Design guide for heat transfer equipment in water-cooled nuclear reactor systems

International Nuclear Information System (INIS)

1975-07-01

Information pertaining to design methods, material selection, fabrication, quality assurance, and performance tests for heat transfer equipment in water-cooled nuclear reactor systems is given in this design guide. This information is intended to assist those concerned with the design, specification, and evaluation of heat transfer equipment for nuclear service and the systems in which this equipment is required. (U.S.)

Development of a movable table for a bending magnet with removable guides

International Nuclear Information System (INIS)

Shibuya, T.; Ito, I.; Kudoh, H.

2004-01-01

We develop the movable table for a bending magnet with removable guides. This table has two parallel rails in order to move the bending magnet smoothly and set it precisely. Especially this table has two removable expanded rail guides. Removing this expanded rail guides allow us to make more enough spaces, for example, to install another insertion devices. We measure the reliability of setting this table by moving this table along the rails. And we found this reliability is less than ±3 μm. We also measure the long-term stability of this table setting. (author)

Study Of Robotic Replacement Of Equipment Modules

Science.gov (United States)

Backes, Paul G.; Tso, Kam S.

1992-01-01

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

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

International Nuclear Information System (INIS)

Stade, R.E.

1978-01-01

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

Neutron guides and scientific neutron equipment at CILAS/GMI

International Nuclear Information System (INIS)

Gautier-Picard, P.

2003-01-01

CILAS company is the world's leading supplier of complete neutron guides systems. The neutron optics with multilayer coatings produced by CILAS have become an international standard for neutron beam transportation in the modern research institutes. During the last 30 years, CILAS designed, produced and installed more than 5000 meters of guides in many European, American and Asian countries. To reinforce its leadership and presence in neutron research, CILAS acquired the company Grenoble Modular Instruments (GMI), a leading company in high precision mechanics, engineering and manufacturing of spectrometers and scientific equipment for neutron and synchrotron research. (author)

Shippingport Station Decommissioning Project: Removal of piping and equipment and removal of primary system components

International Nuclear Information System (INIS)

1989-01-01

This report is a technical synopsis of the removal of contaminated and non-contaminated piping and equipment from the Shippingport Station Decommissioning Project (SSDP). The information is provided as a part of the Technology Transfer Program to document dismantling activities in support of reactor decommissioning. 5 refs., 29 figs., 4 tabs

A guide to qualification of electrical equipment for nuclear power plants. Final report, November 1983

International Nuclear Information System (INIS)

Marion, A.; Lamken, D.; Harrall, T.; Kasturi, S.; Holzman, P.; Carfagno, S.; Thompson, D.; Boyer, B.; Hanneman, H.; Rule, W.

1983-09-01

Equipment qualification demonstrates that nuclear power plant equipment can perform its safety function - that despite age or the adverse conditions of a design basis accident the equipment can work as needed. This report is a guide to the overall process of electrical equipment qualification. It should interest those who design such equipment, those who buy it, or test it, and even those who install and maintain it. (author)

Ultrasound guided percutaneous removal of wooden foreign bodies in the extremities with hydro-dissection technique

Energy Technology Data Exchange (ETDEWEB)

Park, HeeJin; Lee, So Yeon; Chung, Eun Chul; Rho, Myung Ho [Dept. of Radiology, Sungkyunkwan University School of Medicine, Kangbuk Samsung Hospital, Seoul (Korea, Republic of); Lee, Sung Moon; Son, Eun Seok [Dongsan Medical Center, Keimyung University School of Medicine, Daegu (Korea, Republic of); Lee, Sun Joo [Dept. of Radiology, Inje University College of Medicine, Busan Paik Hospital, Busan (Korea, Republic of)

2015-12-15

We described the technique of ultrasound (US)-guided percutaneous removal of the foreign bodies (FB) with hydro-dissection in the radiologic department and presented video files of several cases.Four patients referred to the radiology department for US evaluation and US-guided percutaneous removal of the FBs in the upper and lower extremities between November, 2006 and November, 2013 were included in this study. The procedures started with US evaluation for the exact location and shape of the FB. A 5 mm-sized skin incision was made at the site of the nearest point from the FB where no passing arteries or tendons were present. We adopted a hydro dissection technique to separate the FB from adjacent tissue using a 2% lidocaine solution. Injected anesthetics detached the FBs from surrounding tissue and thereby facilitated removal. After the tip of the mosquito forceps reached the FB, the wooden FBs were removed. The mean time required for the entire procedure was approximately 20 minutes. There were no significant complications during the US-guided removal or long-term complications after the procedure. All 4 FBs were successfully removed from the soft tissue under US guidance. Ultrasound-guided percutaneous removal of the FBs with hydro-dissection in the radiology department is a less invasive and safe method over surgical removal in the operating room. Additionally, the use of a guide wire and serial dilator may help minimize soft tissue injury and facilitate the introduction of forceps.

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

International Nuclear Information System (INIS)

Haberman, W.

1977-06-01

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

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

International Nuclear Information System (INIS)

Haberman, W.

1977-06-01

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

The UK market for dust and particulate removal equipment

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-08-01

The report has a market overview of dust and particulate removal equipment, 1995-1999 and has specific market reports, by value, of fabric, ceramic and sintered filters, electrostatic precipitators, wet scrubbers (venturi, plate and others) and cyclones. It gives environmental expenditure by UK industry and discusses factors affecting supply, demand and success in the market. An overview is given of the industry structure and profiles are presented of 15 companies. Lists of contracts, trade associations and relevant journals are included. 33 tabs.

Double-shell tank emergency pumping guide

International Nuclear Information System (INIS)

BROWN, M.H.

1999-01-01

This Double-Shell Tank Emergency Pumping Guide provides the preplanning necessary to expeditiously remove any waste that may leak from the primary tank to the secondary tank for Hanfords 28 DSTs. The strategy is described, applicable emergency procedures are referenced, and transfer routes and pumping equipment for each tank are identified

Double-shell tank emergency pumping guide

International Nuclear Information System (INIS)

BROWN, M.H.

1999-01-01

This Double-Shell Tank Emergency Pumping Guide provides the preplanning necessary to expeditiously remove any waste that may leak from the primary tank to the secondary tank for Hanford's 28 DSTS. The strategy is described, applicable emergency procedures are referenced, and transfer routes and pumping equipment for each tank are identified

Playground Equipment Guide: For Teachers, Park and Recreation Directors, Parents, Youth Leaders, and Other Concerned Adults.

Science.gov (United States)

Consumer Product Safety Commission, Washington, DC.

This guide was designed to assist parents, teachers, youth leaders, and park and recreation directors in the safe selection, use, installation, maintenance and repair of playground equipment. The nature and necessity of children's play are discussed briefly and information is presented on four main types of playground equipment: (1) swings, (2)…

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

International Nuclear Information System (INIS)

Troyer, G.L.

1998-01-01

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

IEEE No. 323, IEEE trial-use standard: General guide for qualifying Class I electric equipment for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This document describes the basic requirements for the qualification of Class I electric equipment. This is equipment which is essential to the safe shutdown and isolation of the reactor or whose failure or damage could result in significant release of radioactive material. The purpose of this document is to provide guidance for demonstrating the qualifications of electrical equipment as required in the IEEE Std 279 -- Criteria for Nuclear Power Generating Station Protection Systems, and IEEE Std 308 -- Criteria for Class 1E Electric Systems for Nuclear Power Generating Stations. The qualification methods described may be used in conjunction with the Guides for qualifying specific types of equipment, (see Foreword), for updating qualification following modifications or for qualifying equipment for which no applicable Guide exists

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

International Nuclear Information System (INIS)

Mjoenes, L.

2000-02-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Mjoenes, L

2000-02-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1995-02-27

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

Assessment of pressurized nuclear equipment compliance - ASN guide no. 8, version of 04/09/2012

International Nuclear Information System (INIS)

2012-01-01

This document describes the modalities according to which the compliance assessment of pressurized nuclear equipment must be performed by inspecting organisations according to a decree of December 1999 and an order of December 2005. After an indication of reference documents and some technical definitions, this guide describes the equipment classification and the principles of intervention. These principles concern the assessment request and the various assessment tasks to be performed by the inspecting organisation

Preliminary analysis of West Valley Waste Removal System equipment development and mock demonstration facilities

International Nuclear Information System (INIS)

Janicek, G.P.

1981-06-01

This report defines seven areas requiring further investigation to develop and demonstrate a safe and viable West Valley Waste Removal System. These areas of endeavor are discussed in terms of their minimum facility requirements. It is concluded that utilizing separated specific facilities at different points in time is of a greater advantage than an exact duplication of the West Valley tanks. Savannah River Plant's full-scale, full-circle and half-circle tanks, and their twelfth scale model tank would all be useful to varying degrees but would require modifications. Hanford's proposed full-size mock tank would be useful, but is not seriously considered because its construction may not coincide with West Valley needs. Costs of modifying existing facilities and/or constructing new facilities are assessed in terms of their benefit to the equipment development and mock demonstration. Six facilities were identified for further analysis which would benefit development of waste removal equipment

Image-guided percutaneous removal of ballistic foreign bodies secondary to air gun injuries.

Science.gov (United States)

Rothermund, Jacob L; Rabe, Andrew J; Zumberge, Nicholas A; Murakami, James W; Warren, Patrick S; Hogan, Mark J

2018-01-01

Ballistic injuries with retained foreign bodies from air guns is a relatively common problem, particularly in children and adolescents. If not removed in a timely fashion, the foreign bodies can result in complications, including pain and infection. Diagnostic methods to identify the presence of the foreign body run the entire gamut of radiology, particularly radiography, ultrasound (US) and computed tomography (CT). Removal of the foreign bodies can be performed by primary care, emergency, surgical, and radiologic clinicians, with or without imaging guidance. To evaluate the modalities of radiologic detection and the experience of image-guided ballistic foreign body removal related to air gun injuries within the interventional radiology department of a large pediatric hospital. A database of more than 1,000 foreign bodies that were removed with imaging guidance by the interventional radiologists at our institution was searched for ballistic foreign bodies from air guns. The location, dimensions, diagnostic modality, duration, complications and imaging modality used for removal were recorded. In addition, the use of sedation and anesthesia required for the procedures was also recorded. Sixty-one patients with ballistic foreign bodies were identified. All foreign bodies were metallic BBs or pellets. The age of the patients ranged from 5 to 20 years. The initial diagnostic modality to detect the foreign bodies was primarily radiography. The primary modality to assist in removal was US, closely followed by fluoroscopy. For the procedure, 32.7% of the patients required some level of sedation. Only two patients had an active infection at the time of the removal. The foreign bodies were primarily in the soft tissues; however, successful removal was also performed from intraosseous, intraglandular and intratendinous locations. All cases resulted in successful removal without complications. Image-guided removal of ballistic foreign bodies secondary to air guns is a very

Development of ultrasonic testing equipment incorporating electromagnetic acoustic transducer

International Nuclear Information System (INIS)

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

1989-01-01

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

Guide to Effective Business Practices in Buying School Supplies, Instructional Materials, Equipment and Services.

Science.gov (United States)

Association of School Business Officials International, Reston, VA.

This guide to effective business practices is intended to assist schools in establishing general policies and procedures for buying supplies, instructional materials, equipment, and services. Federal, state, and local laws must be considered in addition to the recommendations made in this report. Practical guidelines are given for selecting…

IEEE Std 1205-1993: IEEE guide for assessing, monitoring, and mitigating aging effects on Class 1E equipment used in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1993-01-01

The guidelines are provided for assessing, monitoring, and mitigating degradation of Class 1E equipment used in nuclear power generating stations due to aging. The methods described can be used to identify the performance capability of Class 1E equipment beyond its qualified life. A discussion of stressors and aging mechanisms is included. If aging considerations have been satisfactorily addressed through other means (e.g., equipment qualification), then use of this guide may not be warranted. For some equipment, only partial application of this guide may be warranted

Neutron guides and scientific neutron equipment at CILAS/GMI

International Nuclear Information System (INIS)

Gautier-Picard, P.

