Studies and research concerning BNFP: cask handling equipment standardization

International Nuclear Information System (INIS)

McCreery, P.N.

1980-10-01

This report covers the activities of one of the sub-tasks within the Spent LWR Fuel Transportation Receiving, Handling, and Storage program. The sub-task is identified as Cask Handling Equipment Standardization. The objective of the sub-task specifies: investigate and identify opportunities for standardization of cask interface equipment. This study will examine the potential benefits of standardized yokes, decontamination barriers and special tools, and, to the extent feasible, standardized methods and software for handling the variety of casks presently available in the US fleet. The result of the investigations is a compilation of reports that are related by their common goal of reducing cask turnaround time

Renewal of handling and storage equipment in wholesale company

Directory of Open Access Journals (Sweden)

Tânia Brasileiro Azevedo Teixeira

2015-06-01

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

Remote handling equipment for SNS

International Nuclear Information System (INIS)

Poulten, B.H.

1983-01-01

This report gives information on the areas of the SNS, facility which become highly radioactive preventing hands-on maintenance. Levels of activity are sufficiently high in the Target Station Area of the SNS, especially under fault conditions, to warrant reactor technology to be used in the design of the water, drainage and ventilation systems. These problems, together with the type of remote handling equipment required in the SNS, are discussed

Development of nuclear fuel microsphere handling techniques and equipment

International Nuclear Information System (INIS)

Mack, J.E.; Suchomel, R.R.; Angelini, P.

1979-01-01

Considerable progress has been made in the development of microsphere handling techniques and equipment for nuclear applications. Work at Oak Ridge National Laboratory with microspherical fuel forms dates back to the early sixties with the development of the sol-gel process. Since that time a number of equipment items and systems specifically related to microsphere handling and characterization have been identified and developed for eventual application in a remote recycle facility. These include positive and negative pressure transfer systems, samplers, weighers, a blender-dispenser, and automated devices for particle size distribution and crushing strength analysis. The current status of these and other components and systems is discussed

Progress in control equipment for fuel-handling machinery

International Nuclear Information System (INIS)

Nutting, B.A.

1986-01-01

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

Performance Evaluation and Suggestion of Upgraded Fuel Handling Equipment for Operating OPR1000

International Nuclear Information System (INIS)

Chang, Sang Gyoon; Hwang, Jeung Ki; Choi, Taek Sang; Na, Eun Seok; Lee, Myung Lyul; Baek, Seung Jin; Kim, Man Su; Kunik, Jack

2011-01-01

The purpose of this study is to evaluate the performance of upgraded FHE (Fuel Handling Equipment) for operating OPR 1000 (Optimized Power Reactor) by using data measured during the fuel reloading, and make some suggestions on enhancing the performance of the FHE. The fuel handling equipment, which serves critical processes in the refueling outage, has been upgraded to increase and improve the operational availability of the plant. The evaluation and suggestion of this study can be a beneficial tool related to the performance of the fuel handling equipment

ITER L 7 duct remote handling equipment design report

International Nuclear Information System (INIS)

Millard, J.

1996-09-01

The operation, design and interfaces of the 'Duct Vehicle' and it's associated remote handling equipment are briefly described in this document. This equipment is being designed by Spar Aerospace Ltd. for the Divertor Test Platform as part of ITER Research and Development Project L-7. Canadian Fusion Fuels Technology Project funds this work as part of the Canadian Contribution to ITER. This document describes the equipment design status at the September 1996 design review. 23 figs

Development of remote handling tools and equipment

International Nuclear Information System (INIS)

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

1997-01-01

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

77 FR 23117 - Rigging Equipment for Material Handling Construction Standard; Correction and Technical Amendment

Science.gov (United States)

2012-04-18

... Equipment for Material Handling Construction Standard; Correction and Technical Amendment AGENCY... AND HEALTH REGULATIONS FOR CONSTRUCTION Subpart H--Materials Handling, Storage, Use, and Disposal 0 1... amendment. SUMMARY: OSHA is correcting its sling standard for construction titled ``Rigging Equipment for...

Design guides for radioactive-material-handling facilities and equipment

International Nuclear Information System (INIS)

Doman, D.R.; Barker, R.E.

1980-01-01

Fourteen key areas relating to facilities and equipment for handling radioactive materials involved in examination, reprocessing, fusion fuel handling and remote maintenance have been defined and writing groups established to prepare design guides for each areas. The guides will give guidance applicable to design, construction, operation, maintenance and safety, together with examples and checklists. Each guide will be reviewed by an independent review group. The guides are expected to be compiled and published as a single document

Design of remote handling equipment for the ITER NBI

Energy Technology Data Exchange (ETDEWEB)

Oka, Kiyoshi; Tada, Eisuke [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1999-08-01

The ITER machine has three Neutral Beam Injectors (NBIs) placed tangential to the plasma at a minimum radius of 6.25 m. During operation, neutrons produced by the D-T reactions will irradiate the NBI structure and it will become radioactive. Radiation levels will be such that all subsequent maintenance of the NBIs must be carried out remotely. The presence of tritium and possibly radioactive dust requires that precautions be taken during maintenance to prevent the escape of these contaminants beyond the prescribed boundaries. The scope of this task is both the development of remote maintenance procedures and the design of the remote handling equipment to handle the NBIs. This report describes the design of remote handling tools for the ion source and its filaments, transfer cask, maintenance time, manufacturing schedule and cost estimation. (author)

Demonstration of remotely operated TRU waste size reduction and material handling equipment

International Nuclear Information System (INIS)

Looper, M.G.; Charlesworth, D.L.

1988-01-01

The Savannah River Laboratory (SRL) is developing remote size reduction and material handling equipment to prepare 238 Pu contaminated waste for permanent disposal at the Waste Isolation Pilot Plant (WIPP) in New Mexico. The waste is generated at the Savannah River Plant (SRP) from normal operation and decommissioning activity and is retrievably stored onsite. A Transuranic Waste Facility for preparing, size-reducing, and packaging this waste for disposal is scheduled for completion in 1995. A cold test facility for demonstrating the size reduction and material handling equipment was built, and testing began in January 1987. 9 figs., 1 tab

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

Classification and handling of non-conformance item of nuclear class equipment during manufacture phase

International Nuclear Information System (INIS)

Wang Ruiping

2001-01-01

Based on inspection experiences in years on nuclear class equipment manufacturing, the author discusses the classification and handling of non-conformance items occurred during equipment manufacturing, and certain technical considerations are presented

78 FR 70326 - Rigging Equipment for Material Handling; Extension of the Office of Management and Budget's (OMB...

Science.gov (United States)

2013-11-25

...] Rigging Equipment for Material Handling; Extension of the Office of Management and Budget's (OMB) Approval... on Rigging Equipment for Material Handling (29 CFR 1926.251). These paragraphs require affixing... automated or other technological information collection and transmission techniques. III. Proposed Actions...

Remote handling equipment design for the HEDL fuel supply program

International Nuclear Information System (INIS)

Metcalf, I.L.

1984-09-01

A process line is currently being developed for fabrication of high exposure mixed uranium-plutonium core assemblies. This paper describes the design philosophy, process flow, equipment, and the handling and radiation shielding techniques used for inspection of Fast Flux Test Facility (FFTF) fuel pins and assembly of Driver Fuel Assemblies (DFAs) 6 figures

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

International Nuclear Information System (INIS)

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

2006-03-01

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

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

Directory of Open Access Journals (Sweden)

Abdolreza Yazdani-Chamzini

2012-10-01

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

Remotely-operated equipment for inspection, measurement and handling

CERN Document Server

Bertone, C; CERN. Geneva. TS Department

2008-01-01

As part of the application of ALARA radiation dose reduction principles at CERN, inspection, measurement and handling interventions in controlled areas are being studied in detail. A number of activities which could be carried out as remote operations have already been identified and equipment is being developed. Example applications include visual inspection to check for ice formation on LHC components or water leaks, measurement of radiation levels before allowing personnel access, measurement of collimator or magnet alignment, visual inspection or measurements before fire service access in the event of fire, gas leak or oxygen deficiency. For these applications, a modular monorail train, TIM, has been developed with inspection and measurement wagons. In addition TIM provides traction, power and data communication for lifting and handling units such as the remote collimator exchange module and vision for other remotely operated units such as the TAN detector exchange mini-cranes. This paper describes the eq...

Fuel Handling Equipment Maintenance for Critical Path Time Savings

Energy Technology Data Exchange (ETDEWEB)

Saville, M.; Williams, A.

2015-07-01

By sharing lessons learned and operating experience gained by AREVA Stearns RogerTM Services from more than 45 years of servicing, maintaining, and upgrading Fuel Handling Equipment (FHE) and as the original equipment manufacturer to 56% of domestic U.S. FHE (PWR and BWR) as well as 19 units overseas, this paper presents trends and market forces that have led to the neglect of FHE, the risks of not adequately maintaining FHE, and the financial benefits of proactively maintaining FHE. The benefit to audiences is to come to a better understanding of how critical path delays can be avoided and thus reduce nuclear power plant operating costs. Note that statistics and monetary values given herein are based on recent typical experiences of AREVA Stearns RogerTM Services. Examples discussed are based on actual lessons learned. For the purposes of this paper, upgrades are considered a part of equipment maintenance unless specifically discussed separately. (Author)

29 CFR 1926.1000 - Rollover protective structures (ROPS) for material handling equipment.

Science.gov (United States)

2010-07-01

... 29 Labor 8 2010-07-01 2010-07-01 false Rollover protective structures (ROPS) for material handling equipment. 1926.1000 Section 1926.1000 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY... CONSTRUCTION Rollover Protective Structures; Overhead Protection § 1926.1000 Rollover protective structures...

49 CFR 232.609 - Handling of defective equipment with ECP brake systems.

Science.gov (United States)

2010-10-01

... (ECP) Braking Systems § 232.609 Handling of defective equipment with ECP brake systems. (a) Ninety-five... systems. 232.609 Section 232.609 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL RAILROAD ADMINISTRATION, DEPARTMENT OF TRANSPORTATION BRAKE SYSTEM SAFETY STANDARDS FOR FREIGHT...

Minimizing the carbon footprint of material handling equipment: Comparison of electric and LPG forklifts

Energy Technology Data Exchange (ETDEWEB)

Facchini, F.; Mummolo, G.; Mossa, G.; Digiesi, S.; Boenzi, F.; Verriello, R.

2016-07-01

Purpose: The aim of this study is to identify the best Material Handling Equipment (MHE) to minimize the carbon footprint of inbound logistic activities, based on the type of the warehouse (layout, facilities and order-picking strategy) as well as the weight of the loads to be handled. Design/methodology/approach: A model to select the best environmental MHE for inbound logistic activities has been developed. Environmental performance of the MHE has been evaluated in terms of carbon Footprint (CF). The model is tested with a tool adopting a VBA macro as well as a simulation software allowing the evaluation of energy and time required by the forklift in each phase of the material handling cycle: picking, sorting and storing of the items. Findings: Nowadays, it is not possible to identify ‘a priori’ a particular engine equipped forklift performing better than others under an environmental perspective. Consistently, the application of the developed model allows to identify the best MHE tailored to each case analyzed. Originality/value: This work gives a contribution to the disagreement between environmental performances of forklifts equipped with different engines. The developed model can be considered a valid support for decision makers to identify the best MHE minimizing the carbon footprint of inbound logistic activities.

Minimizing the carbon footprint of material handling equipment: Comparison of electric and LPG forklifts

International Nuclear Information System (INIS)

Facchini, F.; Mummolo, G.; Mossa, G.; Digiesi, S.; Boenzi, F.; Verriello, R.

2016-01-01

Purpose: The aim of this study is to identify the best Material Handling Equipment (MHE) to minimize the carbon footprint of inbound logistic activities, based on the type of the warehouse (layout, facilities and order-picking strategy) as well as the weight of the loads to be handled. Design/methodology/approach: A model to select the best environmental MHE for inbound logistic activities has been developed. Environmental performance of the MHE has been evaluated in terms of carbon Footprint (CF). The model is tested with a tool adopting a VBA macro as well as a simulation software allowing the evaluation of energy and time required by the forklift in each phase of the material handling cycle: picking, sorting and storing of the items. Findings: Nowadays, it is not possible to identify ‘a priori’ a particular engine equipped forklift performing better than others under an environmental perspective. Consistently, the application of the developed model allows to identify the best MHE tailored to each case analyzed. Originality/value: This work gives a contribution to the disagreement between environmental performances of forklifts equipped with different engines. The developed model can be considered a valid support for decision makers to identify the best MHE minimizing the carbon footprint of inbound logistic activities.

Minimizing the carbon footprint of material handling equipment: Comparison of electric and LPG forklifts

Directory of Open Access Journals (Sweden)

Francesco Facchini

2016-12-01

Full Text Available Purpose: The aim of this study is to identify the best Material Handling Equipment (MHE to minimize the carbon footprint of inbound logistic activities, based on the type of the warehouse (layout, facilities and order-picking strategy as well as the weight of the loads to be handled. Design/methodology/approach: A model to select the best environmental MHE for inbound logistic activities has been developed. Environmental performance of the MHE has been evaluated in terms of carbon Footprint (CF. The model is tested with a tool adopting a VBA macro as well as a simulation software allowing the evaluation of energy and time required by the forklift in each phase of the material handling cycle: picking, sorting and storing of the items. Findings: Nowadays, it is not possible to identify ‘a priori’ a particular engine equipped forklift performing better than others under an environmental perspective. Consistently, the application of the developed model allows to identify the best MHE tailored to each case analyzed.   Originality/value: This work gives a contribution to the disagreement between environmental performances of forklifts equipped with different engines. The developed model can be considered a valid support for decision makers to identify the best MHE minimizing the carbon footprint of inbound logistic activities.

Development of a telerobotic system for handling contaminated process equipment

International Nuclear Information System (INIS)

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

1987-01-01

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

Development of a zonal applicability tool for remote handling equipment in DEMO

Energy Technology Data Exchange (ETDEWEB)

Madzharov, Vladimir, E-mail: vladimir.madzharov@kit.edu [Karlsruhe Institute of Technology, Institute for Material Handling and Logistics, Karlsruhe (Germany); Mittwollen, Martin [Karlsruhe Institute of Technology, Institute for Material Handling and Logistics, Karlsruhe (Germany); Leichtle, Dieter [Fusion for Energy F4E, Barcelona (Spain); Hermon, Gary [Culham Center for Fusion Energy, Culham Science Centre, OX14 3DB Abingdon (United Kingdom)

2015-10-15

Highlights: • Radiation-hardness assessment of remote handling (RH) components used in DEMO. • A radiation assessment tool for supporting remote handling engineers. • Connecting data from the radiation field analysis to the radiation hardness data. • Output is the expected lifetime of the selected RH component used for maintenance. - Abstract: A radiation-induced damage caused by the ionizing radiation can induce a malfunctioning of the remote handling equipment (RHE) used during maintenance in fusion power plants, other nuclear power stations and high-energy accelerators facilities like e.g. IFMIF. Therefore to achieve a sufficient length of operational time inside future fusion power plants, a suitable radiation tolerant RHE for maintenance operations in radiation environments is inevitably required. To assess the influence of the radiation on remote handling equipment (RHE), an investigation about radiation hardness assessment of typically used RHE components, has been performed. Additionally, information about the absorbed total dose that every component can withstand before failure was collected. Furthermore, the development of a zonal applicability tool for supporting RHE designers has been started using Excel VBA. The tool connects the data from the radiation field analysis (3-D radiation map) to the radiation hardness data of the planned RHE for DEMO remote maintenance. The intelligent combination of the available information for the radiation behaviour and radiation level at certain time and certain location may help with the taking of decisions about the application of RHE in radiation environment. The user inputs the following parameters: the specific device used in the RHE, the planned location and the maintenance period. The output is the expected lifetime of the selected RHE component at the given location and maintenance period. Planned action times have to be also considered. After having all the parameters it can be decided, if specific RHE

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

International Nuclear Information System (INIS)

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

1990-05-01

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

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

International Nuclear Information System (INIS)

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

1991-01-01

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

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

CERN Document Server

Bertone, C; CERN. Geneva. TS Department

2004-01-01

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

Preventive maintenance basis: Volume 21 -- HVAC, air handling equipment. Final report

International Nuclear Information System (INIS)

Worledge, D.; Hinchcliffe, G.

1997-12-01

US nuclear plants are implementing preventive maintenance (PM) tasks with little documented basis beyond fundamental vendor information to support the tasks or their intervals. The Preventive Maintenance Basis project provides utilities with the technical basis for PM tasks and task intervals associated with 40 specific components such as valves, electric motors, pumps, and HVAC equipment. This report provides an overview of the PM Basis project and describes use of the PM Basis database. Volume 21 of the report provides a program of PM tasks suitable for application to HVAC-Air Handling Equipment. The PM tasks that are recommended provide a cost-effective way to intercept the causes and mechanisms that lead to degradation and failure. They can be used, in conjunction with material from other sources, to develop a complete PM program or to improve an existing program. Users of this information will be utility managers, supervisors, craft technicians, and training instructors responsible for developing, optimizing, or fine-tuning PM programs

TMI-2 [Three Mile Island Nuclear Power Station] fuel canister and core sample handling equipment used in INEL hot cells

International Nuclear Information System (INIS)

McConnell, J.W. Jr.; Shurtliff, W.T.; Lynch, R.J.; Croft, K.M.; Whitmill, L.J.; Allen, S.M.

1987-01-01

This paper describes the specialized remote handling equipment developed and used at the Idaho National Engineering Laboratory (INEL) to handle samples obtained from the core of the damaged Unit 2 reactor at Three Mile Island Nuclear Power Station (TM-2). Samples of the core were removed, placed in TMI-2 fuel canisters, and transported to the INEL. Those samples will be examined as part of the analysis of the TMI-2 accident. The equipment described herein was designed for removing sample materials from the fuel canisters, assisting with initial examination, and processing samples in preparation for detailed examinations. The more complex equipment used microprocessor remote controls with electric motor drives providing the required force and motion capabilities. The remaining components were unpowered and manipulator assisted

Safety Analysis of 'Older/Aged' Handling and Transportation Equipment for Heavy Loads, Radioactive Waste and Materials in Accordance with German Nuclear Standards KTA 3902, 3903 and 3905

International Nuclear Information System (INIS)

Macias, P.; Prucker, E.; Stang, W.

2006-01-01

The purpose of this paper is to present a general safety analysis of important handling and transportation processes and their related equipment ('load chains' consisting of cranes, load-bearing equipment and load-attaching points). This project was arranged by the responsible Bavarian ministry for environment, health and consumer protection (StMUGV) in agreement with the power plant operators of all Bavarian nuclear power plants to work out potential safety improvements. The range of the equipment (e.g. reactor building, crane, refuelling machine, load-bearing equipment and load-attaching points) covers the handling and transportation of fuel elements (e. g. with fuel flasks), heavy loads (e.g. reactor pressure vessel closure head, shielding slabs) and radioactive materials and waste (e.g. waste flasks, control elements, fuel channels, structure elements). The handling equipment was subjected to a general safety analysis taking into account the ageing of the equipment and the progress of standards. Compliance with the current valid requirements of the state of science and technology as required by German Atomic Act and particularly of the nuclear safety KTA-standards (3902, 3903 and 3905) was examined. The higher protection aims 'safe handling and transportation of heavy loads and safe handling of radioactive materials and waste' of the whole analysis are to avoid a criticality accident, the release of radioactivity and inadmissible effects on important technical equipment and buildings. The scope of the analysis was to check whether these protection aims were fulfilled for all important technical handling and transportation processes. In particularly the design and manufacturing of the components and the regulations of the handling itself were examined. (authors)

30 CFR 250.108 - What requirements must I follow for cranes and other material-handling equipment?

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 2 2010-07-01 2010-07-01 false What requirements must I follow for cranes and... Performance Standards § 250.108 What requirements must I follow for cranes and other material-handling equipment? (a) All cranes installed on fixed platforms must be operated in accordance with American...

Specialization and Flexibility in Port Cargo Handling

Directory of Open Access Journals (Sweden)

Hakkı KİŞİ

2016-11-01

Full Text Available Cargo handling appears to be the fundamental function of ports. In this context, the question of type of equipment and capacity rate need to be tackled with respect to cargo handling principles. The purpose of this study is to discuss the types of equipment to be used in ports, relating the matter to costs and capacity. The question is studied with a basic economic theoretical approach. Various conditions like port location, size, resources, cargo traffic, ships, etc. are given parameters to dictate the type and specification of the cargo handling equipment. Besides, a simple approach in the context of cost capacity relation can be useful in deciding whether to use specialized or flexible equipment. Port equipment is sometimes expected to be flexible to handle various types of cargo as many as possible and sometimes to be specialized to handle one specific type of cargo. The cases that might be suitable for those alternatives are discussed from an economic point of view in this article. Consequently, effectiveness and efficiency criteria play important roles in determining the handling equipment in ports.

Comparison of Customer Preference for Bulk Material Handling Equipment through Fuzzy-AHP Approach

Science.gov (United States)

Sen, Kingshuk; Ghosh, Surojit; Sarkar, Bijan

2017-06-01

In the present study, customer's perception has played one of the important roles for selection of the exact equipment out of available alternatives. The present study is dealt with the method of optimization of selection criteria of a material handling equipment, based on the technical specifications considered to be available at the user end. In this work, the needs of customers have been identified and prioritized, that lead to the selection of number of criteria, which have direct effect upon the performance of the equipment. To check the consistency of selection criteria, first of all an AHP based methodology is adopted with the identified criteria and available product categories, based upon which, the judgments of the users are defined to derive the priority scales. Such judgments expressed the relative strength or intensity of the impact of the elements of the hierarchy. Subsequently, all the alternatives have ranked for each identified criteria with subsequent constitution of weighted matrices. The same has been compared with the normalized values of approximate selling prices of the equipments to determine individual cost-benefit ratio. Based on the cost-benefit ratio, the equipment is ranked. With same conditions, the study is obtained again with a Fuzzy AHP concept, where a fuzzy linguistic approach has reduced the amount of uncertainty in decision making, caused by conventional AHP due to lack of deterministic approach. The priority vectors of category and criteria are determined separately and multiplied to obtain composite score. Subsequently, the average of fuzzy weights was determined and the preferences of equipment are ranked.

Order of 2 May 1977 on a proficiency certificate for handling industrial radioscopy and radiography equipment

International Nuclear Information System (INIS)

1977-01-01

This Order lays down that any person handling industrial radioscopy or radiography equipment must obtain a proficiency certificate delivered by a regional jury made up of the regional director for labour and manpower or his representative, a physician competent for industrial medicine and specialized in radiation protection and an expert in industrial radiology. (NEA) [fr

Proposal for the award of a contract for the maintenance of industrial transport and handling equipment

CERN Document Server

European Organization for Nuclear Research

2002-01-01

This document concerns the award of a contract for the maintenance of industrial transport and handling equipment. Following a market survey carried out among 145 firms in sixteen Member States, a call for tenders (IT-3049/ST) was sent on 8 May 2002 to two firms and four consortia, one consortium consisting of three firms and three consortia consisting of two firms, in three Member States. By the closing date, CERN had received six tenders from six consortia in three Member States. The Finance Committee is invited to agree to the negotiation of a contract with the consortium CEGELEC (FR), SPIE-TRINDEL (FR), ELECTRON (NL) and FENWICK-LINDE (FR), the lowest bidder after alignment, for the maintenance of industrial transport and handling equipment for a total amount of 2 973 280 euros (4 346 900 Swiss francs), covering an initial period of three years starting on 1 October 2002, subject to revision for inflation from 1 October 2005. The contract will include an option for two further one-year extensions beyond t...

Remote handling facility and equipment used for space truss assembly

International Nuclear Information System (INIS)

Burgess, T.W.

1987-01-01

The ACCESS truss remote handling experiments were performed at Oak Ridge National Laboratory's (ORNL's) Remote Operation and Maintenance Demonstration (ROMD) facility. The ROMD facility has been developed by the US Department of Energy's (DOE's) Consolidated Fuel Reprocessing Program to develop and demonstrate remote maintenance techniques for advanced nuclear fuel reprocessing equipment and other programs of national interest. The facility is a large-volume, high-bay area that encloses a complete, technologically advanced remote maintenance system that first began operation in FY 1982. The maintenance system consists of a full complement of teleoperated manipulators, manipulator transport systems, and overhead hoists that provide the capability of performing a large variety of remote handling tasks. This system has been used to demonstrate remote manipulation techniques for the DOE, the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan, and the US Navy in addition to the National Aeronautics and Space Administration. ACCESS truss remote assembly was performed in the ROMD facility using the Central Research Laboratory's (CRL) model M-2 servomanipulator. The model M-2 is a dual-arm, bilateral force-reflecting, master/slave servomanipulator which was jointly developed by CRL and ORNL and represents the state of the art in teleoperated manipulators commercially available in the United States today. The model M-2 servomanipulator incorporates a distributed, microprocessor-based digital control system and was the first successful implementation of an entirely digitally controlled servomanipulator. The system has been in operation since FY 1983. 3 refs., 2 figs

The JET experience with remote handling equipment and future prospects

International Nuclear Information System (INIS)

Raimondi, T.

1989-01-01

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

The Jet experience with remote handling equipment and future prospects

International Nuclear Information System (INIS)

Raimondi, T.

1989-01-01

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

The JET experience with remote handling equipment and future prospects

International Nuclear Information System (INIS)

Raimondi, T.

1989-01-01

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

Fuel handling machine and auxiliary systems for a fuel handling cell

International Nuclear Information System (INIS)

Suikki, M.

2013-10-01

This working report is an update for as well as a supplement to an earlier fuel handling machine design (Kukkola and Roennqvist 2006). A focus in the earlier design proposal was primarily on the selection of a mechanical structure and operating principle for the fuel handling machine. This report introduces not only a fuel handling machine design but also auxiliary fuel handling cell equipment and its operation. An objective of the design work was to verify the operating principles of and space allocations for fuel handling cell equipment. The fuel handling machine is a remote controlled apparatus capable of handling intensely radiating fuel assemblies in the fuel handling cell of an encapsulation plant. The fuel handling cell is air tight space radiation-shielded with massive concrete walls. The fuel handling machine is based on a bridge crane capable of traveling in the handling cell along wall tracks. The bridge crane has its carriage provided with a carousel type turntable having mounted thereon both fixed and telescopic masts. The fixed mast has a gripper movable on linear guides for the transfer of fuel assemblies. The telescopic mast has a manipulator arm capable of maneuvering equipment present in the fuel handling cell, as well as conducting necessary maintenance and cleaning operations or rectifying possible fault conditions. The auxiliary fuel handling cell systems consist of several subsystems. The subsystems include a service manipulator, a tool carrier for manipulators, a material hatch, assisting winches, a vacuum cleaner, as well as a hose reel. With the exception of the vacuum cleaner, the devices included in the fuel handling cell's auxiliary system are only used when the actual encapsulation process is not ongoing. The malfunctions of mechanisms or actuators responsible for the motion actions of a fuel handling machine preclude in a worst case scenario the bringing of the fuel handling cell and related systems to a condition appropriate for

Fuel handling machine and auxiliary systems for a fuel handling cell

Energy Technology Data Exchange (ETDEWEB)

Suikki, M. [Optimik Oy, Turku (Finland)

2013-10-15

This working report is an update for as well as a supplement to an earlier fuel handling machine design (Kukkola and Roennqvist 2006). A focus in the earlier design proposal was primarily on the selection of a mechanical structure and operating principle for the fuel handling machine. This report introduces not only a fuel handling machine design but also auxiliary fuel handling cell equipment and its operation. An objective of the design work was to verify the operating principles of and space allocations for fuel handling cell equipment. The fuel handling machine is a remote controlled apparatus capable of handling intensely radiating fuel assemblies in the fuel handling cell of an encapsulation plant. The fuel handling cell is air tight space radiation-shielded with massive concrete walls. The fuel handling machine is based on a bridge crane capable of traveling in the handling cell along wall tracks. The bridge crane has its carriage provided with a carousel type turntable having mounted thereon both fixed and telescopic masts. The fixed mast has a gripper movable on linear guides for the transfer of fuel assemblies. The telescopic mast has a manipulator arm capable of maneuvering equipment present in the fuel handling cell, as well as conducting necessary maintenance and cleaning operations or rectifying possible fault conditions. The auxiliary fuel handling cell systems consist of several subsystems. The subsystems include a service manipulator, a tool carrier for manipulators, a material hatch, assisting winches, a vacuum cleaner, as well as a hose reel. With the exception of the vacuum cleaner, the devices included in the fuel handling cell's auxiliary system are only used when the actual encapsulation process is not ongoing. The malfunctions of mechanisms or actuators responsible for the motion actions of a fuel handling machine preclude in a worst case scenario the bringing of the fuel handling cell and related systems to a condition appropriate for

Evaluation of the Total Cost of Ownership of Fuel Cell-Powered Material Handling Equipment

Energy Technology Data Exchange (ETDEWEB)

Ramsden, T.

2013-04-01

This report discusses an analysis of the total cost of ownership of fuel cell-powered and traditional battery-powered material handling equipment (MHE, or more typically 'forklifts'). A number of fuel cell MHE deployments have received funding support from the federal government. Using data from these government co-funded deployments, DOE's National Renewable Energy Laboratory (NREL) has been evaluating the performance of fuel cells in material handling applications. NREL has assessed the total cost of ownership of fuel cell MHE and compared it to the cost of ownership of traditional battery-powered MHE. As part of its cost of ownership assessment, NREL looked at a range of costs associated with MHE operation, including the capital costs of battery and fuel cell systems, the cost of supporting infrastructure, maintenance costs, warehouse space costs, and labor costs. Considering all these costs, NREL found that fuel cell MHE can have a lower overall cost of ownership than comparable battery-powered MHE.

9 CFR 381.201 - Means of conveyance and equipment used in handling poultry products offered for entry to be...

Science.gov (United States)

2010-01-01

... INSPECTION AND CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS Imported Poultry Products § 381.201... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Means of conveyance and equipment used in handling poultry products offered for entry to be maintained in sanitary condition. 381.201...

Management of transport and handling contracts

CERN Document Server

Rühl, I

2004-01-01

This paper shall outline the content, application and management strategies for the various contracts related to transport and handling activities. In total, the two sections Logistics and Handling Maintenance are in charge of 27 (!) contracts ranging from small supply contracts to big industrial support contracts. The activities as well as the contracts can generally be divided into four main topics "Vehicle Fleet Management"; "Supply, Installation and Commissioning of Lifting and Hoisting Equipment"; "Equipment Maintenance" and "Industrial Support for Transport and Handling". Each activity and contract requires different approaches and permanent adaptation to the often changing CERN's requirements. In particular, the management and the difficulties experienced with the contracts E072 "Maintenance of lifting and hoisting equipment", F420 "Supply of seven overhead traveling cranes for LHC" and S090/S103 "Industrial support for transport and handling" will be explained in detail.

A multi-component patient-handling intervention improves attitudes and behaviors for safe patient handling and reduces aggression experienced by nursing staff

DEFF Research Database (Denmark)

Risør, Bettina Wulff; Casper, Sven Dalgas; Andersen, Lars L.

2017-01-01

This study evaluated an intervention for patient-handling equipment aimed to improve nursing staffs' use of patient handling equipment and improve their general health, reduce musculoskeletal problems, aggressive episodes, days of absence and work-related accidents. As a controlled before......-after study, questionnaire data were collected at baseline and 12-month follow-up among nursing staff at intervention and control wards at two hospitals. At 12-month follow-up, the intervention group had more positive attitudes towards patient-handling equipment and increased use of specific patient......-handling equipment. In addition, a lower proportion of nursing staff in the intervention group had experienced physically aggressive episodes. No significant change was observed in general health status, musculoskeletal problems, days of absence or work-related accidents. The intervention resulted in more positive...

A new virtual-reality training module for laparoscopic surgical skills and equipment handling: can multitasking be trained? A randomized controlled trial

NARCIS (Netherlands)

Bongers, P.J.; van Hove, P.D.; Stassen, L.P.S.; Schreuder, HWR; Dankelman, J.

Objective During laparoscopic surgery distractions often occur and multitasking between surgery and other tasks, such as technical equipment handling, is a necessary competence. In psychological research, reduction of adverse effects of distraction is demonstrated when specifically multitasking is

Overhead remote handling systems for the process facility modifications project

International Nuclear Information System (INIS)

Wiesener, R.W.; Grover, D.L.

1987-01-01

Each of the cells in the process facility modifications (PFM) project complex is provided with a variety of general purpose remote handling equipment including bridge cranes, monorail hoist, bridge-mounted electromechanical manipulator (EMM) and an overhead robot used for high efficiency particulate air (HEPA) filter changeout. This equipment supplements master-slave manipulators (MSMs) located throughout the complex to provide an overall remote handling system capability. The overhead handling equipment is used for fuel and waste material handling operations throughout the process cells. The system also provides the capability for remote replacement of all in-cell process equipment which may fail or be replaced for upgrading during the lifetime of the facility

Ergonomics and patient handling.

Science.gov (United States)

McCoskey, Kelsey L

2007-11-01

This study aimed to describe patient-handling demands in inpatient units during a 24-hour period at a military health care facility. A 1-day total population survey described the diverse nature and impact of patient-handling tasks relative to a variety of nursing care units, patient characteristics, and transfer equipment. Productivity baselines were established based on patient dependency, physical exertion, type of transfer, and time spent performing the transfer. Descriptions of the physiological effect of transfers on staff based on patient, transfer, and staff characteristics were developed. Nursing staff response to surveys demonstrated how patient-handling demands are impacted by the staff's physical exertion and level of patient dependency. The findings of this study describe the types of transfers occurring in these inpatient units and the physical exertion and time requirements for these transfers. This description may guide selection of the most appropriate and cost-effective patient-handling equipment required for specific units and patients.

Comparative analysis of numerical models of pipe handling equipment used in offshore drilling applications

Energy Technology Data Exchange (ETDEWEB)

Pawlus, Witold, E-mail: witold.p.pawlus@ieee.org; Ebbesen, Morten K.; Hansen, Michael R.; Choux, Martin; Hovland, Geir [Department of Engineering Sciences, University of Agder, PO Box 509, N-4898 Grimstad (Norway)

2016-06-08

Design of offshore drilling equipment is a task that involves not only analysis of strict machine specifications and safety requirements but also consideration of changeable weather conditions and harsh environment. These challenges call for a multidisciplinary approach and make the design process complex. Various modeling software products are currently available to aid design engineers in their effort to test and redesign equipment before it is manufactured. However, given the number of available modeling tools and methods, the choice of the proper modeling methodology becomes not obvious and – in some cases – troublesome. Therefore, we present a comparative analysis of two popular approaches used in modeling and simulation of mechanical systems: multibody and analytical modeling. A gripper arm of the offshore vertical pipe handling machine is selected as a case study for which both models are created. In contrast to some other works, the current paper shows verification of both systems by benchmarking their simulation results against each other. Such criteria as modeling effort and results accuracy are evaluated to assess which modeling strategy is the most suitable given its eventual application.

General Guidelines for Remote Operation and Maintenance of Pyroprocess Equipment

Energy Technology Data Exchange (ETDEWEB)

Kim, S. H.; Park, B. S.; Park, H. S.; Lee, H. J.; Choi, C. W.; Lee, J. K

2007-12-15

As the pyroprocess handle the high radioactive materials, a high radioactive material handling facility required high safety, radioactive shielding, strict quality control, and the remote handling equipment of high technology. This report describes the guidelines of for pyroprocess based the design guides for radioactive material handling facility and equipment from American Nuclear Society(ANS), design guidelines for remotely maintained equipment from Oak Ridge National Laboratory(ORNL), and the experience of design for ACP equipment installed at the ACPF(Advanced Conditioning Process Facility). The General guidelines in this report are as follows. The General guidelines for remote operation and maintenance of pyroprocess equipment: Pyroprocess, Remote handling equipment for pyroprocess, General guide for remote operation and maintenance, general guidelines for the design of remotely operated and maintained equipment, Estimation and analysis for remote maintenance.

Remote handling equipment for laboratory research of fuel reprocessing in Nuclear Research Institute at Rez

International Nuclear Information System (INIS)

Fidler, J.; Novy, P.; Kyrs, M.

1985-04-01

Laboratory installations were developed for two nuclear fuel reprocessing methods, viz., the solvent extraction process and the fluoride volatility process. The apparatus for solvent extraction reprocessing consists of a pneumatically driven rod-chopper, a dissolver, mixer-settler extractors, an automatic fire extinguishing device and other components and it was tested using irradiated uranium. The technological line for the fluoride volatility process consists of a fluorimater, condensers, sorption columns with NaF pellets and a distillation column for the separation of volatile fluorides from UF 6 . The line has not yet been tested using irradiated fuel. Some features of the remote handling equipment of both installations are briefly described. (author)

Remote handling demonstration of ITER blanket module replacement

International Nuclear Information System (INIS)

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

2001-01-01

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

Safe handling of tritium

International Nuclear Information System (INIS)

1991-01-01

The main objective of this publication is to provide practical guidance and recommendations on operational radiation protection aspects related to the safe handling of tritium in laboratories, industrial-scale nuclear facilities such as heavy-water reactors, tritium removal plants and fission fuel reprocessing plants, and facilities for manufacturing commercial tritium-containing devices and radiochemicals. The requirements of nuclear fusion reactors are not addressed specifically, since there is as yet no tritium handling experience with them. However, much of the material covered is expected to be relevant to them as well. Annex III briefly addresses problems in the comparatively small-scale use of tritium at universities, medical research centres and similar establishments. However, the main subject of this publication is the handling of larger quantities of tritium. Operational aspects include designing for tritium safety, safe handling practice, the selection of tritium-compatible materials and equipment, exposure assessment, monitoring, contamination control and the design and use of personal protective equipment. This publication does not address the technologies involved in tritium control and cleanup of effluents, tritium removal, or immobilization and disposal of tritium wastes, nor does it address the environmental behaviour of tritium. Refs, figs and tabs

40 CFR 82.36 - Approved refrigerant handling equipment.

Science.gov (United States)

2010-07-01

... equipment. 82.36 Section 82.36 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) PROTECTION OF STRATOSPHERIC OZONE Servicing of Motor Vehicle Air Conditioners § 82.36...-12, Extraction and Recycle Equipment for Mobile Automotive Air-Conditioning Systems, and Standard of...

Preoperational checkout of the remote-handled transuranic waste handling at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1987-09-01

This plan describes the preoperational checkout for handling Remote-Handled Transuranic (RH-TRU) Wastes from their receipt at the Waste Isolation Pilot Plant (WIPP) to their emplacement underground. This plan identifies the handling operations to be performed, personnel groups responsible for executing these operations, and required equipment items. In addition, this plan describes the quality assurance that will be exercised throughout the checkout, and finally, it establishes criteria by which to measure the success of the checkout. 7 refs., 5 figs

WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

J. D. Bigbee

2000-06-21

The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status.

WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

J. D. Bigbee

2000-01-01

The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status

Handling wood shavings

Energy Technology Data Exchange (ETDEWEB)

1974-09-18

Details of bulk handling equipment suitable for collection and compressing wood waste from commercial joinery works are discussed. The Redler Bin Discharger ensures free flow of chips from storage silo discharge prior to compression into briquettes for use as fuel or processing into chipboard.

ITER L 6 equatorial maintenance duct remote handling study

International Nuclear Information System (INIS)

Millard, J.

1996-09-01

The status and conclusions of a preliminary study of equatorial maintenance duct remote handling is reported. Due to issues with the original duct design a significant portion of the study had to be refocused on equatorial duct layout studies. The study gives an overview of some of the options for design of these ducts and the impact of the design on the equipment to work in the duct. To develop a remote handling concept for creating access through the ducts the following design tasks should be performed: define the operations sequences for equatorial maintenance duct opening and closing; review the remote handling requirements for equatorial maintenance duct opening and closing; design concept for door and pipe handling equipment and to propose preliminary procedures for material handling outsides the duct. 35 figs

Handling of multiassembly sealed baskets between reactor storage and a remote handling facility

International Nuclear Information System (INIS)

Massey, J.V.; Kessler, J.H.; McSherry, A.J.

1989-06-01

The storage of multiple fuel assemblies in sealed (welded) dry storage baskets is gaining increasing use to augment at-reactor fuel storage capacity. Since this increasing use will place a significant number of such baskets on reactor sites, some initial downstream planning for their future handling scenarios for retrieving multi-assembly sealed baskets (MSBs) from onsite storage and transferring and shipping the fuel (and/or the baskets) to a federally operated remote handling facility (RHF). Numerous options or at-reactor and away-from-reactor handling were investigated. Materials handling flowsheets were developed along with conceptual designs for the equipment and tools required to handle and open the MSBs. The handling options were evaluated and compared to a reference case, fuel handling sequence (i.e., fuel assemblies are taken from the fuel pool, shipped to a receiving and handling facility and placed into interim storage). The main parameters analyzed are throughout, radiation dose burden and cost. In addition to evaluating the handling of MSBs, this work also evaluated handling consolidated fuel canisters (CFCs). In summary, the handling of MSBs and CFCs in the store, ship and bury fuel cycle was found to be feasible and, under some conditions, to offer significant benefits in terms of throughput, cost and safety. 14 refs., 20 figs., 24 tabs

Confinement facilities for handling plutonium

International Nuclear Information System (INIS)

Maraman, W.J.; McNeese, W.D.; Stafford, R.G.

1975-01-01

Plutonium handling on a multigram scale began in 1944. Early criteria, equipment, and techniques for confining contamination have been superseded by more stringent criteria and vastly improved equipment and techniques for in-process contamination control, effluent air cleaning and treatment of liquid wastes. This paper describes the evolution of equipment and practices to minimize exposure of workers and escape of contamination into work areas and into the environment. Early and current contamination controls are compared. (author)

Conceptual design report for a remotely operated cask handling system. Revision 1

International Nuclear Information System (INIS)

Yount, J.A.; Berger, J.D.

1984-09-01

Recent advances in remote handling utilizing commercial robotics are conceptually applied to lowering operator cumulative radiation exposure and increasing throughput during cask handling operations in nuclear shipping and receiving facilities. Revision 1 incorporates functional criteria for facility equipment, equipment technical outline specifications, and interface control drawings to assist Architect Engineers in the application of remote handling to waste shipping and receiving facilities. The document has also been updated to show some of the equipment used in proof-of-principle testing during fiscal year 1984. 10 references, 50 figures, 1 table

Development of remote handling techniques for the HLLW solidification plant

International Nuclear Information System (INIS)

Tosha, Yoshitsugu; Iwata, Toshio; Inada, Eiichi; Nagaki, Hiroshi; Yamamoto, Masao

1982-01-01

To develop the techniques for the remote maintenance of the equipment in a HLLW (high-level liquid waste) solidification plant, the mock-up test facility (MTF) has been designed and constructed. Before its construction, the specific mock-up equipment was manufactured and tested. The results of the test and the outline of the MTF are described. As the mock-up equipment, a denitrater-concentrator, a ceramic melter and a canister handling equipment were selected. Remote operation was performed according to the maintenance program, and the evaluation of the component was conducted on the easiness of operation, performance, and the suitability to remote handling equipment. As a result of the test, four important elements were identified; they were guides, lifting fixtures, remote handling bolts, and remote pipe connectors. Many improvements of these elements were achieved, and reflected in the design of the MTF. The MTF is a steel-framed and slate-covered building (25 mL x 20 mW x 27 mH) with five storys of test bases. It contains the following four main systems: pretreatment and off-gas treatment system, glass melting system, canister handling system and secondary waste liquid recovery system. Further development of the remote maintenance techniques is expected through the test in the MTF. (Aoki, K.)

Harvesting and handling agricultural residues for energy

Energy Technology Data Exchange (ETDEWEB)

Jenkins, B.M.; Summer, H.R.

1986-05-01

Significant progress in understanding the needs for design of agricultural residue collection and handling systems has been made but additional research is required. Recommendations are made for research to (a) integrate residue collection and handling systems into general agricultural practices through the development of multi-use equipment and total harvest systems; (b) improve methods for routine evaluation of agricultural residue resources, possibly through remote sensing and image processing; (c) analyze biomass properties to obtain detailed data relevant to engineering design and analysis; (d) evaluate long-term environmental, social, and agronomic impacts of residue collection; (e) develop improved equipment with higher capacities to reduce residue collection and handling costs, with emphasis on optimal design of complete systems including collection, transportation, processing, storage, and utilization; and (f) produce standard forms of biomass fuels or products to enhance material handling and expand biomass markets through improved reliability and automatic control of biomass conversion and other utilization systems. 118 references.

Measurement and control system for ITER remote maintenance equipment

Energy Technology Data Exchange (ETDEWEB)

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

1998-04-01

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

Measurement and control system for ITER remote maintenance equipment

International Nuclear Information System (INIS)

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

1998-01-01

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

30 CFR 75.817 - Cable handling and support systems.

Science.gov (United States)

2010-07-01

... High-Voltage Longwalls § 75.817 Cable handling and support systems. Longwall mining equipment must be provided with cable-handling and support systems that are constructed, installed and maintained to minimize... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Cable handling and support systems. 75.817...

A Perspective on Remote Handling Operations and Human Machine Interface for Remote Handling in Fusion

International Nuclear Information System (INIS)

Haist, B.; Hamilton, D.; Sanders, St.

2006-01-01

A large-scale fusion device presents many challenges to the remote handling operations team. This paper is based on unique operational experience at JET and gives a perspective on remote handling task development, logistics and resource management, as well as command, control and human-machine interface systems. Remote operations require an accurate perception of a dynamic environment, ideally providing the operators with the same unrestricted knowledge of the task scene as would be available if they were actually at the remote work location. Traditional camera based systems suffer from a limited number of viewpoints and also degrade quickly when exposed to high radiation. Virtual Reality and Augmented Reality software offer great assistance. The remote handling system required to maintain a tokamak requires a large number of different and complex pieces of equipment coordinating to perform a large array of tasks. The demands on the operator's skill in performing the tasks can escalate to a point where the efficiency and safety of operations are compromised. An operations guidance system designed to facilitate the planning, development, validation and execution of remote handling procedures is essential. Automatic planning of motion trajectories of remote handling equipment and the remote transfer of heavy loads will be routine and need to be reliable. This paper discusses the solutions developed at JET in these areas and also the trends in management and presentation of operational data as well as command, control and HMI technology development offering the potential to greatly assist remote handling in future fusion machines. (author)

Trends in remote handling device development

International Nuclear Information System (INIS)

Raimondi, T.

1991-01-01

A brief review is given of studies on layouts and methods for handling some major components requiring remote maintenance in future fusion reactors: Neutral sources and beam lines, the blanket, divertor plates, armour tiles and vacuum pumps. Comparison is made to problems encountered in JET, methods and equipment used and development work done there. Areas requiring development and research are outlined. These include topics which are the subject of papers presented here, such as dynamic studies and control of transporters, improvements to the man-machine interface and hot cell equipment. A variety of other topics where effort is needed are also mentioned: Environmental tolerance of components and equipment, TV viewing and compensation of viewing difficulties with aids such as computer graphics and image processing, safety assessment, computer aids for remote manipulation, remote cutting and welding techniques, routine in-vessel inspection methods and selection of connectors and flanges for remote handling. (orig.)

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

Getting to grips with remote handling and robotics

Energy Technology Data Exchange (ETDEWEB)

Mosey, D [Ontario Hydro, Toronto (Canada)

1984-12-01

A report on the Canadian Nuclear Society Conference on robotics and remote handling in the nuclear industry, September 1984. Remote handling in reactor operations, particularly in the Candu reactors is discussed, and the costs and benefits of use of remote handling equipment are considered. Steam generator inspection and repair is an area in which practical application of robotic technology has made a major advance.

PND fuel handling decontamination: facilities and techniques

International Nuclear Information System (INIS)

Pan, R.Y.

1996-01-01

The use of various decontamination techniques and equipment has become a critical part of Fuel Handling maintenance work at Ontario Hydro's Pickering Nuclear Division. This paper presents an overview of the set up and techniques used for decontamination in the PND Fuel Handling Maintenance Facility and the effectiveness of each. (author). 1 tab., 9 figs

Torus sector handling system

International Nuclear Information System (INIS)

Grisham, D.L.

1981-01-01

A remote handling system is proposed for moving a torus sector of the accelerator from under the cryostat to a point where it can be handled by a crane and for the reverse process for a new sector. Equipment recommendations are presented, as well as possible alignment schemes. Some general comments about future remote-handling methods and the present capabilities of existing systems will also be included. The specific task to be addressed is the removal and replacement of a 425 to 450 ton torus sector. This requires a horizontal movement of approx. 10 m from a normal operating position to a point where its further transport can be accomplished by more conventional means (crane or floor transporter). The same horizontal movement is required for reinstallation, but a positional tolerance of 2 cm is required to allow reasonable fit-up for the vacuum seal from the radial frames to the torus sector. Since the sectors are not only heavy but rather tall and narrow, the transport system must provide a safe, stable, and repeatable method fo sector movement. This limited study indicates that the LAMPF-based method of transporting torus sectors offers a proven method of moving heavy items. In addition, the present state of the art in remote equipment is adequate for FED maintenance

Modern power station practice mechanical boilers, fuel-, and ash-handling plant

CERN Document Server

Sherry, A; Cruddace, AE

2014-01-01

Modern Power Station Practice, Second Edition, Volume 2: Mechanical (Boilers, Fuel-, and Ash-Handling Plant) focuses on the design, manufacture and operation of boiler units and fuel-and ash-handling plants.This book is organized into five main topics-furnace and combustion equipment, steam and water circuits, ancillary plant and fittings, dust extraction and draught plant, and fuel-and ash-handling plant.In these topics, this text specifically discusses the influence of nature of coal on choice of firing equipment; oil-burner arrangements, ignition and control; disposition of the heating surf

PND fuel handling decontamination: facilities and techniques

Energy Technology Data Exchange (ETDEWEB)

Pan, R Y [Ontario Hydro, Toronto, ON (Canada)

1997-12-31

The use of various decontamination techniques and equipment has become a critical part of Fuel Handling maintenance work at Ontario Hydro`s Pickering Nuclear Division. This paper presents an overview of the set up and techniques used for decontamination in the PND Fuel Handling Maintenance Facility and the effectiveness of each. (author). 1 tab., 9 figs.

