Assessment of the performance of containment and surveillance equipment part 2: trial application

International Nuclear Information System (INIS)

Rezniczek, A.; Richter, B.; Jussofie, A.

2009-01-01

The adopted methodological approach for assessing the performance of Containment and Surveillance (C/S) equipment resulted from an account of work performed for and in cooperation with the ESARDA Working Group on C/S. It was applied on a trial basis to a dry storage facility for spent nuclear fuel and consisted of the following steps: (1) Acquisition and analysis of design information and operational characteristics of the facility under consideration, (2) assumptions on diversion and misuse scenarios, (3) assumptions on safeguards approach and definition of safeguards requirements, (4) compilation and characterisation of candidate C/S equipment, (5) performance assessment of C/S equipment. The candidate equipment taken into account was routinely used by the IAEA: DCM14-type camera, Type E capand- wire seal, COBRA fibre optic seal, and VACOSS electronic seal. Four applications were considered: camera mounted in the reception area, seal on secondary lid of transport and storage cask, seal on protective lid, and seal on group of casks. For these applications, requirements were defined and requirement levels were attributed. The assignment of performance levels was carried out by using the technical specifications and design basis tolerances provided by the equipment manufacturers. The results were entered into four performance assessment tables. Although the assessment methodology was not yet fully developed, its trial application yielded promising results with regard to the selection of appropriate C/S equipment.

Method for removing hydrogen sulphide from oil-containing water and equipment therefore; Fremgangsmaate for aa fjerne hydrogensulfid fra oljeholdig vann

Energy Technology Data Exchange (ETDEWEB)

Hoeyvik, H; Hovland, J; Eskilt, J P

1995-02-27

The invention relates to an method for removing hydrogen sulphide (H{sub 2}S) from oil-containing water and equipment therefore. Oil-containing water and nitrate is conducted through a bioreactor to remove H{sub 2}S. Nitrate is added to the oil-containing water in a dose ratio (sulphide:nitrate) of 1:10 to 1:40. The retention time in the reactor tank is for 10-60 minutes. After this treatment, purified water, where >90% of the H{sub 2}S-amount is removed, is let out of the tank. The equipment for performing the above mentioned method, is based on a bioreactor having large density of denitrifying bacteria. The reactor tank, is filled with carrying material providing large contact area. Even distribution of oil-containing water and nitrate over the carrying material which already may be covered by septic mud, forms an active sulphide oxidizing biofilm having large surface. This biofilm makes an extremely effective equipment for removing sulphide from oil-containing water. 3 figs.

Report on further development of the Winfrith Modular Containment System and associated equipment

International Nuclear Information System (INIS)

Sanders, M.J.; Pengelly, M.G.A.

1988-03-01

As a result of operational experience gained with the Winfrith Modular Containment, the need for a lifting aid to facilitate the decommissioning of tall plant, a 2-stage mobile ventilation system and an improved shower entry tunnel was identified. Improved plant and equipment has been designed, constructed and tested and the results are presented here. (author)

Combining simulation and multi-objective optimisation for equipment quantity optimisation in container terminals

OpenAIRE

Lin, Zhougeng

2013-01-01

This thesis proposes a combination framework to integrate simulation and multi-objective optimisation (MOO) for container terminal equipment optimisation. It addresses how the strengths of simulation and multi-objective optimisation can be integrated to find high quality solutions for multiple objectives with low computational cost. Three structures for the combination framework are proposed respectively: pre-MOO structure, integrated MOO structure and post-MOO structure. The applications of ...

Report on further development of the Winfrith Modular Containment System and associated equipment

International Nuclear Information System (INIS)

Sanders, M.J.; Pengelly, M.G.A.

1987-12-01

The Winfrith modular containment system was developed to enable redundant plutonium processing plant to be safely decommissioned. As a result of operational experience the need for a lifting aid to facilitate the decommissioning of tall plant, a 2-stage mobile ventilation system and an improved shower entry tunnel was identified. Improved plant and equipment has been designed, constructed and tested and the results are presented here. (author)

9 CFR 82.10 - Interstate movement of vehicles, cages, coops, containers, troughs, and other equipment from a...

Science.gov (United States)

2010-01-01

... after being moved interstate. (c) Before moving interstate any vehicles, cages, coops, containers... other containers or equipment used by or to move pet birds moved interstate in accordance with § 82.5(a... generated by or litter used by the birds or poultry, may be moved interstate from a quarantined area only in...

Evaluation of retrieval activities and equipment for removal of containers from the transuranic storage area retrieval enclosure

International Nuclear Information System (INIS)

Bannister, R.; Rhoden, G.; Davies, G.B.

1995-09-01

Since 1970, the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory has accepted over 55,000 cubic meters of Transuranic contaminated hazardous waste for interim storage. The waste has been neatly stored in ''cell'' configurations on adjoining, above ground asphalt pads at the Transuranic Storage Area (TSA). A number of reports have been supplied for review and comment describing the methodology and equipment proposed for retrieval of drums and boxes from a storage facility at the INEL site. The contract for this review requires two main issues to be addressed. First, the adequacy of equipment and methodology for the retrieval of containers which have been breached, lost structural integrity, or are otherwise damaged, Second, to review the strategies and equipment for retrieval of intact waste containers. These issues are presented in the following report along with additional detail in the methodology to complete the description of the operations required for retrieval under most operational scenarios. The documentation reviewed is considered to be at an interim stage and is therefore expected to be subject to the development of the methodology from the existing level of detail with input from the facility operators. This review aims to anticipate some of this development by providing suggested detailed methods of retrieval and equipment for both normal and abnormal operations

Procedure for qualification of electric equipment installed in containments for pressurized water reactors subject to accident conditions

International Nuclear Information System (INIS)

1991-11-01

This generic norm is usable for electrical equipment installed in containment building of PWR subject to accidental conditions. She defines the qualification methods and the general rules usable for the test specifications of qualification for these materials

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

Science.gov (United States)

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

2016-02-01

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

Combined cogeneration equipment containing gas turbine using low sulphur heavy stock as fuel

Energy Technology Data Exchange (ETDEWEB)

Taguchi, Goro; Ishiki, Katsuhiko

1988-03-10

This paper describes the combined cogeneration in Chemical and Plastics Co. Madras (India) which uses low sulphur heavy stock (LSHS) as a fuel. By the combined cogeneration of gas turbine and boiler steam turbine power generation, the exhaust from the steam turbine is supplied to the factory as a process steam. This equipment has a capacity of 4835 kW in overall generation power and 23.5 tons/hrs. in steam evaporation. The gas turbine system is equipped with an axial-flow, 11 step compressor, an axial flow, 4 step turbine, and a single-can back flow combustor fixed to the intermediate casing. The temperature of the exhaust from the gas turbine is 542/sup 0/C. Low quality LSHS when burned exerts no influence on the service life of the turbine blades. The boiler is a horizontal bent pipe, forced circulation type, and the steam turbine is a back pressure control type. The fuel is treated with a horizontal, two drum, electrostatic separator to which a demulsifier is supplied, to be separated into oil and water. As to the vanadium salts contained in the fuels, a chemical liquid containing MgO as a major ingredient is added to the fuel prior to the combustion. Thereby, the melting temperature of the vanadium oxide is enhanced, which serves for prevention of the melting and adhesion of the vanadium oxide to the gas turbine. LSHS is a residual oil produced by the ordinary pressure distillation of India-produced crude oil, has a sulphur content of 1.75%, and is solid at room temperature. Attention should be paid to clogging of the pipings. The overall efficiency is 80%. The combined cogeneration can be coordinated with load variations of 10 - 20%. (12 figs, 1 tab)

Visual communication and terminal equipment

International Nuclear Information System (INIS)

Kang, Cheol Hui

1988-06-01

This book is divided two parts about visual communication and terminal equipment. The first part introduces visual communication, which deals with foundation of visual communication, technique of visual communication, equipment of visual communication, a facsimile and pictorial image system. The second part contains terminal equipment such as telephone, terminal equipment for data transmission on constitution and constituent of terminal equipment for data transmission, input device and output device, terminal device and up-to-date terminal device.

Visual communication and terminal equipment

Energy Technology Data Exchange (ETDEWEB)

Kang, Cheol Hui

1988-06-15

This book is divided two parts about visual communication and terminal equipment. The first part introduces visual communication, which deals with foundation of visual communication, technique of visual communication, equipment of visual communication, a facsimile and pictorial image system. The second part contains terminal equipment such as telephone, terminal equipment for data transmission on constitution and constituent of terminal equipment for data transmission, input device and output device, terminal device and up-to-date terminal device.

Weight/balance portable test equipment

International Nuclear Information System (INIS)

Whitlock, R.W.

1994-01-01

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

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

Standard operational radiation protection instructions for process instrumentation and control engineering applying radiometric equipment containing sealed sources

International Nuclear Information System (INIS)

1989-01-01

According to article 16(3) of the Ordinance on the Implementation of Atomic Safety and Radiation Protection of 11 October 1984, operational radiation protection instructions have to be worked out for each type of nuclear energy application. Based on the valid legal provisions of the GDR and on experience and knowledge gained in practice, the most important operational instructions and procedures for the operation of radiometric equipment containing sealed sources were compiled. The example should enable the management to make the instructions directly applicable and, if necessary, to modify or supplement them

Storage options for Long Length Contaminated Equipment (LLCE) items

International Nuclear Information System (INIS)

Hodgson, R.D.

1994-11-01

A review of the Washington state requirements for the storage of long equipment items removed from tanks indicate that if the contaminated materials on the long equipment items are analyzed and determined to be DW, and not EHW, the containers can be stored on an uncovered, RCRA approved, storage pad. Long equipment items contaminated with reportable levels of EHW, or suspected of being contaminated with EHW, must be protected from the elements by means of a building or other protective covering that otherwise allows adequate inspection of the containers. Storage of the long equipment item containers on an uncovered storage pad is recommended and will reduce construction costs for new storage by an estimated 60 percent when compared to construction costs for enclosed storage

Waste Electrical and Electronic Equipment

DEFF Research Database (Denmark)

Bigum, Marianne Kristine Kjærgaard; Christensen, Thomas Højlund

2011-01-01

Waste electrical and electronic equipment (WEEE) is one of the fastest growing special waste types with an estimated growth of 3–5% per year (Cui and Forssberg, 2003). WEEE is a very heterogeneous waste type that contains many compounds that are considered to be harmful to both humans and the env......Waste electrical and electronic equipment (WEEE) is one of the fastest growing special waste types with an estimated growth of 3–5% per year (Cui and Forssberg, 2003). WEEE is a very heterogeneous waste type that contains many compounds that are considered to be harmful to both humans...

Equipment Qualification Data Base user manual

International Nuclear Information System (INIS)

Decker, Q.R.; Fackrell, L.J.; Fitch, L.R.; Meeky, O.B.

1985-09-01

This manual details the Equipment Qualification Data Base (EQDB), its usage, and contents. The EQDB consists of two files; the Plant Qualification File (PQF) and the Equipment Qualification File (EQF). The PQF contains plant specific environmental data and the EQF contains summaries of various test results. Two data management systems are used to manipulate the data and are discussed in this manual. SAS Institute System 2000 (S2K) is the management system for the PQF and Query Update (QU) is the operating system for the EQF. Each management system contains report writers. These writers and how to use them are discussed in detail in this manual

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

International Nuclear Information System (INIS)

Smet, D.B.

1996-01-01

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

Qualification of Electrical Equipment in Nuclear Power Plants - Management of ageing

International Nuclear Information System (INIS)

Spaang, Kjell; Staahl, Gunnar

2013-02-01

The purpose of this report is to describe programs and tools for assessment of accomplished and documented qualification with respect to ageing of electrical equipment and for development of complimentary ageing management programs. In addition to description of complete programs for management of ageing, tools for validation of the status with regard to ageing of installed ('old') equipment and, where needed, for complementation of their qualification are also included. The report is restricted to safety related equipment containing ageing sensitive parts, mainly organic materials. To this category belong cables and cable joints and a number of equipment containing oils, seals (o-rings), etc. For equipment located in the containment, the possibilities of continuous supervision are limited. The accessibility for regular inspections is also limited in many cases. The main part of this report deals with the qualification of such equipment. Some safety related equipment outside the containment can be located in areas where they are subjected to high temperature and other excessive environmental stresses during normal operation and in areas affected by an accident. Therefore, some material is given also on qualification of equipment located outside containment with better possibilities for frequent inspection and supervision. Part 1 of the report is an executive summary with a general review of the methodologies and their application. The more detailed description of the programs and underlying material, useful data, etc. is given in Part 2

Diagnostic x-ray equipment and its use

International Nuclear Information System (INIS)

1993-01-01

The guide contains the requirements for the use, structure and operation of diagnostic x-ray equipment necessary to ensure the radiation safety of workers and patients. The guide is intended for the party responsible for operating the x-ray units, the staff operating, installing and maintaining x-ray examination equipment, and companies manufacturing and selling such equipment. Special requirements for mammographic and dental x-ray equipments are given in separate ST guides. (5 refs., 1 figs., 2 tabs.)

Charging equipment. Ladegeraet

Energy Technology Data Exchange (ETDEWEB)

Neumann, E

1981-09-17

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

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

Requirements for industrial x-ray equipment

International Nuclear Information System (INIS)

1987-01-01

This safety code is concerned with the protection of all individuals who may be exposed to radiation emitted by X-ray equipment operating at energies up to 1 MeV as used in industrial radiography. This code presents basic radiation safety information for the protection of personnel operating and servicing X-ray equipment and other workers and the general public in the vicinity of areas where X-ray equipment is in operation. It specifies general safety features of design, construction and functioning of X-ray equipment and facilities; describes the responsibilities of the user, operator and maintenance personnel; contains recommendations to ensure that the X-ray equipment is used and maintained in accordance with the ALARA principle; and describes a program of personnel monitoring and radiation safety surveys. ( 6 refs., 5 tabs., 4 figs.)

Status analysis of Chinese standards on enclosure equipment and proposed countermeasures

International Nuclear Information System (INIS)

Wu Luping

1998-12-01

Enclosure equipment, such as glove box, tong box etc., is an important kind of equipment for nuclear industry and nuclear scientific research. The status of the establishment and implementation of Chinese standards on enclosure equipment is briefly described. Some problems and deficiency existing in these standards are pointed out. The ISO standard projects on containment enclosures as well as their present progress situations are introduced. The measure for updating Chinese standards on enclosure equipment in accordance with the principle of adopting international standards are recommended. Some issues which should be taken into account in adopting ISO standards on containment enclosures are also discussed

Hot conditioning equipment conceptual design report

International Nuclear Information System (INIS)

Bradshaw, F.W.

1996-01-01

This report documents the conceptual design of the Hot Conditioning System Equipment. The Hot conditioning System will consist of two separate designs: the Hot Conditioning System Equipment; and the Hot Conditioning System Annex. The Hot Conditioning System Equipment Design includes the equipment such as ovens, vacuum pumps, inert gas delivery systems, etc.necessary to condition spent nuclear fuel currently in storage in the K Basins of the Hanford Site. The Hot Conditioning System Annex consists of the facility of house the Hot Conditioning System. The Hot Conditioning System will be housed in an annex to the Canister Storage Building. The Hot Conditioning System will consist of pits in the floor which contain ovens in which the spent nuclear will be conditioned prior to interim storage

Hot conditioning equipment conceptual design report

Energy Technology Data Exchange (ETDEWEB)

Bradshaw, F.W., Westinghouse Hanford

1996-08-06

This report documents the conceptual design of the Hot Conditioning System Equipment. The Hot conditioning System will consist of two separate designs: the Hot Conditioning System Equipment; and the Hot Conditioning System Annex. The Hot Conditioning System Equipment Design includes the equipment such as ovens, vacuum pumps, inert gas delivery systems, etc.necessary to condition spent nuclear fuel currently in storage in the K Basins of the Hanford Site. The Hot Conditioning System Annex consists of the facility of house the Hot Conditioning System. The Hot Conditioning System will be housed in an annex to the Canister Storage Building. The Hot Conditioning System will consist of pits in the floor which contain ovens in which the spent nuclear will be conditioned prior to interim storage.

Performance monitoring of safeguards equipment

International Nuclear Information System (INIS)

Sirisena, K.; Peltoranta, M.; Goussarov, V.; Vodrazka, P.

1999-01-01

SGTCS is responsible for monitoring and reporting the performance of the SG equipment. Performance monitoring (PM) has been implemented in most important safeguards equipment operating unattended in nuclear facilities. Inspectors acquire equipment performance data in facilities. After inspection, the data package is submitted to SGTCS for processing and analysis. The performance data is used for identification of systems or components, which should be changed in the field and for identification of modules which, should be diagnosed at HQ in order to determine the cause of failure. Moreover, the performance data is used for preventive maintenance and spares distribution planning, and to provide statistics for official reports and management decision making. An important part of the performance monitoring is reporting. Equipment performance reports contain information about equipment inventory, utilization, failure types, failure distribution, and reliability. Trends in performance are given in graphical form in cases, where past data is available. Reliability estimates such as expected times between failures are provided. The automated reporting tools are obtainable through EMIS database application. (author)

Records Management Handbook; Source Data Automation Equipment Guide.

Science.gov (United States)

National Archives and Records Service (GSA), Washington, DC. Office of Records Management.

A detailed guide to selecting appropriate source data automation equipment is presented. Source data automation equipment is used to prepare data for electronic data processing or computerized recordkeeping. The guide contains specifications, performance data cost, and pictures of the major types of machines used in source data automation.…

Containment at the Source during Waste Volume Reduction of Large Radioactive Components Using Oxylance High-Temperature Cutting Equipment - 13595

International Nuclear Information System (INIS)

Keeney, G. Neil

2013-01-01

As a waste-volume reduction and management technique, highly contaminated Control Element Drive Mechanism (CEDM) housings were severed from the Reactor Pressure Vessel Head (RPVH) inside the San Onofre Unit 2 primary containment utilizing Oxylance high-temperature cutting equipment and techniques. Presented are relevant data concerning: - Radiological profiles of the RPVH and individual CEDMs; - Design overviews of the engineering controls and the specialized confinement housings; - Utilization of specialized shielding; - Observations of apparent metallurgical-contamination coalescence phenomena at high temperatures resulting in positive control over loose-surface contamination conditions; - General results of radiological and industrial hygiene air sampling and monitoring; - Collective dose and personnel contamination event statistics; - Lessons learned. (author)

Containment at the Source during Waste Volume Reduction of Large Radioactive Components Using Oxylance High-Temperature Cutting Equipment - 13595

Energy Technology Data Exchange (ETDEWEB)

Keeney, G. Neil [Health Physicist, HazMat CATS, LLC (United States)

2013-07-01

As a waste-volume reduction and management technique, highly contaminated Control Element Drive Mechanism (CEDM) housings were severed from the Reactor Pressure Vessel Head (RPVH) inside the San Onofre Unit 2 primary containment utilizing Oxylance high-temperature cutting equipment and techniques. Presented are relevant data concerning: - Radiological profiles of the RPVH and individual CEDMs; - Design overviews of the engineering controls and the specialized confinement housings; - Utilization of specialized shielding; - Observations of apparent metallurgical-contamination coalescence phenomena at high temperatures resulting in positive control over loose-surface contamination conditions; - General results of radiological and industrial hygiene air sampling and monitoring; - Collective dose and personnel contamination event statistics; - Lessons learned. (author)

Manufacture and maintenance of laboratory equipment

Energy Technology Data Exchange (ETDEWEB)

Hwang, Chang Kyu; Hwang, Bong Ha; Lee, Jong Wha; Kim, Jong Kyun; Yeum, Ki Eon; Park, Myung Ku; Hong, Soon Eon; Choi, Ho Young; An, Dae Kyu; An, Choon; Park, In Won; Kim, Kyung Sik; Lee, Won Jae; Yoon, Ki Byung; Kim, Heung Woo; Lee, In Bae; Yeom, Jeong Hyun; Lee, Chul Ku; Sin, Keon Ju; Oh, Wan Ho; Seo, Yong Chil; Yang, Song Yeul; Lee, Young Soon; Choi, Byung Kwon; Chang, Kyung Duk [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1993-12-01

This report on the manufacture and maintenance of laboratory equipment contains working contents, scope and contents of request working to the machine shop, also records the principal production design, manufacture contents and a relevant working drawing. The working content and scope of the machine shop is to support the successful and convenient performance of the R and D by manufacture and maintenance of all sorts of laboratory equipment. 11 tabs., 3 figs. (Author) .new.

Manufacture and maintenance of laboratory equipment

International Nuclear Information System (INIS)

Hwang, Chang Kyu; Hwang, Bong Ha; Lee, Jong Wha; Kim, Jong Kyun; Yeum, Ki Eon; Park, Myung Ku; Hong, Soon Eon; Choi, Ho Young; An, Dae Kyu; An, Choon; Park, In Won; Kim, Kyung Sik; Lee, Won Jae; Yoon, Ki Byung; Kim, Heung Woo; Lee, In Bae; Yeom, Jeong Hyun; Lee, Chul Ku; Sin, Keon Ju; Oh, Wan Ho; Seo, Yong Chil; Yang, Song Yeul; Lee, Young Soon; Choi, Byung Kwon; Chang, Kyung Duk

1993-12-01

This report on the manufacture and maintenance of laboratory equipment contains working contents, scope and contents of request working to the machine shop, also records the principal production design, manufacture contents and a relevant working drawing. The working content and scope of the machine shop is to support the successful and convenient performance of the R and D by manufacture and maintenance of all sorts of laboratory equipment. 11 tabs., 3 figs. (Author) .new

Manufacture and maintenance of laboratory equipment

International Nuclear Information System (INIS)

Kim, Jong Kyun; Hwang, Chang Kyu; Hwang, Bong Ha; Lee, Jong Wha; Yeom, Ki Eon; Park, Myung Ku; Hong, Soon Hyeon; Choi, Ho Young; An, Dae Kyu; An, Choon; Park, In Won; Kim, Kyeong Sik; Lee, In Bae; Yeom, Jeong Heon; Lee, Chul Ku; Sin, Keon Ju; Oh, Wan Ho; Choi, Byung Kwon; Chang, Kyeong Duk; Lee, Young Soon

1995-12-01

This report on the manufacture and maintenance of laboratory equipment contains working contents, scope and contents of a request working to the Machine Shop, also records the principal production design, manufacture contents and a relevant working drawing. The working content and scope of the Machine Shop is to support the successful and convenient performance of the Research and development by manufacture and maintenance of all sorts of laboratory equipment. 12 tabs., 5 figs. (Author) .new

Manufacture and maintenance of laboratory equipment

International Nuclear Information System (INIS)

Kim, J. K.; Whang, C. K.; Lee, J. H.; Youm, K. Y.; Hong, S. H.; Choi, H. Y.; An, C.; Park, I. W.; Kim, K. S.; Lee, W. J.; Yoon, K. B.; Kim, H. W.; Lee, I. B.; Lee, C. K.; Youm, J. H.; Oho, W. H.; Choi, B. K.; Jang, K. D.

1996-12-01

This report on the manufacture and maintenance of laboratory equipment contains working contents, scope and contents of a request working to the Machine Shop, also records the principal production design, manufacture contents and a relevant working drawing. The working content and scope of the Machine Shop is to support the successful and convenient performance of the R and D by manufacture and maintenance of all sorts of laboratory equipment. (author). 9 tabs., 12 figs

Manufacture and maintenance of laboratory equipment

Energy Technology Data Exchange (ETDEWEB)

Kim, Jong Kyun; Hwang, Chang Kyu; Hwang, Bong Ha; Lee, Jong Wha; Yeom, Ki Eon; Park, Myung Ku; Hong, Soon Hyeon; Choi, Ho Young; An, Dae Kyu; An, Choon; Park, In Won; Kim, Kyeong Sik; Lee, In Bae; Yeom, Jeong Heon; Lee, Chul Ku; Sin, Keon Ju; Oh, Wan Ho; Choi, Byung Kwon; Chang, Kyeong Duk; Lee, Young Soon [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-12-01

This report on the manufacture and maintenance of laboratory equipment contains working contents, scope and contents of a request working to the Machine Shop, also records the principal production design, manufacture contents and a relevant working drawing. The working content and scope of the Machine Shop is to support the successful and convenient performance of the Research and development by manufacture and maintenance of all sorts of laboratory equipment. 12 tabs., 5 figs. (Author) .new.

7 CFR 58.626 - Packaging equipment.

Science.gov (United States)

2010-01-01

... containers with frozen desserts shall be constructed so that all product contact surfaces shall be of... Standards for Equipment for Packaging Frozen Desserts and Cottage Cheese. Quality Specifications for Raw...

Overall Equipment Effectiveness Implementation Criteria

Science.gov (United States)

Abramova, I. G.; Abramov, D. A.

2018-01-01

This article documents the methods applied in production control technics specifically focused on commonly used parameter OEE (Overall Equipment Effectiveness). The indicators of extensive and intensive use of equipment are considered. Their appointment this is comparison in the same type of production within the industry and comparison of single-type and / or different types of equipment in terms of capacity. However, it is shown that there is no possibility of revealing the reasons for the machine’s operation: productive / unproductive, with disturbances. Therefore, in the article reveals the approaches to calculating the indicator characterizing the direct operation of the equipment. The Machine Load coefficient is approaching closely to the indicator of the efficiency of the use of equipment. Methods analysis is proceeded through the historically applied techniques such as “Stopwatch” and “Motion” studies. Was performed the analysis of the efficiency index of OEE equipment using the comparable indexes performance of equipment in the Russian practice. An important indicator of OEE contains three components. The meaning of each of them reflects historically applicable indicators. The value of the availability of equipment indicator is close to the value of the equipment extensibility index. The value of the indicator of the efficiency of work can be compared with the characteristic of the capacity of the equipment and the indicator of the quality level can meet the requirements for compliance with the manufacturing technology. Shown that the sum of the values of the coefficient of “Availability” of the equipment and the value of the “Factor of compaction of working hours” are one. As well as the total value of the indicator “level of quality” and the coefficient of marriage given in the result unit. The measurability of the indicators makes it possible to make a prediction about efficiency of the equipment.

Burial container subsidence load stress calculations

International Nuclear Information System (INIS)

Veith, E.M.

1995-11-01

This document captures the supporting analyses conducted to determine if the LLCE (Long-Length Contaminated Equipment) burial containers are structurally adequate under different trench closure scenarios. The LLCE is equipment that was inside tank farm tanks

Tworty Box to Improve the Equipment Logistics of Container Lines

Directory of Open Access Journals (Sweden)

Ulrich Malchow

2016-07-01

Full Text Available A major share of all empty container positioning (deadheading is resulting from imbalances with regard to container sizes (20ft/40ft. In order to reduce the shipments of 'containerised air' a new type of container has been developed by the author: The Tworty Boxes can either be used as a standard 20ft or in coupled condition as a 40ft container. The outside appearance resembles any standard 20ft container. However the Tworty Box is unique in that it has an additional door at the front side that opens to the inside. This door can be fixed to the ceiling and by using of bonding elements another Tworty Box can be joined up, thereby creating the full 40ft inside space. Operated as a single 20ft box the additional door remains locked, access is only through the existing standard door. Tworty Boxes do not require any additional components and fulfil all ISO and CSC requirements.

Pocket dictionary of laboratory equipment

International Nuclear Information System (INIS)

Junge, H.D.

1987-01-01

This pocket dictionary contains the 2500 most common terms for scientific and technical equipment in chemical laboratories. It is a useful tool for those who are used to communicating in German and English, but have to learn the special terminology in this field. (orig.) [de

46 CFR 160.026-3 - Container.

Science.gov (United States)

2010-10-01

... 46 Shipping 6 2010-10-01 2010-10-01 false Container. 160.026-3 Section 160.026-3 Shipping COAST...: SPECIFICATIONS AND APPROVAL LIFESAVING EQUIPMENT Water, Emergency Drinking (In Hermetically Sealed Containers), for Merchant Vessels § 160.026-3 Container. (a) General. The emergency drinking water container shall...

Safeguards techniques and equipment

International Nuclear Information System (INIS)

1997-01-01

The current booklet is intended to give a full and balanced description of the techniques and equipment used for both nuclear material accountancy and containment and surveillance measures, and for the new safeguards measure of environmental sampling. As new verification measures continue to be developed, the material in the booklet will be periodically reviewed and updated versions issued. (author)

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

46 CFR 160.028-6 - Container.

Science.gov (United States)

2010-10-01

... 46 Shipping 6 2010-10-01 2010-10-01 false Container. 160.028-6 Section 160.028-6 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) EQUIPMENT, CONSTRUCTION, AND MATERIALS... Container. (a) General. Containers for the stowage of signal pistols and pistol projected parachute red...

Influence of Different Container Closure Systems and Capping Process Parameters on Product Quality and Container Closure Integrity (CCI) in GMP Drug Product Manufacturing.

Science.gov (United States)

Mathaes, Roman; Mahler, Hanns-Christian; Roggo, Yves; Huwyler, Joerg; Eder, Juergen; Fritsch, Kamila; Posset, Tobias; Mohl, Silke; Streubel, Alexander

2016-01-01

Capping equipment used in good manufacturing practice manufacturing features different designs and a variety of adjustable process parameters. The overall capping result is a complex interplay of the different capping process parameters and is insufficiently described in literature. It remains poorly studied how the different capping equipment designs and capping equipment process parameters (e.g., pre-compression force, capping plate height, turntable rotating speed) contribute to the final residual seal force of a sealed container closure system and its relation to container closure integrity and other drug product quality parameters. Stopper compression measured by computer tomography correlated to residual seal force measurements.In our studies, we used different container closure system configurations from different good manufacturing practice drug product fill & finish facilities to investigate the influence of differences in primary packaging, that is, vial size and rubber stopper design on the capping process and the capped drug product. In addition, we compared two large-scale good manufacturing practice manufacturing capping equipment and different capping equipment settings and their impact on product quality and integrity, as determined by residual seal force.The capping plate to plunger distance had a major influence on the obtained residual seal force values of a sealed vial, whereas the capping pre-compression force and the turntable rotation speed showed only a minor influence on the residual seal force of a sealed vial. Capping process parameters could not easily be transferred from capping equipment of different manufacturers. However, the residual seal force tester did provide a valuable tool to compare capping performance of different capping equipment. No vial showed any leakage greater than 10(-8)mbar L/s as measured by a helium mass spectrometry system, suggesting that container closure integrity was warranted in the residual seal force range

Failure diagnosis aiding device for plant equipment

International Nuclear Information System (INIS)

Uhara, Yoshihiko.

1990-01-01

The present invention intends to improve the efficiency of trouble shooting for equipments of industrial plants such as nuclear power plants. The device of the present invention comprises an intelligence base and an inference mechanism base. The intelligence base comprises a rule base, an information storing section having a part frame and a working frame and a user's frame. The parts frame contains the failure rate on every parts and data on related operations. The working frame contains the importance and frequency of working. The user's frame contains parameters showing the extent of user's skills. The rule base, the parts frame and the working frame can be selected in accordance with the extent of the user's skill in the inference mechanism. With such a constitution, failures can be checked with the intelligence base in accordance with the knowledges for the failures of the equipments and the extent of user's skill by way of the inference mechanism. (I.S.)

Equipment for the handling of thorium materials

International Nuclear Information System (INIS)

Heisler, S.W. Jr.; Mihalovich, G.S.

1988-01-01

The Feed Materials Production Center (FMPC) is the United States Department of Energy's storage facility for thorium. FMPC thorium handling and overpacking projects ensure the continued safe handling and storage of the thorium inventory until final disposition of the materials is determined and implemented. The handling and overpacking of the thorium materials requires the design of a system that utilizes remote handling and overpacking equipment not currently utilized at the FMPC in the handling of uranium materials. The use of remote equipment significantly reduces radiation exposure to personnel during the handling and overpacking efforts. The design system combines existing technologies from the nuclear industry, the materials processing and handling industry and the mining industry. The designed system consists of a modified fork lift truck for the transport of thorium containers, automated equipment for material identification and inventory control, and remote handling and overpacking equipment for material identification and inventory control, and remote handling and overpacking equipment for repackaging of the thorium materials

Specific equipment for the transfer and transport of radioactive liquids

International Nuclear Information System (INIS)

Leblais, R.

1983-01-01

Safety regulations impose a system of transport high-level radioactive liquids which excludes all risk of accidental projections. Ets. LEMER have collaborated with the A.E.C. for the industrial manufacture of more than 250 pieces of equipment for FRANCE and for 13 nuclear centres abroad. This equipment can be classified in two categories: - CENDRILLON containers which must be placed in special shock-proof and fire-proof shells for transport on public roads; - containers mounted on trailors provided with their own shock-proof and fire-proof protection

Rules and procedures for the design and operation of hazardous research equipment

International Nuclear Information System (INIS)

1978-12-01

The manual has been prepared for use by research personnel involved in experiments at the Lawrence Berkeley Laboratory. It contains rules and procedures for the design, test, installation, and operation of hazardous research equipment. Sect. I contains such information as responsibility of experimenters for safety, descriptions of the various Laboratory safety organizations, and enumeration of various services available to experimenters at the Laboratory. Sect. II describes specific rules for the setup and operation of experimental equipment at the Laboratory. Sect. III gives detailed design criteria and procedures for equipment frequently encountered in the high energy physics laboratory

VIRTUAL ELECTRONIC COMPONENTS OF THE ELECTRONIC EQUIPMENT

Directory of Open Access Journals (Sweden)

E. Lazarevich

2013-01-01

Full Text Available The article is present new idea of the creation, developments and improvements of the electronic equipment of complex systems by means of the virtual electronic components. The idea of the virtual electronic components is a presentation and perception of the creation and developments of the equipment on two forming: real – in the manner of standard marketed block of the intellectual property and image – in the manner of virtual component. The real component in most cases slows the development of the electronic equipment. The imaginary component is the «locomotive» of development of the electronic equipment. The Imaginary component contains the scientific has brushed against developer. The scientific has brushed against developer reveals of itself in the manner of virtual component on the modern level of the design rates of microelectronics.

Environmental qualification program of electric equipment for Angra 1

Energy Technology Data Exchange (ETDEWEB)

Muzitano, Grazielle F.; Justino, Marcelo C.; Silva, Marcos C., E-mail: grazi@eletronuclear.gov.br, E-mail: justino@eletronuclear.gov.br, E-mail: candeia@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

2017-11-01

This paper describes the development of the environmental qualification program for important electrical equipment (EQPEE) used for safety in Angra 1 Nuclear Power Plant (NPP). The environmental qualification program started in United States of America by the Nuclear Regulatory Commission (NRC) after the Three Mile Island (TMI) Nuclear Power Plant Accident in 1979. In that event, some equipment installed inside the reactor containment of TMI failed due the harsh conditions that occurred after the accident. Because of this fact, the NRC issued the Regulation 50.49 'Environmental qualification of electric equipment important to safety for nuclear power plants'. The Brazilian regulatory commission CNEN also asked Angra 1 to follow this regulation and to implement an EQPEE similar to the programs adopted by American and other NPPs around the world. Due to the importance to maintain the critical equipment operating in normal and abnormal environment conditions, the program aims to assure that this equipment remains qualified to work under the harsh conditions found inside the reactor containment. The aging of these components are also analyzed in this program that is important in the process to extend the operating life of Angra 1 for more 20 years, which is normally referred as Long Term Operation (LTO). (author)

Environmental qualification program of electric equipment for Angra 1

International Nuclear Information System (INIS)

Muzitano, Grazielle F.; Justino, Marcelo C.; Silva, Marcos C.