2001-01-01

The French company CILAS is the world's leading supplier of complete neutron guide systems. The neutron optics with multilayer coatings produced by CILAS has become an international standard for neutron beam transportation at modern research institutes. During the last 30 years, CILAS designed, produced and installed more than 5000 meters of guides in many European, American and Asian countries. By these projects the company has acquired a very strong experience with: conception, design, manufacturing, setting up of Neutron Guides. In most cases, CILAS was in charge of the design, as well as the manufacturing of the whole system, comprising optical and mechanical components, vacuum system, shutter and shielding definition. By our long experience we have also acquired good knowledge of the materials used in this specific nuclear environment and their behavior under radiation such as glass, borated or not, coatings, glue or metal. To reinforce its leadership and presence in neutron research, CILAS acquired the company Grenoble Modular Instruments (GMI) a leading company in high precision mechanics, engineering and manufacturing of spectrometers and scientific equipment for neutron and synchrotron research. This merger allows us to design and to supply a complete range of high precision optical and mechanical eqipment for neutron research. CILAS and GMI have designed, manufactured and installed a High Resolution Powder Diffractometer for the 30MW Korean Hanaro Reactor. This project included the calculation, design and supply of the complete biological shielding of the instrument as well as for the primary beam shutter on the thermal beamport. (author)

Selective removal of esthetic composite restorations with spectral guided laser ablation

Science.gov (United States)

Yi, Ivana; Chan, Kenneth H.; Tsuji, Grant H.; Staninec, Michal; Darling, Cynthia L.; Fried, Daniel

2016-02-01

Dental composites are used for a wide range of applications such as fillings for cavities, adhesives for orthodontic brackets, and closure of gaps (diastemas) between teeth by esthetic bonding. Anterior restorations are used to replace missing, diseased and unsightly tooth structure for both appearance and function. When these restorations must be replaced, they are difficult to remove mechanically without causing excessive removal or damage to enamel because dental composites are color matched to teeth. Previous studies have shown that CO2 lasers have high ablation selectivity and are well suited for removal of composite on occlusal surfaces while minimizing healthy tissue loss. A spectral feedback guidance system may be used to discriminate between dental composite and dental hard tissue for selective ablation of composite material. The removal of composite restorations filling diastemas is more challenging due to the esthetic concern for anterior teeth. The objective of this study is to determine if composite spanning a diastema between anterior teeth can be removed by spectral guided laser ablation at clinically relevant rates with minimal damage to peripheral healthy tissue and with higher selectivity than a high speed dental handpiece.

Removal of Uranium in Soil Using Large-scale Electrokinetic Decontamination Equipment

Energy Technology Data Exchange (ETDEWEB)

Kim, Gye Nam; Kim, Il gook; Jeong, Jung Whan; Kim, Seung Soo; Choi, Jong Won [KAERI, Daejeon (Korea, Republic of)

2016-05-15

A method to remediate a large volume of radioactive soil should be developed. Until now the soil washing method has been studied to remediate soil contaminated with uranium, cobalt, cesium, and so on. However, it has a lower removal efficiency of nuclide from soils and generated a large volume of waste-solution. In addition, its application to the soil composed of fine particle is impossible. Thus, the electrokinetic method has been studied as a new technology for soil remediation recently. In this study, for a reduction of the waste electrolyte volume, the reuse period of waste electrolyte in the electrokinetic decontamination experiment through several experiments with the manufactured 1.2 ton electrokinetic decontamination equipment. In addition, the time required to reach below the clearance concentration level for self- disposal was estimated through several experiments using the manufactured electrokinetic decontamination equipment. When the initial uranium concentrations in the soils were 7.0-20.0 Bq/g, the times required to reach below the clearance concentration level for self-disposal were 25-40 days with the waste and reclaimed electrolytes.

Diagnostic x-ray equipment and its use

International Nuclear Information System (INIS)

1993-01-01

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

A Guide for Developing Standard Operating Job Procedures for the Screening & Grinding Process Wastewater Treatment Facility. SOJP No. 1.

Science.gov (United States)

Deal, Gerald A.; Montgomery, James A.

This guide describes standard operating job procedures for the screening and grinding process of wastewater treatment facilities. The objective of this process is the removal of coarse materials from the raw waste stream for the protection of subsequent equipment and processes. The guide gives step-by-step instructions for safety inspection,…

Chitosan membrane development and design of equipment for the removal of heavy metals from water

International Nuclear Information System (INIS)

Mora Molina, Jesus; Chaves Barquero, Luis; Araya Marchena, Mario; Starbird Perez, Ricardo

2012-01-01

A filtration technique has compared with 1,75% m/v chitosan membranes, crosslinked with glutaraldehyde (0,08% m/v) and without cross link, to quantify the removal capacity of chromium, copper and cadmium ions of model solutions. In addition, a simple and low cost equipment was developed to use with prepared membranes. The main goal has been to use biodegradable materials for removing heavy metals from water, through a low energy consumption, cheap, and applicable to specific problems. Two data sheets were prepared for the membranes and was found that chromium was the metal with the highest removal from water, by using a crosslinked membrane. Metal adsorption was best adjusted to the Freundlich isotherm model, better than Langmuir isotherm model. However, no correlation has been found between pore size of the membranes and crosslinking degree. (author) [es

Chitosan membrane development and design of equipment for the removal of heavy metals from water

International Nuclear Information System (INIS)

Mora Molina, Jesus; Starbird Perez, Ricardo; Chaves Barquero, Luis; Araya Marchena, Mario

2011-01-01

A filtration technique has compared with 1,75% m/v chitosan membranes, crosslinked with glutaraldehyde (0,08% m/v) and without cross link, to quantify the removal capacity of chromium, copper and cadmium ions of model solutions. In addition, a simple and low cost equipment was developed to use with prepared membranes. The main goal has been to use biodegradable materials for removing heavy metals from water, through a low energy consumption, cheap, and applicable to specific problems. Two data sheets were prepared for the membranes and was found that chromium was the metal with the highest removal from water, by using a crosslinked membrane. Metal adsorption was best adjusted to the Freundlich isotherm model, better than Langmuir isotherm model. However, no correlation has been found between pore size of the membranes and crosslinking degree. (author) [es

A Technique to Facilitate Tooth Modification for Removable Partial Denture Prosthesis Guide Planes.

Science.gov (United States)

Haeberle, C Brent; Abreu, Amara; Metzler, Kurt

2016-07-01

The technique in this article was developed to provide a means to create prepared guide planes of proper dimension to ensure a more stable and retentive removable partial denture prosthesis (RPDP) framework when providing this service for a patient. Using commonly found clinical materials, a paralleling device can be fabricated from the modified diagnostic cast of the patient's dental arch requiring an RPDP. Polymethyl methacrylate or composite added to an altered thermoplastic form can be positioned intraorally and used as a guide to predictably adjust tooth structure for guide planes. Since it can potentially minimize the number of impressions and diagnostic casts made during the procedure, this can help achieve the desired result more efficiently and quickly for the patient. © 2015 by the American College of Prosthodontists.

Emergency removal of football equipment: a cadaveric cervical spine injury model.

Science.gov (United States)

Gastel, J A; Palumbo, M A; Hulstyn, M J; Fadale, P D; Lucas, P

1998-10-01

To determine the influence of football helmet and shoulder pads, alone or in combination, on alignment of the unstable cervical spine. The alignment of the intact cervical spine in 8 cadavers was assessed radiographically under 4 different football equipment conditions: (1) no equipment, (2) helmet only, (3) helmet and shoulder pads, and (4) shoulder pads only. Each specimen was then surgically destabilized at C5-C6 to simulate a flexion-distraction injury. Repeat radiographs were obtained under the same 4 equipment conditions, and alignment of the unstable segment was analyzed. Before the destabilization, neutral alignment was maintained when both helmet and shoulder pads were in place. The "helmet only" condition caused a significant decrease in lordosis (mean, 9.6 +/- 4.7 degrees), whereas the "shoulder pads only" condition caused increased lordosis (13.6 +/- 6.3 degrees). After destabilization, the "helmet-only" condition demonstrated significant mean increases in C5-C6 forward angulation (16.5 +/- 8.6 degrees), posterior disc space height (3.8 +/- 2.3 mm), and dorsal element distraction (8.3 +/- 5.4 mm). Our flexion-distraction model demonstrated that immobilization of the neck-injured football player with only the helmet in place violates the principle of splinting the cervical spine in neutral alignment. By extrapolation to an extension-type injury, immobilization with only the shoulder pads left in place similarly violates this principle. In order to maintain a neutral position and minimize secondary injury to the cervical neural elements, the helmet and shoulder pads should be either both left on or both removed in the emergency setting.

Electrical equipment qualification

International Nuclear Information System (INIS)

Farmer, W.S.

1983-01-01

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

Complete removal of a breast mass by US-guided mammotome biopsy: histologic assessment by marginal sampling

International Nuclear Information System (INIS)

Kim, Youn Jeong; Choi, Hye Young; Moon, Byung In; Lee, Shi Nae

2005-01-01

The aim of this study was to assess whether the complete removal of a breast mass using ultrasound (US) guided mammotome biopsy was successful using a marginal biopsy after insuring the total visual excision of the breast mass on US images. The relationship of complete breast mass removal, and the hematoma, mass size and shape were also evaluated. A US guided mammotome biopsy was performed in a total of 136 cases in 133 patients, with marginal biopsies also added when the complete removal of breast mass had been identified by sonography. The results of the marginal biopsies were serially dividing into three groups, as follows: group I were the cases in the initial 6 months, group II after the initial 6 months and group III having undergone two marginal biopsies. The marginal biopsies were performed in four directions around the probe, with 'marginal positivity' defined as the same histopathological findings to that of the main mass in at least one direction. A statistical analysis was also used to evaluate between the marginal positivity and the hematoma, mass size and shape. The marginal positivities of groups I, II and III were 48.8, 29.4 and 45.5%, respectively. The marginal positivity of those with a lobular shaped mass was significantly higher (ρ = 0.0121) than those with round or oval shaped masses (61.5 vs 33.7 vs 50%), but showed no statistical relationship with hematoma size of the lesions. Although the lesions were removed by US using a US-guided mammotome biopsy, many residual lesions were still histologically present in the marginal samplings, especially in the lobular shaped masse

Entrapment of Guide Wire in an Inferior Vena Cava Filter: A Technique for Removal

International Nuclear Information System (INIS)

Abdel-Aal, Ahmed Kamel; Saddekni, Souheil; Hamed, Maysoon Farouk; Fitzpatrick, Farley

2013-01-01

Entrapment of a central venous catheter (CVC) guide wire in an inferior vena cava (IVC) filter is a rare, but reported complication during CVC placement. With the increasing use of vena cava filters (VCFs), this number will most likely continue to grow. The consequences of this complication can be serious, as continued traction upon the guide wire may result in filter dislodgement and migration, filter fracture, or injury to the IVC. We describe a case in which a J-tipped guide wire introduced through a left subclavian access without fluoroscopic guidance during CVC placement was entrapped at the apex of an IVC filter. We describe a technique that we used successfully in removing the entrapped wire through the left subclavian access site. We also present simple useful recommendations to prevent this complication.

Alternative Fuel and Advanced Technology Commercial Lawn Equipment

Energy Technology Data Exchange (ETDEWEB)

None

2014-10-10

The U.S. Department of Energy's Clean Cities program produced this guide to help inform the commercial mowing industry about product options and potential benefits. This guide provides information about equipment powered by propane, ethanol, compressed natural gas, biodiesel, and electricity, as well as advanced engine technology. In addition to providing an overview for organizations considering alternative fuel lawn equipment, this guide may also be helpful for organizations that want to consider using additional alternative fueled equipment.

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…

Information technology equipment cooling method

Science.gov (United States)

Schultz, Mark D.

2015-10-20

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

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

International Nuclear Information System (INIS)

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

1987-03-01

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

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

International Nuclear Information System (INIS)

Schabert, H.P.; Winkler, F.

1975-01-01

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

Alternative Fuel and Advanced Technology Commercial Lawn Equipment (Brochure)

Energy Technology Data Exchange (ETDEWEB)

2014-10-01

The U.S. Department of Energy's Clean Cities program produced this guide to help inform the commercial mowing industry about product options and potential benefits. This guide provides information about equipment powered by propane, ethanol, compressed natural gas, biodiesel, and electricity, as well as advanced engine technology. In addition to providing an overview for organizations considering alternative fuel lawn equipment, this guide may also be helpful for organizations that want to consider using additional alternative fueled equipment.