Spent fuel cask handling at an operating nuclear power plant

International Nuclear Information System (INIS)

Pal, A.C.

1988-01-01

The importance of spent fuel handling at operating nuclear power plants cannot be overstated. Because of its highly radioactive nature, however, spent fuel must be handled in thick, lead-lined containers or casks. Thus, all casks for spent fuel handling are heavy loads by the US Nuclear Regulatory Commission's definition, and any load-drop must be evaluated for its potential to damage safety-related equipment. Nuclear Regulatory Guide NUREG-0612 prescribes the regulatory requirements of alternative heavy-load-handling methodologies such as (a) by providing cranes that meet the requirements of NUREG-0554, which shall be called the soft path, or (b) by providing protective devices at all postulated load-drop areas to prevent any damage to safety-related equipment, which shall be called the hard path. The work reported in this paper relates to cask handling at New York Power Authority's James A. FitzPatrick (JAF) plant

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

International Nuclear Information System (INIS)

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

1998-01-01

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

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

Handling system for nuclear fuel pellet inspection

International Nuclear Information System (INIS)

Nyman, D.H.; McLemore, D.R.; Sturges, R.H.

1978-11-01

HEDL is developing automated fabrication equipment for fast reactor fuel. A major inspection operation in the process is the gaging of fuel pellets. A key element in the system has been the development of a handling system that reliably moves pellets at the rate of three per second without product damage or excessive equipment wear

The training for nuclear fuel handling at EDF

International Nuclear Information System (INIS)

Marion, J.P.

1999-01-01

The handling of fuel assemblies in a nuclear power plant presents 3 types of work: the taking delivery of fresh fuel, the refueling and the disposal of spent fuel. These operations are realized by teams made up of 3 handling operators and a supervisor. The refueling is made by 3*8-hour teams. These handling operations are important for the nuclear safety, a mishandling can damage the fuel cladding which is the first containment barrier, so a training center (CETIC) has been created. This center was founded in 1986 by EDF and Framatome, the purpose was to validate maintenance procedures, to test handling equipment and to train the teams which work on site. Various training programmes have been set up and a system of qualification degrees has been organized. The CETIC is fitted up with equipment that are full-sized mockups of real installations. Fuel assemblies don't react in a similar way to the different mechanical and neutronic stresses they undergo while they are in the core, they get deformed and the handling operations become more delicate. The mockup fuel assemblies are quite deformed to train the teams and prepare them to face any real situation. (A.C.)

TRANSPORT/HANDLING REQUESTS

CERN Multimedia

Groupe ST/HM

2002-01-01

A new EDH document entitled 'Transport/Handling Request' will be in operation as of Monday, 11th February 2002, when the corresponding icon will be accessible from the EDH desktop, together with the application instructions. This EDH form will replace the paper-format transport/handling request form for all activities involving the transport of equipment and materials. However, the paper form will still be used for all vehicle-hire requests. The introduction of the EDH transport/handling request form is accompanied by the establishment of the following time limits for the various services concerned: 24 hours for the removal of office items, 48 hours for the transport of heavy items (of up to 6 metric tons and of standard road width), 5 working days for a crane operation, extra-heavy transport operation or complete removal, 5 working days for all transport operations relating to LHC installation. ST/HM Group, Logistics Section Tel: 72672 - 72202

Beginnings of remote handling at the RAL Spallation Neutron Source

International Nuclear Information System (INIS)

Liska, D.J.; Hirst, J.

1985-01-01

Expenditure of funds and resources for remote maintenance systems traditionally are delayed until late in an accelerator's development. However, simple remote-surveillance equipment can be included early in facility planning to set the stage for future remote-handling needs and to identify appropriate personnel. Some basic equipment developed in the UK at the Spallation Neutron Source (SNS) that serves this function and that has been used to monitor beam loss during commissioning is described. A photograph of this equipment, positioned over the extractor septum magnet, is shown. This method can serve as a pattern approach to the problem of initiating remote-handling activities in other facilities

Remote handling systems for the Pride application

International Nuclear Information System (INIS)

Kim, K.; Lee, J.; Lee, H.; Kim, S.; Kim, H.

2010-10-01

In this paper is described the development of remote handling systems for use in the pyro processing technology development. Remote handling systems mainly include a BDSM (Bridge transported Dual arm Servo-Manipulator) and a simulator, all of which will be applied to the Pride (Pyro process integrated inactive demonstration facility) that is under construction at KAERI. BDMS that will traverse the length of the ceiling is designed to have two pairs of master-slave manipulators of which each pair of master-slave manipulators has a kinematic similarity and a force reflection. A simulator is also designed to provide an efficient means for simulating and verifying the conceptual design, developments, arrangements, and rehearsal of the pyro processing equipment and relevant devices from the viewpoint of remote operation and maintenance. In our research is presented activities and progress made in developing remote handling systems to be used for the remote operation and maintenance of the pyro processing equipment and relevant devices in the Pride. (Author)

Man-machine cooperation in remote handling for fusion plants

International Nuclear Information System (INIS)

Leinemann, K.

1984-01-01

Man-machine cooperation in remote handling for fusion plants comprises cooperation for design of equipment and planning of procedures using a CAD system, and cooperation during operation of the equipment with computer aided telemanipulation systems (CAT). This concept is presently being implemented for support of slave positioning, camera tracking, and camera alignment in the KfK manipulator test facility. The pilot implementation will be used to test various man-machine interface layouts, and to establish a set of basic buildings blocks for future implementations of advanced remote handling control systems. (author)

Development of nuclear fuel cycle remote handling technology

International Nuclear Information System (INIS)

Kim, K. H.; Park, B. S.; Kim, S. H.

2012-04-01

This report presents the development of remote handling systems and remote equipment for use in the pyprocessing verification at the PRIDE (PyRoprocess Integrated inactive Demonstration facility). There are four areas conducted in this work. In first area, the prototypes of an engineering-scale high-throughput decladding voloxidizer which is capable of separating spent fuel rod-cuts into hulls and powder and collecting them separately, and an automatic equipment which is capable of collecting residual powder remaining on separated hulls were developed. In second area, a servo-manipulator system was developed to operate and maintain pyroprocess equipment located at the argon cell of the PRIDE in a remote manner. A servo-manipulator with dual arm that is mounted on the lower part of a bridge transporter will be installed on the ceiling of the in-cell and can travel the length of the ceiling. In third area, a digital mock-up and a remote handling evaluation mock-up were constructed to evaluate the pyroprocess equipments from the in-cell arrangements, remote operability and maintainability viewpoint before they are installed in the PRIDE. In last area, a base technology for remote automation of integrated pyroprocess was developed. The developed decladding voloxidizer and automatic equipment will be utilized in the development of a head-end process for pyroprocessing. In addition, the developed servo-manipulator will be used for remote operation and maintenance of the pyroprocess equipments in the PRIDE. The constructed digital mock-up and remote handling evaluation mock-up will be also used to verify and improve the pyroprocess equipments for the PRIDE application. Moreover, these remote technologies described above can be directly used in the PRIDE and applied for the KAPF (Korea Advanced Pyroprocess Facility) development

Equipment for RAW handling, packaging, transport and storage from ZTS VVU KOSICE a.s

International Nuclear Information System (INIS)

Vargovcik, L.

2004-01-01

Since 1988, the company ZTS VVU KOSICE has devoted a great part of its activities to the development of equipment for RAW handling, packaging, transport and storage, mainly for application in the decommissioning of NPP A1 at Jaslovske Bohunice in Slovakia. This is a HWGCR NPP shut down following a breakdown in 1977. This incident was caused by disruption of the technological channel serving as a barrier between heavy water moderator and fuel assembly. Damage of this barrier enabled heavy water leakage into the primary circuit with partial fuel elements cladding damage and subsequent additional contamination of the primary circuit. During two consecutive years after the incident main effort was focused on activities related to personnel and environment protection, moderator draining, reactor defuelling, dry cleaning of the primary circuit, repair and maintenance of equipment. The next step was the preparation of the concept of NPP A-1 introduction into dry safe state. The order of importance of RAW liquidation was as follows: 1. Spent fuel - spent fuel assemblies from NPP A-1 were, after short cooling, stored temporarily in storage pipe containers filled at the beginning of NPP operation with ''chrompik'' (an aqueous solution of K 2 Cr 2 O 7 with concentration of 3-5%), later with ''dowtherm'' (mixture of bi-phenyl oxide and bi-phenyl). The containers were placed in a storage pond filled with water. 2. Liquid RAW - combustible (dowtherm, oils) and non-combustible (chrompik, Demi water, decontaminating solutions, sludge, sorbents, etc.) 3. Solid RAW - metallic and non-metallic For this purpose, it was necessary to build RAW processing lines, intermediate storage facilities and systems for manipulation and transport of RAW

Effects of the European Community directive on lifting and handling practice.

Science.gov (United States)

Docker, S M

1993-07-01

The new legislation on lifting and handling requires the application of ergonomic principles to manual handling operations. A written assessment is required for all unavoidable manual handling operations which involve the risk of injury to employees. Employers are now expected to provide equipment to enable staff to avoid lifting heavy loads.

Superphenix 1 primary handling system fabrication and testing

International Nuclear Information System (INIS)

Branchu, J.; Ebbinghaus, K.; Gigarel, C.

1985-01-01

Primary handling covers the operations performed for spent fuel removal, new fuel insertion, and the insodium storage outside the new or spent fuel vessel. This equipment typifies many of the difficulties encountered with the project as a whole: fabrication coordination when several countries are involved and design and construction of very large, relatively complex components. Detailed design studies were mainly influenced by thermal and seismic requirements, as applicable to sodium-immersed structures. Where possible, well-tried mechanical solutions were used, but widely differing techniques were involved, ranging from the high precision fabrication of structures and mechanisms comprising numerous component parts, implying complex machining operations. No particular problems were encountered during the sodium testing of the primary handling equipment. Trends for the 1500-MW (electric) breeder include investigation of the advisability of fuel storage in the core lattice and the possibility of handling system simplification

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…

SP-100 reactor disassembly remote handling test program

International Nuclear Information System (INIS)

Wilson, C.E.; Potter, J.D.; Maiden, G.E.; Vader, D.P.

1991-01-01

This paper is presented as an overview of the remote handling equipment validation testing, which will be conducted before installation and use in the ground engineering test facility. This equipment will be used to defuel the SP-100 reactor core after removing it from the Test Assembly following nuclear testing. A series of full scale mock-up operational tests will be conducted at a Hanford Site facility to verify equipment design, operation, and capabilities

Robotics and remote handling in the nuclear industry

Energy Technology Data Exchange (ETDEWEB)

1984-01-01

This book presents the papers given at a conference on the use of remote handling equipment in nuclear facilities. Topics considered at the conference included dose reduction, artificial intelligence in nuclear plant maintenance, robotic welding, uncertainty covariances, reactor operation and inspection, reactor maintenance and repair, uranium mining, fuel fabrication, reactor component manufacture, irradiated fuel and radioactive waste management, and radioisotope handling.

Transfer Area Mechanical Handling Calculation

International Nuclear Information System (INIS)

Dianda, B.

2004-01-01

This calculation is intended to support the License Application (LA) submittal of December 2004, in accordance with the directive given by DOE correspondence received on the 27th of January 2004 entitled: ''Authorization for Bechtel SAX Company L.L. C. to Include a Bare Fuel Handling Facility and Increased Aging Capacity in the License Application, Contract Number DE-AC--28-01R W12101'' (Arthur, W.J., I11 2004). This correspondence was appended by further Correspondence received on the 19th of February 2004 entitled: ''Technical Direction to Bechtel SAIC Company L.L. C. for Surface Facility Improvements, Contract Number DE-AC--28-OIRW12101; TDL No. 04-024'' (BSC 2004a). These documents give the authorization for a Fuel Handling Facility to be included in the baseline. The purpose of this calculation is to establish preliminary bounding equipment envelopes and weights for the Fuel Handling Facility (FHF) transfer areas equipment. This calculation provides preliminary information only to support development of facility layouts and preliminary load calculations. The limitations of this preliminary calculation lie within the assumptions of section 5 , as this calculation is part of an evolutionary design process. It is intended that this calculation is superseded as the design advances to reflect information necessary to support License Application. The design choices outlined within this calculation represent a demonstration of feasibility and may or may not be included in the completed design. This calculation provides preliminary weight, dimensional envelope, and equipment position in building for the purposes of defining interface variables. This calculation identifies and sizes major equipment and assemblies that dictate overall equipment dimensions and facility interfaces. Sizing of components is based on the selection of commercially available products, where applicable. This is not a specific recommendation for the future use of these components or their

ITER - TVPS remote handling critical design issues

International Nuclear Information System (INIS)

1990-09-01

This report describes critical design issues concerning remote maintenance of the ITER Torus Vacuum Pumping System (TVPS). The key issues under investigation are the regeneration/isolation valve seal and seal mechanism replacement; impact of inert gas operation; impact of remote handling (RH) on the building configuration and RH equipment requirements. Seal exchange concepts are developed and their impact on the valve design identified. Concerns regarding the design and operation of RH equipment in an inert gas atmosphere are also explored. The report compares preliminary RH equipment options, pumping equipment maintenance frequency and their impact on the building design, and makes recommendations where a conflict exists between pumping equipment and the building layout. (51 figs., 11 refs.)

Remote handling for an ISIS target change

International Nuclear Information System (INIS)

Broome, T.A.; Holding, M.

1989-01-01

During 1987 two ISIS targets were changed. This document describes the main features of the remote handling aspects of the work. All the work has to be carried out using remote handling techniques. The radiation level measured on the surface of the reflector when the second target had been removed was about 800 mGy/h demonstrating that hands on operations on any part of the target reflector moderator assembly is not practical. The target changes were the first large scale operations in the Target Station Remote Handling Cell and a great deal was learned about both equipment and working practices. Some general principles emerged which are applicable to other active handling tasks on facilities like ISIS and these are discussed below. 8 figs

EBR-II fuel handling console digital upgrade

International Nuclear Information System (INIS)

Peters, G.G.; Wiege, D.D.; Christensen, L.J.

1995-01-01

The main fuel handling console and control system at the Experimental Breeder Reactor II (EBR-II) are being upgraded to a computerized system using high-end workstations for the operator interface and a programmable logic controller (PLC) for the control system. Two-dimensional (2D) and three-dimensional (3D) computer graphics will be provided for the operator which will show the relative position of under-sodium fuel handling equipment. This equipment is operated remotely with no means of directly viewing the transfer. This paper describes various aspects of the modification including reasons for the upgrade, capabilities the new system provides over the old control system, philosophies and rationale behind the new design, testing and simulation work, diagnostic features, and the advanced graphics techniques used to display information to the operator

Potential applications of advanced remote handling and maintenance technology to future waste handling facilities

International Nuclear Information System (INIS)

Kring, C.T.; Herndon, J.N.; Meacham, S.A.

1987-01-01

The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) has been advancing the technology in remote handling and remote maintenance of in-cell systems planned for future US nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor are directly applicable to the in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The ORNL developments are based on the application of teleoperated force-reflecting servomanipulators controlled by an operator completely removed from the hazardous environment. These developments address the nonrepetitive nature of remote maintenance in the unstructured environments encountered in a waste handling facility. Employing technological advancements in dexterous manipulators, as well as basic design guidelines that have been developed for remotely maintained equipment and processes, can increase operation and maintenance system capabilities, thereby allowing the attainment of two Federal Waste Management System major objectives: decreasing plant personnel radiation exposure and increasing plant availability by decreasing the mean-time-to-repair in-cell maintenance and process equipment

Potential applications of advanced remote handling and maintenance technology to future waste handling facilities

International Nuclear Information System (INIS)

Kring, C.T.; Herndon, J.N.; Meacham, S.A.

1987-01-01

The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) has been advancing the technology in remote handling and remote maintenance of in-cell systems planned for future U.S. nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor are directly applicable to the in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The ORNL developments are based on the application of teleoperated force-reflecting servomanipulators controlled by an operator completely removed from the hazardous environment. These developments address the nonrepetitive nature of remote maintenance in the unstructured environments encountered in a waste handling facility. Employing technological advancements in dexterous manipulators, as well as basic design guidelines that have been developed for remotely maintained equipment and processes, can increase operation and maintenance system capabilities, thereby allowing the attainment of two Federal Waste Management System major objectives: decreasing plant personnel radiation exposure and increasing plant availability by decreasing the mean-time-to-repair in-cell maintenance and process equipment

Musculoskeletal injuries resulting from patient handling tasks among hospital workers.

Science.gov (United States)

Pompeii, Lisa A; Lipscomb, Hester J; Schoenfisch, Ashley L; Dement, John M

2009-07-01

The purpose of this study was to evaluate musculoskeletal injuries and disorders resulting from patient handling prior to the implementation of a "minimal manual lift" policy at a large tertiary care medical center. We sought to define the circumstances surrounding patient handling injuries and to identify potential preventive measures. Human resources data were used to define the cohort and their time at work. Workers' compensation records (1997-2003) were utilized to identify work-related musculoskeletal claims, while the workers' description of injury was used to identify those that resulted from patient handling. Adjusted rate ratios were generated using Poisson regression. One-third (n = 876) of all musculoskeletal injuries resulted from patient handling activities. Most (83%) of the injury burden was incurred by inpatient nurses, nurses' aides and radiology technicians, while injury rates were highest for nurses' aides (8.8/100 full-time equivalent, FTEs) and smaller workgroups including emergency medical technicians (10.3/100 FTEs), patient transporters (4.3/100 FTEs), operating room technicians (3.1/100 FTEs), and morgue technicians (2.2/100 FTEs). Forty percent of injuries due to lifting/transferring patients may have been prevented through the use of mechanical lift equipment, while 32% of injuries resulting from repositioning/turning patients, pulling patients up in bed, or catching falling patients may not have been prevented by the use of lift equipment. The use of mechanical lift equipment could significantly reduce the risk of some patient handling injuries but additional interventions need to be considered that address other patient handling tasks. Smaller high-risk workgroups should not be neglected in prevention efforts.

Fire and earthquake counter measures in radiation handling facilities

International Nuclear Information System (INIS)

1985-01-01

'Fire countermeasures in radiation handling facilities' published in 1961 is still widely utilized as a valuable guideline for those handling radiation through the revision in 1972. However, science and technology rapidly advanced, and the relevant laws were revised after the publication, and many points which do not conform to the present state have become to be found. Therefore, it was decided to rewrite this book, and the new book has been completed. The title was changed to 'Fire and earthquake countermeasures in radiation handling facilities', and the countermeasures to earthquakes were added. Moreover, consideration was given so that the book is sufficiently useful also for those concerned with fire fighting, not only for those handling radiation. In this book, the way of thinking about the countermeasures against fires and earthquakes, the countermeasures in normal state and when a fire or an earthquake occurred, the countermeasures when the warning declaration has been announced, and the data on fires, earthquakes, the risk of radioisotopes, fire fighting equipment, the earthquake counter measures for equipment, protectors and radiation measuring instruments, first aid, the example of emergency system in radiation handling facilities, the activities of fire fighters, the example of accidents and so on are described. (Kako, I.)

Handling of UF6 in U.S. gaseous diffusion plants

International Nuclear Information System (INIS)

Legeay, A.J.

1978-01-01

A comprehensive systems analysis of UF 6 handling has been made in the three U.S. gaseous diffusion plants and has resulted in a significant impact on the equipment design and the operating procedures of these facilities. The equipment, facilities, and industrial practices in UF 6 handling operations as they existed in the early 1970's are reviewed with particular emphasis placed on the changes which have been implemented. The changes were applied to the systems and operating methods which evolved from the design, startup, and operation of the Oak Ridge Gaseous Diffusion Plant in 1945

Handling of disused radioactive materials in Ecuador

International Nuclear Information System (INIS)

Benitez, Manuel

1999-10-01

This paper describes the handling of disused radioactive sources. It also shows graphic information of medical and industrial equipment containing radioactive sources. This information was prepared as part of a training course on radioactive wastes. (The author)

PND fuel handling decontamination program: specialized techniques and results

International Nuclear Information System (INIS)

Pan, R.; Hobbs, K.; Minnis, M.; Graham, K.

1995-01-01

The use of various decontamination techniques and equipment has become a critical part of Fuel Handling maintenance work at the Pickering Nuclear Station, an eight unit CANDU station located about 30 km east of Toronto. This paper presents an overview of the set up and techniques used for cleaning in the PND Fuel Handling Maintenance Facility, and the results achieved. (author)

SRV-automatic handling device

International Nuclear Information System (INIS)

Yamada, Koji

1987-01-01

Automatic handling device for the steam relief valves (SRV's) is developed in order to achieve a decrease in exposure of workers, increase in availability factor, improvement in reliability, improvement in safety of operation, and labor saving. A survey is made during a periodical inspection to examine the actual SVR handling operation. An SRV automatic handling device consists of four components: conveyor, armed conveyor, lifting machine, and control/monitoring system. The conveyor is so designed that the existing I-rail installed in the containment vessel can be used without any modification. This is employed for conveying an SRV along the rail. The armed conveyor, designed for a box rail, is used for an SRV installed away from the rail. By using the lifting machine, an SRV installed away from the I-rail is brought to a spot just below the rail so that the SRV can be transferred by the conveyor. The control/monitoring system consists of a control computer, operation panel, TV monitor and annunciator. The SRV handling device is operated by remote control from a control room. A trial equipment is constructed and performance/function testing is carried out using actual SRV's. As a result, is it shown that the SRV handling device requires only two operators to serve satisfactorily. The required time for removal and replacement of one SRV is about 10 minutes. (Nogami, K.)

Equipment improvements for performance enhancement

International Nuclear Information System (INIS)

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

1994-01-01

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

How to handle and care for bulbs in ophthalmic equipment

Directory of Open Access Journals (Sweden)

Ismael Cordero

2013-08-01

Full Text Available Many devices used in eye care rely on light bulbs or lamps for their operation. All light bulbs have a limited lifespan and when the bulb fails the device becomes unusable. Therefore, knowing how to handle, how to inspect and how to replace bulbs is important. Just as important is keeping spare bulbs to hand!

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

Energy Technology Data Exchange (ETDEWEB)

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

1982-01-01

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

Proposed master-slave and automated remote handling system for high-temperature gas-cooled reactor fuel refabrication

International Nuclear Information System (INIS)

Grundmann, J.G.

1974-01-01

The Oak Ridge National Laboratory's Thorium-Uranium Recycle Facility (TURF) will be used to develop High-Temperature Gas-Cooled Reactor (HTGR) fuel recycle technology which can be applied to future HTGR commercial fuel recycling plants. To achieve recycle capabilities it is necessary to develop an effective material handling system to remotely transport equipment and materials and to perform maintenance tasks within a hot cell facility. The TURF facility includes hot cells which contain remote material handling equipment. To extend the capabilities of this equipment, the development of a master-slave manipulator and a 3D-TV system is necessary. Additional work entails the development of computer controls to provide: automatic execution of tasks, automatic traverse of material handling equipment, automatic 3D-TV camera sighting, and computer monitoring of in-cell equipment positions to prevent accidental collisions. A prototype system which will be used in the development of the above capabilities is presented. (U.S.)

Techniques for remote maintenance of in-cell material-handling system in the HFEF/N main cell

International Nuclear Information System (INIS)

Tobias, D.A.; Frickey, C.A.

1975-01-01

Operations in the main cell of HFEF/N have required development of remote handling equipment and unique techniques for maintaining the in-cell material-handling system. Specially designed equipment is used to remove a disabled crane or electromechanical manipulator bridge from its support rails and place it on floor stands for repair or maintenance. Support areas for the main cell, such as the spray chamber and hot repair area, provide essential decontamination, repair, and staging areas for the in-cell material-handling-system equipment and tools. A combined engineering and technical effort in upgrading existing master-slave manipulators has definitely reduced the requirements for their maintenance. The cell is primarily for postirradiation examination of LMFBR materials and fuel elements

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

CubeSat Handling of Multisystem Precision Time Transfer (CHOMPTT)

Data.gov (United States)

National Aeronautics and Space Administration — The CubeSat Handling of Multisystem Precision Time Transfer (CHOMPTT) mission is a precision timing satellite equipped with atomic clocks synchronized with a ground...

Construction and commissioning of workrooms for handling of unsealed radioactive materials

International Nuclear Information System (INIS)

Weinhold, G.; Jost, E.; Koenig, W.

1976-03-01

The requirements prescribed for planning, design and construction of type II and III workrooms for handling of unsealed sources are outlined. The 'Guide Concerning Construction and Equipment of Rooms for Handling of Radioactive Materials' is explained and supplemented in part. Furthermore, problems of radiation protection organization and measuring techniques are discussed. (author)

Manual on Safety Aspects of the Design and Equipment of Hot Laboratories

International Nuclear Information System (INIS)

1969-01-01

With the development of atomic energy application and research, hot laboratories are now being constructed in a number of countries. The present publication describes and discusses experience in several countries in designing equipment for these laboratories. The safe handling of highly radioactive substances is the main purpose of hot laboratory design and equipment. The manual aims at helping those persons, particularly in the developing countries, who plan to design and construct a new hot laboratory or modify an existing one. It does not deal in great detail with the engineering design of protective and handling equipment; these matters can be found in the comprehensive list of references. The manual itself covers only basic ideas and different approaches in the design of laboratory building, hot cells, shielded and glove boxes, fume cupboards, and handling and viewing equipment. Systems for transferring materials and main services are also discussed.

Considerations for evaluation and selection of solid waste handling apron conveyors

Energy Technology Data Exchange (ETDEWEB)

Lisiecki, H.G.

1976-11-01

Criteria to be used in evaluating and selecting conveyer equipment for facilities handling solid wastes, such as solid waste resource recovery facilities, are discussed. Types of conveyer pan design and chain mechanisms are described. It is concluded that the conveyer purchaser must be knowledgeable about the equipment available, the specific use of equipment, its performance specifications, and the overall maintenance and operating costs. (LCL)

7 CFR 1436.6 - Eligible storage or handling equipment.

Science.gov (United States)

2010-01-01

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

Hot laboratory in Saclay. Equipment and radio-metallurgy technique of the hot lab in Saclay. Description of hot cell for handling of plutonium salts. Installation of an hot cell

International Nuclear Information System (INIS)

Bazire, R.; Blin, J.; Cherel, G.; Duvaux, Y.; Cherel, G.; Mustelier, J.P.; Bussy, P.; Gondal, G.; Bloch, J.; Faugeras, P.; Raggenbass, A.; Raggenbass, P.; Fufresne, J.

1959-01-01

Describes the conception and installation of the hot laboratory in Saclay (CEA, France). The construction ended in 1958. The main aim of this laboratory is to examine fuel rods of EL2 and EL3 as well as nuclear fuel studies. It is placed in between both reactors. In a first part, the functioning and specifications of the hot lab are given. The different hot cells are described with details of the ventilation and filtration system as well as the waste material and effluents disposal. The different safety measures are explained: description of the radiation protection, decontamination room and personnel monitoring. The remote handling equipment is composed of cutting and welding machine controlled with manipulators. Periscopes are used for sight control of the operation. In a second part, it describes the equipment of the hot lab. The unit for an accurate measurement of the density of irradiated uranium is equipped with an high precision balance and a thermostat. The equipment used for the working of irradiated uranium is described and the time length of each operation is given. There is also an installation for metallographic studies which is equipped with a manipulation bench for polishing and cleaning surfaces and a metallographic microscope. X-ray examination of uranium pellets will also be made and results will be compared with those of metallography. The last part describes the hot cells used for the manipulation of plutonium salts. The plutonium comes from the reprocessing plant and arrived as a nitric solution. Thus these cells are used to study the preparation of plutonium fluorides from nitric solution. The successive operations needed are explained: filtration, decontamination and extraction with TBP, purification on ion exchangers and finally formation of the plutonium fluorides. Particular attention has been given to the description of the specifications of the different gloveboxes and remote handling equipment used in the different reaction steps and

On-site equipment and materials against CBRNE terrorism

International Nuclear Information System (INIS)

Yamamoto, Soichiro; Tokita, Kenichi

2016-01-01

There is no almighty field service equipment that can handle by itself all CBRNE (Chemical, Biological, Radiological, Nuclear, Explosive) terrorism. Since there is merit and demerit for each of equipment, operation methods and linkage of material/equipment based on detection principle are indispensable. This paper explained the principle and operation method of detection equipment, operation using multiple material/equipment, and system construction to facilitate cooperation with related ministries and agencies. There are six examples as typical material/equipment and detection principle for handling CBRNE as shown below: (1) ion mobility spectrometer, (2) infrared spectroscopy, (3) Raman scattering spectroscopy, (4) gas chromatographic mass spectrometry, (5) fluorescent reactive dye classification method, and (6) antigen antibody reaction method. This paper shows a flowchart that can measure within the duration of a respirator while wearing Level A protective clothing (about 15 to 20 min) by the combination of detector/analyzer based on these methods. The authors developed an information system that allows prompt information exchange between the on-site administrative agencies, research institutes, and other related organizations via network, in the case when substances etc. could not be specified in the above flowchart. (A.O.)

Coal handling equipment - making the right choices in a competitive market

Energy Technology Data Exchange (ETDEWEB)

Dodds-Ely, L.

2009-02-15

Liebherr is a dominant crane supplier for coal-handling in Kalimantan, the main coal producing area of Indonesia. Since the delivery of the first heavy-duty, high-performance CBG from-rope grab cranes to Pulau Laut Coal Terminal and Balikpapan Coal Terminal ten years ago the number of fixed cargo cranes (FCC) operating on jetties and quaysides alone in Kalimantan has risen to no fewer than ten further orders in the pipeline, confirming the high quality and reliability of Liebherr's producers and the company's excellent reputation in the coal-handling business. The Liebherr CBG heavy-duty high-performance four-rope grab cranes are specially designed for continuous operation and ensure rapid and efficient turnover of all types of bulk cargo. With maximum lifting capacities of 30 tonnes at an outreach of 28 metres, each of the Balikpapan cranes achievers an hourly turnover of approximately ,000 tonnes. The article describes the key characteristics of the crane and its additional optimal features. 2 photos.

Application of advanced remote systems technology to future waste handling facilities

International Nuclear Information System (INIS)

Kring, C.T.; Meacham, S.A.

1987-01-01

The Consolidated Fuel Reprocessing Program (CFRP) at Oak Ridge National Laboratory (ORNL) has been advancing the technology of remote handling and remote maintenance for in-cell systems planned for future nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor is directly applicable to the proposed in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The application of teleoperated, force-reflecting servomanipulators with television viewing could be a major step forward in waste handling facility design. Primary emphasis in the current program is the operation of a prototype remote handling and maintenance system, the advanced servomanipulator (ASM), which specifically addresses the requirements of fuel reprocessing and waste handling with emphasis on force reflection, remote maintainability, reliability, radiation tolerance, and corrosion resistance. Concurrent with the evolution of dexterous manipulators, concepts have also been developed that provide guidance for standardization of the design of the remotely operated and maintained equipment, the interface between the maintenance tools and the equipment, and the interface between the in-cell components and the facility

Remote handling in reprocessing plants

International Nuclear Information System (INIS)

Streiff, G.

1984-01-01

Remote control will be the rule for maintenance in hot cells of future spent fuel reprocessing plants because of the radioactivity level. New handling equipments will be developed and intervention principles defined. Existing materials, recommendations for use and new manipulators are found in the PMDS' documentation. It is also a help in the choice and use of intervention means and a guide for the user [fr

Process & Quality procedures for transport & handling activities

CERN Document Server

Böttcher, O

2002-01-01

To respect the detailed and complex planning of the LHC installation project it is essential to reduce possible faults in every technical service that can cause delays in the schedule. In order to ensure proper execution of transport and handling activities it is important to get detailed information from the clients as early as possible in order to do the planning and the organisation of the required resources. One procedure that requires greater focus in the future is the preparation of the resources. The goal is to prevent equipment breakdowns and accidents while executing transport and handling activities. In the LEP dismantling project multiple breakdowns of important cranes caused serious problems in the project schedule. For the LHC installation project similar incidents in the reliability of the equipment cannot be accepted because of the high sensitivity of the whole schedule. This paper shall outline the efforts and methods that are put in place in order to meet the LHC installation requirements.

Bacteriological research for the contamination of equipment in chest radiography

International Nuclear Information System (INIS)

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

2015-01-01

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

Bacteriological research for the contamination of equipment in chest radiography

Energy Technology Data Exchange (ETDEWEB)

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

2015-12-15

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

18 years experience on UF{sub 6} handling at Japanese nuclear fuel manufacturer

Energy Technology Data Exchange (ETDEWEB)

Fujinaga, H.; Yamazaki, N.; Takebe, N. [Japan Nucelar Fuel Conversion Co., Ltd., Ibaraki (Japan)

1991-12-31

In the spring of 1991, a leading nuclear fuel manufacturing company in Japan, celebrated its 18th anniversary. Since 1973, the company has produced over 5000 metric ton of ceramic grade UO{sub 2} powder to supply to Japanese fabricators, without major accident/incident and especially with a successful safety record on UF{sub 6} handling. The company`s 18 years experience on nuclear fuel manufacturing reveals that key factors for the safe handling of UF{sub 6} are (1) installing adequate facilities, equipped with safety devices, (2) providing UF{sub 6} handling manuals and executing them strictly, and (3) repeating on and off the job training for operators. In this paper, equipment and the operation mode for UF{sub 6} processing at their facility are discussed.

Lack of genotoxicity in medical oncology nurses handling antineoplastic drugs: effect of work environment and protective equipment.

Science.gov (United States)

Gulten, Tuna; Evke, Elif; Ercan, Ilker; Evrensel, Turkkan; Kurt, Ender; Manavoglu, Osman

2011-01-01

In this study we aimed to investigate the genotoxic effects of antineoplastic agents in occupationally exposed oncology nurses. Genotoxic effects mean the disruptive effects in the integrity of DNA and they are associated with cancer development. Biomonitoring of health care workers handling antineoplastic agents is helpful for the evaluation of exposure to cytostatics. The study included an exposed and two control groups. The exposed group (n=9) was comprised of oncology nurses. The first (n=9) and second (n=10) control groups were comprised of subjects who did not come into contact with antineoplastic drugs working respectively in the same department with oncology nurses and in different departments. Genotoxicity evaluation was performed using SCE analysis. After applying culture, harvest and chromosome staining procedures, a total of 25 metaphases were analyzed per person. Kruskal Wallis test was used to perform statistical analysis. A statistically significant difference of sister chromatid exchange frequencies was not observed between the exposed and control groups. Lack of genotoxicity in medical oncology nurses might be due to good working conditions with high standards of technical equipment and improved personal protection.

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)

Conceptual design report for a remotely operated cask handling system

International Nuclear Information System (INIS)

Yount, J.A.; Berger, J.D.

Recent advances in remote handling utilizing commercial robotics are conceptually applied to the problem of lowering operator cumulative dose and increasing throughput during cask handling operations in proposed nuclear waste container shipping and receiving facilities. The functional criteria for each subsystem are defined, and candidate systems are described. The report also contains a generic description of a waste receiving facility, to show possible deployment configurations for the equipment

Progress in the design of the ITER Neutral Beam cell Remote Handling System

Energy Technology Data Exchange (ETDEWEB)

Shuff, R., E-mail: robin.shuff@f4e.europa.eu [Fusion for Energy, Torres Diagonal Litoral B3, Josep Pla 2, 08019 Barcelona (Spain); Van Uffelen, M.; Damiani, C. [Fusion for Energy, Torres Diagonal Litoral B3, Josep Pla 2, 08019 Barcelona (Spain); Tesini, A.; Choi, C.-H. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul-lez-Durance (France); Meek, R. [Oxford Technologies Limited, 7 Nuffield Way, Abingdon OX14 1RL (United Kingdom)

2014-10-15

The ITER Neutral Beam cell will include a suite of Remote Handling equipment for maintenance tasks. This paper summarises the current status and recent developments in the design of the ITER Neutral Beam Remote Handling System. Its concept design was successfully completed in July 2012 by CCFE in the frame of a grant agreement with F4E, in collaboration with the ITER Organisation, including major systems like monorail crane, Beam Line Transporter, beam source equipment, upper port and neutron shield equipment and associated tooling. Research and development activities are now underway on the monorail crane radiation hardened on-board control system and first of a kind remote pipe and lip seal maintenance tooling for the beam line vessel, reported in this paper.

Progress in the design of the ITER Neutral Beam cell Remote Handling System

International Nuclear Information System (INIS)

Shuff, R.; Van Uffelen, M.; Damiani, C.; Tesini, A.; Choi, C.-H.; Meek, R.

2014-01-01

The ITER Neutral Beam cell will include a suite of Remote Handling equipment for maintenance tasks. This paper summarises the current status and recent developments in the design of the ITER Neutral Beam Remote Handling System. Its concept design was successfully completed in July 2012 by CCFE in the frame of a grant agreement with F4E, in collaboration with the ITER Organisation, including major systems like monorail crane, Beam Line Transporter, beam source equipment, upper port and neutron shield equipment and associated tooling. Research and development activities are now underway on the monorail crane radiation hardened on-board control system and first of a kind remote pipe and lip seal maintenance tooling for the beam line vessel, reported in this paper

DISPOSAL CONTAINER HANDLING SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

E. F. Loros

2000-06-30

. This includes the primary hot cell bounded by the receiving area and WP transport exit air locks; and isolation doors at ATS, CTS, and Waste Package Remediation. The hot cell includes areas for welding, various staging, tilting, and WP transporter loading. There are associated operating galleries and equipment maintenance areas outside the hot cell. These areas operate concurrently to accommodate the DC/WP throughput rates and support system maintenance. The new DC preparation area is located in an unshielded structure. The handling equipment includes DC/WP bridge cranes, tilting stations, and horizontal transfer carts. The welding area includes DC/WP welders and staging stations. Welding operations are supported by remotely operated equipment including a bridge crane and hoists, welder jib cranes, welding turntables, and manipulators. WP transfer includes a transfer/decontamination and transporter load area. The transfer operations are supported by a remotely operated horizontal lifting system, decontamination system, decontamination and inspection manipulator, and a WP horizontal transfer cart. All handling operations are supported by a suite of fixtures including collars, yokes, lift beams, and lid attachments. Remote equipment is designed to facilitate decontamination and maintenance. Interchangeable components are provided where appropriate. Set-aside areas are included, as required, for fixtures and tooling to support off-normal and recovery operations. Semi-automatic, manual, and backup control methods support normal, maintenance, and recovery operations. The system interfaces with the ATS and CTS to provide empty and receive loaded DCs. The Waste Emplacement/Retrieval System interfaces are for loading/unloading WPs on/from the transporter. The system also interfaces with the Waste Package Remediation System for DC/WP repair. The system is housed, shielded, supported, and has ventilation boundaries by the Waste Handling Building (WHB). The system is ventilated

Application of Minicomputers and Microcomputers to Information Handling.

Science.gov (United States)

Griffiths, Jose-Marie

This study assesses the application of both minicomputers and microcomputers to information-handling procedures and makes recommendations for automating such procedures, particularly in developing nations. The report is based on a survey of existing uses of small computing equipment in libraries, archives, and information centers which was…

Radioactivity, shielding, radiation damage, and remote handling

International Nuclear Information System (INIS)

Wilson, M.T.

1975-01-01

Proton beams of a few hundred million electron volts of energy are capable of inducing hundreds of curies of activity per microampere of beam intensity into the materials they intercept. This adds a new dimension to the parameters that must be considered when designing and operating a high-intensity accelerator facility. Large investments must be made in shielding. The shielding itself may become activated and require special considerations as to its composition, location, and method of handling. Equipment must be designed to withstand large radiation dosages. Items such as vacuum seals, water tubing, and electrical insulation must be fabricated from radiation-resistant materials. Methods of maintaining and replacing equipment are required that limit the radiation dosages to workers.The high-intensity facilities of LAMPF, SIN, and TRIUMF and the high-energy facility of FERMILAB have each evolved a philosophy of radiation handling that matches their particular machine and physical plant layouts. Special tooling, commercial manipulator systems, remote viewing, and other techniques of the hot cell and fission reactor realms are finding application within accelerator facilities. (U.S.)

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

Experimental equipment, ch. 6

International Nuclear Information System (INIS)

Boomstra, F.; Hoogenboom, A.M.; Prins, C.M.; Strasters, B.A.; Vermeer, A.; Wit, P. de; Zwol, N.A. van.

1977-01-01

The experimental equipment in use at Utrecht university is discussed. Attention is paid to the tandem Van de Graaff accelerator and the 4MV and 1MV accelerators. The detection systems for gamma-ray spectroscopy are reviewed with emphasis on the compton-suppression spectrometer. The data-handling system used for experiments with the tandem is also briefly discussed

The use of virtual reality for preparation and implementation of JET remote handling operations

International Nuclear Information System (INIS)

Sanders, S.; Rolfe, A.C.

2003-01-01

The use of real time 3-D computer graphic models for preparation and support of remote handling operations on JET has been in use since the mid 1980s. A complete review has been undertaken of the functional requirements and benefits of VR for remote handling and a subsequent market survey of the present state-of-the-art of VR systems has resulted in the implementation of a new system for JET. The VR system is used in two discrete modes: in on-line mode the remote handling equipment Electro-mechanical hardware is connected to the VR system and provides input for the VR system to update a real time 3-D display of the equipment inside the torus. This mode supplements the video camera system and assists with camera control and warnings of impending or potential collisions. In Off-line mode the operator manipulates the VR system model with no connections to the remote handling equipment. This mode is used during preparation of RH operational strategies, checking of operational feasibility and operations procedures. Various VR systems were evaluated against a detailed technical specification that covered visualisation function and performance, user interface design and base model input/creation capabilities. The cheapest of those systems that satisfied the technical requirements was selected

Modelling dust liberation in bulk material handling systems

NARCIS (Netherlands)

Derakhshani, S.M.

2016-01-01

Dust has negative effects on the environmental conditions, human health as well as industrial equipment and processes. In this thesis, the transfer point of a belt conveyor as a bulk material handling system with a very high potential place for dust liberation is studied. This study is conducted

Head-end reprocessing equipment remote maintenance demonstration

International Nuclear Information System (INIS)

Evans, J.H.; Metz, C.F. III.

1989-01-01

Prototype equipment for reprocessing breeder reactor nuclear fuel was installed in the Remote Operation and Maintenance Demonstration (ROMD) area of the Consolidated Fuel Reprocessing Program (CFRP) facility at the Oak Ridge National Laboratory (ORNL) in order to evaluate the design of this equipment in a cold mock-up of a remotely maintained hot cell. This equipment included the Remote Disassembly System (RDS) and the Remote Shear System (RSS). These systems were disassembled and reassembled remotely by using the extensive remote handling systems that are installed in this simulated hot-cell environment. 5 refs., 5 figs

Innovations in Equipment Erection of Prototype Fast Breeder Reactor (PFBR)

International Nuclear Information System (INIS)

Sreekanth, S.; Kumar, Prabhat

2013-01-01

• PFBR equipment erection was a challenging task where thin walled vessels had transported and handled with utmost precautions to avoid redial forces on the vessels, which could buckle the vessels. • There was a real challenge in lifting the vessels without swing, placement of large size and heavy vessel at a distance of 57 meters where the crane operator has no line of sight to equipment's being erected. • Lot of care had been taken during lifting, handling and erection of thin walled ODC with innovative methods used for lifting fixtures, guiding arrangements, alignment fixtures and achieved the stringent erection tolerances

Advanced robotic remote handling system for reactor dismantlement

International Nuclear Information System (INIS)

Shinohara, Yoshikuni; Usui, Hozumi; Fujii, Yoshio

1991-01-01

An advanced robotic remote handling system equipped with a multi-functional amphibious manipulator has been developed and used to dismantle a portion of radioactive reactor internals of an experimental boiling water reactor in the program of reactor decommissioning technology development carried out by the Japan Atomic Energy Research Institute. (author)

Study over problems related to fuel and ash handling systems; Probleminventering braensle- och askhantering

Energy Technology Data Exchange (ETDEWEB)

Njurell, Rolf; Wikman, Karin [AaF-Energi och Miljoe AB, Stockhom (Sweden)

2003-10-01

There have been a lot of problems related to fuel and ash handling systems since the combustion of different types of biofuels started in the 70s. Many measures have been taken to solve some of the problems, but others have become part of the daily work. The purpose of this study has been to do a compilation of the fuel and ash handling problems that exist at different types of heat and power plants. The study over problems related to fuel and ash handling systems has been carried out through a questionnaire via the Internet. Directors at about 150 energy production plants were contacted by phone or e-mail in the beginning of the project and asked to participate in the study. 72 of these plants accepted to fill in the questionnaire. After several reminders by e-mails and phone calls there were in the end 32 plants that completed the form. Together they reported about 25 problems related to fuel handling and 27 problems related to ash handling. In general each of the plants reported one problem of each kind. Even if the material from the questionnaire is not enough to make statistical analysis a few conclusions can be made about the most common problems, the cause of the problems and where they appear. Fuel handling problems that occur at several plants are stoppage in the conveying equipment, bridging in the boiler silo or the tipping bunker and problems with the sieve for separation. The distribution of the fuel handling problems is almost equal for all equipment parts (receiving, separation, transport etc.). For the ash handling systems problems with transport of dry bottom ash dominate, followed by and the moistening of fly ash and transport of wet bottom ash. Most of the problems related to fuel handling are caused by the fuel quality. For example several plants have reported that bark is a fuel that is hard to handle. Nevertheless the quality for a specific fuel is not always bad when it is delivered to the plant but the fuel quality might change during

Development of spent fuel remote handling technology

International Nuclear Information System (INIS)

Yoon, J. S.; Hong, H. D.; Kim, S. H.

2004-02-01

In this research, the remote handling technology is developed for the advanced spent fuel conditioning process which gives a possible solution to deal with the rapidly increasing spent fuels. In detail, a fuel rod slitting device is developed for the decladding of the spent fuel. A series of experiments has been performed to find out the optimal condition of the spent fuel voloxidation which converts the UO 2 pellet into U 3 O 8 powder. The design requirements of the ACP equipment for hot test is established by analysing the modular requirement, radiation hardening and thermal protection of the process equipment, etc. The prototype of the servo manipulator is developed. The manipulator has an excellent performance in terms of the payload to weight ratio that is 30 % higher than that of existing manipulators. To provide reliability and safety of the ACP, the 3 dimensional graphic simulator is developed. Using the simulator the remote handling operation is simulated and as a result, the optimal layout of ACP is obtained. The supervisory control system is designed to control and monitor the several different unit processes. Also the failure monitoring system is developed to detect the possible accidents of the reduction reactor

Conceptual design of the handling and storage system for spent target vessel

Energy Technology Data Exchange (ETDEWEB)

Adachi, Junichi; Sasaki, Shinobu; Kaminaga, Masanori; Hino, Ryutaro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2001-03-01

A conceptual design of a handling and storage system for spent target vessels has been carried out, in order to establish spent target technology for the neutron scattering facility. The spent target vessels must be treated remotely with high reliability and safety, since they are highly activated and contain the poisonous mercury. The system is composed of a target exchange trolley to exchange the target vessel, remote handling equipment such as manipulators, airtight casks for the spent target vessel, storage pits and so on. This report presents the results of conceptual design study on a basic plan, a handling procedure, main devices and their arrangement of a handling and storage system for the spent target vessels. (author)

Powder handling for automated fuel processing

International Nuclear Information System (INIS)

Frederickson, J.R.; Eschenbaum, R.C.; Goldmann, L.H.

1989-01-01

Installation of the Secure Automated Fabrication (SAF) line has been completed. It is located in the Fuel Cycle Plant (FCP) at the Department of Energy's (DOE) Hanford site near Richland, Washington. The SAF line was designed to fabricate advanced reactor fuel pellets and assemble fuel pins by automated, remote operation. This paper describes powder handling equipment and techniques utilized for automated powder processing and powder conditioning systems in this line. 9 figs

340 Waste Handling Facility interim safety basis

International Nuclear Information System (INIS)

Bendixsen, R.B.