2017-01-01

This paper describes the development of the environmental qualification program for important electrical equipment (EQPEE) used for safety in Angra 1 Nuclear Power Plant (NPP). The environmental qualification program started in United States of America by the Nuclear Regulatory Commission (NRC) after the Three Mile Island (TMI) Nuclear Power Plant Accident in 1979. In that event, some equipment installed inside the reactor containment of TMI failed due the harsh conditions that occurred after the accident. Because of this fact, the NRC issued the Regulation 50.49 'Environmental qualification of electric equipment important to safety for nuclear power plants'. The Brazilian regulatory commission CNEN also asked Angra 1 to follow this regulation and to implement an EQPEE similar to the programs adopted by American and other NPPs around the world. Due to the importance to maintain the critical equipment operating in normal and abnormal environment conditions, the program aims to assure that this equipment remains qualified to work under the harsh conditions found inside the reactor containment. The aging of these components are also analyzed in this program that is important in the process to extend the operating life of Angra 1 for more 20 years, which is normally referred as Long Term Operation (LTO). (author)

Empty Container Logistics

Directory of Open Access Journals (Sweden)

Jakov Karmelić

2012-05-01

Full Text Available Within the whole world container traffic, the largest share of containers is in the status of repositioning. Container repositioning results from the need for harmonization between the point of empty container accumulation and the point of demand, and waiting time for the availability of the first next transport of cargo. This status of containers on the container market is the consequence of imbalances in the worldwide trade distribution on most important shipping routes. The need for fast and effective reallocation of empty containers causes high costs and often represents an obstacle affecting the efficiency of port container terminals and inland carriers.In accordance with the above issue, this paper is mainly focused on the analysis of the data concerning global container capacities and the roots of container equipment imbalances, with the aim of determining the importance of empty container management and the need for empty container micro-logistic planning at the spread port area.

29 CFR 1915.173 - Drums and containers.

Science.gov (United States)

2010-07-01

... 29 Labor 7 2010-07-01 2010-07-01 false Drums and containers. 1915.173 Section 1915.173 Labor... Vessels, Drums and Containers, Other Than Ship's Equipment § 1915.173 Drums and containers. (a) Shipping drums and containers shall not be pressurized to remove their contents. (b) A temporarily assembled...

Development of processes and equipment for the refabrication of HTGR fuels

International Nuclear Information System (INIS)

Sease, J.D.; Lotts, A.L.

1976-06-01

Refabrication is in the step in the HTGR thorium fuel cycle that begins with a nitrate solution containing 238 U and culminates in the assembly of this material into fuel elements for use in an HTGR. Refabrication of HTGR fuel is essentially a manufacturing operation and consists of preparation of fuel kernels, application of multiple layers of pyrolytic carbon and SiC, preparation of fuel rods, and assembly of fuel rods in fuel elements. All the equipment for refabrication of 238 U-containing fuel must be designed for completely remote operation and maintenance in hot cell facilities. This paper describes the status of processes and equipment development for the remote refabrication of HTGR fuels. The feasibility of HTGR refabrication processes has been proven by laboratory development. Engineering-scale development is now being performed on a unit basis on the majority of the major equipment items. Engineering-scale equipment described includes full-scale resin loading equipment, a 5-in.-dia (0.13-m) microsphere coating furnace, a fuel rod forming machine, and a cure-in-place furnace

47 CFR 15.305 - Equipment authorization requirement.

Science.gov (United States)

2010-10-01

... Section 15.305 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL RADIO FREQUENCY DEVICES Unlicensed Personal Communications Service Devices § 15.305 Equipment authorization requirement. PCS devices... 2 of this chapter before marketing. The application for certification must contain sufficient...

PROMSYS, Plant Equipment Maintenance and Inspection Scheduling

International Nuclear Information System (INIS)

Morgan, D.L.; Srite, B.E.

1986-01-01

1 - Description of problem or function: PROMSYS is a computer system designed to automate the scheduling of routine maintenance and inspection of plant equipment. This 'programmed maintenance' provides the detailed planning and accomplishment of lubrication, inspection, and similar repetitive maintenance activities which can be scheduled at specified predetermined intervals throughout the year. The equipment items included are the typical pumps, blowers, motors, compressors, automotive equipment, refrigeration units, filtering systems, machine shop equipment, cranes, elevators, motor-generator sets, and electrical switchgear found throughout industry, as well as cell ventilation, shielding, containment, and material handling equipment unique to nuclear research and development facilities. Four related programs are used to produce sorted schedule lists, delinquent work lists, and optional master lists. Five additional programs are used to create and maintain records of all scheduled and unscheduled maintenance history. 2 - Method of solution: Service specifications and frequency are established and stored. The computer program reviews schedules weekly and prints, on schedule cards, instructions for service that is due the following week. The basic output from the computer program comes in two forms: programmed-maintenance schedule cards and programmed-maintenance data sheets. The data sheets can be issued in numerical building, route, and location number sequence as equipment lists, grouped for work assigned to a particular foreman as the foreman's equipment list, or grouped by work charged to a particular work order as the work-order list. Data sheets grouped by equipment classification are called the equipment classification list

46 CFR 160.037-6 - Container.

Science.gov (United States)

2010-10-01

... 46 Shipping 6 2010-10-01 2010-10-01 false Container. 160.037-6 Section 160.037-6 Shipping COAST...: SPECIFICATIONS AND APPROVAL LIFESAVING EQUIPMENT Hand Orange Smoke Distress Signals § 160.037-6 Container. (a) General. The container for storing the signals on lifeboats and liferafts is not required to be of a...

Development and Manufacture of the Nuclear Laboratory Equipment

International Nuclear Information System (INIS)

Youm, Ki Un; Kim, J. K.; Kim, K. S.; Lee, I. B.; Youm, J. H.; Park, I. W.

2008-12-01

This report on development and manufacture of the nuclear laboratory equipment contains the work scope and contents performed for supporting the researches and the developments projects efficiently. And also, the records for the principal production design, the manufacture contents, the working drawings and the CNC program are described in it. Most of works are to support the successful and convenient performance of the R and D projects by development and manufacturing the requested laboratory equipment

Development and Manufacture of the Nuclear Laboratory Equipment

International Nuclear Information System (INIS)

Youm, Ki Un; Moon, J. S.; Lee, I. B.; Youn, J. H.

2010-12-01

This report on development and manufacture of the nuclear laboratory equipment contains the work scope and contents performed for supporting the researches and the developments projects efficiently. And also, the records for the principal production design, the manufacture contents, the working drawings and the CNC program are described in it. Most of works are to support the successful and convenient performance of the R and D projects by development and manufacturing the requested laboratory equipment

Development and Manufacture of the Nuclear laboratory equipment

International Nuclear Information System (INIS)

Youm, Ki Un; Lee, I. B.; Youm, J. H.

2009-12-01

This report on development and manufacture of the nuclear laboratory equipment contains the work scope and contents performed for supporting the researches and the developments projects efficiently. And also, the records for the principal production design, the manufacture contents, the working drawings and the CNC program are described in it. Most of works are to support the successful and convenient performance of the R and D projects by development and manufacturing the requested laboratory equipment

Ventilation of gloveboxes and containment shells

International Nuclear Information System (INIS)

Guetron, R.

1984-01-01

In this paper are defined fundamental principles for the ventilation of containment enclosures and gloveboxes, and examined criteria required to maintain containment in normal or accidental conditions. Dimensioning of ventilation network and associated equipment (adjustement and filtering devices). Some examples are given [fr

Photoelectric equipment type MFS-7 for analyzing oils

International Nuclear Information System (INIS)

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

1987-01-01

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

Analysis of Electrical Power Consumption in Container Crane of Container Terminal Surabaya

Directory of Open Access Journals (Sweden)

A.A. Masroeri

2017-12-01

Full Text Available Container crane electrification is a re-powering process of container cranes from diesel to electricity. In electrification process, it is required an analysis of electrical power consumption that is needed in the operational of container crane. It aims to determine whether the amount of electrical power that is supplied by PLN can be optimally used in the operational of container crane to do loading and unloading activities. To perform the analysis of electrical power consumption, it is required various data and calculations. The required data are container crane specifications and other electrical equipment specifications, the amount of electrical power that is supplied by PLN, also the single line diagram from the electrical system at the port. While, the calculations that is needed to be performed are the calculation of electrical power load in motors and other electrical equipments, the calculation of nominal current and start current, the selection of cable and busbar, and the calculation of wiring diagram junction power. From the calculations that has been done, then the next step is to do the load flow analysis simulation by using software simulation, so an accurate and effective load flow analysis can be obtained to optimize loading and unloading activities at the port. The result of this research, it can be seen that container crane electrification will give advantages in both technical and economical for the company and for the ship, such as accelerate the loading and unloading time of containers and reduce idle time, especially in the operational of diesel generator.

42 CFR 84.74 - Apparatus containers; minimum requirements.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Apparatus containers; minimum requirements. 84.74...-Contained Breathing Apparatus § 84.74 Apparatus containers; minimum requirements. (a) Apparatus may be equipped with a substantial, durable container bearing markings which show the applicant's name, the type...

7 CFR 58.514 - Container fillers.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Container fillers. 58.514 Section 58.514 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Standards....514 Container fillers. Shall comply with the 3-A Sanitary Standards for Equipment for Packaging Frozen...

Component failure experiments of the seal casing for the multiple-row bolted connection of the containment equipment hatch of the nuclear power plant Philippsburg II; Experimente zum Versagen des Dichtkastens fuer die Materialschleusenverschraubung im Containment des KKW Philippsburg II

Energy Technology Data Exchange (ETDEWEB)

Messemer, G.

2008-06-15

For the weakness analysis of the containment under internal pressure a question that arose was at what pressure the seal casing for the equipment hatch will fail. For this investigation model strips of the seal casing cross section were manufactured as tensile specimens. Variations of the seal plates welding seams were considered and tested. The type of failure and the associated deformations and resulting forces were measured for 6 specimens. (orig.)

The first equipment for protection from nanoparticles

International Nuclear Information System (INIS)

Faure, Louis-Paul; Bombardier, Pierre; Reinwalt, Jean-Marie

2009-01-01

How can we guarantee the containment of ultrafine particles but also implement the ergonomic and handling constraints voiced by researchers? This is the equation that the engineers at FAURE INGENIERIE had to resolve to develop the first barrier protection equipment for nanoparticle research.

The first equipment for protection from nanoparticles

Energy Technology Data Exchange (ETDEWEB)

Faure, Louis-Paul; Bombardier, Pierre; Reinwalt, Jean-Marie [FAURE INGENIERIE S.A., Parc Technologique des Fontaines, Chemin des Fontaines, F-38190 Bernin (France)], E-mail: laboratoire@faureingenierie.com

2009-05-01

How can we guarantee the containment of ultrafine particles but also implement the ergonomic and handling constraints voiced by researchers? This is the equation that the engineers at FAURE INGENIERIE had to resolve to develop the first barrier protection equipment for nanoparticle research.

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

Containment test in area of high latitude and low temperature

International Nuclear Information System (INIS)

Cai Jiantao; Ni Yongsheng; Jia Wutong

2014-01-01

The effects of high latitude and low temperature on containment test are detailed analyzed from the view of design, equipment, construct and start-up, and the solution is put forward. The major problems resolved is as below: the effects of low temperature and high wind on defect inspection of the containment surface, the effects of test load on the affiliated equipment of containment in the condition of low temperature, and the effects of low temperature on the containment leak rate measurement. Application in Hongyanhe Unit 1 showed that the proposed scheme can effectively overcome the influence of adverse weather on the containment test. (authors)

Oil-field equipment in Romania. Export trade information

International Nuclear Information System (INIS)

Tinis, R.

1991-09-01

The Industry Sector Analyses (I.S.A.) for oil field equipment contains statistical and narrative information on projected market demand, end-users, receptivity of Romanian consumers to U.S. products, the competitive situation - Romanian production, total import market, U.S. market position, foreign competition, and competitive factors, and market access - Romanian tariffs, non-tariff barriers, standards, taxes and distribution channels. The I.S.A. provides the United States industry with meaningful information regarding the Romanian market for oil field equipment

Nuclear power plant containment construction

International Nuclear Information System (INIS)

Schabert, H.P.; Danisch, R.; Strickroth, E.

1975-01-01

The Nuclear Power Plant Containment Construction includes the spherical steel safety enclosure for the reactor and the equipment associated with the reactor and requiring this type of enclosure. This steel enclosure is externally structurally protected against accident by a concrete construction providing a foundation for the steel enclosure and having a cylindrical wall and a hemispherical dome, these parts being dimensioned to form an annular space surrounding the spherical steel enclosure, the latter and the concrete construction heretofore being concentrically arranged with respect to each other. In the disclosed construction the two parts are arranged with their vertical axis horizontally offset from each other so that opposite to the offsetting direction of the concrete construction a relatively large space is formed in the now asymmetrical annular space in which reactor auxiliary equipment not requiring enclosure by the steel containment vessel or safety enclosure, may be located outside of the steel containment vessel and inside of the concrete construction where it is structurally protected by the latter

Self-contained microfluidic systems: a review.

Science.gov (United States)

Boyd-Moss, Mitchell; Baratchi, Sara; Di Venere, Martina; Khoshmanesh, Khashayar

2016-08-16

Microfluidic systems enable rapid diagnosis, screening and monitoring of diseases and health conditions using small amounts of biological samples and reagents. Despite these remarkable features, conventional microfluidic systems rely on bulky expensive external equipment, which hinders their utility as powerful analysis tools outside of research laboratories. 'Self-contained' microfluidic systems, which contain all necessary components to facilitate a complete assay, have been developed to address this limitation. In this review, we provide an in-depth overview of self-contained microfluidic systems. We categorise these systems based on their operating mechanisms into three major groups: passive, hand-powered and active. Several examples are provided to discuss the structure, capabilities and shortcomings of each group. In particular, we discuss the self-contained microfluidic systems enabled by active mechanisms, due to their unique capability for running multi-step and highly controllable diagnostic assays. Integration of self-contained microfluidic systems with the image acquisition and processing capabilities of smartphones, especially those equipped with accessory optical components, enables highly sensitive and quantitative assays, which are discussed. Finally, the future trends and possible solutions to expand the versatility of self-contained, stand-alone microfluidic platforms are outlined.

42 CFR 84.197 - Respirator containers; minimum requirements.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Respirator containers; minimum requirements. 84.197... Cartridge Respirators § 84.197 Respirator containers; minimum requirements. Respirators shall be equipped with a substantial, durable container bearing markings which show the applicant's name, the type and...

Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems

Directory of Open Access Journals (Sweden)

Siniša Šadek

2017-01-01

Full Text Available The integrity of the containment will be challenged during a severe accident due to pressurization caused by the accumulation of steam and other gases and possible ignition of hydrogen and carbon monoxide. Installation of a passive filtered venting system and passive autocatalytic recombiners allows control of the pressure, radioactive releases, and concentration of flammable gases. Thermal hydraulic analysis of the containment equipped with dedicated passive safety systems after a hypothetical station blackout event is performed for a two-loop pressurized water reactor NPP with three integral severe accident codes: ASTEC, MELCOR, and MAAP. MELCOR and MAAP are two major US codes for severe accident analyses, and the ASTEC code is the European code, joint property of Institut de Radioprotection et de Sûreté Nucléaire (IRSN, France and Gesellschaft für Anlagen und Reaktorsicherheit (GRS, Germany. Codes’ overall characteristics, physics models, and the analysis results are compared herein. Despite considerable differences between the codes’ modelling features, the general trends of the NPP behaviour are found to be similar, although discrepancies related to simulation of the processes in the containment cavity are also observed and discussed in the paper.

Conceptual design report, CEBAF basic experimental equipment

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-04-13

The Continuous Electron Beam Accelerator Facility (CEBAF) will be dedicated to basic research in Nuclear Physics using electrons and photons as projectiles. The accelerator configuration allows three nearly continuous beams to be delivered simultaneously in three experimental halls, which will be equipped with complementary sets of instruments: Hall A--two high resolution magnetic spectrometers; Hall B--a large acceptance magnetic spectrometer; Hall C--a high-momentum, moderate resolution, magnetic spectrometer and a variety of more dedicated instruments. This report contains a short description of the initial complement of experimental equipment to be installed in each of the three halls.

42 CFR 84.134 - Respirator containers; minimum requirements.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Respirator containers; minimum requirements. 84.134... Respirators § 84.134 Respirator containers; minimum requirements. Supplied-air respirators shall be equipped with a substantial, durable container bearing markings which show the applicant's name, the type and...

42 CFR 84.1134 - Respirator containers; minimum requirements.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Respirator containers; minimum requirements. 84... Combination Gas Masks § 84.1134 Respirator containers; minimum requirements. (a) Except as provided in paragraph (b) of this section each respirator shall be equipped with a substantial, durable container...

Initial acceptance test experience with FFTF plant equipment

International Nuclear Information System (INIS)

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

1978-09-01

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

1994 Solid waste forecast container volume summary

International Nuclear Information System (INIS)

Templeton, K.J.; Clary, J.L.

1994-09-01

This report describes a 30-year forecast of the solid waste volumes by container type. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste. These volumes and their associated container types will be generated or received at the US Department of Energy Hanford Site for storage, treatment, and disposal at Westinghouse Hanford Company's Solid Waste Operations Complex (SWOC) during a 30-year period from FY 1994 through FY 2023. The forecast data for the 30-year period indicates that approximately 307,150 m 3 of LLMW and TRU/TRUM waste will be managed by the SWOC. The main container type for this waste is 55-gallon drums, which will be used to ship 36% of the LLMW and TRU/TRUM waste. The main waste generator forecasting the use of 55-gallon drums is Past Practice Remediation. This waste will be generated by the Environmental Restoration Program during remediation of Hanford's past practice sites. Although Past Practice Remediation is the primary generator of 55-gallon drums, most waste generators are planning to ship some percentage of their waste in 55-gallon drums. Long-length equipment containers (LECs) are forecasted to contain 32% of the LLMW and TRU/TRUM waste. The main waste generator forecasting the use of LECs is the Long-Length Equipment waste generator, which is responsible for retrieving contaminated long-length equipment from the tank farms. Boxes are forecasted to contain 21% of the waste. These containers are primarily forecasted for use by the Environmental Restoration Operations--D ampersand D of Surplus Facilities waste generator. This waste generator is responsible for the solid waste generated during decontamination and decommissioning (D ampersand D) of the facilities currently on the Surplus Facilities Program Plan. The remaining LLMW and TRU/TRUM waste volume is planned to be shipped in casks and other miscellaneous containers

GreenChill Store Certification Protocol for Sub-Cooling Contained on Racks Separate from Refrigeration Equipment

Science.gov (United States)

Document describes the protocol used to determine the total load and refrigerant charge of stores that have placed all sub-cooling on a rack separate from all other commercial refrigeration equipment.

Providing reliable equipment to IAEA through a low risk transition plan

International Nuclear Information System (INIS)

Green, L.; Weinstock, E.V.; Karlin, E.W.

1988-01-01

The development and production of safeguards equipment is a complex process containing many potential pitfalls between the conceptual design and its implementation in the field. The conditions for equipment use are especially demanding. At the same time, the consequences of failure may be serious. Repeated failure may result in the loss of credibility of safeguards. Expensive back up measures such as re-verification of inventories may be required. Inspectors may come to distrust the equipment. Finally, the expense of maintaining the equipment may be excessive. It is therefore essential that the process for bringing equipment for the conceptual stage to actual routine use minimizes the risk of producing equipment that is unsuitable for the job. Fortunately, approaches for accomplishing this have already been developed in both the industrial and commercial sectors. One such approach, the Low Risk Transition Plan (LRTP) is described to show it can be applied to the production of reliable safeguards equipment

Returnable containers: an example of reverse logistics

NARCIS (Netherlands)

L.G. Kroon (Leo); G.M.C. Vrijens

1996-01-01

textabstractConsiders the application of returnable containers as an example of reverse logistics. A returnable container is a type of secondary packaging that can be used several times in the same form, in contrast with traditional cardboard boxes. For this equipment to be used, a system for the

Nuclear reactor containment device

International Nuclear Information System (INIS)

Ichiki, Tadaharu.

1980-01-01

Purpose: To reduce the volume of a containment shell and decrease the size of a containment equipment for BWR type reactors by connecting the containment shell and a suppression pool with slanted vent tubes to thereby shorten the vent tubes. Constitution: A pressure vessel containing a reactor core is installed at the center of a building and a containment vessel for the nuclear reactor that contains the pressure vessel forms a cabin. To a building situated below the containment shell, is provided a suppression chamber in which cooling water is charged to form a suppression pool. The suppression pool is communicated with vent tubes that pass through the partition wall of the containment vessel. The vent tubes are slanted and their lower openings are immersed in coolants. Therefore, if accident is resulted and fluid at high temperature and high pressure is jetted from the pressure vessel, the jetting fluid is injected and condensated in the cooling water. (Moriyama, K.)

Equipment designs for the spent LWR fuel dry storage demonstration

International Nuclear Information System (INIS)

Steffen, R.J.; Kurasch, D.H.; Hardin, R.T.; Schmitten, P.F.

1980-01-01

In conjunction with the Spent Fuel Handling and Packaging Program (SFHPP) equipment has been designed, fabricated and successfully utilized to demonstrate the packaging and interim dry storage of spent LWR fuel. Surface and near surface storage configurations containing PWR fuel assemblies are currently on test and generating baseline data. Specific areas of hardware design focused upon include storage cell components and the support related equipment associated with encapsulation, leak testing, lag storage, and emplacement operations

Project management in nuclear equipment manufacture

International Nuclear Information System (INIS)

Liu Jiancheng

2005-01-01

The completion of the management organization shall be firstly considered in project management for a nuclear power plant. The organization of nuclear equipment quality assurance program and project management consists of 5 departments such as the nuclear power container department, the manufacture department and the quality assurance department. The general manager takes the overall responsibility for the quality of the nuclear press usr bearing equipment, and the vice general manager takes responsibility for the quality, technology and schedule related with the manufacture of the equipment, and organizes the organization department for the audit. The director of the quality assurance department takes the responsibility for the establishment and completion of the quality assurance program, with enough rights authorized by the general manager, including the right not bounded by the cost and schedule, and confirms the implementation of the program by related departments and personnel. The manufacture schedule shall be prepared to ensure the implementation feasibility, process continuity and flexibility. The schedule shall be followed and monitored for the whole process, to check and feedback the implementation. (authors)

Radioactive wastes assay technique and equipment

International Nuclear Information System (INIS)

Lee, K. M.; Hong, D. S; Kim, T. K.; Bae, S. M.; Shon, J. S.; Hong, K. P.

2004-12-01

The waste inventory records such as the activities and radio- nuclides contained in the waste packages are to be submitted with the radioactive wastes packages for the final disposal. The nearly around 10,000 drums of waste stocked in KAERI now should be assayed for the preparation of the waste inventory records too. For the successive execution of the waste assay, the investigation into the present waste assay techniques and equipment are to be taken first. Also the installation of the waste assay equipment through the comprehensive design, manufacturing and procurement should be proceeded timely. As the characteristics of the KAERI-stocked wastes are very different from that of the nuclear power plant and those have no regular waste streams, the application of the in-direct waste assay method using the scaling factors are not effective for the KAERI-generated wastes. Considering for the versal conveniency including the accuracy over the wide range of waste forms and the combination of assay time and sensitivity, the TGS(Tomographic Gamma Scanner) is appropriate as for the KAERI -generated radioactive waste assay equipment

Catalog of physical protection equipment. Book 1: Volume I. Barriers and structural components

International Nuclear Information System (INIS)

Haberman, W.

1977-06-01

A catalog of commercially available physical protection equipment has been prepared for use by the U.S. Nuclear Regulatory Commission (NRC). Included is information on barrier structures and equipment, interior and exterior intrusion detection sensors, entry (access) control devices, surveillance and alarm assessment equipment, contraband detection sensors, automated response equipment, general purpose displays and general purpose communications, with one volume devoted to each of these eight areas. For each item of equipment the information included consists of performance, physical, cost and supply/logistics data. The entire catalog is contained in three notebooks for ease in its use by licensing and inspection staff at NRC

Catalog of physical protection equipment. Book 3: Volume VII. General purpose display components

International Nuclear Information System (INIS)

1977-06-01

A catalog of commercially available physical protection equipment has been prepared under MITRE contract AT(49-24)-0376 for use by the U. S. Nuclear Regulatory Commission (NRC). Included is information on barrier structures and equipment, interior and exterior intrusion detection sensors, entry (access) control devices, surveillance and alarm assessment equipment, contraband detection sensors, automated response equipment, general purpose displays and general purpose communications, with one volume devoted to each of these eight areas. For each item of equipment the information included consists of performance, physical, cost and supply/logistics data. The entire catalog is contained in three notebooks for ease in its use by licensing and inspection staff at NRC

Radiation safety of sealed sources and equipment containing them

International Nuclear Information System (INIS)

1993-01-01

The guide gives information and requirements concerning the technical construction, installation, use and licensing of devices containing sealed radioactive sources in order to ensure the operational safety. The requirements are in accordance with the international standards ISO 1677, ISO 2919, ISO 7205 and Nordic Recommendations on radiation protection for radionuclide gauges in permanent installation. The guide explains also the practical measures that must be taken into account when a radiation device is repaired, maintained or removed from the use. (8 refs.)

Regulations for pressurized equipment in the European Single Market - construction of steam boilers, containers and pipelines

International Nuclear Information System (INIS)

Grassmuck, J.

1992-01-01

The impulses produced by the data of the standardized EC Single Market have now reached pressurized equipment in the field of EC Guidelines and European standardisation. This must be regarded as a great challenge to the interested and concerned parties. All efforts to represent the interested parties in European Committees must be made. In order to reach the goal quickly and successfully, a considerable readiness to compromise is, however, necessary. At the end of the development process, a comprehensible, standardized set of regulations will be available for pressurized equipment throughout Europe. The regulations will consist of national ones converted into European Guidelines and Standards. (orig.) [de

Safeguards techniques and equipment. 2003 ed

International Nuclear Information System (INIS)

2003-01-01

The 1990s saw significant non-proliferation related developments in the world, resulting in a new period of safeguards development. Over several years an assessment was made of how to strengthen the effectiveness and improve the efficiency of IAEA safeguards. In May 1997 this culminated in the adoption by the IAEA Board of Governors of a Protocol Additional to Safeguards Agreements which significantly broadens the role of IAEA safeguards. As a consequence, the IAEA safeguards system entered a new era. In 1997 the IAEA began to publish a new series of booklets on safeguards, called the International Nuclear Verification Series (NVS). The objective of these booklets was to help in explaining IAEA safeguards, especially the new developments in safeguards, particularly for facility operators and government officers involved with these topics. The current booklet, which is a revision and update of IAEA/NVS/1, is intended to give a full and balanced description of the techniques and equipment used for both nuclear material accountancy and containment and surveillance measures, and for the new safeguards measure of environmental sampling. A completely new section on data security has been added to describe the specific features that are included in installed equipment systems in order to ensure the authenticity and confidentiality of information. As new verification measures continue to be developed the material in this booklet will be periodically reviewed and updated versions issued. The basic verification measure used by the IAEA is nuclear material accountancy. In applying nuclear material accountancy, IAEA safeguards inspectors make independent measurements to verify quantitatively the amount of nuclear material presented in the State's accounts. For this purpose, inspectors count items (e.g. fuel assemblies, bundles or rods, or containers of powdered compounds of uranium or plutonium) and measure attributes of these items during their inspections using non

Guide for the evaluation of physical protection equipment. Book 2: Volumes IV--VIII

International Nuclear Information System (INIS)

Haberman, W.

1977-06-01

A guide for evaluating the performance of commercially available physical protection equipment has been prepared for use by U.S. NRC. Separate evaluation procedures are provided for each generic type of equipment contained in the companion document, Catalog of Physical Protection Equipment (NUREG-0274). Among the equipment parameters evaluated are sensitivity, area/volume of coverage, false/nuisance alarm rate, resistance to countermeasures, environmental requirements, installation parameters and maintenance. Four evaluation techniques are employed (inspections, analyses, demonstrations and tests); standard test equipment (both commercially available as well as developmental) to be used in the evaluation is listed. The following categories of equipment are covered: surveillance and alarm assessment components, contraband detection components, automated response components, general purpose display components, and general purpose communication components

Common floor system vertical earthquake-proof structure for reactor equipment

International Nuclear Information System (INIS)

Morishita, Masaki.

1996-01-01

In an LMFBR type reactor, a reactor container, a recycling pump and a heat exchanger are disposed on a common floor. Vertical earthquake-proof devices which can be stretched only in vertical direction formed by laminating large-sized bellevilles are disposed on a concrete wall at the circumference of each of reactor equipments. A common floor is placed on all of the vertical earthquake-proof devices to support the entire earthquake-proof structure simultaneously. If each of reactor equipments is loaded on the common floor and the common floor is entirely supported against earthquakes altogether, since the movement of each of the reactor equipments loaded on the common floor is identical, relative dislocation is not exerted on the main pipelines which connect the equipments. In addition, since the entire earthquake structure has a flat common floor and each of the reactor equipments is suspended to minimize the distance between a gravitational center and a support point, locking vibration is less caused to the horizontal earthquake. (N.H.)

Choice and maintenance of equipment for electron crystallography.

Science.gov (United States)

Mills, Deryck J; Vonck, Janet

2013-01-01

The choice of equipment for an electron crystallography laboratory will ultimately be determined by the available budget; nevertheless, the ideal lab will have two electron microscopes: a dedicated 300 kV cryo-EM with a field emission gun and a smaller LaB(6) machine for screening. The high-end machine should be equipped with photographic film or a very large CCD or CMOS camera for 2D crystal data collection; the screening microscope needs a mid-size CCD for rapid evaluation of crystal samples. The microscope room installations should provide adequate space and a special environment that puts no restrictions on the collection of high-resolution data. Equipment for specimen preparation includes a carbon coater, glow discharge unit, light microscope, plunge freezer, and liquid nitrogen containers and storage dewars. When photographic film is to be used, additional requirements are a film desiccator, dark room, optical diffractometer, and a film scanner. Having the electron microscopes and ancillary equipment well maintained and always in optimum condition facilitates the production of high-quality data.

Otolaryngology Consult Carts: Maximizing Patient Care, Surgeon Efficiency, and Cost Containment.

Science.gov (United States)

Royer, Mark C; Royer, Allison K

2015-11-01

The objective of this study was to develop an otolaryngology consult cart system to ensure prompt delivery to the bedside of all the unique equipment and medications required for emergent and urgent otolaryngology consults. An otolaryngology practice responsible for emergency room and hospital consult coverage sought to create a cart containing all equipment, medications, and supplies for otolaryngology consults. Meetings with hospital administration and emergency room, nursing, pharmacy, central processing, and operating room staff were held to develop a system for the emergent delivery of the cart to the needed location, sterilization and restocking of equipment between uses, and appropriate billing of supplies. Two months were required from conception to implementation. All equipment was purchased new, including flexible scopes and headlights. The cart is sterilized, restocked, and maintained by central processing after each use. The equipment is available to handle all airway emergencies as well as all common otolaryngology consults and is delivered bedside in less than 5 minutes. The development of a self-contained otolaryngology consult cart requires coordination with a wide variety of hospital departments. This system, while requiring initial monetary and time investment, has resulted in improved patient care, cost containment, and surgeon convenience. © The Author(s) 2015.

Westinghouse radiological containment guide

International Nuclear Information System (INIS)

Aitken, S.B.; Brown, R.L.; Cantrell, J.R.; Wilcox, D.P.

1994-03-01

This document provides uniform guidance for Westinghouse contractors on the implementation of radiological containments. This document reflects standard industry practices and is provided as a guide. The guidance presented herein is consistent with the requirements of the DOE Radiological Control Manual (DOE N 5480.6). This guidance should further serve to enable and encourage the use of containments for contamination control and to accomplish the following: Minimize personnel contamination; Prevent the spread of contamination; Minimize the required use of protective clothing and personal protective equipment; Minimize the generation of waste

Westinghouse radiological containment guide

Energy Technology Data Exchange (ETDEWEB)

Aitken, S.B. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Brown, R.L. [Westinghouse Hanford Co., Richland, WA (United States); Cantrell, J.R. [Westinghouse Savannah River Co., Aiken, SC (United States); Wilcox, D.P. [West Valley Nuclear Services Co., Inc., West Valley, NY (United States)

1994-03-01

This document provides uniform guidance for Westinghouse contractors on the implementation of radiological containments. This document reflects standard industry practices and is provided as a guide. The guidance presented herein is consistent with the requirements of the DOE Radiological Control Manual (DOE N 5480.6). This guidance should further serve to enable and encourage the use of containments for contamination control and to accomplish the following: Minimize personnel contamination; Prevent the spread of contamination; Minimize the required use of protective clothing and personal protective equipment; Minimize the generation of waste.

Equipment for liquid metal pressure measurement

International Nuclear Information System (INIS)

Jung, J.

1977-01-01

Equipment is proposed for measuring liquid metal pressure in piping or a tank. An auxiliary piping is connected to the piping or tank at the measuring point. The auxiliary piping transports liquid metal to a container by means of an electromagnetic pump. The piping also houses an electromagnetic flow ratemeter connected to an electric comparator. The comparator and the electromagnetic pump are connected to the pump output generator. (Z.M.)

Guide for the evaluation of physical protection equipment. Book 1: Volumes I--III

International Nuclear Information System (INIS)

Haberman, W.

1977-06-01

A guide for evaluating the performance of commercially available physical protection equipment has been prepared in partial fulfillment of Task 2 of MITRE contract AT(49-24)-0376 for use by the U.S. Nuclear Regulatory Commission (NRC). Separate evaluation procedures are provided for each generic type of equipment contained in the companion document, Catalog of Physical Protection Equipment. Among the equipment parameters evaluated, as appropriate, are sensitivity, area/volume of coverage, false/nuisance alarm rate, resistance to countermeasures, environmental requirements, installation parameters and maintenance. Four evaluation techniques are employed (inspections, analyses, demonstrations and tests); standard test equipment (both commercially available as well as developmental) to be used in the evaluation are listed

Weapon container catalog. Volumes 1 & 2

Energy Technology Data Exchange (ETDEWEB)

Brown, L.A.; Higuera, M.C.

1998-02-01

The Weapon Container Catalog describes H-gear (shipping and storage containers, bomb hand trucks and the ancillary equipment required for loading) used for weapon programs and for special use containers. When completed, the catalog will contain five volumes. Volume 1 for enduring stockpile programs (B53, B61, B83, W62, W76, W78, W80, W84, W87, and W88) and Volume 2, Special Use Containers, are being released. The catalog is intended as a source of information for weapon program engineers and also provides historical information. The catalog also will be published on the SNL Internal Web and will undergo periodic updates.

Container for liquefied gas

Energy Technology Data Exchange (ETDEWEB)

Short, A J

1967-05-18

Containers for liquefied gases are of double-wall construction with a vacuum between the 2 walls; the upper end of the neck contains a vapor chamber and is equipped with means for withdrawing gas from the container. According to this invention, the vapor chamber is connected to a damping chamber by means of a choke line which has an internal diameter of at least 1.6 mm and a length equal to at least 52 times the diameter. The damping chamber has a volume of at least 5 cu cm and is larger than the outer part of the chamber. The interior length of the damping chamber is at least twice the diameter of the choke line. (5 claims)

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

International Nuclear Information System (INIS)

Mast, J.C.

1994-01-01

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

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

International Nuclear Information System (INIS)

Jech, J.B.

1997-01-01

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

Timing criteria for supplemental BWR emergency response equipment

International Nuclear Information System (INIS)

Bickel, John H.

2015-01-01

The Great Tohuku Earthquake and subsequent Tsunami represented a double failure event which destroyed offsite power connections to Fukushima-Daiichi site and then destroyed on-site electrical systems needed to run decay heat removal systems. The accident could have been mitigated had there been supplemental portable battery chargers, supplemental pumps, and in-place piping connections to provide alternate decay heat removal. In response to this event in the USA, two national response centers, one in Memphis, Tennessee, and another in Phoenix, Arizona, will begin operation. They will be able to dispatch supplemental emergency response equipment to any nuclear plant in the U.S. within 24 hours. In order to define requirements for supplemental nuclear power plant emergency response equipment maintained onsite vs. in a regional support center it is necessary to confirm: (a) the earliest time such equipment might be needed depending on the specific scenario, (b) the nominal time to move the equipment from a storage location either on-site or within the region of a nuclear power plant, and (c) the time required to connect in the supplemental equipment to use it. This paper describes an evaluation process for a BWR-4 with a Mark I Containment starting with: (a) severe accident simulation to define best estimate times available for recovery based on the specific scenario, (b) identify the key supplemental response equipment needed at specific times to accomplish recovery of key safety functions, and (c) evaluate what types of equipment should be warehoused on-site vs. in regional response centers. (authors)

Material Handling Equipment Evaluation for Crater Repair

Science.gov (United States)

2016-11-01

lifting (www.mcneiluscompanies.com). Agricultural/Mechanical Industry. The final equipment solution investigated was a telescoping boom crane (see... crane include: • Trailer-tongue mounting would provide for self-contained lifting capabilities on the simplified volumetric mixer. • Some models are...jib crane could potentially be effective as integrating lifting capabilities with the current simplified volumetric mixer. Both options could be

UF{sub 6} cylinder lifting equipment enhancements

Energy Technology Data Exchange (ETDEWEB)

Hortel, J.M. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States)

1991-12-31

This paper presents numerous enhancements that have been made to the Portsmouth lifting equipment to ensure the safe handling of cylinders containing liquid uranium hexafluoride (UF{sub 6}). The basic approach has been to provide redundancy to all components of the lift path so that any one component failure would not cause the load to drop or cause any undesirable movement.