Information technology equipment cooling system

Science.gov (United States)

Schultz, Mark D.

2014-06-10

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

Fluoroscopy-Guided Percutaneous Gallstone Removal Using a 12-Fr Sheath in High-Risk Surgical Patients with Acute Cholecystitis

International Nuclear Information System (INIS)

Kim, Young Hwan; Kim, Yong Joo; Shin, Tae Beom

2011-01-01

To evaluate the technical feasibility and clinical efficacy of percutaneous transhepatic cholecystolithotomy under fluoroscopic guidance in high-risk surgical patients with acute cholecystitis. Sixty-three consecutive patients of high surgical risk with acute calculous cholecystitis underwent percutaneous transhepatic gallstone removal under conscious sedation. The stones were extracted through the 12-Fr sheath using a Wittich nitinol stone basket under fluoroscopic guidance on three days after performing a percutaneous cholecystostomy. Large or hard stones were fragmented using either the snare guide wire technique or the metallic cannula technique. Gallstones were successfully removed from 59 of the 63 patients (94%). Reasons for stone removal failure included the inability to grasp a large stone in two patients, and the loss of tract during the procedure in two patients with a contracted gallbladder. The mean hospitalization duration was 7.3 days for acute cholecystitis patients and 9.4 days for gallbladder empyema patients. Bile peritonitis requiring percutaneous drainage developed in two patients. No symptomatic recurrence occurred during follow-up (mean, 608.3 days). Fluoroscopy-guided percutaneous gallstone removal using a 12-Fr sheath is technically feasible and clinically effective in high-risk surgical patients with acute cholecystitis

Fluoroscopy-Guided Percutaneous Gallstone Removal Using a 12-Fr Sheath in High-Risk Surgical Patients with Acute Cholecystitis

Energy Technology Data Exchange (ETDEWEB)

Kim, Young Hwan [Keimyung University, College of Medicine, Daegu (Korea, Republic of); Kim, Yong Joo [Andong General Hospital, Andong (Korea, Republic of); Shin, Tae Beom [Gyeonsang National University, College of Medicine, Jinju (Korea, Republic of)

2011-04-15

To evaluate the technical feasibility and clinical efficacy of percutaneous transhepatic cholecystolithotomy under fluoroscopic guidance in high-risk surgical patients with acute cholecystitis. Sixty-three consecutive patients of high surgical risk with acute calculous cholecystitis underwent percutaneous transhepatic gallstone removal under conscious sedation. The stones were extracted through the 12-Fr sheath using a Wittich nitinol stone basket under fluoroscopic guidance on three days after performing a percutaneous cholecystostomy. Large or hard stones were fragmented using either the snare guide wire technique or the metallic cannula technique. Gallstones were successfully removed from 59 of the 63 patients (94%). Reasons for stone removal failure included the inability to grasp a large stone in two patients, and the loss of tract during the procedure in two patients with a contracted gallbladder. The mean hospitalization duration was 7.3 days for acute cholecystitis patients and 9.4 days for gallbladder empyema patients. Bile peritonitis requiring percutaneous drainage developed in two patients. No symptomatic recurrence occurred during follow-up (mean, 608.3 days). Fluoroscopy-guided percutaneous gallstone removal using a 12-Fr sheath is technically feasible and clinically effective in high-risk surgical patients with acute cholecystitis

Usefulness and Complications of Ultrasonography- Guided Vacuum Assisted Biopsy for the Removal of Benign Breast Lesions

Energy Technology Data Exchange (ETDEWEB)

Kim, Keum Won; Cho, Young Jun; Hwang, Cheol Mog; Kim, Dae Ho; Oh, Kyoung Jin; Yoon, Dae Sung [Konyang University College of Medicine, Daejeon (Korea, Republic of); Kim, Kyu Soon [Eulji University College of Medicine, Daejeon (Korea, Republic of)

2010-09-15

To evaluate the usefulness and complications of ultrasonography (US)- guided vacuum assisted biopsy (VAB) for the removal of benign breast lesions, and the short- and long-term changes after VAB as shown on follow-up US. From January 2007 to May 2008, 110 sonographically benign lesions in 62 patients were sampled via US-guided VAB. We prospectively evaluated the sonographic findings 1 week and 6 months after VAB in all patients to determine the presence of residual tumors, hematomas and scarring. We evaluated the prevalence of hematoma, pain, skin dimpling, fibrotic scarring and residual tumors after US-guided VAB, and determined if correlation existed between complications, size of the lesions and lesion pathology. The age of the patients was 15-65 years, with a mean age of 36.5 years. The pathologic diagnoses were fibroadenomas (41.8%, n = 46), fibrocystic changes (30.9%, n = 34), fibroadenomatoid hyperplasias (13.6%, n = 15), fibroadenomatoid mastopathies (6.3%, n = 7), adenoses (3.6%, n = 4), hamartomas (1.8%, n = 2) and phyllodes tumors (1.8%, n = 2). Complications 1 week after the US-guided VAB included hematomas (n = 39, 35.4%), pain (n = 23, 20.9%), fibrotic scars (n = 26, 23.68%), residual tumors (n = 4, 3.6%) and skin dimplings (n = 4, 3.6%). Complications 6 months after the US-guided VAB included hematomas (n = 12, 10.9%), pain (n = 3 2.7%), fibrotic scars (n = 14, 12.7%), and residual tumors (n = 17, 15.4%). Residual tumor after US-guided VAB existed in association with 15.2% of fibroadenomas (7/46), 14.7% of fibrocystic changes (5/34), 13.3% of fibroadenomatoid hyperplasias (2/15), 25% of adenoses (1/4), and 100% of phyllodes tumors (2/2). US-guided VAB is an effective procedure for removal of benign breast lesion. Periodic follow up studies at 1 week and 6 months after the VAB are useful to assess Post-VAB complications

Usefulness and Complications of Ultrasonography- Guided Vacuum Assisted Biopsy for the Removal of Benign Breast Lesions

International Nuclear Information System (INIS)

Kim, Keum Won; Cho, Young Jun; Hwang, Cheol Mog; Kim, Dae Ho; Oh, Kyoung Jin; Yoon, Dae Sung; Kim, Kyu Soon

2010-01-01

To evaluate the usefulness and complications of ultrasonography (US)- guided vacuum assisted biopsy (VAB) for the removal of benign breast lesions, and the short- and long-term changes after VAB as shown on follow-up US. From January 2007 to May 2008, 110 sonographically benign lesions in 62 patients were sampled via US-guided VAB. We prospectively evaluated the sonographic findings 1 week and 6 months after VAB in all patients to determine the presence of residual tumors, hematomas and scarring. We evaluated the prevalence of hematoma, pain, skin dimpling, fibrotic scarring and residual tumors after US-guided VAB, and determined if correlation existed between complications, size of the lesions and lesion pathology. The age of the patients was 15-65 years, with a mean age of 36.5 years. The pathologic diagnoses were fibroadenomas (41.8%, n = 46), fibrocystic changes (30.9%, n = 34), fibroadenomatoid hyperplasias (13.6%, n = 15), fibroadenomatoid mastopathies (6.3%, n = 7), adenoses (3.6%, n = 4), hamartomas (1.8%, n = 2) and phyllodes tumors (1.8%, n = 2). Complications 1 week after the US-guided VAB included hematomas (n = 39, 35.4%), pain (n = 23, 20.9%), fibrotic scars (n = 26, 23.68%), residual tumors (n = 4, 3.6%) and skin dimplings (n = 4, 3.6%). Complications 6 months after the US-guided VAB included hematomas (n = 12, 10.9%), pain (n = 3 2.7%), fibrotic scars (n = 14, 12.7%), and residual tumors (n = 17, 15.4%). Residual tumor after US-guided VAB existed in association with 15.2% of fibroadenomas (7/46), 14.7% of fibrocystic changes (5/34), 13.3% of fibroadenomatoid hyperplasias (2/15), 25% of adenoses (1/4), and 100% of phyllodes tumors (2/2). US-guided VAB is an effective procedure for removal of benign breast lesion. Periodic follow up studies at 1 week and 6 months after the VAB are useful to assess Post-VAB complications

Structural analysis of the equipment removal system for tank 241SY101

International Nuclear Information System (INIS)

Mackey, T.C.

1995-01-01

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

Computed tomography-guided percutaneous trephine removal of the nidus in osteoid osteoma patients: experience of a single center in Brazil

Energy Technology Data Exchange (ETDEWEB)

Petrilli, Marcelo; Senerchia, Andreza Almeida; Petrilli, Antonio Sergio; Lederman, Henrique Manoel; Garcia Filho, Reynaldo Jesus, E-mail: andrezasenerchia@hotmail.com [Universidade Federal de Sao Paulo (UNIFESP), Sao Paulo, SP (Brazil). Instituto de Oncologia Pediatrica

2015-07-15

Objective: to report the results of computed tomography (CT)-guided percutaneous resection of the nidus in 18 cases of osteoid osteoma. Materials and methods: the medical records of 18 cases of osteoid osteoma in children, adolescents and young adults, who underwent CT-guided removal of the nidus between November, 2004 and March, 2009 were reviewed retrospectively for demographic data, lesion site, clinical outcome and complications after procedure. Results: clinical follow-up was available for all cases at a median of 29 months (range 6-60 months). No persistence of pre-procedural pain was noted on 17 patients. Only one patient experienced recurrence of symptoms 12 months after percutaneous resection, and was successfully retreated by the same technique, resulting in a secondary success rate of 18/18 (100%). Conclusion: CT-guided removal or destruction of the nidus is a safe and effective alternative to surgical resection of the osteoid osteoma nidus. (author)

Hoisting appliances and fuel handling equipment at nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-12-31

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

Equipment Reliability Process in Krsko NPP

International Nuclear Information System (INIS)

Gluhak, M.

2016-01-01

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

Does Ultrasound-Guided Directional Vacuum-Assisted Removal Help Eliminate Abnormal Nipple Discharge in Patients with Benign Intraductal Single Mass?

Energy Technology Data Exchange (ETDEWEB)

Chang, Jung Min; Cho, Na Ri Ya; Moon, Woo Kyung [Seoul National University Hospital, Seoul (Korea, Republic of); Park, Jeong Seon [Hanyang University Hospital, Seoul (Korea, Republic of); Chung, Se Yeong [Seoul National University Boramae Hospital, Seoul (Korea, Republic of); Jang, Mi Jung [Seoul National University Bundang Hospital, Seongnam (Korea, Republic of)

2009-12-15

To evaluate whether the removal of an intraductal mass using an ultrasound (US)-guided directional vacuum-assisted device can eliminate symptoms in patients presenting with abnormal nipple discharge. Between March 2004 and October 2006, 36 patients who presented with abnormal nipple discharge, underwent US-guided, 11-gauge vacuum-assisted biopsy for a benign intraductal single mass on US. The ability of the procedure to eliminate nipple discharge was evaluated by physical examination during follow-up US. Lesion characteristics, biopsy variables, and histologic features were analyzed to identify factors affecting symptom resolution. Of the 36 lesions, 25 (69%) were intraductal papillomas, 10 (28%) were fibrocystic changes, and one (3%) was a fibroadenoma. The nipple discharge disappeared in 69% (25 of 36) of the women at a mean follow-up time of 25 months (range 12-42 month). There was no difference in the lesion characteristics, biopsy variables, and the histologic features between groups that eliminated the symptom compared those with persistent nipple discharge. US-guided directional vacuum-assisted removal of an intraductal mass appears to eliminate nipple discharge in only 69% of patients and thus, it should not be considered as an alternative to surgical excision.

Airborne asbestos concentrations associated with heavy equipment brake removal.