1995-01-01

This document establishes the interim safety basis (ISB) for the 340 Waste Handling Facility (340 Facility). An ISB is a documented safety basis that provides a justification for the continued operation of the facility until an upgraded final safety analysis report is prepared that complies with US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports. The ISB for the 340 Facility documents the current design and operation of the facility. The 340 Facility ISB (ISB-003) is based on a facility walkdown and review of the design and operation of the facility, as described in the existing safety documentation. The safety documents reviewed, to develop ISB-003, include the following: OSD-SW-153-0001, Operating Specification Document for the 340 Waste Handling Facility (WHC 1990); OSR-SW-152-00003, Operating Limits for the 340 Waste Handling Facility (WHC 1989); SD-RE-SAP-013, Safety Analysis Report for Packaging, Railroad Liquid Waste Tank Cars (Mercado 1993); SD-WM-TM-001, Safety Assessment Document for the 340 Waste Handling Facility (Berneski 1994a); SD-WM-SEL-016, 340 Facility Safety Equipment List (Berneski 1992); and 340 Complex Fire Hazard Analysis, Draft (Hughes Assoc. Inc. 1994)

American Nurses Association position statement on elimination of manual patient handling to prevent work-related musculoskeletal disorders.

Science.gov (United States)

In order to establish a safe environment for nurses and patients, the American Nurses Association (ANA) supports actions and policies that result in the elimination of manual patient handling. Patient handling, such as lifting, repositioning, and transferring, has conventionally been performed by nurses. The performance of these tasks exposes nurses to increased risk for work-related musculoskeletal disorders. With the development of assistive equipment, such as lift and transfer devices, the risk of musculoskeletal injury can be significantly reduced. Effective use of assistive equipment and devices for patient handling creates a safe healthcare environment by separating the physical burden from the nurse and ensuring the safety, comfort, and dignity of the patient.

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.

Handling and storage of conditioned high-level wastes

International Nuclear Information System (INIS)

1983-01-01

This report deals with certain aspects of the management of one of the most important wastes, i.e. the handling and storage of conditioned (immobilized and packaged) high-level waste from the reprocessing of spent nuclear fuel and, although much of the material presented here is based on information concerning high-level waste from reprocessing LWR fuel, the principles, as well as many of the details involved, are applicable to all fuel types. The report provides illustrative background material on the arising and characteristics of high-level wastes and, qualitatively, their requirements for conditioning. The report introduces the principles important in conditioned high-level waste storage and describes the types of equipment and facilities, used or studied, for handling and storage of such waste. Finally, it discusses the safety and economic aspects that are considered in the design and operation of handling and storage facilities

Concept design of DEMO divertor cassette remote handling: Simply supported beam approach

Energy Technology Data Exchange (ETDEWEB)

Mozzillo, Rocco [CREATE, University of Naples Federico II, DII, P.le Tecchio 80, 80125, Naples (Italy); Di Gironimo, Giuseppei, E-mail: peppe.digironimo@gmail.com [CREATE, University of Naples Federico II, DII, P.le Tecchio 80, 80125, Naples (Italy); Mäkinen, Harri [VTT Technical Research Centre of Finland, P.O. Box 1300, FI-33101 Tampere (Finland); Miccichè, Gioacchino [ENEA – CR Brasimone, I-40032 Camugnano, BO (Italy); Määttä, Timo [VTT Technical Research Centre of Finland, P.O. Box 1300, FI-33101 Tampere (Finland)

2017-03-15

Highlights: • The present work focused on a new approach to the design of DEMO Divertor Cassette Remote Handling Equipment. • The work provides an alternative approach to the design based on the concept of a simply supported beam. • The approach proposed focuses a Divertor Cassette mover that performs the maintenance of the three cassettes at each port. • First rough dimensioning of the main components has been provided and demonstrating the feasibility of the design solutions. • The main idea of the work consisted on a design capable to use knowledge already adopted in industrial contexts. - Abstract: The present work focused on the development of a new approach to the concept design of DEMO Divertor Cassette (DC) Remote Handling Equipment (RHE). The approach is based on three main assumptions: the DC remote handling activities and the equipment shall be simplified as much as possible; technologies well known and consolidated in the industrial context can be adopted also in the nuclear fusion field; the design of the RHE should be based on a simply supported beam approach instead of cantilever approach. In detail, during the maintenance activities the barycentre of the DC is centred with respect to DC supports. This solution could simplify the design of RHE with a consequent reduction of the design and development costs. Moreover also the DC remote handling tasks shall be simplified in order to better manage the DC maintenance processes. For this reason the DC assembly and disassembly process has been simplified dividing the main sequences in basic movements. For each movement a dedicated tool has been conceived.

Canadian capabilities in fusion fuels technology and remote handling

International Nuclear Information System (INIS)

1987-10-01

This report describes Canadian expertise in fusion fuels technology and remote handling. The Canadian Fusion Fuels Technology Project (CFFTP) was established and is funded by the Canadian government, the province of Ontario and Ontario Hydro to focus on the technology necessary to produce and manage the tritium and deuterium fuels to be used in fusion power reactors. Its activities are divided amongst three responsibility areas, namely, the development of blanket, first wall, reactor exhaust and fuel processing systems, the development of safe and reliable operating procedures for fusion facilities, and, finally, the application of these developments to specific projects such as tritium laboratories. CFFTP also hopes to utilize and adapt Canadian developments in an international sense, by, for instance, offering training courses to the international tritium community. Tritium management expertise is widely available in Canada because tritium is a byproduct of the routine operation of CANDU reactors. Expertise in remote handling is another byproduct of research and development of of CANDU facilities. In addition to describing the remote handling technology developed in Canada, this report contains a brief description of the Canadian tritium laboratories, storage beds and extraction plants as well as a discussion of tritium monitors and equipment developed in support of the CANDU reactor and fusion programs. Appendix A lists Canadian manufacturers of tritium equipment and Appendix B describes some of the projects performed by CFFTP for offshore clients

The design of in-cell crane handling systems for nuclear plants

International Nuclear Information System (INIS)

Hansford, S.M.; Scott, R.

1992-01-01

The reprocessing and waste management facilities at (BNFL's) British Nuclear Fuels Limited's Sellafield site make extensive use of crane handling systems. These range from conventional mechanical handling operations as used generally in industry to high integrity applications through to remote robotic handling operations in radiation environments. This paper describes the design methodologies developed for the design of crane systems for remote handling operations - in-cell crane systems. In most applications the in-cell crane systems are an integral part of the plant process equipment and reliable and safe operations are a key design parameter. Outlined are the techniques developed to achieve high levels of crane system availability for operations in hazardous radiation environments. These techniques are now well established and proven through many years of successful plant operation. A recent application of in-cell crane handling systems design for process duty application is described. The benefits of a systematic design approach and a functionally-based engineering organization are also highlighted. (author)

Remote handling equipment for the decommissioning of the Windscale Advanced Gas Cooled Reactor

International Nuclear Information System (INIS)

Barker, A.; Birss, I.R.; Fish, G.

1984-01-01

A decision to decommission the Windscale Advanced Gas Cooled Reactor was taken shortly after reactor shutdown in 1981. The fuel has now been discharged and the decommissioning programme will last about 10-12 years. The paper describes the programme and objectives and deals with methods of handling and disposing of the radioactive waste material. The main new facility required is a Waste Packaging Building adjacent to the existing reactor in which the waste boxes will be filled, active waste encapsulated in concrete and the boxes cleaned, swabbed and monitored to comply with IAEA transport regulations. The handling machine concept and features are described. The assaying and packaging of the waste material, the control of box movement and the process of concrete encapsulation is described. The paper concludes with a description of the development programme to support the Project. The tasks include a study of cutting techniques, production and control of dust and smoke, viewing and lighting methods, filtration, decontamination and fixing of contamination

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

International Nuclear Information System (INIS)

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

1990-01-01

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

Treatment of plutonium-contaminated solid waste: a review of handling systems

International Nuclear Information System (INIS)

Meredith, B.E.; Hardy, A.R.

1985-02-01

Handling techniques are reviewed to identify those suitable for adaptation for use in transporting large items of redundant plutonium contaminated plant and equipment to a remotely operated size reduction facility, moving them into the facility, presenting them to size reduction equipment and loading the processed waste into drums. It is concluded that an integrated system based on a combination of slatted conveyors, roller tables, air transporters and manipulators, merits further consideration. An appropriate experimental programme is outlined. (author)

Procedure of safe handling with cytostatic drugs

Directory of Open Access Journals (Sweden)

Kodžo Dragan

2003-01-01

Full Text Available Working group for safe handling with cytostatic drugs has been formed by the Ministry of Health, and it consists of professionals from IORS, Federal Bureau of Weights and Measures, Industrial Medicine, Institute of Hematology, Military Medical Academy, and Crown Agents. The aim of this working group is to prepare procedures for safe handling with cytostatic drugs, as well as program for educational seminar for nurses, medical technicians, and pharmaceutical technicians. The procedures will serve as a guide of good practice of oncology health care, and will refer to all actions that health care professionals carry out from the moment of drugs arrival to the pharmacy to the moment of their application. In the first segment of this procedure, general rules are given for working with cytotoxic agents, control for risky exposures, safe system of work, control of working environment, monitoring of the employees' health condition adequate protection in the working environment, protective equipment of the employees (gloves, mask, cap, eyeglasses, shoe covers, coats and chambers for vertical laminary air stream. Storing of cytostatics, procedure in case of accident, and waste handling and removal are also described in this segment. Fifty-three standard operational procedures are described in detail in the second segment. Training scheme for preparation of chemotherapy is given in the third segment - education related to various fields and practical part, which would be carried out through workshops, and at the end of the course participants would pass a test and obtain certificate. After the procedures for safe handling with cytostatics are legally regulated employer will have to provide minimum of protective equipment, special rooms for the drugs dissolving, chambers with laminar airflow, 6 hours working time, rotation of the staff working with drugs dissolving in intervals of every five years, higher efficiency, better health control. In conclusion

Repository waste-handling operations, 1998

International Nuclear Information System (INIS)

Cottam, A.E.; Connell, L.

1986-04-01

The Civilian Radioactive Waste Management Program Mission Plan and the Generic Requirements for a Mined Geologic Disposal System state that beginning in 1998, commercial spent fuel not exceeding 70,000 metric tons of heavy metal, or a quantity of solidified high-level radioactive waste resulting from the reprocessing of such a quantity of spent fuel, will be shipped to a deep geologic repository for permanent storage. The development of a waste-handling system that can process 3000 metric tons of heavy metal annually will require the adoption of a fully automated approach. The safety and minimum exposure of personnel will be the prime goals of the repository waste handling system. A man-out-of-the-loop approach will be used in all operations including the receipt of spent fuel in shipping casks, the inspection and unloading of the spent fuel into automated hot-cell facilities, the disassembly of spent fuel assemblies, the consolidation of fuel rods, and the packaging of fuel rods into heavy-walled site-specific containers. These containers are designed to contain the radionuclides for up to 1000 years. The ability of a repository to handle more than 6000 pressurized water reactor spent-fuel rods per day on a production basis for approximately a 23-year period will require that a systems approach be adopted that combines space-age technology, robotics, and sophisticated automated computerized equipment. New advanced inspection techniques, maintenance by robots, and safety will be key factors in the design, construction, and licensing of a repository waste-handling facility for 1998

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

International Nuclear Information System (INIS)

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

2000-09-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2000-09-01

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

Potential application of nuclear remote-handling technology to underwater inspection and maintenance

International Nuclear Information System (INIS)

Eccleston, M.J.

1990-01-01

Examples are given of remote handling equipment developed within the nuclear industry and employing telemanipulative or telerobotic principles. In telerobotics the nuclear industry has been following a trend towards increased levels of autonomy, delegating operator control to a computer, for example, in resolved rate manipulator tip control, teach-and-repeat control and collision avoidance. Illustrations are presented of remote-handling techniques from the nuclear industry which may be carried over into undersea remote inspection, maintenance and repair systems. (author)

Systems for harvesting and handling cotton plant residue

Energy Technology Data Exchange (ETDEWEB)

Coates, W. [Univ. of Arizona, Tucson, AZ (United States)

1993-12-31

In the warmer regions of the United States, cotton plant residue must be buried to prevent it from serving as an overwintering site for insect pests such as the pink bollworm. Most of the field operations used to bury the residue are high energy consumers and tend to degrade soil structure, thereby increasing the potential for erosion. The residue is of little value as a soil amendment and consequently is considered a negative value biomass. A commercial system to harvest cotton plant residue would be of both economic and environmental benefit to cotton producers. Research has been underway at the University of Arizona since the spring of 1991 to develop a commercially viable system for harvesting cotton plant residue. Equipment durability, degree of densification, energy required, cleanliness of the harvested material, and ease of product handling and transport are some of the performance variables which have been measured. Two systems have proven superior. In both, the plants are pulled from the ground using an implement developed specifically for the purpose. In one system, the stalks are baled using a large round baler, while in the other the stalks are chopped with a forage harvester, and then made into packages using a cotton module maker. Field capacities, energy requirements, package density and durability, and ease of handling with commercially available equipment have been measured for both systems. Selection of an optimum system for a specific operation depends upon end use of the product, and upon equipment availability.

Vitrification process equipment design for the West Valley Demonstration Project

International Nuclear Information System (INIS)

Chapman, C.C.; Drosjack, W.P.

1988-10-01

The vitrification process and equipment design is nearing completion for the West Valley Project. This report provides the basis and current status for the design of the major vessels and equipment within the West Valley Vitrification Plant. A review of the function and key design features of the equipment is also provided. The major subsystems described include the feed preparation and delivery systems, the melter, the canister handling systems, and the process off-gas system. 11 refs., 33 figs., 4 tabs

Better fuel handling system performance through improved elastomers and seals

Energy Technology Data Exchange (ETDEWEB)

Wensel, R G; Metcalfe, R [Atomic Energy of Canada Ltd., Chalk River, ON (Canada)

1997-12-31

In the area of elastomers, tests have identified specific compounds that perform well in each class of CANDU service. They offer gains in service life, sometimes by factors of ten or more. Moreover, the aging characteristics of these specific compounds are being thoroughly investigated, whereas many elastomers used previously were either non-specific or their aging was unknown. In this paper the benefits of elastomer upgrading, as well as the deficiencies of current station elastomer practices, are discussed in the context of fuel handling equipment. Guidelines for procurement, storage, handling and condition monitoring of elastomer seals are outlined. (author). 3 figs.

Better fuel handling system performance through improved elastomers and seals

International Nuclear Information System (INIS)

Wensel, R.G.; Metcalfe, R.

1996-01-01

In the area of elastomers, tests have identified specific compounds that perform well in each class of CANDU service. They offer gains in service life, sometimes by factors of ten or more. Moreover, the aging characteristics of these specific compounds are being thoroughly investigated, whereas many elastomers used previously were either non-specific or their aging was unknown. In this paper the benefits of elastomer upgrading, as well as the deficiencies of current station elastomer practices, are discussed in the context of fuel handling equipment. Guidelines for procurement, storage, handling and condition monitoring of elastomer seals are outlined. (author). 3 figs

Scoping studies of tritium handling in a tokamak experimental power reactor

International Nuclear Information System (INIS)

Cherdack, R.; Watson, J.S.; Clinton, S.D.; Fisher, P.W.

1975-01-01

Tritium handling techniques in an experimental fusion power reactor (EPR) are evaluated to determine the requirements of the system and to compare different equipment and techniques for meeting those requirements. Tritium process equipment is needed to (1) evacuate and maintain a vacuum in the plasma vessel and the neutral beam injectors, (2) purify and recycle tritium and deuterium for the plasma fuel cycle, (3) recover tritium from experimental breeding modules, and (4) provide tritium containment and atmospheric cleanup. A development program is outlined to develop and demonstrate the required techniques and equipment and to permit confident design of an EPR for operation by the mid-1980s

The design and qualification of radiation tolerant equipment for the nuclear power industry

International Nuclear Information System (INIS)

Sharp, R.; Pater, L.

1995-01-01

The nuclear power industry has many demands for equipment tolerant to the damaging effects of radiation. The wide variety of applications, including components handling, tooling, monitoring and communications, means that a systematic evaluation of the effects of radiation on materials and components used for equipment in radioactive facilities is often required. This paper describes the various effects of radiation on equipment, and discusses how to manage them when using and designing equipment. (Author)

Remote handling recognition and display device

International Nuclear Information System (INIS)

Kimura, Motohiko.

1979-01-01

Purpose: To surely recognize the movements of remote handling equipments in a reactor by the use of a device in a simple structure. Constitution: A light emission surface and a light reception surface are provided, for example, putting therebetween a hook of a nob of a control rod as a remote control equipment. Depending on the position of the hook, there are two possible cases where the light can not arrive the light reception surface inhibited by the hook and where the light can be received not inhibited by the hook. By visually monitoring the presence or absence of the light reception from the outside of the reactor, the movement of the nob for the control rod can be recognized. Optical fibers connect the optical source with the light emission surface, and the light reception surface with the display surface. (Ikeda, J.)

Virtual reality applications in remote handling development for tokamaks in India

International Nuclear Information System (INIS)

Dutta, Pramit; Rastogi, Naveen; Gotewal, Krishan Kumar

2017-01-01

Highlights: • Evaluation of Virtual Reality (VR) in design and operation phases of Remote Handling (RH) equipment for tokamak. • VR based centralized facility, to cater RH development and operation, is setup at Institute for Plasma Research, India. • The VR facility system architecture and components are discussed. • Introduction to various VR applications developed for design and development of tokamak RH equipment. - Abstract: A tokamak is a plasma confinement device that can be used to achieve magnetically confined nuclear fusion within a reactor. Owing to the harsh environment, Remote Handling (RH) systems are used for inspection and maintenance of the tokamak in-vessel components. As the number of in-vessel components requiring RH maintenance is large, physical prototyping of all strategies becomes a major challenge. The operation of RH systems poses further challenge as all equipment have to be controlled remotely within very strict accuracy limits with minimum reliance on the available camera feedback. In both design and operation phases of RH equipment, application of Virtual Reality (VR) becomes imperative. The scope of this paper is to introduce some applications of VR in the design and operation cycle of RH, which are not available commercially. The paper discusses the requirement of VR as a tool for RH equipment design and operation. The details of a comprehensive VR facility that has been established to support the RH development for Indian tokamaks are also presented. Further, various cases studies are provided to highlight the utilization of this VR facility within phases of RH development and operation.

Virtual reality applications in remote handling development for tokamaks in India

Energy Technology Data Exchange (ETDEWEB)

Dutta, Pramit, E-mail: pramitd@ipr.res.in; Rastogi, Naveen; Gotewal, Krishan Kumar

2017-05-15

Highlights: • Evaluation of Virtual Reality (VR) in design and operation phases of Remote Handling (RH) equipment for tokamak. • VR based centralized facility, to cater RH development and operation, is setup at Institute for Plasma Research, India. • The VR facility system architecture and components are discussed. • Introduction to various VR applications developed for design and development of tokamak RH equipment. - Abstract: A tokamak is a plasma confinement device that can be used to achieve magnetically confined nuclear fusion within a reactor. Owing to the harsh environment, Remote Handling (RH) systems are used for inspection and maintenance of the tokamak in-vessel components. As the number of in-vessel components requiring RH maintenance is large, physical prototyping of all strategies becomes a major challenge. The operation of RH systems poses further challenge as all equipment have to be controlled remotely within very strict accuracy limits with minimum reliance on the available camera feedback. In both design and operation phases of RH equipment, application of Virtual Reality (VR) becomes imperative. The scope of this paper is to introduce some applications of VR in the design and operation cycle of RH, which are not available commercially. The paper discusses the requirement of VR as a tool for RH equipment design and operation. The details of a comprehensive VR facility that has been established to support the RH development for Indian tokamaks are also presented. Further, various cases studies are provided to highlight the utilization of this VR facility within phases of RH development and operation.

Remote handling needs of the Princeton Plasma Physics Laboratory

International Nuclear Information System (INIS)

Smiltnieks, V.

1982-07-01

This report is the result of a Task Force study commissioned by the Canadian Fusion Fuels Technology Project (CFFTP) to investigate the remote handling requirements at the Princeton Plasma Physics Laboratory (PPPL) and identify specific areas where CFFTP could offer a contractual or collaborative participation, drawing on the Canadian industrial expertise in remote handling technology. The Task Force reviewed four areas related to remote handling requirements; the TFTR facility as a whole, the service equipment required for remote maintenance, the more complex in-vessel components, and the tritium systems. Remote maintenance requirements both inside the vacuum vessel and around the periphery of the machine were identified as the principal areas where Canadian resources could effectively provide an input, initially in requirement definition, concept evaluation and feasibility design, and subsequently in detailed design and manufacture. Support requirements were identified in such areas as the mock-up facility and a variety of planning studies relating to reliability, availability, and staff training. Specific tasks are described which provide an important data base to the facility's remote handling requirements. Canadian involvement in the areas is suggested where expertise exists and support for the remote handling work is warranted. Reliability, maintenance operations, inspection strategy and decommissioning are suggested for study. Several specific components are singled out as needing development

Design and operation of a remotely operated plutonium waste size reduction and material handling process

International Nuclear Information System (INIS)

Stewart, J.A. III; Charlesworth, D.L.

1986-01-01

Noncombustible 238 Pu and 239 Pu waste is generated as a result of normal operation and decommissioning activity at the Savannah River Plant, and is being retrievably stored there. As part of the long-term plant to process the stored waste and current waste for permanent disposal, a remote size reduction and material handling process is being cold-tested at Savannah River Laboratory. The process consists of a large, low-speed shredder and material handling system, a remote worktable, a bagless transfer system, and a robotically controlled manipulator. Initial testing of the shredder and material handling system and a cycle test of the bagless transfer system has been completed. Fabrication and acceptance testing of the Telerobat, a robotically controlled manipulator has been completed. Testing is scheduled to begin in 3/86. Design features maximizing the ability to remotely maintain the equipment were incorporated. Complete cold-testing of the equipment is scheduled to be completed in 1987

Material handling for the Los Alamos National Laboratory Nuclear Storage Facility

International Nuclear Information System (INIS)

Pittman, P.; Roybal, J.; Durrer, R.; Gordon, D.

1999-01-01

This paper will present the design and application of material handling and automation systems currently being developed for the Los Alamos National Laboratory (LANL) Nuclear Material Storage Facility (NMSF) renovation project. The NMSF is a long-term storage facility for nuclear material in various forms. The material is stored within tubes in a rack called a basket. The material handling equipment range from simple lift assist devices to more sophisticated fully automated robots, and are split into three basic systems: a Vault Automation System, an NDA automation System, and a Drum handling System. The Vault Automation system provides a mechanism to handle a basket of material cans and to load/unload storage tubes within the material vault. In addition, another robot is provided to load/unload material cans within the baskets. The NDA Automation System provides a mechanism to move material within the small canister NDA laboratory and to load/unload the NDA instruments. The Drum Handling System consists of a series of off the shelf components used to assist in lifting heavy objects such as pallets of material or drums and barrels

Storage, handling and movement of fuel and related components at nuclear power plants

International Nuclear Information System (INIS)

1979-01-01

The report describes in general terms the various operations involved in the handling of fresh fuel, irradiated fuel, and core components such as control rods, neutron sources, burnable poisons and removable instruments. It outlines the principal safety problems in these operations and provides the broad safety criteria which must be observed in the design, operation and maintenance of equipment and facilities for handling, transferring, and storing nuclear fuel and core components at nuclear power reactor sites

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

Spent fuel storage process equipment development

International Nuclear Information System (INIS)

Park, Hyun Soo; Lee, Jae Sol; Yoo, Jae Hyung

1990-02-01

Nuclear energy which is a major energy source of national energy supply entails spent fuels. Spent fuels which are high level radioactive meterials, are tricky to manage and need high technology. The objectives of this study are to establish and develop key elements of spent fuel management technologies: handling equipment and maintenance, process automation technology, colling system, and cleanup system. (author)

Guidelines for Remote Handling Maintenance of ITER Neutral Beam Components

International Nuclear Information System (INIS)

Cordier, J.-J.; Hemsworth, R.; Bayetti, P.

2006-01-01

Remote handling maintenance of ITER components is one of the main challenges of the ITER project. This type of maintenance shall be operational for the nuclear phase of exploitation of ITER, and be considered at a very early stage since it significantly impacts on the components design, interfaces management and integration business. A large part of the R/H equipment will be procured by the EU partner, in particular the whole Neutral Beam Remote Handling (RH) equipment package. A great deal of work has already been done in this field during the EDA phase of ITER project, but improvements and alternative option that are now proposed by ITER lead to added RH and maintenance engineering studies. The Neutral Beam Heating -and- Current Drive system 1 is being revisited by the ITER project. The vertical maintenance scheme that is presently considered by ITER, may significantly impact on the reference design of the Neutral Beam (NB) system and associated components and lead to new design of the NB box itself. In addition, revision of both NB cell radiation level zoning and remote handling classification of the beam line injector will also significantly impact on components design and maintenance. Based on the experience gained on the vertical maintenance scheme, developed in detail for the ITER Neutral Beam Test Facility 2 to be built in Europe in a near future, guidelines for the revision of the design and preliminary feasibility study of the remote handling vertical maintenance scheme of beam line components are described in the paper. A maintenance option for the SINGAP3 accelerator is also presented. (author)

Individual Information-Centered Approach for Handling Physical Activity Missing Data

Science.gov (United States)

Kang, Minsoo; Rowe, David A.; Barreira, Tiago V.; Robinson, Terrance S.; Mahar, Matthew T.

2009-01-01

The purpose of this study was to validate individual information (II)-centered methods for handling missing data, using data samples of 118 middle-aged adults and 91 older adults equipped with Yamax SW-200 pedometers and Actigraph accelerometers for 7 days. We used a semisimulation approach to create six data sets: three physical activity outcome…

Handling final storage of unreprocessed spent nuclear fuel

International Nuclear Information System (INIS)

1978-01-01

The present second report from KBS describes how the safe final storage of spent unreprocessed nuclear fuel can be implemented. According to the Swedish Stipulation Law, the owner must specify in which form the waste is to be stored, how final storage is to be effected, how the waste is to be transported and all other aspects of fuel handling and storage which must be taken into consideration in judging whether the proposed final storage method can be considered to be absolutely safe and feasible. Thus, the description must go beyond general plans and sketches. The description is therefore relatively detailed, even concerning those parts which are less essential for evaluating the safety of the waste storage method. For those parts of the handling chain which are the same for both alternatives of the Stipulation Law, the reader is referred in some cases to the first report. Both of the alternatives of the Stipulation Law may be used in the future. Handling equipment and facilities for the two storage methods are so designed that a combination in the desired proportions is practically feasible. In this first part of the report are presented: premises and data, a description of the various steps of the handling procedure, a summary of dispersal processes and a safety analysis. (author)

Eye-in-Hand Manipulation for Remote Handling: Experimental Setup

Science.gov (United States)

Niu, Longchuan; Suominen, Olli; Aref, Mohammad M.; Mattila, Jouni; Ruiz, Emilio; Esque, Salvador

2018-03-01

A prototype for eye-in-hand manipulation in the context of remote handling in the International Thermonuclear Experimental Reactor (ITER)1 is presented in this paper. The setup consists of an industrial robot manipulator with a modified open control architecture and equipped with a pair of stereoscopic cameras, a force/torque sensor, and pneumatic tools. It is controlled through a haptic device in a mock-up environment. The industrial robot controller has been replaced by a single industrial PC running Xenomai that has a real-time connection to both the robot controller and another Linux PC running as the controller for the haptic device. The new remote handling control environment enables further development of advanced control schemes for autonomous and semi-autonomous manipulation tasks. This setup benefits from a stereovision system for accurate tracking of the target objects with irregular shapes. The overall environmental setup successfully demonstrates the required robustness and precision that remote handling tasks need.

Current US strategy and technologies for spent fuel handling

International Nuclear Information System (INIS)

Bennett, P.C.; Stringer, J.B.

1999-01-01

The United States Department of Energy has recently completed a topical safety analysis report outlining the design and operation of a Centralized Interim Storage Facility for spent commercial nuclear fuel. During the course of the design, dose assessments indicated the need for remote operation of many of the cask handling operations. Use of robotic equipment was identified as a desirable handling solution that is capable of automating many of the operations to maintain throughput, and sufficiently flexible to handle five or more different storage cask designs in varying numbers on a given day. This paper discusses the facility and the dose assessment leading to this choice, and reviews factors to be considered when choosing robotics or automation. Further, a new computer simulation tool to quantify dose to humans working in radiological environments, the Radiological Environment Modeling System (REMS), is introduced. REMS has been developed to produce a more accurate estimate of dose to radiation workers in new activities with radiological hazards. (author)

Vestibule and Cask Preparation Mechanical Handling Calculation

International Nuclear Information System (INIS)

Ambre, N.

2004-01-01

The scope of this document is to develop the size, operational envelopes, and major requirements of the equipment to be used in the vestibule, cask preparation area, and the crane maintenance area of the Fuel Handling Facility. This calculation is intended to support the License Application (LA) submittal of December 2004, in accordance with the directive given by DOE correspondence received on the 27th of January 2004 entitled: ''Authorization for Bechtel SAIC Company L.L.C. to Include a Bare Fuel Handling Facility and Increased Aging Capacity in the License Application, Contract Number DE-AC--28-01R W12101'' (Ref. 167124). This correspondence was appended by further correspondence received on the 19th of February 2004 entitled: ''Technical Direction to Bechtel SAIC Company L.L. C. for Surface Facility Improvements, Contract Number DE-AC--28-01R W12101; TDL No. 04-024'' (Ref. 16875 1). These documents give the authorization for a Fuel Handling Facility to be included in the baseline. The limitations of this preliminary calculation lie within the assumptions of section 5 , as this calculation is part of an evolutionary design process

Criticality safety evaluation report for the cold vacuum drying facility's process water handling system

International Nuclear Information System (INIS)

NELSON, J.V.

1999-01-01

This report addresses the criticality concerns associated with process water handling in the Cold Vacuum Drying Facility. The controls and limitations on equipment design and operations to control potential criticality occurrences are identified

The on-board data handling system of the AFIS-P mission

Energy Technology Data Exchange (ETDEWEB)

Gaisbauer, Dominic; Greenwald, Daniel; Hahn, Alexander; Hauptmann, Philipp; Konorov, Igor; Meng, Lingxin; Paul, Stephan; Poeschl, Thomas [Physics Department E18, Technische Universitaet Muenchen (Germany); Losekamm, Martin [Physics Department E18, Technische Universitaet Muenchen (Germany); Institute of Astronautics, Technische Universitaet Muenchen (Germany); Renker, Dieter [Physics Department E17, Technische Universitaet Muenchen (Germany)

2014-07-01

The Antiproton Flux in Space experiment (AFIS) is a novel particle detector comprised of silicon photomultipliers and scintillating plastic fibers. Its purpose is to measure the trapped antiproton flux in low Earth orbit. To test the detector and the data acquisition system, a prototype detector will be flown aboard a high altitude research balloon as part of the REXUS/BEXUS program by the German Aerospace Center (DLR). This talk presents the on-board data handling system and the ground support equipment of AFIS-P. It will also highlight the data handling algorithms developed and used for the mission.

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

Design of equipment used for high-level waste vitrification at the West Valley Demonstration Project

International Nuclear Information System (INIS)

Vance, R.F.; Brill, B.A.; Carl, D.E.

1997-06-01

The equipment as designed, started, and operated for high-level radioactive waste vitrification at the West Valley Demonstration Project in western New York State is described. Equipment for the processes of melter feed make-up, vitrification, canister handling, and off-gas treatment are included. For each item of equipment the functional requirements, process description, and hardware descriptions are presented

Round table on the Supply Chain for NPPs construction: Localization - Daya Bay Experience; REEL Handling and Lifting Systems, More than 60 years expertise in lifting and handling equipment in production process

International Nuclear Information System (INIS)

Frantz, Philippe; Lachaise, Marc; Lau, Steven

2014-01-01

The second day afternoon began with the round table on the Supply Chain for NPPs construction with Philippe Frantz, President of REEL, Marc Lachaise, Head of procurement of NNB at EDF Energy, and Steven Lau, First Deputy General Manager of DNMC. Philippe Frantz started to present the activities and the contribution of REEL in the construction of NPPs as a main supplier of handling system. Then, Marc Lachaise took the lead to present Hinkley Point C Project, the Values of NNB and the key role of the supply chain in this Project. Steven Lau went on to describe the link of the supply chain with the operating of NPPs and explained the cooperation between EDF and CGNPC in order to secure the supply of equipment. Following their presentation, they started the open discussion with the audience by explaining their strategy to make or to buy and the link of this strategy to their core business. They also highlighted the new relations and the new partnership between supplier and customer. They insisted on the necessity to invest on supply chain and to have a strong Nuclear Safety Culture in the supply chain

Interim design status and operational report for remote handling fixtures: primary and secondary burners

International Nuclear Information System (INIS)

Burgoyne, R.M.

1976-12-01

The HTGR reprocessing flowsheet consists of two basic process elements: (1) spent fuel crushing and burning and (2) solvent extraction. Fundamental to these elements is the design and development of specialized process equipment and support facilities. A major consideration of this design and development program is equipment maintenance: specifically, the design and demonstration of selected remote maintenance capabilities and the integration of these into process equipment design. This report documents the current status of the development of remote handling and maintenance fixtures for the primary and secondary burners

Queuing theory models used for port equipment sizing

Science.gov (United States)

Dragu, V.; Dinu, O.; Ruscă, A.; Burciu, Ş.; Roman, E. A.

2017-08-01

The significant growth of volumes and distances on road transportation led to the necessity of finding solutions to increase water transportation market share together with the handling and transfer technologies within its terminals. It is widely known that the biggest times are consumed within the transport terminals (loading/unloading/transfer) and so the necessity of constantly developing handling techniques and technologies in concordance with the goods flows size so that the total waiting time of ships within ports is reduced. Port development should be achieved by harmonizing the contradictory interests of port administration and users. Port administrators aim profit increase opposite to users that want savings by increasing consumers’ surplus. The difficulty consists in the fact that the transport demand - supply equilibrium must be realised at costs and goods quantities transiting the port in order to satisfy the interests of both parties involved. This paper presents a port equipment sizing model by using queueing theory so that the sum of costs for ships waiting operations and equipment usage would be minimum. Ship operation within the port is assimilated to a mass service waiting system in which parameters are later used to determine the main costs for ships and port equipment.

Licence template for mobile handling and storage of radioactive substances for the nondestructive testing of materials

International Nuclear Information System (INIS)

Lange, A.; Schumann, J.; Huhn, W.

2016-01-01

The Technical Committee ''Radiation Protection'' (Fachausschuss ''Strahlenschutz'') and the Laender Committee ''X-ray ordinance'' (Laenderausschuss ''Roentgenverordnung'') have appointed a working group for the formulation of licence templates for the nationwide use of X-ray equipment or handling of radioactive substances. To date, the following licence templates have been adopted: - Mobile operation of X-ray equipment under technical radiography to the coarse structural analysis in material testing; - Mobile operation of a handheld X-ray fluorescence system; - Mobile operation of a flash X-ray system; - Operation of an X-ray system for teleradiology The licence template ''Mobile handling and storage of radioactive substances for the nondestructive testing of materials'' is scheduled for publication. The licence template ''Practices in external facilities and installations'' is currently being revised. The licence template ''Mobile handling and storage of radioactive substances for the nondestructive testing of materials'' is used as an example to demonstrate the legal framework and the results of the working group.

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

Autonomous underwater handling system for service, measurement and cutting tasks for the decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Hahn, M.; Haferkamp, H.; Bach, W.; Rose, N.

1992-01-01

For about 10 years the Institute for Material Science at the Hanover University has worked on projects of underwater cutting and welding. Increasing tasks to be done in nuclear facilities led to the development of special handling systems to support and handle the cutting tools. Also sensors and computers for extensive and complex tasks were integrated. A small sized freediving handling system, equipped with 2 video cameras, ultrasonic and radiation sensors and a plasma cutting torch for inspection and decommissioning tasks in nuclear facilities is described in this paper. (Author)

TA-60-1 Heavy Equipment Shop Areas SWPPP Rev 2 Jan 2017-Final

Energy Technology Data Exchange (ETDEWEB)

Burgin, Jillian Elizabeth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-02-07

The primary activities and equipment areas at the facility that are potential stormwater pollution sources include; The storage of vehicles and heavy equipment awaiting repair; or repaired vehicles waiting to be picked up; The storage and handling of oils, anti-freeze, solvents, degreasers, batteries and other chemicals for the maintenance of vehicles and heavy equipment; and Equipment cleaning operations including exterior vehicle wash-down. Steam cleaning is only done on the steam cleaning pad area located at the north east end of Building 60-0001.

Principles of commercially available pretreatment and feeding equipment for baled biomass

Energy Technology Data Exchange (ETDEWEB)

Koch, T. [Thomas Koch Energi, Vanloese (Denmark); Hummelshoej, R.M. [COWIconsult, Lyngby (Denmark)

1993-12-31

During the last 15 years, there has been a growing interest in utilizing waste biomass for energy production in Denmark. Since 1990, it has been unlawful to burn surplus straw on open land. Before the year 2000, it is intended to utilize most of the 2--3 million tons of surplus straw as an energy resource. The type of plants that were built in the beginning were combustion plants for district heating. The feeding equipment for these plants has been developed to an acceptable standard. Later, combustion plants for combined heat and power production based on a steam turbine were introduced. This type of plant demands a much greater continuity in the fuel flow, and the consequences of minor discontinuities are to be dropped from the grid. Gasification and pyrolysis demands a high sealing ability of the feeding equipment, because of the explosive and poisonous gas in the plant and a need for a very high continuity in the fuel feed. The first plants were built with the equipment and experiences from the farming industries, which have a long tradition in working with biomass-handling. The experiences gained with this type of equipment were not very promising, and in the early eighties, a more industrial type of biomass-handling equipment was developed. This paper presents the principles of the heavy-duty biomass pretreatment and feeding equipment that was commercially available in Denmark in May, 1993.

Design by analysis of composite pressure equipment

International Nuclear Information System (INIS)

Durand, S.; Mallard, H.

2004-01-01

Design by analysis has been particularly pointed out by the european pressure equipment directive. Advanced mechanical analysis like finite element method are used instead of classical design by formulas or graphs. Structural behaviour can be understood by the designer. Design by analysis of metallic pressure equipments is widely used. Material behaviour or limits analysis is based on sophisticated approach (elasto-plastic analysis,..). Design by analysis of composite pressure equipments is not systematically used for industrial products. The difficulty comes from the number of information to handle. The laws of mechanics are the same for composite materials than for steel. The authors want to show that in design by analysis, the composite material approach is only more complete than the metallic approach. Mechanics is more general but not more complicated. A multi-material approach is a natural evolution of design by analysis of composite equipments. The presentation is illustrated by several industrial cases - composite vessel: analogy with metallic calculations; - composite pipes and fittings; - welding and bounding of thermoplastic equipments. (authors)

Criticality Safety Evaluation Report for the Cold Vacuum Drying (CVD) Facility's Process Water Handling System

International Nuclear Information System (INIS)

KESSLER, S.F.

2000-01-01

This report addresses the criticality concerns associated with process water handling in the Cold Vacuum Drying Facility. The controls and limitations on equipment design and operations to control potential criticality occurrences are identified

Safe handling of kilogram amounts of fuel-grade plutonium and of gram amounts of plutonium-238, americium-241 and curium-244

International Nuclear Information System (INIS)

Louwrier, K.P.; Richter, K.

1976-01-01

During the past 10 years about 600 glove-boxes have been installed at the Institute for Transuranium Elements at Karlsruhe. About 80% of these glove-boxes have been designed and equipped for handling 100-g to 1-kg amounts of 239 Pu containing 8-12% 240 Pu (low-exposure plutonium). A small proportion of the glove-boxes is equipped with additional shielding in the form of lead sheet or lead glass for work with recycled plutonium. In these glove-boxes gram-amounts of 241 Am have also been handled for preparation of Al-Am targets using tongs and additional shielding inside the glove-boxes themselves. Water- and lead-shielded glove-boxes equipped with telemanipulators have been installed for routine work with gram-amounts of 241 Am, 243 Am and 244 Cm. A prediction of the expected radiation dose for the personnel is difficult and only valid for a preparation procedure with well-defined preparation steps, owing to the fact that gamma dose-rates depend strongly upon proximity and source seize. Gamma radiation dose measurements during non-routine work for 241 Am target preparation showed that handling of gram amounts leads to a rather high irradiation dose for the personnel, despite lead or steel glove-box shielding and shielding within the glove-boxes. A direct glove-hand to americium contact must be avoided. For all glove-handling of materials with gamma radiation an irradiation control of the forearms of the personnel by, for example, thermoluminescence dosimeters is necessary. Routine handling of americium and curium should be executed with master-slave equipment behind neutron and gamma shielding. (author)

Equipment system for advanced nuclear fuel development

International Nuclear Information System (INIS)

Kwon, Hyuk Il; Ji, C. G.; Bae, S. O.

2002-11-01

The purpose of the settlement of equipment system for nuclear Fuel Technology Development Facility(FTDF) is to build a seismic designed facility that can accommodate handling of nuclear materials including <20% enriched Uranium and produce HANARO fuel commercially, and also to establish the advanced common research equipment essential for the research on advanced fuel development. For this purpose, this research works were performed for the settlement of radiation protection system and facility special equipment for the FTDF, and the advanced common research equipment for the fuel fabrication and research. As a result, 11 kinds of radiation protection systems such as criticality detection and alarm system, 5 kinds of facility special equipment such as environmental pollution protection system and 5 kinds of common research equipment such as electron-beam welding machine were established. By the settlement of exclusive domestic facility for the research of advanced fuel, the fabrication and supply of HANARO fuel is possible and also can export KAERI-invented centrifugal dispersion fuel materials and its technology to the nations having research reactors in operation. For the future, the utilization of the facility will be expanded to universities, industries and other research institutes

Irradiation tests of critical components for remote handling in gamma radiation environment

International Nuclear Information System (INIS)

Obara, Henjiro; Kakudate, Satoshi; Oka, Kiyoshi

1994-08-01

Since the fusion power core of a D-T fusion reactor will be highly activated once it starts operation, personnel access will be prohibited so that assembly and maintenance of the components in the reactor core will have to be totally conducted by remote handling technology. Fusion experimental reactors such as ITER require unprecedented remote handling equipments which are tolerable under gamma radiation of more than 10 6 R/h. For this purpose, the Japan Atomic Energy Research Institute (JAERI) has been developing radiation hard components for remote handling purpose and a number of key components have been tested over 10 9 rad at a radiation dose rate of around 10 6 R/h, using Gamma Ray Radiation Test Facility in JAERI-Takasaki Establishment. This report summarizes the irradiation test results and the latest status of AC servo motor, potentiometer, optical elements, lubricant, sensors and cables, which are key elements of the remote handling system. (author)

Liver dysfunction among workers handling 5-nitro-o-toluidine.

Science.gov (United States)

Shimizu, H; Kumada, T; Nakano, S; Kiriyama, S; Sone, Y; Honda, T; Watanabe, K; Nakano, I; Fukuda, Y; Hayakawa, T

2002-02-01

5-Nitro-o-toluidine is an aromatic nitro amino compound. While other aromatic compounds are known to damage the human liver and are registered as toxic substances, toxicity information concerning 5-nitro-o-toluidine is lacking. To investigate the hepatotoxicity of 5-nitro-o-toluidine. Of 15 workers in the same factory who handled 5-nitro-o-toluidine, three were hospitalised with symptoms of acute liver dysfunction. Suspecting a link between liver dysfunction and working conditions, we correlated workplace factors with clinical findings in all 15 workers. Blood biochemistry tests indicated liver damage in seven of 15 study subjects. Workers who handled 5-nitro-o-toluidine and nitrosyl sulphuric acid often loosened their respiratory protective equipment shortly after 5-nitro-o-toluidine powder had been dispersed into the air of the room. No potential hepatotoxins were present except for 5-nitro-o-toluidine. Six of the affected workers had handled 5-nitro-o-toluidine 12 to 20 times; the seventh worker had handled the powder three times; and the other eight workers without liver dysfunction had handled the material once or twice. No other significant differences in background were evident between the affected and unaffected workers, such as age, sex, or protective measures. Histological findings during recovery from liver damage were similar to those of acute viral hepatitis. None of the 15 subjects has demonstrated liver damage since the factory was closed. A link between liver dysfunction and 5-nitro-o-toluidine exposure is suggested by greater severity of liver dysfunction associated with more episodes of handling.

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.

MANU. Handling of bentonite prior buffer block manufacturing

International Nuclear Information System (INIS)

Laaksonen, R.

2010-01-01

The aim of this study is to describe the entire bentonite handling process starting from freight from harbour to storage facility and ending up to the manufacturing filling process of the bentonite block moulds. This work describes the bentonite handling prior to the process in which bentonite blocks are manufactured in great quantities. This work included a study of relevant Nordic and international well documented cases of storage, processing and techniques involving bentonite material. Information about storage and handling processes from producers or re-sellers of bentonite was collected while keeping in mind the requirements coming from the Posiva side. Also a limited experiment was made for humidification of different material types. This work includes a detailed description of methods and equipment needed for bentonite storage and processing. Posiva Oy used Jauhetekniikka Oy as a consultant to prepare handling process flow charts for bentonite. Jauhetekniikka Oy also evaluated the content of this report. The handling of bentonite was based on the assumption that bentonite process work is done in one factory for 11 months of work time while the weekly volume is around 41-45 tons. Storage space needed in this case is about 300 tons of bentonite which equals about seven weeks of raw material consumption. This work concluded several things to be carefully considered: sampling at various phases of the process, the air quality at the production/storage facilities (humidity and temperature), the level of automation/process control of the manufacturing process and the means of producing/saving data from different phases of the process. (orig.)

Development of monitoring-control methods for heavy remote handling operations in an irradiated environment

Energy Technology Data Exchange (ETDEWEB)

Argouac' h, J R [Alsthom-Atlantique, ACB Nantes (France)

1984-11-01

Heavy remote handling equipment units have benefited from the progress made in robotics, but with certain specific constraints linked to the environment in which they are required to operate. Notably, these constraints impose the exclusive use of electrical techniques.

On current US strategy and technologies for spent fuel handling

International Nuclear Information System (INIS)

Bennett, P.C.

1997-01-01

The US Department of Energy has recently completed a topical safety analysis report outlining the design and operation of a Centralized Interim Storage Facility for spent commercial nuclear fuel. During the course of the design, dose assessments indicated the need for remote operation of many of the cask handling operations. Use of robotic equipment was identified as a desirable handling solution that is capable of automating many of the operations to maintain throughput, and sufficiently flexible to handle five or more different storage cask designs in varying numbers on a given day. This paper discusses the facility and the dose assessment leading to this choice, and reviews factors to be considered when choosing robotics or automation. Further, a new computer simulation tool to quantify dose to humans working in radiological environments, the Radiological Environment Modeling System (REMS), is introduced. REMS has been developed to produce a more accurate estimate of dose to radiation workers in new activities with radiological hazards

Radiation-tolerant cable management systems for remote handling applications in the nuclear industry

International Nuclear Information System (INIS)

Cullen, S.; Thom, M.

1993-01-01

Experience has shown that one of the most vulnerable areas within remote handling equipment is the umbilical cable and termination system. Repairs of a damaged system can be very long due to poorly designed termination techniques. Over the past five years W.L. Gore has gained considerable experience in the design and manufacture of cable systems, utilising unique radiation tolerant materials and manufacturing processes. The cable systems manufactured at the W.L. Gore, Dunfermline, Scotland facility have proven to give excellent performance in the most demanding of remote handling applications. (author)

Design of special purpose equipment - remote control dozer

International Nuclear Information System (INIS)

Aprameyan, K.

1990-01-01

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

FFTF radioactive solid waste handling and transport

International Nuclear Information System (INIS)

Thomson, J.D.

1982-01-01

The equipment necessary for the disposal of radioactive solid waste from the Fast Flux Test Facility (FFTF) is scheduled to be available for operation in late 1982. The plan for disposal of radioactive waste from FFTF will utilize special waste containers, a reusable Solid Waste Cask (SWC) and a Disposable Solid Waste Cask (DSWC). The SWC will be used to transport the waste from the Reactor Containment Building to a concrete and steel DSWC. The DSWC will then be transported to a burial site on the Hanford Reservation near Richland, Washington. Radioactive solid waste generated during the operation of the FFTF consists of activated test assembly hardware, reflectors, in-core shim assemblies and control rods. This radioactive waste must be cleaned (sodium removed) prior to disposal. This paper provides a description of the solid waste disposal process, and the casks and equipment used for handling and transport

Touch Temperature Coating for Off-the-Shelf Electrical Equipment Used on Spacecraft

Science.gov (United States)

Ungar, Eugene K.; Brady, Timothy K.

2010-01-01

Off-the-shelf electrical equipment is frequently used in space-based applications to control costs. However, the reduced heat transfer in the spacecraft microgravity environment causes the equipment to operate at significantly higher temperatures than it would in terrestrial applications. This creates touch temperature issues where items particularly metallic ones become too hot for the crew to handle safely. A touch temperature coating layup has been developed that can be added to spacebased electrically powered hardware. The coating allows the crew to safely handle the hardware, but only slightly impedes the heat transfer from the component during normal operation. In the present work, the coating generic requirements are developed and a layup is described that meets these specifications. Analytical and experimental results are presented that demonstrate the ability of the coating layup to increase the allowable limits of touch temperature while only marginally degrading heat transfer to the environment. This allows the spacecraft crew to handle objects that, if not coated, would be hot enough to cause pain or skin damage.