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

IEEE standard for qualifying class IE equipment for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1974-01-01

The Institute of Electrical and Electrical Engineers, Inc. (IEEE) standards for electrical equipment (Class IE) for nuclear power generating stations are given. The standards are to provide guidance for demonstrating and documenting the adequacy of electric equipment used in all Class IE and interface systems. Representative in containment design basis event conditions for the principal reactor types are included in the appendixes for guidance in enviromental simulation

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

Aspects of safety assessments for package with additional equipment components

International Nuclear Information System (INIS)

Reiche, I.; Boerst, F.M.; Krietsch, T.

2004-01-01

Many paragraphs in TS-R-1 contain the terms ''package'' or ''packaging''. These terms are defined in TS-R-1 paras 230 and 231 and explained in TS-G-1.1 paras 230.1 - 230.6. The importance of a consistent understanding of these definitions has been shown by recent discussions during the assessment of applications for package design approval. There was disagreement, if equipment components attached to the container body during transport, e.g. a transport frame, should be considered part of the package and taken into account in the safety assessment for the package. Discussions were also caused by the way inner design components are treated in the safety assessment of the package. This paper summarises the regulatory requirements to such additional equipment components and presents the way of their inclusion into the package design approval process in Germany

JCE Online: Equipment Buyers Guide

Science.gov (United States)

Holmes, Jon L.

1999-01-01

The Equipment Buyers Guide was edited by Jo Rita Jordan. The new Equipment Buyers Guide, bound into the back of this issue, is also a new resource of JCE Internet. This resource provides an online source for the information contained in the printed guide. Placing this information online allows us to regularly update it and to provide live links to the suppliers' WWW sites. The organization of the online version parallels that of the print version. There is an alphabetical list of suppliers and a categorical listing. Links to these lists are provided on every page in the left-hand navigation bar. To quickly find information about a particular supplier, you click Supplier List, click the letter that begins the supplier's name, and scroll through the list to find the supplier. To find which suppliers provide a particular type of instrument or equipment, use the Categories link; click the category of the equipment you are looking for and then click the link to a supplier. You will then be taken to an alphabetical supplier listing page where you can scroll until you find the particular supplier of the item for which you are looking. Once you have found a supplier, the online Equipment Buyers Guide gives you the traditional contact information. But in addition, you also get one-click access to the WWW sites of the suppliers that have them. Depending on the site, you should be able to find information about the items that you seek and may even be able to order the items online! We think that you will find the online version of the Equipment Buyers Guide useful. To make it more useful, please send your suggestions, any errors or omissions you find, and any additional categories to the editor at jjordan@world.std.com The online Equipment Buyers Guide can be found at JCE Online at http://JChemEd.chem.wisc.edu/JCEWWW/Resources/EBG/ JCE Online in '99 JCE Online is your online source of "all things JCE". In order to provide you with an even more useful online resource, JCE

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 ...

Code of Practice for Protection Against Ionizing Radiation Emitted from X-ray Analysis Equipment (1984)

International Nuclear Information System (INIS)

1984-01-01

Appropriate working rules, safety features and monitoring requirements for general X-ray analysis units or equipment are laid down in this Code which is intended for users of such equipment. The Code advises that establishments draw up their own working procedures based on appropriate legislation and on the recommendations contained in this Code. The Code also describes the requirements for X-ray analysis equipment necessary to ensure safety. (NEA) [fr

Recommended practices and guidelines for procurement of magnetic-fusion-energy electrical equipment

International Nuclear Information System (INIS)

1982-06-01

The followng three chapters are included: (1) administrative guidelines, (2) technical practices, and (3) check list. The first two chapters contain detailed information which is to be used as a reference by specification writers in preparing specifications. Chapter 3 is intended to provide a uniform specification format for specification writers, and is further intended to satisfy equipment manufactures' complaints that different specification formats are used to describe essentially identical 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

42 CFR 84.117 - Gas mask containers; minimum requirements.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Gas mask containers; minimum requirements. 84.117... SAFETY AND HEALTH RESEARCH AND RELATED ACTIVITIES APPROVAL OF RESPIRATORY PROTECTIVE DEVICES Gas Masks § 84.117 Gas mask containers; minimum requirements. (a) Gas masks shall be equipped with a substantial...

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.

Research on U.S. nuclear power plant major equipment aging

International Nuclear Information System (INIS)

Nakos, J.T.; Rosinski, S.T.

1994-01-01

The U.S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI), in cooperation with nuclear power plant utilities and the Nuclear Energy Institute, have prepared equipment aging evaluations of nuclear power plant equipment for life extension considerations. Specifically, these evaluations focused on equipment considered important for plant license renewal (U.S. Code of Federal Regulations 10CFR54). open-quotes Industry Reportsclose quotes (IRs), jointly funded by DOE and EPRI, evaluated the aging of major systems, structures, and components (e.g., reactor pressure vessels, Class I structures, PWR and BWR containments, etc.) and contain a mixture of technical and licensing information. open-quotes Aging Management Guidelinesclose quotes (AMGs), funded by DOE, evaluate aging for commodity types of equipment (e.g., pumps, electrical switchgear, heat exchangers, etc.) and concentrate on technical issues only. AMGs are intended for systems engineers and plant maintenance staff. A significant number of technical issues were resolved during IR interactions with the U.S. Nuclear Regulatory Commission (NRC). However, certain technical issues have not been resolved and are considered open-quotes openclose quotes. Examples include certain issues related to fatigue, neutron irradiation embrittlement, intergranular stress corrosion cracking (IGSCC) and electrical cable equipment qualification. Direct NRC interaction did not take place during preparation of individual AMGs due to their purely technical nature. The eventual use of AMGs in a future license renewal application will likely require NRC interaction at that time. With a few noted exceptions, the AMG process indicated that current aging management practices of U.S. utilities were effective in preventing age-related degradation. This paper briefly describes the IR and AMG processes and summarizes the unresolved technical issues identified through preparation of the documents

Power Product Equipment Technician: Outboard-Engine Boat Systems. Teacher Edition [and] Student Edition.

Science.gov (United States)

Hilley, Robert

This curriculum guide contains teacher and student materials for a course on outboard-engine boat systems for power product equipment technician occupations. The course contains the following three units of instruction: (1) Orientation to Outboard-Engine Boat Systems and Rigging; (2) Trailers and Safe Towing and Boat Operation; and (3) Seasonal…

Research on the organization of equipment of nuclear emergency

International Nuclear Information System (INIS)

Li Xiaoming; Yang Jun

2012-01-01

The emergency rescue operation on major accident of nuclear facilities contains four kinds of abilities that are command and control, radiation protection, radiation monitoring and radioactive decontamination, so it needs to organize some equipment of nuclear emergency to enhance the efficiency of nuclear emergency operation. The organization of equipment of nuclear emergency should accord to the reality of the development in our country. It should have extractive structure, brief variety and advance capability, and also should be convenient, useful and adequate. The method of organization can first accord to the organization of group and organize the facilities accord to the organization of group of the emergency rescue force. (authors)

Containment and surveillance techniques at power reactors

International Nuclear Information System (INIS)

Stirling, A.J.

1982-01-01

This session will provide participants with an understanding of the functions of safeguards equipment at power reactors, including equipment for fuel accounting, video and film surveillance, diversion monitoring, and containment and surveillance of irradiated fuel in storage. In addition, some appreciation of the impact that reactor safeguards have on the plant operator will be gained. From this, participants will be able to ensure that a reactor safeguards system meets their nation's international and national nonproliferation objectives with a minimum of interference to plant operations

Overview of Mobile Equipment Used in Case of Beyond Design Basis Accident at NPP Krsko

International Nuclear Information System (INIS)

Lukacevic, H.; Kopinc, D.; Ivanjko, M.

2016-01-01

Terrorist attack in USA in the September 11, 2001 and accident at the Fukushima - Daiichi Nuclear Power Station in the March 11, 2011 highlight the importance of mitigating strategies in responding to Beyond Design Basis Accident (BDBA), while ensuring cooling of reactor core, containment and spent fuel pool. Nuclear Power Plant Krsko (NEK) has acquired additional mobile equipment and made necessary modifications on existing systems for the connection of this equipment (fast couplers). Usage of mobile equipment is not only limited to design basis accident (DBA), but, also to prevent and mitigate the consequences in case of BDBA, when other plant systems are not available. NEK also decided to take steps for upgrade of safety measures and prepared Safety Upgrade Program (SUP), which is consistent with the nuclear industry response to the Fukushima accident and is implementing main projects and modifications related to SUP. NEK mobile equipment is not required to operate under normal reactor plant operation except for periodic surveillance testing and is incorporated into the normal training process. Equipment is dislocated from the reactor building and most of the equipment is located in the new building, able to withstand extreme natural events, including earthquakes and tornadoes. The usage of all mobile equipment is prescribed as an additional option in NEK operating procedures in following cases and enables following options: filling various tanks, filling the steam generators, filling the containment, additional compressed air source, spent fuel pool refilling and spraying, alternative power supply. This document provides an overview of NEK mobile equipment, which consists of various mobile fire protection pumps, air compressors, protective equipment, fire trucks, diesel generators. Sufficient fuel supply for the equipment is provided on site for a minimum three days of operation. (author).

Damages of industrial equipments in the 1995 Hyougoken-Nanbu Earthquake

International Nuclear Information System (INIS)

Iwatsubo, Takuzo

1997-01-01

Hanshin-Awaji area has a population of approximately 3 million and many industries, including heavy industry, harbor facilities and international trading companies. The 1995 Hyougoken-Nanbu Earthquake occurred just in this area which is 25kmx2km oblong containing Kobe city. About 5,500 people were killed and 250,000 people lost their houses. Japan society of mechanical engineers organized the investigative committee of earthquake disaster of industrial equipments after the earthquake in order to investigate the disaster damages of industrial equipments and to give data for a design manual for mechanical equipments against earthquake excitation. This is an investigation report of the disaster damages of industrial machine equipments. Damages to machine equipment of industries in the high intensity region of the earthquake are illustrated. The mechanisms of the damages and measures against earthquake and safety of nuclear power plant design are discussed. Then it is known that the design of nuclear power plant is different from the general industrial facilities and the damage which was suffered in the general industrial facilities does not occur in the nuclear power plant. (J.P.N.)

Damages of industrial equipments in the 1995 Hyougoken-Nanbu Earthquake

Energy Technology Data Exchange (ETDEWEB)

Iwatsubo, Takuzo [Kobe Univ. (Japan). Faculty of Engineering

1997-03-01

Hanshin-Awaji area has a population of approximately 3 million and many industries, including heavy industry, harbor facilities and international trading companies. The 1995 Hyougoken-Nanbu Earthquake occurred just in this area which is 25kmx2km oblong containing Kobe city. About 5,500 people were killed and 250,000 people lost their houses. Japan society of mechanical engineers organized the investigative committee of earthquake disaster of industrial equipments after the earthquake in order to investigate the disaster damages of industrial equipments and to give data for a design manual for mechanical equipments against earthquake excitation. This is an investigation report of the disaster damages of industrial machine equipments. Damages to machine equipment of industries in the high intensity region of the earthquake are illustrated. The mechanisms of the damages and measures against earthquake and safety of nuclear power plant design are discussed. Then it is known that the design of nuclear power plant is different from the general industrial facilities and the damage which was suffered in the general industrial facilities does not occur in the nuclear power plant. (J.P.N.)

Impact of Vial Capping on Residual Seal Force and Container Closure Integrity.

Science.gov (United States)

Mathaes, Roman; Mahler, Hanns-Christian; Roggo, Yves; Ovadia, Robert; Lam, Philippe; Stauch, Oliver; Vogt, Martin; Roehl, Holger; Huwyler, Joerg; Mohl, Silke; Streubel, Alexander

2016-01-01

The vial capping process is a critical unit operation during drug product manufacturing, as it could possibly generate cosmetic defects or even affect container closure integrity. Yet there is significant variability in capping equipment and processes, and their relation to potential defects or container closure integrity has not been thoroughly studied. In this study we applied several methods-residual seal force tester, a self-developed system of a piezo force sensor measurement, and computed tomography-to characterize different container closure system combinations that had been sealed using different capping process parameter settings. Additionally, container closure integrity of these samples was measured using helium leakage (physical container closure integrity) and compared to characterization data. The different capping equipment settings lead to residual seal force values from 7 to 115 N. High residual seal force values were achieved with high capping pre-compression force and a short distance between the capping plate and plunge. The choice of container closure system influenced the obtained residual seal force values. The residual seal force tester and piezoelectric measurements showed similar trends. All vials passed physical container closure integrity testing, and no stopper rupture was seen with any of the settings applied, suggesting that container closure integrity was warranted for the studied container closure system with the chosen capping setting ranges. The vial capping process is a critical unit operation during drug product manufacturing, as it could possibly generate cosmetic defects or even affect container closure integrity. Yet there is significant variability in capping equipment and processes, and their relation to potential defects or container closure integrity has not been thoroughly studied. In this study we applied several methods-residual seal force tester, a self-developed system of a piezo force sensor measurement, and

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

Radiological security of portable equipment used in the industry

International Nuclear Information System (INIS)

Cateriano, M.A.

2006-01-01

The industrial meters with encapsulated sources are used intensely in the present time due to the economic benefits that generate. Their use in all the one world has been reflected in an improvement of the quality of the analyzed product and of one optimization of the production process, allowing to carry out these measurements and controls without interrupting the process and in non destructive form generating an energy saving in turn and of materials. Although these industrial meters are intrinsically safe for design in the portable meters their safety also is strongly governed in the strict pursuit of procedures and in the adequate personnel's training that operate these equipment. In the Argentine Republic in 2005 the Nuclear Regulatory Authority (RNA) had registered a quantity of 160 portable equipment. In the period 1995-2003, 2 incidents took place with these equipment one of them used to measure soils humidity of Troxler trademark containing a source of Am-241(Be) of 370 MBq and the remaining one also of Troxler trademark used to measure density and humidity of soils containing 2 sources of Cs-137 of 296 MBq and Am-241(Be) of 1.48 GBq respectively. The incidents were developed without relevant radiological implications had taken place. In this work those mentioned incidents are analyzed in order to determining the causes that originated the same ones, for this way to be able to elaborate recommendations with the purpose of to correct errors and to diminish the recurrence probability improving the safety in the use of these equipment. From the analyses of these incidents result that should put on more emphasis in the personnel training and the invigoration of the safety culture in the use of the industrial meters. Also a present panorama of the inventory of equipment, sources and users that possess these portable meters in the Argentine Republic is also presented. (Author)

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.

Costs and indices for domestic oil and gas field equipment and production operations 1990 through 1993

Energy Technology Data Exchange (ETDEWEB)

1994-07-08

This report presents estimated costs and indice for domestic oil and gas field equipment and production operations for 1990, 1991, 1992, and 1993. The costs of all equipment and serives were those in effect during June of each year. The sums (aggregates) of the costs for representative leases by region, depth, and production rate were averaged and indexed. This provides a general measure of the increased or decreased costs from year to year for lease equipment and operations. These general measures do not capture changes in industry-wide costs exactly because of annual variations in the ratio of oil wells to gas wells. The body of the report contains summary tables, and the appendices contain detailed tables. Price changes for oil and gas, changes in taxes on oil and gas revenues, and environmental factors (costs and lease availability) have significant impact on the number and cost of oil and gas wells drilled. These changes also impact the cost of oil and gas production equipment and operations.

Costs and indices for domestic oil and gas field equipment and production operations 1990 through 1993

International Nuclear Information System (INIS)

1994-01-01

This report presents estimated costs and indice for domestic oil and gas field equipment and production operations for 1990, 1991, 1992, and 1993. The costs of all equipment and serives were those in effect during June of each year. The sums (aggregates) of the costs for representative leases by region, depth, and production rate were averaged and indexed. This provides a general measure of the increased or decreased costs from year to year for lease equipment and operations. These general measures do not capture changes in industry-wide costs exactly because of annual variations in the ratio of oil wells to gas wells. The body of the report contains summary tables, and the appendices contain detailed tables. Price changes for oil and gas, changes in taxes on oil and gas revenues, and environmental factors (costs and lease availability) have significant impact on the number and cost of oil and gas wells drilled. These changes also impact the cost of oil and gas production equipment and operations

The equipment for low radioactivity measurements in industrial and field conditions

International Nuclear Information System (INIS)

Malik, R.; Owczarczyk, A.; Szpilowski, S.; Zenczykiewicz, Z.

1992-01-01

The equipment for low radioactivity measurements in industrial and field conditions has been worked out. Three scintillation detectors applied work in coincidence system. Their scintillation crystals are divided one to another by lead shieldings. All measuring system is situated in a lead container with lead cover. The measuring vessel fills practically all free volume of the lead container. Their shape ensures the best possible measurement geometry. (author). 3 figs

Urgent reconstruction and re-equipping of coking plants

Energy Technology Data Exchange (ETDEWEB)

Kvitkin, I.A.; Martynenko, V.M.; Rozenfel' d, M.S.; Svyatogorov, A.A.; Shvartsman, I.G.

1986-03-01

This paper discusses the various options involved: complete or partial reconstruction of existing buildings and equipment or new construction with new equipment and new underground and surface communications. It explains that reconstruction work is divided into three phases: initial phase (clearance, dismantling, closing down coking batteries); basic phase (fitting heat-resistant materials, prestart-up assembly work); final phase (drying out, heating up, adjustments, start-up). A structured scheme for a typical initial phase is described and a method of calculating the durations of the various phases is discussed. Conclusion is that there is an urgent requirement for a document to be produced for the control of reconstruction work; it should contain standard durations and could serve as a standard for coking plant reconstruction work.

Optimal facility and equipment specification to support cost-effective recycling

International Nuclear Information System (INIS)

Redus, K.S.; Yuracko, K.L.

1998-01-01

The authors demonstrate a project management approach for D and D projects to select those facility areas or equipment systems on which to concentrate resources so that project materials disposition costs are minimized, safety requirements are always met, recycle and reuse goals are achieved, and programmatic or stakeholder concerns are met. The authors examine a facility that contains realistic areas and equipment, and they apply the approach to illustrate the different results that can be obtained depending on the strength or weakness of safety risk requirements, goals for recycle and reuse of materials, and programmatic or stakeholder concerns

Evaluation of an air drilling cuttings containment system

Energy Technology Data Exchange (ETDEWEB)

Westmoreland, J.

1994-04-01

Drilling at hazardous waste sites for environmental remediation or monitoring requires containment of all drilling fluids and cuttings to protect personnel and the environment. At many sites, air drilling techniques have advantages over other drilling methods, requiring effective filtering and containment of the return air/cuttings stream. A study of. current containment methods indicated improvements could be made in the filtering of radionuclides and volatile organic compounds, and in equipment like alarms, instrumentation or pressure safety features. Sandia National Laboratories, Dept. 61 11 Environmental Drilling Projects Group, initiated this work to address these concerns. A look at the industry showed that asbestos abatement equipment could be adapted for containment and filtration of air drilling returns. An industry manufacturer was selected to build a prototype machine. The machine was leased and put through a six-month testing and evaluation period at Sandia National Laboratories. Various materials were vacuumed and filtered with the machine during this time. In addition, it was used in an actual air drive drilling operation. Results of these tests indicate that the vacuum/filter unit will meet or exceed our drilling requirements. This vacuum/filter unit could be employed at a hazardous waste site or any site where drilling operations require cuttings and air containment.

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

Costs and indices for domestic oil and gas field equipment and production operations, 1992--1995

International Nuclear Information System (INIS)

1996-08-01

This report presents estimated costs and cost indices for domestic oil and natural gas field equipment and production operations for 1992, 1993, 1994, and 1995. The costs of all equipment and services are those in effect during June of each year. The sum (aggregates) of the costs for representative leases by region, depth, and production rate were averaged and indexed. This provides a general measure of the increased or decreased costs from year to year for lease equipment and operations. These general measured do not capture changes in industry-wide costs exactly because of annual variations in the ratio of the total number of oil wells to the total number of gas wells. The detail provided in this report is unavailable elsewhere. The body of this report contains summary tables, and the appendices contain detailed tables

Productivity simulation model for optimization of maritime container terminals

Directory of Open Access Journals (Sweden)

Elen TWRDY

2009-01-01

Full Text Available This article describes a proposed productivity simulation model enabling container terminal operators to find optimization possibilities. A research of more than forty terminals has been done, in order to provide a helping tool for maritime container terminals. By applying an adequate simulation model, it is possible to measure and increase the productivity in all subsystem of the maritime container terminal. Management of a maritime container terminal includes a vast number of different financial and operational decisions. Financial decisions are often in a direct connection with investments in infrastructure and handling equipment. Such investments are very expensive. Therefore, they must give back the invested money as soon as possible. On the other hand, some terminals are limited by the physical extension and are forced to increase annual throughput only with sophisticated equipment on the berth side and on the yard as well. Considering all these important facts in container and shipping industry, the proposed simulation model gives a helping tool for checking the productivity and its time variation and monitoring competitiveness of a certain maritime terminal with terminals from the same group.

Simulated E-Bomb Effects on Electronically Equipped Targets

Science.gov (United States)

2009-09-01

This enclosing metal barrier, called Faraday Cage , prevents the effect of electromagnetic field interference to the sensitive equipment (Deveci, 2007...utilization of fiber optic cables, which contain no conductive metal , can also reduce the effect of high power microwave weapon. High power microwave...Finally, the modeled results and the two described threshold effect reference data values will be compared and demonstrated to conclude what kind of

Dynamic tension testing equipment for paperboard and corrugated fiberboard

Science.gov (United States)

W. D. Godshall

1965-01-01

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

Power Product Equipment Technician: Outboard-Engine Systems and Service. Teacher Edition [and] Student Edition.

Science.gov (United States)

Hilley, Robert

This curriculum guide contains teacher and student materials for a course on outboard-engine boat systems and service for power product equipment technician occupations. The course contains the following four units of instruction: (1) Outboard-Engine Design and Identification; (2) Operation and Service of Engine-Support Systems; (3) Operation and…

Pocket dictionary of laboratory equipment. English/German. Taschenwoerterbuch Laborausruestung. Deutsch/Englisch

Energy Technology Data Exchange (ETDEWEB)

Junge, H D

1987-01-01

This pocket dictionary contains the 2500 most common terms for scientific and technical equipment in chemical laboratories. It is a useful tool for those who are used to communicating in German and English, but have to learn the special terminology in this field.

Optimising waste from electric and electronic equipment collection systems: a comparison of approaches in European countries.

Science.gov (United States)

Friege, Henning; Oberdörfer, Michael; Günther, Marko

2015-03-01

The first European waste from electric and electronic equipment directive obliged the Member States to collect 4 kg of used devices per inhabitant and year. The target of the amended directive focuses on the ratio between the amount of waste from electric and electronic equipment collected and the mass of electric and electronic devices put on the market in the three foregoing years. The minimum collection target is 45% starting in 2016, being increased to 65% in 2019 or alternatively 85% of waste from electric and electronic equipment generated. Being aware of the new target, the question arises how Member States with 'best practice' organise their collection systems and how they enforce the parties in this playing field. Therefore the waste from electric and electronic equipment schemes of Sweden, Denmark, Switzerland, Germany and the Flemish region of Belgium were investigated focusing on the categories IT and telecommunications equipment, consumer equipment like audio systems and discharge lamps containing hazardous substances, e.g. mercury. The systems for waste from electric and electronic equipment collection in these countries vary considerably. Recycling yards turned out to be the backbone of waste from electric and electronic equipment collection in most countries studied. For discharge lamps, take-back by retailers seems to be more important. Sampling points like special containers in shopping centres, lidded waste bins and complementary return of used devices in all retail shops for electric equipment may serve as supplements. High transparency of collection and recycling efforts can encourage ambition among the concerned parties. Though the results from the study cannot be transferred in a simplistic manner, they serve as an indication for best practice methods for waste from electric and electronic equipment collection. © The Author(s) 2015.

Method of Data storing, collection and aggregation for definition of life-cycle resources of electromechanical equipment

Science.gov (United States)

Zhukovskiy, Y.; Koteleva, N.

2017-10-01

Analysis of technical and technological conditions for the emergence of emergency situations during the operation of electromechanical equipment of enterprises of the mineral and raw materials complex shows that when developing the basis for ensuring safe operation, it is necessary to take into account not only the technical condition, but also the non-stationary operation of the operating conditions of equipment, and the nonstationarity of operational operating parameters of technological processes. Violations of the operation of individual parts of the machine, not detected in time, can lead to severe accidents at work, as well as to unplanned downtime and loss of profits. That is why, the issues of obtaining and processing Big data obtained during the life cycle of electromechanical equipment, for assessing the current state of the electromechanical equipment used, timely diagnostics of emergency and pre-emergency modes of its operation, estimating the residual resource, as well as prediction the technical state on the basis of machine learning are very important. This article is dedicated to developing the special method of data storing, collection and aggregation for definition of life-cycle resources of electromechanical equipment. This method can be used in working with big data and can allow extracting the knowledge from different data types: the plants’ historical data and the factory historical data. The data of the plants contains the information about electromechanical equipment operation and the data of the factory contains the information about a production of electromechanical equipment.

Waste Handling Equipment Development Test and Evaluation Study

International Nuclear Information System (INIS)

R.L. Tome

1998-01-01

planned and conducted by the appropriate design organization as part of the design process. The scope of this study, therefore, will address only surface development testing activities that will be performed prior to detail design and procurement of the MGR surface waste handling equipment. Testing to support development of additional MGR surface equipment and operations, such as cooling of shipping casks and dual-purpose canisters (DPCs) prior to pool entry, decontamination of disposal containers (DCs), and recovery systems for various equipment, is not addressed in this study. These equipment items/systems were not developed for VA and are not currently identified as specific MGR surface waste handling equipment

Justification for Selecting Level A vs. Level B Personal Protective Equipment to Remediate a Room Containing Concentrated Acids, Bases and Radiological Constituents

International Nuclear Information System (INIS)

Hylko, J. M.; Thompson, A. L.; Walter, J. F.; Deecke, T. A.

2002-01-01

Selecting the appropriate personal protective equipment (PPE) is based on providing an adequate level of employee protection relative to the task-specific conditions and hazards. PPE is categorized into four ensembles, based on the degree of protection afforded; e.g., Levels A (most restrictive), B, C, and D (least restrictive). What is often overlooked in preparing an ensemble is that the PPE itself can create significant worker hazards; i.e., the greater the level of PPE, the greater the associated risks. Furthermore, there is confusion as to whether a more ''conservative approach'' should always be taken since Level B provides the same level of respiratory protection as Level A but less skin protection. This paper summarizes the Occupational Safety and Health Administration regulations addressing Level A versus Level B, and provides justification for selecting Level B over Level A without under-protecting the employee during a particular remediation scenario. The scenario consisted of an entry team performing (1) an initial entry into a room containing concentrated acids (e.g., hydrofluoric acid), bases, and radiological constituents; (2) sampling and characterizing container contents; and (3) retrieving characterized containers. The invasive nature of the hydrofluoric acid sampling and characterization scenario created a high potential for splash, immersion, and exposure to hazardous vapors, requiring additional skin protection. The hazards associated with this scenario and the chemical nature of hydrofluoric acid provided qualitative evidence to justify Level A. Once the hydrofluoric acid was removed from the room, PPE performance was evaluated against the remaining chemical inventory. If chemical breakthrough from direct contact was not expected to occur and instrument readings confirmed the absence of any hazardous vapors, additional skin protection afforded by wearing a vapor-tight, totally-encapsulated suit was not required. Therefore, PPE performance and

A DDC Bibliography on Microfiche, Microfilm and Related Equipment, Volume 1.

Science.gov (United States)

Defense Documentation Center, Alexandria, VA.

This bibliography contains abstracts of 40 unclassified-unlimited reports on microfiche, microfilm and related equipment acquired by the Defense Documentation Center since 1953. Citations are topically arranged in AD sequence, ascending order. The following computer produced indexes are provided: subject, corporate author, personal author,…

RETRIEVAL EQUIPMENT DESCRIPTIONS

International Nuclear Information System (INIS)

J. Steinhoff

1997-01-01

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

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

Remotely controlled large container disposal methodology

International Nuclear Information System (INIS)

Amir, S.J.

1994-09-01

Remotely Handled Large Containers (RHLC), also called drag-off boxes, have been used at the Hanford Site since the 1940s to dispose of large pieces of radioactively contaminated equipment. These containers are typically large steel-reinforced concrete boxes, which weigh as much as 40 tons. Because large quantities of high-dose waste can produce radiation levels as high as 200 mrem/hour at 200 ft, the containers are remotely handled (either lifted off the railcar by crane or dragged off with a cable). Many of the existing containers do not meet existing structural and safety design criteria and some of the transportation requirements. The drag-off method of pulling the box off the railcar using a cable and a tractor is also not considered a safe operation, especially in view of past mishaps

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

Characterisation of vibration equipment used for the immobilisation of solid items in cement grout

International Nuclear Information System (INIS)

Dalton, M.J.

1984-12-01

Processes are being developed at AEE Winfrith for the immobilisation of solid radioactive waste in cement grouts. The flow of grout during the infilling stage is assisted by vibration of the waste container. A high resolution signal analyser has been used to measure the operating frequency and amplitude characteristics of vibrating equipment used in the solid immobilisation process. In this report the commissioning of the instrument and results obtained on the equipment are described. (author)

Safety/relief valve quencher loads: evaluation for BWR Mark II and III containments

International Nuclear Information System (INIS)

Su, T.M.

1982-10-01

Boiling water reactor (BWR) plants are equipped with safety/relief valves (SRVs) to protect the reactor from overpressurization. Plant operational transients, such as turbine trips, will actuate the SRV. Once the SRV opens, the air column within the partially submerged discharge line is compressed by the high-pressure steam released from the reactor. The compressed air discharged into the suppression pool produces high-pressure bubbles. Oscillatory expansion and contraction of these bubbles create hydrodynamic loads on the containment structures, piping, and equipment inside containment. This report presents the results of the staff's evaluation of SRV loads. The evaluation, however, is limited to the quencher devices used in Mark II and III containments. With respect to Mark I containments, the SRV acceptance criteria are presented in NUREG-0661 issued July 1980. The staff acceptance criteria for SRV loads for Mark II and III containments are presented in this report

Report on equipment availability for the ten-year period, 1966--1975

Energy Technology Data Exchange (ETDEWEB)

1976-12-01

This is an annual report of availability and outage statistics for electric power generating facilities operating in the United States. A list of utility organizations voluntarily participating in the EEI Equipment Availability Program in 1975 is located in Appendix F. All summary reports in this publication are for the 10-year period 1966-1975. Each reporting utility company has received reports on individual units for which data were submitted. Also, selected major equipment manufacturers receive copies of computer reports showing an analysis of the data for their equipment. Revised reporting instructions to incorporate Safety and Environmental Requirement Cause Codes were issued effective January 1, 1976. In addition, provisions were made for identifying major equipment manufactured outisde of the United States or under foreign license. Recognizing that an Annual Report contains only a limited amount of general outage data in selected categories, the Task Force has agreed to perform special analyses of the data bank if the cost of computer services is met by the requestor and if the required analysis conforms to some designated policy guidelines.

Development of instrumentation systems for severe accidents. 4. New accident tolerant in-containment pressure transducer for containment pressure monitoring system

International Nuclear Information System (INIS)

Oba, Masato; Teruya, Kuniyuki; Yoshitsugu, Makoto; Ikeuchi, Takeshi

2015-01-01

The accident at Tokyo Electric Power Company's Fukushima Dai-ichi Nuclear Power Plant (TF-1 accident) caused severe situations and resulted in a difficulty in measuring important parameters for monitoring plant conditions. Therefore, we have studied the TF-1 accident to select the important parameters that should be monitored at the severe accident and are developing the Severe Accident Instrumentations and Monitoring Systems that could measure the parameters in severe accident conditions. Mitsubishi Heavy Industries, LTD (MHI) developed a new accident tolerant containment pressure monitoring system and demonstrated that the monitoring system could endure extremely harsh environmental conditions that envelop severe accident environmental conditions inside a containment such as maximum operating temperature of up to 300degC and total integrated dose (TID) of 1 MGy gamma. The new containment pressure monitoring system comprises of a strain gage type pressure transducer and a mineral insulated (MI) cable with ceramic connectors, which are located in the containment, and a strain measuring amplifier located outside the containment. Less thermal and radiation degradation is achieved because of minimizing use of organic materials for in-containment equipment such as the transducer and connectors. Several tests were performed to demonstrate the performance and capability of the in-containment equipment under severe accident environmental conditions and the major steps in this testing were run in the following test sequences: (1) the baseline functional tests (e.g., repeatability, non-linearity, hysteresis, and so on) under normal conditions, (2) accident radiation testing, (3) seismic testing, and (4) steam/temperature test exposed to simulated severe accident environmental conditions. The test results demonstrate that the new pressure transducer can endure the simulated severe accident conditions. (author)

Design for a Remote Monitoring Equipment of Krypton-85

Institute of Scientific and Technical Information of China (English)

LUXue-sheng; LIUGuo-rong; YEFeng; JINHui-min; TANGPei-jia

2003-01-01

A prototype equipment for monitoring Krypton-85 in situ is designed and set up. A series of relevant software is also developed for remote control, data acquirement and data analysis. Weight of the system is about 300 kg, which is composed of NaI(T1) detector, digi DART, Marillin measurement container and lead shield. The whole system is placed on a homemade go-cart.

Device for protecting the containment vessel dome of a nuclear reactor

International Nuclear Information System (INIS)

Allain, A.; Filloleau, E.; Mulot, P.

1976-01-01

A device is disclosed for protecting the dome of a nuclear reactor containment vessel against the upward displacement of the concrete shield slab of said reactor and the resultant effects of tilting of an equipment unit mounted on the shield slab at the periphery of said slab, wherein said device comprises: (1) means for separating the equipment unit into two sections consisting of an upper section and a lower section, said lower section being rigidly fixed to said shield slab and said means being actuated by the upward displacement of said slab, (2) a system for vertical rectilinear guiding of said upper section within the containment vessel, and (3) rigid mechanical components which provide a coupling between the aforesaid upper and lower sections of the equipment unit and exert on said upper section under the action of the tilting motion of said lower section a thrust which causes the upward displacement of said upper section

A multi-criteria decision making approach for the selection of a flexible packaging equipment

Directory of Open Access Journals (Sweden)

Cristea Ciprian

2017-01-01

Full Text Available Flexible packaging is one of the fastest growing segments of the packaging industry, combining paper, plastic film and aluminum foil to deliver a broad array of products for food and beverage, personal care products, and pharmaceutical industries. In order to preserve the quality and safety of the product contained in them, there are currently a variety of flexible packaging equipment options available. However their relative costs and performance differ. This study proposes an application of a ranking methodology to assess a selection of the most suitable flexible packaging equipment. The adequate criteria in the selection of equipment have been identified, and the considered options are assessed, considering the decision maker’s preferences and existing constraints. The options are ranked in terms of their suitability for selecting equipment by using the Electre III method. The results obtained from the simulation experiment highlight the effectiveness of the model in outranking different options in the process of equipment selection.

Industry sector analysis, Mexico: Electric power production and distribution equipment. Export Trade Information

International Nuclear Information System (INIS)

Wood, J.S.; Miller, R.W.

1988-09-01

The Industry Sector Analyses (I.S.A.) for electric power production and distribution equipment contains statistical and narrative information on projected market demand, end-users, receptivity of Mexican consumers to U.S. products, the competitive situation - Mexican production, total import market, U.S. market position, foreign competition, and competitive factors, and market access - Mexican tariffs, non-tariff barriers, standards, taxes and distribution channels. The I.S.A. provides the United States industry with meaningful information regarding the Mexican market for electric power production and distribution equipment

Availability of emergency drugs and equipment in general and specialist dental settings in Babol, Iran.