Science.gov (United States)

Madl, A K; Gaffney, S H; Balzer, J L; Paustenbach, D J

2009-11-01

Asbestos-containing brake linings were used in heavy-duty construction equipment such as tractors, backhoes, and bulldozers prior to the 1980s. While several published studies have evaluated exposures to mechanics during brake repair work, most have focused on automobiles and light trucks, not on heavy agricultural or construction vehicles. The purpose of this study is to characterize the airborne concentration of asbestos to workers and bystanders from brake wear debris during brake removal from 12 loader/backhoes and tractors manufactured between 1960 and 1980. Asbestos content in brake lining (average 20% chrysotile by polarized light microscopy) and brake wear debris [average 0.49% chrysotile by transmission electron microscopy (TEM)] was also quantified. Breathing zone samples on the lapel of mechanics (n = 44) and area samples at bystander (n = 34), remote (n = 22), and ambient (n = 12) locations were collected during 12 brake changes and analyzed using phase contrast microscopy (PCM) [National Institute for Occupational Safety and Health (NIOSH) 7400] and TEM (NIOSH 7402). In addition, the fiber distribution by size and morphology was evaluated according to the International Organization for Standardization method for asbestos. Applying the ratio of asbestos fibers:total fibers (including non-asbestos) as determined by TEM to the PCM results, the average airborne chrysotile concentrations (PCM equivalent) were 0.024 f/cc for the mechanic and 0.009 f/cc for persons standing 1.2-3.1 m from the activity during the period of exposure ( approximately 0.5 to 1 h). Considering the time involved in the activity, and assuming three brake jobs per shift, these results would convert to an average 8-h time-weighted average of 0.009 f/cc for a mechanic and 0.006 f/cc for a bystander. The results indicate that (i) the airborne concentrations for worker and bystander samples were significantly less than the current occupational exposure limit of 0.1 f/cc; (ii

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.

Guide to optimized replacement of equipment seals

International Nuclear Information System (INIS)

Gleason, J.F.

1990-03-01

A reevaluation of current scheduled replacement intervals of polymeric seals in plant equipment can achieve significant benefits. Information is provided which has the potential for increasing replacement intervals based on better information on how seals have performed through unique nuclear industry tests to qualify equipment, improved elastomers and increased knowledge of the failure mechanisms and related performance. The research was performed by reviewing applications of elastomeric seals in nuclear plants and practice associated with defining seal replacement intervals in the nuclear power and other industries. Performance indicators and how they predict degradation of seals were evaluated. Guidelines and a flow chart for reevaluating seal replacement intervals are provided. 29 refs., 38 figs., 8 tabs

Influence of surface layer removal of shade guide tabs on the measured color by spectrophotometer and spectroradiometer.

Science.gov (United States)

Kim, Jin-Cheol; Yu, Bin; Lee, Yong-Keun

2008-12-01

To determine the changes in color parameters of Vitapan 3D-Master shade guide tabs by a spectrophotometer (SP) or a spectroradiometer (SR), and by the removal of the surface layer of the tabs that was performed to make a flat measuring surface for the SP color measurement. Color of the shade tabs was measured before and after removing the surface layer of the tabs using SP and SR. Correlations between the color parameters between the original (OR) and the surface layer removed (RM) tabs and between the SP and the SR measurements were determined (alpha=0.05). Based on SP, the lightness, chroma, CIE a* and b* values measured after the surface layer removal were higher than those of the original tabs except a few cases. Based on SR, the chroma and CIE a* and b* values measured after surface layer removal were higher than those of the original tabs except a few cases; however, in case of the lightness, the changes varied by the shade designation. Type of instrument influenced the changes in color parameters based on paired t-test (pspectrophotometer or a spectroradiometer, measurement protocols should be specified because color difference by the surface layer removal and the instrument was high.

241-AZ-101 pump removal trough analysis

International Nuclear Information System (INIS)

Coverdell, B.L.

1995-01-01

As part of the current Hanford mission of environmental cleanup, various long length equipment must be removed from highly radioactive waste tanks. The removal of equipment will utilize portions of the Equipment Removal System for Project W320 (ERS-W320), specifically the 50 ton hydraulic trailer system. Because the ERS-W320 system was designed to accommodate much heavier equipment it is adequate to support the dead weight of the trough, carriage and related equipment for 241AZ101 pump removal project. However, the ERS-W320 components when combined with the trough and its' related components must also be analyzed for overturning due to wind loads. Two troughs were designed, one for the 20 in. diameter carriage and one for the 36 in. diameter carriage. A proposed 52 in. trough was not designed and, therefore is not included in this document. In order to fit in the ERS-W320 strongback the troughs were design with the same widths. Structurally, the only difference between the two troughs is that more material was removed from the stiffener plates on the 36 in trough. The reduction in stiffener plate material reduces the allowable load. Therefore, only the 36 in. trough was analyzed

CONTAMINATED PROCESS EQUIPMENT REMOVAL FOR THE DECOMMISSIONG AND DECONTAMINATION OF THE 232-Z CONTAMINATED WASTE RECOVERY PROCESS FACILITY AT THE PLUTONIUM FINISHING PLANT

International Nuclear Information System (INIS)

HOPKINS, A.M.; MINETTE, M.J.; KLOS, D.B.

2007-01-01

This paper describes the unique challenges encountered and subsequent resolutions to accomplish the deactivation and decontamination of a plutonium ash contaminated building. The 232-Z Contaminated Waste Recovery Process Facility at the Plutonium Finishing Plant was used to recover plutonium from process wastes such as rags, gloves, containers and other items by incinerating the items and dissolving the resulting ash. The incineration process resulted in a light-weight plutonium ash residue that was highly mobile in air. This light-weight ash coated the incinerator's process equipment, which included gloveboxes, blowers, filters, furnaces, ducts, and filter boxes. Significant airborne contamination (over 1 million derived air concentration hours [DAC]) was found in the scrubber cell of the facility. Over 1300 grams of plutonium held up in the process equipment and attached to the walls had to be removed, packaged and disposed. This ash had to be removed before demolition of the building could take place

Nuclear power plant equipped with hydrogen removing system

International Nuclear Information System (INIS)

Ezawa, Shin-ichi; Yamanari, Shozo; Okura, Minoru; Kamizuma, Nobuaki.

1998-01-01

A γ-shield and container spray pipelines are disposed to an upper dry well in a reactor container incorporating a reactor pressure vessel. A plurality of catalytic hydrogen removing devices are disposed close to a wall on the side of the pressure vessel in the dry well and a wall on the side of the outer wall of the reactor container. The plurality of catalytic hydrogen removing devices are disposed substantially equally in horizontal direction and circumferential direction of the side walls. If container spray water is sprayed, the atmospheric gases in the reactor are compulsory circulated. In addition, since the temperature of the γ-shield is higher than the atmospheric temperature, spontaneous circulation is caused. As a result, rising currents of gases are formed at regions in the vicinity of the γ-shield. The catalytic hydrogen removing devices are disposed to the places where the rising currents are formed. (I.N.)

Hoisting appliances and fuel handling equipment at nuclear facilities

International Nuclear Information System (INIS)

1987-01-01

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

A novel removable shield attached to C-arm units against scattered X-rays from a patient's side

Energy Technology Data Exchange (ETDEWEB)

Mori, Hiroshige [Hokkaido Social Insurance Hospital, Department of Radiology, Sapporo, Hokkaido (Japan); Kanazawa University, Department of Quantum Medical Technology, Division of Health Sciences, Graduate School of Medical Science, Kanazawa, Ishikawa (Japan); Koshida, Kichiro; Matsubara, Kosuke [Kanazawa University, School of Health Sciences, College of Medical, Pharmaceutical and Health Sciences, Kanazawa, Ishikawa (Japan); Ishigamori, Osamu [Hokkaido Social Insurance Hospital, Department of Radiology, Sapporo, Hokkaido (Japan)

2014-08-15

We invented a drape-like shield against scattered X-rays that can safely come into contact with medical equipment or people during fluoroscopically guided procedures. The shield can be easily removed from a C-arm unit using one hand. We evaluated the use of the novel removable shield during the endoscopic retrograde cholangiopancreatography (ERCP) procedure. We measured the dose rate of scattered X-rays around endoscopists with and without this removable shield and surveyed the occupational doses to the ERCP staff. We also examined the endurance of the shield. The removable shield reduced the dose rate of scattered X-rays to one-tenth and reduced the monthly dose to an endoscopist by at least two-fifths. For 2.5 years, there was no damage to the shield and no loosening of the seam. The bonding of the hook-and-loop fasteners did not weaken, although the powerful double-sided tapes made especially for plastic did. The removable shield can reduce radiation exposure to the ERCP staff and may contribute to reducing the exposure to the eye lenses of operators. It would also be possible to expand its use to other fluoroscopically guided procedures besides ERCP because it is a light, simple, and useful device. (orig.)

Orphee reactor experimental equipment

International Nuclear Information System (INIS)

1987-01-01

Experimental equipment around the ORPHEE reactor is presented. The neutron source; and the spectrometers and sample environment (inelastic and quasi-elastic scattering, elastic scattering, spread scattering, small angle scattering) are described. An experiment proposal and reports guide is supplied [fr

Removal of contaminants from equipment and debris and waste minimization using TechXtract{reg_sign} technology

Energy Technology Data Exchange (ETDEWEB)

Bonem, M.W. [EET, Inc., Bellaire, TX (United States)

1997-10-01

Under this Program Research and Development Agreement (PRDA), EET, Inc., is extending its proprietary TechXtract{reg_sign} chemical decontamination technology into an effective, economical, integrated contaminant removal system. This integrated system will consist of a series of decontamination baths using the TechXtract{reg_sign} chemical formulas, followed by a waste treatment process that will remove the contaminants from the spent chemicals. Sufficient decontamination will result so that materials can be released without restriction after they have been treated, even those materials that have traditionally been considered to be {open_quotes}undecontaminable.{close_quotes} The secondary liquid waste will then be treated to separate any hazardous and radioactive contaminants, so that the spent chemicals and wastewater can be discharged through conventional, permitted outlets. The TechXtract{reg_sign} technology is a unique process that chemically extracts hazardous contaminants from the surface and substrate of concrete, steel, and other solid materials. This technology has been used successfully to remove contaminants as varied as PCBs, radionuclides, heavy metals, and hazardous organics. The process` advantage over other alternatives is its effectiveness in safe and consistent extraction of subsurface contamination. TechXtract{reg_sign} is a proprietary process developed, owned, and provided by EET, Inc. The objective of the PRDA is to demonstrate on a full-scale basis an economical system for decontaminating equipment and debris, with further treatment of secondary waste streams to minimize waste volumes. Contaminants will be removed from the contaminated items to levels where they can be released for unrestricted use. The entire system will be designed with maximum flexibility and automation in mind.

Removal of contaminants from equipment and debris and waste minimization using TechXtract reg-sign technology

International Nuclear Information System (INIS)

Bonem, M.W.