Equipment Specific Optimum Blast-Design Using Genetic Algorithm

Directory of Open Access Journals (Sweden)

Rahul Upadhyay

2015-08-01

Full Text Available Design of blasting parameters plays an important role in the optimization of mining cost as well as cost of subsequent processing of ore. Drilling and handling costs are the major mining cost. This work presents an indirect optimization model for mining cost through optimization of blasting parameters for a particular set of drilling and loading equipment.

Design and operation of equipment used to develop remote coating capability for HTGR fuel particles

International Nuclear Information System (INIS)

Suchomel, R.R.; Stinton, D.P.; Preston, M.K.; Heck, J.L.; Bolfing, B.J.; Lackey, W.J.

1978-12-01

Refabrication of HTGR fuels is a manufacturing process that consists of preparation of fuel kernels, application of multiple layers of pyrolytic carbon and silicon carbide, preparation of fuel rods, and assembly of fuel rods into fuel elements. All the equipment for refabrication of 233 U-containing fuel must be designed for completely remote operation and maintenance in hot-cell facilities. Equipment to remotely coated HTGR fuel particles has been designed and operated. Although not all of the equipment development needed for a fully remote coating system has been completed, significant progress has been made. The most important component of the coating furnace is the gas distributor, which must be simple, reliable, and easily maintainable. Techniques for loading and unloading the coater and handling microspheres have been developed. An engineering-scale system, currently in operation, is being used to verify the workability of these concepts. Coating crucible handling components are used to remove the crucible from the furnace, remove coated particles, and exchange the crucible, if necessary. After the batch of particles has been unloaded, it is transferred, weighed, and sampled. The components used in these processes have been tested to ensure that no particle breakage or holdup occurs. Tests of the particle handling system have been very encouraging because no major problems have been encountered. Instrumentation that controls the equipment performed very smoothly and reliably and can be operated remotely

A procedure for routine radiation protection checking of mammography equipment

International Nuclear Information System (INIS)

Bengtsson, L.G.; Lundehn, I.

1980-01-01

A procedure was developed for checking of mammography equipment used in screening for mammary cancer. The procedure will be handled by hospital physicists or x-ray inspectors and is intended to permit checking of x-ray equipment performance as well as evaluation of mean dose or eneray imparted to groups of patients. Measurement methods studied involve TLD, ionization chambers and a new plastic scintillator designed to measure energy imparted. After careful study of sizes and attenuation properties of breasts, a 50 mm polymethylmetacrylate phantom seemed the most appropriate. The choice of measuring equipment is reported as well as some preliminary results from field measurements. (author)

Conceptual design of divertor cassette handling by remote handling system for JT-60SA

International Nuclear Information System (INIS)

Hayashi, Takao; Sakurai, Shinji; Masaki, Kei; Tamai, Hiroshi; Yoshida, Kiyoshi; Matsukawa, Makoto

2007-01-01

The JT-60SA aims to contribute and supplement ITER toward DEMO reactor based on tokamak concept. One of the features of JT-60SA is its high power long pulse heating, causing the large annual neutron fluence. Because the expected dose rate at the vacuum vessel (VV) may exceed 1 mSv/hr after 10 years operation and three month cooling, the human access inside the VV is prohibited. Therefore a remote handling (RH) system is necessary for the maintenance and repair of in-vessel components. This paper described the RH system of JT-60SA, especially the expansion of the RH rail and exchange of the divertor modules. The RH rail is divided into nine and three-point mounting. The nine sections can cover 225 degrees in toroidal direction. A divertor module, which is 10 degrees wide in toroidal direction and weighs 500kg itself due to the limitations of port width and handling weight, can be exchanged by heavy weight manipulator (HWM). The HWM brings the divertor module to the front of the other RH port, which is used for supporting the rail and/or carrying in and out equipments. Then another RH device receives and brings out the module by a pallet installed from outside the VV. (author)

Conceptual design of divertor cassette handling by remote handling system of JT-60SA

International Nuclear Information System (INIS)

Hayashi, Takao; Sakurai, Shinji; Masaki, Kei; Tamai, Hiroshi; Yoshida, Kiyoshi; Matsukawa, Makoto

2008-01-01

The JT-60SA aims to contribute and supplement ITER toward demonstration fusion reactor based on tokamak concept. One of the features of JT-60SA is its high power long pulse heating, causing the large annual neutron fluence. Because the expected dose rate at the vacuum vessel (VV) may exceed 1 mSv/hr after 10 years operation and three month cooling, the human access inside the VV is restricted. Therefore a remote handling (RH) system is necessary for the maintenance and repair of in-vessel components. This paper described the RH system of JT-60SA, especially the expansion of the RH rail and exchange of the divertor cassettes. The RH rail is divided into nine and three-point mounting. The nine sections can cover 225 degrees in toroidal direction. A divertor cassette, which is 10 degrees wide in toroidal direction and weighs 500 kg itself due to the limitations of port width and handling weight, can be exchanged by heavy weight manipulator (HWM). The HWM brings the divertor cassette to the front of the other RH port, which is used for supporting the rail and/or carrying in and out equipments. Then another RH device receives and brings out the cassette by a pallet installed from outside the VV. (author)

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

Equipment experience in a radioactive LFCM [liquid-fed ceramic melter] vitrification facility

International Nuclear Information System (INIS)

Holton, L.K. Jr.; Dierks, R.D.; Sevigny, G.J.; Goles, R.W.; Surma, J.E.; Thomas, N.M.

1986-11-01

Since October 1984, the Pacific Northwest Laboratory (PNL) has operated a pilot-scale radioactive liquid-fed ceramic melter (RLFCM) vitrification process in shielded manipulator hot cells. This vitrification facility is being operated for the Department of Energy (DOE) to remotely test vitrification equipment components in a radioactive environment and to develop design and operation data that can be applied to production-scale projects. This paper summarizes equipment and process experience obtained from the operations of equipment systems for waste feeding, waste vitrification, canister filling, canister handling, and vitrification off-gas treatment

Adverse risk: a 'dynamic interaction model of patient moving and handling'.

Science.gov (United States)

Griffiths, Howard

2012-09-01

The aim of the present study was to examine patient adverse events associated with sub-optimal patient moving and handling. Few studies have examined the patient's perspective on adverse risk during manual handling episodes. A narrative review was undertaken to develop the 'Dynamic Interaction Model of Patient Moving and Handling' in an orthopaedic rehabilitation setting, using peer-reviewed publications published in English between 1992 and 2010. Five predominant themes emerged from the narrative review: 'patient's need to know about analgesics prior to movement/ambulation'; 'comfort care'; 'mastery of and acceptance of mobility aids/equipment'; 'psychological adjustment to fear of falling'; and 'the need for movement to prevent tissue pressure damage'. Prevalence of discomfort, pain, falls, pressure sores together with a specific Direct Instrument Nursing Observation (DINO) tool enable back care advisers to measure quality of patient manual handling. Evaluation of patients' use of mobility aids together with fear of falling may be important in determining patients' recovery trajectory. Clinical governance places a responsibility on nurse managers to consider quality of care for their service users. 'Dynamic Interaction Model of Nurse-Patient Moving and Handling' provides back care advisers, clinical risk managers and occupational health managers with an alternative perspective to clinical risk and occupational risk. © 2011 Blackwell Publishing Ltd.

Spent nuclear fuel retrieval system fuel handling development testing. Final report

International Nuclear Information System (INIS)

Jackson, D.R.; Meeuwsen, P.V.

1997-09-01

Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project, a subtask of the Spent Nuclear Fuel Project at the Hanford Site in Richland, Washington. The FRS will be used to retrieve and repackage K-Basin Spent Nuclear Fuel (SNF) currently stored in old K-Plant storage basins. The FRS is required to retrieve full fuel canisters from the basin, clean the fuel elements inside the canister to remove excessive uranium corrosion products (or sludge), remove the contents from the canisters and sort the resulting debris, scrap, and fuel for repackaging. The fuel elements and scrap will be collected in fuel storage and scrap baskets in preparation for loading into a multi canister overpack (MCO), while the debris is loaded into a debris bin and disposed of as solid waste. This report describes fuel handling development testing performed from May 1, 1997 through the end of August 1997. Testing during this period was mainly focused on performance of a Schilling Robotic Systems' Conan manipulator used to simulate a custom designed version, labeled Konan, being fabricated for K-Basin deployment. In addition to the manipulator, the camera viewing system, process table layout, and fuel handling processes were evaluated. The Conan test manipulator was installed and fully functional for testing in early 1997. Formal testing began May 1. The purposes of fuel handling development testing were to provide proof of concept and criteria, optimize equipment layout, initialize the process definition, and identify special needs/tools and required design changes to support development of the performance specification. The test program was set up to accomplish these objectives through cold (non-radiological) development testing using simulated and prototype equipment

Interim report spent nuclear fuel retrieval system fuel handling development testing

Energy Technology Data Exchange (ETDEWEB)

Ketner, G.L.; Meeuwsen, P.V.; Potter, J.D.; Smalley, J.T.; Baker, C.P.; Jaquish, W.R.

1997-06-01

Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project at the Hanford Site. The project will retrieve spent nuclear fuel, clean and remove fuel from canisters, repackage fuel into baskets, and load fuel into a multi-canister overpack (MCO) for vacuum drying and interim dry storage. The FRS is required to retrieve basin fuel canisters, clean fuel elements sufficiently of uranium corrosion products (or sludge), empty fuel from canisters, sort debris and scrap from whole elements, and repackage fuel in baskets in preparation for MCO loading. The purpose of fuel handling development testing was to examine the systems ability to accomplish mission activities, optimization of equipment layouts for initial process definition, identification of special needs/tools, verification of required design changes to support performance specification development, and validation of estimated activity times/throughput. The test program was set up to accomplish this purpose through cold development testing using simulated and prototype equipment; cold demonstration testing using vendor expertise and systems; and graphical computer modeling to confirm feasibility and throughput. To test the fuel handling process, a test mockup that represented the process table was fabricated and installed. The test mockup included a Schilling HV series manipulator that was prototypic of the Schilling Hydra manipulator. The process table mockup included the tipping station, sorting area, disassembly and inspection zones, fuel staging areas, and basket loading stations. The test results clearly indicate that the Schilling Hydra arm cannot effectively perform the fuel handling tasks required unless it is attached to some device that can impart vertical translation, azimuth rotation, and X-Y translation. Other test results indicate the importance of camera locations and capabilities, and of the jaw and end effector tool design. 5 refs., 35 figs., 3 tabs.

Gender difference in safe and unsafe practice of pesticide handling in tobacco farmers of malaysia.

Science.gov (United States)

Bin Nordin, R; Araki, S; Sato, H; Yokoyama, K; Bin Wan Muda, W A; Win Kyi, D

2001-01-01

To identify gender difference in safe and unsafe practice of pesticide handling in tobacco farmers of Malaysia, we conducted a 20-item questionnaire interview on storage of pesticide (4 questions), mixing of pesticide (3 questions), use of personal protective equipment and clothing while spraying pesticide (7 questions), activities during and after spraying of pesticide (5 questions), and maintenance of pesticide sprayer (1 question) in 496 tobacco farmers (395 males and 101 females) in Bachok District, Kelantan, Malaysia. Duration of employment was significantly longer in females than those in males (pwork habit, (3) reading and following instructions on pesticide label, (4) security, storage and disposal of pesticide container, (5) safe work habit, (6) proper handling of pesticide and maintenance of pesticide sprayer, (7) use of personal protective clothing, and (8) safe handling of pesticide. Results of analysis of covariance for the eight factor scores of all male and female farmers, controlling for educational level and duration of employment, showed that: (1) factor scores for use of personal protective equipment (pwork habit (p0.05). We therefore conclude that: (1) for female tobacco farmers, choice of personal attire tend to result in lower scores on use of personal protective equipment and personal protective clothing while personal hygiene practices result in lower score on safe work habit; and, (2) for male tobacco farmers, the lower scores on reading and following instruction on pesticide label and mixing pesticide and maintenance of pesticide sprayer in good condition suggests that they were not primarily involved in these activities. It is postulated that these differences in safe and unsafe practices of pesticide handling across gender is related to the choice of personal attire, personal hygiene practices and division of labour within farming households which in turn is influenced by prevailing sociocultural norms in the community.

Systematic review of patient handling activities starting in lying, sitting and standing positions.

Science.gov (United States)

Hignett, Sue

2003-03-01

Over the last 20 years a number of methods have been recommended in professional guidelines for moving patients. This review was undertaken as it was recognized that there was a need for clinical work involving handling patients (systems of work and equipment) to be based on scientific evidence. The aim of this paper is to report the methodology, search strategy and results relating to work involving the care, treatment and transfer of patients starting in lying, sitting and standing positions. An unusual philosophical stance has been taken by appraising studies within a study type rather than comparatively. This facilitated the inclusion of a wide range of study designs (quantitative and qualitative). A string search was run on eight databases and supplemented by other search strategies. A published checklist was selected and inter-rater reliability established before the main review commenced. A systematic process for inclusion, exclusion, appraisal, extraction and synthesis was undertaken. Thirty-two studies were included: nine for activities with the patient starting in a lying position and 23 for the sitting position. No studies were found with respect to patient handling activities starting in a standing position. These data were synthesized into evidence statements. The evidence statements support the use of hoists (for nonweight bearing patients), standaids, sliding sheets (double thickness rollers), lateral transfer boards, walking belts and adjustable height beds and baths. It is suggested that these items should constitute a minimum equipment list for any clinical environment where patient handling takes place on a regular basis. The lack of research relating to patient handling in standing is of particular concern and it is recommended that this area should be a high research priority to address concerns about patient handling in rehabilitation activities.

Report on coal refining and chemical equipment analogous to coal liquefaction equipment in fiscal 1981. Maintenance of equipment for direct desulfurization, indirect desulfurization, and fluidized catalytic cracking; 1981 nendo sekitan ekika ruiji seiyu seisei oyobi kagaku sochi ni kansuru chosa hokokusho. Chokudatsu, kandatsu, ryudo sesshoku bunkai sochi no hozen

Energy Technology Data Exchange (ETDEWEB)

NONE

1981-07-01

This questionnaire survey was intended to investigate the actual state of maintenance such as materials used, conditions for use, anti-corrosion measures, and cases and handling of damage, concerning primary apparatus in the direct/indirect desulfurization equipment and the fluidized catalytic crackers, which are owned by each oil refinery and which are analogous to coal liquefaction equipment. The questionnaire was intended for the following equipment and apparatus, with the actual state of their maintenance investigated. 1. Questionnaire concerning maintenance of direct desulfurization (reactor, high temperature separation tank, material furnace tube, reactor exit piping, high temperature heat exchanger, low temperature heat exchanger, and pressure reducing valve), 2. Questionnaire concerning maintenance of indirect desulfurization (reactor, high temperature separation tank, material furnace tube, reactor exit piping, high temperature heat exchanger, low temperature heat exchanger, and pressure reducing valve), 3. Questionnaire concerning maintenance of fluidized catalytic cracker (reactor, regeneration tower, riser pipe, and fractionator bottom pump). The questionnaire this time was distributed to 27 domestic oil companies, with the reply received from 23 of them. The replies were summarized by each type of equipment. Shown at the back of the report were the cases of damage and handling in FCC's and reactors. (NEDO)

Progress in standardization for ITER Remote Handling control system

International Nuclear Information System (INIS)

Hamilton, David Thomas; Tesini, Alessandro; Ranz, Roberto; Kozaka, Hiroshi

2014-01-01

Graphical abstract: - Highlights: • Standard parts specified for ITER Remote Handling (RH) control system. • Standard approach for VR modeling of structural deformations in real-time. • RH Core System produced as standard platform for RH controller applications. • Synthetic Viewing investigated and demonstrated. • Structured language defined for RH operation procedures and motion sequences. - Abstract: An integrated control system architecture has been defined for the ITER Remote Handling (RH) equipment systems, and work has been continuing to develop and validate standards for this architecture. Evaluations of standard parts and a standard control room work-cell have contributed to an update of the RH Control System Design Handbook, while R and D activities have been carried out to validate concepts for standard solutions to ITER RH problems: the use of a standard master arm with different slave arms, the achievement of high accuracy tracking of RH operations within virtual reality, and condition monitoring of RH equipment systems. The standardization efforts have been consolidated through the development of a freely distributable software platform to support the adoption of the ITER RH standards. The RH Core System installs on top of the CODAC Core System and provides the basic platform for the development of ITER RH equipment controller applications. The standardization work has continued in the areas of RH viewing, network communication protocols, and a structured language for programming ITER RH operations. Prototyping has been done on high-level control system applications, and R and D has been carried out in the area of synthetic viewing for ITER RH. These developments will be reflected in a new version of the RH Core System to be produced during 2013

Progress in standardization for ITER Remote Handling control system

Energy Technology Data Exchange (ETDEWEB)

Hamilton, David Thomas, E-mail: david.hamilton@iter.org [ITER Organization, Route de Vinon, 13115 St. Paul-lez-Durance (France); Tesini, Alessandro [ITER Organization, Route de Vinon, 13115 St. Paul-lez-Durance (France); Ranz, Roberto [Fusion for Energy, Torres Diagonal Litoral B3, Josep Pla 2, 08019 Barcelona (Spain); Kozaka, Hiroshi [Japan Atomic Energy Agency, Fusion Research and Development Directorate, Naka, Ibaraki-ken 311-0193 (Japan)

2014-10-15

Graphical abstract: - Highlights: • Standard parts specified for ITER Remote Handling (RH) control system. • Standard approach for VR modeling of structural deformations in real-time. • RH Core System produced as standard platform for RH controller applications. • Synthetic Viewing investigated and demonstrated. • Structured language defined for RH operation procedures and motion sequences. - Abstract: An integrated control system architecture has been defined for the ITER Remote Handling (RH) equipment systems, and work has been continuing to develop and validate standards for this architecture. Evaluations of standard parts and a standard control room work-cell have contributed to an update of the RH Control System Design Handbook, while R and D activities have been carried out to validate concepts for standard solutions to ITER RH problems: the use of a standard master arm with different slave arms, the achievement of high accuracy tracking of RH operations within virtual reality, and condition monitoring of RH equipment systems. The standardization efforts have been consolidated through the development of a freely distributable software platform to support the adoption of the ITER RH standards. The RH Core System installs on top of the CODAC Core System and provides the basic platform for the development of ITER RH equipment controller applications. The standardization work has continued in the areas of RH viewing, network communication protocols, and a structured language for programming ITER RH operations. Prototyping has been done on high-level control system applications, and R and D has been carried out in the area of synthetic viewing for ITER RH. These developments will be reflected in a new version of the RH Core System to be produced during 2013.

Development of nuclear fuel cycle remote handling technology

International Nuclear Information System (INIS)

Kim, K. H.; Park, B. S.; Kim, S. H.

2010-04-01

This report presents the development of remote handling systems and remote equipment for use in the pyprocessing verification at the PRIDE (PyRoprocess Integrated inactive Demonstration facility). There are three areas conducted in this work. In first area, developed were the prototypes of an engineering-scale high-throughput decladding voloxidizer which is capable of separating spent fuel rod-cuts into hulls and powder and collecting them separately and an automatic equipment which is capable of collecting residual powder remaining on separated hulls. In second area, a servo-manipulator prototype was developed to operate and maintain pyroprocess equipment located at the argon cell of the PRIDE in a remote manner. A servo-manipulator with dual arm that is mounted on the lower part of a bridge transporter will be installed on the ceiling of the in-cell and can travel the length of the ceiling. In last area, a simulator was developed to simulate and evaluate the design developments of the pyroprocess equipment from the in-cell arrangements, remote operability and maintainability viewpoint in a virtual process environment in advance before they are constructed. The developed decladding voloxidizer and automatic equipment will be utilized in the development of a head-end process for pyroprocessing. In addition, the developed servo-manipulator will be installed in the PRIDE and used for remote operation and maintenance of the pyroprocess equipment. The developed simulator will be also used to verify and improve the design of the pyroprocess equipment for the PRIDE application. Moreover, these remote technologies described above can be directly used in the PRIDE and applied for the ESPF (Engineering Scale Pyroprocess Facility) and KAPF (Korea Advanced Pyroprocess Facility) development

Automated handling for SAF batch furnace and chemistry analysis operations

International Nuclear Information System (INIS)

Bowen, W.W.; Sherrell, D.L.; Wiemers, M.J.

1981-01-01

The Secure Automated Fabrication Program is developing a remotely operated breeder reactor fuel pin fabrication line. The equipment will be installed in the Fuels and Materials Examination Facility being constructed at Hanford, Washington. Production is scheduled to start in mid-1986. The application of small pneumatically operated industrial robots for loading and unloading product into and out of batch furnaces and for distribution and handling of chemistry samples is described

Operating experience with remote handling equipment in a typical hot facility

International Nuclear Information System (INIS)

Ravishankar, A.; Balasubramanian, G.R.

1990-01-01

Large number of articulated arm manipulators and special purpose remote tools have been used either alone or in combination in a recent campaign of treatment of irradiated J rods of CIRUS for separation of 233 U. These equipments were used for operations such as remote maintenance of centrifuge, centrifugal extractor, direct sampling, assistance for sample conveying operations etc. Paper discusses problems encountered in using articulated arm manipulators of type MAll,AMl and how they were overcome. Problems encountered in use of model-8 manipulator for chopper maintenence in a mockup facility are also highlighted. (author). 4 figs., 1 tab

Applying remote handling attributes to the ITER neutral beam cell monorail crane

Energy Technology Data Exchange (ETDEWEB)

Crofts, O., E-mail: Oliver.Crofts@CCFE.ac.uk [CCFE, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Allan, P.; Raimbach, J. [CCFE, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Tesini, A.; Choi, C.-H. [ITER Organisation, CS90 046, 13067 St. Paul les Durance Cedex (France); Damiani, C.; Van Uffelen, M. [Fusion for Energy, C/Josep Pla 2, Torres Diagonal Litoral-B3, E-08019 Barcelona (Spain)

2013-10-15

The maintenance requirements for the equipment in the ITER neutral beam cell require components to be lifted and transported within the cell by remote means. To meet this requirement, the provision of an overhead crane with remote handling capabilities has been initiated. The layout of the cell has driven the design to consist of a monorail crane that travels on a branched monorail track attached to the cell ceiling. This paper describes the principle design constraints and how the remote handling attributes were applied to the concept design of the monorail crane, concentrating on areas where novel design solutions have been required and on the remote recovery requirements and solutions.

Applying remote handling attributes to the ITER neutral beam cell monorail crane

International Nuclear Information System (INIS)

Crofts, O.; Allan, P.; Raimbach, J.; Tesini, A.; Choi, C.-H.; Damiani, C.; Van Uffelen, M.

2013-01-01

The maintenance requirements for the equipment in the ITER neutral beam cell require components to be lifted and transported within the cell by remote means. To meet this requirement, the provision of an overhead crane with remote handling capabilities has been initiated. The layout of the cell has driven the design to consist of a monorail crane that travels on a branched monorail track attached to the cell ceiling. This paper describes the principle design constraints and how the remote handling attributes were applied to the concept design of the monorail crane, concentrating on areas where novel design solutions have been required and on the remote recovery requirements and solutions

Remote handling and automation in back end of fuel cycle

International Nuclear Information System (INIS)

Nair, K.N.S.

2010-01-01

Full text: Indian nuclear programme is readying for a quantum leap and it is essential that technology is available for building advanced fuel recycle plants in the back end and for sustained operation of such plants. Remote technology and automation plays a big role to achieve this goal. With the introduction of advanced fuel cycles in indigenous programme and scenario of international cooperation it is essential to be ready with indigenous technology for meeting all challenges. Work has been progressing to develop locally support technology for remote handling and automation with good success. Essential RH tools such as master slave manipulators, power manipulators and hot cell viewing systems have been developed and commercial production has been established. Customised RH requirements for back end plants have been met and the designs have proven to be worthy for hot operations over the years. In the last few years stress has been on development of equipment and technology to meet the increasing demands of higher throughput plants. Substantial progress has been achieved in the head end and reconversion laboratory systems of reprocessing plants. Similarly successful efforts have also been made for establishing Thoria processing cells and also the RH in the reconversion operations. Custom designed equipment has been developed for decommissioning of ceramic melter, used glove boxes etc. Efforts are on hand to develop automated RH equipment for material handling in underground repositories. This paper aims at bringing out the theme based on some of our own experiences and some reports from plants in operation abroad. (author)

Unvented Drum Handling Plan

International Nuclear Information System (INIS)

MCDONALD, K.M.

2000-01-01

This drum-handling plan proposes a method to deal with unvented transuranic drums encountered during retrieval of drums. Finding unvented drums during retrieval activities was expected, as identified in the Transuranic (TRU) Phase I Retrieval Plan (HNF-4781). However, significant numbers of unvented drums were not expected until excavation of buried drums began. This plan represents accelerated planning for management of unvented drums. A plan is proposed that manages unvented drums differently based on three categories. The first category of drums is any that visually appear to be pressurized. These will be vented immediately, using either the Hanford Fire Department Hazardous Materials (Haz. Mat.) team, if such are encountered before the facilities' capabilities are established, or using internal capabilities, once established. To date, no drums have been retrieved that showed signs of pressurization. The second category consists of drums that contain a minimal amount of Pu isotopes. This minimal amount is typically less than 1 gram of Pu, but may be waste-stream dependent. Drums in this category are assayed to determine if they are low-level waste (LLW). LLW drums are typically disposed of without venting. Any unvented drums that assay as TRU will be staged for a future venting campaign, using appropriate safety precautions in their handling. The third category of drums is those for which records show larger amounts of Pu isotopes (typically greater than or equal to 1 gram of Pu). These are assumed to be TRU and are not assayed at this point, but are staged for a future venting campaign. Any of these drums that do not have a visible venting device will be staged awaiting venting, and will be managed under appropriate controls, including covering the drums to protect from direct solar exposure, minimizing of container movement, and placement of a barrier to restrict vehicle access. There are a number of equipment options available to perform the venting. The

Thermodynamic processes associated with frostbite in the handling of liquid nitrogen

Science.gov (United States)

Johnson, W. L.; Cook, C. R.

2014-01-01

It is often taught that exposure to liquid nitrogen will cause frostbite or more severe damage to exposed skin tissue. However, it is also demonstrated that a full hand can be briefly immersed in liquid nitrogen without damage. To better understand and possibly visualize the effects of human tissue exposure to liquid nitrogen, a series of tests were conducted using simulated hands and arms composed of molded gelatin forms. The simulated hands and arms were immersed, sprayed, or splashed with liquid nitrogen both with and without state of the art personal protective equipment. Thermocouples were located within the test articles to allow for thermal mapping during the freezing process. The study is aimed to help understand frostbite hazards and the time constants involved with the handling of liquid nitrogen to improve future safety protocols for the safe handling of cryogenic fluids. Results of the testing also show the limits to handling liquid nitrogen while using various means of protection.

Thermodynamic processes associated with frostbite in the handling of liquid nitrogen

Energy Technology Data Exchange (ETDEWEB)

Johnson, W. L. [Cryogenics Test Laboratory, NASA Kennedy Space Center, Kennedy Space Center, FL, 32899 (United States); Cook, C. R. [Dept. Mechanical and Aerospace Engineering, University of Florida, Gainesville, FL, 32611 (United States)

2014-01-29

It is often taught that exposure to liquid nitrogen will cause frostbite or more severe damage to exposed skin tissue. However, it is also demonstrated that a full hand can be briefly immersed in liquid nitrogen without damage. To better understand and possibly visualize the effects of human tissue exposure to liquid nitrogen, a series of tests were conducted using simulated hands and arms composed of molded gelatin forms. The simulated hands and arms were immersed, sprayed, or splashed with liquid nitrogen both with and without state of the art personal protective equipment. Thermocouples were located within the test articles to allow for thermal mapping during the freezing process. The study is aimed to help understand frostbite hazards and the time constants involved with the handling of liquid nitrogen to improve future safety protocols for the safe handling of cryogenic fluids. Results of the testing also show the limits to handling liquid nitrogen while using various means of protection.

Thermodynamic processes associated with frostbite in the handling of liquid nitrogen

International Nuclear Information System (INIS)

Johnson, W. L.; Cook, C. R.

2014-01-01

It is often taught that exposure to liquid nitrogen will cause frostbite or more severe damage to exposed skin tissue. However, it is also demonstrated that a full hand can be briefly immersed in liquid nitrogen without damage. To better understand and possibly visualize the effects of human tissue exposure to liquid nitrogen, a series of tests were conducted using simulated hands and arms composed of molded gelatin forms. The simulated hands and arms were immersed, sprayed, or splashed with liquid nitrogen both with and without state of the art personal protective equipment. Thermocouples were located within the test articles to allow for thermal mapping during the freezing process. The study is aimed to help understand frostbite hazards and the time constants involved with the handling of liquid nitrogen to improve future safety protocols for the safe handling of cryogenic fluids. Results of the testing also show the limits to handling liquid nitrogen while using various means of protection

The Petroleum Handling Equipment Research and Development Program of the Department of the Army

National Research Council Canada - National Science Library

1956-01-01

.... The various Technical Services have made very significant progress in the development of improved equipment and techniques for storing, transporting, dispensing and testing fuels and lubricants...

Fuel handling system of Indian 500 MWe PHWR-evolution and innovations

International Nuclear Information System (INIS)

Sanatkumar, A.; Jit, I.; Muralidhar, G.

1996-01-01

India has gained rich experience in design, manufacture, testing, operation and maintenance of the Fuel Handling System of CANDU type PHWRs. When design and layout of the first 500 MWe PHWR was being evolved, it was possible for us to introduce many special and innovative features in the Fuel Handling System which are friendly for operations and maintenance personnel. Some of these are: Simple, robust and modular mechanisms for ease of maintenance; Shorter turnaround time for refuelling a channel by introduction of transit equipment between the Fuelling Machine (FM) Head and light water equipment; Optimised layout to transport spent fuel in straight and short path and also to facilitate direct wheeling out of the FM Head from the Reactor Building to the Service Building; Provision to operate the FM Head even when the Primary Heat Transport (PHT) System is open for maintenance; Control-console engineered for carrying out refuelling operations in the sitting position; and, Dedicated calibration and maintenance facility to facilitate quick replacement of the FM Head as a single unit. The above special features have been described in this paper. (author). 7 figs

Fuel handling system of Indian 500 MWe PHWR-evolution and innovations

Energy Technology Data Exchange (ETDEWEB)

Sanatkumar, A; Jit, I; Muralidhar, G [Nuclear Power Corporation of India Ltd., Mumbai (India)

1997-12-31

India has gained rich experience in design, manufacture, testing, operation and maintenance of the Fuel Handling System of CANDU type PHWRs. When design and layout of the first 500 MWe PHWR was being evolved, it was possible for us to introduce many special and innovative features in the Fuel Handling System which are friendly for operations and maintenance personnel. Some of these are: Simple, robust and modular mechanisms for ease of maintenance; Shorter turnaround time for refuelling a channel by introduction of transit equipment between the Fuelling Machine (FM) Head and light water equipment; Optimised layout to transport spent fuel in straight and short path and also to facilitate direct wheeling out of the FM Head from the Reactor Building to the Service Building; Provision to operate the FM Head even when the Primary Heat Transport (PHT) System is open for maintenance; Control-console engineered for carrying out refuelling operations in the sitting position; and, Dedicated calibration and maintenance facility to facilitate quick replacement of the FM Head as a single unit. The above special features have been described in this paper. (author). 7 figs.

New System For Tokamak T-10 Experimental Data Acquisition, Data Handling And Remote Access

International Nuclear Information System (INIS)

Sokolov, M. M.; Igonkina, G. B.; Koutcherenko, I. Yu.; Nurov, D. N.

2008-01-01

For carrying out the experiments on nuclear fusion devices in the Institute of Nuclear Fusion, Moscow, a system for experimental data acquisition, data handling and remote access (further 'DAS-T10') was developed and has been used in the Institute since the year 2000. The DAS-T10 maintains the whole cycle of experimental data handling: from configuration of data measuring equipment and acquisition of raw data from the fusion device (the Device), to presentation of math-processed data and support of the experiment data archive. The DAS-T10 provides facilities for the researchers to access the data both at early stages of an experiment and well afterwards, locally from within the experiment network and remotely over the Internet.The DAS-T10 is undergoing a modernization since the year 2007. The new version of the DAS-T10 will accommodate to modern data measuring equipment and will implement improved architectural solutions. The innovations will allow the DAS-T10 to produce and handle larger amounts of experimental data, thus providing the opportunities to intensify and extend the fusion researches. The new features of the DAS-T10 along with the existing design principles are reviewed in this paper

Challenges and innovative technologies on fuel handling systems for future sodium-cooled fast reactors

International Nuclear Information System (INIS)

Chassignet, Mathieu; Dumas, Sebastien; Penigot, Christophe; Prele, Gerard; Capitaine, Alain; Rodriguez, Gilles; Sanseigne, Emmanuel; Beauchamp, Francois

2011-01-01

The reactor refuelling system provides the means of transporting, storing, and handling reactor core subassemblies. The system consists of the facilities and equipment needed to accomplish the scheduled refuelling operations. The choice of a FHS impacts directly on the general design of the reactor vessel (primary vessel, storage, and final cooling before going to reprocessing), its construction cost, and its availability factor. Fuel handling design must take into account various items and in particular operating strategies such as core design and management and core configuration. Moreover, the FHS will have to cope with safety assessments: a permanent cooling strategy to prevent fuel clad rupture, plus provisions to handle short-cooled fuel and criteria to ensure safety during handling. In addition, the handling and elimination of residual sodium must be investigated; it implies specific cleaning treatment to prevent chemical risks such as corrosion or excess hydrogen production. The objective of this study is to identify the challenges of a SFR fuel handling system. It will then present the range of technical options incorporating innovative technologies under development to answer the GENERATION IV SFR requirements. (author)

Discovery Mondays: Transporting tonnes of equipment with millimetre precision

CERN Multimedia

2005-01-01

Transporting huge, very heavy but also frequently fragile items at CERN often presents a real challenge. The task becomes even more challenging when it involves lowering huge LHC machine and detector components 100 metres below ground. The Laboratory's Transport Service uses various techniques and different types of transport and heavy handling equipment to perform these delicate operations. You will have an opportunity to find out more about how they do their job at the next Discovery Monday event. You will have a close encounter with the trailer used to transport the impressive 15 metre-long, 35-tonne dipole magnets. You will be able to install mock-up magnets in a beam line or test your skill using heavy handling equipment to carry out a most unusual fishing operation. You will be able to take a trip in a three-metre-high lorry and have a once-in-a-lifetime opportunity to operate a crane. You will also be able to take a test drive in the famous roll-over simulator vehicle. At the coming Discovery Monday...

Plutonium stabilization and handling quality assurance program plan

International Nuclear Information System (INIS)

Weiss, E.V.

1998-01-01

This Quality Assurance Program Plan (QAPP) identifies project quality assurance requirements for all contractors involved in the planning and execution of Hanford Site activities for design, procurement, construction, testing and inspection for Project W-460, Plutonium Stabilization and Handling. The project encompasses procurement and installation of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing special nuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM

Development of the Simulation Program for the In-Vessel Fuel Handling System of Double Rotating Plug Type

International Nuclear Information System (INIS)

Kim, S. H.; Kim, J. B.

2011-01-01

In-vessel fuel handling machines are the main equipment of the in-vessel fuel handling system, which can move the core assembly inside the reactor vessel along with the rotating plug during refueling. The in vessel fuel handling machines for an advanced sodium cooled fast reactor(SFR) demonstration plant are composed of a direct lift machine(DM) and a fixed arm machine(FM). These machines should be able to access all areas above the reactor core by means of the rotating combination of double rotating plugs. Thus, in the in vessel fuel handling system of the double rotating plug type, it is necessary to decide the rotating plug size and evaluate the accessibility of in-vessel fuel handling machines in given core configuration. In this study, the simulation program based on LABVIEW which can effectively perform the arrangement design of the in vessel fuel handling system and simulate the rotating plug motion was developed. Fig. 1 shows the flow chart of the simulation program

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

Science.gov (United States)

Nowakowski, Piotr

2016-11-01

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

Do Technical Aids for Patient Handling Prevent Musculoskeletal Complaints in Health Care Workers?—A Systematic Review of Intervention Studies

Directory of Open Access Journals (Sweden)

Janice Hegewald

2018-03-01

Full Text Available The physical load ensuing from the repositioning and moving of patients puts health care workers at risk of musculoskeletal complaints. Technical equipment developed to aid with patient handling should reduce physical strain and workload; however, the efficacy of these aids in preventing musculoskeletal disorders and complaints is still unclear. A systematic review of controlled intervention studies was conducted to examine if the risk of musculoskeletal complaints and disorders is reduced by technical patient handling equipment. MEDLINE®/PubMed®, EMBASE®, Allied and Complementary Medicine Database (AMED, and Cumulative Index of Nursing and Allied Health Literature (CINAHL® were searched using terms for nursing, caregiving, technical aids, musculoskeletal injuries, and complaints. Randomized controlled trials and controlled before-after studies of interventions including technical patient handling equipment were included. The titles and abstracts of 9554 publications and 97 full-texts were screened by two reviewers. The qualitative synthesis included one randomized controlled trial (RCT and ten controlled before-after studies. A meta-analysis of four studies resulted in a pooled risk ratio for musculoskeletal injury claims (post-intervention of 0.78 (95% confidence interval 0.68–0.90. Overall, the methodological quality of the studies was poor and the results often based on administrative injury claim data, introducing potential selection bias. Interventions with technical patient handling aids appear to prevent musculoskeletal complaints, but the certainty of the evidence according to GRADE approach ranged from low to very low.

Shielded enclosure for handling radioactive material

International Nuclear Information System (INIS)

Laurent, H.; Courouble, J.M.

1959-01-01

Two enclosures linked by an air-lock are described: they are designed for the safe handling of 5 curies 0.3 to 0.5 MeV γ emitters, and each is composed of a semi-tight case, ventilated, clad in 80 mm steel plate, and suited for a wide variety of physics and chemistry operations. The equipment required for any given operation can be installed in the shortest possible time, access to the enclosure being via a removable front. Visual control is assured through a lead-glass screen. Each enclosure is fitted with a master-slave manipulator, Argon model 7, and plugs and air-locks are provided for the introduction of liquids and solids. (author) [fr

Standard guide for hot cell specialized support equipment and tools

CERN Document Server

American Society for Testing and Materials. Philadelphia

2010-01-01

1.1 Intent: 1.1.1 This guide presents practices and guidelines for the design and implementation of equipment and tools to assist assembly, disassembly, alignment, fastening, maintenance, or general handling of equipment in a hot cell. Operating in a remote hot cell environment significantly increases the difficulty and time required to perform a task compared to completing a similar task directly by hand. Successful specialized support equipment and tools minimize the required effort, reduce risks, and increase operating efficiencies. 1.2 Applicability: 1.2.1 This guide may apply to the design of specialized support equipment and tools anywhere it is remotely operated, maintained, and viewed through shielding windows or by other remote viewing systems. 1.2.2 Consideration should be given to the need for specialized support equipment and tools early in the design process. 1.2.3 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conv...

Recent fuel handling experience in Canada

International Nuclear Information System (INIS)

Welch, A.C.

1991-01-01

For many years, good operation of the fuel handling system at Ontario Hydro's nuclear stations has been taken for granted with the unavailability of the station arising from fuel handling system-related problems usually contributing less than one percent of the total unavailability of the stations. While the situation at the newer Hydro stations continues generally to be good (with the specific exception of some units at Pickering B) some specific and some general problems have caused significant loss of availability at the older plants (Pickering A and Bruce A). Generally the experience at the 600 MWe units in Canada has also continued to be good with Point Lepreau leading the world in availability. As a result of working to correct identified deficiencies, there were some changes for the better as some items of equipment that were a chronic source of trouble were replaced with improved components. In addition, the fuel handling system has been used three times as a delivery system for large-scale non destructive examination of the pressure tubes, twice at Bruce and once at Pickering and performing these inspections this way has saved many days of reactor downtime. Under COG there are several programs to develop improved versions of some of the main assemblies of the fuelling machine head. This paper will generally cover the events relating to Pickering in more detail but will describe the problems with the Bruce Fuelling Machine Bridges since the 600 MW 1P stations have a bridge drive arrangement that is somewhat similar to Bruce

Remote handling assessment of attachment concepts for DEMO blanket segments

Energy Technology Data Exchange (ETDEWEB)

Iglesias, Daniel, E-mail: daniel.iglesias@ccfe.ac.uk [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Bastow, Roger; Cooper, Dave; Crowe, Robert; Middleton-Gear, Dave [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Sibois, Romain [VTT, Technical Research Centre of Finland, Industrial Systems, ROViR, Tampere (Finland); Carloni, Dario [Institute of Neutron Physics and Reactor Technology, Karlsruhe Institute of Technology (KIT) (Germany); Vizvary, Zsolt; Crofts, Oliver [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Harman, Jon [EFDA Close Support Unit Garching, Boltzmannstaße 2, D-85748 Garching bei München (Germany); Loving, Antony [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom)

2015-10-15

Highlights: • Challenges are identified for the remote handling of blanket segments’ attachments. • Two attachment design approaches are assessed for remote handling (RH) feasibility. • An alternative is proposed, which potentially simplifies and speeds-up RH operations. • Up to three different assemblies are proposed for the remote handling of the attachments. • Proposed integrated design of upper port is compatible with the attachment systems. - Abstract: The replacement strategy of the massive Multi-Module Blanket Segments (MMS) is a key driver in the design of several DEMO systems. These include the blankets themselves, the vacuum vessel (VV) and its ports and the Remote Maintenance System (RMS). Common challenges to any blanket attachment system have been identified, such as the need for applying a preload to the MMS manifold, the effects of the decay heat and several uncertainties related to permanent deformations when removing the blanket segments after service. The WP12 kinematics of the MMS in-vessel transportation was adapted to the requirements of each of the supports during 2013 and 2014 design activities. The RM equipment envisaged for handling attachments and earth connections may be composed of up to three different assemblies. An In-Vessel Mover at the divertor level handles the lower support and earth bonding, and could stabilize the MMS during transportation. A Shield Plug crane with a 6 DoF manipulator operates the upper attachment and earth straps. And a Vertical Maintenance Crane is responsible for the in-vessel MMS transportation and can handle the removable upper support pins. A final proposal is presented which can potentially reduce the number of required systems, at the same time that speeds-up the RMS global operations.

High level radioactive waste vitrification process equipment component testing

International Nuclear Information System (INIS)

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

1985-04-01

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

Specialized equipment needs for the transportation of radioactive material

International Nuclear Information System (INIS)

Condrey, D.; Lambert, M.

1998-01-01

To ensure the safe and reliable transportation of radioactive materials and components, from both the front and back-end of the nuclear fuel cycle, a transport management company needs three key elements: specialized knowledge, training and specialized equipment. These three elements result, in part, from national and international regulations which require specialized handling of all radioactive shipments. While the reasons behind the first two elements are readily apparent, the role of specialized equipment is often not considered until too late shipment process even though it plays an integral part of any radioactive material transport. This paper will describe the specialized equipment needed to transport three of the major commodities comprising the bulk of international nuclear transports: natural uranium (UF6), low enriched uranium (UF6) and fresh nuclear fuel. (authors)

Safe handling of cytotoxic compounds in a biopharmaceutical environment.

Science.gov (United States)

Hensgen, Miriam I; Stump, Bernhard

2013-01-01

Handling cytotoxic drugs such as antibody-drug conjugates (ADCs) in a biopharmaceutical environment represents a challenge based on the potency of the compounds. These derivatives are dangerous to humans if they accidentally get in contact with the skin, are inhaled, or are ingested, either as pure compounds in their solid state or as a solution dissolved in a co-solvent. Any contamination of people involved in the manufacturing process has to be avoided. On the other hand, biopharmaceuticals need to be protected simultaneously against any contamination from the manufacturing personnel. Therefore, a tailor-made work environment is mandatory in order to manufacture ADCs. This asks for appropriate technical equipment to keep potential hazardous substances contained. In addition, clearly defined working procedures based on risk assessments as well as proper training for all personnel involved in the manufacturing process are needed to safely handle these highly potent pharmaceuticals.

Study on new-type fuel-related assembly handling tools for PWR NPP

International Nuclear Information System (INIS)

Fan Xiumei

2013-01-01

This article describes the design and study on a set of new-type fuel-related assembly snatching tools used for PWR NPP. The purpose is mainly to enhance the tool safety, reliability and convenientness by improvement of the mechanism and structure of the tool for snatching preciseness and avoiding from falling and abrasion of fuel-related assemblies for any condition. The new-type fuel-related assembly handling tools are compared with similar equipment in worldwide in terms of function, main technical characteristic, and safety and protection, some of them are better than the similar equipment in that they have reliable loading and unloading and conveying capabilities. (author)

Concept study: Use of grout vaults for disposal of long-length contaminated equipment

International Nuclear Information System (INIS)

Clem, D.K.

1994-01-01

Study considers the potential for use of grout vaults for disposal of untreated long length equipment removed from waste tanks. Looks at ways to access vaults, material handling, regulatory aspects, and advantages and disadvantages of vault disposal

The establish and application of equipment reliability database in Nuclear Power Plant

International Nuclear Information System (INIS)

Zheng Wei; Li He

2006-03-01

Take the case of Daya Bay Nuclear Power Plant, the collecting and handling of equipment reliability data, the calculation method of reliability parameters and the establish and application of reliability databases, etc. are discussed. The data source involved the design information of the equipment, the operation information, the maintenance information and periodically test record, etc. Equipment reliability database built on a base of the operation experience. It provided the valid tool for thoroughly and objectively recording the operation history and the present condition of various equipment of the plant; supervising the appearance of the equipment, especially the safety-related equipment, provided the very practical worth information for enhancing the safety and availability management of the equipment and insuring the safety and economic operation of the plant; and provided the essential data for the research and applications in safety management, reliability analysis, probabilistic safety assessment, reliability centered maintenance and economic management in nuclear power plant. (authors)

Factors influencing oncology nurses' use of hazardous drug safe-handling precautions.

Science.gov (United States)

Polovich, Martha; Clark, Patricia C

2012-05-01

To examine relationships among factors affecting nurses' use of hazardous drug (HD) safe-handling precautions, identify factors that promote or interfere with HD precaution use, and determine managers' perspectives on the use of HD safe-handling precautions. Cross-sectional, mixed methods; mailed survey to nurses who handle chemotherapy and telephone interviews with managers. Mailed invitation to oncology centers across the United States. 165 nurses who reported handling chemotherapy and 20 managers of nurses handling chemotherapy. Instruments measured the use of HD precautions and individual and organizational factors believed to influence precaution use. Data analysis included descriptive statistics and hierarchical regression. Manager interview data were analyzed using content analysis. Chemotherapy exposure knowledge, self-efficacy, perceived barriers, perceived risk, interpersonal influences, and workplace safety climate. Nurses were well educated, experienced, and certified in oncology nursing. The majority worked in outpatient settings and administered chemotherapy to an average of 6.8 patients per day. Exposure knowledge, self-efficacy for using personal protective equipment, and perceived risk of harm from HD exposure were high; total precaution use was low. Nurse characteristics did not predict HD precaution use. Fewer barriers, better workplace safety climate, and fewer patients per day were independent predictors of higher HD precaution use. HD handling policies were present, but many did not reflect current recommendations. Few managers formally monitored nurses' HD precaution use. Circumstances in the workplace interfere with nurses' use of HD precautions. Interventions should include fostering a positive workplace safety climate, reducing barriers, and providing appropriate nurse-patient ratios.