Science.gov (United States)

Mehdizadeh, Mohammad; Nosrati, Kamran; Hamzeh, Mahtab

2014-11-01

Medical emergencies can frequently happen in dental settings and it is critical to outfit the clinic by emergency drugs and equipment. The aim of this study was to evaluate the emergency drugs and equipment in general and specialist dental settings in Babol, Iran. A questionnaire containing closed ended questions about the available emergency drugs and equipment was used in this descriptive-analytical study. Data were subjected to descriptive analysis using SPSS 18.0 to identify the most frequent drugs and equipment. Chi-square and t-test were used to evaluate the correlation between the variables. p < 0.05 was considered statistically significant. One hundred and twelve dentists answered the questionnaire. The most available drug and equipment were epinephrine (67%) and single use syringe (81.3%) respectively. Significant correlation was found between degree of education and availability of first group of emergency drugs and between sex and possession of second group of emergency equipment (p < 0.05). Degree of availability of emergency drugs and equipment was moderate to low and training about emergencies should be included in the didactic topics of universities and workshops. Information about emergency drug and equipment would help to manage the unwanted emergency situations.

A Model of Intelligent Fault Diagnosis of Power Equipment Based on CBR

Directory of Open Access Journals (Sweden)

Gang Ma

2015-01-01

Full Text Available Nowadays the demand of power supply reliability has been strongly increased as the development within power industry grows rapidly. Nevertheless such large demand requires substantial power grid to sustain. Therefore power equipment’s running and testing data which contains vast information underpins online monitoring and fault diagnosis to finally achieve state maintenance. In this paper, an intelligent fault diagnosis model for power equipment based on case-based reasoning (IFDCBR will be proposed. The model intends to discover the potential rules of equipment fault by data mining. The intelligent model constructs a condition case base of equipment by analyzing the following four categories of data: online recording data, history data, basic test data, and environmental data. SVM regression analysis was also applied in mining the case base so as to further establish the equipment condition fingerprint. The running data of equipment can be diagnosed by such condition fingerprint to detect whether there is a fault or not. Finally, this paper verifies the intelligent model and three-ratio method based on a set of practical data. The resulting research demonstrates that this intelligent model is more effective and accurate in fault diagnosis.

Application and issues of online maintenance for equipment of nuclear power plants

International Nuclear Information System (INIS)

Higasa, Hisakazu

2011-01-01

The maintenance systems for long-term safety and repair costs reduction of equipment of nuclear power plants are stated. Planned maintenance contained the breakdown maintenance (BM) and the preventive maintenance, which consists of the time based maintenance (MBM) and the condition based maintenance (CBM). Explained are the characteristics of equipments, maintenance methods, maintenance solutions and the self-evaluation maintenance power, damage mechanism and solutions, and monitoring tools and application. Stated are the maintenance system and application of monitoring technology, periodical maintenance, application of diagnosis, vibration monitoring techniques, decision of vibration monitoring, and application of monitoring techniques for improvement of maintenance. Illustrated are realization of planned maintenance by reorganization of maintenance, a trend of maintenance of equipments, table of classified maintenance systems, change of maintenance program, maintenance data and investigation of damage mechanism, examples of self-evaluation maintenance power, examples of analysis of damage of parts of equipments, evaluation of rotating machines by vibration method, examples of results of diagnosis of bearing of rotating machines, online maintenance system of Asahi Kasei Engineering Corporation, degradation pattern of pomp, estimation of lifetime by total vibration and vibration on acceleration, and improvement of equipments. (S.Y.)

Instruction manual for the use of CSIR triaxial rock stress measuring equipment

CSIR Research Space (South Africa)

Coetzer, SJ

1998-08-01

Full Text Available This is an updated version of CSIR Report no ME 1763 entitled "Instruction manual for the use for the CSIR triaxial rock stress measuring equipment" by F A Vreede. The manual contains a detailed description of CSIR Triaxial rock stress measuring...

Costs and indices for domestic oil and gas field equipment and production operations 1994 through 1997

International Nuclear Information System (INIS)

1998-03-01

This report presents estimated costs and cost indices for domestic oil and natural gas field equipment and production operations for 1994, 1995, 1996, and 1997. The costs of all equipment and services are those in effect during June of each year. The sums (aggregates) of the costs for representative leases by region, depth, and production rate were averaged and indexed. This provides a general measure of the increased or decreased costs from year to year for lease equipment and operations. These general measures do not capture changes in industry-wide costs exactly because of annual variations in the ratio of the total number of oil wells to the total number of gas wells. The detail provided in this report is unavailable elsewhere. The body of this report contains summary tables, and the appendices contain detailed tables. Price changes for oil and gas, changes in taxes on oil and gas revenues, and environmental factors (compliance costs and lease availability) have a significant impact on the number and cost of oil and gas wells drilled. These changes also impact the cost of oil and gas equipment and production operations

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...

Airlocks in the containment of nuclear power plants

International Nuclear Information System (INIS)

1978-01-01

An equipment hatch according to this regulator is a pressure-resisting and technically gas-tight hollow body which is connected with the containment and has got two doors, the inner door connecting the inner space of the hatch with the interior of the containment and the outer door connecting the inner space of the hatch with the exterior. It is exclusively destinied for the transport of material or objects and not of persons. (orig./HP) [de

Evaluation of severe accident environmental conditions taking accident management strategy into account for equipment survivability assessments

International Nuclear Information System (INIS)

Lee, Byung Chul; Jeong, Ji Hwan; Na, Man Gyun; Kim, Soong Pyung

2003-01-01

This paper presents a methodology utilizing accident management strategy in order to determine accident environmental conditions in equipment survivability assessments. In case that there is well-established accident management strategy for specific nuclear power plant, an application of this tool can provide a technical rationale on equipment survivability assessment so that plant-specific and time-dependent accident environmental conditions could be practically and realistically defined in accordance with the equipment and instrumentation required for accident management strategy or action appropriately taken. For this work, three different tools are introduced; Probabilistic Safety Assessment (PSA) outcomes, major accident management strategy actions, and Accident Environmental Stages (AESs). In order to quantitatively investigate an applicability of accident management strategy to equipment survivability, the accident simulation for a most likely scenario in Korean Standard Nuclear Power Plants (KSNPs) is performed with MAAP4 code. The Accident Management Guidance (AMG) actions such as the Reactor Control System (RCS) depressurization, water injection into the RCS, the containment pressure and temperature control, and hydrogen concentration control in containment are applied. The effects of these AMG actions on the accident environmental conditions are investigated by comparing with those from previous normal accident simulation, especially focused on equipment survivability assessment. As a result, the AMG-involved case shows the higher accident consequences along the accident environmental stages

Automatization of welding for nuclear power equipments and facilities

International Nuclear Information System (INIS)

Tamai, Yasumasa; Matsumoto, Teruo; Koyama, Takaichi

1980-01-01

For the requirement of high reliability in the construction of nuclear power plants and the reduction of radiation exposure in the modefying works of existing plants, the automation and remote operation of welding have increased their necessity. In this paper, the present state of the automation of welding for making machines, equipments and pipings for nuclear power plants in Hitachi Ltd. is described, and the aim of developing the automation, the features of the equipments and the state of application to actual plants are introduced, centering around the automation of welding for large structures such as reactor containment vessels and the remote type automatic welding system for pipings. By these automations, the large outcomes were obtained in the improvement of welding quality required for the machines and equipments for atomic energy. Moreover, the conspicuous results were also obtained in case of the peculiar works to nuclear power plants, in which the reduction of the radiation exposure related to human bodies and the welding of high quality are demanded. The present state of the automation of welding for nuclear installations in Hitachi Ltd., the development of automatic welding equipments and the present state of application to actual plants, and the development and application of the automatic pipe working machine for reducing radiation exposure are explained. (Kako, I.)

Qualification of Programmable Electronic System (PES) equipment based on international nuclear I and C standards

International Nuclear Information System (INIS)

De Grosbois, J.; Hepburn, G. A.; Olmstead, R.; Goble, W.; Kumar, V.

2006-01-01

Nuclear power plants (NPPs) are increasingly faced with the challenge of qualifying procured equipment, sub-components, and systems that contain digital programmed electronics for use in safety-related applications. Referred to as a 'programmable electronic system' (PES), such equipment typically contains both complex logic that is vulnerable to systematic design faults, and low voltage electronics hardware that is subject to random faults. Procured PES products or components are often only commercial grade, yet can offer reliable cost effective alternatives to custom-designed or nuclear qualified equipment, provided they can be shown to meet the quality assurance, functional safety, environmental, and reliability requirements of a particular application. The process of confirming this is referred to as application-specific product qualification (ASPQ) and can be challenging and costly. This paper provides an overview of an approach that has been developed at Atomic Energy Canada Limited (AECL) and successfully applied to PES equipment intended for use in domestic Candu R 6 nuclear power plants and special purpose reactors at Chalk River Laboratories. The approach has evolved over the past decade and has recently been adapted to be consistent with, and take advantage of new standards that are applicable to nuclear safety-related I and C systems. Also discussed are how recognized third-party safety-certifications of PES equipment to International Electrotechnical Commission (IEC) standards, and the assessment methods employed, may be used to reduce ASPQ effort. (authors)

340 Facility secondary containment and leak detection

International Nuclear Information System (INIS)

Bendixsen, R.B.

1995-01-01

This document presents a preliminary safety evaluation for the 340 Facility Secondary Containment and Leak Containment system, Project W-302. Project W-302 will construct Building 340-C which has been designed to replace the current 340 Building and vault tank system for collection of liquid wastes from the Pacific Northwest Laboratory buildings in the 300 Area. This new nuclear facility is Hazard Category 3. The vault tank and related monitoring and control equipment are Safety Class 2 with the remainder of the structure, systems and components as Safety Class 3 or 4

Development of Wireless System for Containment Integrated Leakage Rate Test

International Nuclear Information System (INIS)

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

2006-01-01

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

Evaluation of containment hydrogen and oxygen analyzers

International Nuclear Information System (INIS)

Booth, H.R.; Stanley, L.

1993-02-01

This report contains information concerning operation and calibration of detectors utilized at US nuclear power plants for determining concentration of hydrogen and oxygen within the containment structure.A study was prompted by reports that several plants had experienced problems in operating, calibrating, and maintaining the detectors supplied by various vendors. A survey of all nuclear power plants was conducted to identify the specific problems. Discussions were held with key vendors concerning these problems. The major area of interest was centered around problems associated with calibration of the detectors. Many variations from plant-to-plant concerning calibration accuracies, calibration time periods, and frequencies were identified. Another area of prime consideration involved variations as to maintenance of the equipment. Some plants devoted considerable effort to in-house maintenance of equipment while others relied heavily on the vendor for such maintenance. A workshop was conducted with key utility and vendor personnel in attendance to discuss findings of the survey. It was resolved that a much improved coordinated effort between the vendors and utilities would be initiated as a means to resolve existing problems

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

Safety systems I/C equipment reliability analyses of the Kozloduy NPP units 3 and 4

Energy Technology Data Exchange (ETDEWEB)

Halev, G; Christov, N [Risk Engineering Ltd., Sofia (Bulgaria)

1996-12-31

The purpose of the analysis is to assess the safety systems I/C equipment reliability. The assessment includes: quantification of the safety systems unavailability due to component failures; definition of the minimal cut sets leading to the analysed safety systems failure; quantification of the I/C equipment importance measures of the dominant contribution components. The safety systems I/C equipment reliability has been analysed using PSAPACK (a code for probabilistic safety assessment). Fault trees for the following safety systems of the Kozloduy-3 and Kozloduy-4 reactors have been constructed: neutron flow control equipment, reactor protection system, main coolant pumps, pressurizer safety valves `Sempell`, steam dump systems, spray system, low pressure injection system, emergency feeding water system, essential service water system. THree separate reports have been issued containing the performed analyses and results. 1 ref.

Underwater fuel handling equipment maintenance. Verification of design assumptions, specific problems and tools, case study

International Nuclear Information System (INIS)

Kurek, J.B.

1995-01-01

The majority of CANDU Fuel Transfer System equipment at Pickering is located under fourteen feet of water, as dictated by the containment and shielding requirements. Such arrangement, however, creates specific problems with equipment maintenance. Each single piece of equipment serves two generating units, which means in case of defect- double losses on production, or two units shut down simultaneously for planned maintenance. The requirement for underwater maintenance was not anticipated at the design stage, which multiples the level of difficulty, and creates requirement for developing special tools for each work. Removal of the damaged fuel from the receiving bays and decontamination of submerged equipment is also part of the problem. The purpose of this presentation is to share our experience with the designers, operators, maintenance mechanics and technical personnel of the other CANDU generating stations

ER-E4 regulation. Transitional arrangement to implement the rules for evaluating and state control of medical equipment

International Nuclear Information System (INIS)

2015-01-01

Establish a regulatory document where the validity and status of the documents contained in the Regulatory Legal Base Technical Program of medical equipment is exposed, given the scope thereof to comply with the provisions of the Regulation. This regulation is aimed at all subjects (manufacturers or producers, suppliers or distributors, importers, users, medical equipment, as well as health institutions SNS) involved in activities related to the evaluation and control of the State Medical equipment and make use of complementary technical legal documents.

Pressure release in containments of nuclear power stations

International Nuclear Information System (INIS)

Pauli, W.; Pellaud, B.; Saitoh, A.

1992-01-01

In France, Germany, Sweden and Switzerland, the licensing authorities have decided to equip nuclear reactor containments with a filter venting system to ensure survival of the containment after postulated severe nuclear accidents. This is a curious paradox. For years, the established wisdom was unambiguously 'Keep the containment tight. It's the ultimate barrier.' Three Mile Island seemed to prove the point. Yet, an old mechanical engineer's rule is 'Every pressure vessel must have a safety valve.' Filtered containment venting attempts to reconcile these two conflicting objectives by allowing a filtered pressure relief after an accident, in order to prevent containment failure due to overpressure, while keeping the release within acceptable limits. Achieving this dual objective is a matter of proper timing, i.e. pressure relief, not too early, not too late. (author)

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.

Equipment repair in coal mines

Energy Technology Data Exchange (ETDEWEB)

Zhang, S

1982-01-01

Most equipment in Chinese coal mines consists of machinery and equipment produced in the 1950s; the efficiency of 4-62, CTD-57 and 70B/sub 2/ ventilators is 15% lower than that of new ones; that of SSM and AYaP pumps, 10% lower than of modern ones. Equipment renovation is done in three ways: replacing obsolete equipment with new equipment of the same type; improving the performance of existing equipment by introducing efficiency and reconstruction; and replacing obsolete equipment with advanced equipment. It is indicated that the second way, for example, replacement of 4-62 ventilator blades with a maximum efficiency of 73% by 4-72 ventilator blades raises its efficiency to 90%. Replacing the 8DA-8x3 water pump, having a maximum efficiency of 63%, with the 200D 43x3 pump with a maximum efficiency of 78%, enables an electricity savings of 7000 yuan per year, which exceeds all replacement costs (600 yuan). The need to improve equipment maintenance and preventive work to increase equipment service life and to introduce new techniques and efficiency is noted.

Current state of commercial radiation detection equipment for homeland security applications

International Nuclear Information System (INIS)

Klann, R.T.; Shergur, J.; Mattesich, G.

2009-01-01

With the creation of the U.S. Department of Homeland Security (DHS) came the increased concern that terrorist groups would attempt to manufacture and use an improvised nuclear device or radiological dispersal device. As such, a primary mission of DHS is to protect the public against the use of these devices and to assist state and local responders in finding, locating, and identifying these types of devices and materials used to manufacture these devices. This assistance from DHS to state and local responders comes in the form of grant money to procure radiation detection equipment. In addition to this grant program, DHS has supported the development of American National Standards Institute standards for radiation detection equipment and has conducted testing of commercially available instruments. This paper identifies the types and kinds of commercially available equipment that can be used to detect and identify radiological material - for use in traditional search applications as well as primary and secondary screening of personnel, vehicles, and cargo containers. In doing so, key considerations for the conduct of operations are described as well as critical features of the instruments for specific applications. The current state of commercial instruments is described for different categories of detection equipment including personal radiation detectors, radioisotope identifiers, man-portable detection equipment, and radiation portal monitors. In addition, emerging technologies are also discussed, such as spectroscopic detectors and advanced spectroscopic portal monitors

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.

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...

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

49 CFR 173.230 - Fuel cell cartridges containing hazardous material.

Science.gov (United States)

2010-10-01

... integral vent feature) is deemed to pass the fire test if: (A) The internal pressure vents to zero gauge... required to power the equipment, plus two spares; (5) Large robust articles containing fuel cells may be...

Annual report on the state of RB reactor components and equipment, december 1999

International Nuclear Information System (INIS)

Milosevic, M.

1999-12-01

According to the performed analysis, it is considered that the RB reactor can be operated safely until the existing control and safety systems could be maintained in satisfactory operable state. Failures of heavy water circulation system valves which may cause decreased availability but no accident. During 1998 the reactor lattice was changed 13 times, meaning that experiments were done with 13 configurations of the reactor core. Total reactor operation amounted to 84 Wh with 40 start-ups (attained criticality levels). This report contains 4 Annexes, detailed description of the state of reactor equipment in 1999, reactor operation nd utilization data, plan for regular annual maintenance and refurbishment of reactor equipment and plan for minimum needed resources for regular maintenance of the components and equipment in the forthcoming year

Annual report on the state of RB reactor components and equipment, december 1998

International Nuclear Information System (INIS)

Milosevic, M.

1998-12-01

According to the performed analysis, it is considered that the RB reactor can be operated safely until the existing control and safety systems could be maintained in satisfactory operable state. Failures of heavy water circulation system valves which may cause decreased availability but no accident. During 1998 the reactor lattice was changed 7 times, meaning that experiments were done with 7 configurations of the reactor core. Total reactor operation amounted to 177.5 Wh with 40 start-ups (attained criticality levels). This report contains 4 Annexes, detailed description of the state of reactor equipment in 1998, reactor operation nd utilization data, plan for regular annual maintenance and refurbishment of reactor equipment and plan for minimum needed resources for regular maintenance of the components and equipment in the forthcoming year

NATO ARI on Ergonomic Data for Equipment Design

CERN Document Server

1984-01-01

For many years ergonomists and human engineering specialists have made significant contributions to the solution of problems faced in the area of human labour and to the introduction of their research results and field experience into the process of equipment design. However, the rapid increase in complexity of equipment in use as well as in development demonstrates the necessity of broaden­ ing the point of view continuously. The workshop held in Munich from March 22nd to March 26th, 1982, was an excellent opportunity for the participants to discuss their respective interests and their interpretation of needs for future research. The workshop was sponsored by the Human Factors Special Programme Panel of the Scientific Affairs Division of NATO. This sponsorship, together with the helpful assistance rendered by Drs. Bayraktar, Kroemer, and Sanders, is gratefully acknowledged. This volume contains the papers presented during the workshop. All these papers are directly related to the general aim: the ex­ chang...

Nitrogen oxides emission of mobile equipment in the port of Rotterdam. Consequences for nitrogen dioxide concentration, nitrogen deposition and a deduction of emission factors for container and bulk businesses; Stikstofoxidenemissies van mobiele werktuigen in de Rotterdamse haven. Gevolgen voor stikstofdioxide concentratie, stikstofdepositie, en een afleiding van emissiefactoren voor container- en droge bulk bedrijven

Energy Technology Data Exchange (ETDEWEB)

Okkerse, W J.H.; De Gier, C W

2011-08-15

In container terminals, dry bulk businesses and construction sites in the port of Rotterdam, the Netherlands, large masses of goods are transported by means of diesel-fuelled equipment every year. The combustion of diesel in this equipment results in emissions of nitrogen oxides (NOx) and particulate matter. This study has calculated the amounts of NOx emissions of the involved businesses based on detailed data on the composition of the equipment fleet of six representative storage and transshipment businesses. The resulting contribution to nitrogen oxide concentration at ground level and the nitrogen deposition have been calculated with the OPS model (Operational Priority Substances) [Dutch] Bij containerterminals, droge bulk bedrijven en bouwplaatsen in de Rotterdamse haven wordt jaarlijks een grote massa aan goederen getransporteerd met behulp van dieselaangedreven apparatuur. De verbranding van diesel in deze apparatuur zorgt voor de emissie van stikstofoxiden (NOx) en stof. In dit onderzoek zijn de NOx emissies van de betrokken bedrijven berekend op basis van gedetailleerde gegevens over de samenstelling van het werktuigenpark van zes representatieve op- en overslagbedrijven. De resulterende bijdrage aan de stikstofdioxide (NO2) concentratie op leefniveau en de stikstofdepositie is berekend met het OPS-model (Operationele Prioritaire Stoffen)

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...

DEMONSTRATiON OF A SUBSURFACE CONTAINMENT SYSTEM FOR INSTALLATION AT DOE WASTE SITES

Energy Technology Data Exchange (ETDEWEB)

Thomas J. Crocker; Verna M. Carpenter

2003-05-21

Between 1952 and 1970, DOE buried mixed waste in pits and trenches that now have special cleanup needs. The disposal practices used decades ago left these landfills and other trenches, pits, and disposal sites filled with three million cubic meters of buried waste. This waste is becoming harmful to human safety and health. Today's cleanup and waste removal is time-consuming and expensive with some sites scheduled to complete cleanup by 2006 or later. An interim solution to the DOE buried waste problem is to encapsulate and hydraulically isolate the waste with a geomembrane barrier and monitor the performance of the barrier over its 50-yr lifetime. The installed containment barriers would isolate the buried waste and protect groundwater from pollutants until final remediations are completed. The DOE has awarded a contract to RAHCO International, Inc.; of Spokane, Washington; to design, develop, and test a novel subsurface barrier installation system, referred to as a Subsurface Containment System (SCS). The installed containment barrier consists of commercially available geomembrane materials that isolates the underground waste, similar to the way a swimming pools hold water, without disrupting hazardous material that was buried decades ago. The barrier protects soil and groundwater from contamination and effectively meets environmental cleanup standards while reducing risks, schedules, and costs. Constructing the subsurface containment barrier uses a combination of conventional and specialized equipment and a unique continuous construction process. This innovative equipment and construction method can construct a 1000-ft-long X 34-ft-wide X 30-ft-deep barrier at construction rates to 12 Wday (8 hr/day operation). Life cycle costs including RCRA cover and long-term monitoring range from approximately $380 to $590/cu yd of waste contained or $100 to $160/sq ft of placed barrier based upon the subsurface geology surrounding the waste. Project objectives for Phase

PROBLEMS PERTAINING TO DIVERSIFICATION OF CIVIL EQUIPMENT IN EQUIPMENT OF MILITARY PURPOSE

OpenAIRE

A. I. Kotlabay; V. A. Korobkin; V. F. Tamelo; I. V. Kostko; S. V. Kondratiev

2009-01-01

Study of directions concerning development of military equipment, its modernization with the purpose to improve its military efficiency is an actual problem for the Armed Forces, military science, designers and researchers.The paper analyzes and estimates possibilities to use civil equipment for military purpose. Problems pertaining to technologies of double application, diversification of civil equipment in military engineering machinery are considered in the paper.

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...

Japanese contributions to containment structure, assembly and maintenance and reactor building for ITER

International Nuclear Information System (INIS)

Shibanuma, Kiyoshi; Honda, Tsutomu; Kanamori, Naokazu

1991-06-01

Joint design work on Conceptual Design Activity of International Thermonuclear Experimental Reactor (ITER) with four parties, Japan, the United States, the Soviet Union and the European Community began in April 1988 and was successfully completed in December 1990. In Japan, the home team was established in wide range of collaboration between JAERI and national institute, universities and heavy industries. The Fusion Experimental Reactor (FER) Team at JAERI is assigned as a core of the Japanese home team to support the joint Team activity and mainly conducted the design and R and D in the area of containment structure, remote handling and plant system. This report mainly describes the Japanese contribution on the ITER containment structure, remote handling and reactor building design. Main areas of contributions are vacuum vessel, attaching locks, electromagnetic analysis, cryostat, port and service line layout for containment structure, in-vessel handling equipment design and analysis, blanket handling equipment design and related short term R and D for assembly and maintenance, and finally reactor building design and analysis based on the equipment and service line layout and components flow during assembly and maintenance. (author)

Free-world microelectronic manufacturing equipment

Science.gov (United States)

Kilby, J. S.; Arnold, W. H.; Booth, W. T.; Cunningham, J. A.; Hutcheson, J. D.; Owen, R. W.; Runyan, W. R.; McKenney, Barbara L.; McGrain, Moira; Taub, Renee G.

1988-12-01

Equipment is examined and evaluated for the manufacture of microelectronic integrated circuit devices and sources for that equipment within the Free World. Equipment suitable for the following are examined: single-crystal silicon slice manufacturing and processing; required lithographic processes; wafer processing; device packaging; and test of digital integrated circuits. Availability of the equipment is also discussed, now and in the near future. Very adequate equipment for most stages of the integrated circuit manufacturing process is available from several sources, in different countries, although the best and most widely used versions of most manufacturing equipment are made in the United States or Japan. There is also an active market in used equipment, suitable for manufacture of capable integrated circuits with performance somewhat short of the present state of the art.

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...

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...

[Simplicia and medical containers from the Jesuit pharmacy in Telč].

Science.gov (United States)

Hamrlová, Anna

2017-01-01

The Jesuit pharmacy in Telč was founded after 1657 within the premises of the Jesuit cloister; it survived the dissolution of Jesuits in 1773 and thanks to its purchase by the last pharmacist Ignac Lyro it was relocated to one of the houses in the square. During the stocktaking of the property and its sale, a detailed inventory of pharmacy equipment was recorded, including cabinets, laboratory tools, ingredients or drugs. The inventory is divided into parts of ingredients and prepared medications, the last lists recording the tools and containers for its preparation, production and preservation. The ingredients contain various parts of plants, minerals, precious stones or even parts of animals. The list is written mainly in the alphabetical order, in some cases with specified types of groups. Every item is provided with information about its price and quantity. Many ingredients originated from overseas countries, the areas of Jesuit missionary activities. Of the former rich equipment, only three pharmacy cabinets and a few containers, mainly veneer boxes and ceramic drug jars, have survived. All these parts together with the inventory give us a comparatively clear notion about the equipment and even facilities of the Jesuit apothecary in Telč, which sold items from different parts of the world. The Jesuit convent seems to be an important centre for town inhabitants not only in the 18th century; its legacy has remained in the local pharmacy till today.Key words: pharmacy Societas Jesus 18th century medications medical containers.

Containment performance working group report. Draft report for comment

International Nuclear Information System (INIS)

1985-05-01

Containment buildings for power reactors have been studied to estimate their leak rate as a function of increasing internal pressure and temperature associated with severe accident sequences involving significant core damage. Potential leak paths through containment penetration assemblies (such as equipment hatches, airlocks, purge and vent valves, and electrical penetrations) have been identified and their contributions to leak area for the containment are incorporated into containment response analyses of selected severe accident sequences to predict the containment leak rate and pressure/temperature response as a function of time. Because of lack of reliable experimental data on the leakage behavior of containment penetrations and isolation barriers at pressures beyond their design conditions, an analytical approach has been used to estimate the leakage behavior of components found in specific reference plants that approximately characterize the various containment types

Environmental/dynamic mechanical equipment qualification and dynamic electrical equipment qualification program (EDQP)

International Nuclear Information System (INIS)

Hunter, J.A.

1984-01-01

Equipment qualification research is being conducted to investigate acceptable criteria, requirements, and methodologies for the dynamic (including seismic) and environmental qualification of mechanical equipment and for the dynamic (including seismic) qualification of electrical equipment. The program is organized into three elements: (1) General Research, (2) Environmental Research, and (3) Dynamic Research. This paper presents the highlights of the results to date in these three elements of the program

Regulations No. 59 of 20 February 1978 on X-ray skin therapy equipment up to 50 kV

International Nuclear Information System (INIS)

1978-01-01

These regulations lay down the provisions to be complied with for the protection of medical staff and patients when using X-ray equipment for skin therapy. The operators of such equipment must comply with the technical guidelines contained in the regulations and provision is made for annual inspections to ensure that the devices meet the necessary safety standards. (NEA) [fr

Use of Equipment Information System (EQUIS) to determine priority for purchasing safeguards equipment

International Nuclear Information System (INIS)

Silberberg, S.

1988-01-01

To manage its large world-wide inventory of safeguards equipment, the IAEA Safeguards department uses a computerized Equipment Information System (EQUIS). EQUIS data have been analyzed using Queueing Theory to determine if inventory is adequate to meet inspector demands and in those cases where it is inadequate, to indicate how many additional units should be procured. Results are tabulated for various types of non-destructive analysis (NDA) equipment. For equipment where there is a high turnover and hence a large amount of data, the analysis provides a powerful tool for assisting procurement decisions

Industry sector analysis, Mexico: Oil and gas field machinery and equipment. Export Trade Information

International Nuclear Information System (INIS)

1990-04-01

The Industry Sector Analyses (I.S.A.) for oil and gas field machinery and equipment contains statistical and narrative information on projected market demand, end-users, receptivity of Mexican consumers to U.S. products, the competitive situation - Mexican production, total import market, U.S. market position, foreign competition, and competitive factors, and market access - Mexican tariffs, non-tariff barriers, standards, taxes and distribution channels. The I.S.A. provides the United States industry with meaningful information regarding the Mexican market for oil and gas field machinery and equipment

The Preliminary Prototype of Medium Dose Rate Brachytherapy Equipment

Directory of Open Access Journals (Sweden)

A. Satmoko

2013-08-01

Full Text Available A preliminary prototype of a brachytherapy equipment has been constructed. The work started by developing conceptual design, followed by basic design and detailed design. In the conceptual design, design requirements are stated. In the basic design, technical specifications for main components are determined. In detailed design, general drawings are discussed. The prototype consists of three main systems: a mechanical system, an instrumentation system, and a safety system. The mechanical system assures the movement mechanism of the isotope source position beginning from the standby position until the applicators. It consists of three main modules: a position handling module, a container module, and a channel distribution module. The position handling module serves to move the isotope source position. As shielding, the second module is to store the source when the equipment is in standby position. The prototype provides 12 output channels. The channel selection is performed by the third module. The instrumentation system controls the movement of source position by handling motor operations. It consists of several modules. A microcontroller module serves as a control center whose task includes both controlling motors and communicating with computer. A motor module serves to handle motors. 10 sensors, including their signal conditionings, are introduced to read the environment conditions of the equipment. LEDs are used to display these conditions. In order to facilitate the operators’ duty, communication via RS232 is provided. The brachytherapy equipment can therefore be operated by using computer. Interface software is developed using C# language. To complete both mechanical and instrumentation systems performance, a safety system is developed to make sure that the safety for operator and patients from receiving excessive radiation. An interlock system is introduced to guard against abnormal conditions. In the worst case, a manual intervention

Numerical simulation of an equipment hatch for a steel containment vessel to loading beyond the design basis

International Nuclear Information System (INIS)

Kulak, R.F.; Hsieh, B.J.; Ash, J.E.; Kennedy, J.M.; McLennan, G.A.

1985-01-01

A preliminary analysis of the sealing deformations of a large equipment hatch with a pressure-seated gasket due to overpressurization was performed. An axisymmetric finite element analysis of the penetration sleeve revealed that its surface can undergo large rotations; values for sealing surface rotation of 7 0 were computed. Estimates for the order of magnitude of leakage due to the sealing surface rotation were made. 10 refs., 7 figs., 1 tab

Method and multichannel equipment for chemical analysis by X-ray emission

International Nuclear Information System (INIS)

Bacso, J.; Horkay, Gy.; Kalinka, G.; Kertesz, Zs.; Kiss Varga, M.; Lakatos, T.; Mathe, Gy.; Paal, A.; Sulik, B.

1978-01-01

In the patent a simple method and an apparatus are described for chemical analysis based on X-ray emission generated by irradiation. The concentrations of pre-selected elements can be determined easily by this method using an equipment containing microprocessor. The number of channels and the elements to be determined can be modified by a simple change in the program. (Sz.J.)

Deactivation of tracer-flo equipment thru retrieval of its radioactive Krypton-85 gas

International Nuclear Information System (INIS)

Domondon, D.B.; Rara, R.B.; Borras, A.M.

1994-01-01

Tracer-flo equipment must be cleared of Krypton-85 before these can be transported. The rules and regulations on safe transport of radioactive materials require Kr-85 gas to be transported in an approved container. A new innovative technique/procedure in deactivating tracer-flo equipment i.e., without separation of the Kr-85 from the nitrogen was developed by the authors. The developed procedure was successfully applied in four tracer-flo equipment of three (3) semiconductor firms. In the process, the three firms have saved about US$ 28,000.00 (P 800,000.00) if the deactivation were undertaken by a foreign service company. The Philippine Nuclear Research Institute (PNRI) retrieved about P 382,000.00 worth of Kr-85 that could be used in industrial applications such as leak tracing of buried pipes, etc. (author). 1 ref.; 5 figs

Explosion Clad for Upstream Oil and Gas Equipment

Science.gov (United States)

Banker, John G.; Massarello, Jack; Pauly, Stephane

2011-01-01

Today's upstream oil and gas facilities frequently involve the combination of high pressures, high temperatures, and highly corrosive environments, requiring equipment that is thick wall, corrosion resistant, and cost effective. When significant concentrations of CO2 and/or H2S and/or chlorides are present, corrosion resistant alloys (CRA) can become the material of choice for separator equipment, piping, related components, and line pipe. They can provide reliable resistance to both corrosion and hydrogen embrittlement. For these applications, the more commonly used CRA's are 316L, 317L and duplex stainless steels, alloy 825 and alloy 625, dependent upon the application and the severity of the environment. Titanium is also an exceptional choice from the technical perspective, but is less commonly used except for heat exchangers. Explosion clad offers significant savings by providing a relatively thin corrosion resistant alloy on the surface metallurgically bonded to a thick, lower cost, steel substrate for the pressure containment. Developed and industrialized in the 1960's the explosion cladding technology can be used for cladding the more commonly used nickel based and stainless steel CRA's as well as titanium. It has many years of proven experience as a reliable and highly robust clad manufacturing process. The unique cold welding characteristics of explosion cladding reduce problems of alloy sensitization and dissimilar metal incompatibility. Explosion clad materials have been used extensively in both upstream and downstream oil, gas and petrochemical facilities for well over 40 years. The explosion clad equipment has demonstrated excellent resistance to corrosion, embrittlement and disbonding. Factors critical to insure reliable clad manufacture and equipment design and fabrication are addressed.

Explosion Clad for Upstream Oil and Gas Equipment

International Nuclear Information System (INIS)

Banker, John G.; Massarello, Jack; Pauly, Stephane

2011-01-01

Today's upstream oil and gas facilities frequently involve the combination of high pressures, high temperatures, and highly corrosive environments, requiring equipment that is thick wall, corrosion resistant, and cost effective. When significant concentrations of CO 2 and/or H 2 S and/or chlorides are present, corrosion resistant alloys (CRA) can become the material of choice for separator equipment, piping, related components, and line pipe. They can provide reliable resistance to both corrosion and hydrogen embrittlement. For these applications, the more commonly used CRA's are 316L, 317L and duplex stainless steels, alloy 825 and alloy 625, dependent upon the application and the severity of the environment. Titanium is also an exceptional choice from the technical perspective, but is less commonly used except for heat exchangers. Explosion clad offers significant savings by providing a relatively thin corrosion resistant alloy on the surface metallurgically bonded to a thick, lower cost, steel substrate for the pressure containment. Developed and industrialized in the 1960's the explosion cladding technology can be used for cladding the more commonly used nickel based and stainless steel CRA's as well as titanium. It has many years of proven experience as a reliable and highly robust clad manufacturing process. The unique cold welding characteristics of explosion cladding reduce problems of alloy sensitization and dissimilar metal incompatibility. Explosion clad materials have been used extensively in both upstream and downstream oil, gas and petrochemical facilities for well over 40 years. The explosion clad equipment has demonstrated excellent resistance to corrosion, embrittlement and disbonding. Factors critical to insure reliable clad manufacture and equipment design and fabrication are addressed.

Chapter 12. 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.