1997-01-01

Under this Program Research and Development Agreement (PRDA), EET, Inc., is extending its proprietary TechXtract reg-sign chemical decontamination technology into an effective, economical, integrated contaminant removal system. This integrated system will consist of a series of decontamination baths using the TechXtract reg-sign chemical formulas, followed by a waste treatment process that will remove the contaminants from the spent chemicals. Sufficient decontamination will result so that materials can be released without restriction after they have been treated, even those materials that have traditionally been considered to be open-quotes undecontaminable.close quotes The secondary liquid waste will then be treated to separate any hazardous and radioactive contaminants, so that the spent chemicals and wastewater can be discharged through conventional, permitted outlets. The TechXtract reg-sign technology is a unique process that chemically extracts hazardous contaminants from the surface and substrate of concrete, steel, and other solid materials. This technology has been used successfully to remove contaminants as varied as PCBs, radionuclides, heavy metals, and hazardous organics. The process' advantage over other alternatives is its effectiveness in safe and consistent extraction of subsurface contamination. TechXtract reg-sign is a proprietary process developed, owned, and provided by EET, Inc. The objective of the PRDA is to demonstrate on a full-scale basis an economical system for decontaminating equipment and debris, with further treatment of secondary waste streams to minimize waste volumes. Contaminants will be removed from the contaminated items to levels where they can be released for unrestricted use. The entire system will be designed with maximum flexibility and automation in mind

Passive breath gating equipment for cone beam CT-guided RapidArc gastric cancer treatments

International Nuclear Information System (INIS)

Hu, Weigang; Li, Guichao; Ye, Jinsong; Wang, Jiazhou; Peng, Jiayuan; Gong, Min; Yu, Xiaoli; Studentski, Matthew T.; Xiao, Ying; Zhang, Zhen

2015-01-01

Background and purpose: To report preliminary results of passive breath gating (PBG) equipment for cone-beam CT image-guided gated RapidArc gastric cancer treatments. Material and methods: Home-developed PBG equipment integrated with the real-time position management system (RPM) for passive patient breath hold was used in CT simulation, online partial breath hold (PBH) CBCT acquisition, and breath-hold gating (BHG) RapidArc delivery. The treatment was discontinuously delivered with beam on during BH and beam off for free breathing (FB). Pretreatment verification PBH CBCT was obtained with the PBG-RPM system. Additionally, the reproducibility of the gating accuracy was evaluated. Results: A total of 375 fractions of breath-hold gating RapidArc treatments were successfully delivered and 233 PBH CBCTs were available for analysis. The PBH CBCT images were acquired with 2–3 breath holds and 1–2 FB breaks. The imaging time was the same for PBH CBCT and conventional FB CBCT (60 s). Compared to FB CBCT, the motion artifacts seen in PBH CBCT images were remarkably reduced. The average BHG RapidArc delivery time was 103 s for one 270-degree arc and 269 s for two full arcs. Conclusions: The PBG-RPM based PBH CBCT verification and BHG RapidArc delivery was successfully implemented clinically. The BHG RapidArc treatment was accomplished using a conventional RapidArc machine with high delivery efficiency

Quality control of diagnostic x-ray equipment and film processing

International Nuclear Information System (INIS)

1993-01-01

According to the section 40 of the Radiation Act (592/92), the licensee is required in Finland to make the arrangements to control the function of the radiation equipment and related facilities used for medical procedures. The guide explains how quality control can be organized for diagnostic x-ray equipment. It also gives recommendations for constancy tests for conventional x-ray radiographic and fluoroscopic equipment and for film processing. The recommendations are based on the publications and statements of the International Committee for Radiation Protection (ICRP) and standardization organizations. The intention is that the operators of x-ray equipment or the maintenance personnel are able to perform the quality control tests presented in the guide

Intelligent Image Analysis for Image-Guided Laser Hair Removal and Skin Therapy

Science.gov (United States)

Walker, Brian; Lu, Thomas; Chao, Tien-Hsin

2012-01-01

We present the development of advanced automatic target recognition (ATR) algorithms for the hair follicles identification in digital skin images to accurately direct the laser beam to remove the hair. The ATR system first performs a wavelet filtering to enhance the contrast of the hair features in the image. The system then extracts the unique features of the targets and sends the features to an Adaboost based classifier for training and recognition operations. The ATR system automatically classifies the hair, moles, or other skin lesion and provides the accurate coordinates of the intended hair follicle locations. The coordinates can be used to guide a scanning laser to focus energy only on the hair follicles. The intended benefit would be to protect the skin from unwanted laser exposure and to provide more effective skin therapy.

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

International Nuclear Information System (INIS)

2015-01-01

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

Test Plan for the overburden removal demonstration

International Nuclear Information System (INIS)

Rice, P.; Thompson, D.; Winberg, M.; Skaggs, J.

1993-06-01

The removal of soil overburdens from contaminated pits and trenches involves using equipment that will remove a small layer of soil from 3 to 6 in. at any time. As a layer of soil is removed, overburden characterization techniques perform surveys to a depth that exceeds each overburden removal layer to ensure that the removed soil will be free of contamination. It is generally expected that no contamination will be found in the soil overburden, which was brought in after the waste was put in place. It is anticipated that some containers in the waste zone have lost their integrity, and the waste leakage from those containers has migrated by gravity downward into the waste zone. To maintain a safe work environment, this method of overburden removal should allow safe preparation of a pit or trench for final remediation. To demonstrate the soil overburden techniques, the Buried Waste Integrated Demonstration Program has contracted vendor services to provide equipment and techniques demonstrating soil overburden removal technology. The demonstration will include tests that will evaluate equipment performance and techniques for removal of overburden soil, control of contamination spread, and dust control. To evaluate the performance of these techniques, air particulate samples, physical measurements of the excavation soil cuts, maneuverability measurements, and time versus volume (rate) of soil removal data will be collected during removal operations. To provide a medium for sample evaluation, the overburden will be spiked at specific locations and depths with rare earth tracers. This test plan will be describe the objectives of the demonstration, data quality objectives, methods to be used to operate the equipment and use the techniques in the test area, and methods to be used in collecting data during the demonstration

Employee guide to respiratory protection

International Nuclear Information System (INIS)

Wright, E.M.

1982-01-01

This employee guide discusses use of respiratory protective equipment for particulates, gases, vapors, supplied air, and self-contained breathing apparatus. It also covers equipment selection medical factors, fitting criteria; care; and employee responsibilities

Control of nuclear material specified equipment and specified material

International Nuclear Information System (INIS)

1982-04-01

The goal and application field of NE 2.02 regulatory guide of CNEN (Comissao Nacional de Energia Nuclear), are described. This regulatory guide is about nuclear material management, specified equipment and specified material. (E.G.) [pt

Methods to estimate equipment and materials that are candidates for removal during the decontamination of fuel processing facilities

International Nuclear Information System (INIS)

Duncan, D.R.; Valero, O.J.; Hyre, R.A.; Pottmeyer, J.A.; Millar, J.S.; Reddick, J.A.

1995-02-01

The methodology presented in this report provides a model for estimating the volume and types of waste expected from the removal of equipment and other materials during Decontamination and Decommissioning (D and D) of canyon-type fuel reprocessing facilities. This methodology offers a rough estimation technique based on a comparative analysis for a similar, previously studied, reprocessing facility. This approach is especially useful as a planning tool to save time and money while preparing for final D and D. The basic methodology described here can be extended for use at other types of facilities, such as glovebox or reactor facilities

Structural analysis of the equipment removal system for tanks 241C106 and 241AY102

International Nuclear Information System (INIS)

Mackey, T.C.

1994-10-01

The calculations documented in this report show that the ERS major components are structurally qualified to complete the objective: install the removed equipment into a shipping container, transport and store the container at the Central Waste Complex (CWC). The analysis for the structural members of the ERS components considers live load with an impact factor of 125% and dead load. An allowable stress of 1/3 yield is used for all structural components carrying the load based on DOE-RL-92-36. Adherence to DOE-RL-92-36 is not a code requirement. However, due to the loads considered, this factor of safety is appropriate. The calculations meet the strength requirements of the American Institute for Steel Construction (AISC 1989) for all non-critical structural elements

VDTT removal system functional design criteria

International Nuclear Information System (INIS)

Legare, D.E.

1996-01-01

Two Velocity Density Temperature Trees (H-2-815016) are to be removed from risers 14A and 1B of tank 241-SY-101. This document provides functional design criteria for the removal system. The removal system consists of a Liquid Removal Tool, Flexible Receiver (H-2-79216), Burial Container, Transport Trailers, and associated equipment

Safety analysis report for packaging (onsite) decontaminated equipment self-container

International Nuclear Information System (INIS)

Boehnke, W.M.

1998-01-01

The purpose of this Safety Analysis Report for Packaging (SARP) is to demonstrate that specific decontaminated equipment can be safely used as its own self-container. As a Decontaminated Equipment Self-Container (also referred to as a self-container), no other packaging, such as a burial box, would be required to transport the equipment onsite. The self-container will consist of a piece of equipment or apparatus which has all readily removable interior contamination removed, all of its external openings sealed, and all external surfaces decontaminated to less than 2000 dpm/100 cm for gamma-emitting radionuclides and less than 220 dpm/100 CM2 for alpha-emitting radionuclides

In-vessel inspection before head removal: TMI II: Phase I. (Conceptual development)

International Nuclear Information System (INIS)

Calloway, N.E.; Greenlee, D.W.; Lawrence, G.R.; Paglia, A.L.; Piatt, T.D.; Tucker, B.A.

1981-08-01

The objective of the task is to provide for an internal inspection of the reactor vessel and the fuel assemblies prior to reactor vessel head removal. Because the degree of damage to equipment and fuel in the TMI-II reactor is not precisely known, it is important that as much information as possible be obtained on present conditions inside the reactor. This information will serve to benchmark the various analyses already completed or underway and will also guide the development of programs to obtain more information on the TMI-II core damage. In addition, the early look will provide data for planning the reactor disassembly program

Treatment of osteoid osteoma using CT-guided radiofrequency ablation versus MR-guided laser ablation: A cost comparison

International Nuclear Information System (INIS)

Maurer, M.H.; Gebauer, B.; Wieners, G.; De Bucourt, M.; Renz, D.M.; Hamm, B.; Streitparth, F.

2012-01-01

Objective: To compare the costs of CT-guided radiofrequency ablation (RFA) and MR-guided laser ablation (LA) for minimally invasive percutaneous treatment of osteoid osteoma. Materials and methods: Between November 2005 and October 2011, 20 patients (14 males, 6 females, mean age 20.3 ± 9.1 years) underwent CT-guided RFA and 24 patients (18 males, 6 females; mean age, 23.8 ± 13.8 years) MR-guided LA (open 1.0 Tesla, Panorama HFO, Philips, Best, Netherlands) for osteoid osteoma diagnosed on the basis of clinical presentation and imaging findings. Prorated costs of equipment use (purchase, depreciation, and maintenance), staff costs, and expenditure for disposables were identified for CT-guided RFA and MR-guided LA procedures. Results: The average total costs per patient were EUR 1762 for CT-guided RFA and EUR 1417 for MR-guided LA. These were (RFA/LA) EUR 92/260 for equipment use, EUR 149/208 for staff, and EUR 870/300 for disposables. Conclusion: MR-guided LA is less expensive than CT-guided RFA for minimally invasive percutaneous ablation of osteoid osteoma. The higher costs of RFA are primarily due to the higher price of the disposable RFA probes.

WP EMPLACEMENT CONTROL AND COMMUNICATION EQUIPMENT DESCRIPTIONS

International Nuclear Information System (INIS)

Raczka, N.T.

1997-01-01

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

40 CFR 273.4 - Applicability-Mercury-containing equipment.

Science.gov (United States)

2010-07-01

... equipment. 273.4 Section 273.4 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR UNIVERSAL WASTE MANAGEMENT General § 273.4 Applicability—Mercury...-containing components have been removed. (c) Generation of waste mercury-containing equipment. (1) Used...

Physical protection equipment study. Final report

International Nuclear Information System (INIS)

Haberman, W.

1977-06-01

This report summarizes the work performed by MITRE for the U.S. Nuclear Regulatory Commission. The major products of this effort are a Catalog of Physical Protection Equipment, a Guide for Evaluation of Physical Protection Equipment, a book of Reference Materials, and a set of guidelines for use in the development of a methodology for measuring levels of security system effectiveness. A summary of recommendations resulting from this study is also presented

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

Nuclear reactor fuel assembly with a removably top nozzle

International Nuclear Information System (INIS)

Shallenberger, J.M.; Ferlan, S.J.

1985-01-01

The invention relates to a nuclear fuel assembly having an improved attaching structure for removably mounting the top nozzle of the fuel assembly on the upper end of a control-rod guide thimble. The attaching structure comprises an outer socket defined in a portion of the top nozzle, an inner socket extending from the upper end of the guide thimble and removably received in the outer socket for interlocking engagement therewith, and an elongate locking member adapted to be inserted into the inner socket to maintain said interlocking engagement. Removal of the locking member from the inner socket enables the latter to be withdrawn from the outer socket, thereby enabling the top nozzle to be removed from the guide thimble

Nuclear EQ sourcebook: A compilation of documents for nuclear equipment qualification

International Nuclear Information System (INIS)

Anon.