Hot laboratory in Saclay. Equipment and radio-metallurgy technique of the hot lab in Saclay. Description of hot cell for handling of plutonium salts. Installation of an hot cell; Laboratoire a tres haute activite de Saclay. Equipement et techniques radiometallurgiques du laboratoire a haute activite de Saclay. Description de cellules pour manipulation de sels de plutonium. Amenagement d'une cellule du laboratoire de haute activite

Energy Technology Data Exchange (ETDEWEB)

Bazire, R; Blin, J; Cherel, G; Duvaux, Y; Cherel, G; Mustelier, J P; Bussy, P; Gondal, G; Bloch, J; Faugeras, P; Raggenbass, A; Raggenbass, P; Fufresne, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1959-07-01

Describes the conception and installation of the hot laboratory in Saclay (CEA, France). The construction ended in 1958. The main aim of this laboratory is to examine fuel rods of EL2 and EL3 as well as nuclear fuel studies. It is placed in between both reactors. In a first part, the functioning and specifications of the hot lab are given. The different hot cells are described with details of the ventilation and filtration system as well as the waste material and effluents disposal. The different safety measures are explained: description of the radiation protection, decontamination room and personnel monitoring. The remote handling equipment is composed of cutting and welding machine controlled with manipulators. Periscopes are used for sight control of the operation. In a second part, it describes the equipment of the hot lab. The unit for an accurate measurement of the density of irradiated uranium is equipped with an high precision balance and a thermostat. The equipment used for the working of irradiated uranium is described and the time length of each operation is given. There is also an installation for metallographic studies which is equipped with a manipulation bench for polishing and cleaning surfaces and a metallographic microscope. X-ray examination of uranium pellets will also be made and results will be compared with those of metallography. The last part describes the hot cells used for the manipulation of plutonium salts. The plutonium comes from the reprocessing plant and arrived as a nitric solution. Thus these cells are used to study the preparation of plutonium fluorides from nitric solution. The successive operations needed are explained: filtration, decontamination and extraction with TBP, purification on ion exchangers and finally formation of the plutonium fluorides. Particular attention has been given to the description of the specifications of the different gloveboxes and remote handling equipment used in the different reaction steps and

Hot laboratory in Saclay. Equipment and radio-metallurgy technique of the hot lab in Saclay. Description of hot cell for handling of plutonium salts. Installation of an hot cell; Laboratoire a tres haute activite de Saclay. Equipement et techniques radiometallurgiques du laboratoire a haute activite de Saclay. Description de cellules pour manipulation de sels de plutonium. Amenagement d'une cellule du laboratoire de haute activite

Energy Technology Data Exchange (ETDEWEB)

Bazire, R.; Blin, J.; Cherel, G.; Duvaux, Y.; Cherel, G.; Mustelier, J.P.; Bussy, P.; Gondal, G.; Bloch, J.; Faugeras, P.; Raggenbass, A.; Raggenbass, P.; Fufresne, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1959-07-01

Describes the conception and installation of the hot laboratory in Saclay (CEA, France). The construction ended in 1958. The main aim of this laboratory is to examine fuel rods of EL2 and EL3 as well as nuclear fuel studies. It is placed in between both reactors. In a first part, the functioning and specifications of the hot lab are given. The different hot cells are described with details of the ventilation and filtration system as well as the waste material and effluents disposal. The different safety measures are explained: description of the radiation protection, decontamination room and personnel monitoring. The remote handling equipment is composed of cutting and welding machine controlled with manipulators. Periscopes are used for sight control of the operation. In a second part, it describes the equipment of the hot lab. The unit for an accurate measurement of the density of irradiated uranium is equipped with an high precision balance and a thermostat. The equipment used for the working of irradiated uranium is described and the time length of each operation is given. There is also an installation for metallographic studies which is equipped with a manipulation bench for polishing and cleaning surfaces and a metallographic microscope. X-ray examination of uranium pellets will also be made and results will be compared with those of metallography. The last part describes the hot cells used for the manipulation of plutonium salts. The plutonium comes from the reprocessing plant and arrived as a nitric solution. Thus these cells are used to study the preparation of plutonium fluorides from nitric solution. The successive operations needed are explained: filtration, decontamination and extraction with TBP, purification on ion exchangers and finally formation of the plutonium fluorides. Particular attention has been given to the description of the specifications of the different gloveboxes and remote handling equipment used in the different reaction steps and

Experimental Research on the Determination of the Coefficient of Sliding Wear under Iron Ore Handling Conditions

Directory of Open Access Journals (Sweden)

G. Chen

2017-09-01

Full Text Available The handling of iron ore bulk solids maintains an increasing trend due to economic development. Because iron ore particles have hard composites and irregular shapes, the bulk solids handling equipment surface can suffer from severe sliding wear. Prediction of equipment surface wear volume is beneficial to the efficient maintenance of worn areas. Archard’s equation provides a theoretical solution to predict wear volume. To use Archard’s equation, the coefficient of sliding wear must be determined. To our best knowledge, the coefficient of sliding wear for iron ore handling conditions has not yet been determined. In this research, using a pin-on-disk tribometer, the coefficients of sliding wear for both Sishen particles and mild steel are determined with regard to iron ore handling conditions. Both naturally irregular and spherical shapes of particles are used to estimate average values of wear rate. Moreover, the hardness and inner structures of Sishen particles are examined, which adds the evidence of the interpretation of wear results. It is concluded that the coefficients of sliding wear can vary largely for both Sishen particle and mild steel. The wear rate decreases from transient- to steady-state. The average coefficient of sliding wear is capable of predicting wear with respect to long distances at the steady-state. Two types of sliding friction are distinguished. In addition, it is found that the temperature rise of the friction pairs has negligible influence on wear rate.

Applying HAZOP analysis in assessing remote handling compatibility of ITER port plugs

International Nuclear Information System (INIS)

Duisings, L.P.M.; Til, S. van; Magielsen, A.J.; Ronden, D.M.S.; Elzendoorn, B.S.Q.; Heemskerk, C.J.M.

2013-01-01

Highlights: ► We applied HAZOP analysis to assess the criticality of remote handling maintenance activities on port plugs in the ITER Hot Cell facility. ► We identified several weak points in the general upper port plug maintenance concept. ► We made clear recommendations on redesign in port plug design, operational sequence and Hot Cell equipment. ► The use of a HAZOP approach for the ECH UL port can also be applied to ITER port plugs in general. -- Abstract: This paper describes the application of a Hazard and Operability Analysis (HAZOP) methodology in assessing the criticality of remote handling maintenance activities on port plugs in the ITER Hot Cell facility. As part of the ECHUL consortium, the remote handling team at the DIFFER Institute is developing maintenance tools and procedures for critical components of the ECH Upper launcher (UL). Based on NRG's experience with nuclear risk analysis and Hot Cell procedures, early versions of these tool concepts and maintenance procedures were subjected to a HAZOP analysis. The analysis identified several weak points in the general upper port plug maintenance concept and led to clear recommendations on redesigns in port plug design, the operational sequence and ITER Hot Cell equipment. The paper describes the HAZOP methodology and illustrates its application with specific procedures: the Steering Mirror Assembly (SMA) replacement and the exchange of the Mid Shield Optics (MSO) in the ECH UPL. A selection of recommended changes to the launcher design associated with the accessibility, maintainability and manageability of replaceable components are presented

Remote handling of the blanket segments: testing of 1/3 scale mock-ups at the Robertino facility

International Nuclear Information System (INIS)

Maisonnier, D.; Amelotti, F.; Chiasera, A.; Gaggini, P.; Damiani, C.; Degli Esposti, L.; Gatti, G.; Castillo, E.; Caravati, D.; Farfalletti-Casali, F.; Gritzmann, P.; Ruiz, E.

1995-01-01

The remote replacement of blanket segments inside the vacuum vessel of a fusion reactor is probably the most complex task from the maintenance standpoint. Its success will rely on the definition of appropriate handling concepts and equipment, but also on a ''maintenance friendly'' reactor layout and blanket design. The key difficulty is the lack of rigidity of the segments which results in considerable deformations since they cannot be gripped above their centre of gravity. These deformations may be up to five times greater than the assembly clearance and one order of magnitude larger than the required positioning accuracy. Experimental activities have been undertaken to select appropriate handling devices and procedures, to assess the design of the components handled, and to review specific technical issues such as kinematics and dynamics performance, trajectory planning and control and sensors requirement for the handling devices. Work was performed in the Robertino facility where two handling concepts have been tested at a 1/3 scale. (orig.)

Evolution of the Darlington NGS fuel handling computer systems

International Nuclear Information System (INIS)

Leung, V.; Crouse, B.

1996-01-01

The ability to improve the capabilities and reliability of digital control systems in nuclear power stations to meet changing plant and personnel requirements is a formidable challenge. Many of these systems have high quality assurance standards that must be met to ensure adequate nuclear safety. Also many of these systems contain obsolete hardware along with software that is not easily transported to newer technology computer equipment. Combining modern technology upgrades into a system of obsolete hardware components is not an easy task. Lastly, as users become more accustomed to using modern technology computer systems in other areas of the station (e.g. information systems), their expectations of the capabilities of the plant systems increase. This paper will present three areas of the Darlington NGS fuel handling computer system that have been or are in the process of being upgraded to current technology components within the framework of an existing fuel handling control system. (author). 3 figs

Evolution of the Darlington NGS fuel handling computer systems

Energy Technology Data Exchange (ETDEWEB)

Leung, V; Crouse, B [Ontario Hydro, Bowmanville (Canada). Darlington Nuclear Generating Station

1997-12-31

The ability to improve the capabilities and reliability of digital control systems in nuclear power stations to meet changing plant and personnel requirements is a formidable challenge. Many of these systems have high quality assurance standards that must be met to ensure adequate nuclear safety. Also many of these systems contain obsolete hardware along with software that is not easily transported to newer technology computer equipment. Combining modern technology upgrades into a system of obsolete hardware components is not an easy task. Lastly, as users become more accustomed to using modern technology computer systems in other areas of the station (e.g. information systems), their expectations of the capabilities of the plant systems increase. This paper will present three areas of the Darlington NGS fuel handling computer system that have been or are in the process of being upgraded to current technology components within the framework of an existing fuel handling control system. (author). 3 figs.

Safety in handling helium and nitrogen

International Nuclear Information System (INIS)

Schmauch, G.; Lansing, L.; Santay, T.; Nahmias, D.

1991-01-01

Based upon the authors' industrial experience and practices, they have provided an overview of safety in storage, handling, and transfer of both laboratory and bulk quantities of gaseous and liquid forms of nitrogen and helium. They have addressed the properties and characteristics of both the gaseous and liquid fluids, typical storage and transport containers, transfer techniques, and the associated hazards which include low temperatures, high pressures, and asphyxiation. Methods and procedures to control and eliminate these hazards are described, as well as risk remediation through safety awareness training, personal protective equipment, area ventilation, and atmosphere monitoring. They have included as an example a recent process hazards analysis performed by Air Products on the asphyxiation hazard associated with the use of liquid helium in MRI magnet systems

Conceptual design of a test facility for the remote handling operations of the ITER Test Blanker Modules

International Nuclear Information System (INIS)

Marqueta, A.; Garcia, I.; Gomez, A.; Garcia, L.; Sedano, E.; Fernandez, I.

2012-01-01

Conceptual Design of a test facility for the remote handling operations of the ITER Test Blanket Modules. Conditions inside a fusion reactor are incompatible with conventional manual maintenance tasks. the same applies for ancillary equipment. As a consequence, it will become necessary to turn to remote visualization and remote handling techniques, which will have in consideration the extreme conditions, both physical and operating, of ITER. Main goal of the project has been the realization of the conceptual design for the test facility for the Test Blanket Modules of ITER and their associated systems, related to the Remote Handling operations regarding the Port Cell area. Besides the definition of the operations and the specification of the main components and ancillary systems of the TBM graphical simulation have been used for the design, verification and validation of the remote handling operations. (Author)

Development of remote handling technology for nuclear fuel cycle facilities in Japan

International Nuclear Information System (INIS)

Maekawa, Hiromichi; Sakai, Akira; Miura, Noriaki; Kozaka, Tetsuo; Hamada, Takashi

2015-01-01

Remote handling technology has been systematically developed for nuclear fuel cycle facilities in Japan since 1970s, primarily in parallel with the development of reprocessing and HLLW (High Level Liquid Waste) vitrification process. In case of reprocessing and vitrification process to handle highly radioactive and hazardous materials, the most of components are installed in the radiation shielded hot cells and operators are not allowed to enter the work area in the cells for operation and maintenance. Therefore, a completely remote handling system is adopted for the cells to reduce radiation doses of operators and increase the availability of the facility. The hot cells are generally designed considering the scale of components (laboratory, demonstration, or full-scale), the function of the systems (chemical process, material handling, dismantling, decontamination, or chemical analysis), and the environmental conditions (radiation dose rate, airborne concentration, surface contamination, or fume/mist/dust). Throughout our domestic development work for remote handling technology, the concept of the large scale integrated cell has been adopted rather than a number of small scale separated cells, for the reasons to reduce the total installation space and the number of remote handling equipment required for the each cell as much as possible. In our domestic remote maintenance design, several new concepts have been developed, tested, and demonstrated in the Tokai Virtrification Facility (TVF) and the Rokkasho HLLW Vitrification and Storage Facility (K-facility). Layout in the hot cells, the performance of remote handling equipment, and the structure of the in-cell components are important factors for remote maintenance design. In case of TVF (hot tests started in 1995), piping and vessels are prefabricated in the rack modules and installed in two lines on both sides of the cell. These modules are designed to be remotely replaced in the whole rack. Two overhead cranes

Handling and transport problems (1960)

International Nuclear Information System (INIS)

Pomarola, J.; Savouyaud, J.

1960-01-01

I. The handling and transport of radioactive wastes involves the danger of irradiation and contamination. It is indispensable: - to lay down a special set of rules governing the removal and transport of wastes within centres or from one centre to another; - to give charge of this transportation to a group containing teams of specialists. The organisation, equipment and output of these teams is being examined. II. Certain materials are particularly dangerous to transport, and for these special vehicles and fixed installations are necessary. This is the case especially for the evacuation of very active liquids. A transport vehicle is described, consisting of a trailer tractor and a recipient holding 500 litres of liquid of which the activity can reach 1000 C/l; the decanting operation, the route to be followed by the vehicle, and the precautions taken are also described. (author) [fr

Calibration and compensation of deflections and compliances in remote handling equipment configurations

International Nuclear Information System (INIS)

Kivelae, Tuomo; Saarinen, H.; Mattila, J.; Haemaelaeinen, V.; Siuko, M.; Semeraro, L.

2011-01-01

This paper presents a generic method of calibrating and compensating remote handling system configurations subject to manufacturing and assembly tolerances, deflections and compliances. A method consists of kinematic part and non-kinematic part. A kinematic calibration algorithm is presented for finding the values of kinematic model errors by measuring the end-effector Cartesian position. This is a conventional way to calibrate industrial robots. However, in this case the kinematic calibration is not able to compensate flaws fully due to large deflections and compliances caused by a massive Cassette payload (approx. 9 ton). Positioning error at the furthest point of the cassette before any compensation was 80 mm. Therefore, extra compensation must be introduced in addition to a kinematic calibration. A kinematic calibration together with an extra compensation is a demanding task to carry out. The resulting complex compensation function has to be such that it can be implemented in real-time Cassette Multifunctional Mover (CMM) control system software.

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

ITER - torus vacuum pumping system remote handling issues

International Nuclear Information System (INIS)

Stringer, J.

1992-11-01

This report describes design issues concerning remote maintenance of the ITER torus vacuum pumping system. Key issues under investigation in this report are bearings for inert gas operation, transporter integration options, cryopump access, gate valve maintenance frequency, tritium effects on materials, turbomolecular pump design, and remote maintenance. Alternative bearing materials are explored for inert gas operation. Encapsulated motors and rotary feedthroughs offer an alternative option where space requirements are restrictive. A number of transporter options are studied. The preferred scheme depends on the shielded reconfigured ducts to prevent streaming and activation of RH (remote handling) equipment. A radiation mapping of the cell is required to evaluate this concept. Valve seal and bellow life are critical issues and need to be evaluated, as they have a direct bearing on the provision of adequate RH equipment to meet scheduled and unscheduled maintenance outages. The limited space on the inboard side of the cryopumps for RH equipment access requires a reconfigured duct and manifold. A modified shielded duct arrangement is proposed, which would provide more access space, reduced activation of components, and the potential for improved valve seal life. Work at Mound Laboratories has shown the adverse effects of tritium on some bearing lubricants. Silicone-based lubricants should be avoided. (11 refs., 2 tabs., 31 figs.)

Optimized hardware design for the divertor remote handling control system

Energy Technology Data Exchange (ETDEWEB)

Saarinen, Hannu [Tampere University of Technology, Korkeakoulunkatu 6, 33720 Tampere (Finland)], E-mail: hannu.saarinen@tut.fi; Tiitinen, Juha; Aha, Liisa; Muhammad, Ali; Mattila, Jouni; Siuko, Mikko; Vilenius, Matti [Tampere University of Technology, Korkeakoulunkatu 6, 33720 Tampere (Finland); Jaervenpaeae, Jorma [VTT Systems Engineering, Tekniikankatu 1, 33720 Tampere (Finland); Irving, Mike; Damiani, Carlo; Semeraro, Luigi [Fusion for Energy, Josep Pla 2, Torres Diagonal Litoral B3, 08019 Barcelona (Spain)

2009-06-15

A key ITER maintenance activity is the exchange of the divertor cassettes. One of the major focuses of the EU Remote Handling (RH) programme has been the study and development of the remote handling equipment necessary for divertor exchange. The current major step in this programme involves the construction of a full scale physical test facility, namely DTP2 (Divertor Test Platform 2), in which to demonstrate and refine the RH equipment designs for ITER using prototypes. The major objective of the DTP2 project is the proof of concept studies of various RH devices, but is also important to define principles for standardizing control hardware and methods around the ITER maintenance equipment. This paper focuses on describing the control system hardware design optimization that is taking place at DTP2. Here there will be two RH movers, namely the Cassette Multifuctional Mover (CMM), Cassette Toroidal Mover (CTM) and assisting water hydraulic force feedback manipulators (WHMAN) located aboard each Mover. The idea here is to use common Real Time Operating Systems (RTOS), measurement and control IO-cards etc. for all maintenance devices and to standardize sensors and control components as much as possible. In this paper, new optimized DTP2 control system hardware design and some initial experimentation with the new DTP2 RH control system platform are presented. The proposed new approach is able to fulfil the functional requirements for both Mover and Manipulator control systems. Since the new control system hardware design has reduced architecture there are a number of benefits compared to the old approach. The simplified hardware solution enables the use of a single software development environment and a single communication protocol. This will result in easier maintainability of the software and hardware, less dependence on trained personnel, easier training of operators and hence reduced the development costs of ITER RH.

Effectiveness of Medical-Care Equipment Management: Case Study in a Public Hospital in Belo Horizonte / Minas Gerais

OpenAIRE

Estevão Maria Campolina de Oliveira; Eloísa Helena Rodrigues Guimaraes; Ester Eliane Jeunon

2017-01-01

This study aimed to identify and analyze the factors that contribute to the effectiveness of the management of medical-care equipment at the Hospital of Federal University of Minas Gerais (HC-UFMG) in Belo Horizonte, Minas Gerais. To achieve this goal, a case study was performed along with a field research at HC-UFMG, through interviews using a semi-structured questionnaire to professionals who handle and operate medical-care equipment; professionals who provide maintenance on equipment, and ...

Development of equipment for fabricating DUPIC fuel powder

International Nuclear Information System (INIS)

Kim, Ki Ho; Yang, M. S.; Park, J. J.; Lee, J. W.; Kim, J. H.; Cho, K. H.; Lee, D. Y.; Lee, Y. S.; Na, S. H.

1999-06-01

The powder fabrication processes, as the first stage of manufacturing DUPIC (Direct Use of PWR spent fuel In CANDU) fuel, consist of the slitting of spent PWR fuel rods, REOX (Oxidation and REduction of Oxide Fuels) processing to produce the powder feedstock, the milling of the produced powder, the granulation of the milled powder, and the mixing of the granulated powder with pressing lubricants. All these processes should be conducted by remote means in a hot-cell environment where the direct human access is limited to the strictest minimum due to the high radioactivity. This report describe the development of the equipment for fabricating DUPIC fuel powder. These equipment are Slitting Machine, Oxidation and Reduction (OREOX) Furnace, Mill, Roll Compactor, and Mixer. Remote design concept was applied to all the equipment for use in the M6 hot-cell of the IMEF. Mechanical design considerations and capabilities of the equipment for remote operation and maintenance are presented. First prototypes were developed and installed in the DUPIC full scale mock-up and tested using a master-slave manipulator. Redesign and reconstruction were made on each equipment based on mock-up test results. The remote technology acquired through this research was utilized in developing other equipment for DUPIC fuel fabrication, thereby improving safety and increasing productivity. This technology could also be extended to the area of remote handling equipment development for use in hazardous environments. (author). 14 refs., 9 tabs., 21 figs

Development of equipment for fabricating DUPIC fuel powder

Energy Technology Data Exchange (ETDEWEB)

Kim, Ki Ho; Yang, M. S.; Park, J. J.; Lee, J. W.; Kim, J. H.; Cho, K. H.; Lee, D. Y.; Lee, Y. S.; Na, S. H

1999-06-01

The powder fabrication processes, as the first stage of manufacturing DUPIC (Direct Use of PWR spent fuel In CANDU) fuel, consist of the slitting of spent PWR fuel rods, REOX (Oxidation and REduction of Oxide Fuels) processing to produce the powder feedstock, the milling of the produced powder, the granulation of the milled powder, and the mixing of the granulated powder with pressing lubricants. All these processes should be conducted by remote means in a hot-cell environment where the direct human access is limited to the strictest minimum due to the high radioactivity. This report describe the development of the equipment for fabricating DUPIC fuel powder. These equipment are Slitting Machine, Oxidation and Reduction (OREOX) Furnace, Mill, Roll Compactor, and Mixer. Remote design concept was applied to all the equipment for use in the M6 hot-cell of the IMEF. Mechanical design considerations and capabilities of the equipment for remote operation and maintenance are presented. First prototypes were developed and installed in the DUPIC full scale mock-up and tested using a master-slave manipulator. Redesign and reconstruction were made on each equipment based on mock-up test results. The remote technology acquired through this research was utilized in developing other equipment for DUPIC fuel fabrication, thereby improving safety and increasing productivity. This technology could also be extended to the area of remote handling equipment development for use in hazardous environments. (author). 14 refs., 9 tabs., 21 figs.

Milk postharvest handling practices across the supply chain in Eastern Ethiopia

Directory of Open Access Journals (Sweden)

Tadele Amentie

2016-06-01

Full Text Available Objective: This study was conducted to assess hygienic cow milk handling practices of milk producers, traders (informal collectors, transporters and vendors and consumers across the milk supply chain in the Eastern Ethiopia. Materials and methods: A total of 160 milk producers in Babile district were selected using multistage stratified sampling technique. Moreover, a total of 54 milk collectors and transporters (5, 40, 9 from Jigjiga, Harar and Dire Dawa town, respectively, 152 vendors (40 from Bable, Harar and Dire Dawa town and 32 from Jigjiga town and 160 consumers (40 from each town were selected using snowball sampling technique. Data from the selected actors were collected using focus group discussion, questionnaire survey and observations. Results: The study revealed that the majority of milk handling operations in the study area is carried out by females. The majority of respondent milk producers (87.5-92.5%, collectors and transporters (88.9-100%, vendors (77.5-90.7% and some consumers (37.5-47.5% performing milk handling operations were illiterate. Most of the observed actors in the study area perform malpractices (such as failure to stop milk handling while showing disease symptoms, improper hand washing and handling of risk factors while working with milk. Majority of respondent milk producers (87.5-97.5%, all traders and some consumers (12.5-32.5% use plastic containers for milk handling. Milk handling equipments were commonly washed using warm water, detergent and sand; however, in most case they were not properly protected from risk factors after washing. Majority of respondent milk producers (55-65%, collectors and transporters (60-66.7%, and some vendors (0-50% and consumers (0-55% use water from non-tap sources for hygienic practices. Conclusion: In general; the findings indicated that milk handling practices performed across the supply chain in the study area were unhygienic and therefore suggested the need for improving

A new virtual-reality training module for laparoscopic surgical skills and equipment handling: can multitasking be trained? A randomized controlled trial.

Science.gov (United States)

Bongers, Pim J; Diederick van Hove, P; Stassen, Laurents P S; Dankelman, Jenny; Schreuder, Henk W R

2015-01-01

During laparoscopic surgery distractions often occur and multitasking between surgery and other tasks, such as technical equipment handling, is a necessary competence. In psychological research, reduction of adverse effects of distraction is demonstrated when specifically multitasking is trained. The aim of this study was to examine whether multitasking and more specifically task-switching can be trained in a virtual-reality (VR) laparoscopic skills simulator. After randomization, the control group trained separately with an insufflator simulation module and a laparoscopic skills exercise module on a VR simulator. In the intervention group, insufflator module and VR skills exercises were combined to develop a new integrated training in which multitasking was a required competence. At random moments, problems with the insufflator appeared and forced the trainee to multitask. During several repetitions of a different multitask VR skills exercise as posttest, performance parameters (laparoscopy time, insufflator time, and errors) were measured and compared between both the groups as well with a pretest exercise to establish the learning effect. A face-validity questionnaire was filled afterward. University Medical Centre Utrecht, The Netherlands. Medical and PhD students (n = 42) from University Medical Centre Utrecht, without previous experience in laparoscopic simulation, were randomly assigned to either intervention (n = 21) or control group (n = 21). All participants performed better in the posttest exercises without distraction of the insufflator compared with the exercises in which multitasking was necessary to solve the insufflator problems. After training, the intervention group was significantly quicker in solving the insufflator problems (mean = 1.60Log(s) vs 1.70Log(s), p = 0.02). No significant differences between both the groups were seen in laparoscopy time and errors. Multitasking has negative effects on the laparoscopic performance. This study suggests

Using operational equipment to read accident dosemeters.

Science.gov (United States)

Devine, R T; Vigil, M M; Martinez, W A

2004-01-01

Analysis of accident dosemeters usually involves the use of laboratory-based counting equipment. Gamma spectrometers are used for indium, copper and gold, and alpha-beta detectors for sulphur. This equipment is usually not easily transported due to the shielding required and the weight and delicacy of the counters. For intercomparison studies that require reading the dosemeters on site, a transportable system is required unless the site operating the study can count samples for all the participants. In the case of an actual accident these systems would have a difficulty in counting a large number of accident dosemeters. In an accident, personnel are usually subdivided according to their level of exposure. Those exposed to higher doses are treated immediately. An alternate system should be made available to handle the dosemeters worn by those personnel are likely to receive lower doses. Improvements in portable operational equipment for gamma and beta monitoring allow their use as spectrometers. Such a system was used for the SILENE intercomparison conducted at IRSN Valduc on 12 June and 19, 2002, and the preliminary results compared well with the other participants.

78 FR 26110 - Kicking Cars and Going Between Rolling Equipment During Flat Switching Operations

Science.gov (United States)

2013-05-03

... Cars and Going Between Rolling Equipment During Flat Switching Operations AGENCY: Federal Railroad... occurred during a railroad switching operation that involved a railroad employee kicking cars and... make recommendations to railroads regarding the adoption of car-handling procedures during flat...

Remote removal of contaminated equipment from a radiochemical engineering cell

International Nuclear Information System (INIS)

Scharnhorst, N.L.; Bryan, G.H.; Bjorklund, W.J.

1984-01-01

Large-scale vitrification equipment in a radioactive cell was dismantled and packed for burial through the use of viewing windows with manipulators, two overhead cranes, and unique tools for disassembling, grabbing, and handling the equipment components. An air-driven reciprocating hacksaw, remotely placed and operated, was used to cut large structural members inaccessible by the manipulators. Remotely operated circular saws and a plasma torch were used to cut calciners, furnaces, storage vessels, piping, pumps, and structural members into pieces that were placed safely into shielded burial boxes. This engineering effort was accomplished without any exposure problems in approximately 17 months, which required almost 10 equivalent worker-years. 8 figures, 1 table

Nuclear fuel handling apparatus

International Nuclear Information System (INIS)

Andrea, C.; Dupen, C.F.G.; Noyes, R.C.

1977-01-01

A fuel handling machine for a liquid metal cooled nuclear reactor in which a retractable handling tube and gripper are lowered into the reactor to withdraw a spent fuel assembly into the handling tube. The handling tube containing the fuel assembly immersed in liquid sodium is then withdrawn completely from the reactor into the outer barrel of the handling machine. The machine is then used to transport the spent fuel assembly directly to a remotely located decay tank. The fuel handling machine includes a decay heat removal system which continuously removes heat from the interior of the handling tube and which is capable of operating at its full cooling capacity at all times. The handling tube is supported in the machine from an articulated joint which enables it to readily align itself with the correct position in the core. An emergency sodium supply is carried directly by the machine to provide make up in the event of a loss of sodium from the handling tube during transport to the decay tank. 5 claims, 32 drawing figures

Implementation and adoption of mechanical patient lift equipment in the hospital setting: The importance of organizational and cultural factors.

Science.gov (United States)

Schoenfisch, Ashley L; Myers, Douglas J; Pompeii, Lisa A; Lipscomb, Hester J

2011-12-01

Work focused on understanding implementation and adoption of interventions designed to prevent patient-handling injuries in the hospital setting is lacking in the injury literature and may be more insightful than more traditional evaluation measures. Data from focus groups with health care workers were used to describe barriers and promoters of the adoption of patient lift equipment and a shift to a "minimal-manual lift environment" at two affiliated hospitals. Several factors influencing the adoption of the lift equipment and patient-handling policy were noted: time, knowledge/ability, staffing, patient characteristics, and organizational and cultural aspects of work. The adoption process was complex, and considerable variability by hospital and across units was observed. The use of qualitative data can enhance the understanding of factors that influence implementation and adoption of interventions designed to prevent patient-handling injuries among health care workers. Copyright © 2011 Wiley Periodicals, Inc.

Analysis of fuel-handling incidents (safety analysis detailed report no. 5). PEC Brasimone reactor design basis accidents

Energy Technology Data Exchange (ETDEWEB)

1988-01-15

The features covered by this report deal with the equipment and cells in which the handling, examination, measurement, conditioning and storage of core elements are carried out. The operations covered range from the receiving of new element shipments to their insertion in the vessel (excluding handling inside the vessel itself, which is covered in report no. 2) and removal of the spent-elements from the vessel, transfer to their final storage and their ultimate loading into containers for transport outside the plant. The incident analysis along the path of the spent fuel was conducted with the same method adopted for other plant systems. It is treated separately here because the operation of the handling system is practically autonomous from reactor operation.

Advanced dust monitoring system applied to new TRU handling facility of JAERI

International Nuclear Information System (INIS)

Yabuta, H.; Shigeta, Y.; Sawahata, K.; Hasegawa, K.

1993-01-01

In JAERI, a large, scale multipurpose facility is under construction, which consists of a TRU waste management testing installation, a solution fuel treatment installation and critical assemblies with uranium and/or plutonium solution fuel. The facility is also equipped with a lot of gloveboxes for handling and treatment of solution fuel and hot cells for research on reprocessing process. As there may be a relatively high potential of air contamination, it is important to monitor air contamination effectively and efficiently. An advanced dust monitoring system was introduced for convenience of handling and automatical measurement of filter papers, by developing a filter-holder with an IC memory and a radioactivity measuring device with an automatic filter-holder changing mechanism as a part of a centralized monitoring system with a computer

Illegal handling of radioactive and nuclear materials. Threats and suggestions for measures

International Nuclear Information System (INIS)

Oliver, Lena; Melin, Lena; Prawitz, Jan; Ringbom, Anders; Sandstroem, Bjoern; Wigg, Lars; Wirstam, Jens

2004-01-01

This project deals with threats from smuggling or other illegal transportation of radioactive or nuclear materials across the borders to Sweden, and with the security of handling such materials in Sweden. The project has included studies of relevant documentation; visits and interviews at industries, hospitals, research institutes and military institutions in Sweden that handle radioactive materials; a pilot study at the Stockholm freeport, where equipment for detection of radioactive materials has been tested for six months; an analysis of incidents reported to the IAEA database; and an analysis of Swedish incidents. The following conclusions are drawn: Stricter rules regarding the physical protection of radiation sources and radioactive materials should be implemented in Sweden. The recommendations recently issued by IAEA should serve as a point of departure for working out such rules

Optical system for UV-laser technological equipment

Science.gov (United States)

Fedosov, Yuri V.; Romanova, Galina E.; Afanasev, Maxim Ya.

2017-09-01

Recently there has been an intensive development of intelligent industrial equipment that is highly automated and can be rapidly adjusted for certain details. This equipment can be robotics systems, automatic wrappers and markers, CNC machines and 3D printers. The work equipment considered is the system for selective curing of photopolymers using a UV-laser and UV-radiation in such equipment that leads to additional technical difficulties. In many cases for transporting the radiation from the laser to the point processed, a multi-mirror system is used: however, such systems are usually difficult to adjust. Additionally, such multi-mirror systems are usually used as a part of the equipment for laser cutting of metals using high-power IR-lasers. For the UV-lasers, using many mirrors leads to crucial radiation losses because of many reflections. Therefore, during the development of the optical system for technological equipment using UV-laser we need to solve two main problems: to transfer the radiation for the working point with minimum losses and to include the system for controlling/handling the radiation spot position. We introduce a system for working with UV-lasers with 450mW of power and a wavelength of 0.45 μm based on a fiber system. In our modelling and design, we achieve spot sizes of about 300 μm, and the designed optical and mechanical systems (prototypes) were manufactured and assembled. In this paper, we present the layout of the technological unit, the results of the theoretical modelling of some parts of the system and some experimental results.

CRBRP design and test results for fuel handling systems, plugs, and seals

International Nuclear Information System (INIS)

Berg, G.E.

1977-01-01

The fuel handling system and reactor rotating plugs for the Clinch River Breeder Reactor Plant (CRBRP) are based primarily on existing technology and, in many respects, follow the concept developed for the Fast Flux Test Facility (FFTF). The equipment and the development programs initiated to verify its performance are described. Test results obtained from the development program, and the extent to which these results verified original design selections, or suggested potential improvements, are discussed

Code of practice for the safe use of industrial radiography equipment (1989)

International Nuclear Information System (INIS)

1989-12-01

This code supersedes the Code of practice for the control and safe handling of sealed radioactive sources used in industrial radiography, published by the National Health and Medical Research Council (NHMRC) in 1968. It differs significantly from the former code because radiation protection practice and recommended standards have changed. The code covers the design, construction and requirements for the safe use of X-radiography equipment and gamma-radiography equipment. It provides illustrative working rules, detailed emergency procedures and comprehensive responsibilities and duties for all personnel involved in supplying and using industrial radiography equipment. The code details those equipment requirements, personnel requirements and work practices that the NHMRC considers necessary to keep exposures to ionizing radiation as low as reasonably achievable. Some equipment and facilities currently in use may not meet all of the mandatory requirements of this code. These requirements have been included in the code to encourage progress towards future compliance in the expectation that, in the interim, statutory authorities will apply them with discretion

Design Methodology of Process Layout considering Various Equipment Types for Large scale Pyro processing Facility

International Nuclear Information System (INIS)

Yu, Seung Nam; Lee, Jong Kwang; Lee, Hyo Jik

2016-01-01

At present, each item of process equipment required for integrated processing is being examined, based on experience acquired during the Pyropocess Integrated Inactive Demonstration Facility (PRIDE) project, and considering the requirements and desired performance enhancement of KAPF as a new facility beyond PRIDE. Essentially, KAPF will be required to handle hazardous materials such as spent nuclear fuel, which must be processed in an isolated and shielded area separate from the operator location. Moreover, an inert-gas atmosphere must be maintained, because of the radiation and deliquescence of the materials. KAPF must also achieve the goal of significantly increased yearly production beyond that of the previous facility; therefore, several parts of the production line must be automated. This article presents the method considered for the conceptual design of both the production line and the overall layout of the KAPF process equipment. This study has proposed a design methodology that can be utilized as a preliminary step for the design of a hot-cell-type, large-scale facility, in which the various types of processing equipment operated by the remote handling system are integrated. The proposed methodology applies to part of the overall design procedure and contains various weaknesses. However, if the designer is required to maximize the efficiency of the installed material-handling system while considering operation restrictions and maintenance conditions, this kind of design process can accommodate the essential components that must be employed simultaneously in a general hot-cell system

Fusion reactor handling operations with cable-driven parallel robots

Energy Technology Data Exchange (ETDEWEB)

Izard, Jean-Baptiste, E-mail: jeanbaptiste.izard@tecnalia.com; Michelin, Micael; Baradat, Cédric

2015-10-15

Highlights: • CDPR allow 6DOF positioning of loads using cable as links without payload swag. • Conceptual design of a CDPR for carrying and positioning tokamak sectors is given. • A CDPR for threading stellarator coils (6D trajectory following) is provided. • Both designs are capable of fullfilling the required precision without tooling. - Abstract: Cable-driven parallel robots (CDPR) are in their concept cranes with inclined cables which allow control of all the degrees of freedom of its payload, and therefore stability of all the degrees of freedom, including rotations. The workspace of a CDPR is only limited by the length of the cables, and the payload capacity related to the mass of the whole robot is very important. Besides, the control being based on kinematic models, the behavior of a CDPR is really that of a robot capable of automated trajectories or remote handling. The present paper gives a presentation of two use case studies based on some of the assembly phases and remote handling actions as designed for the recent fusion machines. Based on the use cases already in place in fusion reactor baselines, the opportunity of using CDPR for assembly of structural elements and coils is discussed. Finally, prospects for remote handling equipment from the reactor in hot cells are envisioned based on current CDPR research.

Handling of high intensity proton beams at 12 GeV

International Nuclear Information System (INIS)

Takasaki, M.; Minakawa, M.; Yamanoi, Y.; Ieiri, M.; Kato, Y.; Ishii, H.; Suzuki, Y.; Suzuki, T.; Tanaka, K.H.

1990-01-01

A new counter experimental hall is now being constructed at the KEK (National Laboratory for High Energy Physics, Japan) 12 GeV Proton Synchrotron (KEK-PS). This hall will be completed by the end of 1989, immediately followed by magnet installation. The present report describes the new technical achievements employed at the hall. The most important and essential feature of the equipment is that the beam-handling system is maintenance-free, though in case of need, maintenance should be carried out quickly from a distant location in order to reduce the absorbed dose during the maintenance work. This paper is divided into three parts. The first part outlines the general design concept of the hall, focusing on the handling of high-intensity beams. The second part addresses the development of a quick-disconnect system, focusing on electric power, interlock signals, cooling water, pumping port, and vacuum flange. The third part describes the development of radiation-resistant instruments, focusing on polyimide magnets and cement magnets. (N.K.)

Handling and Transport of Oversized Accelerator Components and Physics Detectors

CERN Document Server

Prodon, S; Guinchard, M; Minginette, P

2006-01-01

For cost, planning and organisational reasons, it is often decided to install large pre-built accelerators components and physics detectors. As a result surface exceptional transports are required from the construction to the installation sites. Such heavy transports have been numerous during the LHC installation phase. This paper will describe the different types of transport techniques used to fit the particularities of accelerators and detectors components (weight, height, acceleration, planarity) as well as the measurement techniques for monitoring and the logistical aspects (organisation with the police, obstacles on the roads, etc). As far as oversized equipment is concerned, the lowering into the pit is challenging, as well as the transport in tunnel galleries in a very scare space and without handling means attached to the structure like overhead travelling cranes. From the PS accelerator to the LHC, handling systems have been developed at CERN to fit with these particular working conditions. This pap...

Preliminary design report for prototypical spent nuclear fuel rod consolidation equipment

International Nuclear Information System (INIS)

Judson, B.F.; Maillet, J.; O'Neill, G.L.; Tsitsichvili, J.; Tucoulat, D.

1986-12-01

The purpose of the Prototypical Consolidation Demonstration Project (PCDP) is to develop and demonstrate the equipment system that will be used to consolidate the bulk of the spent nuclear fuel generated in the United States prior to its placement in a geological repository. The equipment must thus be capable of operating on a routine production basis over a long period of time with stringent requirements for safety, reliability, productivity and cost-effectiveness. Four phases are planned for the PCDP. Phase 1 is the Preliminary Design of generic consolidation equipment that could be installed at a Monitored Retrievable Storage (MRS) facility or in the Receiving ampersand Handling Facility at a geologic repository site. Phase 2 will be the Final Design and preparation of procurement packages for the equipment in a configuration capable of being installed and tested in a special enclosure within the TAN Hot Shop at DOE's Idaho National Engineering Laboratory. In Phase 3 the equipment will be fabricated and then tested with mock fuel elements in a contractor's facility. Finally, in Phase 4 the equipment will be moved to the TAN facility for demonstration operation with irradiated spent fuel elements. 55 figs., 15 tabs

Initial decontamination of the equipment decontamination room at the West Valley Demonstration Project. Topical report, September 1983-May 1985

International Nuclear Information System (INIS)

Meigs, R.A.

1985-12-01

The purpose of this report is to document the initial decontamination of the Equipment Decontamination Room (EDR). The effort spanned a two-year period and included packaging and removal of waste; grinding away contaminated concrete floors; pump-out and spraydown of an equipment soaking pit; washing and painting of walls, equipment, and floors; refurbishment of utilities and various pieces of equipment; and load tests of EDR and Chemical Process Cell (CPC) cranes. After decontamination, the EDR was converted into a waste handling area for the decommissioning of the CPC

Safe handling and monitoring of tritium in research on nuclear fusion

International Nuclear Information System (INIS)

Yoshida, Yoshikazu; Naruse, Yuji

1978-01-01

An actual condition of technique of safety handling and monitoring of tritium in the laboratory which treated a great quantity of tritium in relation to nuclear fusion, was described. With respect to the technique of safety handling of tritium, an actual condition of the technique in the U.S.A. which had wide experience in treating a great quantity of 3 H was mainly introduced, and it was helpful to a safety measure and a reduction of tritium effluence. Glovebox, hood, and other component machinery and tools for treating 3 H were also introduced briefly. As a monitoring technique, monitoring of indoor air and air exhaust by ionization chamber-type monitor for continuous monitoring of a great quantity of gaseous tritium was mentioned. Next, monitoring of a room, the surfaces of equipments, and draining, internal exposure of the individual, and monitoring of the environment were introduced. (Kanao, N.)

Texas passes first law for safe patient handling in America: landmark legislation protects health-care workers and patients from injury related to manual patient lifting.

Science.gov (United States)

Hudson, Mary Anne

2005-01-01

On June 17,2005, Texas Governor Rick Perry (R) signed into law Senate Bill 1525, making Texas the first state in the nation to require hospitals and nursing homes to implement safe patient handling and movement programs. Governor Perry is to be commended for this heroic first stand for safe patient handling in America. The landmark legislation will take effect January 1, 2006, requiring the establishment of policy to identify, assess, and develop methods of controlling the risk of injury to patients and nurses associated with lifting, transferring, repositioning, and movement of patients; evaluation of alternative methods from manual lifting to reduce the risk of injury from patient lifting, including equipment and patient care environment; restricting, to the extent feasible with existing equipment, manual handling of all or most of a patient's weight to emergency, life-threatening, or exceptional circumstances; and provision for refusal to perform patient handling tasks believed to involve unacceptable risks of injury to a patient or nurse. Manually lifting patients has been called deplorable, inefficient, dangerous to nurses, and painful and brutal to patients; manual lifting can cause needless suffering and injury to patients, with dangers including pain, bruising, skin tears, abrasions, tube dislodgement, dislocations, fractures, and being dropped by nursing staff during attempts to manually lift. Use of safe, secure, mechanical lift equipment and gentle friction-reducing devices for patient maneuvering tasks could eliminate such needless brutality. Research has proven that manual patient lifting is extremely hazardous to health-care workers, creating substantial risk of low-back injury, whether with one or two patient handlers. Studies on the use of mechanical patient lift equipment, by either nursing staff or lift teams, have proven repeatedly that most nursing staff back injury is preventable, leading to substantial savings to employers on medical and

Safe handling of renewable fuels and fuel mixtures

Energy Technology Data Exchange (ETDEWEB)

Wilen, C; Rautalin, A [VTT Energy, Espoo (Finland)

1997-12-01

VTT Energy has for several years carried out co-operation with many European research institutes on contractional basis on safety issues of fuels handling. A two-year co-operational project between VTT Energy and these research institutes was started in EU`s JOULE 3 programme in 1996, the total budget of which is 6.9 million FIM. Dust explosion testing method for `difficult` fuels, and for tests at elevated pressures and temperatures, will be developed in the task `Safe handling of renewable fuels and fuel mixtures`. Self- ignition and dust-explosion characteristics will be generated for wood and agro-biomass based biomasses and for the mixtures of them and coal. Inertization requirements will be studied, and the quenching method, combined with partial inertization, will be tested in 1.0 m{sup 3} test equipment. The ignition properties of the fuels under normal and elevated pressures will be characterised with thermobalances. The self-ignition tests with wood and forest residue dusts at 25 bar pressure have been carried out as scheduled. In addition to this, several fuels have undergone thermobalance tests, sieve analyses and microscopic studies for the characterisation of the fuels

Remote technology related to the handling, storage and disposal of spent fuel. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-11-01

Reduced radiation exposure, greater reliability and cost savings are all potential benefits of the application of remote technologies to the handling of spent nuclear fuel. Remote equipment and technologies are used to some extent in all facilities handling fuel and high-level wastes whether they are for interim storage, processing/repacking, reprocessing or disposal. In view of the use and benefits of remote technologies, as well as recent technical and economic developments in the area, the IAEA organized the Technical Committee Meeting (TCM) on Remote Technology Related to the Handling, Storage and/or Disposal of Spent Fuel. Twenty-one papers were presented at the TCM, divided into five general areas: 1. Choice of technologies; 2. Use of remote technologies in fuel handling; 3. Use of remote technologies for fuel inspection and characterization; 4. Remote maintenance of facilities; and 5. Current and future developments. Refs, figs and tabs.

Advance of Hazardous Operation Robot and its Application in Special Equipment Accident Rescue

Science.gov (United States)

Zeng, Qin-Da; Zhou, Wei; Zheng, Geng-Feng

A survey of hazardous operation robot is given out in this article. Firstly, the latest researches such as nuclear industry robot, fire-fighting robot and explosive-handling robot are shown. Secondly, existing key technologies and their shortcomings are summarized, including moving mechanism, control system, perceptive technology and power technology. Thirdly, the trend of hazardous operation robot is predicted according to current situation. Finally, characteristics and hazards of special equipment accident, as well as feasibility of hazardous operation robot in the area of special equipment accident rescue are analyzed.

Parametrical Method for Determining Optimal Ship Carrying Capacity and Performance of Handling Equipment

Directory of Open Access Journals (Sweden)

Michalski Jan P.

2016-04-01

Full Text Available The paper presents a method of evaluating the optimal value of the cargo ships deadweight and the coupled optimal value of cargo handling capacity. The method may be useful at the stage of establishing the main owners requirements concerning the ship design parameters as well as for choosing a proper second hand ship for a given transportation task. The deadweight and the capacity are determined on the basis of a selected economic measure of the transport effectiveness of ship – the Required Freight Rate. The mathematical model of the problem is of a deterministic character and the simplifying assumptions are justified for ships operating in the liner trade. The assumptions are so selected that solution of the problem is obtained in analytical closed form. The presented method can be useful for application in the preliminary ship design or in the simulation of pre-investment transportation task studies.

Remote-automated inspection and maintenance of nuclear power plant equipment

Energy Technology Data Exchange (ETDEWEB)

Sasaki, Masayoshi; Nakano, Yoshiyuki

1984-12-01

Employing remote-control inspection and maintenance equipment in nuclear power plants increases the plant availability by decreasing the annual shutdown time (outage), as well as radiation exposure and man-power. This paper presents an outline of the latest designs for an automatic refueling machine, a control rod drive handling machine, a fuel preparation machine, and a main steam line plug, which were supplied to the Fukushima Dai-Ni No. 2 Plant of the Tokyo Electric Power Co., Inc. (Fukushima 2-2). Also, the up-to-date developments of other new automatic machines, such as a CRD disassembly and cleaning system, spent fuel channel box volume reduction equipment, and robotics for nuclear plant use are presented.

Underground transportation and handling system for Pollux-casks

International Nuclear Information System (INIS)

Schrimpf, C.

1988-01-01

The concept for the underground transportation and handling system for Pollux-casks was optimized in a first phase by dividing the process in the repository up into the several transportation and manipulation steps. For each step, the possibilities were described and evaluated by means of a list of criteria (technical, safety and economical criteria). The following concept for the transportation and handling was developed: The casks are transported to the unloading area of the surface facilities by railway or truck. After removal of the transport protection, the entry control is performed. The cask is lifted from the vehicle and placed on a railbound transportation vehicle. This transport unit is transferred to the shaft and placed there ready for shaft hoisting. With the hoisting cage protruding, the transport unit is placed on the hoisting cage by means of a pushing-on device, locked, and then conveyed underground. After arrival on the emplacement level, the transport unit is pulled-off from the hoisting cage and taken over by a mine locomotive and transferred through the transportation and access drifts as far as to the emplacement site. There the locomotive pushed the rail transport vehicle into the emplacement drift, as far as to the designated emplacement position. At the emplacement position, the cask is again lifted by means of hoisting equipment. The rail transport vehicle is pulled out of the emplacement drift and returned to the surface for reloading. After deposition of the cask on the drift floor, the emplacement equipment is pulled back in order to give the operation space free for the slinger backfill truck. Within preceding tests two different backfilling techniques were investigated under realistic conditions: pneumatic backfilling and slinger backfilling. The slinger truck was found to be the most suitable for the designated purpose

Impact of shuttle environment on prelaunch handling of nickel-hydrogen batteries

Science.gov (United States)

Green, R. S.

1986-01-01

Deployment of the American Satellite Company 1 spacecraft for the Space Shuttle Discovery in August 1985 set a new milestone in nickel-hydrogen battery technology. This communications satellite is equipped with two 35 Ah nickel-hydrogen batteries and it is the first such satellite launched into orbit via the Space Shuttle. The prelaunch activities, combined with the environmental constraints onboard the Shuttle, led to the development of a new battery handling procedure. An outline of the prelaunch activities, with particular attention to battery charging, is presented.

Demonstration of a remotely operated TRU waste size-reduction and material handling process

International Nuclear Information System (INIS)

Stewart, J.A. III; Schuler, T.F.; Ward, C.R.