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)

Process equipment waste and process waste liquid collection systems

International Nuclear Information System (INIS)

1990-06-01

The US DOE has prepared an environmental assessment for construction related to the Process Equipment Waste (PEW) and Process Waste Liquid (PWL) Collection System Tasks at the Idaho Chemical Processing Plant. This report describes and evaluates the environmental impacts of the proposed action (and alternatives). The purpose of the proposed action would be to ensure that the PEW and PWL collection systems, a series of enclosed process hazardous waste, and radioactive waste lines and associated equipment, would be brought into compliance with applicable State and Federal hazardous waste regulations. This would be accomplished primarily by rerouting the lines to stay within the buildings where the lined floors of the cells and corridors would provide secondary containment. Leak detection would be provided via instrumented collection sumps locate din the cells and corridors. Hazardous waste transfer lines that are routed outside buildings will be constructed using pipe-in-pipe techniques with leak detection instrumentation in the interstitial area. The need for the proposed action was identified when a DOE-sponsored Resource Conservation and Recovery Act (RCRA) compliance assessment of the ICPP facilities found that singly-contained waste lines ran buried in the soil under some of the original facilities. These lines carried wastes with a pH of less than 2.0, which were hazardous waste according to the RCRA standards. 20 refs., 7 figs., 1 tab

Self-Contained Portable Data Acquisition/Control System Unit for Hydrogen Environments

Data.gov (United States)

National Aeronautics and Space Administration — The platform is designed to be a self-contained unit that is built to support a wide variety of electrical equipment, and constructed so that it can be safely...

Benchmarking Analysis between CONTEMPT and COPATTA Containment Codes

Energy Technology Data Exchange (ETDEWEB)

Seo, Kwi Hyun; Song, Wan Jung [ENERGEO Inc. Sungnam, (Korea, Republic of); Song, Dong Soo; Byun, Choong Sup [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

2006-07-01

The containment is the requirement that the releases of radioactive materials subsequent to an accident do not result in doses in excess of the values specified in 10 CFR 100. The containment must withstand the pressure and temperature of the DBA(Design Basis Accident) including margin without exceeding the design leakage rate. COPATTA as Bechtel's vendor code is used for the containment pressure and temperature prediction in power uprating project for Kori 3,4 and Yonggwang 1,2 nuclear power plants(NPPs). However, CONTEMPTLT/ 028 is used for calculating the containment pressure and temperatures in equipment qualification project for the same NPPs. During benchmarking analysis between two codes, it is known two codes have model differences. This paper show the performance evaluation results because of the main model differences.

Benchmarking Analysis between CONTEMPT and COPATTA Containment Codes

International Nuclear Information System (INIS)

Seo, Kwi Hyun; Song, Wan Jung; Song, Dong Soo; Byun, Choong Sup

2006-01-01

The containment is the requirement that the releases of radioactive materials subsequent to an accident do not result in doses in excess of the values specified in 10 CFR 100. The containment must withstand the pressure and temperature of the DBA(Design Basis Accident) including margin without exceeding the design leakage rate. COPATTA as Bechtel's vendor code is used for the containment pressure and temperature prediction in power uprating project for Kori 3,4 and Yonggwang 1,2 nuclear power plants(NPPs). However, CONTEMPTLT/ 028 is used for calculating the containment pressure and temperatures in equipment qualification project for the same NPPs. During benchmarking analysis between two codes, it is known two codes have model differences. This paper show the performance evaluation results because of the main model differences

Decommissioning of the self-contained irradiator Gammacell 500

International Nuclear Information System (INIS)

Llanes Rodriguez, Marisleidys; Rodriguez Perdomo, Yanet; Fraga Acosta, Daniel; Soto Alvarez, Evelio; Soler Roger, Dulce Maria; Abreu Mendez, Yuliel; Benitez Navarro, Juan Carlos; Salgado Mojena, Mercedes; Perez Reyes, Yolanda

2011-01-01

The National Center for Animal and Plant Health used a Gammacell 500 irradiator, with twelve cobalt 60 sealed sources, for sterilization and decontamination of medical devices, pharmaceuticals and several raw materials. Due to the 25 years of exploitation time of the equipment, it was decided to close the facility. For dismantling the equipment, a methodology was developed taking into account the currently national regulations, the recommendations of the Atomic International Energy Organization, the consultation from the operation and equipment maintenance manual and the operational history. The design and implementation of the procedure for the irradiator dismantling are described. The Institutional Irradiator Decommissioning License was obtained, awarded by the National Center for Nuclear Safety. The dismantling operations involved in the container extraction with the radioactive sources and bulk forming to be transported. The operations were performed under radiological security conditions, keeping control under dose and superficial contamination rate during the process. As a conclusion, the notification for the release of the facility was received. (author)

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...

1968 Listing of Swimming Pool Equipment.

Science.gov (United States)

National Sanitation Foundation, Ann Arbor, MI. Testing Lab.

An up-to-date listing of swimming pool equipment including--(1) companies authorized to display the National Sanitation Foundation seal of approval, (2) equipment listed as meeting NSF swimming pool equipment standards relating to diatomite type filters, (3) equipment listed as meeting NSF swimming pool equipment standard relating to sand type…

Use of GOTHIC Code for Assessment of Equipment Environmental Qualification

International Nuclear Information System (INIS)

Cavlina, N.; Feretic, D.; Grgic, D.; Spalj, S.; Spiler, J.

1996-01-01

Environmental qualification (EQ) of equipment important to safety in nuclear power plants ensures its capability to perform designated safety function on demand under postulated service conditions, including harsh accident environment (e. g. LOCA, HELB). The computer code GOTHIC was used to calculate pressure and temperature profiles inside NPP Krsko containment during limiting LOCA and MSLB accidents. The results of the new best-estimate containment code are compared to the older CONTEMPT code using the same input data and assumptions. The predictions obtained by both codes are very similar. As a result of the calculation the envelopes of the LOCA and MSLB pressures and temperatures, as used in FSAR/USAR Chapter 6, can be used in EQ project. (author)

Automation for Crushing and Screening Equipment to Produce Graded Paving Crushed Stone

Science.gov (United States)

Tikhonov, Anatoly; Velichkin, Vladimir

2017-10-01

This paper offers analysis of factors related to production and storage of graded crushed stone, which adversely impact the service life and wear resistance of asphalt-concrete motor road pavements. The paper describes external and technology-related parameters that may cause changes of the preset ratio in graded crushed stone. Control factors are described that ensure the formulated fraction ratio in crushed stone by controlling the operation mode of the crushing and screening equipment. The paper also contains an ACS flow chart for crushing and screening equipment engaged in continuous closed-cycle two-stage technology. Performance of the ACS to maintain the preset fractionated crushed stone ratio has been confirmed with a mathematical model.

Prognostics and health management system for hydropower plant based on fog computing and docker container

Science.gov (United States)

Xiao, Jian; Zhang, Mingqiang; Tian, Haiping; Huang, Bo; Fu, Wenlong

2018-02-01

In this paper, a novel prognostics and health management system architecture for hydropower plant equipment was proposed based on fog computing and Docker container. We employed the fog node to improve the real-time processing ability of improving the cloud architecture-based prognostics and health management system and overcome the problems of long delay time, network congestion and so on. Then Storm-based stream processing of fog node was present and could calculate the health index in the edge of network. Moreover, the distributed micros-service and Docker container architecture of hydropower plants equipment prognostics and health management was also proposed. Using the micro service architecture proposed in this paper, the hydropower unit can achieve the goal of the business intercommunication and seamless integration of different equipment and different manufacturers. Finally a real application case is given in this paper.

A Decision Optimization Model for Leased Manufacturing Equipment with Warranty under Forecasting Production/Maintenance Problem

Directory of Open Access Journals (Sweden)

Zied Hajej

2015-01-01

Full Text Available Due to the expensive production equipment, many manufacturers usually lease production equipment with a warranty period during a finite leasing horizon, rather than purchasing them. The lease contract contains the possibility of obtaining an extended warranty for a given additional cost. In this paper, based on the forecasting production/maintenance optimization problem, we develop a mathematical model to study the lease contract with basic and extended warranty based on win-win relationship between the lessee and the lessor. The influence of the production rates in the equipment degradation consequently on the total cost by each side during the finite leasing horizon is stated in order to determine a theoretical condition under which a compromise-pricing zone exists under different possibilities of maintenance policies.

Refurbishment of the transportation equipment, Task 3.08/04-10

International Nuclear Information System (INIS)

Nikolic, M.; Bratic, A.

1963-01-01

Transportation equipment at the RA reactor includes the bridge crane in the reactor hall, another smaller crane, bridge crane in spent fuel storage space, crane for handling the fuel containers n the room 099 and cart of the transportation channel. Regular testing and maintenance during reactor operation was not considered sufficient, and for that reason the repair and maintenance actions were done during the refurbishment of the reactor while it has been shut-down

29 CFR 1926.952 - Mechanical equipment.

Science.gov (United States)

2010-07-01

... equipment that are not covered with insulating protective equipment. (c) Derrick trucks, cranes and other lifting equipment. (1) All derrick trucks, cranes and other lifting equipment shall comply with subpart N...

Choice of volatile component of fluoroplastics containing varnishes for the equipment of radiation protection technique

International Nuclear Information System (INIS)

Shigorina, I.I.; Egorov, B.N.; Timofeeva, L.N.

1978-01-01

The problems of choosing the volatile part (v.p.) for varnishes on the basis of different flourocopolymers are considered. Ketones, esters, freons, dimethylformamide, tetrahydrofuran, aromatic and chlorinated hydrocarbons have been used as solvents. The volatile component has been estimated by the quality of the varnish film obtained (transparency, bubbles), viscosity of the varnishes, completeness of solvent volatility, porosity degree. Besides, analyzed are such factors as kinetics of solvent evaporation, working life time of varnishes, and the degree of their inflammability. Optimum solvents and their mixtures have been found for different grades of fluorolones. The possibility of producing fluorolone lackuers with a reduced degree of inflammability and of incombustible fluorolone varnishes is shown. Fluorolone varnishes find ever increasing application for radiation-protective coating of the equipment

Hybrid laser arc welding of a used fuel container

Energy Technology Data Exchange (ETDEWEB)

Boyle, C., E-mail: cboyle@nwmo.ca [Nuclear Waste Management Organization, Toronto, ON (Canada); Martel, P. [Novika Solutions, La Pocatiere, QC (Canada)

2015-07-01

The Nuclear Waste Management Organization (NWMO) has designed a novel Used Fuel Container (UFC) optimized for CANDU used nuclear fuel. The Mark II container is constructed of nuclear grade pipe for the body and capped with hemi-spherical heads. The head-to-shell joint fit-up features an integral backing designed for external pressure, eliminating the need for a full penetration closure weld. The NWMO and Novika Solutions have developed a partial penetration, single pass Hybrid Laser Arc Weld (HLAW) closure welding process requiring no post-weld heat treatment. This paper will discuss the joint design, HLAW process, associated welding equipment, and prototype container fabrication. (author)

Hybrid laser arc welding of a used fuel container

Energy Technology Data Exchange (ETDEWEB)

Boyle, C. [Nuclear Waste Management Organization (NWMO), Toronto, Ontario (Canada); Martel, P. [Novika Solutions, La Pocatiere, Quebec (Canada)

2015-09-15

The Nuclear Waste Management Organization (NWMO) has designed a novel Used Fuel Container (UFC) optimized for CANDU used nuclear fuel. The Mark II container is constructed of nuclear grade pipe for the body and capped with hemi-spherical heads. The head-to-shell joint fit-up features an integral backing designed for external pressure, eliminating the need for a full penetration closure weld. The NWMO and Novika Solutions have developed a partial penetration, single pass Hybrid Laser Axe Weld (HLAW) closure welding process requiring no post-weld heat treatment. This paper will discuss the joint design, HLAW process, associated welding equipment, and prototype container fabrication. (author)

Equipment Operational Requirements

Energy Technology Data Exchange (ETDEWEB)

Greenwalt, B; Henderer, B; Hibbard, W; Mercer, M

2009-06-11

The Iraq Department of Border Enforcement is rich in personnel, but poor in equipment. An effective border control system must include detection, discrimination, decision, tracking and interdiction, capture, identification, and disposition. An equipment solution that addresses only a part of this will not succeed, likewise equipment by itself is not the answer without considering the personnel and how they would employ the equipment. The solution should take advantage of the existing in-place system and address all of the critical functions. The solutions are envisioned as being implemented in a phased manner, where Solution 1 is followed by Solution 2 and eventually by Solution 3. This allows adequate time for training and gaining operational experience for successively more complex equipment. Detailed descriptions of the components follow the solution descriptions. Solution 1 - This solution is based on changes to CONOPs, and does not have a technology component. It consists of observers at the forts and annexes, forward patrols along the swamp edge, in depth patrols approximately 10 kilometers inland from the swamp, and checkpoints on major roads. Solution 2 - This solution adds a ground sensor array to the Solution 1 system. Solution 3 - This solution is based around installing a radar/video camera system on each fort. It employs the CONOPS from Solution 1, but uses minimal ground sensors deployed only in areas with poor radar/video camera coverage (such as canals and streams shielded by vegetation), or by roads covered by radar but outside the range of the radar associated cameras. This document provides broad operational requirements for major equipment components along with sufficient operational details to allow the technical community to identify potential hardware candidates. Continuing analysis will develop quantities required and more detailed tactics, techniques, and procedures.

Characterization equipment essential drawing plan

International Nuclear Information System (INIS)

WILSON, G.W.

1999-01-01

The purpose of this document is to list the Characterization equipment drawings that are classified as Essential Drawings. Essential Drawings: Are those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment (HNF 1997a). The Characterization equipment drawings identified in this report are deemed essential drawings as defined in HNF-PRO-242, Engineering Drawing Requirements (HNF 1997a). These drawings will be prepared, revised, and maintained per HNF-PRO-440, Engineering Document Change Control (HNF 1997b). All other Characterization equipment drawings not identified in this document will be considered Support drawings until the Characterization Equipment Drawing Evaluation Report is completed

Fission reactor container

International Nuclear Information System (INIS)

Akagawa, Katsuhiko.

1991-01-01

Cooling water is sent without using dynamic equipments upon loss of coolants accident in a pressure vessel by improving an arrangement of a nuclear reactor pressure vessel. That is, a containing space is formed at the center of a suppression chamber for storing cooling water while being partitioned with each other, in which the pressure vessel is placed. Further, a water reservoir is formed above the pressure vessel. Then a water discharge pipe is connected to the reservoir for submerging the stored water over the pressure vessel upon occurrence of loss of coolants accident. Further, a water injection pipe is disposed between the pressure suppression chamber and the pressure vessel for injecting the cooling water in the pressure suppression chamber to the reactor core of the pressure vessel by the difference of a water head upon loss of coolants accident. With such a constitution, the pressure vessel has high earthquake proofness. Further, upon loss of coolants accident of the pressure vessel, the cooling water in the reservoir is discharged to submerge and cool the pressure vessel efficiently. Further, the reactor core of the pressure vessel can certainly be cooled by the cooling water of the pressure suppression chamber without relying on dynamic equipments. (I.S.)

Review and evaluation of technology, equipment, codes and standards for digitization of industrial radiographic film

International Nuclear Information System (INIS)

1992-05-01

This reports contains a review and evaluation of the technology, equipment, and codes and standards related to the digitization of industrial radiographic film. The report presents recommendations and equipment-performance specifications that will allow the digitization of radiographic film from nuclear power plant components in order to produce faithful reproductions of flaw images of interest on the films. Justification for the specifications selected are provided. Performance demonstration tests for the digitization process are required and criteria for such tests is presented. Also several comments related to implementation of the technology are presented and discussed

Summary of work completed under the Environmental and Dynamic Equipment Qualification research program (EDQP)

International Nuclear Information System (INIS)

Steele, R. Jr.; Bramwell, D.L.; Watkins, J.C.; DeWall, K.G.

1994-02-01

This report documents the results of the main projects undertaken under the Environmental and Dynamic Equipment Qualification Research Program (EDQP) sponsored by the U.S. Nuclear Regulatory Commission (NRC) under FIN A6322. Lasting from fiscal year 1983 to 1987, the program dealt with environmental and dynamic (including seismic) equipment qualification issues for mechanical and electromechanical components and systems used in nuclear power plants. The research results have since been used by both the NRC and industry. The program included seven major research projects that addressed the following issues: (a) containment purge and vent valves performing under design basis loss of coolant accident loads, (b) containment piping penetrations and isolation valves performing under seismic loadings and design basis and severe accident containment wall displacements, (c) shaft seals for primary coolant pumps performing under station blackout conditions, (d) electrical cabinet internals responding to in-structure generated motion (rattling), and (e) in situ piping and valves responding to seismic loadings. Another project investigating whether certain containment isolation valves will close under design basis conditions was also started under this program. This report includes eight main section, each of which provides a brief description of one of the projects, a summary of the findings, and an overview of the application of the results. A bibliography lists the journal articles, papers, and reports that document the research

Beta and gamma dose calculations for PWR and BWR containments

International Nuclear Information System (INIS)

King, D.B.

1989-07-01

Analyses of gamma and beta dose in selected regions in PWR and BWR containment buildings have been performed for a range of fission product releases from selected severe accidents. The objective of this study was to determine the radiation dose that safety-related equipment could experience during the selected severe accident sequences. The resulting dose calculations demonstrate the extent to which design basis accident qualified equipment could also be qualified for the severe accident environments. Surry was chosen as the representative PWR plant while Peach Bottom was selected to represent BWRs. Battelle Columbus Laboratory performed the source term release analyses. The AB epsilon scenario (an intermediate to large LOCA with failure to recover onsite or offsite electrical power) was selected as the base case Surry accident, and the AE scenario (a large break LOCA with one initiating event and a combination of failures in two emergency cooling systems) was selected as the base case Peach Bottom accident. Radionuclide release was bounded for both scenarios by including spray operation and arrested sequences as variations of the base scenarios. Sandia National Laboratories used the source terms to calculate dose to selected containment regions. Scenarios with sprays operational resulted in a total dose comparable to that (2.20 x 10 8 rads) used in current equipment qualification testing. The base case scenarios resulted in some calculated doses roughly an order of magnitude above the current 2.20 x 10 8 rad equipment qualification test region. 8 refs., 23 figs., 12 tabs

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)

Electrically nonconductive shield for electric equipment generating ionizing radiation

International Nuclear Information System (INIS)

Aitken, D.

1979-01-01

As a radiation protection shield there is proposed a nonconductive shield fabricated from epoxides or other plastics material and containing finely dispersed radiation absorbing metal. It is to be designed in such a way that it lies in the range of a high electric gradient in the equipment, close to the radiation-producing component. As suitable metals there are mentioned tin, tungsten, and lead resp. their oxides. As an example there is used an X-ray shielding. (RW) 891 RW/RW 892 MKO [de

Energy to the Edge (E2E) Equipment Assessment U.S. Army Rapid Equipping Force

Science.gov (United States)

2015-05-01

84 Contents Energy to the Edge • U.S. Army Rapid Equipping Force U.S. Army Rapid Equipping Force 1.0 Executive Summary Executive Summary U.S. Army... audiovisual equipment. • Once radiant barrier liner is inserted, the process of subsequent setups • Cables for lighting and outlets are located...behind the internal barrier • The shelter comes with organic audiovisual equipment. b. • • This shelter has a different setup and tear down process

Information technology equipment cooling method

Science.gov (United States)

Schultz, Mark D.

2015-10-20

According to one embodiment, a system for removing heat from a rack of information technology equipment may include a sidecar indoor air to liquid heat exchanger that cools air utilized by the rack of information technology equipment to cool the rack of information technology equipment. The system may also include a liquid to liquid heat exchanger and an outdoor heat exchanger. The system may further include configurable pathways to connect and control fluid flow through the sidecar heat exchanger, the liquid to liquid heat exchanger, the rack of information technology equipment, and the outdoor heat exchanger based upon ambient temperature and/or ambient humidity to remove heat generated by the rack of information technology equipment.

Equipment abnormality monitoring device

International Nuclear Information System (INIS)

Ando, Yasumasa

1991-01-01

When an operator hears sounds in a plantsite, the operator compares normal sounds of equipment which he previously heard and remembered with sounds he actually hears, to judge if they are normal or abnormal. According to the method, there is a worry that abnormal conditions can not be appropriately judged in a case where the number of objective equipments is increased and in a case that the sounds are changed gradually slightly. Then, the device of the present invention comprises a plurality of monitors for monitoring the operation sound of equipments, a recording/reproducing device for recording and reproducing the signals, a selection device for selecting the reproducing signals among the recorded signals, an acoustic device for converting the signals to sounds, a switching device for switching the signals to be transmitted to the acoustic device between to signals of the monitor and the recording/reproducing signals. The abnormality of the equipments can be determined easily by comparing the sounds representing the operation conditions of equipments for controlling the plant operation and the sounds recorded in their normal conditions. (N.H.)

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...

The Potential of Computer Controlled Optimizing Equipment in the Wooden Furniture Industry

Science.gov (United States)

R. Edward Thomas; Urs Buehlmann; Urs Buehlmann

2003-01-01

The goal of the wooden furniture industry is to convert lumber into parts by using the most efficient and cost effective processing methods. The key steps in processing lumber arc removing the regions that contain unacceptable defects or character marks and cutting the remaining areas to the widths and lengths of needed parts. Such equipment has been used in furniture...

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

Reactor containment depressurization and filtration equipment for use in the case of a serious accident

International Nuclear Information System (INIS)

L'Homme, A.

1987-06-01

A study was carried out under the aegis of the OECD into filtered vented containment systems which permit depressurization of the containment and filtration of the effluents released to the environment, in the event of a major accident with a pressurized water reactor (PWR) (or BWR or CANDU type reactors) involving core meltdown, with a view to minimizing the consequences. This paper describes the various systems examined which could possibly be used for this purpose. These comprised the French robust sand filtration system, the Swedish FILTRA system, the vacuum containment and discharge and emergency filtration system used by the CANDU plants of the Ontario-Hydro electricity company in Canada and the BWR pressure-suppression pounds. The positions of the various national authorities regarding incorporation of such systems into nuclear power plants, the design and technical principles underlying the systems, the procedures and criteria for their use and their advantages and disadvantages are examined [fr

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...

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

International Nuclear Information System (INIS)

LaSalle, F.R.

1991-01-01

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

Days individual equipment of protection and professional risks; Equipements de protection individuelle et risques professionnelles

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The personal protection equipment is studied in the legal way (legal liabilities, certification, European texts), technical way (ergonomics, painfulness of ventilated equipment wearing, reliability of a respirable air line, protection gloves against the chemical risk, exposure to nano particulates, working in hot area), human factors (hostile area and emotion management), studies on personal equipment such evaluation, efficiency, conception of new equipment, physiological tolerance, limit of use, and some general safety studies on the working places. (N.C.)

Equipment standards for interventional cardiology

International Nuclear Information System (INIS)

Dowling, A.; Gallagher, A.; Walsh, C.; Malone, J.

2005-01-01

Interventional radiology has seen rapid growth in cardiology and represents an alternative to hazardous surgery. Recently there has been a substantial growth in the number of procedures being performed and interventional cardiology (IC) procedures are the most common interventional procedures in Europe. Advances in imaging technology have facilitated the development of increasingly complex radiological IC equipment. Currently, the technology is developing at a rate ahead of supporting research, equipment standards and a regulatory framework. International standards play a key role in the design, manufacture and performance of radiological IC equipment. A survey of 12 IC systems (15 imaging chains) was conducted in Irish hospitals. The aim of the study was to assess the imbalance between rapidly advancing technology and existing standards and to propose recommendations for new IC equipment standards. The results demonstrate the need for definitive equipment requirements and standardisation in the design, manufacture, acceptance and maintenance of IC equipment. (authors)

Equipment for hydraulic testing

International Nuclear Information System (INIS)

Jacobsson, L.; Norlander, H.

1981-07-01

Hydraulic testing in boreholes is one major task of the hydrogeological program in the Stripa Project. A new testing equipment for this purpose was constructed. It consists of a downhole part and a surface part. The downhole part consists of two packers enclosing two test-sections when inflated; one between the packers and one between the bottom packer and the bottom of the borehole. A probe for downhole electronics is also included in the downhole equipment together with electrical cable and nylon tubing. In order to perform shut-in and pulse tests with high accuracy a surface controlled downhole valve was constructed. The surface equipment consists of the data acquisition system, transducer amplifier and surface gauges. In the report detailed descriptions of each component in the whole testing equipment are given. (Auth.)

Reactor container

International Nuclear Information System (INIS)

Hidaka, Masataka; Hatamiya, Shigeo; Kawasaki, Terufumi; Fukui, Toru; Suzuki, Hiroaki; Kataoka, Yoshiyuki; Kawabe, Ryuhei; Murase, Michio; Naito, Masanori.

1990-01-01

In order to suppress the pressure elevation in a reactor container due to high temperature and high pressure steams jetted out upon pipeway rupture accidents in the reactor container, the steams are introduced to a pressure suppression chamber for condensating them in stored coolants. However, the ability for suppressing the pressure elevation and steam coagulation are deteriorated due to the presence of inactive incondensible gases. Then, there are disposed a vent channel for introducing the steams in a dry well to a pressure suppression chamber in the reactor pressure vessel, a closed space disposed at the position lower than a usual liquid level, a first channel having an inlet in the pressure suppression chamber and an exit in the closed space and a second means connected by way of a backflow checking means for preventing the flow directing to the closed space. The first paths are present by plurality, a portion of which constitutes a syphon. The incondensible gases and the steams are discharged to the dry well at high pressure by using the difference of the water head for a long cooling time after the pipeway rupture accident. Then, safety can be improved without using dynamic equipments as driving source. (N.H.)

Double containment shell for nuclear power plants

International Nuclear Information System (INIS)

Sykora, D.

1977-01-01

A double containment shell is proposed for nuclear power plants, especially those equipped with pressurized water reactors. The shell offers increased environmental protection from primary circuit accidents. The inner shell is built of steel or concrete while the outer shell is always built of concrete. The space between the two shells is filled with water and is provided with several manholes and with stiffeners designed for compensation for load due to the water hydrostatic pressure. Water serves the airtight separation of the containment shell inside from the environment and the absorption of heat released in a primary circuit accident. In case the inner shell is made of concrete, it is provided with heat-removal tubes in-built in its walls ensuring rapid heat transfer from the inside of the containment to the water in the interwall space. (Z.M.)

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

CONTEMPT: computer program for predicting containment pressure-temperature response to a loss-of-coolant accident

International Nuclear Information System (INIS)

Hsii, Y.H.

1978-04-01

The CONTEMPT code is used by Babcock and Wilcox for containment analysis following a postulated loss of coolant accident. An additional model is described which is used for the calculation of long term post reflood mass and energy releases to the containment that is used for the containment design basis LOCA calculations. These calculations maximize the rate of energy flow to the containment. The mass and energy data are given to the containment designer for use in calculating the containment building design pressure and temperature and in sizing containment heat removal equipment

Shipboard and laboratory equipment

Digital Repository Service at National Institute of Oceanography (India)

Shyamprasad, M.; Ramaswamy, V.

The polymetallic nodules occur at an average depth of 4500 m. Adequate equipment and techniques are required for the exploration at such depths. Shipboard and various laboratory equipments for the sampling of polymetallic nodules is described...

Nuclear reactor equipped with a flooding tank and a residual heat removal and emergency cooling system

International Nuclear Information System (INIS)

Schabert, H.P.; Winkler, F.

1975-01-01

A description is given of a nuclear reactor such as a pressurized-water reactor or the like which is equipped with a flooding tank and a residual heat removal and emergency cooling system. The flooding tank is arranged within the containment shell at an elevation above the upper edge of the reactor core and contains a liquid for flooding the reactor core in the event of a loss of coolant

Acceptance test procedure for a portable, self-contained nitrogen supply

International Nuclear Information System (INIS)

Kostelnik, A.J.

1994-01-01

This Acceptance Test Procedure (ATP) will document compliance with the requirements of WHC-S-0249 Rev. 1 and ECN 606112. The equipment being tested is a Portable, Self-Contained Nitrogen Supply. The unit was purchased as a Design and Fabrication procurement activity. The Functional Test was written by the Seller and is contained in Appendix A. The Functional test will be performed by the Seller with representatives of the Westinghouse Hanford Company performing inspection and witnessing the functional test at the Seller's location

40 CFR 792.61 - Equipment design.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 31 2010-07-01 2010-07-01 true Equipment design. 792.61 Section 792.61...) GOOD LABORATORY PRACTICE STANDARDS Equipment § 792.61 Equipment design. Equipment used in the... of appropriate design and adequate capacity to function according to the protocol and shall be...

40 CFR 160.61 - Equipment design.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 23 2010-07-01 2010-07-01 false Equipment design. 160.61 Section 160... LABORATORY PRACTICE STANDARDS Equipment § 160.61 Equipment design. Equipment used in the generation... appropriate design and adequate capacity to function according to the protocol and shall be suitably located...

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

Directory of Open Access Journals (Sweden)

P. B. Gerike

2017-09-01

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

Equipment installation structure of roof slab for tank type FBR and method of equipment installation

International Nuclear Information System (INIS)

Sakai, Takao; Yamakawa, Masanori; Otsuka, Masaya; Sekine, Katsuhisa

1986-01-01

Purpose: To reduce equipment thermal stress and deformation by eliminating uneven temperature distribution caused at the equipment through section of the roof slab for the tank FBR, and at the same time, simplify the structure installation. Method: Multiple number of vertical fin projects are fit on the equipment through-section inside wall for the roof slab and the cylindrical equipment peripheral wall, and with these projected fins, the ring space of the through section is vertically divided into multiple sections in the circumferential direction. The vertical fins on the through-section inside wall and the fins on the equipment peripheral wall are contacted with each other by revolving them in the lateral direction. As a result, the natural convection caused by the difference of temperatures in the vertical direction of the ring space becomes a convection within each sector divided, and never generates circumferential circulation, which reduce uneven temperature distribution caused at the equipment through section. (Kawakami, Y.)

Design and Construction of Equipment for Applying the Geophysical Prospecting Method Electric Tomography

Directory of Open Access Journals (Sweden)

Fabio Héctor Giraldo Sánchez

2013-06-01

Full Text Available Outlines the procedure for the design and construction of electric equipment for geophysical prospecting through electrical tomography method. The team is of average power, ensuring exploration depths quite suitable for applications and commercial and geotechnical studies. The device is essentially a DC voltage source of 500 volts that is able to provide a maximum current of 1 amp. It also contains a small charge current source of electrical currents counteract naturally found in the subsoil and are manifested as a difference in the surface potential. A general explanation of the geophysical method in question, helps to understand the basic principles of operation of the equipment and functions to be fulfilled. After building the team, we conducted a field data acquisition, in area near the town of Gachancipa Cundinamarca. The data from this equipment are processed with specialized software. The images obtained with the software presents the distributions of subsurface resistivity can be associated with the possible structures and geology of the study area.

Equipment concepts for dry intercask transfer of spent fuel

International Nuclear Information System (INIS)

Schneider, K.J.

1983-07-01

This report documents the results of a study of preconceptual design and analysis of four intercask transfer concepts. The four concepts are: a large shielded cylindrical turntable that contains an integral fuel handling machine (turntable concept); a shielded fuel handling machine under which shipping and storage casks are moved horizontally (shuttle concept); a small hot cell containing equipment for transferring fuel between shipping and storage casks (that enter and leave the cell on carts) in a bifurcated trench (trench concept); and a large hot cell, shielded by an earthen berm, that houses equipment for handling fuel between casks that enter and leave the cell on a single cart (igloo concept). The casks considered in this study are most of the transport casks currently operable in the USA, and the storage casks designated REA-2023 and GNS Castor-V. Exclusive of basic services assumed to be provided at the host site, the design and capital costs are estimated to range from $9 to $13 million. The portion of capital costs for portable equipment (for potential later use at another site) was estimated to range from 70% to 98%, depending on the concept. Increasing portability from a range of 70 to 90% to 98% adds $2 to 4 million to the capital costs. Operating costs are estimated at about $2 million/year for all concepts. Implementation times range from about 18 months for the more conventional systems to 40 months for the more unique systems. Times and costs for relocation to another site are 10 to 14 months and about $1 million, plus shipping costs and costs of new construction at the new site. All concepts have estimated capacities for fuel transfer at least equal to the criterion set for this study. Only the hot cell concepts have capability for recanning or repair of canisters. Some development is believed to be required for the turntable and shuttle concepts, but none for the other two concepts

Management methodology for pressure equipment

Science.gov (United States)

Bletchly, P. J.

Pressure equipment constitutes a significant investment in capital and a major proportion of potential high-risk plant in many operations and this is particularly so in an alumina refinery. In many jurisdictions pressure equipment is also subject to statutory regulation that imposes obligations on Owners of the equipment with respect to workplace safety. Most modern technical standards and industry codes of practice employ a risk-based approach to support better decision making with respect to pressure equipment. For a management system to be effective it must demonstrate that risk is being managed within acceptable limits.

Identification and assessment of containment and release management strategies

International Nuclear Information System (INIS)

Lehner, J.R.; Lin, C.C.; Neogy, P.

1990-01-01

Brookhaven National Laboratory, under the auspices of the US Nuclear Regulatory Commission, is investigating accident management strategies which could help preserve containment integrity or minimize releases during a severe accident. The objective is to make use of existing plant systems and equipment in innovative ways to reduce the likelihood of containment failure or to mitigate the release of fission products to the environment if failure cannot be prevented. Many of the strategies would be implemented during the later stages of a severe accident. The identification and assessment process for containment and release strategies is described, and some insights derived from its application to a BWR Mark 1 plant are presented here. 13 refs., 2 figs

IE Information Notice No. 85-08: Industry experience on certain materials used in safety-related equipment

International Nuclear Information System (INIS)

Jordan, E.L.

1992-01-01

This information notice is being issued to provide licensees and construction permit holders with information pertaining to the behavior of certain materials used in safety-related equipment. The materials, as described below, were observed to have the potential of degrading the operability of safety-related equipment. These observations were made during environmental qualification testing and/or during routine inspection of in-service equipment. The notice describes the following: elastomeric seals used in personnel air locks for the reactor containment systems; epoxy phenolic coating applied to the lower portion of the interior surface of diesel oil storage tanks; the use of Viton elastomer as the seal material in hydrogen recombiner applications; and environmental qualification of ASCO NP valves with Viton and ethylene propylene parts

21 CFR 58.61 - Equipment design.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 1 2010-04-01 2010-04-01 false Equipment design. 58.61 Section 58.61 Food and... PRACTICE FOR NONCLINICAL LABORATORY STUDIES Equipment § 58.61 Equipment design. Equipment used in the... of appropriate design and adequate capacity to function according to the protocol and shall be...

21 CFR 866.4540 - Immunonephelometer equipment.

Science.gov (United States)

2010-04-01

...) MEDICAL DEVICES IMMUNOLOGY AND MICROBIOLOGY DEVICES Immunology Laboratory Equipment and Reagents § 866.4540 Immunonephelometer equipment. (a) Identification. Immunonephelometer equipment for clinical use...

Maintenance program guidelines for programmatic equipment

International Nuclear Information System (INIS)

1994-11-01

The Division Directors at Lawrence Berkeley Laboratory are responsible for implementing a maintenance program for research equipment (also referred to as programmatic equipment) assigned to them. The program must allow maintenance to be accomplished in a manner that promotes operational safety, environmental protection and compliance, and cost effectiveness; that preserves the intended functions of the facilities and equipment; and that supports the programmatic mission of the Laboratory. Programmatic equipment -- such as accelerators, lasers, radiation detection equipment, and glove boxes -- is dedicated specifically to research. Installed equipment, by contrast, includes the mechanical and electrical systems installed as part of basic building construction, equipment essential to the normal functioning of the facility and its intended use. Examples of installed equipment are heating, ventilating, and air conditioning systems; elevators; and communications systems. The LBL Operating and Assurance Program Plan (PUB-3111, Revision 4) requires that a maintenance program be prepared for programmatic equipment and defines the basic maintenance program elements. Such a program of regular, documented maintenance is vital to the safety and quality of research activities. As a part of that support, this document offers guidance to Laboratory organizations for developing their maintenance programs. It clarifies the maintenance requirements of the Operating and Assurance Program (OAP) and presents an approach that, while not the only possibility, can be expected to produce an effective maintenance program for research equipment belonging to the Laboratory's organizations

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.