1992-01-01

In the nuclear power industry, environmental and seismic qualification of safety-related electrical and instrumentation equipment is collectively known as Equipment Qualification (EQ). Related technology, as well as regulatory requirements, have evolved rapidly during the last 15 years. For environmental qualification, what began in 1971 with one trial-use guide (IEEE Std 323-1971), now stands as a full complement of Nuclear Regulatory Commission (NRC) rules, guides and industry standards. In addition to the Institute of Electrical and Electronics Engineers (IEEE), the American Society of Mechanical Engineers (ASME) has also undertaken development of its own set of standards for use in qualifying safety-related mechanical equipment. To ensure that the original design and qualification is preserved, engineers need to select and use the correct set of NRC regulations, regulatory guides, industry standards, and generic correspondence. Given that the total number of these documents exceed 200, this task becomes resource intensive. This compilation is the first known publication available to serve the user-community need for a complete and exhaustive single source. Approximately 180 items (Bulletins, Federal Rules, Generic Letters, Notices, Regulatory Guides, IEEE Standards, IEEE Recommended Practices, and IEEE Guides) have been processed separately for inclusion on the data base

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

School Chemistry Laboratory Safety Guide

Science.gov (United States)

Brundage, Patricia; Palassis, John

2006-01-01

The guide presents information about ordering, using, storing, and maintaining chemicals in the high school laboratory. The guide also provides information about chemical waste, safety and emergency equipment, assessing chemical hazards, common safety symbols and signs, and fundamental resources relating to chemical safety, such as Material…

Method and apparatus for removing an in-core monitor

International Nuclear Information System (INIS)

Yoshida, Tomiji; Saito, Takashi; Ishii, Yoshimi; Arikawa, Isamu; Yamagata, Hiroko.

1976-01-01

Object: To cut an unremovable in-core monitor in a suitable position by remote control within a reactor and thereafter to remove the in-core monitor. Structure: A cutter body comprises an upper gripping mechanism, a mechanism for upwardly and downwardly moving the upper gripping mechanism, a cutter portion, and a lower gripping mechanism, and when the in-core monitor becomes impossible to be removed from a core, the cutter body is set within a cell of a top guide. First, the in-core monitor can be gripped by the gripping mechanism and then cut by operation of the cutter portion. Next, the lower part of the monitor is gripped by the lower gripping mechanism. Whereafter, the upwardly and downwardly moving mechanism can be operated to remove the head of the in-core monitor from a recess in a top guide. When the cutter body is then removed from the top guide, the in-core monitor is completed to be cut and removed. (Kamimura, M.)

SCHOOL LUNCH, SUGGESTED GUIDES FOR SELECTING LARGE EQUIPMENT.

Science.gov (United States)

South Carolina State Dept. of Education, Columbia.

THE TYPE AND CAPACITY OF A WIDE RANGE OF SCHOOL KITCHEN EQUIPMENT IS RECOMMENDED WITH RESPECT TO THE NUMBER OF MEALS SERVED PER DAY. THESE RECOMMENDATIONS ARE GIVEN FOR RANGES, SINKS, ELECTRIC HEATING, GAS HEATING, REFRIGERATION, TABLES, KITCHEN MACHINES, TRUCK DOLLIES, SCALES, STORAGE CABINETS, OFFICE SPACES, LOUNGES, GARBAGE AND CAN WASHING…

Feasibility study on the guided wave technique for condenser tube in NPP

International Nuclear Information System (INIS)

Choi, Sung Nam; Kim, Young Ho; Kim, Hyung Nam; Yoo, Hyun Joo; Hwang, W. G.

2004-01-01

The condenser tube is examined by the eddy current test (ECT) method to identify the integrity of the nuclear power plant. Because ECT probe is moved through the tube inside to identify flaws, the ECT probe should be exchanged periodically due to the wear of probe surface in order to remove the noise form the ECT signal. Moreover, it is impossible to examine the tube by ECT method because the ECT probe can not move through the inside due to the deformation such as dent. Recently, the theory of guided wave was established and the equipment applying the theory has been actively developed so as to overcome the limitation of ECT method for the tube inspection of heater exchanger in nuclear power plant. The object of this study is to know the feasibility of applying the guided wave technique to condenser tube in NPP

Electrical equipment design library

International Nuclear Information System (INIS)

1994-01-01

This book guides the design supervision, construction order for electrical equipment. The contents of this library are let's use electricity like this, leading-in-pole and casual power, electric pole install below 300KVA, electric pole install below 301∼1000KVA, electric pole install exceed 1000KVA, rooftop install exceed 1000KVA, CUBICLE type, 154KV services. It adds an appendix.

30 CFR 250.617 - Tubing and wellhead equipment.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Tubing and wellhead equipment. 250.617 Section... Tubing and wellhead equipment. The lessee shall comply with the following requirements during well-workover operations with the tree removed: (a) No tubing string shall be placed in service or continue to...

4-H Club Goat Guide.

Science.gov (United States)

Brown, R. Kipp

This guide provides information for 4-H Club members who have decided on a club goat project. Topics include general information in the following areas: show rules; facilities and equipment (barns/sheds, fences, feeders, water containers, and equipment); selection (structural correctness, muscle, volume and capacity, style and balance, and growth…

User's manual for the master equipment list. Phase 1

International Nuclear Information System (INIS)

Sandoval, J.D.

1997-01-01

This manual is intended to provide a user with enough detailed instruction to guide them through the Master Equipment List Phase 1 (MEL Phase 1) application system operations. The MEL Phase 1 application is a database system that stores Equipment Identification Number (EIN) information to support equipment tracking in the 200E and 200W Tank Farms for the Tank Waste Remediation System Division. The MEL Phase 1 application supports both the user application and administrative control functions. The user application functions include: viewing by Folder, reporting, performing queries, and editing specific data. The administrative control functions include: maintaining valid user identifications, passwords, privileges, defining drop-down lists, and review of the change log relating to EIN data entries, additions, deletions, and editing. The scope of this User's Manual is to discuss these functions and is intended to guide users and answer questions regarding the MEL Phase 1 application

MRI-guided and CT-guided cervical nerve root infiltration therapy. A cost comparison

Energy Technology Data Exchange (ETDEWEB)

Maurer, M.H.; Froeling, V.; Roettgen, R.; Bucourt, M. de; Hamm, B.; Streitparth, F. [Charite University Medicine Berlin (Germany). Dept. of Diagnostic and Interventional Radiology; Bretschneider, T. [Magdeburg Univ. (Germany). Dept. of Radiology and Nuclear Medicine; Hartwig, T.; Disch, A.C. [Charite University Medicine Berlin (Germany). Center for Musculoskeletal Surgery

2014-06-15

Purpose: To evaluate and compare the costs of MRI-guided and CT-guided cervical nerve root infiltration for the minimally invasive treatment of radicular neck pain. Materials and Methods: Between September 2009 and April 2012, 22 patients (9 men, 13 women; mean age: 48.2 years) underwent MRI-guided (1.0 Tesla, Panorama HFO, Philips) single-site periradicular cervical nerve root infiltration with 40 mg triamcinolone acetonide. A further 64 patients (34 men, 30 women; mean age: 50.3 years) were treated under CT fluoroscopic guidance (Somatom Definition 64, Siemens). The mean overall costs were calculated as the sum of the prorated costs of equipment use (purchase, depreciation, maintenance, and energy costs), personnel costs and expenditure for disposables that were identified for MRI- and CT-guided procedures. Additionally, the cost of ultrasound guidance was calculated. Results: The mean intervention time was 24.9 min. (range: 12-36 min.) for MRI-guided infiltration and 19.7 min. (range: 5-54 min.) for CT-guided infiltration. The average total costs per patient were EUR 240 for MRI-guided interventions and EUR 124 for CT-guided interventions. These were (MRI/CT guidance) EUR 150/60 for equipment use, EUR 46/40 for personnel, and EUR 44/25 for disposables. The mean overall cost of ultrasound guidance was EUR 76. Conclusion: Cervical nerve root infiltration using MRI guidance is still about twice as expensive as infiltration using CT guidance. However, since it does not involve radiation exposure for patients and personnel, MRI-guided nerve root infiltration may become a promising alternative to the CT-guided procedure, especially since a further price decrease is expected for MRI devices and MR-compatible disposables. In contrast, ultrasound remains the less expensive method for nerve root infiltration guidance. (orig.)

MRI-guided and CT-guided cervical nerve root infiltration therapy. A cost comparison

International Nuclear Information System (INIS)

Maurer, M.H.; Froeling, V.; Roettgen, R.; Bucourt, M. de; Hamm, B.; Streitparth, F.; Bretschneider, T.; Hartwig, T.; Disch, A.C.

2014-01-01

Purpose: To evaluate and compare the costs of MRI-guided and CT-guided cervical nerve root infiltration for the minimally invasive treatment of radicular neck pain. Materials and Methods: Between September 2009 and April 2012, 22 patients (9 men, 13 women; mean age: 48.2 years) underwent MRI-guided (1.0 Tesla, Panorama HFO, Philips) single-site periradicular cervical nerve root infiltration with 40 mg triamcinolone acetonide. A further 64 patients (34 men, 30 women; mean age: 50.3 years) were treated under CT fluoroscopic guidance (Somatom Definition 64, Siemens). The mean overall costs were calculated as the sum of the prorated costs of equipment use (purchase, depreciation, maintenance, and energy costs), personnel costs and expenditure for disposables that were identified for MRI- and CT-guided procedures. Additionally, the cost of ultrasound guidance was calculated. Results: The mean intervention time was 24.9 min. (range: 12-36 min.) for MRI-guided infiltration and 19.7 min. (range: 5-54 min.) for CT-guided infiltration. The average total costs per patient were EUR 240 for MRI-guided interventions and EUR 124 for CT-guided interventions. These were (MRI/CT guidance) EUR 150/60 for equipment use, EUR 46/40 for personnel, and EUR 44/25 for disposables. The mean overall cost of ultrasound guidance was EUR 76. Conclusion: Cervical nerve root infiltration using MRI guidance is still about twice as expensive as infiltration using CT guidance. However, since it does not involve radiation exposure for patients and personnel, MRI-guided nerve root infiltration may become a promising alternative to the CT-guided procedure, especially since a further price decrease is expected for MRI devices and MR-compatible disposables. In contrast, ultrasound remains the less expensive method for nerve root infiltration guidance. (orig.)

Radiation therapy sources, equipment and installations

International Nuclear Information System (INIS)

2011-03-01

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

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

International Nuclear Information System (INIS)

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

1986-01-01

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

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

International Nuclear Information System (INIS)

2015-01-01

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

Techniques for removing contaminated concrete surfaces

International Nuclear Information System (INIS)

Halter, J.M.; Sullivan, R.G.

1981-01-01

This discussion compares various techniques that have been used to clean concrete surfaces by removing the surface. Three techniques which have been investigated by the Pacific Northwest Laboratory for removing surfaces are also described: the water cannon, the concrete spaller, and high-pressure water jet. The equipment was developed with the assumption that removal of the top 1/8 to 1/4 in. of surface would remove most of the contamination. If the contamination has gone into cracks or deep voids in the surface, the removal processes can be repeated until the surface is acceptable

Application of the Guided Wave Technique to the Heat Exchanger Tube in NPP

International Nuclear Information System (INIS)

Yang, Dong Soon; Kim, Hyung Nam; Yoo, Hyun Joo

2005-01-01

The heat exchanger tube is examined by the method of eddy current test(ECT) to identify the integrity of the nuclear power plant. Because ECT probe is moved through the tube inside to identify flaws, the ECT probe should be exchanged periodically due to the wear of probe surface in order to remove the noise form the ECT signal. Moreover, it is impossible to examine the tube by ECT method because the ECT probe can not move through the inside due to the deformation such as dent. Recently, the theory of guided wave was established and the equipment applying the theory has been actively developed so as to overcome the limitation of ECT method for the tube inspection of heater exchanger in nuclear power plant. The object of this study is to know the application of the guided wave technique to heat exchanger tube in NPP

Furniture and Equipment in Schools: A Purchasing Guide. Managing School Facilities, Guide 7.

Science.gov (United States)

Wadsworth, Alison

This document offers advice on the processes that should be followed when schools in the United Kingdom buy their furniture and equipment (F&E). Sections 1 and 2 examine the first steps, prior to purchasing, such as curriculum analysis and market exploration; and sections 3 and 4 explore the importance of creating a clear specification for…

Equipment for checking bearing tolerances in sealed pumps, especially for nuclear engineering

International Nuclear Information System (INIS)

Zajic, V.