1986-01-01

Noncombustible Pu-238 and Pu-239 waste is generated as a result of normal operation and decommissioning activity at the Savannah River Plant and is being retrievably stored at the site. As part of the long-term plan to process the stored waste and current waste for permanent disposal, a remote size-reduction and material handling process is being tested at Savannah River Laboratory to provide design support for the plant TRU Waste Facility scheduled to be completed in 1993. The process consists of a large, low-speed shredder and material handling system, a remote worktable, a bagless transfer system, and a robotically controlled manipulator, or Telerobot. Initial testing of the shredder and material handling system and a cycle test of the bagless transfer system were completed. Initial Telerobot run-in and system evaluation was completed. User software was evaluated and modified to support complete menu-driven operation. Telerobot prototype size-reduction tooling was designed and successfully tested. Complete nonradioactive testing of the equipment is scheduled to be completed in 1987

Organizational aspects of the handling of radiation accidents in the Federal Republic of Germany

International Nuclear Information System (INIS)

Fliedner, T.M.

1977-01-01

In the Federal Republic of Germany it is a legal requirement that persons exposed to ionizing radiation as a consequence of their employment in radiation facilities should be monitored. Some 90000 persons constitute the population 'at risk' for occupational radiation exposure. The actual radiation accident rate has been very low indeed. Nevertheless, precautions must be taken. Four radiation accident categories may be distinguished: uncomplicated, complicated, contamination and incorporation accidents. In the Federal Republic, the 'Berufsgenossenschaften' (BGS) are required to organize radiation accident care if necessary and take all measures to prevent them. The BGS has issued a pamphlet 'First Aid in case of Increased Exposure to Ionizing Radiation' as a guide to all personnel concerned. The BGS has also organized 5 'Regional Radiation Protection Centres' available to give advice 7 days a week, 24 hours a day in Hamburg, Homburg (Saar), Juelich, Karlsruhe und Munich. These centres are all equipped to provide first aid and decontamination and to cater for a short term stay until a decision is reached as to how to handle a particular accident. The special burns hospital of the BGS in Ludwigshafen is equipped with sterile rooms to handle 'complicated accidents', in particular when skin burns are involved. Two mobile 'radiation protection units' are available in Karlsruhe and Munich to provide help in all problems of dosimetry and health physics. A medical advisory team has been formed to supplement local physicians in dealing with special problems in the handling of radiation accident victims. (author)

75 FR 76254 - Official Performance and Procedural Requirements for Grain Weighing Equipment and Related Grain...

Science.gov (United States)

2010-12-08

... DEPARTMENT OF AGRICULTURE Grain Inspection, Packers and Stockyards Administration 7 CFR Part 802 [Docket GIPSA-2010-FGIS-0012] RIN 0580-AB19 Official Performance and Procedural Requirements for Grain Weighing Equipment and Related Grain Handling Systems AGENCY: Grain Inspection, Packers and Stockyards...

Microphone Handling Noise: Measurements of Perceptual Threshold and Effects on Audio Quality.

Directory of Open Access Journals (Sweden)

Paul Kendrick

Full Text Available A psychoacoustic experiment was carried out to test the effects of microphone handling noise on perceived audio quality. Handling noise is a problem affecting both amateurs using their smartphones and cameras, as well as professionals using separate microphones and digital recorders. The noises used for the tests were measured from a variety of devices, including smartphones, laptops and handheld microphones. The signal features that characterise these noises are analysed and presented. The sounds include various types of transient, impact noises created by tapping or knocking devices, as well as more sustained sounds caused by rubbing. During the perceptual tests, listeners auditioned speech podcasts and were asked to rate the degradation of any unwanted sounds they heard. A representative design test methodology was developed that tried to encourage everyday rather than analytical listening. Signal-to-noise ratio (SNR of the handling noise events was shown to be the best predictor of quality degradation. Other factors such as noise type or background noise in the listening environment did not significantly affect quality ratings. Podcast, microphone type and reproduction equipment were found to be significant but only to a small extent. A model allowing the prediction of degradation from the SNR is presented. The SNR threshold at which 50% of subjects noticed handling noise was found to be 4.2 ± 0.6 dBA. The results from this work are important for the understanding of our perception of impact sound and resonant noises in recordings, and will inform the future development of an automated predictor of quality for handling noise.

Mock-up test on key components of ITER blanket remote handling system

International Nuclear Information System (INIS)

Takeda, Nobukazu; Kakudate, Satoshi; Nakahira, Masataka; Matsumoto, Yasuhiro; Taguchi, Koh; Kozaka, Hiroshi; Shibanuma, Kiyoshi; Tesini, Alessandro

2009-01-01

The maintenance operation of the ITER in-vessel component, such as a blanket and divertor, must be executed by the remote equipment because of the high gamma-ray environment. During the Engineering Design Activity (EDA), the Japan Atomic Energy Agency (then called as Japan Atomic Energy Research Institute) had been fabricated the prototype of the vehicle manipulator system for the blanket remote handling and confirmed feasibility of this system including automatic positioning of the blanket and rail deployment procedure of the articulated rail. The ITER agreement, which entered into force in the last year, formally decided that Japan will procure the blanket remote handling system and the JAEA, as the Japanese Domestic Agency, is continuing several R and Ds so that the system can be procured smoothly. The residual key issues after the EDA are rail connection and cable handling. The mock-ups of the rail connection mechanism and the cable handling system were fabricated from the last year and installed at the JAEA Naka Site in this March. The former was composed of the rail connecting mechanism, two rail segments and their handling systems. The latter one utilized a slip ring, which implemented 80 lines for power and 208 lines for signal, because there is an electrical contact between the rotating spool and the fixed base. The basic function of these systems was confirmed through the mock-up test. The rail connection mechanism, for example, could accept misalignment of 1.5-2 mm at least. The future test plan is also mentioned in the paper.

Assessment of Options for the Collection, Handling, and Transport of Corn Stover

Energy Technology Data Exchange (ETDEWEB)

Perlack, R.D.

2002-11-18

In this report, we discuss the logistics and estimate the delivered costs for collecting, handling, and hauling corn stover to an ethanol conversion facility. We compare costs for two conventional baling systems (large round bales and large rectangular bales), a silage-harvest system, and an unprocessed-pickup system. Our results generally indicate that stover can be collected, stored, and hauled for about $43.60 to $48.80/dry ton ($48.10-$53.80/dry Mg) using conventional baling equipment for conversion facilities ranging in size from 500 to 2000 dry tons/day (450-1810 dry Mg/day). These estimates are inclusive of all costs including farmer payments for the stover. Our results also suggest that costs might be significantly reduced with an unprocessed stover pickup system provided more efficient equipment is developed.

Equipment and performance upgrade of compact nuclear simulator

International Nuclear Information System (INIS)

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

1999-01-01

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

Differences among nursing homes in outcomes of a safe resident handling program.

Science.gov (United States)

Kurowski, Alicia; Gore, Rebecca; Buchholz, Bryan; Punnett, Laura

2012-01-01

A large nursing home corporation implemented a safe resident handling program (SRHP) in 2004-2007. We evaluated its efficacy over a 2-year period by examining differences among 5 centers in program outcomes and potential predictors of those differences. We observed nursing assistants (NAs), recording activities and body postures at 60-second intervals on personal digital assistants at baseline and at 3-month, 12-month, and 24-month follow-ups. The two outcomes computed were change in equipment use during resident handling and change in a physical workload index that estimated spinal loading due to body postures and handled loads. Potential explanatory factors were extracted from post-observation interviews, investigator surveys of the workforce, from administrative data, and employee satisfaction surveys. The facility with the most positive outcome measures was associated with many positive changes in explanatory factors and the facility with the fewest positive outcome measures experienced negative changes in the same factors. These findings suggest greater SRHP benefits where there was lower NA turnover and agency staffing; less time pressure; and better teamwork, staff communication, and supervisory support. © 2012 American Society for Healthcare Risk Management of the American Hospital Association.

Handling and feeding of biomass to pressurized reactors: safety engineering

Energy Technology Data Exchange (ETDEWEB)

Wilen, Carl; Rautalin, Aimo (Valtion Teknillinen Tutkimuskeskus, Espoo (Finland). Lab. of Fuel and Process Technology)

1993-01-01

There are rather few literature references to or experience of the feed of biomass into a pressurized space. Alternatives given in the literature usually concern handling and feeding technology for coal. Some screw- or piston-operated plug feeders and coal and concrete pump equipment have, however, also been tested with biomasses. Explosion characteristics of fuels and their susceptibility to spontaneous ignition have been studied at both atmospheric and elevated pressures. The maximum explosion pressure and maximum rate of pressure rise, being critical factors in the process design and in the choice of safety equipment, have been determined under these conditions. In pressurized processes, the maintenance of sufficient inertization in fuel-feed systems is an especially critical factor. Peat, bark, and forest residues were used as biofuels, and lignite was used as reference fuel. The results obtained with a dynamic method for spontaneous ignition were compared with experience obtained from the operation of a commercial pressurized peat gasifier of 140 MW. (author)

CAMAC - A modular instrumentation system for data handling. Revised description and specification

International Nuclear Information System (INIS)

1977-03-01

CAMAC is a modern data handling system in widespread use with on-line digital computers. It is based on a digital highway for data and control. The CAMAC specifications ensures compatibility between equipment from different sources. The revised specification introduces several new features, but is consistent with the previous version (EUR 4100e, 1969). The CAMAC system was specified by European laboratories, through the Esone Committee, and has been endorsed by the USAEC NIM Committee, who have an identical specification (TID-25875)

REMOTE MATERIAL HANDLING IN THE YUCCA MOUNTAIN WASTE PACKAGE CLOSURE CELL AND SUPPORT AREA GLOVEBOX

International Nuclear Information System (INIS)

K.M. Croft; S.M. Allen; M.W. Borland

2005-01-01

The Yucca Mountain Waste Package Closure System (WPCS) cells provide for shielding of highly radioactive materials contained in unsealed waste packages. The purpose of the cells is to provide safe environments for package handling and sealing operations. Once sealed, the packages are placed in the Yucca Mountain Repository. Closure of a typical waste package involves a number of remote operations. Those involved typically include the placement of matched lids onto the waste package. The lids are then individually sealed to the waste package by welding. Currently, the waste package includes three lids. One lid is placed before movement of the waste package to the closure cell; the final two are placed inside the closure cell, where they are welded to the waste package. These and other important operations require considerable remote material handling within the cell environment. This paper discusses the remote material handling equipment, designs, functions, operations, and maintenance, relative to waste package closure

Recommendations for cask features for robotic handling from the Advanced Handling Technology Project

International Nuclear Information System (INIS)

Drotning, W.

1991-02-01

This report describes the current status and recent progress in the Advanced Handling Technology Project (AHTP) initiated to explore the use of advanced robotic systems and handling technologies to perform automated cask handling operations at radioactive waste handling facilities, and to provide guidance to cask designers on the impact of robotic handling on cask design. Current AHTP tasks have developed system mock-ups to investigate robotic manipulation of impact limiters and cask tiedowns. In addition, cask uprighting and transport, using computer control of a bridge crane and robot, were performed to demonstrate the high speed cask transport operation possible under computer control. All of the current AHTP tasks involving manipulation of impact limiters and tiedowns require robotic operations using a torque wrench. To perform these operations, a pneumatic torque wrench and control system were integrated into the tool suite and control architecture of the gantry robot. The use of captured fasteners is briefly discussed as an area where alternative cask design preferences have resulted from the influence of guidance for robotic handling vs traditional operations experience. Specific robotic handling experiences with these system mock-ups highlight a number of continually recurring design principles: (1) robotic handling feasibility is improved by mechanical designs which emphasize operation with limited dexterity in constrained workspaces; (2) clearances, tolerances, and chamfers must allow for operations under actual conditions with consideration for misalignment and imprecise fixturing; (3) successful robotic handling is enhanced by including design detail in representations for model-based control; (4) robotic handling and overall quality assurance are improved by designs which eliminate the use of loose, disassembled parts. 8 refs., 15 figs

Development of a Remote Handling System in an Integrated Pyroprocessing Facility

Directory of Open Access Journals (Sweden)

Hyo Jik Lee

2013-10-01

Full Text Available Over the course of a decade-long research programme, the Korea Atomic Energy Research Institute (KAERI has developed several remote handling systems for use in pyroprocessing research facilities. These systems are now used successfully for the operation and maintenance of processing equipment. The most recent remote handling system is the bridge-transported dual arm servo-manipulator system (BDSM, which is used for remote operation at the world's largest pyroprocess integrated inactive demonstration facility (PRIDE. Accurate and reliable servo-control is the basic requirement for the BDSM to accomplish any given tasks successfully in a hotcell environment. To achieve this end, the hardware and software of a digital signal processor-based remote control system were fully custom-developed and implemented to control the BDSM. To reduce the residual vibration of the BDSM, several input profiles, including input shaping, were carefully chosen and evaluated. Furthermore, a time delay controller was employed to achieve good tracking performance and systematic gain tuning. The experimental results demonstrate that the applied control algorithms are more effective than conventional approaches. The BDSM successfully completed its performance tests at a mock-up and was installed at PRIDE for real-world operation. The remote handling system at KAERI is expected to advance the actualization of pyroprocessing.

Code of practice for the safe use of industrial radiography equipment (1989)

International Nuclear Information System (INIS)

1989-12-01

This code supersedes the Code of Practice for the control and safe handling of sealed radioactive sources use din industrial radiography, published by the National Health and Medical Research Council (NHMRC) in 1968. It differs significantly from the former code because radiation protection practice and recommended standards have changed. The code covers the design, construction and requirements for the safe use of X-radiography equipment and gamma-radiography equipment. It provides illustrative working rules, detailed emergency procedures and comprehensive responsibilities and duties for all personnel involved in supplying and using industrial radiography equipment. The code details those equipment requirements, personnel requirements and work practices that the NHMRC considers necessary to keep exposures to ionizing radiation as low as reasonably achievable. Some equipment and facilities currently in use may not meet all of the mandatory requirements of this code. These requirements have been included in the code to encourage progress towards future compliance in the expectation that, in the interim, statutory authorities will apply them with discretion. 9 refs., tabs., ills

Remote Handling Devices for Disposition of Enriched Uranium Reactor Fuel Using Melt-Dilute Process

International Nuclear Information System (INIS)

Heckendorn, F.M.

2001-01-01

Remote handling equipment is required to achieve the processing of highly radioactive, post reactor, fuel for the melt-dilute process, which will convert high enrichment uranium fuel elements into lower enrichment forms for subsequent disposal. The melt-dilute process combines highly radioactive enriched uranium fuel elements with deleted uranium and aluminum for inductive melting and inductive stirring steps that produce a stable aluminum/uranium ingot of low enrichment

Design for high productivity remote handling

Energy Technology Data Exchange (ETDEWEB)

Sykes, N., E-mail: nick.sykes@ccfe.ac.uk [Culham Centre For Fusion Energy, Culham Science Centre, OX14 3DB, Abingdon (United Kingdom); Collins, S.; Loving, A.B.; Ricardo, V. [Culham Centre For Fusion Energy, Culham Science Centre, OX14 3DB, Abingdon (United Kingdom); Villedieu, E. [Association Euratom-CEA Cadarache, DSM/IRFM, Saint Paul Les Durance (France)

2011-10-15

As the central part of a programme of enhancements in support of ITER, the Joint European Torus (JET) is being equipped with an all-metal wall. This enhancement programme requires the removal and installation of 6927 tile carriers and tiles, as well as the removal and installation of embedded diagnostics and antennas. The scale of this operation and the necessity to maximise operational availability of the facility added a requirement for high productivity in the remote activities to the existing exigencies of precision, reliability, cleanliness and operational security. This high productivity requirement has been incorporated into the design of the components and associated installation tooling, the design of the installation equipment, the development of installation procedures including the use of a mock-up for optimisation and training. Consideration of the remote handling installation process is vital during the design of the in vessel components. A number of features to meet the need of the high productivity while maintaining the function requirements have been incorporated into the metal wall components and associated tooling including kinematic design with guidance appropriate for remote operation. The component and tools are designed to guide the attachment of the installation tool, the installation path, and the interlocking with adjacent components without contact between the fragile castellated beryllium of the adjacent tiles. Other incorporated ergonomic features are discussed. At JET, the remote maintenance is conducted using end effectors, normally bi-lateral force feed back manipulator, mounted on driven, articulated booms. Prior to the current shutdown one long boom was used to conduct the installation and collect and deliver components to the 'short' boom which was linked to the tile carrier transfer facility. This led to loss of efficiency during these movements. The adoption of a new remote handling philosophy using 'point of

Design for high productivity remote handling

International Nuclear Information System (INIS)

Sykes, N.; Collins, S.; Loving, A.B.; Ricardo, V.; Villedieu, E.

2011-01-01

As the central part of a programme of enhancements in support of ITER, the Joint European Torus (JET) is being equipped with an all-metal wall. This enhancement programme requires the removal and installation of 6927 tile carriers and tiles, as well as the removal and installation of embedded diagnostics and antennas. The scale of this operation and the necessity to maximise operational availability of the facility added a requirement for high productivity in the remote activities to the existing exigencies of precision, reliability, cleanliness and operational security. This high productivity requirement has been incorporated into the design of the components and associated installation tooling, the design of the installation equipment, the development of installation procedures including the use of a mock-up for optimisation and training. Consideration of the remote handling installation process is vital during the design of the in vessel components. A number of features to meet the need of the high productivity while maintaining the function requirements have been incorporated into the metal wall components and associated tooling including kinematic design with guidance appropriate for remote operation. The component and tools are designed to guide the attachment of the installation tool, the installation path, and the interlocking with adjacent components without contact between the fragile castellated beryllium of the adjacent tiles. Other incorporated ergonomic features are discussed. At JET, the remote maintenance is conducted using end effectors, normally bi-lateral force feed back manipulator, mounted on driven, articulated booms. Prior to the current shutdown one long boom was used to conduct the installation and collect and deliver components to the 'short' boom which was linked to the tile carrier transfer facility. This led to loss of efficiency during these movements. The adoption of a new remote handling philosophy using 'point of installation

29 CFR 1917.73 - Terminal facilities handling menhaden and similar species of fish (see also § 1917.2, definition...

Science.gov (United States)

2010-07-01

... of fish (see also § 1917.2, definition of hazardous cargo, material, substance or atmosphere). 1917... facilities handling menhaden and similar species of fish (see also § 1917.2, definition of hazardous cargo... respiratory protective equipment consisting of supplied-air respirators or self-contained breathing apparatus...

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

ITER - torus vacuum pumping system remote handling issues

International Nuclear Information System (INIS)

Stringer, J.

1992-11-01

This report describes further design issues concerning remote maintenance of torus vacuum pumping systems options for ITER. The key issues under investigation in this report are flask support systems for valve seal exchange operations for the compound cryopump scheme and remote maintenance of a proposed multiple turbomolecular pump (TMP) system, an alternative ITER torus exhaust pumping option. Previous studies have shown that the overhead support methods for seal exchange flask equipment could malfunction due to valve/flask misalignment. A floor-mounted support system is described in this report. This scheme provides a more rigid support system for seal exchange operations. An alternative torus pumping system, based on the use of multiple TMPs, is studied from a remote maintenance standpoint. In this concept, centre distance spacing for pump/valve assemblies is too restrictive for remote maintenance. Recommendations are made for adequate spacing of these assemblies based on commercially-available 0.8 m and 1.0 m diameter valves. Fewer pumps will fit in this arrangement, which implies a need for larger TMPs. Pumps of this size are not commercially available. Other concerns regarding the servicing and storage of remote handling equipment in cells are also identified. (9 figs.)

FUEL HANDLING FACILITY BACKUP CENTRAL COMMUNICATIONS ROOM SPACE REQUIREMENTS CALCULATION

International Nuclear Information System (INIS)

SZALEWSKI, B.

2005-01-01

The purpose of the Fuel Handling Facility Backup Central Communications Room Space Requirements Calculation is to determine a preliminary estimate of the space required to house the backup central communications room in the Fuel Handling Facility (FHF). This room provides backup communications capability to the primary communication systems located in the Central Control Center Facility. This calculation will help guide FHF designers in allocating adequate space for communications system equipment in the FHF. This is a preliminary calculation determining preliminary estimates based on the assumptions listed in Section 4. As such, there are currently no limitations on the use of this preliminary calculation. The calculations contained in this document were developed by Design and Engineering and are intended solely for the use of Design and Engineering in its work regarding the FHF Backup Central Communications Room Space Requirements. Yucca Mountain Project personnel from Design and Engineering should be consulted before the use of the calculations for purposes other than those stated herein or use by individuals other than authorized personnel in Design and Engineering

Highly active vitrification plant remote handling operational experience and improvements

International Nuclear Information System (INIS)

Milgate, I.

1996-01-01

All the main process plant and equipment at the Sellafield Waste Vitrification Plant (WVP) is enclosed in heavily shielded concrete walled cells. There is a large quantity of relatively complex plant and equipment which must be remotely operated, maintained or replaced in-cell in a severe environment. The WVP has five in-cell polar cranes which are of modular construction to aid replacement of failed components. Each can be withdrawn into a shielded cell extension for decontamination and hands-on maintenance. The cells have a total of 80 through wall tube positions to receive Master Slave Manipulators (MSMs). The MSMs are used where possible for ''pick and place'' purposes but are often called upon to position substantial pieces of mechanical equipment and thus are subject to heavy loading and high failure rates. An inward flow of air is maintained in the active cells. The discharged air passes through a filter cell where remote damper operation filter changing and maintenance is carried out by means of a PAR3000 manipulator. A Nuclear Engineered Advanced Teleoperated Robot (Neater) swabs the vitrified product container to ensure cleanliness before storage. There is a significant arising of solid radioactive waste from replaced in-cell items which undergoes sorting and size reduction in a breakdown cell equipped with a large reciprocating saw and a hydraulic shear. Improvements to the remote handling facilities made in the light of operational experience are described. (UK)

Simulating and visualizing deflections of a remote handling mechanism

International Nuclear Information System (INIS)

Saarinen, Hannu; Hämäläinen, Vesa; Karjalainen, Jaakko; Määttä, Timo; Siuko, Mikko; Esqué, Salvador; Hamilton, David

2013-01-01

Highlights: ► An infinitesimal transformation represents elastic deflections. ► Equivalent spring factor is used to combine several deformations. ► Initial VR model accuracy improved from 80 to 5 mm. ► The deflection model is capable of adapting to changes in load at the end-effector. ► The algorithms and approach described are generic and can be adopted for other mechanisms. -- Abstract: Continuing ITER divertor second cassette (SC) remote handling (RH) test campaign has been carried out at divertor test platform (DTP2) in Finland. One of the goals has been to develop and implement efficient algorithms and software tools for simulating and visualizing for the operator the non-instrumented deflections of the RH mechanisms under loading conditions. Based on assumptions of the classical beam theory, the presented solution suggests utilization of an infinitesimal transformation to represent elastic deflections in a mechanical structure. Both structural analysis and measurements of the real structure are utilised during the process. The solution suggests one possible implementation strategy of a software component called structural simulator (SS), which is a software component of the remote handling control system (RHCS) architectural model specified by ITER organisation. Utilisation of the proposed SS necessitates modification of the initial virtual reality (VR) model of RH equipment to a format, which can visually represent the structural deflections. In practise this means adding virtual joints into the model. This will improve the accuracy of the VR visualization and will ensure that the virtual representation of the RH equipment closely aligns with the actual RH equipment. Cassette multifunctional mover (CMM) and second cassette end effector (SCEE) carrying SC were selected to be the initial target system for developing the approach. Demonstrations proved that the approach used can give high levels of accuracy even in complex structures such as the CMM

Simulating and visualizing deflections of a remote handling mechanism

Energy Technology Data Exchange (ETDEWEB)

Saarinen, Hannu, E-mail: hannu.saarinen@vtt.fi [VTT, Technical Research Centre of Finland, Tekniikankatu 1, 33720 Tampere (Finland); Hämäläinen, Vesa; Karjalainen, Jaakko; Määttä, Timo; Siuko, Mikko [VTT, Technical Research Centre of Finland, Tekniikankatu 1, 33720 Tampere (Finland); Esqué, Salvador [Fusion for Energy, Torres Diagonal Litoral B3, Josep Pla 2, 08019 Barcelona (Spain); Hamilton, David [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France)

2013-10-15

Highlights: ► An infinitesimal transformation represents elastic deflections. ► Equivalent spring factor is used to combine several deformations. ► Initial VR model accuracy improved from 80 to 5 mm. ► The deflection model is capable of adapting to changes in load at the end-effector. ► The algorithms and approach described are generic and can be adopted for other mechanisms. -- Abstract: Continuing ITER divertor second cassette (SC) remote handling (RH) test campaign has been carried out at divertor test platform (DTP2) in Finland. One of the goals has been to develop and implement efficient algorithms and software tools for simulating and visualizing for the operator the non-instrumented deflections of the RH mechanisms under loading conditions. Based on assumptions of the classical beam theory, the presented solution suggests utilization of an infinitesimal transformation to represent elastic deflections in a mechanical structure. Both structural analysis and measurements of the real structure are utilised during the process. The solution suggests one possible implementation strategy of a software component called structural simulator (SS), which is a software component of the remote handling control system (RHCS) architectural model specified by ITER organisation. Utilisation of the proposed SS necessitates modification of the initial virtual reality (VR) model of RH equipment to a format, which can visually represent the structural deflections. In practise this means adding virtual joints into the model. This will improve the accuracy of the VR visualization and will ensure that the virtual representation of the RH equipment closely aligns with the actual RH equipment. Cassette multifunctional mover (CMM) and second cassette end effector (SCEE) carrying SC were selected to be the initial target system for developing the approach. Demonstrations proved that the approach used can give high levels of accuracy even in complex structures such as the CMM

Study on Adaptive Slid Mode Controller for Improving Handling Stability of Motorized Electric Vehicles

Directory of Open Access Journals (Sweden)

LiQiang Jin

2014-01-01

Full Text Available An adaptive slid mode controller was established for improving the handling stability of motorized electric vehicle (MEV. First and foremost, the structure and advantages of electric vehicle driven by in-wheel motors will be provided. Then, an ideal cornering model of vehicles will be brought and analyzed, after which a method to estimate side-slip angle was also proposed and three typical sensors were used in the theory. Besides, an idea for the recognition of road adhesion coefficient was derived based on MEV platform, which will be helpful for better control performances. Finally, the scheme of control method was given and some typical tests for observing handling properties were implemented based on Simulink and Carsim software. With the outcomes from the experiments, which vividly showed the merits of the controller, one can come to a conclusion that MEV that equips with the adaptive slid mode controller always enjoys better handling performances than the one without control. Furthermore, the controller researched is friendly to the real-time working conditions, which will hold practical values in the future.

Interim design status and operational report for semiremote handling fixtures: size reduction system

International Nuclear Information System (INIS)

Ballard, A.S.

1977-02-01

Crushing of HTGR fuel elements is accomplished by a three-stage crushing system consisting of two overhead eccentric jaw crushers, a double-roll crusher, and an oversize reduction system to ensure complete reduction to the desired size. The crushing system is mounted in a special framework which enables gravity flow, eliminates material transport, and minimizes material holdup. The system has been designated UNIFRAME because of the integrated nature of the equipment. This report addresses the demonstration of semiremote maintenance of the crusher in a nonradioactive environment. Although the crusher maintenance system has some remote handling capability inherent in its design, the scope of this initial program is limited to the handling of selected components and allows for manual assistance in certain circumstances. This mode of operation is designated semiremote maintenance and is intended as an effort to gather experience

Safety for Compressed Gas and Air Equipment. Module SH-26. Safety and Health.

Science.gov (United States)

Center for Occupational Research and Development, Inc., Waco, TX.

This student module on safety for compressed gas and air equipment is one of 50 modules concerned with job safety and health. This module presents technical data about commonly used gases and stresses the procedures necessary for safe handling of compressed gases. Following the introduction, 14 objectives (each keyed to a page in the text) the…

Handling and Treatment of Poultry Hatchery Waste: A Review

Directory of Open Access Journals (Sweden)

Belinda Rodda

2011-01-01

Full Text Available A literature review was undertaken to identify methods being used to handle and treat hatchery waste. Hatchery waste can be separated into solid waste and liquid waste by centrifuging or by using screens. Potential methods for treating hatchery waste on site include use of a furnace to heat the waste to produce steam to run a turbine generator or to use an in line composter to stabilise the waste. There is also potential to use anaerobic digestion at hatcheries to produce methane and fertilisers. Hatcheries disposing wastewater into lagoons could establish a series of ponds where algae, zooplankton and fish utilise the nutrients using integrated aquaculture which cleans the water making it more suitable for irrigation. The ideal system to establish in a hatchery would be to incorporate separation and handling equipment to separate waste into its various components for further treatment. This would save disposal costs, produce biogas to reduce power costs at plants and produce a range of value added products. However the scale of operations at many hatcheries is too small and development of treatment systems may not be viable.

Designing a power supply for Nim-bin formatted equipment

International Nuclear Information System (INIS)

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

2016-09-01

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

Effect of training and lifting equipment for preventing back pain in lifting and handling: systematic review

NARCIS (Netherlands)

Martimo, Kari-Pekka; Verbeek, Jos; Karppinen, Jaro; Furlan, Andrea D.; Takala, Esa-Pekka; Kuijer, P. Paul F. M.; Jauhiainen, Merja; Viikari-Juntura, Eira

2008-01-01

To determine whether advice and training on working techniques and lifting equipment prevent back pain in jobs that involve heavy lifting. Medline, Embase, CENTRAL, Cochrane Back Group's specialised register, CINAHL, Nioshtic, CISdoc, Science Citation Index, and PsychLIT were searched up to

The application of advanced remote systems technology to future waste handling facilities: Waste Systems Data and Development Program

International Nuclear Information System (INIS)

Kring, C.T.; Herndon, J.N.; Meacham, S.A.

1987-01-01

The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory (ORNL) has been advancing the technology in remote handling and remote maintenance of in-cell systems planned for future US nuclear fuel reprocessing plants. Much of the experience and technology developed over the past decade in this endeavor are directly applicable to the in-cell systems being considered for the facilities of the Federal Waste Management System (FWMS). The ORNL developments are based on the application of teleoperated force-reflecting servomanipulators controlled by an operator completely removed from the hazardous environment. These developments address the nonrepetitive nature of remote maintenance in the unstructured environments encountered in a waste handling facility. Employing technological advancements in dexterous manipulators, as well as basic design guidelines that have been developed for remotely maintained equipment and processes, can increase operation and maintenance system capabilities, thereby allowing the attainment of two FWMS major objectives: decreasing plant personnel radiation exposure and increasing plant availability by decreasing the mean-time-to-repair in-cell maintenance and process equipment. 5 refs., 7 figs

Study of ITER equatorial port plug handling system and vacuum sealing interface

Energy Technology Data Exchange (ETDEWEB)

Martins, Jean-Pierre [Association Euratom CEA, CEA/DSM/IRFM, Cadarache, F-13108 Saint-Paul-lez-Durance (France)], E-mail: jean-pierre.martins@cea.fr; Doceul, Louis; Marol, Sebastien; Delchie, Elise [Association Euratom CEA, CEA/DSM/IRFM, Cadarache, F-13108 Saint-Paul-lez-Durance (France); Cordier, Jean-Jacques; Levesy, Bruno; Tesini, Alessandro [ITER International Organization, F-13108 Saint-Paul-lez-Durance cedex (France); Ciattaglia, Emanuela [EFDA CSU - Garching, Boltzmannstr. 2, D-85748 Garching (Germany); Tivey, Richard [Max-Planck-Institut fuer Plasmaphysik, Boltzmannstr. 2, 85748 Garching (Germany); Gillier, Rene; Abbes, Christophe [GARLOCK - Sealing Technologies - 90, rue de la roche du Geai, F-42029 St-Etienne cedex 1 (France)

2009-06-15

In the field of the ITER port plug engineering and integration task, CEA has contributed to define proposals concerning the port plugs vacuum sealing interface with the vessel flange and the equatorial plug handling. The 2001 baseline vacuum flange sealing consisted of TIG welding of a 316L strip plate on to U shapes. This arrangement presented some issues like welding access, implementation of tools, lip consumption, complex local leak test, continuous leak checking. Therefore, an alternate sealing solution based on the use of metallic gaskets is proposed. The different technical aspects are discussed to explain how this design can simplify the maintenance and deal with safety and vacuum requirements. The design of the mechanical attachment and vacuum sealing of the plug has constantly evolved, but the associated remote handling equipment was not systematically reviewed. An update of the cask and maintenance procedure was studied in order to design it in accordance with the last generic plug flange design. This includes a concept of a gripping system that uses the plug flange bolting area and, to help the remote handling process, a cantilever assisting system is suggested to increase the reliability of the transfer operation between vacuum vessel and cask.

Construction of a Learning Agent Handling Its Rewards According to Environmental Situations

Science.gov (United States)

Moriyama, Koichi; Numao, Masayuki

The authors aim at constructing an agent which learns appropriate actions in a Multi-Agent environment with and without social dilemmas. For this aim, the agent must have nonrationality that makes it give up its own profit when it should do that. Since there are many studies on rational learning that brings more and more profit, it is desirable to utilize them for constructing the agent. Therefore, we use a reward-handling manner that makes internal evaluation from the agent's rewards, and then the agent learns actions by a rational learning method with the internal evaluation. If the agent has only a fixed manner, however, it does not act well in the environment with and without dilemmas. Thus, the authors equip the agent with several reward-handling manners and criteria for selecting an effective one for the environmental situation. In the case of humans, what generates the internal evaluation is usually called emotion. Hence, this study also aims at throwing light on emotional activities of humans from a constructive view. In this paper, we divide a Multi-Agent environment into three situations and construct an agent having the reward-handling manners and the criteria. We observe that the agent acts well in all the three Multi-Agent situations composed of homogeneous agents.

Full scale tests on remote handled FFTF fuel assembly waste handling and packaging

International Nuclear Information System (INIS)

Allen, C.R.; Cash, R.J.; Dawson, S.A.; Strode, J.N.

1986-01-01

Handling and packaging of remote handled, high activity solid waste fuel assembly hardware components from spent FFTF reactor fuel assemblies have been evaluated using full scale components. The demonstration was performed using FFTF fuel assembly components and simulated components which were handled remotely using electromechanical manipulators, shielding walls, master slave manipulators, specially designed grapples, and remote TV viewing. The testing and evaluation included handling, packaging for current and conceptual shipping containers, and the effects of volume reduction on packing efficiency and shielding requirements. Effects of waste segregation into transuranic (TRU) and non-transuranic fractions also are discussed

Expanded Occupational Safety and Health Administration 300 log as metric for bariatric patient-handling staff injuries.

Science.gov (United States)

Randall, Stephen B; Pories, Walter J; Pearson, Amy; Drake, Daniel J

2009-01-01

Mobilization of morbidly obese patients poses significant physical challenges to healthcare providers. The purpose of this study was to examine the staff injuries associated with the patient handling of the obese, to describe a process for identifying injuries associated with their mobilization, and to report on the need for safer bariatric patient handling. We performed our study at a 761-bed, level 1 trauma center affiliated with a U.S. medical school. The hospital's Occupational Safety and Health Administration (OSHA) 300 log was expanded to the "E-OSHA 300 log" to specifically identify injuries the staff attributed to bariatric patient handling. The 2007 E-OSHA 300 log was analyzed to identify and describe the frequency, severity, and nature of bariatric versus nonbariatric patient handling injuries. The analyses revealed that during 2007, although patients with a body mass index of > or =35 kg/m(2) constituted patient population, 29.8% of staff injuries related to patient handling were linked to working with a bariatric patient. Bariatric patient handling accounted for 27.9% of all lost workdays and 37.2% of all restricted workdays associated with patient handling. Registered nurses and nursing assistants accounted for 80% of the injuries related to bariatric patient handling. Turning and repositioning the patient in bed accounted for 31% of the injuries incurred. The E-OSHA 300 log narratives revealed that staff injuries associated with obese and nonobese patient handling were usually performed using biomechanics and not equipment. Manual mobilization of morbidly obese patients increases the risk of caregiver injury. A tracking indicator on the OSHA 300 logs for staff injury linked to a bariatric patient would provide the ability to compare obese and nonobese patient handling injuries. The E-OSHA 300 log provides a method to identify the frequency, severity, and nature of caregiver injury during mobilization of the obese. Understanding the heightened risk of

Normas básicas de seguridad durante el manejo de equipos de radiaciones no ionizantes Safety basic rules when handling non-ionizing radiation equipment

Directory of Open Access Journals (Sweden)

Rosa María Armida Bretones

2012-03-01

this Prevention Department in cooperation with The Medical Physics Department a procedure based on basic preventive criteria has been elaborated to guarantee health and safety of the employees who handle non-ionizing radiation emitting equipment in our hospital and specialized centers. To draw the procedure: scientific literature related to the electromagnetic fields effects over health has been checked, periodical working meetings have been held between both above mentioned departments; non-ionizing radiation equipment have been identified as well as the places they are based or used; and expert people advice has been used. The procedure sets control and follow-up measurements both for people and equipment such as follows: Shortwave, microwave and magnetic therapy, Nuclear magnetic resonance, Laser, Ultraviolet radiation. The procedure and illustrative posters have been deployed to the linked departments, the information and training having been given to the employees who work with kind of equipment.

Conceptual design report, plutonium stabilization and handling,project W-460

Energy Technology Data Exchange (ETDEWEB)

Weiss, E.V.

1997-03-06

Project W-460, Plutonium Stabilization and Handling, encompasses procurement and installation of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing special nuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM for up to fifty years. This Conceptual Design Report (CDR) provides conceptual design details for the vault modification, site preparation and site interface with the purchased SPS. Two concepts are described for vault configuration; acceleration of this phase of the project did not allow completion of analysis which would clearly identify a preferred approach.

A versatile data handling system for nuclear physics experiments based on PDP 11/03 micro-computers

International Nuclear Information System (INIS)

Raaf, A.J. de

1979-01-01

A reliable and low cost data handling system for nuclear physics experiments is described. It is based on two PDP 11/03 micro-computers together with Gec-Elliott CAMAC equipment. For the acquisition of the experimental data a fast system has been designed. It consists of a controller for four ADCs together with an intelligent 38k MOS memory with a word size of 24 bits. (Auth.)

SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

S. C. Khamankar

2000-06-20

The Site Generated Radiological Waste Handling System handles radioactive waste products that are generated at the geologic repository operations area. The waste is collected, treated if required, packaged for shipment, and shipped to a disposal site. Waste streams include low-level waste (LLW) in solid and liquid forms, as-well-as mixed waste that contains hazardous and radioactive constituents. Liquid LLW is segregated into two streams, non-recyclable and recyclable. The non-recyclable stream may contain detergents or other non-hazardous cleaning agents and is packaged for shipment. The recyclable stream is treated to recycle a large portion of the water while the remaining concentrated waste is packaged for shipment; this greatly reduces the volume of waste requiring disposal. There will be no liquid LLW discharge. Solid LLW consists of wet solids such as ion exchange resins and filter cartridges, as-well-as dry active waste such as tools, protective clothing, and poly bags. Solids will be sorted, volume reduced, and packaged for shipment. The generation of mixed waste at the Monitored Geologic Repository (MGR) is not planned; however, if it does come into existence, it will be collected and packaged for disposal at its point of occurrence, temporarily staged, then shipped to government-approved off-site facilities for disposal. The Site Generated Radiological Waste Handling System has equipment located in both the Waste Treatment Building (WTB) and in the Waste Handling Building (WHB). All types of liquid and solid LLW are processed in the WTB, while wet solid waste from the Pool Water Treatment and Cooling System is packaged where received in the WHB. There is no installed hardware for mixed waste. The Site Generated Radiological Waste Handling System receives waste from locations where water is used for decontamination functions. In most cases the water is piped back to the WTB for processing. The WTB and WHB provide staging areas for storing and shipping LLW

SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

S. C. Khamankar

2000-01-01

The Site Generated Radiological Waste Handling System handles radioactive waste products that are generated at the geologic repository operations area. The waste is collected, treated if required, packaged for shipment, and shipped to a disposal site. Waste streams include low-level waste (LLW) in solid and liquid forms, as-well-as mixed waste that contains hazardous and radioactive constituents. Liquid LLW is segregated into two streams, non-recyclable and recyclable. The non-recyclable stream may contain detergents or other non-hazardous cleaning agents and is packaged for shipment. The recyclable stream is treated to recycle a large portion of the water while the remaining concentrated waste is packaged for shipment; this greatly reduces the volume of waste requiring disposal. There will be no liquid LLW discharge. Solid LLW consists of wet solids such as ion exchange resins and filter cartridges, as-well-as dry active waste such as tools, protective clothing, and poly bags. Solids will be sorted, volume reduced, and packaged for shipment. The generation of mixed waste at the Monitored Geologic Repository (MGR) is not planned; however, if it does come into existence, it will be collected and packaged for disposal at its point of occurrence, temporarily staged, then shipped to government-approved off-site facilities for disposal. The Site Generated Radiological Waste Handling System has equipment located in both the Waste Treatment Building (WTB) and in the Waste Handling Building (WHB). All types of liquid and solid LLW are processed in the WTB, while wet solid waste from the Pool Water Treatment and Cooling System is packaged where received in the WHB. There is no installed hardware for mixed waste. The Site Generated Radiological Waste Handling System receives waste from locations where water is used for decontamination functions. In most cases the water is piped back to the WTB for processing. The WTB and WHB provide staging areas for storing and shipping LLW

Handling of radiation emergency involving accidental detachment of 20 Ci iridium-192 source in a guide tube of a radiographic equipment in industrial radiography site

International Nuclear Information System (INIS)

Zaparde, S.P.; Murthy, B.K.S.; Vora, V.B.; Subramanian, G.

1979-01-01

The source capsule containing about 17.2 Ci of iridium-192 got accidently unscrewed in a guide tube of a gamma radiography equipment while carrying out the radiography of the spiral casing at construction site of a Hydroelectric Power Station. Immediately after the incident about 10 meter distance all around the spiral casing was cordoned off. The unscrewed capsule along with the source pellet was transferred to a lead container by raising the closed end of the guide tube of about 1/2 meters in length. The source pencil cable and cap of source capsule were separated from the source pellet. The source pellet was further shielded by a steel container and lead sheets. The source pellet was reloaded in the source capsule with limited facilities available at the work site. The source capsule cap was perfectly screwed by standing behind the L bench temporarily constructed out of lead sheets for the above jobs. During the above operation, the person received a whole body dose of 2000 mR and extrimety dose of 3000 mR. Handling of one more radiation emergency of similar type is described. A few appliances designed and fabricated for use in such emergencies are briefly described. (auth.)

Evaluation of design and operation of fuel handling systems for 25 MW biomass fueled CFB power plants

International Nuclear Information System (INIS)

Precht, D.

1991-01-01

Two circulating fluidized bed, biomass fueled, 25MW power plants were placed into operation by Thermo Electron Energy Systems in California during late 1989. This paper discusses the initial fuel and system considerations, system design, actual operating fuel characterisitics, system operation during the first year and modifications. Biomass fuels handled by the system include urban/manufacturing wood wastes and agricultural wastes in the form of orchard prunings, vineyard prunings, pits, shells, rice hulls and straws. Equipment utilized in the fuel handling system are described and costs are evaluated. Lessons learned from the design and operational experience are offered for consideration on future biomass fueled installations where definition of fuel quality and type is subject to change

Localization of cask and plug remote handling system in ITER using multiple video cameras

Energy Technology Data Exchange (ETDEWEB)

Ferreira, João, E-mail: jftferreira@ipfn.ist.utl.pt [Instituto de Plasmas e Fusão Nuclear - Laboratório Associado, Instituto Superior Técnico, Universidade Técnica de Lisboa, Av. Rovisco Pais 1, 1049-001 Lisboa (Portugal); Vale, Alberto [Instituto de Plasmas e Fusão Nuclear - Laboratório Associado, Instituto Superior Técnico, Universidade Técnica de Lisboa, Av. Rovisco Pais 1, 1049-001 Lisboa (Portugal); Ribeiro, Isabel [Laboratório de Robótica e Sistemas em Engenharia e Ciência - Laboratório Associado, Instituto Superior Técnico, Universidade Técnica de Lisboa, Av. Rovisco Pais 1, 1049-001 Lisboa (Portugal)

2013-10-15

Highlights: ► Localization of cask and plug remote handling system with video cameras and markers. ► Video cameras already installed on the building for remote operators. ► Fiducial markers glued or painted on cask and plug remote handling system. ► Augmented reality contents on the video streaming as an aid for remote operators. ► Integration with other localization systems for enhanced robustness and precision. -- Abstract: The cask and plug remote handling system (CPRHS) provides the means for the remote transfer of in-vessel components and remote handling equipment between the Hot Cell building and the Tokamak building in ITER. Different CPRHS typologies will be autonomously guided following predefined trajectories. Therefore, the localization of any CPRHS in operation must be continuously known in real time to provide the feedback for the control system and also for the human supervision. This paper proposes a localization system that uses the video streaming captured by the multiple cameras already installed in the ITER scenario to estimate with precision the position and the orientation of any CPRHS. In addition, an augmented reality system can be implemented using the same video streaming and the libraries for the localization system. The proposed localization system was tested in a mock-up scenario with a scale 1:25 of the divertor level of Tokamak building.

Localization of cask and plug remote handling system in ITER using multiple video cameras

International Nuclear Information System (INIS)

Ferreira, João; Vale, Alberto; Ribeiro, Isabel

2013-01-01

Highlights: ► Localization of cask and plug remote handling system with video cameras and markers. ► Video cameras already installed on the building for remote operators. ► Fiducial markers glued or painted on cask and plug remote handling system. ► Augmented reality contents on the video streaming as an aid for remote operators. ► Integration with other localization systems for enhanced robustness and precision. -- Abstract: The cask and plug remote handling system (CPRHS) provides the means for the remote transfer of in-vessel components and remote handling equipment between the Hot Cell building and the Tokamak building in ITER. Different CPRHS typologies will be autonomously guided following predefined trajectories. Therefore, the localization of any CPRHS in operation must be continuously known in real time to provide the feedback for the control system and also for the human supervision. This paper proposes a localization system that uses the video streaming captured by the multiple cameras already installed in the ITER scenario to estimate with precision the position and the orientation of any CPRHS. In addition, an augmented reality system can be implemented using the same video streaming and the libraries for the localization system. The proposed localization system was tested in a mock-up scenario with a scale 1:25 of the divertor level of Tokamak building

A probabilistic safety analysis of UF{sub 6} handling at the Portsmouth Gaseous Diffusion Plant

Energy Technology Data Exchange (ETDEWEB)

Boyd, G.J.; Lewis, S.R.; Summitt, R.L. [Safety and Reliability Optimization Services (SAROS), Inc., Knoxville, TN (United States)

1991-12-31

A probabilistic safety study of UF{sub 6} handling activities at the Portsmouth Gaseous Diffusion Plant has recently been completed. The analysis provides a unique perspective on the safety of UF{sub 6} handling activities. The estimated release frequencies provide an understanding of current risks, and the examination of individual contributors yields a ranking of important plant features and operations. Aside from the probabilistic results, however, there is an even more important benefit derived from a systematic modeling of all operations. The integrated approach employed in the analysis allows the interrelationships among the equipment and the required operations to be explored in depth. This paper summarizes the methods used in the study and provides an overview of some of the technical insights that were obtained. Specific areas of possible improvement in operations are described.

Ergonomic material-handling device

Science.gov (United States)

Barsnick, Lance E.; Zalk, David M.; Perry, Catherine M.; Biggs, Terry; Tageson, Robert E.

2004-08-24

A hand-held ergonomic material-handling device capable of moving heavy objects, such as large waste containers and other large objects requiring mechanical assistance. The ergonomic material-handling device can be used with neutral postures of the back, shoulders, wrists and knees, thereby reducing potential injury to the user. The device involves two key features: 1) gives the user the ability to adjust the height of the handles of the device to ergonomically fit the needs of the user's back, wrists and shoulders; and 2) has a rounded handlebar shape, as well as the size and configuration of the handles which keep the user's wrists in a neutral posture during manipulation of the device.

Operative experience in handling enriched uranium compounds in an U3O8 production plant

International Nuclear Information System (INIS)

Friedenthal, M.; Cardenas Yucra, H.R.; Cinat, E.; Pino, H.F.; Surin, C.

1987-01-01

The design of a nuclear installation associated with chemical processes depends fundamentally on the risks derived from the materials and process used. The operative experience brings useful data mainly related to the ventilation and equipment design that allow to improve the handling of operational incidents and maintenance work. The paper presents the results extracted from a production campaign; ambient and personal monitoring results from monitorings performed routinely and during special interventions are commented. (Author)

Guidelines for remote handling maintenance of ITER neutral beam line components: Proposal of an alternate supporting system

International Nuclear Information System (INIS)

Cordier, J.J.; Bayetti, P.; Hemsworth, R.; David, O.; Friconneau, J.P.

2007-01-01

Remote handling (R/H) maintenance of ITER components is one of the main challenges of the ITER project. This type of maintenance shall be operational for the assembly and nuclear phase of exploitation of ITER. It must be considered at a very early stage since it significantly impacts on the components design, interfaces management, assembly, maintenance and integration aspects. A large part of the R/H equipment will be procured by the EU Participating Team, including the whole Neutral Beam R/H Equipment. The Neutral Beam Heating and Current Drive system (NB and CD) design is being revisited by the ITER project. A vertical maintenance scheme is presently considered which may significantly impact on the reference design and associated components and lead to a new design of the NB and CD vacuum tank. In addition, NB line components remote handling solutions are being studied. The neutral beam test facility ITER to be built in Europe in the near future is also based on the vertical NB maintenance scheme of beam line components. New design guidelines compliant for both the ITER NB and CD system and the NB test facility proposed by the CEA association are described in the paper

Maintenance of fire systems and equipment at Virginia Power

International Nuclear Information System (INIS)

Doubrely, E.B. Jr.