Communications received from certain Member States regarding guidelines for the export of nuclear material, equipment and technology

International Nuclear Information System (INIS)

1992-07-01

The document reproduces the text of the notes verbales dated 15 May 1992, received by the Director General from the Resident Representatives to the Agency of Australia, Austria, Belgium, Bulgaria, Canada, Czech and Slovak Federal Republic, Denmark, Finland, France, Germany, Greece, Hungary, Ireland, Italy, Japan, Luxembourg, Netherlands, Norway, Poland, Portugal, Romania, Russia Federation, Spain, Sweden, Switzerland, the United Kingdom of Great Britain and Northern Ireland, and the United States of America relating to the export of nuclear material, equipment and technology and the Guidelines for Transfer of Nuclear-Related Dual-Use Equipment, Material and Related Technology. An Annex to these Guidelines contains the list of Nuclear-Related Dual-Use Equipment and Materials and Related Technology

Development of Turbulence-Measuring Equipment

Science.gov (United States)

Kovasznay, Leslie S G

1954-01-01

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

21 CFR 866.4520 - Immunofluorometer equipment.

Science.gov (United States)

2010-04-01

...) MEDICAL DEVICES IMMUNOLOGY AND MICROBIOLOGY DEVICES Immunology Laboratory Equipment and Reagents § 866.4520 Immunofluorometer equipment. (a) Identification. Immunofluorometer equipment for clinical use with...

Surface decontamination in the old storage shed number 99 of the General Plan of IPEN/CNEN-SP, containing production equipment of natural uranium hexafluoride (UF6), aiming at its decommissioning

International Nuclear Information System (INIS)

Almeida, Claudio C. de; Cambises, Paulo B.S.; Paiva, Julio E. de; Paiva, Julio E. de; Silva, Teresina M.; Rodrigues, Demerval L.

2013-01-01

This paper presents the steps adopted in the operation planned for the decontamination of surfaces in the old storage shed number 99 the general layout of the Energy Research and Nuclear IPEN-CNEN/SP, Brazil, and contained various types of equipment originating from production hexafluoride natural uranium (UF6). This operation involved the planning, training of operators of the facility, analysis of workplaces and radiometric surveys for monitoring of external radiation and surface contamination. The training involved the procedures for decontamination of surfaces, segregation of materials and practical procedures for individual monitoring of contamination outside of the body. Were also established rules for the transport of radioactive materials in the internal and external facility and release of material and sites already decontaminated

CASDAC system: Data Terminal Equipment user's guide

International Nuclear Information System (INIS)

Yamamoto, Yoichi; Koyama, Kinji

1993-03-01

The CASDAC (Containment And Surveillance Data Authenticated Communication) system has been developed by JAERI for nuclear safeguards and physical protection of nuclear material. This system is a remote monitoring system for continual verification of security and safeguards status of nuclear material. The CASDAC system consists of two subsystems, one of them is a Grand Command Center (GCC) subsystem and the other is a facility subsystem. This report describes the outline and usage of the Data Terminal Equipment (DTE), which makes available of message data communication between the GCC and a facility subsystem. This work has been carried out in the framework of Japan Support Programme for Agency Safeguards (JASPAS) as a project, JA-1. (author)

Data Center Equipment Location and Monitoring System

DEFF Research Database (Denmark)

2013-01-01

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

The gravitational plant physiology facility-Description of equipment developed for biological research in spacelab

Science.gov (United States)

Heathcote, D. G.; Chapman, D. K.; Brown, A. H.; Lewis, R. F.

1994-01-01

In January 1992, the NASA Suttle mission STS 42 carried a facility designed to perform experiments on plant gravi- and photo-tropic responses. This equipment, the Gravitational Plant Physiology Facility (GPPF) was made up of a number of interconnected units mounted within a Spacelab double rack. The details of these units and the plant growth containers designed for use in GPPF are described. The equipment functioned well during the mission and returned a substantial body of time-lapse video data on plant responses to tropistic stimuli under conditions of orbital microgravity. GPPF is maintained by NASA Ames Research Center, and is flight qualifiable for future spacelab missions.

Equipment Reliability Process in Krsko NPP

International Nuclear Information System (INIS)

Gluhak, M.

2016-01-01

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

Reinforced concrete containment structures in high seismic zones

International Nuclear Information System (INIS)

Aziz, T.S.

1977-01-01

A new structural concept for reinforced concrete containment structures at sites where earthquake ground motions in terms of the Safe Shutdown Earthquake (SSE) exceeds 0.3 g is presented. The structural concept is based on: (1) an inner steel-lined concrete shell which houses the reactor and provides shielding and containment in the event of loss of coolant accident; (2) an outer annular concrete shell structure which houses auxiliary reactor equipment and safeguards systems. These shell structures are supported on a common foundation mat which is embedded in the subgrade. Under stipulated earthquake conditions the two shell structures interact to resist lateral inertia forces. Thus the annular structure which is not a pressure boundary acts as a lateral support for the inner containment shell. The concept is practical, economically feasible and new to practice. (Auth.)

Data center equipment location and monitoring system

DEFF Research Database (Denmark)

2011-01-01

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

PFP vault operations containers for Plutonium Handling and Storage Critical Characteristics

International Nuclear Information System (INIS)

BONADIE, E.P.

2000-01-01

This document specifies the critical characteristics for containers procured for Plutonium Finishing Plant's (PFP's) Vault Operations system as required by HNF-PRO-268 and HNF-PRO-1819. These are the minimum specifications that the equipment must meet in order to perform its safety function

Natural phenomena hazards evaluation of equipment and piping of Gaseous Diffusion Plant Uranium Enrichment Facility

International Nuclear Information System (INIS)

Singhal, M.K.; Kincaid, J.H.; Hammond, C.R.; Stockdale, B.I.; Walls, J.C.

1995-01-01

In support of the Gaseous Diffusion Plant Safety Analysis Report Upgrade program (GDP SARUP), a natural phenomena hazards evaluation was performed for the main process equipment and piping in the uranium enrichment buildings at Paducah and Portsmouth gaseous diffusion plants. In order to reduce the cost of rigorous analyses, the evaluation methodology utilized a graded approach based on an experience data base collected by SQUG/EPRI that contains information on the performance of industrial equipment and piping during past earthquakes. This method consisted of a screening walkthrough of the facility in combination with the use of engineering judgment and simple calculations. By using these screenings combined with evaluations that contain decreasing conservatism, reductions in the time and cost of the analyses were significant. A team of experienced seismic engineers who were trained in the use of the DOE SQUG/EPRI Walkdown Screening Material was essential to the success of this natural phenomena hazards evaluation

Natural phenomena hazards evaluation of equipment and piping of Gaseous Diffusion Plant Uranium Enrichment Facility

Energy Technology Data Exchange (ETDEWEB)

Singhal, M.K.; Kincaid, J.H.; Hammond, C.R.; Stockdale, B.I.; Walls, J.C. [Oak Ridge National Lab., TN (United States). Technical Programs and Services; Brock, W.R.; Denton, D.R. [Lockheed Martin Energy Systems, Inc., Oak Ridge, TN (United States)

1995-12-31

In support of the Gaseous Diffusion Plant Safety Analysis Report Upgrade program (GDP SARUP), a natural phenomena hazards evaluation was performed for the main process equipment and piping in the uranium enrichment buildings at Paducah and Portsmouth gaseous diffusion plants. In order to reduce the cost of rigorous analyses, the evaluation methodology utilized a graded approach based on an experience data base collected by SQUG/EPRI that contains information on the performance of industrial equipment and piping during past earthquakes. This method consisted of a screening walkthrough of the facility in combination with the use of engineering judgment and simple calculations. By using these screenings combined with evaluations that contain decreasing conservatism, reductions in the time and cost of the analyses were significant. A team of experienced seismic engineers who were trained in the use of the DOE SQUG/EPRI Walkdown Screening Material was essential to the success of this natural phenomena hazards evaluation.

Analysis of containment venting for the Peach Bottom Atomic Power Station

International Nuclear Information System (INIS)

Hanson, D.J.; Wright, R.E.; Jenkins, J.P.

1986-01-01

The effectiveness of containment venting as a means of preventing or mitigating the consequences of severe accidents was evaluated for Peach Bottom Atomic Power Station Units 2 and 3 (BWR-4s with Mark I containments). Results from this evaluation indicate that the effectiveness of venting in preventing containment failure is highly dependent on the severe accident sequence. Containment venting can be effective for several classes of sequences, including loss-of-coolant accidents with breaks in the containment and transients with a failure of containment heat removal. However, based on draft procedures and equipment in place at the time of the evaluation, containment venting has limited potential for further reducing the risk associated with several sequences currently identified as significant contributors to risk. Means of improving the potential for risk reduction were identified, but their influence on risk was not analyzed

7 CFR 3015.167 - Replacement of equipment.

Science.gov (United States)

2010-01-01

... 7 Agriculture 15 2010-01-01 2010-01-01 false Replacement of equipment. 3015.167 Section 3015.167..., DEPARTMENT OF AGRICULTURE UNIFORM FEDERAL ASSISTANCE REGULATIONS Property § 3015.167 Replacement of equipment. (a) If needed, equipment may be exchanged for replacement equipment. Replacement of equipment may be...

Use of commercial grade equipment and industrial standards for equipment qualification

International Nuclear Information System (INIS)

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

1984-01-01

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

Cooling of electronic equipment

DEFF Research Database (Denmark)

A. Kristensen, Anders Schmidt

2003-01-01

Cooling of electronic equipment is studied. The design size of electronic equipment decrease causing the thermal density to increase. This affect the cooling which can cause for example failures of critical components due to overheating or thermal induced stresses. Initially a pin fin heat sink...

46 CFR 180.175 - Survival craft equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Survival craft equipment. 180.175 Section 180.175... TONS) LIFESAVING EQUIPMENT AND ARRANGEMENTS Survival Craft Arrangements and Equipment § 180.175 Survival craft equipment. (a) General. Each item of survival craft equipment must be of good quality, and...

Prioritizing equipment for replacement.

Science.gov (United States)

Capuano, Mike

2010-01-01

It is suggested that clinical engineers take the lead in formulating evaluation processes to recommend equipment replacement. Their skill, knowledge, and experience, combined with access to equipment databases, make them a logical choice. Based on ideas from Fennigkoh's scheme, elements such as age, vendor support, accumulated maintenance cost, and function/risk were used.6 Other more subjective criteria such as cost benefits and efficacy of newer technology were not used. The element of downtime was also omitted due to the data element not being available. The resulting Periop Master Equipment List and its rationale was presented to the Perioperative Services Program Council. They deemed the criteria to be robust and provided overwhelming acceptance of the list. It was quickly put to use to estimate required capital funding, justify items already thought to need replacement, and identify high-priority ranked items for replacement. Incorporating prioritization criteria into an existing equipment database would be ideal. Some commercially available systems do have the basic elements of this. Maintaining replacement data can be labor-intensive regardless of the method used. There is usually little time to perform the tasks necessary for prioritizing equipment. However, where appropriate, a clinical engineering department might be able to conduct such an exercise as shown in the following case study.

46 CFR 108.719 - Pilot boarding equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Pilot boarding equipment. 108.719 Section 108.719... AND EQUIPMENT Miscellaneous Equipment § 108.719 Pilot boarding equipment. (a) This section applies to... vessel must have suitable pilot boarding equipment available for use on each side of the vessel. If a...

46 CFR 109.347 - Pilot boarding equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Pilot boarding equipment. 109.347 Section 109.347... OPERATIONS Operation and Stowage of Safety Equipment § 109.347 Pilot boarding equipment. (a) The master or person in charge shall ensure that pilot boarding equipment is maintained as follows: (1) The equipment...

Equipment Management for Sensor Networks: Linking Physical Infrastructure and Actions to Observational Data

Science.gov (United States)

Jones, A. S.; Horsburgh, J. S.; Matos, M.; Caraballo, J.

2015-12-01

Networks conducting long term monitoring using in situ sensors need the functionality to track physical equipment as well as deployments, calibrations, and other actions related to site and equipment maintenance. The observational data being generated by sensors are enhanced if direct linkages to equipment details and actions can be made. This type of information is typically recorded in field notebooks or in static files, which are rarely linked to observations in a way that could be used to interpret results. However, the record of field activities is often relevant to analysis or post-processing of the observational data. We have developed an underlying database schema and deployed a web interface for recording and retrieving information on physical infrastructure and related actions for observational networks. The database schema for equipment was designed as an extension to the Observations Data Model 2 (ODM2), a community-developed information model for spatially discrete, feature based earth observations. The core entities of ODM2 describe location, observed variable, and timing of observations, and the equipment extension contains entities to provide additional metadata specific to the inventory of physical infrastructure and associated actions. The schema is implemented in a relational database system for storage and management with an associated web interface. We designed the web-based tools for technicians to enter and query information on the physical equipment and actions such as site visits, equipment deployments, maintenance, and calibrations. These tools were implemented for the iUTAH (innovative Urban Transitions and Aridregion Hydrosustainability) ecohydrologic observatory, and we anticipate that they will be useful for similar large-scale monitoring networks desiring to link observing infrastructure to observational data to increase the quality of sensor-based data products.

Information technology equipment cooling system

Science.gov (United States)

Schultz, Mark D.

2014-06-10

According to one embodiment, a system for removing heat from a rack of information technology equipment may include a sidecar indoor air to liquid heat exchanger that cools warm air generated by the rack of information technology equipment. The system may also include a liquid to liquid heat exchanger and an outdoor heat exchanger. The system may further include configurable pathways to connect and control fluid flow through the sidecar heat exchanger, the liquid to liquid heat exchanger, the rack of information technology equipment, and the outdoor heat exchanger based upon ambient temperature and/or ambient humidity to remove heat from the rack of information technology equipment.

Isotope-equipped measuring instruments

International Nuclear Information System (INIS)

Miyagawa, Kazuo; Amano, Hiroshi

1980-01-01

In the steel industry, though the investment in isotope-equipped measuring instruments is small as compared with that in machinery, they play important role in the moisture measurement in sintering and blast furnaces, the thickness measurement in rolling process and others in automatic control systems. The economic aspect of the isotope-equipped measuring instruments is described on the basis of the practices in Kimitsu Works of Nippon Steel Corporation: distribution of such instruments, evaluation of economic effects, usefulness evaluation in view of raising the accuracy, and usefulness evaluation viewed from the failure of the isotope instruments. The evaluation of economic effects was made under the premise that the isotope-equipped measuring instruments are not employed. Then, the effects of raising the accuracy are evaluated for a γ-ray plate thickness gauge and a neutron moisture gauge for coke in a blast furnace. Finally, the usefulness was evaluated, assuming possible failure of the isotope-equipped measuring instruments. (J.P.N.)

Electronic equipment packaging technology

CERN Document Server

Ginsberg, Gerald L

1992-01-01

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

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)

Characterization of Hanford tank wastes containing ferrocyanides

International Nuclear Information System (INIS)

Tingey, J.M.; Matheson, J.D.; McKinley, S.G.; Jones, T.E.; Pool, K.H.

1993-02-01

Currently, 17 storage tanks on the Hanford site that are believed to contain > 1,000 gram moles (465 lbs) of ferrocyanide compounds have been identified. Seven other tanks are classified as ferrocyanide containing waste tanks, but contain less than 1,000 gram moles of ferrocyanide compounds. These seven tanks are still included as Hanford Watch List Tanks. These tanks have been declared an unreviewed safety question (USQ) because of potential thermal reactivity hazards associated with the ferrocyanide compounds and nitrate and nitrite. Hanford tanks with waste containing > 1,000 gram moles of ferrocyanide have been sampled. Extensive chemical, radiothermical, and physical characterization have been performed on these waste samples. The reactivity of these wastes were also studied using Differential Scanning Calorimetry (DSC) and Thermogravimetric analysis. Actual tank waste samples were retrieved from tank 241-C-112 using a specially designed and equipped core-sampling truck. Only a small portion of the data obtained from this characterization effort will be reported in this paper. This report will deal primarily with the cyanide and carbon analyses, thermal analyses, and limited physical property measurements

Annual report on the state of RB reactor components and equipment, December 1997

International Nuclear Information System (INIS)

Milosevic, M.

1997-12-01

According to the performed analysis, it is considered that the RB reactor can be operated safely until the existing control and safety systems could be maintained in satisfactory operable state. Failures of heavy water circulation system valves which may cause decreased availability but no accident. During 1997 the reactor lattice was not changed due to application of the coupled fast-thermal core HERBE. Total reactor operation amounted to 69.5 Wh with 66 start-ups (attained criticality levels). This report contains 4 Annexes, detailed description of the state of reactor equipment, plan for forming new HERBE core, plan for regular annual maintenance of the reactor, and plan for minimum needed resources for regular maintenance of the components and equipment in the forthcoming year

Work inside ocean freight containers--personal exposure to off-gassing chemicals.

Science.gov (United States)

Svedberg, Urban; Johanson, Gunnar

2013-11-01

More than 500 million ocean freight container units are shipped annually between countries and continents. Residual levels of fumigants, as well as naturally occurring off-gassing chemicals emanating from the goods, constitute safety risks, which may affect uniformed workers upon entering the container. The aim of this study was to assess workers' exposure during stripping of containers and is the first study of its kind. First, an experimental tracer gas method was investigated to determine its usefulness to approximate real exposures from gaseous fumigants and off-gassing volatile organic compounds (VOCs). Nitrous oxide was injected and left to distribute in the closed containers. The distribution of the tracer gas and initial (arrival) concentrations of off-gassing volatiles were measured prior to opening the containers. Second, personal exposure (breathing zone) and work zone air monitoring of both tracer gas and VOCs were carried out during stripping. Adsorbent tubes, bag samples, and direct-readings instruments (photoionization detector and Fourier transform infrared spectrometry) were used. The distribution studies with nitrous oxide, and the high correlation between the former and VOCs (r(2) ~ 0.8) during stripping, showed that the tracer gas method may well be used to approximate real exposures in containers. The average breathing zone and work zone concentrations during stripping of naturally ventilated 40-foot containers were 1-7% of the arrival concentrations; however, peaks up to 70% were seen during opening. Even if average exposures during stripping are significantly lower than arrival concentrations, they may still represent serious violations of occupational exposure limits in high-risk containers. The results from this and previous studies illustrate the need to establish practices for the safe handling of ocean freight containers. Until comprehensive recommendations are in place, personnel that need to enter such containers should, in addition to

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

International Nuclear Information System (INIS)

Wojas, M.; Walczak, M.

2006-01-01

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

Proceedings of FED remote maintenance equipment workshop

International Nuclear Information System (INIS)

Sager, P.; Garin, J.; Hager, E.R.; Spampinato, P.T.; Tobias, D.; Young, N.

1981-11-01

A workshop was convened in two sessions in January and March 1981, on the remote maintenance equipment for the Fusion Engineering Device (FED). The objectives of the first session were to familiarize the participants with the status of the design of the FED and to develop a remote maintenance equipment list for the FED. The objective of the second session was to have the participants present design concepts for the equipment which had been identified in the first session. The equipment list was developed for general purpose and special purpose equipment. The general purpose equipment was categorized as manipulators and other, while the special purpose equipment was subdivided according to the reactor subsystem it serviced: electrical, magnetic, and nuclear. Both mobile and fixed base manipulators were identified. Handling machines were identified as the major requirement for special purpose equipment

Capital Equipment Replacement Decisions

OpenAIRE

Batterham, Robert L.; Fraser, K.I.

1995-01-01

This paper reviews the literature on the optimal replacement of capital equipment, especially farm machinery. It also considers the influence of taxation and capital rationing on replacement decisions. It concludes that special taxation provisions such as accelerated depreciation and investment allowances are unlikely to greatly influence farmers' capital equipment replacement decisions in Australia.

The development of ISO freight containers as IP-2 packagings

International Nuclear Information System (INIS)

Janicki, M.C.; Vaughan, R.A.

1993-01-01

Design specifications were developed for ISO freight containers to meet the requirements of the transport regulations in the 1985 Edition of IAEA SS6, and to maximize the technical and commercial benefits offered to consignors by this type of container for the transport and handling of bulk LSA/SCO materials. A range of IP-2 ISO freight containers have been designed and built to these specifications and are in use in the UK. This paper discusses the regulatory considerations which had to be reviewed and interpreted in developing freight containers as Industrial Package Type 2 (IP-2) packagings and the development of performance standards to meet the regulatory requirements. Outline details of the packages developed are indicated together with examples of handling equipment developed to facilitate loading and unloading. (J.P.N.)

Alternative Fuels Data Center: Biodiesel Equipment Options

Science.gov (United States)

Equipment Options to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Equipment Options on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Equipment Options on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Equipment Options on Google Bookmark Alternative Fuels

Potential of the tractor-trailer and container segments as entry markets for a proposed refrigeration technology

Energy Technology Data Exchange (ETDEWEB)

Smith, S.A.; Davis, L.J.; Garrett, B.A.

1987-05-01

The refrigerated trailer and container segments of the transportation industry are evaluated as potential entry markets for a proposed absorption refrigeration technology. To perform this analysis the existing transportation refrigeration industry is characterized; this includes a description of the current refrigeration technology, rating systems, equipment manufacturers, maintenance requirements, and sales trends. This information indicates that the current transportation refrigeration industry is composed of two major competitors, Thermo King and Carrier. In addition, it has low profit potential, some barriers to entry and low growth potential. Data are also presented that characterize the transportation refrigeration consumers, specifically, major groups, market segmentation, consumer decision process, and buying criteria. This consumer information indicates that the majority of refrigerated trailer consumers are private carriers, and that the majority of refrigerated container consumers are shipping companies. Also, these consumers are primarily interested in buying reliable equipment at a low price, and are quite satisfied with existing refrigeration equipment.

7 CFR 1753.68 - Purchasing special equipment.

Science.gov (United States)

2010-01-01

... 7 Agriculture 11 2010-01-01 2010-01-01 false Purchasing special equipment. 1753.68 Section 1753.68... AGRICULTURE TELECOMMUNICATIONS SYSTEM CONSTRUCTION POLICIES AND PROCEDURES Purchase and Installation of Special Equipment § 1753.68 Purchasing special equipment. (a) General. (1) Equipment purchases are...

Lifetime of Mechanical Equipment

Energy Technology Data Exchange (ETDEWEB)

Leland, K.

1999-07-01

The gas plant at Kaarstoe was built as part of the Statpipe gas transport system and went on stream in 1985. In 1993 another line was routed from the Sleipner field to carry condensate, and the plant was extended accordingly. Today heavy additional supply- and export lines are under construction, and the plant is extended more than ever. The main role of the factory is to separate the raw gas into commercial products and to pump or ship it to the markets. The site covers a large number of well-known mechanical equipment. This presentation deals with piping, mechanical and structural disciplines. The lifetime of mechanical equipment is often difficult to predict as it depends on many factors, and the subject is complex. Mechanical equipment has been kept in-house, which provides detailed knowledge of the stages from a new to a 14 years old plant. The production regularity has always been very high, as required. The standard of the equipment is well kept, support systems are efficient, and human improvisation is extremely valuable.

49 CFR 174.85 - Position in train of placarded cars, transport vehicles, freight containers, and bulk packagings.

Science.gov (United States)

2010-10-01

... Vehicles and Freight Containers § 174.85 Position in train of placarded cars, transport vehicles, freight... position in a train of each loaded placarded car, transport vehicle, freight container, and bulk packaging..., and other specially equipped cars with tie-down devices for securing vehicles. Permanent bulk head...

Soundness confirmation through cold test of the system equipment of HTTR

International Nuclear Information System (INIS)

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

2014-01-01

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

46 CFR 184.210 - Heating equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Heating equipment. 184.210 Section 184.210 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) SMALL PASSENGER VESSELS (UNDER 100 GROSS TONS) VESSEL CONTROL AND MISCELLANEOUS SYSTEMS AND EQUIPMENT Cooking and Heating § 184.210 Heating equipment...

High-level waste tank modifications, installation of mobilization equipment/check out

International Nuclear Information System (INIS)

Schiffhauer, M.A.; Thompson, S.C.

1992-01-01

PUREX high-level waste (HLW) is contained at the West Valley Demonstration Project (WVDP) in an underground carbon-steel storage tank. The HLW consists of a precipitated sludge and an alkaline supernate. This report describes the system that the WVDP has developed and implemented to resuspend and wash the HLW sludge from the tank. The report discusses Sludge Mobilization and Wash System (SMWS) equipment design, installation, and testing. The storage tank required modifications to accommodate the SMWS. These modifications are discussed as well

40 CFR 1054.626 - What special provisions apply to equipment imported under the Transition Program for Equipment...

Science.gov (United States)

2010-07-01

... EMISSIONS FROM NEW, SMALL NONROAD SPARK-IGNITION ENGINES AND EQUIPMENT Special Compliance Provisions § 1054... provisions of this section and send us an annual report, as follows: (1) Notify the Designated Compliance... and manufacturing equipment. Companies that import equipment into the United States without meeting...

46 CFR 184.220 - Cooking equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Cooking equipment. 184.220 Section 184.220 Shipping...) VESSEL CONTROL AND MISCELLANEOUS SYSTEMS AND EQUIPMENT Cooking and Heating § 184.220 Cooking equipment. (a) Doors on a cooking appliance must be provided with hinges and locking devices to prevent...

46 CFR 121.210 - Heating equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Heating equipment. 121.210 Section 121.210 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) SMALL PASSENGER VESSELS CARRYING MORE THAN 150... SYSTEMS AND EQUIPMENT Cooking and Heating § 121.210 Heating equipment. (a) Each heater must be so...

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

Mississippi Curriculum Framework for Diesel Equipment Technology (CIP: 47.0605--Diesel Engine Mechanic & Repairer). Postsecondary Programs.

Science.gov (United States)

Mississippi Research and Curriculum Unit for Vocational and Technical Education, State College.

This document, which is intended for use by community and junior colleges throughout Mississippi, contains curriculum frameworks for the course sequences in the diesel equipment technology programs cluster. Presented in the introductory section are a description of the program and suggested course sequence. Section I lists baseline competencies,…

Containment structure tendon investigation

International Nuclear Information System (INIS)

Fulton, J.F.; Murray, K.H.

1983-01-01

The paper describes an investigation into the possible causes of lower-than-predicted tendon forces which were measured during past tendon surveillances for a concrete containment. The containment is post tensioned by vertical tendons which are anchored into a rock foundation. The tendons were originally stressed in 1969, and lift-off tests were performed on six occasions subsequent to this date over a period of 11 years. The tendon forces measured in these tests were generally lower than predicted, and by 1979 the prestress level in the containment was only marginally above the design requirement. The tendons were retensioned in 1980, and by this time an investigation into the possible causes was underway. Potential causes investigated include the rock anchors and surrounding rock, elastomeric pad creep, wire stresses, thermal effects, stressing equipment and lift-off procedures, and wire stress relaxation. The investigation activities included stress relaxation testing of wires pulled from actual tendons. The stress relaxation test program included wire specimens at several different temperature and initial stress levels and the effect of a varying temperature history on the stress relaxation property of the wires. For purpose of future force predictions of the retensioned tendons, the test program included tests to determine the effect on stress relaxation due to restressing the wires after they had relaxed for 1000 hours and 10,000 hours. (orig./GL)

30 CFR 72.520 - Diesel equipment inventory.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Diesel equipment inventory. 72.520 Section 72... Mines § 72.520 Diesel equipment inventory. (a) The operator of each mine that utilizes diesel equipment underground, shall prepare and submit in writing to the District Manager, an inventory of diesel equipment...

46 CFR 117.175 - Survival craft equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Survival craft equipment. 117.175 Section 117.175... AND ARRANGEMENTS Survival Craft Arrangements and Equipment § 117.175 Survival craft equipment. (a) General. Each item of survival craft equipment must be of good quality, and efficient for the purpose it...

Analysis of containment venting at the Peach Bottom atomic power station

International Nuclear Information System (INIS)

Hanson, D.J.; Blackman, H.S.; Nelson, W.R.; Wright, R.E.; Leonard, M.T.; DiSalvo, R.

1988-01-01

An analysis of the extent to which containment venting would be effective in preventing or mitigating the consequences of severe accidents has been completed for the Peach Bottom Units 2 and 3 (BWR-4s with Mark I containments). The analysis indicates that the effectiveness of venting in preventing containment overpressurization highly depends on the sequence of the severe accident. Containment venting can be effective for several classes of sequences, including transients with failure of long-term decay heat removal and loss-of-coolant accidents with breaks inside the containment. However, based on draft procedures and equipment in place at the time of the evaluation, containment venting has limited potential for further reducing the risk associated with three severe accident sequences currently identified as important risk contributors at Peach Bottom. Means of improving the potential for risk reduction is identified, but their influence on risk is not analyzed. (orig./HP)

Analysis of containment venting at the Peach Bottom Atomic Power Station

International Nuclear Information System (INIS)

Hanson, D.J.; Blackman, H.S.; Nelson, W.R.; Wright, R.E.; Leonard, M.T.; DiSalvo, R.

1986-01-01

An analysis of the extent to which containment venting would be effective in preventing or mitigating the consequences of severe accidents has been completed for the Peach Bottom Atomic Power Station, Units 2 and 3 (BWR-4s with Mark I containments). The analysis indicates that the effectiveness of venting in preventing containment overpressurization highly depends on the sequence of the severe accident. Containment venting can be effective for several classes of sequences, including transients with failure of long-term decay heat removal and loss-of-coolant accidents with breaks inside the containment. However, based on draft procedures and equipment in place at the time of the evaluation, containment venting has limited potential for further reducing the risk associated with three severe accident sequences currently identified as important risk contributors at Peach Bottom. Means of improving the potential for risk reduction is identified, but their influence on risk is not analyzed

NPP Krsko Containment Response Following Main Steam Line Break

International Nuclear Information System (INIS)

Spalj, S.; Grgic, D.; Cavlina, N.

2000-01-01

This paper presents the calculation of thermohydraulic environmental parameters (pressure and temperature) inside containment of Krsko NPP after postulated Main Steam Line Break (MSLB) accident. This analysis was done as a part of the ambient parameters specification in the frame of the NPP Krsko Equipment Qualification (EQ) project. The RELAP5/mod2 computer code was used for the determination of MSLB mass and energy release and computer code GOTHIC was used to calculate pressure and temperature profiles inside NPP Krsko containment. The analysis was performed for spectrum of break sizes to account for possible steam superheating during accidents with smaller break sizes. (author)

The Cost of Maintaining Educational Communications Equipment.

Science.gov (United States)

Humphrey, David A.

Tentative formulas for calculating the cost of maintaining educational communications equipment are proposed. The formulas are based on a survey of campuses of the State University of New York. The survey analyzed the types of equipment to be maintained, types of maintenance, who uses the equipment, who services the equipment, and the cost…

A Heuristic Procedure for the Outbound Container Relocation Problem during Export Loading Operations

Directory of Open Access Journals (Sweden)

Roberto Guerra-Olivares

2015-01-01

Full Text Available During export ship loading operations, it is often necessary to perform relocation movements with containers that interfere with access to the desired container in the ship loading sequence. This paper presents a real-time heuristic procedure for the container relocation problem employing reachstacker vehicles as container handling equipment. The proposed heuristic searches for good relocation coordinates within a set of nearby bays. The heuristic has a parameter that determines how far from the original bay a container may be relocated. The tradeoff between reducing relocation movements and limiting vehicle travel distances is examined and the performance of the heuristic is compared with a common practice in the smaller container terminals in Chile and Mexico. Finally, a mathematical model for the container relocation problem is presented.

Protective equipment use among female rugby players.

Science.gov (United States)

Comstock, R Dawn; Fields, Sarah K; Knox, Christy L

2005-07-01

Our objective was to assess the prevalence of protective equipment use and the motivation for using protective equipment among a sample of US female rugby players. We surveyed a convenience sample of 234 current US female rugby players from 14 teams participating in a US women's rugby tournament, obtaining self-reported demographic, rugby exposure, and protective equipment use information. Mouthguards were the most commonly used piece of protective equipment: 90.8% of players reported having always worn a mouthguard while playing or practicing rugby within their most recent 3 months of play. Fewer than 15% of players reported having always worn other types of protective equipment. Equipment use varied by playing position. Whereas over 80% of players in all other positions always wore a mouthguard, 66.7% of scrum halves reported always wearing one. Both backs and forwards reported wearing shoulder pads, but only forwards reported always wearing padded headgear. Mouthguards, padded headgear, and shoulder pads were worn "to prevent injury," whereas ankle braces, neoprene sleeves, and athletic tape on joints were worn "to protect a current/recent injury." This is the first study of female rugby players to assess the prevalence of protective equipment use by playing position and the motivation for using protective equipment. With the exception of mouthguards, US female rugby players infrequently use protective equipment. Protective equipment use varies by playing position. Some types of protective equipment appear to be used as primary prevention mechanisms, whereas others are used as secondary or tertiary prevention mechanisms.

Equipment available for automating rig operations

International Nuclear Information System (INIS)

McNair, W.L.

1990-01-01

Several manufacturers are producing automated rig equipment, from complete systems to individual functions for existing drilling rigs. Significant improvements in well site time, costs of operations, and improved drilling performance have led drilling contractors to install this equipment on their rigs. This paper details some of the equipment available for automating rigs

14 CFR 121.605 - Airplane equipment.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Airplane equipment. 121.605 Section 121.605..., FLAG, AND SUPPLEMENTAL OPERATIONS Dispatching and Flight Release Rules § 121.605 Airplane equipment. No person may dispatch or release an airplane unless it is airworthy and is equipped as prescribed in § 121...

Equipment Reliability Program in NPP Krsko

International Nuclear Information System (INIS)

Skaler, F.; Djetelic, N.

2006-01-01

Operation that is safe, reliable, effective and acceptable to public is the common message in a mission statement of commercial nuclear power plants (NPPs). To fulfill these goals, nuclear industry, among other areas, has to focus on: 1 Human Performance (HU) and 2 Equipment Reliability (EQ). The performance objective of HU is as follows: The behaviors of all personnel result in safe and reliable station operation. While unwanted human behaviors in operations mostly result directly in the event, the behavior flaws either in the area of maintenance or engineering usually cause decreased equipment reliability. Unsatisfied Human performance leads even the best designed power plants into significant operating events, which can be found as well-known examples in nuclear industry. Equipment reliability is today recognized as the key to success. While the human performance at most NPPs has been improving since the start of WANO / INPO / IAEA evaluations, the open energy market has forced the nuclear plants to reduce production costs and operate more reliably and effectively. The balance between these two (opposite) goals has made equipment reliability even more important for safe, reliable and efficient production. Insisting on on-line operation by ignoring some principles of safety could nowadays in a well-developed safety culture and human performance environment exceed the cost of electricity losses. In last decade the leading USA nuclear companies put a lot of effort to improve equipment reliability primarily based on INPO Equipment Reliability Program AP-913 at their NPP stations. The Equipment Reliability Program is the key program not only for safe and reliable operation, but also for the Life Cycle Management and Aging Management on the way to the nuclear power plant life extension. The purpose of Equipment Reliability process is to identify, organize, integrate and coordinate equipment reliability activities (preventive and predictive maintenance, maintenance

Modelling and Simulation Methodology for Dynamic Resources Assignment System in Container Terminal

Directory of Open Access Journals (Sweden)

Lu Bo

2016-10-01

Full Text Available As the competition among international container terminals has become increasingly fierce, every port is striving to maintain the competitive edge and provide satisfactory services to port users. By virtue of information technology enhancement, many efforts to raise port competitiveness through an advanced operation system are actively being made, and judging from the viewpoint of investment effect, these efforts are more preferable than infrastructure expansion and additional equipment acquisition. Based on simulation, this study has tried to prove that RFID-based real-time location system (RTLS data collection and dynamic operation of transfer equipment brings a positive effect on the productivity improvement and resource utilization enhancement. Moreover, this study on the demand for the real-time data for container terminal operation have been made, and operation processes have been redesigned along with the collection of related data, and based on them, simulations have been conducted. As a result of them, much higher productivity improvement could be expected.

