Accordingly, various measures to lower the dose equivalent were planned and implemented. We outline radiation controls implemented during the project period. The shroud replacement project was a preventive maintenance project which consisted of replacing the core shroud and other internals with those less susceptible to stress corrosion cracking. Problems related to radiation control during the replacement project of Unit no.3 the year before last were summarized. We studied, planned, and implemented measures to be reflected in the project for Unit no.2. This was done to lower the dose equivalent as much as possible while paying due attention to safety and economy. For radiation control during the project for Unit no.2, experiments with Unit no.3 were fully exploited and any effective measures taken at that time were adopted in this project. Problems pointed out after that project with Unit no.3 resulted in new or improved measures being taken with Unit no.2. Measures taken over from the project with Unit no.3; a. Daily analysis of difference between expected and actual dose equivalents b. Dose reduction measures, chemical decontamination, temporary shield, flushing, etc.; New or improved measures; a. Dose reduction measures: Mechanical removal of radiation sources, strengthening of shield, etc.; b. Automatic remote control system; c. Use of new protective devices. With measures implemented as described above, the dose equivalent during shroud replacement of Unit no.2 was reduced by about 30% when compared with that (11.5 persons · Sv) in the case of Unit no.3. Implemented radiation controls will be checked and reviewed in future for reflection in projects with other units. (author)

Development of FPGA-Based Control Board

Energy Technology Data Exchange (ETDEWEB)

Lee, Yoon Hee; Jeong, See Chae; Choi, Woong Seock; Lee, Chang Jae; Jeong, Jin Kwon; Ha, Jae Hong [Korea Power Engineering Company Inc., Daejeon (Korea, Republic of)

2009-10-15

It is well known that existing nuclear power plant (NPP) control systems contain many components which are becoming obsolete at an increasing rate. Various studies have been conducted to address control system hardware obsolescence. Obsolete analog and digital control systems in non-nuclear power plants are commonly replaced with modern digital control systems, programmable logic controllers (PLC) and distributed control systems (DCS). Field Programmable Gate Arrays (FPGAs) are highlighted as an alternative means for obsolete control systems. FPGAs are advanced digital integrated circuits (ICs) that contain configurable (programmable) blocks of logic along with configurable interconnects between these blocks. Designers can configure (program) such devices to perform a tremendous variety of tasks. FPGAs have been evolved from the technology of Programmable Logic Device (PLD). Nowadays they can contain millions of logic gates by nanotechnology and so be used to implement extremely large and complex functions that previously could be realized only using Application-Specific Integrated Circuits (ASICs). This paper is to present the development of a FPGAbased control board performing user-defined control functions. An Actel ProASIC{sup plus} FPGA platform is implemented as the comparator of Plant Protection System (PPS). Functional simulation is implemented for the comparator.

Used energy-related laboratory equipment grant program for institutions of higher learning. Eligible equipment catalog

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

This is a listing of energy related equipment available through the Energy-Related Laboratory Equipment Grant Program which grants used equipment to institutions of higher education for energy-related research. Information included is an overview of the program, how to apply for a grant of equipment, eligibility requirements, types of equipment available, and the costs for the institution.

Delirium After Transcatheter Aortic Valve Replacement.

Science.gov (United States)

Giuseffi, Jennifer L; Borges, Nyal E; Boehm, Leanne M; Wang, Li; McPherson, John A; Fredi, Joseph L; Ahmad, Rashid M; Ely, E Wesley; Pandharipande, Pratik P

2017-07-01

Postoperative delirium is associated with increased mortality. Patients undergoing transcatheter aortic valve replacement are at risk for delirium because of comorbid conditions. To compare the incidence, odds, and mortality implications of delirium between patients undergoing transcatheter replacement and patients undergoing surgical replacement. The Richmond Agitation-Sedation Scale and the Confusion Assessment Method for the Intensive Care Unit were used to assess arousal level and delirium prospectively in all patients with severe aortic stenosis who had transcatheter or surgical aortic valve replacement at an academic medical center. Multivariable logistic regression was used to determine the relationship between procedure type and occurrence of delirium. Cox regression was used to assess the association between postoperative delirium and 6-month mortality. A total of 105 patients had transcatheter replacement and 121 had surgical replacement. Patients in the transcatheter group were older (median age, 81 vs 68 years; P replacement. Delirium is less likely to develop in the transcatheter group but is associated with higher mortality in both groups. ©2017 American Association of Critical-Care Nurses.

BP volume reduction equipment

International Nuclear Information System (INIS)

Kitamura, Yoshinori; Muroo, Yoji; Hamanaka, Isao

2003-01-01

A new type of burnable poison (BP) volume reduction system is currently being developed. Many BP rods, a subcomponent of spent fuel assemblies are discharged from nuclear power reactors. This new system reduces the overall volume of BP rods. The main system consists of BP rod cutting equipment, equipment for the recovery of BP cut pieces, and special transport equipment for the cut rods. The equipment is all operated by hydraulic press cylinders in water to reduce operator exposure to radioactivity. (author)

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.

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

Feeder replacement tooling and processes

International Nuclear Information System (INIS)

Mallozzi, R.; Goslin, R.; Pink, D.; Askari, A.

2008-01-01

Primary heat transport system feeder integrity has become a concern at some CANDU nuclear plants as a result of thinning caused by flow accelerated corrosion (FAC). Feeder inspections are indicating that life-limiting wall thinning can occur in the region between the Grayloc hub weld and second elbow of some outlet feeders. In some cases it has become necessary to replace thinned sections of affected feeders to restore feeder integrity to planned end of life. Atomic Energy of Canada Limited (AECL) and Babcock and Wilcox Canada Ltd. (B and W) have developed a new capability for replacement of single feeders at any location on the reactor face without impacting or interrupting operation of neighbouring feeders. This new capability consists of deploying trained crews with specialized tools and procedures for feeder replacements during planned outages. As may be expected, performing single feeder replacement in the congested working environment of an operational CANDU reactor face involves overcoming many challenges with respect to access to feeders, available clearances for tooling, and tooling operation and performance. This paper describes some of the challenges encountered during single feeder replacements and actions being taken by AECL and B and W to promote continuous improvement of feeder replacement tooling and processes and ensure well-executed outages. (author)