1980-01-01

The equipment consists of a guide pin passing through a coaxial telescopic insert mounted in a support nut for connection to the pump suction branch. The guide pin is fitted with a shoulder engaging with the pump flywheel and comprises a pin for exerting torsional, pitching and sliding motion. The support nut is provided with two guide surfaces (on the front face and on the circumference). A third guide surface is on the guide pin face. (H.S.)

Operations & Maintenance Best Practices - A Guide to Achieving Operational Efficiency (Release 3)

Energy Technology Data Exchange (ETDEWEB)

Sullivan, Greg; Pugh, Ray; Melendez, Aldo P.; Hunt, W. D.

2010-08-04

This guide highlights operations and maintenance programs targeting energy and water efficiency that are estimated to save 5% to 20% on energy bills without a significant capital investment. The purpose of this guide is to provide you, the Operations and Maintenance (O&M)/Energy manager and practitioner, with useful information about O&M management, technologies, energy and water efficiency, and cost-reduction approaches. To make this guide useful and to reflect your needs and concerns, the authors met with O&M and Energy managers via Federal Energy Management Program (FEMP) workshops. In addition, the authors conducted extensive literature searches and contacted numerous vendors and industry experts. The information and case studies that appear in this guide resulted from these activities. It needs to be stated at the outset that this guide is designed to provide information on effective O&M as it applies to systems and equipment typically found at Federal facilities. This guide is not designed to provide the reader with step-by-step procedures for performing O&M on any specific piece of equipment. Rather, this guide first directs the user to the manufacturer's specifications and recommendations. In no way should the recommendations in this guide be used in place of manufacturer's recommendations. The recommendations in this guide are designed to supplement those of the manufacturer, or, as is all too often the case, provide guidance for systems and equipment for which all technical documentation has been lost. As a rule, this guide will first defer to the manufacturer's recommendations on equipment operation and maintenance.

High-speed railway signal trackside equipment patrol inspection system

Science.gov (United States)

Wu, Nan

2018-03-01

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

Regulatory Guide 1.122: Development of floor design response spectra for seismic design of floor-supported equipment or components

International Nuclear Information System (INIS)

Anon.

1993-01-01

''Reactor Site Criteria,'' requires, in part, that safety-related structures, systems, and components remain functional in the event of a Safe Shutdown Earthquake (SSE). It specifies the use of a suitable dynamic analysis as one method of ensuring that the structures, systems, and components can withstand the seismic loads. Similarly, paragraph (a)(2) of Section VI of the same appendix requires, in part, that the structures, systems, and components necessary for continued operation without undue risk to the health and safety of the public remain functional in the event of an Operating Basis Earthquake (OBE). Again, the use of suitable dynamic analysis is specified as one method of ensuring that the structures, systems, and components can withstand the seismic loads. This guide describes methods acceptable to the NRC staff for developing two horizontal and one vertical floor design response spectra at various floors or other equipment-support locations of interest from the time-history motions resulting from the dynamic analysis of the supporting structure. These floor design response spectra are needed for the dynamic analysis of the systems or equipment supported at various locations of the supporting structure

AX Tank Farm ancillary equipment study

International Nuclear Information System (INIS)

SKELLY, W.A.

1999-01-01

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

Development of an equipment diagnostic system that evaluates sensor drift

International Nuclear Information System (INIS)

Kanada, Masaki; Arita, Setsuo; Tada, Nobuo; Yokota, Katsuo

2011-01-01

The importance of condition monitoring technology for equipment has increased with the introduction of condition-based maintenance in nuclear power plants. We are developing a diagnostic system using process signals for plant equipment, such as pumps and motors. It is important to enable the diagnostic system to distinguish sensor drift and equipment failure. We have developed a sensor drift diagnostic method that combines some highly correlative sensor signals by using the MT (Mahalanobis-Taguchi) method. Furthermore, we have developed an equipment failure diagnostic method that measures the Mahalanobis distance from the normal state of equipment by the MT method. These methods can respectively detect sensor drift and equipment failure, but there are the following problems. In the sensor drift diagnosis, there is a possibility of misjudging the sensor drift when the equipment failure occurs and the process signal changes because the behavior of the process signal is the same as that of the sensor drift. Oppositely, in the equipment failure diagnosis, there is a possibility of misjudging the equipment failure when the sensor drift occurs because the sensor drift influences the change of process signal. To solve these problems, we propose a diagnostic method combining the sensor drift diagnosis and the equipment failure diagnosis by the MT method. Firstly, the sensor drift values are estimated by the sensor drift diagnosis, and the sensor drift is removed from the process signal. It is necessary to judge the validity of the estimated sensor drift values before removing the sensor drift from the process signal. We developed a method for judging the validity of the estimated sensor drift values by using the drift distribution based on the sensor calibration data. And then, the equipment failure is diagnosed by using the process signals after removal of the sensor drifts. To verify the developed diagnostic system, several sets of simulation data based on abnormal cases

1996 Buyer's Guide

International Nuclear Information System (INIS)

Anon.

1996-01-01

The Buyer's Guide consists of two sections: a list of vendors by category and an alphabetical list of vendors. The type of equipment and services include: air compressors, air conditioning, gas analysis, pipe anchors, anodes, gas appliances, augers, backhoes, pipe bending machines, billing systems, bits, blasting equipment, gas boilers, boring equipment, gas burners, calorimeters, well casings, cathodic protection equipment and surveys, coating machines, coatings, cogeneration equipment, gas heaters, communications equipment, compactors, compressor stations, computer software, flow computers, portable computers, connectors, consulting services, control equipment, cooling systems, corrosion control systems, couplings, cranes, cutting tools, data acquisition systems, dehydration equipment, gas detectors, drilling machines, engine controls and monitors, engineering services, diesel engines, gas engines, excavators, filters, financial services, fireplace equipment, pipe fittings, flanges, flowmeters, food services, fork lifts, gas furnaces, gas exploration, gas marketing services, gas processing, gas production, gas storage, gas transmission, electric generators, heat exchangers, heating systems, hydrostatic testing services, information systems, instruments, insulation, insurance, expansion joints, leak detectors, legal services, lightning protection, lubricants, meter reading services, meter sets, gas meters, NGV equipment, nondestructive test equipment, odorants, offshore drilling, pigs, pipes, pipe maintenance services, pressure relief valves, pressure vessels, pumps, recording equipment, regulators, risers, safety equipment, gas scrubbers, sealants, security systems, separators, SCADA equipment, survey instruments, tanks, telemetering equipment, tractors, training, trenching equipment, gas turbines, underwater tools, valve actuators, valves, vibration analyzers, gas water heaters, weld inspection, welding equipment, and wires and cables

GuideLiner™ as guide catheter extension for the unreachable mammary bypass graft.

Science.gov (United States)

Vishnevsky, Alec; Savage, Michael P; Fischman, David L

2018-03-09

Percutaneous coronary intervention (PCI) of mammary artery bypass grafts through a trans-radial (TR) approach can present unique challenges, including coaxial vessel engagement of the guiding catheter, adequate visualization of the target lesion, sufficient backup support for equipment delivery, and the ability to reach very distal lesions. The GuideLiner catheter, a rapid exchange monorail mother-in-daughter system, facilitates successful interventions in such challenging anatomy. We present a case of a patient undergoing PCI of a right internal mammary artery (RIMA) graft via TR access in whom the graft could not be engaged with any guiding catheter. Using a balloon tracking technique over a guidewire, a GuideLiner was placed as an extension of the guiding catheter and facilitated TR-PCI by overcoming technical challenges associated with difficult anatomy. © 2018 Wiley Periodicals, Inc.

Citizen's Guide to Pesticides.

Science.gov (United States)

Environmental Protection Agency, Washington, DC. Office of Pesticide Programs.

This guide provides suggestions on pest control and safety rules for pesticide use at home. Pest prevention may be possible by modification of pest habitat: removal of food and water sources, removal or destruction of pest shelter and breeding sites, and good horticultural practices that reduce plant stress. Nonchemical alternatives to pesticides…

Retrieval of buried waste using conventional equipment

International Nuclear Information System (INIS)

Valentich, D.J.

1994-01-01

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

A device for reduction of metal oxides generated in electrokinetic separation equipment

International Nuclear Information System (INIS)

Kim, Gye-Nam; Kim, Seung-Soo; Kim, Il-Gook; Jeong, Jung-Whan; Choi, Jong-Won

2015-01-01

For a reduction of waste electrolyte volume and metal oxide volume, the reuse period of the waste electrolyte in the electrokinetic decontamination experiment and the method of a reduction of metal oxide volume in the cathode chamber were drawn out through several experiments with the manufactured 1.2 ton electrokinetic decontamination equipment. The optimum pH of electrolyte in cathode chamber for a reduction of volume of metal oxides was below 2.35. Indoor electrokinetic decontamination equipment for treatment of 1.2 tons of the contaminated soil per batch was manufactured to remove uranium from soil with high removal efficiency during a short time. For a reduction of waste electrolyte volume and metal oxide volume, the reuse period of waste electrolyte in the electrokinetic decontamination experiment and the method of a reduction of metal oxide volume in the cathode chamber were drawn out through several experiments with the manufactured electrokinetic equipment. Indoor electrokinetic decontamination equipment for treatment of 1.2 tons of the contaminated soil was manufactured to remove uranium from soil during a short time

A device for reduction of metal oxides generated in electrokinetic separation equipment

Energy Technology Data Exchange (ETDEWEB)

Kim, Gye-Nam; Kim, Seung-Soo; Kim, Il-Gook; Jeong, Jung-Whan; Choi, Jong-Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

For a reduction of waste electrolyte volume and metal oxide volume, the reuse period of the waste electrolyte in the electrokinetic decontamination experiment and the method of a reduction of metal oxide volume in the cathode chamber were drawn out through several experiments with the manufactured 1.2 ton electrokinetic decontamination equipment. The optimum pH of electrolyte in cathode chamber for a reduction of volume of metal oxides was below 2.35. Indoor electrokinetic decontamination equipment for treatment of 1.2 tons of the contaminated soil per batch was manufactured to remove uranium from soil with high removal efficiency during a short time. For a reduction of waste electrolyte volume and metal oxide volume, the reuse period of waste electrolyte in the electrokinetic decontamination experiment and the method of a reduction of metal oxide volume in the cathode chamber were drawn out through several experiments with the manufactured electrokinetic equipment. Indoor electrokinetic decontamination equipment for treatment of 1.2 tons of the contaminated soil was manufactured to remove uranium from soil during a short time.

Guide to research facilities

Energy Technology Data Exchange (ETDEWEB)

1993-06-01

This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

Improved guide tube bulge tool

International Nuclear Information System (INIS)

Vaill, R.E.; Phillips, W.D.

1979-01-01

A guide tube bulge tool for securing control rod guide tubes to a fuel assembly grid, includes a cylinder having several flexible tines each of which is equipped with a semispherical radially outwardly extending projection. A tapered ram fits into the cylinder so as to force the tines outwardly when the ram is pulled into the cylinder while supporting the other tines. (UK)

Timing criteria for supplemental BWR emergency response equipment

International Nuclear Information System (INIS)

Bickel, John H.