DISPOSAL CONTAINER HANDLING SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

E. F. Loros

2000-06-30

The Disposal Container Handling System receives and prepares new disposal containers (DCs) and transfers them to the Assembly Transfer System (ATS) or Canister Transfer System (CTS) for loading. The system receives the loaded DCs from ATS or CTS and welds the lids. When the welds are accepted the DCs are termed waste packages (WPs). The system may stage the WP for later transfer or transfer the WP directly to the Waste Emplacement/Retrieval System. The system can also transfer DCs/WPs to/from the Waste Package Remediation System. The Disposal Container Handling System begins with new DC preparation, which includes installing collars, tilting the DC upright, and outfitting the container for the specific fuel it is to receive. DCs and their lids are staged in the receipt area for transfer to the needed location. When called for, a DC is put on a cart and sent through an airlock into a hot cell. From this point on, all processes are done remotely. The DC transfer operation moves the DC to the ATS or CTS for loading and then receives the DC for welding. The DC welding operation receives loaded DCs directly from the waste handling lines or from interim lag storage for welding of the lids. The welding operation includes mounting the DC on a turntable, removing lid seals, and installing and welding the inner and outer lids. After the weld process and non-destructive examination are successfully completed, the WP is either staged or transferred to a tilting station. At the tilting station, the WP is tilted horizontally onto a cart and the collars removed. The cart is taken through an air lock where the WP is lifted, surveyed, decontaminated if required, and then moved into the Waste Emplacement/Retrieval System. DCs that do not meet the welding non-destructive examination criteria are transferred to the Waste Package Remediation System for weld preparation or removal of the lids. The Disposal Container Handling System is contained within the Waste Handling Building System

30 CFR 250.602 - Equipment movement.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Equipment movement. 250.602 Section 250.602... OPERATIONS IN THE OUTER CONTINENTAL SHELF Oil and Gas Well-Workover Operations § 250.602 Equipment movement. The movement of well-workover rigs and related equipment on and off a platform or from well to well on...

30 CFR 250.502 - Equipment movement.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Equipment movement. 250.502 Section 250.502... OPERATIONS IN THE OUTER CONTINENTAL SHELF Oil and Gas Well-Completion Operations § 250.502 Equipment movement. The movement of well-completion rigs and related equipment on and off a platform or from well to well...

46 CFR 121.220 - Cooking equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Cooking equipment. 121.220 Section 121.220 Shipping... SYSTEMS AND EQUIPMENT Cooking and Heating § 121.220 Cooking equipment. (a) Doors on a cooking appliance... cooking appliance must be installed to prevent movement in heavy seas. (c) For a grill or similar type of...

Californium-252 Program Equipment Evaluation

Energy Technology Data Exchange (ETDEWEB)

Chattin, Fred Rhea [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wilson, Kenton [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ezold, Julie G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-12-01

To successfully continue the ²⁵²Cf production and meet the needs of the customers, a comprehensive evaluation of the Building 7920 processing equipment was requested to identify equipment critical to the operational continuity of the program.

After-hours Power Status of Office Equipment and Inventory of Miscellaneous Plug-load Equipment

Energy Technology Data Exchange (ETDEWEB)

Roberson, Judy A.; Webber, Carrie A.; McWhinney, Marla C.; Brown, Richard E.; Pinckard, Margaret J.; Busch, John F.

2004-01-22

This research was conducted in support of two branches of the EPA ENERGY STAR program, whose overall goal is to reduce, through voluntary market-based means, the amount of carbon dioxide emitted in the U.S. The primary objective was to collect data for the ENERGY STAR Office Equipment program on the after-hours power state of computers, monitors, printers, copiers, scanners, fax machines, and multi-function devices. We also collected data for the ENERGY STAR Commercial Buildings branch on the types and amounts of ''miscellaneous'' plug-load equipment, a significant and growing end use that is not usually accounted for by building energy managers. This data set is the first of its kind that we know of, and is an important first step in characterizing miscellaneous plug loads in commercial buildings. The main purpose of this study is to supplement and update previous data we collected on the extent to which electronic office equipment is turned off or automatically enters a low power state when not in active use. In addition, it provides data on numbers and types of office equipment, and helps identify trends in office equipment usage patterns. These data improve our estimates of typical unit energy consumption and savings for each equipment type, and enables the ENERGY STAR Office Equipment program to focus future effort on products with the highest energy savings potential. This study expands our previous sample of office buildings in California and Washington DC to include education and health care facilities, and buildings in other states. We report data from twelve commercial buildings in California, Georgia, and Pennsylvania: two health care buildings, two large offices (> 500 employees each), three medium offices (50-500 employees), four education buildings, and one ''small office'' that is actually an aggregate of five small businesses. Two buildings are in the San Francisco Bay area of California, five are in

AVM branch vibration test equipment

International Nuclear Information System (INIS)

Anne, J.P.

1995-01-01

An inventory of the test equipment of the AVM Branch ''Acoustic and Vibratory Mechanics Analysis Methods'' group has been undertaken. The purpose of this inventory is to enable better acquaintance with the technical characteristics of the equipment, providing an accurate definition of their functionalities, ad to inform potential users of the possibilities and equipment available in this field. The report first summarizes the various experimental surveys conduced. Then, using the AVM equipment database to draw up an exhaustive list of available equipment, it provides a full-scope picture of the vibration measurement systems (sensors, conditioners and exciters) and data processing resources commonly used on industrial sites and in laboratories. A definition is also given of a mobile test unit, called 'shelter', and a test bench used for the testing and performance rating of the experimental analysis methods developed by the group. The report concludes with a description of two fixed installations: - the calibration bench ensuring the requisite quality level for the vibration measurement systems ; - the training bench, whereby know-how acquired in the field in the field of measurement and experimental analysis processes is made available to others. (author). 27 refs., 15 figs., 2 appends

Application of electron irradiation to food containers and packaging materials

International Nuclear Information System (INIS)

Ueno, Koji

2010-01-01

Problems caused by microbial contamination and hazardous chemicals have attracted much attention in the food industry. The number of systems such as hygienic management systems and Hazard Analysis Critical Control Point (HACCP) systems adopted in the manufacturing process is increasing. As manufacturing process control has become stricter, stricter control is also required for microbial control for containers and packaging materials (from disinfection to sterilization). Since safe and reliable methods for sterilizing food containers and packaging materials that leave no residue are required, electron beam sterilization used for medical equipment has attracted attention from the food industry. This paper describes an electron irradiation facility, methods for applying electron beams to food containers and packaging materials, and products irradiated with electron beams. (author)

Quality assurance for radiodiagnostic equipment in Uruguay

International Nuclear Information System (INIS)

Cotelo, Elena D.

2001-01-01

Since Uruguay did not have an study on X-ray equipment, students of Radiation Protection course (RP) made this field work throughout the country. The objective is to obtain information on the number and kind of X-ray radiodiagnostic equipment. Some of the results are: there are 666 radiodiagnostic equipment. The ratio of population to equipment is 4.515 to 1 in the capital and the mean rate in the rest of the country is 4.383 to one, with a minimum of 1.707 and a maximum of 8.220. The Public Health Ministry (MSP) and the Instituciones de Asistencia Medica Colectiva (a kind of private heath assurance) (IAMC) have less equipment in the capital than in the rest of the country. The 37% of the capital population receives assistance through the IAMC , with a 42.5 % of the equipment. Uruguay except the capital has 18 districts and 17 computed tomography equipment, from which only 3 belong to the MSP. Five districts do not have any. In Montevideo, there are 11.500 females over forty years of age per X-ray mammography equipment, and this relation in the rest of the country is 13.900. There are 21 X-ray Interventional radiology equipment, 16 of them are in the capital. Is from relating the radiodiagnostic equipment, the population and the procedures, that quality assistance indicators emerge. This owns high importance on the way to create a RP National Programme. (author)

Polymeric hydrogels containing complexant agents for retention of pollutants containing thorium

International Nuclear Information System (INIS)

Oliveira, Maria Jose A.; Carreiro, Julio C.; Parra, Duclerc F.; Lugao, Ademar B.

2005-01-01

The hydrogels of poly(N-vinyl-2-pyrrolidone) (PVP), constituted of around 90% of water , show properties of retaining great amount of water and consequently can also retain substances that were made soluble, with either particular or specific reactive properties. In the light of this, these matrixes can be used as support for both capture and retention of radioactive substances of contaminated surfaces. Modified hydrogels containing complexant agents had been obtained in solution, in order to capture contaminated substances. The study of the ionizing radiation effect in polymer is of great interest not only to the development of materials which operate in conditions of radiation but also to the usage of the technique with purpose of both polymeric structure modification and acquisition of new materials. Membranes of hydrogels have been obtained with poly(N-vinyl-2-pyrrolidone)-PVP, polyethyleneglycol (PEG), Agar and several concentrations of ethylenediaminetetraacetic acid (EDTA), and sodium citrate. Theses samples were irradiated in 60 Co source, 15 kGy/h dose and submitted to thermal characterization in a Mettler-Toledo SDTA/851 equipment. The hydrogels membranes polymerized by radiation were put in contact with thorium nitrate solution, dehydrated and calcined, after that their ashes were analyzed. In the case of solution containing thorium were analyzed by spectrophotometric. (author)

TRANSPORT AND EMPLACEMENT EQUIPMENT DESCRIPTIONS

International Nuclear Information System (INIS)

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) Transport and Emplacement in 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. The Transport and Emplacement equipment described in this document consists of the following: (1) WP Transporter; (2) Reusable Rail Car; (3) Emplacement Gantry; (4) Gantry Carrier; and (5) Transport Locomotive

Plant-wide integrated equipment monitoring and analysis system

International Nuclear Information System (INIS)

Morimoto, C.N.; Hunter, T.A.; Chiang, S.C.

2004-01-01

A nuclear power plant equipment monitoring system monitors plant equipment and reports deteriorating equipment conditions. The more advanced equipment monitoring systems can also provide information for understanding the symptoms and diagnosing the root cause of a problem. Maximizing the equipment availability and minimizing or eliminating consequential damages are the ultimate goals of equipment monitoring systems. GE Integrated Equipment Monitoring System (GEIEMS) is designed as an integrated intelligent monitoring and analysis system for plant-wide application for BWR plants. This approach reduces system maintenance efforts and equipment monitoring costs and provides information for integrated planning. This paper describes GEIEMS and how the current system is being upgraded to meet General Electric's vision for plant-wide decision support. (author)

Sample-related peripheral equipment at IPNS

International Nuclear Information System (INIS)

Bohringer, D.E.; Crawford, R.K.

1985-01-01

This paper describes samples environment equipment provided by IPNS to visiting users and staff scientists. Of the twelve horizontal neutron beam stations, (ten now operational, two under construction) all use one or more form of such support equipment. An in-house support group devotes a significant fraction of its time to development, calibration, and maintenance of this equipment

Development of vitrification line technology and the manufacture of equipment

International Nuclear Information System (INIS)

Alexa, J.

1989-01-01

The development is described of technology and the production of equipment for the vitrification of liquid radioactive wastes. For vitrification, frit Frita F270 is used containing up to 20% titanium and featuring a corrosion effect lower by one order than that of lead glass. The liquid waste is discharged in a measuring tank where it is mixed with formic acid. It is then pumped into an evaporator. Breed vapor is carried via a condenser to a condensate tank. The evaporator concentrate is transported to a homogenizer where it is gradually mixed with Frita. The viscous mush thus produced is carried into a furnace where the remaining water is evaporated. The furnace decontamination factor is 10 2 to 10 3 . At a temperature of up to 1,050 degC the frit melts and is discharged into a case. Currently, technology has been developed of mush preparation and the design has been completed of a vitrification furnace featuring remote lid opening and closing, and of equipment for processing furnace emissions. (J.B.). 3 figs., 1 tab., 1 ref

Expert system GIP-WWER for verification of seismic adequacy of WWER equipment

International Nuclear Information System (INIS)

Masopust, R.

1999-01-01

The aim of this report is to describe the modified Generic Implementation Procedure (GIP) titled GIP-WWER which can be used to verify seismic adequacy of the safe shutdown mechanical and electrical equipment and distribution systems of operating or constructed WWER NPPs, namely WWER-440/213 type. The WWER-GIP procedure was prepared using available information contained in GIP and the experience taken from various seismic inspections and evaluations of WWER type NPPs performed in the last five years

Mark III Containment vessel/annulus concrete design

International Nuclear Information System (INIS)

Chang, P.S.; Moussa, M.M.

1981-01-01

Recently, engineers have been considering the significant dynamic impact of safety/relief valve (S/RV) discharge loads on the containment structures, safety equipment, and piping systems in BWR type reactors. For a plant in the construction stage, extensive modifications will be made to qualify these new loads. The lower portion of the containment vessel serves as a suppression pool pressure boundary and is designed to sustain the effects of postulated loss of coolant accidents, seismic occurrences, S/RV discharge loads, and other effects. Extremely high spectral peak accelerations of the free-standing steel containment vessel can be obtained during the air dearing process of the S/RV discharge. Parametric studies indicated that a substantial reduction in response can be obtained by increasing the stiffness of the steel containment vessel in the lover area. A concrete backing configuration in the suppression pool area of Mark III Containment is proposed in this paper. A composite action is assumed between the steel containment vessel shell and the concrete section. The system is physically separated from the shield building. This approach warrants an early erection of the shield building and a late installation of piping systems in the containment vessel suppression pool area. Finite element analyses are performed by using ASHSD2 and EASE2 computer codes. The results of the analyses have shown the proposed stress criteria are satisfied. The approach pressented is justified to be a workable system for a new plant design. (orig./HP)

Electronic equipment of the extended system for beam diagnostics of the ''Lyudmila'' liquid-hydrogen chamber

International Nuclear Information System (INIS)

Basiladze, S.G.; Bulanov, N.F.; Nguen V'et Zung; Yudin, V.K.

1978-01-01

The electronic equipment of an expanded system of beam monitoring for the Lyudmila liquid-hydrogen bubble chamber is described. The system contains ten proportional chambers: nine two-coordinate and one one-coordinate chambers, spacing being 1 mm. The total number of wires is 912. Signals are measured in parallel from all the 48 wires for any plane, or for two planes from even and odd wires. The electronic equipment includes preamplifiers on a field transistor, charge-digital converters, and followers. The electronic circuits in the chambers are distinguished by simplicity and low power consumption: one transistor and 1 mW per wire respectively. The system operates with a small TPA-i computer

7 CFR 58.229 - Filler and packaging equipment.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Filler and packaging equipment. 58.229 Section 58.229....229 Filler and packaging equipment. All filling and packaging equipment shall be of sanitary... equipment should comply with the 3-A Sanitary Standards for equipment for Packaging Dry Milk and Dry Milk...

WP EMPLACEMENT CONTROL AND COMMUNICATION EQUIPMENT DESCRIPTIONS

International Nuclear Information System (INIS)

Raczka, N.T.

1997-01-01

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

Automatic monitoring of vibration welding equipment

Science.gov (United States)

Spicer, John Patrick; Chakraborty, Debejyo; Wincek, Michael Anthony; Wang, Hui; Abell, Jeffrey A; Bracey, Jennifer; Cai, Wayne W

2014-10-14

A vibration welding system includes vibration welding equipment having a welding horn and anvil, a host device, a check station, and a robot. The robot moves the horn and anvil via an arm to the check station. Sensors, e.g., temperature sensors, are positioned with respect to the welding equipment. Additional sensors are positioned with respect to the check station, including a pressure-sensitive array. The host device, which monitors a condition of the welding equipment, measures signals via the sensors positioned with respect to the welding equipment when the horn is actively forming a weld. The robot moves the horn and anvil to the check station, activates the check station sensors at the check station, and determines a condition of the welding equipment by processing the received signals. Acoustic, force, temperature, displacement, amplitude, and/or attitude/gyroscopic sensors may be used.

Monitoring equipment environment during nuclear plant operation at Salem and Hope Creek generating stations

International Nuclear Information System (INIS)

Blum, A.; Smith, R.J.

1991-01-01

Monitoring of environmental parameters has become a significant issue for operating nuclear power plants. While the long-term benefits of plant life extension programs are being pursued with comprehensive environmental monitoring programs, the potential effect of local hot spots at various plant locations needs to be evaluated for its effect on equipment degradation and shortening of equipment qualified life. A significant benefit can be experienced from temperature monitoring when a margin exists between the design versus actual operating temperature. This margin can be translated into longer equipment qualified life and significant reduction in maintenance activities. At PSE and G, the immediate need for monitoring environmental parameters is being accomplished via the use of a Logic Beach Bitlogger. The Bitlogger is a portable data loggings system consisting of a system base, input modules and a communication software package. Thermocouples are installed on selected electrical equipment and cables are run from the thermocouples to the input module of the Bitlogger. Temperature readings are taken at selected intervals, stored in memory, and downloaded periodically to a PC software program, i.e., Lotus. The data is formatted into tabular or graphical documents. Because of their versatility, Bitloggers are being used differently at the authors Nuclear facility. At the Salem Station (2 Units-4 loop Westinghouse PWR), a battery powered, fully portable, calibrated Bitlogger is located in an accessible area inside Containment where it monitors the temperature of various electrical equipment within the Pressurizer Enclosure. It is planned that close monitoring of the local hot spot temperatures in this area will allow them to adjust and reconcile the environmental qualification of the equipment

A neutron-absorbing porcelain enamel for coating nuclear equipment

International Nuclear Information System (INIS)

Iverson, D.C.

1988-01-01

In 1985, nuclear safety analyses showed that under upset conditions, strict administrative controls were necessary to limit access to a new processing vessel for enriched uranium service at the Savannah River Plant (SRP). In order to increase the level of nuclear safety associated with that vessel, the traditional methods of incorporating neutron absorbers (borated stainless steel, boral, cadmium foil, etc.) were reviewed, however, process conditions did not permit their use. A neutron-absorbing porcelain enamel containing large amounts of cadmium and boron was developed as a safe, cost-effective alternative to traditional neutron-absorbing methods. Several pieces of coated process equipment have been installed or are planned for installation at SRP

A preliminary categorization of end-of-life electrical and electronic equipment as secondary metal resources

International Nuclear Information System (INIS)

Oguchi, Masahiro; Murakami, Shinsuke; Sakanakura, Hirofumi; Kida, Akiko; Kameya, Takashi

2011-01-01

Highlights: → End-of-life electrical and electronic equipment (EEE) as secondary metal resources. → The content and the total amount of metals in specific equipment are both important. → We categorized 21 EEE types from contents and total amounts of various metals. → Important equipment types as secondary resources were listed for each metal kind. → Collectability and possible collection systems of various EEE types were discussed. - Abstract: End-of-life electrical and electronic equipment (EEE) has recently received attention as a secondary source of metals. This study examined characteristics of end-of-life EEE as secondary metal resources to consider efficient collection and metal recovery systems according to the specific metals and types of EEE. We constructed an analogy between natural resource development and metal recovery from end-of-life EEE and found that metal content and total annual amount of metal contained in each type of end-of-life EEE should be considered in secondary resource development, as well as the collectability of the end-of-life products. We then categorized 21 EEE types into five groups and discussed their potential as secondary metal resources. Refrigerators, washing machines, air conditioners, and CRT TVs were evaluated as the most important sources of common metals, and personal computers, mobile phones, and video games were evaluated as the most important sources of precious metals. Several types of small digital equipment were also identified as important sources of precious metals; however, mid-size information and communication technology (ICT) equipment (e.g., printers and fax machines) and audio/video equipment were shown to be more important as a source of a variety of less common metals. The physical collectability of each type of EEE was roughly characterized by unit size and number of end-of-life products generated annually. Current collection systems in Japan were examined and potentially appropriate collection

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

Accident management to prevent containment failure and reduce fission product release

International Nuclear Information System (INIS)

Lehner, J.R.; Lin, C.C.; Luckas, W.J.; Pratt, W.T.

1991-01-01

Brookhaven National Laboratory, under the auspices of the US Nuclear Regulatory Commission, is investigating accident management strategies which could help preserve containment integrity or minimize releases during a severe accident. The strategies considered make use of existing plant systems and equipment in innovative ways to reduce the likelihood of containment failure or to mitigate the release of fission products to the environment if failure cannot be prevented. Many of these strategies would be implemented during the later stages of a severe accident, i.e. after vessel breach, and sizable uncertainties exist regarding some of the phenomena involved. The identification and assessment process for containment and release strategies is described, and some insights derived from its application to specific containment types are presented. 2 refs., 5 figs., 2 tabs

Special equipment for etching nitrocellulose film

International Nuclear Information System (INIS)

Domanus, J.C.

1983-08-01

Nitrocellulose film and converter screens used for neutron radiography are described. Difficulties in visualization of radiographs on those films are mentioned. Because there is no equipment for etching nitrocellulose film available on the market Risoe has designed and produced such equipment at an estimated cost of Dkr. 15,000. Design criteria for this equipment are given and its performance described

An on-line monitoring system for navigation equipment

Science.gov (United States)

Wang, Bo; Yang, Ping; Liu, Jing; Yang, Zhengbo; Liang, Fei

2017-10-01

Civil air navigation equipment is the most important infrastructure of Civil Aviation, which is closely related to flight safety. In addition to regular flight inspection, navigation equipment's patrol measuring, maintenance measuring, running measuring under special weather conditions are the important means of ensuring aviation flight safety. According to the safety maintenance requirements of Civil Aviation Air Traffic Control navigation equipment, this paper developed one on-line monitoring system with independent intellectual property rights for navigation equipment, the system breakthroughs the key technologies of measuring navigation equipment on-line including Instrument Landing System (ILS) and VHF Omni-directional Range (VOR), which also meets the requirements of navigation equipment ground measurement set by the ICAO DOC 8071, it provides technical means of the ground on-line measurement for navigation equipment, improves the safety of navigation equipment operation, and reduces the impact of measuring navigation equipment on airport operation.

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...

46 CFR 77.40-1 - Pilot boarding equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 3 2010-10-01 2010-10-01 false Pilot boarding equipment. 77.40-1 Section 77.40-1... MISCELLANEOUS SYSTEMS AND EQUIPMENT Pilot Boarding Equipment § 77.40-1 Pilot boarding equipment. (a) This... vessel. (b) Each vessel must have suitable pilot boarding equipment available for use on each side of the...

Operation monitor for plant equipment

International Nuclear Information System (INIS)

Kondo, Tetsufumi; Kanemoto, Shigeru.

1991-01-01

In a nuclear power plant, states of each of equipment in the plant are monitored accurately even under such a operation condition that the power is changed. That is, the fundamental idea is based on a model comparison method. A deviation between an output signal upon normal plant state obtained in a forecasting model device and that of the objective equipment in the plant are compared with a predetermined value. The result of the comparison is inputted to an alarm device to alarm the abnormality of the states of the equipment to an operator. The device of the present invention thus constituted can monitor the abnormality of the operation of equipment accurately even under such a condition that a power level fluctuates. As a result, it can remarkably contribute to mitigate operator's monitoring operation under the condition such as during load following operation. (I.S.)

Practical biosafety in the tuberculosis laboratory: containment at the source is what truly counts

NARCIS (Netherlands)

Soolingen, D.; Wisselink, H.J.; Lumb, R.; Anthony, R.; Zanden, van der A.; Gilpin, C.

2014-01-01

In industrialised countries, sufficient resources for establishing and maintaining fully equipped biosafety level 3 (BSL-3) laboratories according to international standards are generally available. BSL-3 laboratories are designed to provide several layers of containment to protect the laboratory

Establishment for Nuclear Equipment -Overview

International Nuclear Information System (INIS)

Pracz, J.

2006-01-01

Research and development works conducted in the Establishment for Nuclear Equipment (ZdAJ) were focused around 3 subject areas: an accelerator for cancer treatment, therapeutical tables, systems and methods for controlling objects that cross international borders. The new, medium energy accelerator for cancer therapy cases is being designed in the Establishment for several years. In 2005 progress was achieved. A physical part, containing an electron beam has been completed and the parameters of that beam make it useful for therapeutical purposes. Consequently, the work on designing and testing of beam control systems, ensuring its high stability, repetition of irradiation parameters and accuracy of dosage have been started. Results of these tests make it very probable that 2006 will be the final year of scientific works and in 2007 the new apparatus will be ready for sales. Therapeutical tables have become a leading product of ZdAJ IPJ. Their technical parameters, reliability and universality in uses are appreciated by many customers of ZdAJ. In 2005, the table Polkam 16 was registered by the national Office for Registration of Medical Equipment as the first product of ZdAJ that meets all technical and formal requirements of the safety mark CE. This allows sales of the product on the market of the European Union. The research and development part of designing a therapeutical table for uses in the total body irradiation technique was also concluded in 2005. After the September 11 terrorist attacks on WTC a matter of controlling international borders have become a priority for many countries. In 2005 in ZdAJ IPJ, we conducted many preliminary calculations and experiments analyzing systems of irradiation sources, both photon and neutron as well as systems of detection and designing of signals triggered by controlling objects crossing the border. The results so far have enabled us to formulate a research project which has been positively evaluated by experts and found

Seismic analysis of liquid storage container in nuclear reactors

International Nuclear Information System (INIS)

Zhang Zhengming; He Shuyan; Xu Ming

2007-01-01

Seismic analysis of liquid storage containers is always difficult in the seismic design of nuclear reactor equipment. The main reason is that the liquid will generate significant seismic loads under earthquake. These dynamic liquid loads usually form the main source of the stresses in the container. For this kind of structure-fluid coupling problem, some simplified theoretical methods were usually used previously. But this cannot satisfy the requirements of engineering design. The Finite Element Method, which is now full developed and very useful for the structural analysis, is still not mature for the structure-fluid coupling problem. This paper introduces a method suitable for engineering mechanical analysis. Combining theoretical analysis of the dynamic liquid loads and finite element analysis of the structure together, this method can give practical solutions in the seismic design of liquid storage containers

Procurement strategic analysis of nuclear safety equipment

International Nuclear Information System (INIS)

Wu Caixia; Yang Haifeng; Li Xiaoyang; Li Shixin

2013-01-01

The nuclear power development plan in China puts forward a challenge on procurement of nuclear safety equipment. Based on the characteristics of the procurement of nuclear safety equipment, requirements are raised for procurement process, including further clarification of equipment technical specification, establishment and improvement of the expert database of the nuclear power industry, adoption of more reasonable evaluation method and establishment of a unified platform for nuclear power plants to procure nuclear safety equipment. This paper makes recommendation of procurement strategy for nuclear power production enterprises from following aspects, making a plan of procurement progress, dividing procurement packages rationally, establishing supplier database through qualification review and implementing classified management, promoting localization process of key equipment continually and further improving the system and mechanism of procurement of nuclear safety equipment. (authors)

Intermodal Transport and Repositioning of Empty Containers in Central and Eastern Europe Hinterland

DEFF Research Database (Denmark)

Kolar, Petr; Schramm, Hans-Joachim; Prockl, Günter

2018-01-01

The objective of this article is to provide a review of literature dealing with empty container repositioning. This review is interlinked with a qualitative data analysis based on semi-structured interviews with representatives of ocean carriers, which are key actors determining empty container....... By addressing the research questions and conducting the analysis, the authors determine whether empty container repositioning is a problem only concerning equipment allocation by an ocean carrier or requires a collaborative resolution involving various parties engaged in container movements in landlocked...... hinterlands. This article confirms that most existing literature dealing with empty container repositioning ignores the actual dynamics of landlocked hinterlands as well as business practitioners' perspective. The authors' analysis of the empirical research complements and challenges the reviewed research...

Equipment qualification research program: program plan

International Nuclear Information System (INIS)

Dong, R.G.; Smith, P.D.

1982-01-01

The Lawrence Livermore National Laboratory (LLNL) under the sponsorship of the US Nuclear Regulatory Commission (NRC) has developed this program plan for research in equipment qualification (EQA). In this report the research program which will be executed in accordance with this plan will be referred to as the Equipment Qualification Research Program (EQRP). Covered are electrical and mechanical equipment under the conditions described in the OBJECTIVE section of this report. The EQRP has two phases; Phase I is primarily to produce early results and to develop information for Phase II. Phase I will last 18 months and consists of six projects. The first project is program management. The second project is responsible for in-depth evaluation and review of EQ issues and EQ processes. The third project is responsible for detailed planning to initiate Phase II. The remaining three projects address specific equipment; i.e., valves, electrical equipment, and a pump

Food Service Equipment and Appurtenances.

Science.gov (United States)

National Sanitation Foundation, Ann Arbor, MI.

Equipment design specifications are presented relating to tables of all kinds, counters, sinks and drainboards, bins, shelves, drawers, hoods and similar kitchen appurtenances, not including baking, roasting, toasting, broiling or frying equipment, food preparation machinery such as slicers, choppers, and cutters, mixers and grinders, steam…

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

A stochastic discrete optimization model for designing container terminal facilities

Science.gov (United States)

Zukhruf, Febri; Frazila, Russ Bona; Burhani, Jzolanda Tsavalista

2017-11-01

As uncertainty essentially affect the total transportation cost, it remains important in the container terminal that incorporates several modes and transshipments process. This paper then presents a stochastic discrete optimization model for designing the container terminal, which involves the decision of facilities improvement action. The container terminal operation model is constructed by accounting the variation of demand and facilities performance. In addition, for illustrating the conflicting issue that practically raises in the terminal operation, the model also takes into account the possible increment delay of facilities due to the increasing number of equipment, especially the container truck. Those variations expectantly reflect the uncertainty issue in the container terminal operation. A Monte Carlo simulation is invoked to propagate the variations by following the observed distribution. The problem is constructed within the framework of the combinatorial optimization problem for investigating the optimal decision of facilities improvement. A new variant of glow-worm swarm optimization (GSO) is thus proposed for solving the optimization, which is rarely explored in the transportation field. The model applicability is tested by considering the actual characteristics of the container terminal.

Automatic dose-rate controlling equipment

International Nuclear Information System (INIS)

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

1977-01-01

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

Analysis of a radiation incident with intraoral dental radiological equipment

International Nuclear Information System (INIS)

Malone, J.F.

1996-01-01

A case is described involving a serious incident with dental radiological equipment, containing many lessons that may be applied to the preparation of other cases. The description includes an account of the incident, the circumstances surrounding it, the dosimetry, risk estimates and the medical consequences of the incident. In addition, some aspects of the associated legal proceedings are reviewed and assessed. As a result of the incident described, a number of conclusions are drawn with respect to important practices in ensuring the safety of installations and the value of evidence brought forward by expert witnesses. (author)

A complex method of equipment replacement planning. An advanced plan for the replacement of medical equipment.

Science.gov (United States)

Dondelinger, Robert M

2004-01-01

This complex method of equipment replacement planning is a methodology; it is a means to an end, a process that focuses on equipment most in need of replacement, rather than the end itself. It uses data available from the maintenance management database, and attempts to quantify those subjective items important [figure: see text] in making equipment replacement decisions. Like the simple method of the last issue, it is a starting point--albeit an advanced starting point--which the user can modify to fit their particular organization, but the complex method leaves room for expansion. It is based on sound logic, documented facts, and is fully defensible during the decision-making process and will serve your organization well as provide a structure for your equipment replacement planning decisions.

After-hours power status of office equipment and energy use of miscellaneous plug-load equipment

Energy Technology Data Exchange (ETDEWEB)

Roberson, Judy A.; Webber, Carrie A.; McWhinney, Marla C.; Brown, Richard E.; Pinckard, Marageret J.; Busch, John F.

2004-05-27

This research was conducted in support of two branches of the EPA ENERGY STAR program, whose overall goal is to reduce, through voluntary market-based means, the amount of carbon dioxide emitted in the U.S. The primary objective was to collect data for the ENERGY STAR Office Equipment program on the after-hours power state of computers, monitors, printers, copiers, scanners, fax machines, and multi-function devices. We also collected data for the ENERGY STAR Commercial Buildings branch on the types and amounts of miscellaneous plug-load equipment, a significant and growing end use that is not usually accounted for by building energy managers. For most types of miscellaneous equipment, we also estimated typical unit energy consumption in order to estimate total energy consumption of the miscellaneous devices within our sample. This data set is the first of its kind that we know of, and is an important first step in characterizing miscellaneous plug loads in commercial buildings. The main purpose of this study is to supplement and update previous data we collected on the extent to which electronic office equipment is turned off or automatically enters a low power state when not in active use. In addition, it provides data on numbers and types of office equipment, and helps identify trends in office equipment usage patterns. These data improve our estimates of typical unit energy consumption and savings for each equipment type, and enables the ENERGY STAR Office Equipment program to focus future effort on products with the highest energy savings potential. This study expands our previous sample of office buildings in California and Washington DC to include education and health care facilities, and buildings in other states. We report data from sixteen commercial buildings in California, Georgia, and Pennsylvania: four education buildings, two medical buildings, two large offices (> 500 employees each), three medium offices (50-500 employees each), and five small

A study of the effects of penetration framing on steel containment buckling capacity

International Nuclear Information System (INIS)

Baker, W.E.; Butler, T.A.

1987-05-01

Polycarbonate cylinders modeling steel containment structures were tested to study the effects of different framing designs around large penetrations on the static buckling capacity of containments. Two of the four models had equipment hatch penetrations and two had personnel airlock penetrations. Both types of models were tested with axial and shear loads as framing was incrementally added. Results indicate that, for the models constructed of polycarbonate, buckling is influenced minimally with added framing. Numerical results support the experimental results. Extrapolation of the results to containment constructed under field conditions with prototypic steel materials is discussed and further testing is recommended

Effectiveness of disinfectant wipes for decontamination of bacteria on patients' environmental and medical equipment surfaces at Siriraj Hospital.

Science.gov (United States)

Seenama, Chakkraphong; Tachasirinugune, Peenithi; Jintanothaitavorn, Duangporn; Kachintorn, Kanchana; Thamlikitkul, Visanu

2013-02-01

To determine the effectiveness of Virusolve+ disinfectant wipes and PAL disinfectant wipes for decontamination of inoculated bacteria on patients' environmental and medical equipment surfaces at Siriraj Hospital. Tryptic soy broths containing MRSA and XDR A. baumannii were painted onto the surfaces of patient's stainless steel bed rail, patient's fiber footboard, control panel of infusion pump machine and control panel of respirator. The contaminated surfaces were cleaned by either tap water, tap water containing detergent, Virusolve+ disinfectant wipes or PAL disinfectant wipes. The surfaces without any cleaning procedures served as the control surface. The contaminated surfaces cleaned with the aforementioned procedures and control surfaces were swabbed with cotton swabs. The swabs were streaked on agar plates to determine the presence of MRSA and XDR A. baumannii. MRSA and XDR A. baumannii were recovered from all control surfaces. All surfaces cleaned with tap water or tap water containing detergent revealed presence of both MRSA and XDR A. baumannii. However the amounts of bacteria on the surfaces cleaned with tap water containing detergent were less than those cleaned with tap water alone. All surfaces cleaned with PAL disinfectant wipes also revealed presence of both MRSA and XDR A. baumannii. However the amounts of bacteria on the surfaces cleaned with PAL disinfectant wipes were less than those cleaned with tap water containing detergent. No bacteria were recovered from all surfaces cleaned with Virusolve+ disinfectant wipes. Virusolve+ disinfectant wipes were more effective than tap water; tap water containing detergent and PAL disinfectant wipes for decontamination of bacteria inoculated on patients environmental and medical equipment surfaces at Siriraj Hospital.

Expert system for controlling plant growth in a contained environment

Science.gov (United States)

May, George A. (Inventor); Lanoue, Mark Allen (Inventor); Bethel, Matthew (Inventor); Ryan, Robert E. (Inventor)

2011-01-01

In a system for optimizing crop growth, vegetation is cultivated in a contained environment, such as a greenhouse, an underground cavern or other enclosed space. Imaging equipment is positioned within or about the contained environment, to acquire spatially distributed crop growth information, and environmental sensors are provided to acquire data regarding multiple environmental conditions that can affect crop development. Illumination within the contained environment, and the addition of essential nutrients and chemicals are in turn controlled in response to data acquired by the imaging apparatus and environmental sensors, by an "expert system" which is trained to analyze and evaluate crop conditions. The expert system controls the spatial and temporal lighting pattern within the contained area, and the timing and allocation of nutrients and chemicals to achieve optimized crop development. A user can access the "expert system" remotely, to assess activity within the growth chamber, and can override the "expert system".

Secondary containment systems for bulk oil storage facilities

International Nuclear Information System (INIS)

Carr, B.A.