1989-01-01

The basics of fire protection systems maintenance are well codified and documented in the National Fire Codes published by the National Fire Protection Association. In addition, Insurers often promulgate minimum standards for fire protection systems design and maintenance to which they attach conditions of insurability. Regulatory agencies and even in-house corporate policies can impact the maintenance of fire protection systems and equipment. This presentation will focus on the various methods and alternate ways of performing system maintenance, whether required by code, insurer, or by some regulatory commitment at Virginia Powers North Anna and Surry nuclear power stations. The approach to performing similar work is handled differently at each station. This difference can be attributed to proximity to outside assistance as well as plant philosophy. In addition to station maintenance practices, a discussion of in-house servicing of portable fire suppression equipment is offered. 1 tab

A dynamic simulation to study NET in-vessel handling operations

International Nuclear Information System (INIS)

Fung, P.T.F.

1989-01-01

The inspection, maintenance and repair of the Next European Torus (NET) fusion machine will require the extensive use of remote handling equipment to minimise the human exposure to the high radiation environment. The use of efficient manipulators will reduce the NET downtime by reducing the preparation time for entry into the controlled area and by performing the task with reasonable area and by performing the task with reasonable dexterity and speed, consistent with safety. A high fidelity simulation is a valuable tool to assist in the manipulator design, operations, trajectory planning, parameter optimisation and system verification. A manipulator simulation package called ASAD was originally developed by Spar for space manipulator applications. It is now being adapted to simulate the in-Vessel HandlingUnit for the NET program. This terestrial version of ASAD has been name ASAD - T. Spar, through the services of the Canadian Fusion Fuels Technology Project, is under contract to the NET program for the performance of this activity. This paper describes the capabillities and underlying assumptions of ASAD - T, aling with description of the simulation development of the NET in-vessel manipulator. (author). 4 refs.; 7 figs

Combilift ideal for maneuvering oil and gas equipment

Energy Technology Data Exchange (ETDEWEB)

Anon.

2009-07-15

This article described an innovative forklift that responds to the oil industry's need for a safer, better and easier way to move long tubular products that cannot be carried high in the air. The Gator Jaw is a duplex pipe clamp attachment that secures to the Combilift forklift carriage. The clamp arm can be hydraulically moved upwards to allow the operator full use of the forks without interference from the hold down arm. The Combilift's platform is ideal for maneuvering oil and gas equipment close to the ground. Since it can travel sideways, the length of the load is not critical. The Gator Jaw's unique design makes it possible for one forklift to handle both skids and pallets. The C-Series product extends to the subsea oil and gas industry, which works with long loads such as oil drilling tools and pipe. The benefits include safer product handling, significant space savings, increased productivity and versatile indoor and outdoor use. The machines are available with a fuel-efficient liquefied petroleum gas (LPG) or diesel engine. 1 fig.

Work-related musculoskeletal risks associated with nurses and nursing assistants handling overweight and obese patients: A literature review.

Science.gov (United States)

Choi, Sang D; Brings, Kathryn

2015-01-01

Nurses and nursing assistants are susceptible to work-related musculoskeletal disorders and injuries (WMSDs) due to the increase in overweight and obese patients they are handling on a daily basis. This study aimed to review work-related musculoskeletal hazards and risks associated with handling overweight and obese patients, and summarize the recommended interventions to mitigate musculoskeletal concerns among nurses and nursing assistants. Approximately 350 publications were initially screened and 22 refereed articles were used to synthesize for this study on the bases of inclusion/exclusion relevance and strength of evidence on overweight or obese patient handling. Evidence suggested that the work-related musculoskeletal risks among nurses and nursing assistants included sprains/strains, low back pain, wrist, knee and shoulder injuries. The findings indicated that the WMSD risks increased when nurses and nursing assistants were manually moving or lifting patients, especially when the patients were overweight or obese. The recommended solutions included the lifting/transfer equipment and devices, ergonomic assessments and controls, no-lift policies, and training and education. To alleviate the risk of musculoskeletal disorders and injuries among nurses and nursing assistants handling overweight or obese patients, additional research and development into what safe patient handling interventions suit this growing population needs to be addressed.

Handling small arbovirus vectors safely during biosafety level 3 containment: Culicoides variipennis sonorensis (Diptera:Ceratopogonidae) and exotic bluetongue viruses.

Science.gov (United States)

Hunt, G J; Tabachnick, W J

1996-05-01

Equipment and procedures are described for biosafety level 3 (BL-3) containment work with small, zoophilic arthropods. BL-3 classified pathogens always must be manipulated in biological safety cabinets. Procedures, including physical barriers and handling methods, that prevent the escape of potentially virus-infected insects are discussed, and the use of a monitoring system for insect security is explained. The inability to recover escaped minute, flying insects poses a major difference from similar work with larger insects, such as mosquitoes. Methods were developed for the safe and secure handling of Culicoides variipennis sonorensis Wirth & Jones infected with exotic bluetongue viruses during BL-3 containment.

30o inclination in handles of plastic boxes can reduce postural and muscular workload during handling

Directory of Open Access Journals (Sweden)

Luciana C. C. B. Silva

2013-06-01

Full Text Available BACKGROUND: The handling of materials, which occurs in the industrial sector, is associated with lesions on the lumbar spine and in the upper limbs. Inserting handles in industrial boxes is a way to reduce work-related risks. Although the position and angle of the handles are significant factors in comfort and safety during handling, these factors have rarely been studied objectively. OBJECTIVE: To compare the handling of a commercial box and prototypes with handles and to evaluate the effects on upper limb posture, muscle electrical activity, and perceived acceptability using different grips while handling materials from different heights. METHOD: Thirty-seven healthy volunteers evaluated the handles of prototypes that allowed for changes in position (top and bottom and angle (0°, 15°, and 30°. Wrist, elbow, and shoulder movements were evaluated using electrogoniometry and inclinometry. The muscle electrical activity in the wrist extensors, biceps brachii, and the upper portion of the trapezius was measured using a portable electromyographer. The recorded data on muscle movements and electrical activity were synchronized. Subjective evaluations of acceptability were evaluated using a visual analog scale. RESULTS AND CONCLUSIONS: The prototypes with handles at a 30° angle produced the highest acceptability ratings, more neutral wrist positions, lower levels of electromyographic activity for the upper trapezius, and lower elevation angles for the arms. The different measurement methods were complementary in evaluating the upper limbs during handling.

WIPP conceptual design report. Addendum J. Support equipment in the high level waste facility of the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Rieb, M.J.; Foley, R.S.

1977-04-01

The Aerojet Manufacturing Company (AMCO) received a contract in November 1976 to provide consulting services in assisting Holmes and Narver, Incorporated with the conceptual designs, cost estimates, and schedules of equipment used to handle waste casks, to decontaminate waste canisters and to overpack damaged or highly contaminated waste canisters for the Waste Isolation Pilot Plant (WIPP). Also, the layout of the hot cell in which canister handling, overpack and decontamination takes place was to be reviewed along with the time and motion study of the cell operations. This report has been prepared to present the results of the efforts and contains all technical and planning data developed during the program. The contents of this report are presented in three sections: (1) comments on the existing design criteria, equipment conceptual designs, hot cell design and time and motion studies of projected hot cell activities; (2) design descriptions of the equipment concepts and justification for varying from the existing concept (if a variation occurred). Drawings of each concept are provided in Appendix A. These design descriptions and drawings were used as the basis for the cost estimates; and (3) schedule projections and cost estimates for the equipment described in Section 2. Detail cost estimate backup data is provided in Appendix B

Equipment to weld fuel rods of mixed oxides

International Nuclear Information System (INIS)

Aparicio, G.; Orlando, O.S.; Olano, V.R.; Toubes, B.; Munoz, C.A.

1987-01-01

Two welding outfits system T1G were designed and constructed to weld fuel rods with mixed oxides pellets (uranium and plutonium). One of them is connected to a glove box where the loading of sheaths takes place. The sheaths are driven to the welder through a removable plug pusher in the welding chamber. This equipment was designed to perform welding tests changing the parameters (gas composition and pressure, welding current, electrode position, etc.). The components of the welder, such as plug holder, chamber closure and peripheral accessories, were designed and constructed taking into account the working pressures in the machine, which is placed in a controlled area and connected to a glove box, where special safety conditions are necessary. The equipment to weld fuel bars is complemented by another machine, located in cold area, of the type presently used in the fuel elements factory. This equipment has been designed to perform some welding operations in sheaths and mixed oxide rods of the type Atucha I and II. Both machines have a programmed power supply of wide range and a vacuum, and pressurizing system that allows the change of parameters. Both systems have special features of handling and operation. (Author)

New transport and handling contract

CERN Multimedia

SC Department

2008-01-01

A new transport and handling contract entered into force on 1.10.2008. As with the previous contract, the user interface is the internal transport/handling request form on EDH: https://edh.cern.ch/Document/TransportRequest/ To ensure that you receive the best possible service, we invite you to complete the various fields as accurately as possible and to include a mobile telephone number on which we can reach you. You can follow the progress of your request (schedule, completion) in the EDH request routing information. We remind you that the following deadlines apply: 48 hours for the transport of heavy goods (up to 8 tonnes) or simple handling operations 5 working days for crane operations, transport of extra-heavy goods, complex handling operations and combined transport and handling operations in the tunnel. For all enquiries, the number to contact remains unchanged: 72202. Heavy Handling Section TS-HE-HH 72672 - 160319

Equipment support for the implementation of safeguards

International Nuclear Information System (INIS)

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

2001-01-01

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

The effect of laryngoscope handle size on possible endotracheal intubation success in university football, ice hockey, and soccer players.

Science.gov (United States)

Delaney, J Scott; Al-Kashmiri, Ammar; Baylis, Penny-Jane; Aljufaili, Mahmood; Correa, José A

2012-07-01

To assess the effectiveness of a standard long-handle laryngoscope and a short-handle laryngoscope on ease of possible intubation in football, ice hockey, and soccer players. Prospective crossover study. University Sport Medicine Clinic. Sixty-two university varsity football (62 males), 45 ice hockey (26 males and 19 females), and 39 soccer players (20 males, 19 females). Athletes were assessed for different airway and physical characteristics. Three different physicians then assessed the use of laryngoscopes of different handle sizes in supine athletes who were wearing protective equipment while in-line cervical spine immobilization was maintained. The ease of passage of a laryngoscope blade into the posterior oropharynx of a supine athlete was assessed using both a standard long-handle and a short-handle laryngoscope. Use of a short-handle laryngoscope was easier for all physicians in all sports as compared with a standard-sized laryngoscope. Passage of a laryngoscope blade into the posterior oropharynx of a supine athlete was easiest in soccer players and most difficult in football and ice hockey players for both sizes of laryngoscope. Interference from chest or shoulder pads was a common cause for difficulty in passing the laryngoscope blade into the posterior oropharynx for football and ice hockey players. In the rare instances that an endotracheal intubation is to be attempted on an unconscious athlete, a short-handle laryngoscope may provide the best chance for successful intubation.

Report of the remote-handled transuranic waste mock retrieval demonstration

International Nuclear Information System (INIS)

1987-05-01

This report documents the results of the mock, onsite retrieval demonstration that was conducted on May 19 and 20, 1987, for representatives of the New Mexico Environmental Evaluation Group (EEG). Demonstration of the retrievability of remote-handled transuranic (RH TRU) waste is part of a milestone included in the Agreement for Consultation and Cooperation between the state of New Mexico and the United States Department of Energy. Retrieval equipment design documents and a retrievability demonstration plan for RH TRU waste were previously transmitted to the EEG. This report documents the results of the demonstration by evaluating the demonstration against the acceptance criteria that were established in the Demonstration Plan. 1 fig., 2 tabs

Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP - Project W-460

International Nuclear Information System (INIS)

WEISS, E.V.

2000-01-01

This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP

Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP - Project W-460

CERN Document Server

Weiss, E V

2000-01-01

This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP.

Failure Mode and Effect Analysis for remote handling transfer systems of ITER

International Nuclear Information System (INIS)

Pinna, T.; Caporali, R.; Tesini, A.

2008-01-01

A Failure Mode and Effect Analysis (FMEA) at component level was done to study safety-relevant implications arising from possible failures in performing remote handling (RH) operations at ITER facility . Autonomous air cushion transporter, pallet, sealed casks and tractor movers needed for port plug mounting/dismantling operation were analysed. For each sub-system, the breakdown of significant components was outlined and, for each component, possible failure modes have been investigated pointing out possible causes, possible actions to prevent the causes, consequences and actions to prevent or mitigate consequences. Off-normal events which may result in hazardous consequences to the public and the environment have been defined as Postulated Initiating Events (PIEs). Two safety-relevant PIEs have been defined by assessing elementary failures related to the analysed system. Each PIE has been discussed in order to qualitatively identify accident sequences arising from each of them. As an output of this FMEA study, possible incidental scenarios, where the intervention of rescue RH equipments is required to overcome critical situations determined by fault of RH components, were defined as well. Being rescue scenarios of main concern for ITER remote handling activities, such families could be helpful in defining the design requirements of port handling systems in general and on RH transfer system in particular. Furthermore, they could be useful in defining casks and vehicles to be used for rescue activities

Waste Isolation Pilot Plant contact-handled transuranic waste preoperational checkout: Final report

International Nuclear Information System (INIS)

1988-07-01

This report documents the results of the WIPP CH TRU Preoperational Checkout which was completed between June 8 and June 14, 1988 during which period, a total of 10 TRUPACT shipping containers were processed from site receipt through emplacement of the simulated waste packages in the underground storage area. Since the design of WIPP includes provisions to unload an internally contaminated TRUPACT, in the controlled environment of the Overpack and Repair Room, one TRUPACT was partially processed through this sequence of operations to verify this portion of the waste handling process as part of the checkout. The successful completion of the CH TRU Preoperational Checkout confirmed the acceptability of WIPP operating procedures, personnel, equipment, and techniques. Extrapolation of time-line data using a computer simulation model of the waste handling process has confirmed that WIPP operations can achieve the design throughput capability of 500,000 ft 3 /year, if required, using two waste handling shifts. The single shift throughput capability of 273,000 ft 3 /year exceeds the anticipated operating receival rate of about 230,000 ft 3 /year. At the 230,000 ft 3 /year rate, the combined CH TRU annual operator dose and the average individual dose (based on minimum crew size) is projected to be 13.7 rem and 0.7 rem, respectively. 6 refs., 27 figs., 3 tabs

Trends in Modern Exception Handling

Directory of Open Access Journals (Sweden)

Marcin Kuta

2003-01-01

Full Text Available Exception handling is nowadays a necessary component of error proof information systems. The paper presents overview of techniques and models of exception handling, problems connected with them and potential solutions. The aspects of implementation of propagation mechanisms and exception handling, their effect on semantics and general program efficiency are also taken into account. Presented mechanisms were adopted to modern programming languages. Considering design area, formal methods and formal verification of program properties we can notice exception handling mechanisms are weakly present what makes a field for future research.

Remote handling machines

International Nuclear Information System (INIS)

Sato, Shinri

1985-01-01

In nuclear power facilities, the management of radioactive wastes is made with its technology plus the automatic techniques. Under the radiation field, the maintenance or aid of such systems is important. To cope with this situation, MF-2 system, MF-3 system and a manipulator system as remote handling machines are described. MF-2 system consists of an MF-2 carrier truck, a control unit and a command trailer. It is capable of handling heavy-weight objects. The system is not by hydraulic but by electrical means. MF-3 system consists of a four-crawler truck and a manipulator. The truck is versatile in its posture by means of the four independent crawlers. The manipulator system is bilateral in operation, so that the delicate handling is made possible. (Mori, K.)

Reactor fuel charging equipment

International Nuclear Information System (INIS)

Wade, Elman.

1977-01-01

In many types of reactor fuel charging equipment, tongs or a grab, attached to a trolley, housed in a guide duct, can be used for withdrawing from the core a selected spent fuel assembly or to place a new fuel assembly in the core. In these facilities, the trolley may have wheels that roll on rails in the guide duct. This ensures the correct alignment of the grab, the trolley and fuel assembly when this fuel assembly is being moved. By raising or lowering such a fuel assembly, the trolley can be immerged in the coolant bath of the reactor, whereas at other times it can be at a certain level above the upper surface of the coolant bath. The main object of the invention is to create a fuel handling apparatus for a sodium cooled reactor with bearings lubricated by the sodium coolant and in which the contamination of these bearings is prevented [fr

Remotely controlled inspection and handling systems for decommissioning tasks in nuclear facilities

International Nuclear Information System (INIS)

Schreck, G.; Bach, W.; Haferkamp, H.

1993-01-01

The Institut fur Werkstoffkunde at the University of Hanover has recently developed three remotely controlled systems for different underwater inspection and dismantling tasks. ODIN I is a tool guiding device, particularly being designed for the dismantling of the steam dryer housing of the KRB A power plant at Gundremmingen, Germany. After being approved by the licencing organization TUEV Bayern, hot operation started in November 1992. The seven axes remotely controlled handling system ZEUS, consisting of a three translatory axes guiding machine and a tool handling device with four rotatory axes, has been developed for the demonstration of underwater plasma arc cutting of spherical metallic components with great wall thicknesses. A specially designed twin sensor system and a modular torch, exchanged by means of a remote controlled tool changing device, will be used for different complex cutting tasks. FAUST, an autonomous, freediving underwater vehicle, was designed for complex inspection, maintenance and dismantling tasks. It is equipped with two video cameras, an ultrasonic and a radiologic sensor and a small plasma torch. A gripper and a subsidiary vehicle for inspection may be attached. (author)

The remote handling compatibility analysis of the ITER generic upper port plug structure

Energy Technology Data Exchange (ETDEWEB)

Ronden, D.M.S., E-mail: d.m.s.ronden@differ.nl [FOM Institute DIFFER, P.O. Box 1207, 3430 BE Nieuwegein (Netherlands); Dammann, A. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul-lez-Durance (France); Elzendoorn, B. [FOM Institute DIFFER, P.O. Box 1207, 3430 BE Nieuwegein (Netherlands); Giacomin, T. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul-lez-Durance (France); Heemskerk, C. [Heemskerk Innovative Technology, Merelhof 2, 2172 HZ Sassenheim (Netherlands); Loesser, D. [Princeton Plasma Physics Laboratory, Princeton, NJ 08543-0451 (United States); Maquet, P. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul-lez-Durance (France); Oosterhout, J. van [FOM Institute DIFFER, P.O. Box 1207, 3430 BE Nieuwegein (Netherlands); Pak, S.; Pitcher, C.S.; Portales, M.; Proust, M.; Udintsev, V.S.; Walsh, M.J. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul-lez-Durance (France)

2014-10-15

Highlights: • We describe the remote handling compatibility of the ITER generic upper port plug. • Concepts are presented of specific design solutions to improve RH compatibility. • Simulation in VR of the GUPP DSM replacement indicates possible collisions. • Specific tooling concepts are proposed for GUPP handling equipment for the hot cell. - Abstract: The ITER diagnostics generic upper port plug (GUPP) is developed as a standardized design for all diagnostic upper port plugs, in which a variety of payloads can be mounted. Here, the remote handling compatibility analysis (RHCA) of the GUPP design is presented that was performed for the GUPP final design review. The analysis focuses mainly on the insertion and extraction procedure of the diagnostic shield module (DSM), a removable cassette that contains the diagnostic in-vessel components. It is foreseen that the DSM is a replaceable component – the procedure of which is to be performed inside the ITER hot cell facility (HCF), where the GUPP can be oriented in a vertical position. The DSM removal procedure in the HCF consists of removing locking pins, an M30 sized shoulder bolt and two electrical straps through the use of a dexterous manipulator, after which the DSM is lifted out of the GUPP by an overhead crane. For optimum access to its internals, the DSM is mounted in a handling device. The insertion of a new or refurbished DSM follows the reverse procedure. The RHCA shows that the GUPP design requires a moderate amount of changes to become fully compatible with RH maintenance requirements.

The remote handling compatibility analysis of the ITER generic upper port plug structure

International Nuclear Information System (INIS)

Ronden, D.M.S.; Dammann, A.; Elzendoorn, B.; Giacomin, T.; Heemskerk, C.; Loesser, D.; Maquet, P.; Oosterhout, J. van; Pak, S.; Pitcher, C.S.; Portales, M.; Proust, M.; Udintsev, V.S.; Walsh, M.J.

2014-01-01

Highlights: • We describe the remote handling compatibility of the ITER generic upper port plug. • Concepts are presented of specific design solutions to improve RH compatibility. • Simulation in VR of the GUPP DSM replacement indicates possible collisions. • Specific tooling concepts are proposed for GUPP handling equipment for the hot cell. - Abstract: The ITER diagnostics generic upper port plug (GUPP) is developed as a standardized design for all diagnostic upper port plugs, in which a variety of payloads can be mounted. Here, the remote handling compatibility analysis (RHCA) of the GUPP design is presented that was performed for the GUPP final design review. The analysis focuses mainly on the insertion and extraction procedure of the diagnostic shield module (DSM), a removable cassette that contains the diagnostic in-vessel components. It is foreseen that the DSM is a replaceable component – the procedure of which is to be performed inside the ITER hot cell facility (HCF), where the GUPP can be oriented in a vertical position. The DSM removal procedure in the HCF consists of removing locking pins, an M30 sized shoulder bolt and two electrical straps through the use of a dexterous manipulator, after which the DSM is lifted out of the GUPP by an overhead crane. For optimum access to its internals, the DSM is mounted in a handling device. The insertion of a new or refurbished DSM follows the reverse procedure. The RHCA shows that the GUPP design requires a moderate amount of changes to become fully compatible with RH maintenance requirements

Evaluation formulas of manpower needs for dismantling of equipments in uranium refining and conversion plant

International Nuclear Information System (INIS)

Izumo, Sari; Usui, Hideo; Kubota, Shintaro; Tachibana, Mitsuo; Kawagoshi, Hiroshi; Tokuyasu, Takashi; Takahashi, Nobuo; Morimoto, Yasuyuki; Tanaka, Yoshio; Sugitsue, Noritake

2014-07-01

Japan Atomic Energy Agency has developed PROject management data evaluation code for DIsmantling Activities (PRODIA) to make an efficient decommissioning for nuclear facilities. PRODIA is a source code which provides estimated value such as manpower needs, costs, etc., for dismantling by evaluation formulas according to the type of nuclear facility. Evaluation formulas of manpower needs for dismantling of equipments about reprocessed uranium conversion in Uranium Refining and Conversion Plant (URCP) have been developed in this report. In the result, evaluation formulas of manpower needs for dismantling of equipment were derived based on the classifications of equipment's functions or work items. These evaluation formulas are widely applicable to the estimation of the manpower needs for dismantling the other nuclear facilities, in particular uranium handling facilities. It was confirmed that some of these evaluation formulas with the same applicable condition could be unified to some inclusive evaluation formulas. It turned out that all steel equipment contaminated by uranium could be evaluated by one evaluation formula. (author)

Safety of Cargo Aircraft Handling Procedure

Directory of Open Access Journals (Sweden)

Daniel Hlavatý

2017-07-01

Full Text Available The aim of this paper is to get acquainted with the ways how to improve the safety management system during cargo aircraft handling. The first chapter is dedicated to general information about air cargo transportation. This includes the history or types of cargo aircraft handling, but also the means of handling. The second part is focused on detailed description of cargo aircraft handling, including a description of activities that are performed before and after handling. The following part of this paper covers a theoretical interpretation of safety, safety indicators and legislative provisions related to the safety of cargo aircraft handling. The fourth part of this paper analyzes the fault trees of events which might occur during handling. The factors found by this analysis are compared with safety reports of FedEx. Based on the comparison, there is a proposal on how to improve the safety management in this transportation company.

Equipment for handling ionization chamber

International Nuclear Information System (INIS)

Altmann, J.

1988-01-01

The device consists of an ionization channel with an ionization chamber, of a support ring, axial and radial bearings, a sleeve, a screw gear and an electric motor. The ionization chamber is freely placed on the bottom of the ionization channel. The bottom part of the channel deviates from the vertical axis. The support ring propped against the axial bearing in the sleeve is firmly fixed to the top part of the ionization channel. The sleeve is fixed to the reactor lid. Its bottom part is provided with a recess for the radial bearing which is propped against a screw wheel firmly connected to the ionization channel. In measuring neutron flux, the screw wheel is rotated by the motor, thus rotating the whole ionization channel such that the ionization chamber is displaced into the reactor core.(J.B.). 1 fig

Structure Analysis of the Graphic Simulator for the PRIDE Equipment

International Nuclear Information System (INIS)

Kim, Chang Hoi; Kim, Seong Hyun; Park, Byung Suk; Lee, Jong Kwang; Lee, Hyo Jik; Kim, Ki Ho

2010-12-01

Simulation technology based on the computer graphics is able to minimize the trial and error and reduce the development cost and period dramatically at the design stage of the pyroprocessing facility construction and the equipment development. For this purpose, the 3D graphic simulation program named HotCell has been developed. HotCell has continuously updated for the functional addition and the bug fix, and now it reaches version third. The Digital mockup of PRIDE is furnished with the MSM(matster-slave manipulator), BDSM(bridge transported dual arm servo manipulator) and Crane in order to remote handling the processing equipment. HotCell program can be interface with the 3D mouse, the haptic device and the joystick for the realistic operation of above device. The posture of MSM can be recorded with the simple keyboard operation in order to reproduce the behavior of the MSM

Progress in the design, R and D and procurement preparation of the ITER Divertor Remote Handling System

Energy Technology Data Exchange (ETDEWEB)

Esqué, Salvador, E-mail: Salvador.Esque@f4e.europa.eu [Fusion for Energy, Torres Diagonal Litoral B3, Josep Pla 2, 08019 Barcelona (Spain); Hille, Carine van; Ranz, Roberto; Damiani, Carlo [Fusion for Energy, Torres Diagonal Litoral B3, Josep Pla 2, 08019 Barcelona (Spain); Palmer, Jim; Hamilton, David [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul-lez-Durance (France)

2014-10-15

Highlights: •The ITER Divertor Remote Handling System (DRHS) reference design is presented. •Different R and D activities that have contributed to the development and validation of the current reference design are reported. •The DRHS turns to be a unique system in terms of complexity due to size of the to-be-handled components, the novelty of the remote operations and the operational conditions. -- Abstract: The ITER Divertor Remote Handling System (DRHS) consists of a number of dedicated remote handling equipment and tooling that will provide the means to perform the exchange of the divertor system in a full-remote way. In order to achieve this objective the DRHS will need to perform a number of novel and complex remote operations in a contaminated and space-constrained environment, in rather poor lightening conditions. Fusion for Energy has recently launched the tendering phase for the in-kind procurement of the DRHS. The procurement is based on a set of system requirements and functional specifications supported by a reference design which are presented and discussed in this paper along with the main outcomes of the different R and D activities that have contributed to the development and validation of the current reference design.

Overview of remote handling technologies developed for inspection and maintenance of spent fuel management facilities in France

Energy Technology Data Exchange (ETDEWEB)

Desbats, Philippe [CEA - Direction de la Recherche Technologique / LIST, BP 6 - 92265, Fontenay-aux-Roses cedex (France); Piolain, Gerard [COGEMA-HAG/DMCO, AREVA NC SA, 2, rue Paul Dautier, BP 4, 78 141 Velizy Cedex (France)

2006-07-01

In the facilities of the end of the nuclear fuel cycle, like spent fuel storage pools, reprocessing plants, Plutonium-based fuel manufacturing plants or waste temporary storage units, materials handling must be carried out remotely, taking into account the nuclear radiating environment. In addition to the automation requirement, robotics equipment in the nuclear industry must be substituted to human operators in order to respect the ALARA principle. More over, remote handling technologies aim to improve the working conditions, as well as the quality of the work achieved by the operators. Ten years ago, COGEMA (AREVA Group) and CEA (French Atomic Energy Agency) started an ambitious R and D program in robotics and remote handling technologies applied to COGEMA spent fuel management facilities in France, with the aim to cover the requirements of the different plant life cycle steps. The paper gives an overview of the important developments that have been carried out by CEA and then transferred to the COGEMA industrial group. The range includes the next generation of servo-manipulators, long range inspection tools and carriers, nuclear versions of industrial robots, radiation hardened electronic systems, interactive environment modeling tools, as well as force-feedback master-slave generic control software for tele-operation systems. Some applications of this development are presented in the paper: - rad-hard electronic modules for robotic equipment which are used by COGEMA in high radiating environment; - long reach articulated carrier for inspection of spent full management blind cells; - new electrical force feedback master/slave system to improve the tele-operation of standard tele-manipulators; - generic control software for tele-manipulators. The results of the robotic program carried out by COGEMA and CEA have been very valuable for the introduction of new technologies inside nuclear industry. Innovative products and sub-systems can be integrated now in a large

Modular magazine for suitable handling of microparts in industry

Science.gov (United States)

Grimme, Ralf; Schmutz, Wolfgang; Schlenker, Dirk; Schuenemann, Matthias; Stock, Achim; Schaefer, Wolfgang

1998-01-01

Microassembly and microadjustment techniques are key technologies in the industrial production of hybrid microelectromechanical systems. One focal point in current microproduction research and engineering is the design and development of high-precision microassembly and microadjustment equipment capable of operating within the framework of flexible automated industrial production. As well as these developments, suitable microassembly tools for industrial use also need to be equipped with interfaces for the supply and delivery of microcomponents. The microassembly process necessitates the supply of microparts in a geometrically defined manner. In order to reduce processing steps and production costs, there is a demand for magazines capable of providing free accessibility to the fixed microcomponents. Commonly used at present are feeding techniques, which originate from the field of semiconductor production. However none of these techniques fully meets the requirements of industrial microassembly technology. A novel modular magazine set, developed and tested in a joint project, is presented here. The magazines are able to hold microcomponents during cleaning, inspection and assembly without nay additional handling steps. The modularity of their design allows for maximum technical flexibility. The modular magazine fits into currently practiced SEMI standards. The design and concept of the magazine enables industrial manufacturers to promote a cost-efficient and flexible precision assembly of microelectromechanical systems.

Interdisciplinary Approach to Tool-Handle Design Based on Medical Imaging

Directory of Open Access Journals (Sweden)

G. Harih

2013-01-01

Full Text Available Products are becoming increasingly complex; therefore, designers are faced with a challenging task to incorporate new functionality, higher performance, and optimal shape design. Traditional user-centered design techniques such as designing with anthropometric data do not incorporate enough subject data to design products with optimal shape for best fit to the target population. To overcome these limitations, we present an interdisciplinary approach with medical imaging. The use of this approach is being presented on the development of an optimal sized and shaped tool handle where the hand is imaged using magnetic resonance imaging machine. The obtained images of the hand are reconstructed and imported into computer-aided design software, where optimal shape of the handle is obtained with Boolean operations. Methods can be used to develop fully customized products with optimal shape to provide best fit to the target population. This increases subjective comfort rating, performance and can prevent acute and cumulative trauma disorders. Provided methods are especially suited for products where high stresses and exceptional performance is expected (high performance tools, professional sports, and military equipment, etc.. With the use of these interdisciplinary methods, the value of the product is increased, which also increases the competitiveness of the product on the market.

How to Handle Abuse

Science.gov (United States)

... Handle Abuse KidsHealth / For Kids / How to Handle Abuse What's in this article? Tell Right Away How Do You Know Something Is Abuse? ... babysitter, teacher, coach, or a bigger kid. Child abuse can happen anywhere — at ... building. Tell Right Away A kid who is being seriously hurt ...

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

International Nuclear Information System (INIS)

Fernandes, Marco A.R.

2009-01-01

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

Waste Handling Building Conceptual Study

International Nuclear Information System (INIS)

G.W. Rowe

2000-01-01

The objective of the ''Waste Handling Building Conceptual Study'' is to develop proposed design requirements for the repository Waste Handling System in sufficient detail to allow the surface facility design to proceed to the License Application effort if the proposed requirements are approved by DOE. Proposed requirements were developed to further refine waste handling facility performance characteristics and design constraints with an emphasis on supporting modular construction, minimizing fuel inventory, and optimizing facility maintainability and dry handling operations. To meet this objective, this study attempts to provide an alternative design to the Site Recommendation design that is flexible, simple, reliable, and can be constructed in phases. The design concept will be input to the ''Modular Design/Construction and Operation Options Report'', which will address the overall program objectives and direction, including options and issues associated with transportation, the subsurface facility, and Total System Life Cycle Cost. This study (herein) is limited to the Waste Handling System and associated fuel staging system

Practices of Handling

DEFF Research Database (Denmark)

Ræbild, Ulla

to touch, pick up, carry, or feel with the hands. Figuratively it is to manage, deal with, direct, train, or control. Additionally, as a noun, a handle is something by which we grasp or open up something. Lastly, handle also has a Nordic root, here meaning to trade, bargain or deal. Together all four...... meanings seem to merge in the fashion design process, thus opening up for an embodied engagement with matter that entails direction giving, organizational management and negotiation. By seeing processes of handling as a key fashion methodological practice, it is possible to divert the discourse away from...... introduces four ways whereby fashion designers apply their own bodies as tools for design; a) re-activating past garment-design experiences, b) testing present garment-design experiences c) probing for new garment-design experiences and d) design of future garment experiences by body proxy. The paper...

Flexible path optimization for the Cask and Plug Remote Handling System in ITER

Energy Technology Data Exchange (ETDEWEB)

Vale, Alberto, E-mail: avale@ipfn.ist.utl.pt [Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Universidade Técnica de Lisboa, Av. Rovisco Pais 1, 1049-001 Lisboa (Portugal); Fonte, Daniel; Valente, Filipe; Ferreira, João [Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Universidade Técnica de Lisboa, Av. Rovisco Pais 1, 1049-001 Lisboa (Portugal); Ribeiro, Isabel [Laboratório de Robótica e Sistemas em Engenharia e Ciência, Instituto Superior Técnico, Universidade Técnica de Lisboa, Av. Rovisco Pais 1, 1049-001 Lisboa (Portugal); Gonzalez, Carmen [Fusion for Energy Agency (F4E), Torres Diagonal Litoral B3, Josep Pla 2, 08019 Barcelona (Spain)

2013-10-15

Highlights: ► Complementary approach for path optimization named free roaming that takes full advantage of the rhombic like kinematics of the Cask and Plug Remote Handling System (CPRHS). ► Possibility to find trajectories not possible in the past using the line guidance developed in a previous work, in particular when moving the Cask Transfer System (CTS) beneath the pallet or in rescue missions. ► Methodology that maximizes the common parts of different trajectories in the same level of ITER buildings. -- Abstract: The Cask and Plug Remote Handling System (CPRHS) provides the means for the remote transfer of in-vessel components and remote handling equipment between the Hot Cell Building and the Tokamak Building in ITER along pre-defined optimized trajectories. A first approach for CPRHS path optimization was previously proposed using line guidance as the navigation methodology to be adopted. This approach might not lead to feasible paths in new situations not considered during the previous work, as rescue operations. This paper addresses this problem by presenting a complementary approach for path optimization inspired in rigid body dynamics that takes full advantage of the rhombic like kinematics of the CPRHS. It also presents a methodology that maximizes the common parts of different trajectories in the same level of ITER buildings. The results gathered from 500 optimized trajectories are summarized. Conclusions and open issues are presented and discussed.

Progress in ion implantation equipment for semiconductor manufacturing

International Nuclear Information System (INIS)

Kawai, Tadashi; Naito, Masao

1987-01-01

In the semiconductor device manufacturing industry, ion implantation systems are used to dope semiconductor substrates with impurities that act as donor or acceptor. In an ion implantation system, required impurity ions are generated from an ion source, subjected to mass analysis, accelerated, converged and implanted in semiconductor wafers. High-tension arc tends to cause troubles in these systems, but improvement in design increased the average operation rate of medium-power systems from bout 70 percent to 90 percent during the past 10 years. Freeman type ion sources have replaced most RF ion sources and cold cathode PIG sources, which had been widely used until the early 1970s. Many of the recent ion sources are equipped with a P and As vaporizer to increase the beam intensity. By an increased beam intensity or decreased handling time in combination with an automatic handling system, the throughput has reached 330 wafers per hour for 10 second implantation. The yield has increased due to the development of improved scanning methods, vacuum devices such as cryopump, and processes and apparatus that serve for preventing particles from being contained in micro-devices. Various other improvements have been made to permit efficient production. (Nogami, K.)

PFP Commercial Grade Food Pack Cans for Plutonium Handling and Storage Critical Characteristics

International Nuclear Information System (INIS)

BONADIE, E.P.

1999-01-01

This document specifies the critical characteristics for Commercial Grade Items (CGI) procured for 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. The changes in these specifications have no detrimental effect on the descriptions and parameters related to handling plutonium solids in the authorization basis. Because no parameters or sequences exceed the limits described in the authorization bases, no accident or abnormal conditions are affected. The specifications prescribed in this critical characteristics document do not represent an unreviewed safety question

Grain Handling and Storage.

Science.gov (United States)

Harris, Troy G.; Minor, John

This text for a secondary- or postecondary-level course in grain handling and storage contains ten chapters. Chapter titles are (1) Introduction to Grain Handling and Storage, (2) Elevator Safety, (3) Grain Grading and Seed Identification, (4) Moisture Control, (5) Insect and Rodent Control, (6) Grain Inventory Control, (7) Elevator Maintenance,…

Cleaning and sterilisation of infant feeding equipment: a systematic review.

Science.gov (United States)

Renfrew, Mary J; McLoughlin, Marie; McFadden, Alison

2008-11-01

To assess the clinical and cost-effectiveness of different methods of cleaning and sterilisation of infant feeding equipment used in the home. Systematic review of studies from developed countries on the effectiveness of methods of cleaning and sterilisation of infant feeding equipment used in the home. A brief telephone survey of UK-based manufacturers of infant feeding equipment and formula to ascertain the evidence base used for their recommendations, and a comparison of current relevant guidelines in developed countries, informed the work. National guidelines from six countries demonstrated variation and lack of evidence to support current guidance. Manufacturers did not report evidence of effectiveness to support their recommendations. Nine studies were identified; eight conducted between 1962 and 1985 and one in 1997. All had methodological weaknesses. Hand-washing was identified as fundamentally important. Health professionals were reported as not providing appropriate education on the importance and methods of cleaning and sterilisation. Mothers of subsequent babies and women from lower socio-economic groups were less likely to follow recommended procedures. There is a lack of good-quality evidence on effective ways of cleaning and sterilising infant feeding equipment in the home. The evidence base does not answer the question about which of the methods in common use is most effective or most likely to be used by parents. Hand-washing before handling feeding equipment remains important. Further research on the range of methods used in the home environment, including assessment of the views of parents and carers, is required.

Simulator for candu600 fuel handling system. environmental implications

International Nuclear Information System (INIS)

Vulpe, S.; Valeca, S.; Predescu, D.

2016-01-01

Personnel training are a main topic in the security and reliability of several industrial processes. The simulator is a physical device that reproduces real operation of a device used in a production process technology. Typically, a simulator is intended to train the operators to work properly with the real device in the production process, but simulators can be involved frequently in the research and evaluation of performance of human operators. Process simulation has a significant role in the training of operators of nuclear plants. To ensure the safe operation, protection of workers and the environment, of any nuclear power plant, the training of its operators in all operating modes of the plant is essential. A trained operator who can handle any emergency in a controlled manner, without panic, protecting equipment and personnel is an asset for a nuclear power plant. (authors)

Conceptual design of the handling and storage system of the spent target vessel for neutron scattering facility 2

International Nuclear Information System (INIS)

Adachi, Junichi; Kaminaga, Masanori; Sasaki, Shinobu; Haga, Katsuhiro; Aso, Tomokazu; Kinoshita, Hidetaka; Hino, Ryutaro

2002-01-01

In designing the neutron scattering facility, a spent target vessel should be replaced with remote handling devices in order to protect radioactive exposure, since it would be highly activated through the high energy neutron irradiation caused by the spallation reaction between mercury of the target material and the MW-class proton beam. In the storage of the spent target vessel, it is necessary to consider decay heat of the target vessel and mercury contamination caused by vaporization of the residual mercury in the vessel. A conceptual design has been carried out to establish basic concept and to clarify its specification of main equipments on handling and storage systems for the spent target vessel. This report presents the basic concept and a system plot plan based on latest design works of remote handling devices such as a spent target vessel storage cask and a target vessel exchange trolley, which aim at reasonability and simplification. In addition, storage systems for the spent moderator vessel, the spent proton beam window and the spent reflector vessel are also investigated based on the plot plan. (author)

Cask system design guidance for robotic handling

International Nuclear Information System (INIS)

Griesmeyer, J.M.; Drotning, W.D.; Morimoto, A.K.; Bennett, P.C.

1990-10-01

Remote automated cask handling has the potential to reduce both the occupational exposure and the time required to process a nuclear waste transport cask at a handling facility. The ongoing Advanced Handling Technologies Project (AHTP) at Sandia National Laboratories is described. AHTP was initiated to explore the use of advanced robotic systems to perform cask handling operations at handling facilities for radioactive waste, and to provide guidance to cask designers regarding the impact of robotic handling on cask design. The proof-of-concept robotic systems developed in AHTP are intended to extrapolate from currently available commercial systems to the systems that will be available by the time that a repository would be open for operation. The project investigates those cask handling operations that would be performed at a nuclear waste repository facility during cask receiving and handling. The ongoing AHTP indicates that design guidance, rather than design specification, is appropriate, since the requirements for robotic handling do not place severe restrictions on cask design but rather focus on attention to detail and design for limited dexterity. The cask system design features that facilitate robotic handling operations are discussed, and results obtained from AHTP design and operation experience are summarized. The application of these design considerations is illustrated by discussion of the robot systems and their operation on cask feature mock-ups used in the AHTP project. 11 refs., 11 figs

Production management of window handles

Directory of Open Access Journals (Sweden)

Manuela Ingaldi

2014-12-01

Full Text Available In the chapter a company involved in the production of aluminum window and door handles was presented. The main customers of the company are primarily companies which produce PCV joinery and wholesalers supplying these companies. One chosen product from the research company - a single-arm pin-lift window handle - was described and its production process depicted technologically. The chapter also includes SWOT analysis conducted in the research company and the value stream of the single-arm pin-lift window handle.

7 CFR 58.443 - Whey handling.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Whey handling. 58.443 Section 58.443 Agriculture... Procedures § 58.443 Whey handling. (a) Adequate sanitary facilities shall be provided for the handling of whey. If outside, necessary precautions shall be taken to minimize flies, insects and development of...

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

Factors affecting food handling Practices among food handlers of Dangila town food and drink establishments, North West Ethiopia

Science.gov (United States)

2014-01-01

Background Food borne diseases are major health problems in developed and developing countries including Ethiopia. The problem is more noticeable in developing countries due to prevailing poor food handling and sanitation practices, inadequate food safety laws, weak regulatory systems, lack of financial resources to invest on safer equipments, and lack of education for food handlers. Methods The objective of this study was to assess food handling practice and associated factors among food handlers working in food and drinking establishments of Dangila town, North West Ethiopia. Cross-sectional quantitative study design was conducted among 406 food handlers working in 105 food and drink establishments from July to August 2013 in Dangila town. Data were collected using face to face interview with pretested structured questionnaire and physical observation. Result The mean age of the respondents was 22.7 ± 4.2 years of which 62.8% of the food handlers were females. Two hundred thirteen (52.5%) of food handlers had good food handling practices. Marital status (AOR = 7.52, 95% CI, 1.45-38.97), monthly income (AOR = 0.395, 95% CI, 0.25-0.62), knowledge about food handling (AOR = 1.69, 95% CI, 1.05-2.73), existence of shower facility (AOR = 1.89, 95% CI, 1.12-3.21) and separate dressing room (AOR = 1.97, 95% CI, 1.11-3.49) were found to be significantly associated with good food handling Practices. Conclusion Above half of food handlers had good food handling practices. Marital status, monthly income, knowledge status, existence of shower facility, existence of separate dressing room and presence of insect and rodent were factors associated with food handling Practices. PMID:24908104

Development of commercial robots for radwaste handling

International Nuclear Information System (INIS)

Colborn, K.A.

1988-01-01

The cost and dose burden associated with low level radwaste handling activities is a matter of increasing concern to the commercial nuclear power industry. This concern is evidenced by the fact that many utilities have begun to revaluate waste generation, handling, and disposal activities at their plants in an effort to improve their overall radwaste handling operations. This paper reports on the project Robots for Radwaste Handling, to identify the potential of robots to improve radwaste handling operations. The project has focussed on the potential of remote or automated technology to improve well defined, recognizable radwaste operations. The project focussed on repetitive, low skill level radwaste handling and decontamination tasks which involve significant radiation exposure

Market study on the Mexican market for electrical distribution equipment

International Nuclear Information System (INIS)

1991-01-01

A brief historical survey of the development of the Mexican electric power sector is presented, along with an overview of the state of the Mexican economy since the late 1980s and the present characteristics of the Mexican electricity sector. The Mexican market for electric power generation and distribution equipment is then assessed, from the perspective of Canadian suppliers and manufacturers intending to enter this market. Projected consumption of electrical generation and distribution equipment in Mexico for 1994 is estimated at US$1,035,600,000 ($719.4 million in production, $356.9 million in imports, and $40.7 million in exports). This market increased 12.3% in 1990, and since power demand in Mexico has been growing faster than growth in capacity, it is possible that investments in the electricity sector will grow at faster rates. Items which are traditionally imported include nuclear reactors and related equipment, boilers, turbines, power breakers, valves, coal and ash handling equipment, relays, automatic controls, and chemical treatment equipment. The USA has the greatest share of the import market with 35%, followed by Japan (22%), Switzerland (18%), and Germany (13%). Canadian exports have concentrated on distribution equipment and only totalled $1.7 million in 1990. Electricity is distributed to some 16.6 million users over a national interconnected system having total installed capacity of 30,513 MW in 1991. There are plans to increase capacity by 9.7 GW by 1994 and another 37.4-47.8 GW between 1995 and 2010. Projections of electricity needs by region are listed along with the new power plants targeted for investment. Market liberalization and lowering of tariffs have made the Mexican market more accessible to exporters. 8 tabs

Contribution of the C.E.A. to standardization of nuclear plant equipments

International Nuclear Information System (INIS)

Dumax, P.; Seran, R.

1980-01-01

In research and production laboratories working in the nuclear field standardization of equipments greatly improves the profits of the installation and the protection of individuals and goods. The standardization effort on technical equipments of shielding, handling, detection and safety (so called P.M.D.S.) initiated by the C.E.A. in 1967 is being carried out now within the Institute of Protection and Nuclear Safety (I.P.S.N.) by a technical Service specialized in protection and dosimetry (S.T.E.P.D.). Its purpose is to establish standardization documents for internal use and to take part in the work of official standardization organizations. The benefits of standardization are reviewed. The achievements of the various working groups common to C.E.A. centers are stated and the documents published or to be published are listed [fr

Radiological safety aspects during handling of adjuster rod (cobalt-60) samples at Cirus

International Nuclear Information System (INIS)

Yadav, R.K.B.; Prasad, S.K.; Khuspe, R.R.; Babu, K.S.; Kamble, M.K.; Deshpande, S.B.; Srivastava, Alok; Ramesh, N.; Sharma, R.C.

2008-01-01

Cobalt -60 produced from the irradiation of the 59 Co capsules in adjuster rod of Cirus is used in many medical and industrial applications such as radiation therapy, sterilization of agricultural products, sterilization of medical equipment, industrial gamma exposure devices, nucleonic gauging sources etc. Two adjuster rods used for adjusting small reactivity loads (3.5 mk at 40 MW) in reactor contain thirty 59 Co slugs each. The 59 Co slugs are in the form of small capsules. These slugs were irradiated for nearly 3 years of full power operation. Since the amount of activity handled in the adjuster rod is very high (35 - 40 kCi), adequate radiological safety coverage is to be provided during the transfer of adjuster rod from the reactor pile to Tray Rod Facility (TRF) and during remote handling and loading of adjuster rod samples in shipping flask at TRF. Radiation fields observed are 0.4 - 3.0 Gy/h. In Cirus, falling of Adjuster rod from vertical flask at top of pile could result in declaration of evacuation emergency due to potential hazards associated with the high radiation field (∼26 Gy/h at 1m) of 60 Co slugs. Entire process of remote handling is viewed through lead glass and movement of samples is carried out with the help of a pair of master slave manipulator (MSM) arms. TRF with full samples give a radiation background of 0.2 - 20 mGy/h, requiring control of movement of personnel in the area. This paper explains in detail about the health physics aspects during handling of adjuster rod from reactor pile to TRF and back to pile, unloading and loading of radioisotope samples, operational radiation protection experience gained and collective dose consumed for the above transfer and loading job. The collective dose consumed in the handling of two adjuster rods is 8.7 per-mSv. (author)

Preference Handling for Artificial Intelligence

OpenAIRE

Goldsmith, Judy; University of Kentucky; Junker, Ulrich; ILOG

2009-01-01

This article explains the benefits of preferences for AI systems and draws a picture of current AI research on preference handling. It thus provides an introduction to the topics covered by this special issue on preference handling.