1996-01-01

The United States Environmental Protection Agency has conducted site inspections at several onshore bulk oil above ground storage facilities, to ensure that owners follow the spill prevention, control and countermeasure regulations. The four violations which were most frequently cited at these facilities were: (1) lack of a spill prevention plan, (2) lack of appropriate containment equipment to prevent discharged oil from reaching a navigable water course, (3) inadequate secondary containment structures, and (4) lack of an adequate quick drainage system in the facility tank loading/unloading area. Suggestions for feasible designs which would improve the impermeability of secondary containment for above ground storage tanks (AST) included the addition of a liner, retrofitting the bottom of an AST with a second steel plate, using a geosynthetic liner on top of the original bottom, installing a leak detection system in the interstitial space between the steel plates, or installing an under-tank liner with a leak detection system during construction of a new AST. 2 refs

Origins of eponymous orthopaedic equipment.

Science.gov (United States)

Meals, Clifton; Wang, Jeffrey

2010-06-01

Orthopaedists make great use of eponymous equipment, however the origins of these tools are unknown to many users. This history enriches, enlightens, and enhances surgical education, and may inspire modern innovation. We explored the origins of common and eponymous orthopaedic equipment. We selected pieces of equipment named for their inventors and in the broadest use by modern orthopaedists. We do not describe specialized orthopaedic implants and instruments owing to the overwhelming number of these devices. The history of this equipment reflects the coevolution of orthopaedics and battlefield medicine. Additionally, these stories evidence the primacy of elegant design and suggest that innovation is often a process of revision and refinement rather than sudden inspiration. Their history exposes surgical innovators as brilliant, lucky, hardworking, and sometimes odd. These stories amuse, enlighten, and may inspire modern orthopaedists to develop creative solutions of their own. The rich history of the field's eponymous instruments informs an ongoing tradition of innovation in orthopaedics.

Progress on EPRI electrical equipment qualification research

International Nuclear Information System (INIS)

Sliter, G.E.

1983-01-01

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

Equipment for testing a group of nuclear reactor fuel elements for damage to the cans

International Nuclear Information System (INIS)

Mohm, F.

1977-01-01

Equipment is described for use in sodium cooled nuclear reactors, with which the fuel elements consisting of bundles of fuel and fertile rods can be examined for damage to the cans. Fission poducts occurring in the liquid coolant act as indicators. The coolant is sucked via pipelines which penetrate into the elements into a collecting container, and a special pipeline is available for every element of a group, where the highest points of individual pipelines at different hydrostatic heads are taken to the collecting container. This permits the checking of one line at a time due to pressure changes. (UWI) [de

TDRSS multimode transponder program. Phase 2: Equipment development

Science.gov (United States)

Cnossen, R. S.

1974-01-01

This report contains a complete description of the TDRS Multimode Transponder and its associated ground support equipment. The transponder will demonstrate candidate modulation techniques to provide the required information for the design of an eventual VHF/UHF transponder suitable for installation in a user satellite, capable of operating as part of a Tracking and Data Relay Satellite (TDRS) systems. Use of geosynchronous TDRS which can serve both low data rate users at VHF and high data rate users at other frequencies has been considered. The effects of radio frequency interference from the earth and of multipath propagation due to reflections from the earth are expected to pose problems for the TDRS system at VHF. Investigations have suggested several modulation techniques that offer promise to overcome these problems.

78 FR 25916 - Authorization of Radiofrequency Equipment

Science.gov (United States)

2013-05-03

...] Authorization of Radiofrequency Equipment AGENCY: Federal Communications Commission. ACTION: Proposed rule... bodies, and measurement procedures used to determine RF equipment compliance. The Commission believes... Commission is responsible for an equipment authorization program for radiofrequency (RF) devices under part 2...

Diagnostic imaging and radiation therapy equipment

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-05-01

This is the third edition of CSA Standard C22.2 No. 114 (now CAN/CSA-C22.2 No. 114), which is one of a series of standards issued by the Canadian Standards Association under Part II of the Canadian Electrical Code. This edition marks an important shift towards harmonization of Canadian requirements with those of the European community and the United States. Also important to this edition is the expansion of its scope to include the complete range of diagnostic imaging and radiation therapy equipment, rather than solely radiation-emitting equipment. In so doing, equipment previously addressed by CSA Standard C22.2 No. 125, Electromedical Equipment, specifically lasers for medical applications and diagnostic ultrasound units, is now dealt with in the new edition. By virtue of this expanded scope, many of the technical requirements in the electromedical equipment standard have been introduced to the new edition, thereby bringing CSA Standard C22.2 No. 114 up to date. 14 tabs., 16 figs.

Diagnostic imaging and radiation therapy equipment

International Nuclear Information System (INIS)

1990-05-01

This is the third edition of CSA Standard C22.2 No. 114 (now CAN/CSA-C22.2 No. 114), which is one of a series of standards issued by the Canadian Standards Association under Part II of the Canadian Electrical Code. This edition marks an important shift towards harmonization of Canadian requirements with those of the European community and the United States. Also important to this edition is the expansion of its scope to include the complete range of diagnostic imaging and radiation therapy equipment, rather than solely radiation-emitting equipment. In so doing, equipment previously addressed by CSA Standard C22.2 No. 125, Electromedical Equipment, specifically lasers for medical applications and diagnostic ultrasound units, is now dealt with in the new edition. By virtue of this expanded scope, many of the technical requirements in the electromedical equipment standard have been introduced to the new edition, thereby bringing CSA Standard C22.2 No. 114 up to date. 14 tabs., 16 figs

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

CERN Multimedia

Jesus Puerta-Pelayo

2003-01-01

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

30 CFR 75.524 - Electric face equipment; electric equipment used in return air outby the last open crosscut...

Science.gov (United States)

2010-07-01

... used in return air outby the last open crosscut; maximum level of alternating or direct electric... other in return air outby the last open crosscut, shall not exceed one ampere as determined from the... Electrical Equipment-General § 75.524 Electric face equipment; electric equipment used in return air outby...

21 CFR 606.60 - Equipment.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 7 2010-04-01 2010-04-01 false Equipment. 606.60 Section 606.60 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) BIOLOGICS CURRENT... following frequency, include but are not limited to: Equipment Performance check Frequency Frequency of...

Underground storage tanks containing hazardous chemicals

International Nuclear Information System (INIS)

Wise, R.F.; Starr, J.W.; Maresca, J.W. Jr.; Hillger, R.W.; Tafuri, A.N.

1991-01-01

The regulations issued by the United States Environmental Protection Agency in 1988 require, with several exceptions, that underground storage tank systems containing petroleum fuels and hazardous chemicals be routinely tested for releases. This paper summarizes the release detection regulations for tank systems containing chemicals and gives a preliminary assessment of the approaches to release detection currently being used. To make this assessment, detailed discussions were conducted with providers and manufacturers of leak detection equipment and testing services, owners or operators of different types of chemical storage tank systems, and state and local regulators. While these discussions were limited to a small percentage of each type of organization, certain observations are sufficiently distinctive and important that they are reported for further investigation and evaluation. To make it clearer why certain approaches are being used, this paper also summarizes the types of chemicals being stored, the effectiveness of several leak detection testing systems, and the number and characteristics of the tank systems being used to store these products

48 CFR 870.115 - Food service equipment.

Science.gov (United States)

2010-10-01

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

Design and Implementation of Equipment for Enhanced Safeguards of a Plutonium Storage in a Reprocessing Plant

International Nuclear Information System (INIS)

Richir, P.; Dechamp, L.; Buchet, P.; Dransart, P.; Dzbikowicz, Z.; Peerani, P.; ); Pierssens, L.; Persson, L.; Ancius, D.; Synetos, S.; ); Edmonds, N.; Homer, A.; Benn, K.-A.; Polkey, A.

2015-01-01

The Nuclear Security unit (NUSEC) of the Institute for Transuranium Elements (ITU, JRC) was entrusted by DG ENER to design and implement equipment in order to achieve enhanced safeguards of a plutonium dioxide storage located on the MAGNOX reprocessing plant in Sellafield (UK). Enhanced safeguards must lead to a win-win situation for all parties involved. In this case the DG ENER inspectorate will save inspection time, manpower and future financial resources and the operator will have the right to access its storage without the need for inspector presence. To reach this goal, while at the same time taking into account current budget constraints, NUSEC developed applications that use equipment commonly used in the safety and security fields but so far have not been used in safeguards. For instance, two laser scanners are used to detect entry/exit events into and out of the store and to provide the necessary information to an algorithm in order to categorize objects/people passing the scanners, e.g., a Fork Lift Truck, a trolley used to bring in PuO 2 containers, a system used for the dispatch of cans, people, etc. An RFID reader is used to identify equipment duly authorized to access the store. All PuO 2 containers arriving from the production line must be weighed, identified and measured using gamma and neutron detectors before they can be transferred to the store. For this purpose an Unattended Combined Measurement System (UCMS) was designed and manufactured by the JRC in order to do all verification activities using a single instrument. This paper describes the design features of the equipment and its implementation with the support of the Sellafield Ltd. in the framework of the MAGNOX store project. (author)

Connected Equipment Maturity Model Version 1.0

Energy Technology Data Exchange (ETDEWEB)

Butzbaugh, Joshua B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Mayhorn, Ebony T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sullivan, Greg [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Whalen, Scott A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-05-01

The Connected Equipment Maturity Model (CEMM) evaluates the high-level functionality and characteristics that enable equipment to provide the four categories of energy-related services through communication with other entities (e.g., equipment, third parties, utilities, and users). The CEMM will help the U.S. Department of Energy, industry, energy efficiency organizations, and research institutions benchmark the current state of connected equipment and identify capabilities that may be attained to reach a more advanced, future state.

Trilateral Initiative: IAEA authentication and national certification of verification equipment for facilities with classified forms of fissile material

International Nuclear Information System (INIS)

Haas, Eckard; Sukhanov, Alexander; Murphy, John

2001-01-01

Full text: Within the framework of the Trilateral Initiative, technical challenges have arisen due to the potential of the International Atomic Energy Agency (IAEA) monitoring fissile material with classified characteristics, as well as the IAEA using facility or host country supplied monitoring equipment. In monitoring material with classified characteristics, it is recognized that the host country needs to assure that classified information is not made available to the IAEA inspectors. Thus, any monitoring equipment used to monitor material with classified characteristics has to contain information security capabilities, such as information barriers. But likewise in using host-country-supplied monitoring equipment, regarding the material being monitored the IAEA has to have confidence that the information provided by the equipment is genuine and can be used by the IAEA in fulfilling its obligation to derive conclusions based on independent verification measures. Thus the IAEA needs to go through the process of authenticating the monitoring equipment. In the same way the host country needs to go through the process to assure itself that the monitoring equipment integrated with an information barrier will not divulge any classified information about an inspected sensitive item. Both processes require on large extent identical measures, but partially also may conflict with each other. The fact that monitoring equipment needs to exhibit information security throughout its lifecycle while at the same time be capable of being authenticated necessitates the need for creative technical approaches to be pursued. (author)

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-09-15

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

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

International Nuclear Information System (INIS)

Hong, Dong Hee; KIm, Hyeong Gyun

2016-01-01

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

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...

Future development of IR thermovision weather satellite equipment

Science.gov (United States)

Listratov, A. V.

1974-01-01

The self radiation of the surface being viewed is used for image synthesis in IR thermovision equipment. The installation of such equipment aboard weather satellites makes it possible to obtain cloud cover pictures of the earth's surface in a complete orbit, regardless of the illumination conditions, and also provides quantitative information on the underlying surface temperature and cloud top height. Such equipment is used successfully aboard the Soviet satellites of the Meteor system, and experimentally on the American satellites of the Nimbus series. With regard to surface resolution, the present-day IR weather satellite equipment is inferior to the television equipment. This is due primarily to the comparatively low detectivity of the IR detectors used. While IR equipment has several fundamental advantages in comparison with the conventional television equipment, the problem arises of determining the possibility for future development of weather satellite IR thermovision equipment. Criteria are examined for evaluating the quality of IR.

Melt processing and property testing of a model system of plastics contained in waste from electrical and electronic equipment.

Science.gov (United States)

Triantou, Marianna I; Tarantili, Petroula A; Andreopoulos, Andreas G

2015-05-01

In the present research, blending of polymers used in electrical and electronic equipment, i.e. acrylonitrile-butadiene-styrene terpolymer, polycarbonate and polypropylene, was performed in a twin-screw extruder, in order to explore the effect process parameters on the mixture properties, in an attempt to determine some characteristics of a fast and economical procedure for waste management. The addition of polycarbonate in acrylonitrile-butadiene-styrene terpolymer seemed to increase its thermal stability. Also, the addition of polypropylene in acrylonitrile-butadiene-styrene terpolymer facilitates its melt processing, whereas the addition of acrylonitrile-butadiene-styrene terpolymer in polypropylene improves its mechanical performance. Moreover, the upgrading of the above blends by incorporating 2 phr organically modified montmorillonite was investigated. The prepared nanocomposites exhibit greater tensile strength, elastic modulus and storage modulus, as well as higher melt viscosity, compared with the unreinforced blends. The incorporation of montmorillonite nanoplatelets in polycarbonate-rich acrylonitrile-butadiene-styrene terpolymer/polycarbonate blends turns the thermal degradation mechanism into a two-stage process. Alternatively to mechanical recycling, the energy recovery from the combustion of acrylonitrile-butadiene-styrene terpolymer/polycarbonate and acrylonitrile-butadiene-styrene terpolymer/polypropylene blends was recorded by measuring the gross calorific value. Comparing the investigated polymers, polypropylene presents the higher gross calorific value, followed by acrylonitrile-butadiene-styrene terpolymer and then polycarbonate. The above study allows a rough comparative evaluation of various methodologies for treating plastics from waste from electrical and electronic equipment. © The Author(s) 2015.

Special Equipment and/or Devices.

Science.gov (United States)

National Sanitation Foundation, Ann Arbor, MI.

This standard covers the sanitation requirements for equipment and/or devices used in the storage, preparation, or handling of foods and beverages. The National Sanitation Foundation's basic criteria for the evaluation of special equipment and/or devices has been prepared to fulfill several specific needs, its major function being to serve as a…

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

Procedure for qualify class 1E equipment for nuclear power generating stations; Kvalifikacija elektroopreme za stjecanje klase 1E u nuklearnim elektranama

Energy Technology Data Exchange (ETDEWEB)

Smiljanic, D [' Rade Koncar' Institut, Zagreb (Yugoslavia)

1983-07-01

This paper describes the basic requirements for qualifying Class 1E equipment and systems that are to be used in nuclear power generating stations. The requirements presented include the principles, procedures and methods of qualification. The qualification requirements will confirm the adequacy of the equipment design under normal, abnormal, design basis event, post design basis event and containment test conditions for the performance of Class 1 E functions. The presented methods of qualification are in accordance with IEEE Standards and other standards (IEC, JUS, DIN, etc,), and have the primary role to provide guidance for demonstrating the qualification of Class 1E equipment produced by 'Rade Koncar'.(author)

X-ray equipment

International Nuclear Information System (INIS)

Redmayne, I.G.B.

1988-01-01

The patent concerns a warning and protection system for mobile x-ray equipment used for 'on site' radiography, so that workers in the vicinity of such a working unit can be alerted to its presence. The invention is a local repeater warning system which gives a preliminary warning that energisation of the tubehead is imminent, as well as a switch near the tubehead to abort or inhibit energisation. The latter switch allows personnel caught in the vicinity of the tubehead to prevent energisation. The preliminary warning may be flashing lamps or by a klaxon. The control unit for the equipment may include a monitoring circuit to detect failure of the warning light or klaxon. (U.K.)

X-ray equipment

Energy Technology Data Exchange (ETDEWEB)

Redmayne, I.G.B.

1988-01-06

The patent concerns a warning and protection system for mobile x-ray equipment used for 'on site' radiography, so that workers in the vicinity of such a working unit can be alerted to its presence. The invention is a local repeater warning system which gives a preliminary warning that energisation of the tubehead is imminent, as well as a switch near the tubehead to abort or inhibit energisation. The latter switch allows personnel caught in the vicinity of the tubehead to prevent energisation. The preliminary warning may be flashing lamps or by a klaxon. The control unit for the equipment may include a monitoring circuit to detect failure of the warning light or klaxon. (U.K.).

Equipment cost optimization

International Nuclear Information System (INIS)

Ribeiro, E.M.; Farias, M.A.; Dreyer, S.R.B.

1995-01-01

Considering the importance of the cost of material and equipment in the overall cost profile of an oil company, which in the case of Petrobras, represents approximately 23% of the total operational cost or 10% of the sales, an organization for the optimization of such costs has been established within Petrobras. Programs are developed aiming at: optimization of life-cycle cost of material and equipment; optimization of industrial processes costs through material development. This paper describes the methodology used in the management of the development programs and presents some examples of concluded and ongoing programs, which are conducted in permanent cooperation with suppliers, technical laboratories and research institutions and have been showing relevant results

7 CFR 550.39 - Equipment replacement insurance.

Science.gov (United States)

2010-01-01

... 7 Agriculture 6 2010-01-01 2010-01-01 false Equipment replacement insurance. 550.39 Section 550.39... Agreements Equipment/property Standards § 550.39 Equipment replacement insurance. If required by the terms and conditions of the award, the Cooperator shall provide adequate insurance coverage for replacement...

47 CFR 76.1621 - Equipment compatibility offer.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 4 2010-10-01 2010-10-01 false Equipment compatibility offer. 76.1621 Section... MULTICHANNEL VIDEO AND CABLE TELEVISION SERVICE Notices § 76.1621 Equipment compatibility offer. Cable system... offer to supply each subscriber with special equipment that will enable the simultaneous reception of...

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...

14 CFR 25.1441 - Oxygen equipment and supply.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Oxygen equipment and supply. 25.1441... Oxygen equipment and supply. (a) If certification with supplemental oxygen equipment is requested, the... oxygen available in each source of supply. (d) The oxygen flow rate and the oxygen equipment for...

47 CFR 36.126 - Circuit equipment-Category 4.

Science.gov (United States)

2010-10-01

... separating property associated with special services, circuit equipment included in Categories 4.12 (other... Equipment Excluding Wideband—Category 4.13—The cost of Circuit Equipment associated with exchange line plant... 47 Telecommunication 2 2010-10-01 2010-10-01 false Circuit equipment-Category 4. 36.126 Section 36...

49 CFR 238.230 - Safety appliances-new equipment.

Science.gov (United States)

2010-10-01

... 49 Transportation 4 2010-10-01 2010-10-01 false Safety appliances-new equipment. 238.230 Section... I Passenger Equipment § 238.230 Safety appliances—new equipment. (a) Applicability. This section..., 2007, that is equipped with a safety appliance, required by the “manner of application” provisions in...

Studies for aseismatic design of atomic power equipment

International Nuclear Information System (INIS)

Uchiyama, Yuichi; Takayanagi, Masaaki; Moriyama, Takeo; Mizuno, Sadao

1976-01-01

The social requirements for the safety of nuclear power stations are very severe, and especially in Japan where earthquakes occur frequently, the safety against earthquakes is regarded as an important matter. The numerous machinery and equipments composing nuclear power plants have largely different roles in the safety, accordingly it is important to maintain effectively the safety as a whole. The design is carried out by classifying buildings, machinery and equipments, pipings and electric appliances according to the importance, and so that the aseismatic property corresponding to the importance is given to each. In most cases, the aseismatic design is carried out with computing codes, but it is necessary to forward the design by proving the propriety of analysis models and calculated results. Efforts are exerted in Hitachi Ltd. to improve the accuracy of the aseismatic analysis by carrying out basic experiment, the demonstration test in actual plants and the study on analytical method as many as possible. The measurement of the vibration of actual pipings in order to confirm the supporting conditions, the comparison of multi-input analysis and SRSS method for piping analysis, and the vibration tests of a model containment vessel and a fuel assembly were carried out, and the results are reported in this paper. It is important to improve the accuracy of earthquake response analysis further. (Kako, I.)

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

International Nuclear Information System (INIS)

Ohno, Tokue; Tanaka, Nagatoshi

1988-01-01

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

Structural analysis of the equipment removal system for tank 241SY101

International Nuclear Information System (INIS)

Mackey, T.C.

1995-01-01

The calculations documented in this report show that the ERS major components are structurally qualified to complete the objective, i.e., to install the removed equipment into a shipping container and transport and store the container at the Central Waste Complex (CWC). The analysis for the structural members of the ERS components considers live load with an impact factor of 125 % added to dead load. An allowable stress of one-third yield is used for all structural components carrying the load based on DOE-RL-92-36. Adherence to DOE-RL-92-36 is not a code requirement. However, the loads considered make this factor of safety appropriate. The calculations meet the strength requirements of the American Institute for Steel Construction (ASIC 1989) for all non-critical structural elements

Practical approaches to implementing facility wide equipment strengthening programs

International Nuclear Information System (INIS)

Kincaid, R.H.; Smietana, E.A.

1989-01-01

Equipment strengthening programs typically focus on components required to ensure operability of safety related equipment or to prevent the release of toxic substances. Survival of non-safety related equipment may also be crucial to ensure rapid recovery and minimize business interruption losses. Implementing a strengthening program for non-safety related equipment can be difficult due to the large amounts of equipment involved and limited budget availability. EQE has successfully implemented comprehensive equipment strengthening programs for a number of California corporations. Many of the lessons learned from these projects are applicable to DOE facilities. These include techniques for prioritizing equipment and three general methodologies for anchoring equipment. Pros and cons of each anchorage approach are presented along with typical equipment strengthening costs

Mine railway equipments management information system

Energy Technology Data Exchange (ETDEWEB)

Zhang, X.; Han, K.; Duan, T.; Liu, Z.; Lu, H. [China University of Mining and Technology, Xuzhou (China)

2007-06-15

Based on client/server and browser/server models, the management information system described realized the entire life-cycle management of mine railway equipment which included universal equipment and special equipment in the locomotive depot, track maintenance division, electrical depot and car depot. The system has other online functions such as transmitting reports, graphics management, statistics, searches, graphics wizard and web propaganda. It was applied in Pingdingshan Coal Co. Ltd.'s Railway Transport Department. 5 refs., 4 figs.

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...

41 CFR 109-50.4801 - Equipment Gift Agreement.

Science.gov (United States)

2010-07-01

... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Equipment Gift Agreement... 50-SPECIAL DOE DISPOSAL AUTHORITIES 50.48-Exhibits § 109-50.4801 Equipment Gift Agreement. (a) The following Equipment Gift Agreement format will be used to provide gifts of excess and/or surplus equipment...

36 CFR 1207.32 - Equipment.

Science.gov (United States)

2010-07-01

... 1207.32 Parks, Forests, and Public Property NATIONAL ARCHIVES AND RECORDS ADMINISTRATION GENERAL RULES... as follows: (1) Items of equipment with a current per-unit fair market value of less than $5,000 may...) Items of equipment with a current per unit fair market value in excess of $5,000 may be retained or sold...

Management of radiological related equipments. Creating the equipment management database and analysis of the repair and maintenance records

International Nuclear Information System (INIS)

Eguchi, Megumu; Taguchi, Keiichi; Oota, Takashi; Kajiwara, Hiroki; Ono, Kiyotune; Hagio, Kiyofumi; Uesugi, Ekizo; Kajishima, Tetuo; Ueda, Kenji

2002-01-01

In 1997, we established the committee of equipments maintenance and management in our department. We designed the database in order to classify and register all the radiological related equipments using Microsoft Access. The management of conditions and cost of each equipment has become easier, by keeping and recording the database in the equipments management ledger and by filing the history of repairs or maintenances occurred to modalities. We then accounted numbers, cost of repairs and downtimes from the data of the repair and maintenance records for four years, and we reexamined the causal analysis of failures and the contents of the regular maintenance for CT and MRI equipments that had shown the higher numbers of repairs. Consequently, we have found the improvement of registration method of the data and the more economical way to use of the cost of repair. (author)

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 63.1434 - Equipment leak provisions.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 11 2010-07-01 2010-07-01 true Equipment leak provisions. 63.1434... Standards for Hazardous Air Pollutant Emissions for Polyether Polyols Production § 63.1434 Equipment leak provisions. (a) The owner or operator of each affected source shall comply with the HON equipment leak...

Characterization equipment essential/support drawing plan

International Nuclear Information System (INIS)

WILSON, G.W.

1999-01-01

The purpose of this document is to list the Characterization equipment drawings that are classified as Essential Drawings and Support Drawings. Essential Drawings: Are those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment (HNF 1997a). Support Drawings: Are those drawings identified by facility staff that further describe the design details of structures, systems, or components shown on essential drawings. (HNF 1997a) The Characterization equipment drawings identified in this report are deemed essential drawings as defined in HNF-PRO-242, Engineering Drawing Requirements (HNF 1997a). These drawings will be prepared, revised, and maintained per HNF-PRO-440, Engineering Document Change Control (HNF 1997b). All other Characterization equipment drawings not identified in this document will be considered General drawings until the Characterization Equipment Drawing Evaluation Report (Wilson 1998) is updated during fiscal year 1999. Trucks 1 and 2 drawings are not included in this revision of the essential drawing list due to uncertainty about future use

Radioactive decontamination of equipment

International Nuclear Information System (INIS)

1982-03-01

After a recall of some definitions relating to decontamination techniques and of the regulation into effect, the principles to be respected to arrange rationally work zones are quoted while insisting more particularly on the types of coatings which facilitate maintenance operations and the dismantling of these installations. Then, the processes and equipments to use in decontamination units for routine or particular operations are described; the list of recommended chemical products to decontaminate the equipment is given. The influence of these treatments on the state and the duration of life of equipments is studied, and some perfectible methods are quoted. In the appendix, are given: the limits of surface contamination accepted in the centers; a standard project which defines the criteria of admissible residual contamination in wastes considered as cold wastes; some remarks on the interest that certain special ventilation and air curtain devices for the protection of operators working on apparatus generating contaminated dusts [fr

46 CFR 96.40-1 - Pilot boarding equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Pilot boarding equipment. 96.40-1 Section 96.40-1... CONTROL AND MISCELLANEOUS SYSTEMS AND EQUIPMENT Pilot Boarding Equipment § 96.40-1 Pilot boarding... boat or other vessel. (b) Each vessel must have suitable pilot boarding equipment available for use on...

46 CFR 195.40-1 - Pilot boarding equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Pilot boarding equipment. 195.40-1 Section 195.40-1... CONTROL AND MISCELLANEOUS SYSTEMS AND EQUIPMENT Pilot Boarding Equipment § 195.40-1 Pilot boarding... boat or other vessel. (b) Each vessel must have suitable pilot boarding equipment available for use on...

The importance of social networks in their association to drug equipment sharing among injection drug users: a review.

Science.gov (United States)

De, Prithwish; Cox, Joseph; Boivin, Jean-François; Platt, Robert W; Jolly, Ann M

2007-11-01

To examine the scientific evidence regarding the association between characteristics of social networks of injection drug users (IDUs) and the sharing of drug injection equipment. A search was performed on MEDLINE, EMBASE, BIOSIS, Current Contents, PsycINFO databases and other sources to identify published studies on social networks of IDUs. Papers were selected based on their examination of social network factors in relation to the sharing of syringes and drug preparation equipment (e.g. containers, filters, water). Additional relevant papers were found from the reference list of identified articles. Network correlates of drug equipment sharing are multi-factorial and include structural factors (network size, density, position, turnover), compositional factors (network member characteristics, role and quality of relationships with members) and behavioural factors (injecting norms, patterns of drug use, severity of drug addiction). Factors appear to be related differentially to equipment sharing. Social network characteristics are associated with drug injection risk behaviours and should be considered alongside personal risk behaviours in prevention programmes. Recommendations for future research into the social networks of IDUs are proposed.

Three equipment concepts for the Fusion Engineering Device

International Nuclear Information System (INIS)

Spampinato, P.T.; Masson, L.S.; Watts, K.D.; Grant, N.R.; Kuban, D.P.

1982-01-01

Maintenance equipment which is needed to remotely handle fusion device components is being conceptually developed for the Fusion Engineering Design Center. This will test the assumption that these equipment needs can be satisfied by present technology. In addition, the development of equipment conceptual designs will allow for cost estimates which have a much higher degree of certainty. Accurate equipment costs will be useful for assessments which trade off gains in availability as a function of increased investments in maintenance equipment

14 CFR 135.173 - Airborne thunderstorm detection equipment requirements.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Airborne thunderstorm detection equipment... Aircraft and Equipment § 135.173 Airborne thunderstorm detection equipment requirements. (a) No person may... the aircraft is equipped with either approved thunderstorm detection equipment or approved airborne...

RA Reactor operation and maintenance (I-IX), Part III, Task 3.08/04-02 Refurbishment of the electrical equipment; Pogon i odrzavanje reaktora RA (I-IX), III Deo, Zadatak 3.08/04-02 Remont elektro opreme

Energy Technology Data Exchange (ETDEWEB)

Zecevic, V; Nikolic, M; Poznanovic, B; Rajic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

1963-12-15

This volume contains detailed action plan for repair of electrical equipment of the RA reactor, the list of electrical equipment parts which were either repaired or exchanged for improvement of their performance. Detailed work describing the repair and maintenance work done of the listed equipment is part of this report. Equipment related to dosimetry and control systems are included as well.

30 CFR 77.906 - Trailing cables supplying power to low-voltage mobile equipment; ground wires and ground check...

Science.gov (United States)

2010-07-01

... portable or mobile equipment from low-voltage three-phase resistance grounded power systems shall contain... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Trailing cables supplying power to low-voltage... STANDARDS, SURFACE COAL MINES AND SURFACE WORK AREAS OF UNDERGROUND COAL MINES Low- and Medium-Voltage...

14 CFR 25.1439 - Protective breathing equipment.

Science.gov (United States)

2010-01-01

... also enable the flightcrew to use radio equipment. (4) The part of the equipment protecting the eyes... Regulations: (1) The equipment must be designed to protect the appropriate crewmember from smoke, carbon... must include— (i) Masks covering the eyes, nose and mouth, or (ii) Masks covering the nose and mouth...

40 CFR 63.769 - Equipment leak standards.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 10 2010-07-01 2010-07-01 false Equipment leak standards. 63.769... § 63.769 Equipment leak standards. (a) This section applies to equipment subject to this subpart and... release to detect leaks, except under the following conditions. (i) The owner or operator has obtained...

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...

Numerical Analysis of a Passive Containment Filtered Venting System

International Nuclear Information System (INIS)

Kim, Taejoon; Ha, Huiun; Heo, Sun

2014-01-01

The passive Containment Filtered Venting system (CFVS) does not have principally any kind of isolation valves or filtering devices which need periodic maintenance. In this study, the hydro-thermal analysis is presented to investigate the existence of flow instability in the passive CFVS and its performance under the pressure change of APR+ containment building with LB-LOCA M/E data. The Passive Containment Filtered Venting System was suggested as a part in i-Power development project and the operation mechanism was investigated by numerical modeling and simulation using GOTHIC8.0 system code. There are four Phases for consideration to investigate the pressurization of the containment building, loss of hydrostatic head in the pipe line of CFVS, opening of pipe line and gas ejection to the coolant tank, and the head recovery inside the pipe as the containment gas exhausted. The simulation results show that gas generation rate determine the timing of head recovery in the CFVS pipe line and that the equipment of various devices inducing pressure loss at the pipe can give the capacity of Phase control of the passive CFVS operation

Cost analysis for heavy equipment in earthfill work - An optimization of heavy equipment fleet (Case study: Jabung ring dike project)

Science.gov (United States)

Arifin, Muhammad Faizal Ardhiansyah

2017-03-01

Earth fill work with large volumes of soil deposits will involve a lot of heavy equipment with a variety of functions and with different objectives. Where each machine will have different productivity anyway. So that in this paper discusses the calculation of the cost required to do the compacted earthfill work for embankment in accordance with the volume of work, the target date for implementation, and the number of heavy equipment needs. As the cost calculations used heavy equipment rental price per hour. In the cost analysis calculations use heavy equipment here there are several factors that we included in the calculation, are: 1.)Hauling distance; 2.)Effective hour a day; 3.)Change factor of Soil Volume; 4.)Effective Speed; 5.)Equipment efficiency factor; 6.)Equipment coefficient; 7.)Cycle Time.

46 CFR 32.90-1 - Pilot boarding equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 1 2010-10-01 2010-10-01 false Pilot boarding equipment. 32.90-1 Section 32.90-1... REQUIREMENTS Pilot Boarding Equipment § 32.90-1 Pilot boarding equipment. (a) This section applies to each... must have suitable pilot boarding equipment available for use on each side of the vessel. If a vessel...

Nuclear power equipment procurement management under EPC mode

International Nuclear Information System (INIS)

Shuai Yuezhi

2014-01-01

Nuclear power equipment procurement is one of the major constraints and management difficulties in the process of domestic nuclear power project construction for a long time. The construction of Hainan Changjiang Project can not meet the milestones due to the major equipment supply delay. Through the introduction to the organization and features of Changjiang project equipment procurement under EPC mode, and the main problems in the procurement process and its reason analysis, the purpose of this paper is to put forward ideas and suggestions of these items, i.e. selection of equipment suppliers, equipment localization, mass material design and procurement, complete system equipment supply, spare parts delivery and storage, owner process management, providing reference for follow-up projects. (author)

Drawing Evaluation Report for Sampling Equipment Drawings

International Nuclear Information System (INIS)

BOGER, R.M.

1999-01-01

This document presents the results of a task to update the evaluation of River Protection Project (WP) sampling equipment drawings and updates the assigned drawings category as either essential, support, or general drawings. This report updates the drawing evaluation that was originally done per Engineering Task Plan For Truck 3 and 4 Drawing Compliance and Evaluation. The scope of this report is limited to updating the evaluation and identification of drawing category for drawings of certain tank waste sampling equipment for which the RPP Characterization Project has been assigned custody, including: vapor sampling, grab sampling, auger sampling, all core sampling equipment, and Light Duty Utility Arm (LDUA) (see LMHC contract No. 519, release 10). This report does not address drawings for other waste tank deployed equipment systems having similar assigned custody, such as, Cone Penetrometer system, or Long Length Contaminated Equipment (LLCE). The Cone Penetrometer system, which is depicted on vendor drawings, (not H- series), is not currently turned over to operations for deployment. The LLCE equipment was just recently assigned to Characterization Project and was not included in the original scope for this update and will be addressed in the evaluation update scheduled for later in fiscal year 1999, when equipment ownership is determined

Drawing evaluation report for sampling equipment drawings

International Nuclear Information System (INIS)

WILSON, G.W.

1999-01-01

This document presents the results of a task to evaluate Tank Waste Remediation System (TWRS) sampling equipment drawings and identifies drawings category as either essential, support, or general drawings. This report completes the drawing evaluation task as outlined in Engineering Task Plan For Truck 3 and 4 Drawing Compliance and Evaluation (Wilson, 1997). The scope of this report is limited to an evaluation and identification of drawing category for drawings of certain tank waste sampling equipment for which the TRWS Characterization Project has been assigned custody, including: vapor sampling, grab sampling, auger sampling, and all core sampling equipment (see LMHC Task Order 304). This report does not address drawings for other waste tank deployed equipment systems having similar assigned custody, such as, Light Duty Utility Arm (LDUA), Cone Penetrometer system, or Long Length Contaminated Equipment (LLCE). The LDUA drawings are addressed in the Characterization Equipment Essential Drawings (HNF 1998). The Cone Penetrometer system drawings which are vendor drawings (not H- series) is not currently turned over to operations for deployment. The LLCE equipment was just recently assigned to Characterization Project and were not included in the original scope for this evaluation and will be addressed in the evaluation update scheduled for fiscal year 1999

AX Tank Farm ancillary equipment study

International Nuclear Information System (INIS)

SKELLY, W.A.

1999-01-01

This report examines the feasibility of remediating ancillary equipment associated with the 241-AX Tank Farm at the Hanford Site. Ancillary equipment includes surface structures and equipment, process waste piping, ventilation components, wells, and pits, boxes, sumps, and tanks used to make waste transfers to/from the AX tanks and adjoining tank farms. Two remedial alternatives are considered: (1) excavation and removal of all ancillary equipment items, and (2) in-situ stabilization by grout filling, the 241-AX Tank Farm is being employed as a strawman in engineering studies evaluating clean and landfill closure options for Hanford single-shell tanks. This is one of several reports being prepared for use by the Hanford Tanks Initiative Project to explore potential closure options and to develop retrieval performance evaluation criteria for tank farms

29 CFR 1926.603 - Pile driving equipment.