Religious Serpent Handling and Community Relations.

Science.gov (United States)

Williamson, W Paul; Hood, Ralph W

2015-01-01

Christian serpent handling sects of Appalachia comprise a community that has long been mischaracterized and marginalized by the larger communities surrounding them. To explore this dynamic, this article traces the emergence of serpent handling in Appalachia and the emergence of anti-serpent-handling state laws, which eventually failed to curb the practice, as local communities gave serpent handling groups support. We present two studies to consider for improving community relations with serpent handling sects. In study 1, we present data relating the incidence of reported serpent-bite deaths with the rise of anti-serpent-handling laws and their eventual abatement, based on increasing acceptance of serpent handlers by the larger community. Study 2 presents interview data on serpent bites and death that provide explanations for these events from the cultural and religious perspective. We conclude that first-hand knowledge about serpent handlers, and other marginalized groups, helps to lessen suspicion and allows them to be seen as not much different, which are tendencies that are important for promoting inter-community harmony.

Urenco`s experience of UF{sub 6} handling

Energy Technology Data Exchange (ETDEWEB)

Saelmans, F. [Urenco Almelo (Netherlands); Scane, C. [Urenco Capenhurst (United Kingdom); Christofzik, J. [Urenco Gronau (Germany)

1991-12-31

Urenco operates enrichment plants at three sites, Almelo (Netherlands), Capenhurst (United Kingdom) and Gronau (Germany). Current installed separative work capacity is 2,500 tSWpa. Since 1971, when the first pilot plants were built, enrichment production has totalled 18,000 tSW. During this last 20 years over 3,500 48 containers of UF{sub 6} have been fed to the plants, over 3,700 30 containers have been filled with product and delivered successfully to Urenco`s customers worldwide and over 3,000 48 containers of depleted tails have been filled and have either been returned to customers or retained for long term storage on site. The paper gives a brief outline of Urenco`s experience in handling UF{sub 6}: the equipment and methods used in receiving, feeding, filling, blending, liquid sampling, storing, moving on site and despatching of UF{sub 6} containers. Some of the difficulties experienced with UF{sub 6} containers are appended.

Prevalence of Visible and Occult Blood on Airway Management Equipment Used Outside the Operating Room

Science.gov (United States)

1999-10-01

instruments that make direct contact with mucus membranes such as laryngoscopy handles and blades, Magill forceps and stylets, and fiberoptic laryngoscopy...saliva in dental procedures, human breast milk , any body fluid that is visibly contaminated with blood, and all body fluids in situations where it is...noted on mucus membranes and airway management equipment reinforces the fact that all anesthesia providers are at risk for acquiring or transmitting

How Retailers Handle Complaint Management

DEFF Research Database (Denmark)

Hansen, Torben; Wilke, Ricky; Zaichkowsky, Judy

2009-01-01

This article fills a gap in the literature by providing insight about the handling of complaint management (CM) across a large cross section of retailers in the grocery, furniture, electronic and auto sectors. Determinants of retailers’ CM handling are investigated and insight is gained as to the......This article fills a gap in the literature by providing insight about the handling of complaint management (CM) across a large cross section of retailers in the grocery, furniture, electronic and auto sectors. Determinants of retailers’ CM handling are investigated and insight is gained...... as to the links between CM and redress of consumers’ complaints. The results suggest that retailers who attach large negative consequences to consumer dissatisfaction are more likely than other retailers to develop a positive strategic view on customer complaining, but at the same time an increase in perceived...

Effectiveness of Medical-Care Equipment Management: Case Study in a Public Hospital in Belo Horizonte / Minas Gerais

Directory of Open Access Journals (Sweden)

Estevão Maria Campolina de Oliveira

2017-03-01

Full Text Available This study aimed to identify and analyze the factors that contribute to the effectiveness of the management of medical-care equipment at the Hospital of Federal University of Minas Gerais (HC-UFMG in Belo Horizonte, Minas Gerais. To achieve this goal, a case study was performed along with a field research at HC-UFMG, through interviews using a semi-structured questionnaire to professionals who handle and operate medical-care equipment; professionals who provide maintenance on equipment, and professionals who manage the operation and maintenance of equipment. As a strategy for discussion of the results, the Collective Subject Discourse (CSD was used supported by the analysis of the Central Idea (CI of each question or question groups. According to the CSD results, it was possible to identify factors that contribute to the effectiveness of the management of medical-care equipment, such as: professional qualification; practical knowledge; work professionalization; supervision focused on evaluation, development, results and continuous improvement; professional updating and technical support; individual accountability; adequate infrastructure; and implementation of equipment management planning. These factors indicate, to the institutions, opportunities of culture change and organizational growth.

Reviews Equipment: Data logger Book: Imagined Worlds Equipment: Mini data loggers Equipment: PICAXE-18M2 data logger Books: Engineering: A Very Short Introduction and To Engineer Is Human Book: Soap, Science, & Flat-Screen TVs Equipment: uLog and SensorLab Web Watch

Science.gov (United States)

2012-07-01

WE RECOMMEND Data logger Fourier NOVA LINK: data logging and analysis To Engineer is Human Engineering: essays and insights Soap, Science, & Flat-Screen TVs People, politics, business and science overlap uLog sensors and sensor adapter A new addition to the LogIT range offers simplicity and ease of use WORTH A LOOK Imagined Worlds Socio-scientific predictions for the future Mini light data logger and mini temperature data logger Small-scale equipment for schools SensorLab Plus LogIT's supporting software, with extra features HANDLE WITH CARE CAXE110P PICAXE-18M2 data logger Data logger 'on view' but disappoints Engineering: A Very Short Introduction A broad-brush treatment fails to satisfy WEB WATCH Two very different websites for students: advanced physics questions answered and a more general BBC science resource

7 CFR 926.9 - Handle.

Science.gov (United States)

2010-01-01

... the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements and Orders; Fruits, Vegetables, Nuts), DEPARTMENT OF AGRICULTURE DATA COLLECTION, REPORTING AND RECORDKEEPING REQUIREMENTS APPLICABLE TO CRANBERRIES NOT SUBJECT TO THE CRANBERRY MARKETING ORDER § 926.9 Handle. Handle...

Remote handling at LAMPF

International Nuclear Information System (INIS)

Grisham, D.L.; Lambert, J.E.

1983-01-01

Experimental area A at the Clinton P. Anderson Meson Physics Facility (LAMPF) encompasses a large area. Presently there are four experimental target cells along the main proton beam line that have become highly radioactive, thus dictating that all maintenance be performed remotely. The Monitor remote handling system was developed to perform in situ maintenance at any location within area A. Due to the complexity of experimental systems and confined space, conventional remote handling methods based upon hot cell and/or hot bay concepts are not workable. Contrary to conventional remote handling which require special tooling for each specifically planned operation, the Monitor concept is aimed at providing a totally flexible system capable of remotely performing general mechanical and electrical maintenance operations using standard tools. The Monitor system is described

Construction and equipment requirements for installations and laboratories handling unsealed radioactive materials in low and medium activity - Proposal of an Israeli standard

Energy Technology Data Exchange (ETDEWEB)

Ben-Shlomo, A; Schlesinger, T; Barshad, M [Soreq Nuclear Research Center, Yavne (Israel)

1993-10-01

Working with unsealed radioactive materials involves risks of internal or external exposure to ionizing radiation. Exposure of human beings to ionizing radiation involves adverse health effects and must be prevented or at least reduced to reasonable levels. Radiation sources in this work are unsealed radioactive materials, that may be solids, liquid or in gaseous states, and in varying toxic levels. Various works and actions that are performed on the unsealed radioactive materials have varying potentials of dispersion, contamination and exposure, so that the combination of the type of work activity, isotope characteristics and physical state dictate the internal and external exposure risks. In order to limit the exposure of the personnel of installations and laboratories which deals with unsealed radioactive materials, national and international authorities and organizations standards and procedures for the requirements of construction and equipment of such installations and laboratories. This document means to be a proposal for an Israeli standard requirements for equipment and construction of installations working with low and medium activity unsealed radioactive materials. The targets for defining the, construction and equipment, requirements are: a. Safety and proper protection of personnel and public from external and internal exposure while the work is done properly. Proper protection against the risk of contaminating the environment. c. Standardization of requirements. d. Proper design of installations and laboratories. e. Supply means for evaluation and reduction of construction costs.The equipment detailed here refers to fixed (none movable) equipment which is a part of the construction of the laboratory or installation, unless specified otherwise. The document starts with a review of the recommendations of some international organizations (WHO, IAEA, NRPB) for construction and equipment requirements for these laboratories and installations. Then the

MRI of meniscal bucket-handle tears

Energy Technology Data Exchange (ETDEWEB)

Magee, T.H.; Hinson, G.W. [Menorah Medical Center, Overland Park, KS (United States). Dept. of Radiology

1998-09-01

A meniscal bucket-handle tear is a tear with an attached fragment displaced from the meniscus of the knee joint. Low sensitivity of MRI for detection of bucket-handle tears (64% as compared with arthroscopy) has been reported previously. We report increased sensitivity for detecting bucket-handle tears with the use of coronal short tau inversion recovery (STIR) images. Results. By using four criteria for diagnosis of meniscal bucket-handle tears, our overall sensitivity compared with arthroscopy was 93% (28 of 30 meniscal bucket-handle tears seen at arthroscopy were detected by MRI). The meniscal fragment was well visualized in all 28 cases on coronal STIR images. The double posterior cruciate ligament sign was seen in 8 of 30 cases, the flipped meniscus was seen in 10 of 30 cases and a fragment in the intercondylar notch was seen in 18 of 30 cases. (orig.)

Licence template for mobile handling and storage of radioactive substances for the nondestructive testing of materials; Mustergenehmigung zur ortsveraenderlichen Verwendung und Lagerung radioaktiver Stoffe im Rahmen der zerstoerungsfreien Materialpruefung

Energy Technology Data Exchange (ETDEWEB)

Lange, A. [Niedersaechsisches Ministerium fuer Umwelt, Energie und Klimaschutz (Germany); Schumann, J. [Landesamt fuer Arbeitsschutz, Gesundheitsschutz und technische Sicherheit, Berlin (Germany); Huhn, W.

2016-07-01

The Technical Committee ''Radiation Protection'' (Fachausschuss ''Strahlenschutz'') and the Laender Committee ''X-ray ordinance'' (Laenderausschuss ''Roentgenverordnung'') have appointed a working group for the formulation of licence templates for the nationwide use of X-ray equipment or handling of radioactive substances. To date, the following licence templates have been adopted: - Mobile operation of X-ray equipment under technical radiography to the coarse structural analysis in material testing; - Mobile operation of a handheld X-ray fluorescence system; - Mobile operation of a flash X-ray system; - Operation of an X-ray system for teleradiology The licence template ''Mobile handling and storage of radioactive substances for the nondestructive testing of materials'' is scheduled for publication. The licence template ''Practices in external facilities and installations'' is currently being revised. The licence template ''Mobile handling and storage of radioactive substances for the nondestructive testing of materials'' is used as an example to demonstrate the legal framework and the results of the working group.

Sophisticated fuel handling system evolved

International Nuclear Information System (INIS)

Ross, D.A.

1988-01-01

The control systems at Sellafield fuel handling plant are described. The requirements called for built-in diagnostic features as well as the ability to handle a large sequencing application. Speed was also important; responses better than 50ms were required. The control systems are used to automate operations within each of the three main process caves - two Magnox fuel decanners and an advanced gas-cooled reactor fuel dismantler. The fuel route within the fuel handling plant is illustrated and described. ASPIC (Automated Sequence Package for Industrial Control) which was developed as a controller for the plant processes is described. (U.K.)

TFTR tritium handling concepts

International Nuclear Information System (INIS)

Garber, H.J.

1976-01-01

The Tokamak Fusion Test Reactor, to be located on the Princeton Forrestal Campus, is expected to operate with 1 to 2.5 MA tritium--deuterium plasmas, with the pulses involving injection of 50 to 150 Ci (5 to 16 mg) of tritium. Attainment of fusion conditions is based on generation of an approximately 1 keV tritium plasma by ohmic heating and conversion to a moderately hot tritium--deuterium ion plasma by injection of a ''preheating'' deuterium neutral beam (40 to 80 keV), followed by injection of a ''reacting'' beam of high energy neutral deuterium (120 to 150 keV). Additionally, compressions accompany the beam injections. Environmental, safety and cost considerations led to the decision to limit the amount of tritium gas on-site to that required for an experiment, maintaining all other tritium in ''solidified'' form. The form of the tritium supply is as uranium tritide, while the spent tritium and other hydrogen isotopes are getter-trapped by zirconium--aluminum alloy. The issues treated include: (1) design concepts for the tritium generator and its purification, dispensing, replenishment, containment, and containment--cleanup systems; (2) features of the spent plasma trapping system, particularly the regenerable absorption cartridges, their integration into the vacuum system, and the handling of non-getterables; (3) tritium permeation through the equipment and the anticipated releases to the environment; (4) overview of the tritium related ventilation systems; and (5) design bases for the facility's tritium clean-up systems

Development of radiation-hard electric connector with ball bearing for in-vessel remote maintenance equipment of ITER

International Nuclear Information System (INIS)

Ito, Akira; Obara, Kenjiro; Tada, Eisuke; Morita, Yousuke; Yagi, Toshiaki; Iida, Kazuhisa; Sato, Masaru.

1997-12-01

Development of radiation-hard electric connector with ball bearing for in-vessel remote maintenance equipment of ITER (International Thermonuclear Experimental Reactor) has been conducted. Since the in-vessel remote maintenance equipment is operated under the condition of 10 6 R/h gamma ray dose rate, the electric connector has to be radiation hard for an accumulation dose of 10 10 R. In addition, the simple attachment/removal mechanism is essential for remote operation. For this, the alumina (Al203) ceramics and a ball bearing were adopted to electric insulator and plug (male) of connector, respectively. The handling tests on attachment/removal of the connector were conducted by using master slave manipulator and general purpose robot with handling tool, and as a result, the validity of the attachment/removal mechanism was verified. In the gamma ray irradiation tests, which are under way, no degradation in break down voltage (1000V 1min.) up to 10 10 R was confirmed. However insulation resistance and contact resistance between contact pin and contact socket were deteriorated in proportion to the accumulation dose. Increase of contact resistance is considered due to an erosion of contact pin. (author)

The natural angle between the hand and handle and the effect of handle orientation on wrist radial/ulnar deviation during maximal push exertions.

Science.gov (United States)

Young, Justin G; Lin, Jia-Hua; Chang, Chien-Chi; McGorry, Raymond W

2013-01-01

The purpose of this experiment was to quantify the natural angle between the hand and a handle, and to investigate three design factors: handle rotation, handle tilt and between-handle width on the natural angle as well as resultant wrist radial/ulnar deviation ('RUD') for pushing tasks. Photographs taken of the right upper limb of 31 participants (14 women and 17 men) performing maximal seated push exertions on different handles were analysed. Natural hand/handle angle and RUD were assessed. It was found that all of the three design factors significantly affected natural handle angle and wrist RUD, but participant gender did not. The natural angle between the hand and the cylindrical handle was 65 ± 7°. Wrist deviation was reduced for handles that were rotated 0° (horizontal) and at the narrow width (31 cm). Handles that were tilted forward 15° reduced radial deviation consistently (12-13°) across handle conditions. Manual materials handling (MMH) tasks involving pushing have been related to increased risk of musculoskeletal injury. This study shows that handle orientation influences hand and wrist posture during pushing, and suggests that the design of push handles on carts and other MMH aids can be improved by adjusting their orientation to fit the natural interface between the hand and handle.

9 CFR 3.118 - Handling.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Handling. 3.118 Section 3.118 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE ANIMAL WELFARE STANDARDS Specifications for the Humane Handling, Care, Treatment, and Transportation of Marine...

Safety measuring for sodium handling

Energy Technology Data Exchange (ETDEWEB)

Jeong, Ji Young; Jeong, K C; Kim, T J; Kim, B H; Choi, J H

2001-09-01

This is the report for the safety measures of sodium handling. These contents are prerequisites for the development of sodium technology and thus the workers participate in sodium handling and experiments have to know them perfectly. As an appendix, the relating parts of the laws are presented.

Development of spent fuel remote handling technology

Energy Technology Data Exchange (ETDEWEB)

Park, B. S.; Yoon, J. S.; Hong, H. D. (and others)

2007-02-15

In this research, the remote handling technology was developed for the ACP application. The ACP gives a possible solution to reduce the rapidly cumulative amount of spent fuels generated from the nuclear power plants in Korea. The remote technologies developed in this work are a slitting device, a voloxidizer, a modified telescopic servo manipulator and a digital mock-up. A slitting device was developed to declad the spent fuel rod-cuts and collect the spent fuel UO{sub 2} pellets. A voloxidizer was developed to convert the spent fuel UO{sub 2} pellets obtained from the slitting process in to U{sub 3}O{sub 8} powder. Experiments were performed to test the capabilities and remote operation of the developed slitting device and voloxidizer by using simulated rod-cuts and fuel in the ACP hot cell. A telescopic servo manipulator was redesigned and manufactured improving the structure of the prototype. This servo manipulator was installed in the ACP hot cell, and the target module for maintenance of the process equipment was selected. The optimal procedures for remote operation were made through the maintenance tests by using the servo manipulator. The ACP digital mockup in a virtual environment was established to secure a reliability and safety of remote operation and maintenance. The simulation for the remote operation and maintenance was implemented and the operability was analyzed. A digital mockup about the preliminary conceptual design of an enginnering-scale ACP was established, and an analysis about a scale of facility and remote handling was accomplished. The real-time diagnostic technique was developed to detect the possible fault accidents of the slitting device. An assessment of radiation effect for various sensors was also conducted in the radiation environment.

Radial Internal Material Handling System (RIMS) for Circular Habitat Volumes

Science.gov (United States)

Howe, Alan S.; Haselschwardt, Sally; Bogatko, Alex; Humphrey, Brian; Patel, Amit

2013-01-01

On planetary surfaces, pressurized human habitable volumes will require a means to carry equipment around within the volume of the habitat, regardless of the partial gravity (Earth, Moon, Mars, etc.). On the NASA Habitat Demonstration Unit (HDU), a vertical cylindrical volume, it was determined that a variety of heavy items would need to be carried back and forth from deployed locations to the General Maintenance Work Station (GMWS) when in need of repair, and other equipment may need to be carried inside for repairs, such as rover parts and other external equipment. The vertical cylindrical volume of the HDU lent itself to a circular overhead track and hoist system that allows lifting of heavy objects from anywhere in the habitat to any other point in the habitat interior. In addition, the system is able to hand-off lifted items to other material handling systems through the side hatches, such as through an airlock. The overhead system consists of two concentric circle tracks that have a movable beam between them. The beam has a hoist carriage that can move back and forth on the beam. Therefore, the entire system acts like a bridge crane curved around to meet itself in a circle. The novelty of the system is in its configuration, and how it interfaces with the volume of the HDU habitat. Similar to how a bridge crane allows coverage for an entire rectangular volume, the RIMS system covers a circular volume. The RIMS system is the first generation of what may be applied to future planetary surface vertical cylinder habitats on the Moon or on Mars.

Asthma, guides for diagnostic and handling

International Nuclear Information System (INIS)

Salgado, Carlos E; Caballero A, Andres S; Garcia G, Elizabeth

1999-01-01

The paper defines the asthma, includes topics as diagnostic, handling of the asthma, special situations as asthma and pregnancy, handling of the asthmatic patient's perioperatory and occupational asthma

Safety and availability of the fuel handling system at Embalse nuclear power plant

International Nuclear Information System (INIS)

Santaliz, Jorge O.; Paredes, Juan A.

1998-01-01

The paper attempts the Fuel Handling (F/H) System maintenance and operating methodology at the Embalse Power Station. It doesn't refer to the F/H process, because it's common and well known by all the CANDU Stations. Instead of that, the presentation will be focused on people qualification, training and selection. Also the key subjects for a smooth and successful operation. Additionally will be remarked the human aspect and the role of the person in the organization. The safe and reliable operation of the CNE Fuel Handling System has been always target, supported by the operational experience. The accountability and fitness for the job were the main qualification for the crew members. They have very clear their role and the importance of equipment which they are operating or manipulating. The person who has greater experience and responsibility must struggle continuously to keep the safe and confident operation. Also we have to increase permanently our knowledge with a greater training and experience exchange with another CANDU 6 Station, like this Conference which let us to grow as persons and technicians. It also allows our utility to have access to other realities and work methods. (authors)

Trends and applications of integrated automated ultra-trace sample handling and analysis (T9)

International Nuclear Information System (INIS)

Kingston, H.M.S.; Ye Han; Stewart, L.; Link, D.

2002-01-01

Full text: Automated analysis, sub-ppt detection limits, and the trend toward speciated analysis (rather than just elemental analysis) force the innovation of sophisticated and integrated sample preparation and analysis techniques. Traditionally, the ability to handle samples at ppt and sub-ppt levels has been limited to clean laboratories and special sample handling techniques and equipment. The world of sample handling has passed a threshold where older or 'old fashioned' traditional techniques no longer provide the ability to see the sample due to the influence of the analytical blank and the fragile nature of the analyte. When samples require decomposition, extraction, separation and manipulation, application of newer more sophisticated sample handling systems are emerging that enable ultra-trace analysis and species manipulation. In addition, new instrumentation has emerged which integrate sample preparation and analysis to enable on-line near real-time analysis. Examples of those newer sample-handling methods will be discussed and current examples provided as alternatives to traditional sample handling. Two new techniques applying ultra-trace microwave energy enhanced sample handling have been developed that permit sample separation and refinement while performing species manipulation during decomposition. A demonstration, that applies to semiconductor materials, will be presented. Next, a new approach to the old problem of sample evaporation without losses will be demonstrated that is capable of retaining all elements and species tested. Both of those methods require microwave energy manipulation in specialized systems and are not accessible through convection, conduction, or other traditional energy applications. A new automated integrated method for handling samples for ultra-trace analysis has been developed. An on-line near real-time measurement system will be described that enables many new automated sample handling and measurement capabilities. This

Remote-handled transuranic system assessment appendices. Volume 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-11-01

Volume 2 of this report contains six appendices to the report: Inventory and generation of remote-handled transuranic waste; Remote-handled transuranic waste site storage; Characterization of remote-handled transuranic waste; RH-TRU waste treatment alternatives system analysis; Packaging and transportation study; and Remote-handled transuranic waste disposal alternatives.

Remote-handled transuranic system assessment appendices. Volume 2

International Nuclear Information System (INIS)

1995-11-01

Volume 2 of this report contains six appendices to the report: Inventory and generation of remote-handled transuranic waste; Remote-handled transuranic waste site storage; Characterization of remote-handled transuranic waste; RH-TRU waste treatment alternatives system analysis; Packaging and transportation study; and Remote-handled transuranic waste disposal alternatives

Cleaning, disassembly, and requalification of the FFTF in vessel handling machine

International Nuclear Information System (INIS)

Coops, W.J.

1977-10-01

The Engineering Model In Vessel Handling Machine (IVHM) was successfully removed, cleaned, disassembled, inspected, reassembled and reinstalled into the sodium test vessel at Richland, Washington. This was the first time in the United States a full size operational sodium wetted machine has been cleaned by the water vapor nitrogen process and requalified for operation. The work utilized an atmospheric control system during removal, a tank type water vapor nitrogen cleaning system and an open ''hands on'' disassembly and assembly stand. Results of the work indicate the tools, process and equipment are adequate for the non-radioactive maintenance sequence. Additionally, the work proves that a machine of this complexity can be successfully cleaned, maintained and re-used without the need to replace a large percentage of the sodium wetted parts

DDOS ATTACK DETECTION SIMULATION AND HANDLING MECHANISM

Directory of Open Access Journals (Sweden)

Ahmad Sanmorino

2013-11-01

Full Text Available In this study we discuss how to handle DDoS attack that coming from the attacker by using detection method and handling mechanism. Detection perform by comparing number of packets and number of flow. Whereas handling mechanism perform by limiting or drop the packets that detected as a DDoS attack. The study begins with simulation on real network, which aims to get the real traffic data. Then, dump traffic data obtained from the simulation used for detection method on our prototype system called DASHM (DDoS Attack Simulation and Handling Mechanism. From the result of experiment that has been conducted, the proposed method successfully detect DDoS attack and handle the incoming packet sent by attacker.

Development of the graphic design and control system based on a graphic simulator for the spent fuel dismantling equipment

Energy Technology Data Exchange (ETDEWEB)

Lee, J. Y.; Kim, S. H.; Song, T. G.; Yoon, J. S

2000-06-01

In this study, the graphic design system is developed for designing the spent fuel rod consolidation and the dismantling processes. This system is used throughout the design stages from the conceptual design to the motion analysis. Also, the real-time control system of the rod extracting equipment is developed. This system utilizes the graphic simulator which simulates the motion of the equipment in real time by synchronously connecting the control PC with the graphic server through the TCP/IP network. The developed system is expected to be used as an effective tool in designing the process equipment for the spent fuel management. And the real-time graphic control system can be effectively used to enhance the reliability and safety of the spent fuel handling process by providing the remote monitoring function of the process.

Development of the graphic design and control system based on a graphic simulator for the spent fuel dismantling equipment

International Nuclear Information System (INIS)

Lee, J. Y.; Kim, S. H.; Song, T. G.; Yoon, J. S.

2000-06-01

In this study, the graphic design system is developed for designing the spent fuel rod consolidation and the dismantling processes. This system is used throughout the design stages from the conceptual design to the motion analysis. Also, the real-time control system of the rod extracting equipment is developed. This system utilizes the graphic simulator which simulates the motion of the equipment in real time by synchronously connecting the control PC with the graphic server through the TCP/IP network. The developed system is expected to be used as an effective tool in designing the process equipment for the spent fuel management. And the real-time graphic control system can be effectively used to enhance the reliability and safety of the spent fuel handling process by providing the remote monitoring function of the process

Ergonomics of disposable handles for minimally invasive surgery.

Science.gov (United States)

Büchel, D; Mårvik, R; Hallabrin, B; Matern, U

2010-05-01

The ergonomic deficiencies of currently available minimally invasive surgery (MIS) instrument handles have been addressed in many studies. In this study, a new ergonomic pistol handle concept, realized as a prototype, and two disposable ring handles were investigated according to ergonomic properties set by new European standards. In this study, 25 volunteers performed four practical tasks to evaluate the ergonomics of the handles used in standard operating procedures (e.g., measuring a suture and cutting to length, precise maneuvering and targeting, and dissection of a gallbladder). Moreover, 20 participants underwent electromyography (EMG) tests to measure the muscle strain they experienced while carrying out the basic functions (grasp, rotate, and maneuver) in the x, y, and z axes. The data measured included the number of errors, the time required for task completion, perception of pressure areas, and EMG data. The values for usability in the test were effectiveness, efficiency, and user satisfaction. Surveys relating to the subjective rating were completed after each task for each of the three handles tested. Each handle except the new prototype caused pressure areas and pain. Extreme differences in muscle strain could not be observed for any of the three handles. Experienced surgeons worked more quickly with the prototype when measuring and cutting a suture (approximately 20%) and during precise maneuvering and targeting (approximately 20%). On the other hand, they completed the dissection task faster with the handle manufactured by Ethicon. Fewer errors were made with the prototype in dissection of the gallbladder. In contrast to the handles available on the market, the prototype was always rated as positive by the volunteers in the subjective surveys. None of the handles could fulfil all of the requirements with top scores. Each handle had its advantages and disadvantages. In contrast to the ring handles, the volunteers could fulfil most of the tasks more

Radiological safety aspects of handling plutonium

International Nuclear Information System (INIS)

Sundararajan, A.R.

2016-01-01

Department of Atomic Energy in its scheme of harnessing the nuclear energy for electrical power generation and strategic applications has given a huge role to utilization of plutonium. In the power production programme, fast reactors with plutonium as fuel are expected to play a major role. This would require establishing fuel reprocessing plants to handle both thermal and fast reactor fuels. So in the nuclear fuel cycle facilities variety of chemical, metallurgical, mechanical operations have to be carried out involving significant inventories of "2"3"9 Pu and associated radionuclides. Plutonium is the most radiotoxic radionuclide and therefore any facility handling it has to be designed and operated with utmost care. Two problems of major concern in the protection of persons working in plutonium handling facilities are the internal exposure to the operating personnel from uptake of plutonium and transplutonic nuclides as they are highly radiotoxic and the radiation exposure of hands and eye lens during fuel fabrication operations especially while handling recycled high burn up plutonium. In view of the fact that annual limit for intake is very small for "2"3"9Pu and its radiation emission characteristics are such that it is a huge challenge for the health physicists to detect Pu in air and in workers. This paper discusses the principles and practices followed in providing radiological surveillance to workers in plutonium handling areas. The challenges in protecting the workers from receiving exposures to hands and eye lens in handling high burn up plutonium are also discussed. The sites having Pu fuel cycle facilities should have trained medical staff to handle cases involving excessive intake of plutonium. (author)

Strategic project selection based on evidential reasoning approach for high-end equipment manufacturing industry

Directory of Open Access Journals (Sweden)

Lu Guangyan

2017-01-01

Full Text Available With the rapid development of science and technology, emerging information technologies have significantly changed the daily life of people. In such context, strategic project selection for high-end equipment manufacturing industries faces more and more complexities and uncertainties with the consideration of several complex criteria. For example, a group of experts rather than a single expert should be invited to select strategic project for high-end equipment manufacturing industries and the experts may feel difficulty to express their preferences towards different strategic projects due to their limited cognitive capabilities. In order to handle these complexities and uncertainties, the criteria framework of strategic project selection is firstly constructed based on the characteristics of high-end equipment manufacturing industries and then evidential reasoning (ER approach is introduced in this paper to help experts express their uncertain preferences and aggregate these preferences to generate an appropriate strategic project. A real case of strategic project selection in a high-speed train manufacturing enterprise is investigated to demonstrate the validity of the ER approach in solving strategic project selection problem.

Enclosure for handling high activity materials

International Nuclear Information System (INIS)

Jimeno de Osso, F.

1977-01-01

One of the most important problems that are met at the laboratories producing and handling radioisotopes is that of designing, building and operating enclosures suitable for the safe handling of active substances. With this purpose in mind, an enclosure has been designed and built for handling moderately high activities under a shielding made of 150 mm thick lead. In this report a description is given of those aspects that may be of interest to people working in this field. (Author)

Enclosure for handling high activity materials

Energy Technology Data Exchange (ETDEWEB)

Jimeno de Osso, F

1977-07-01

One of the most important problems that are met at the laboratories producing and handling radioisotopes is that of designing, building and operating enclosures suitable for the safe handling of active substances. With this purpose in mind, an enclosure has been designed and built for handling moderately high activities under a shielding made of 150 mm thick lead. In this report a description is given of those aspects that may be of interest to people working in this field. (Author)

Development and evaluation of a multifaceted ergonomics program to prevent injuries associated with patient handling tasks.

Science.gov (United States)

Nelson, Audrey; Matz, Mary; Chen, Fangfei; Siddharthan, Kris; Lloyd, John; Fragala, Guy

2006-08-01

Nurses have one of the highest rates of work-related musculoskeletal injury of any profession. Over the past 30 years, efforts to reduce work-related musculoskeletal disorders in nurses have been largely unsuccessful. The primary goal of this program was to create safer working environments for nursing staff who provide direct patient care. Our first objective was to design and implement a multifaceted program that successfully integrated evidence-based practice, technology, and safety improvement. The second objective was to evaluate the impact of the program on injury rate, lost and modified work days, job satisfaction, self-reported unsafe patient handling acts, level of support for program, staff and patient acceptance, program effectiveness, costs, and return on investment. The intervention included six program elements: (1) Ergonomic Assessment Protocol, (2) Patient Handling Assessment Criteria and Decision Algorithms, (3) Peer Leader role, "Back Injury Resource Nurses", (4) State-of-the-art Equipment, (5) After Action Reviews, and (6) No Lift Policy. A pre-/post design without a control group was used to evaluate the effectiveness of a patient care ergonomics program on 23 high risk units (19 nursing home care units and 4 spinal cord injury units) in 7 facilities. Injury rates, lost work days, modified work days, job satisfaction, staff , and patient acceptance, program effectiveness, and program costs/savings were compared over two nine month periods: pre-intervention (May 2001-January 2002) and post-intervention (March 2002-November 2002). Data were collected prospectively through surveys, weekly process logs, injury logs, and cost logs. The program elements resulted in a statistically significant decrease in the rate of musculoskeletal injuries as well as the number of modified duty days taken per injury. While the total number of lost workdays decreased by 18% post-intervention, this difference was not statistically significant. There were statistically

Coaxial twin-shaft magnetic fluid seals applied in vacuum wafer-handling robot

Science.gov (United States)

Cong, Ming; Wen, Haiying; Du, Yu; Dai, Penglei

2012-07-01

Compared with traditional mechanical seals, magnetic fluid seals have unique characters of high airtightness, minimal friction torque requirements, pollution-free and long life-span, widely used in vacuum robots. With the rapid development of Integrate Circuit (IC), there is a stringent requirement for sealing wafer-handling robots when working in a vacuum environment. The parameters of magnetic fluid seals structure is very important in the vacuum robot design. This paper gives a magnetic fluid seal device for the robot. Firstly, the seal differential pressure formulas of magnetic fluid seal are deduced according to the theory of ferrohydrodynamics, which indicate that the magnetic field gradient in the sealing gap determines the seal capacity of magnetic fluid seal. Secondly, the magnetic analysis model of twin-shaft magnetic fluid seals structure is established. By analyzing the magnetic field distribution of dual magnetic fluid seal, the optimal value ranges of important parameters, including parameters of the permanent magnetic ring, the magnetic pole tooth, the outer shaft, the outer shaft sleeve and the axial relative position of two permanent magnetic rings, which affect the seal differential pressure, are obtained. A wafer-handling robot equipped with coaxial twin-shaft magnetic fluid rotary seals and bellows seal is devised and an optimized twin-shaft magnetic fluid seals experimental platform is built. Test result shows that when the speed of the two rotational shafts ranges from 0-500 r/min, the maximum burst pressure is about 0.24 MPa. Magnetic fluid rotary seals can provide satisfactory performance in the application of wafer-handling robot. The proposed coaxial twin-shaft magnetic fluid rotary seal provides the instruction to design high-speed vacuum robot.

High-definition television evaluation for remote handling task performance

International Nuclear Information System (INIS)

Fujita, Y.; Omori, E.; Hayashi, S.; Draper, J.V.; Herndon, J.N.

1986-01-01

In a plant that employs remote handling techniques for equipment maintenance, operators perform maintenance tasks primarily by using the information from television systems. The efficiency of the television system has a significant impact on remote maintenance task performance. High-definition television (HDTV) transmits a video image with more than twice the number of horizontal scan lines as standard-resolution television (1125 for HDTV to 525 for standard-resolution NTSC television). The added scan lines dramatically improve the resolution of images on the HDTV monitors. This paper describes experiments designed to evaluate the impact of HDTV on the performance of typical remote tasks. The experiments described in this paper compared the performance of four operators using HDTV with their performance while using other television systems. The experiments included four television systems: (a) high-definition color television, (b) high-definition monochromatic television, (c) standard-resolution monochromatic television, and (d) standard-resolution stereoscopic monochromatic television

Process and equipment development for hot isostatic pressing treatability study

Energy Technology Data Exchange (ETDEWEB)

Bateman, Ken; Wahlquist, Dennis; Malewitz, Tim

2015-03-01

Battelle Energy Alliance (BEA), LLC, has developed processes and equipment for a pilot-scale hot isostatic pressing (HIP) treatability study to stabilize and volume reduce radioactive calcine stored at Idaho National Laboratory (INL). In 2009, the U. S. Department of Energy signed a Record of Decision with the state of Idaho selecting HIP technology as the method to treat 5,800 yd^3 (4,400 m^3) of granular zirconia and alumina calcine produced between 1953 and 1992 as a waste byproduct of spent nuclear fuel reprocessing. Since the 1990s, a variety of radioactive and hazardous waste forms have been remotely treated using HIP within INL hot cells. To execute the remote process at INL, waste is loaded into a stainless-steel or aluminum can, which is evacuated, sealed, and placed into a HIP furnace. The HIP simultaneously heats and pressurizes the waste, reducing its volume and increasing its durability. Two 1 gal cans of calcine waste currently stored in a shielded cask were identified as candidate materials for a treatability study involving the HIP process. Equipment and materials for cask-handling and calcine transfer into INL hot cells, as well as remotely operated equipment for waste can opening, particle sizing, material blending, and HIP can loading have been designed and successfully tested. These results demonstrate BEA’s readiness for treatment of INL calcine.

SpaceWire: IP, Components, Development Support and Test Equipment

Science.gov (United States)

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

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

Introduction to Commercial Cooking Equipment. Learning Activity Pack and Instructor's Guide 4.1. Commercial Foods and Culinary Arts Competency-Based Series. Section 4: Equipment Handling, Operation and Maintenance.

Science.gov (United States)

Florida State Univ., Tallahassee. Center for Studies in Vocational Education.

This document consists of a learning activity packet (LAP) for the student and an instructor's guide for the teacher. The LAP is intended to acquaint occupational home economics students with the workings of and equipment found in commercial kitchens. Illustrated information sheets and learning activities are provided on each of the following…

Noise control of radiological monitoring equipment

International Nuclear Information System (INIS)

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

1998-01-01

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

Liquefied natural gas (LNG) : production, storage and handling. 7. ed.

Energy Technology Data Exchange (ETDEWEB)

Kalra, S; Jaron, K; Adragna, M; Coyle, S; Foley, C; Hawryn, S; Martin, A; McConnell, J [eds.

2003-07-01

This Canadian Standard on the production, storage and handling of liquefied natural gas (LNG) was prepared by the Technical Committee on Liquefied Natural Gas under the jurisdiction of the Steering Committee on Oil and Gas Industry Systems and Materials. It establishes the necessary requirements for the design, installation and safe operation of LNG facilities. The Standard applies to the design, location, construction, operation and maintenance of facilities at any location of the liquefaction of natural gas and for the storage, vaporization, transfer, handling and truck transport of LNG. The training of personnel involved is also included as well as containers for LNG storage, including insulated vacuum systems. It includes non-mandatory guidelines for small LNG facilities but does not apply to the transportation of refrigerants, LNG by rail, marine vessel or pipeline. This latest edition contains changes in working of seismic design requirements and minor editorial changes to several clauses to bring the Standard closer to the US National Fire Protection Association's Committee on Liquefied Natural Gas Standard while maintaining Canadian regulatory requirements. The document is divided into 12 sections including: general requirements; plant site provisions; process equipment; stationary LNG storage containers; vaporization facilities; piping system and components; instrumentation and electrical services; transfer of LNG and refrigerants; fire protection, safety and security; and, operating, maintenance and personnel training. This Standard, like all Canadian Standards, was subject to periodic review and was most recently reaffirmed in 2003. 6 tabs., 6 figs., 3 apps.

HMSRP Hawaiian Monk Seal Handling Data

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains records for all handling and measurement of Hawaiian monk seals since 1981. Live seals are handled and measured during a variety of events...

European Model Code of safe practice in the storage and handling of petroleum products. Part I. Operations

Energy Technology Data Exchange (ETDEWEB)

1973-01-01

This safe practice code was prepared by a working group consisting of experts from 10 Western European countries. It consists of short guidelines and technical advice on general precautions, injuries and medical services, permits to work, fire prevention and fighting, jetties, pipework, storage tanks, static electricity, electrical equipment, road vehicles, tank cars, handling of bitumen products, liquefied petroleum gases, packed products and training of personnel. The code is supplemented by 10 appendices, including a suggested syllabus for a 2-day course on fire prevention and emergency action for managers of oil installations.

Effects of a potential drop of a shipping cask, a waste container, and a bare fuel assembly during waste-handling operations

International Nuclear Information System (INIS)

Wu, C.L.; Lee, J.; Lu, D.L.; Jardine, L.J.

1991-12-01

This study investigates the effects of potential drops of a typical shipping cask, waste container, and bare fuel assembly during waste-handling operations at the prospective Yucca Mountain Repository. The waste-handling process (one stage, no consolidation configuration) is examined to estimate the maximum loads imposed on typical casks and containers as they are handled by various pieces of equipment during waste-handling operations. Maximum potential drop heights for casks and containers are also evaluated for different operations. A nonlinear finite-element model is employed to represent a hybrid spent fuel container subject to drop heights of up to 30 ft onto a reinforced concrete floor. The impact stress, strain, and deformation are calculated, and compared to the failure criteria to estimate the limiting (maximum permissible) drop height for the waste container. A typical Westinghouse 17 x 17 PWR fuel assembly is analyzed by a simplified model to estimate the energy absorption by various parts of the fuel assembly during a 30 ft drop, and to determine the amount of kinetic energy in a fuel pin at impact. A nonlinear finite-element analysis of an individual fuel pin is also performed to estimate the amount of fuel pellet fracture due to impact. This work was completed on May 1990

A Review and Analysis of European Industrial Experience in Handling LWR Spent Fuel and Vitrified High-Level Waste

Energy Technology Data Exchange (ETDEWEB)

Blomeke, J.O.

2001-07-10

The industrial facilities that have been built or are under construction in France, the United Kingdom, Sweden, and West Germany to handle light-water reactor (LWR) spent fuel and canisters of vitrified high-level waste before ultimate disposal are described and illustrated with drawings and photographs. Published information on the operating performance of these facilities is also given. This information was assembled for consideration in planning and design of similar equipment and facilities needed for the Federal Waste Management System in the United States.

Particle release and control of worker exposure during laboratory-scale synthesis, handling and simulated spills of manufactured nanomaterials in fume hoods

Science.gov (United States)

Fonseca, Ana S.; Kuijpers, Eelco; Kling, Kirsten I.; Levin, Marcus; Koivisto, Antti J.; Nielsen, Signe H.; Fransman, W.; Fedutik, Yijri; Jensen, Keld A.; Koponen, Ismo K.

2018-02-01

Fume hoods are one of the most common types of equipment applied to reduce the potential of particle exposure in laboratory environments. A number of previous studies have shown particle release during work with nanomaterials under fume hoods. Here, we assessed laboratory workers' inhalation exposure during synthesis and handling of CuO, TiO2 and ZnO in a fume hood. In addition, we tested the capacity of a fume hood to prevent particle release to laboratory air during simulated spillage of different powders (silica fume, zirconia TZ-3Y and TiO2). Airborne particle concentrations were measured in near field, far field, and in the breathing zone of the worker. Handling CuO nanoparticles increased the concentration of small particles (control during synthesis and handling of nanomaterials. An appropriate fume hood with adequate sash height and face velocity prevents 98.3% of particles release into the surrounding environment. Care should still be made to consider spills and high cleanliness to prevent exposure via resuspension and inadvertent exposure by secondary routes.

MONITORING AND SAFETY OF HANDLING EQUIPMENT

Directory of Open Access Journals (Sweden)

Janusz JURASZEK

2014-04-01

Full Text Available The paper presents a new solution for continuous measurement of deformations of the beam of travelling crane based on optical fibre Bragg gratings system. A verification of obtained results was done using resistive strain gauge method and magnetic metal memory method was used. Usage of the results of continuous measurements of deformation of the structure of the crane as actual boundary conditions in FEM numerical simulations was proposed in order to enable the analysis of the behaviour of whole structure.

Ergonomics: safe patient handling and mobility.

Science.gov (United States)

Hallmark, Beth; Mechan, Patricia; Shores, Lynne

2015-03-01

This article reviews and investigates the issues surrounding ergonomics, with a specific focus on safe patient handling and mobility. The health care worker of today faces many challenges, one of which is related to the safety of patients. Safe patient handling and mobility is on the forefront of the movement to improve patient safety. This article reviews the risks associated with patient handling and mobility, and informs the reader of current evidence-based practice relevant to this area of care. Copyright © 2015 Elsevier Inc. All rights reserved.

Welding method by remote handling

International Nuclear Information System (INIS)

Hashinokuchi, Minoru.

1994-01-01

Water is charged into a pit (or a water reservoir) and an article to be welded is placed on a support in the pit by remote handling. A steel plate is disposed so as to cover the article to be welded by remote handling. The welding device is positioned to the portion to be welded and fixed in a state where the article to be welded is shielded from radiation by water and the steel plate. Water in the pit is drained till the portion to be welded is exposed to the atmosphere. Then, welding is conducted. After completion of the welding, water is charged again to the pit and the welding device and fixing jigs are decomposed in a state where the article to be welded is shielded again from radiation by water and the steel plate. Subsequently, the steel plate is removed by remote handling. Then, the article to be welded is returned from the pit to a temporary placing pool by remote handling. This can reduce operator's exposure. Further, since the amount of the shielding materials can be minimized, the amount of radioactive wastes can be decreased. (I.N.)

Project to develop and demonstrate methods to eliminate frozen coal handling problems. Status report I

Energy Technology Data Exchange (ETDEWEB)

None

1980-09-15

For too many years, problems associated with frozen coal have plagued the companies who mine it, the companies who handle it in transit and the utilities and other industrial concerns that finally burn it. But never before has the magnitude of the frozen coal problem been as great as it is today because of two primary factors, i.e. (1) the majority of coal currently transported and used has been ground to a very fine mesh that absorbs water readily, thus providing more surface area for freezing, and (2) the substantially increased importance of coal, indeed, the now critical necessity for more coal to be used in displacing dangerously uncertain foreign oil supplies that currently account for 50 percent of our daily domestic oil consumption. Frozen coal problems can and do have a devastating effect upon the ability to provide energy from coal during harsh winter months when it is not needed. The majority of these problems have been involved with removing frozen coal from rail cars. To allay the problem, numerous techniques have been tried, all with some measure of success. As an example, certain chemicals have been sprayed on the coal; another common treatment has been widespread use of thaw sheds, which, whether electrically or gas-fired, are all energy intensive, time consuming, hard on rail equipment and expensive to operate over long periods of time. From sledge hammers and crow bars to gas-fired jets and electric thaw sheds, available mechanical de-icing methods often damage coal handling equipment, are time consuming and, therefore, very expensive when demurrage losses must be added to significant investment and/or operating costs.

Civilsamfundets ABC: H for Handling

DEFF Research Database (Denmark)

Lund, Anker Brink; Meyer, Gitte

2015-01-01

Hvad er civilsamfundet? Anker Brink Lund og Gitte Meyer fra CBS Center for Civil Society Studies gennemgår civilsamfundet bogstav for bogstav. Vi er nået til H for Handling.......Hvad er civilsamfundet? Anker Brink Lund og Gitte Meyer fra CBS Center for Civil Society Studies gennemgår civilsamfundet bogstav for bogstav. Vi er nået til H for Handling....

The technique on handling radiation

International Nuclear Information System (INIS)

1997-11-01

This book describes measurement of radiation and handling radiation. The first part deals with measurement of radiation. The contents of this part are characteristic on measurement technique of radiation, radiation detector, measurement of energy spectrum, measurement of radioactivity, measurement for a level of radiation and county's statistics on radiation. The second parts explains handling radiation with treating of sealed radioisotope, treating unsealed source and radiation shield.

Uranium hexafluoride handling

International Nuclear Information System (INIS)

1991-01-01

The United States Department of Energy, Oak Ridge Field Office, and Martin Marietta Energy Systems, Inc., are co-sponsoring this Second International Conference on Uranium Hexafluoride Handling. The conference is offered as a forum for the exchange of information and concepts regarding the technical and regulatory issues and the safety aspects which relate to the handling of uranium hexafluoride. Through the papers presented here, we attempt not only to share technological advances and lessons learned, but also to demonstrate that we are concerned about the health and safety of our workers and the public, and are good stewards of the environment in which we all work and live. These proceedings are a compilation of the work of many experts in that phase of world-wide industry which comprises the nuclear fuel cycle. Their experience spans the entire range over which uranium hexafluoride is involved in the fuel cycle, from the production of UF 6 from the naturally-occurring oxide to its re-conversion to oxide for reactor fuels. The papers furnish insights into the chemical, physical, and nuclear properties of uranium hexafluoride as they influence its transport, storage, and the design and operation of plant-scale facilities for production, processing, and conversion to oxide. The papers demonstrate, in an industry often cited for its excellent safety record, continuing efforts to further improve safety in all areas of handling uranium hexafluoride

Handling Pyrophoric Reagents

Energy Technology Data Exchange (ETDEWEB)

Alnajjar, Mikhail S.; Haynie, Todd O.

2009-08-14

Pyrophoric reagents are extremely hazardous. Special handling techniques are required to prevent contact with air and the resulting fire. This document provides several methods for working with pyrophoric reagents outside of an inert atmosphere.

ATA diagnostic data handling system: an overview

International Nuclear Information System (INIS)

Chambers, F.W.; Kallman, J.; McDonald, J.; Slominski, M.

1984-01-01

The functions to be performed by the ATA diagnostic data handling system are discussed. The capabilities of the present data acquisition system (System 0) are presented. The goals for the next generation acquisition system (System 1), currently under design, are discussed. Facilities on the Octopus system for data handling are reviewed. Finally, we discuss what has been learned about diagnostics and computer based data handling during the past year

Generation of equipment response spectrum considering equipment-structure interaction

International Nuclear Information System (INIS)