2015-01-01

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

Introduction of sample environment equipment for neutron scattering experiments

International Nuclear Information System (INIS)

Shimojo, Yutaka; Ihata, Yoshiaki; Kaneko, Koji; Takeda, Masayasu

2013-02-01

Neutron scattering experiments have been frequently performed under variety of sample conditions, such as various temperatures, pressures, magnetic fields and stresses, and those complex conditions to fully utilize superior properties of neutron. To this aim, a number of sample environment equipment, refrigerators, furnaces, pressure cells, superconducting magnets are equipped in JRR-3 to be used for experiments. In this document, all available sample environment equipment in both JRR-3 reactor and guide halls are summarized. We hope this document would help neutron scattering users to perform effective and excellent experiments. (author)

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

International Nuclear Information System (INIS)

1994-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

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

CASDAC system: Data Terminal Equipment user's guide

International Nuclear Information System (INIS)

Yamamoto, Yoichi; Koyama, Kinji

1993-03-01

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

Reliable design of electronic equipment an engineering guide

CERN Document Server

Natarajan, Dhanasekharan

2014-01-01

This book explains reliability techniques with examples from electronics design for the benefit of engineers. It presents the application of de-rating, FMEA, overstress analyses and reliability improvement tests for designing reliable electronic equipment. Adequate information is provided for designing computerized reliability database system to support the application of the techniques by designers. Pedantic terms and the associated mathematics of reliability engineering discipline are excluded for the benefit of comprehensiveness and practical applications. This book offers excellent support

CEO's guide to world business costs : oil and gas equipment

International Nuclear Information System (INIS)

2004-01-01

This paper presents the results of a detailed study of wellhead equipment manufacturing costs in 11 countries in North America, Europe and Asia-Pacific. According to the Economist Intelligence Unit (EIU), Canada has a 5 per cent cost advantage and will be the best country in the world to do business between 2004 to 2008 because of its foreign trade policies, high quality infrastructure and market opportunities within the North American marketplace. KPMG Consulting developed a web-based cost model that allows investors to examine the costs involved in setting up and operating a business in more than 120 cities in Canada, the United States, the United Kingdom, France, Germany, Italy, Iceland, Luxembourg, the Netherlands, Japan and Australia. According to the model, a comparison of annual costs for oil and gas wellhead equipment manufacturing was presented for the 11 countries with reference to revenues, costs, and profits before and after income tax. In addition, Canada's research and development (R and D) cost advantage compared to the United States was presented, with reference to tax credits, expenditures, salaries, contracts, capital equipment, volume-based tax credits, and research studies. This report also includes a brief summary of 3 oil and gas companies that came to Canada and prospered. tabs., figs

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

Standard guide for the selection, training and qualification of nondestructive assay (NDA) personnel

CERN Document Server

American Society for Testing and Materials. Philadelphia

2004-01-01

1.1 This guide contains good practices for the selection, training, qualification, and professional development of personnel performing analysis, calibration, physical measurements, or data review using nondestructive assay equipment, methods, results, or techniques. The guide also covers NDA personnel involved with NDA equipment setup, selection, diagnosis, troubleshooting, or repair. Selection, training, and qualification programs based on this guide are intended to provide assurance that NDA personnel are qualified to perform their jobs competently. This guide presents a series of options but does not recommend a specific course of action.

The role of ultrasound-guided vacuum-assisted removal of gynecomastia

Energy Technology Data Exchange (ETDEWEB)

Kim, You Me [Dankook University Hospital, Cheonan (Korea, Republic of)

2008-02-15

To evaluate the role of performing ultrasound (US)-guided vacuum-assisted breast biopsies for the treatment (mammotome excision) of gynecomastia. Between November 2005 and December 2006, nine male patients underwent US-guided mammotome excision for eleven cases of true gynecomastia. The patient ages ranged from 14 to 55 years (mean age, 32.3 years). US-guided mammotome excision was performed with an 11-gauge needle in seven cases and an 8-gauge needle in four cases. After the procedure, the cigarette method using gauze packing was performed. The number of samples, procedure time and presence of complications were evaluated. Scheduled follow-up physical and US examinations were performed after three and six months. For 11 cases of US-guided mammotome excision of gynecomastia, the number of samples ranged from 12-126 (mean, 66) and the procedure time ranged from 10-42 minutes (mean time, 25.1 minutes). Clinical significant complications did not occur immediately after the procedure and complications were not seen after a follow-up examination in any of the cases. At the 3-and 6-month follow up examinations, all of the patients showed a normal male physical appearance on a physical examination and there was no evidence of hypoechoic glandular tissues as seen on ultrasonograms. US-guided mammotome excision is effective for the treatment of small, glandular true gynecomastia and is suggested as a new modality to replace the need for surgery or liposuction.

Methods and equipments used in power reactors

International Nuclear Information System (INIS)

Beraha, R.; Delevallee, A.

1976-01-01

The various reactor γ fuel scanning facilities presently operating around the world are reviewed. Both equipments proposed by FRAMATOME are described: one is intended for scanning removable fuel pencils, and the other one for fuel assembly scanning [fr

CPP-603 Chloride Removal System Decontamination and Decommissioning

International Nuclear Information System (INIS)

Moser, C.L.

1993-02-01

The CPP-603 (annex) Chloride Removal System (CRS) Decontamination and Decommissioning (D ampersand D) Project is described in this report. The CRS was used for removing Chloride ions and other contaminants that were suspended in the waters of the underwater fuel storage basins in the CPP-603 Fuel Receiving and Storage Facility (FRSF) from 1975 to 1981. The Environmental Checklist and related documents, facility characterization, decision analysis', and D ampersand D plans' were prepared in 1991. Physical D ampersand D activities were begun in mid summer of 1992 and were completed by the end of November 1992. All process equipment and electrical equipment were removed from the annex following accepted asbestos and radiological contamination removal practices. The D ampersand D activities were performed in a manner such that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) occurred

Equipment for capping drums, especially with radioactive waste

International Nuclear Information System (INIS)

Bednarik, F.

1987-01-01

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

Predisposal management of high level radioactive waste. Safety guide

International Nuclear Information System (INIS)

2005-01-01

Radioactive waste is generated in the generation of electricity in nuclear power plants and in the use of radioactive material in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized. The principles and requirements that govern the safety of the management of radioactive waste are presented in 'The Principles of Radioactive Waste Management', 'Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety' and 'Predisposal Management of Radioactive Waste, Including Decommissioning'. The objective of this Safety Guide is to provide regulatory bodies and the operators that generate and manage radioactive waste with recommendations on how to meet the principles and requirements established in Refs for the predisposal management of HLW. This Safety Guide applies to the predisposal management of HLW. For liquid HLW arising from the reprocessing of spent fuel the recommendations of this Safety Guide apply from when liquid waste from the first extraction process is collected for storage and subsequent processing. Recommendations and guidance on the storage of spent fuel, whether or not declared as waste, subsequent to its removal from the storage facility of a reactor are provided in Refs. For spent fuel declared as waste this Safety Guide applies to all activities subsequent to its removal from the storage facility of a reactor and prior to its disposal. Requirements pertaining to the transport of spent fuel, whether or not declared as waste, and of all forms of HLW are established. This Safety Guide provides recommendations on the safety aspects of managing HLW, including the planning, design, construction, commissioning, operation and decommissioning of equipment or facilities for the predisposal management of HLW. It addresses the following elements: (a) The characterization and processing (i.e. pretreatment

The removal of Cs-137 from soil using washing-electrokinetic decontamination equipment

International Nuclear Information System (INIS)

Kim, Gyenam; Kim, Seungsoo; Kim, Geunho; Park, Hyemin; Kim, Wansuk; Park, Ukryang; Kwon, Hyeokju; Ryu, Ohha; Moon, Jeikwon

2012-01-01

The radioactive soil at the KAERI radioactive waste storage facility has slightly high hydro-conductivity, and was mainly contaminated with 137 Cs 30-35 years ago. Recently, a soil washing method has been applied to remove 137 Cs from radioactive soil, but it appears that the removal efficiency of 137 Cs had low and a lot of waste solution was generated. Meanwhile, an electrokinetic decontamination method provides high removal efficiency of 137 Cs and generates little waste effluent. Thus, it is suggested that an electrokinetic decontamination method is a suitable technology in consideration of the soil characteristics near South Korean nuclear facilities

Reactive power compensation a practical guide

CERN Document Server

Hofmann, Wolfgang; Just, Wolfgang

2012-01-01

The comprehensive resource on reactive power compensation, presenting the design, application and operation of reactive power equipment and installations The area of reactive power compensation is gaining increasing importance worldwide. If suitably designed, it is capable of improving voltage quality significantly, meaning that losses in equipment and power systems are reduced, the permissible loading of equipment can be increased, and the over-all stability of system operation improved. Ultimately, energy use and CO2 emisson are reduced. This unique guide discusses the

The use of adaptive equipment following total knee replacement

OpenAIRE

McNaught, Jamie; Paul, Lorna

2015-01-01

Introduction: This study evaluates the need for adaptive equipment following total knee replacement. There are no recent studies to guide occupational therapists in the optimum time adaptive equipment is required following total knee replacement.\\ud \\ud Method: A non-experimental, concurrent mixed methods approach was used. The study population was patients attending for total knee replacement at a large general hospital. Outcome measures were the Oxford Knee Score, the United Kingdom Functio...

Dust removal from waste gas arising from fluidized beds

International Nuclear Information System (INIS)

Soltys, L.

1992-01-01

Two types dust removal equipment mostly useful for dust removal from waste gas from fluidized beds, i.e. electrofilters and pulsatory bag filters were presented. Their features and functional properties were compared. (author). 7 refs, 4 figs

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

International Nuclear Information System (INIS)

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

2016-01-01

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

Industrial wastes guide for Alsace; Guide des dechets de l`entreprise Alsace

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-01-01

This guide is aimed for industrial plant managers and gives comprehensive information on industrial waste management: effects of wastes on the environment (water, air, soil), waste processing limitations in Alsace, new regulations, taxes and incentives concerning waste processing in France, and references of national and regional (Alsace) administration and industrial agencies that are related with pollution abatement and control and waste management. The different types of wastes are reviewed, from papers to toxic solvents, with information given on volumes, processes, operators, processing equipment and equipment distributors

The removal of Cs-137 from soil using washing-electrokinetic decontamination equipment

Energy Technology Data Exchange (ETDEWEB)

Kim, Gyenam; Kim, Seungsoo; Kim, Geunho; Park, Hyemin; Kim, Wansuk; Park, Ukryang; Kwon, Hyeokju; Ryu, Ohha; Moon, Jeikwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-10-15

The radioactive soil at the KAERI radioactive waste storage facility has slightly high hydro-conductivity, and was mainly contaminated with {sup 137}Cs 30-35 years ago. Recently, a soil washing method has been applied to remove {sup 137}Cs from radioactive soil, but it appears that the removal efficiency of {sup 137}Cs had low and a lot of waste solution was generated. Meanwhile, an electrokinetic decontamination method provides high removal efficiency of {sup 137}Cs and generates little waste effluent. Thus, it is suggested that an electrokinetic decontamination method is a suitable technology in consideration of the soil characteristics near South Korean nuclear facilities.

Manual on panoramic gamma irradiators (categories 2 and 4). Incorporating: Applications guide, procedures guide, basics guide

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

The document is the first revision of a previous one published in 1993 to provide guidance on the safe use and regulation of self-contained gamma irradiators (Co-60 or Cs-137 sources) in different fields of application. It includes three parts: Applications Guide, which describes the main applications of self-contained gamma irradiators, the type of equipment, including safety systems, operation and maintenance, and how to deal with incidents. Procedures Guide, which gives step by step instructions on how to carry out the practice. Basics Guide, which explains the fundamentals of radiation, the system of units, interaction of radiation with matter radiation detection, etc. The manual is aimed primarily at persons handling such radiation sources on a daily routine basis, as well as at the competent authorities for training of workers in radiation protection or for setting up local radiation protection rules.

Manual on panoramic gamma irradiators (categories 2 and 4). Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1996-01-01

The document is the first revision of a previous one published in 1993 to provide guidance on the safe use and regulation of self-contained gamma irradiators (Co-60 or Cs-137 sources) in different fields of application. It includes three parts: Applications Guide, which describes the main applications of self-contained gamma irradiators, the type of equipment, including safety systems, operation and maintenance, and how to deal with incidents. Procedures Guide, which gives step by step instructions on how to carry out the practice. Basics Guide, which explains the fundamentals of radiation, the system of units, interaction of radiation with matter radiation detection, etc. The manual is aimed primarily at persons handling such radiation sources on a daily routine basis, as well as at the competent authorities for training of workers in radiation protection or for setting up local radiation protection rules

Removal of a seized fuel channel from the KANUPP reactor

International Nuclear Information System (INIS)

Butt, W.M.; Gunn, R.J.

1995-01-01

In support of the Safe operation of KANUPP program, AECL was commissioned in early 1992 to assist the Karachi Nuclear Power Plant in the design and supply of equipment and procedures for removal of a seized fuel channel from the KANUPP CANDU reactor. In addition AECL was also asked to supply technical site support to assist the KANUPP station staff during the removal of the G-12 channel. The design of a fuel channel removal system presented an interesting challenge. The fuel channel design was unique to KANUPP with no history of previous channel removal, consequently nearly all tools and equipment had to be specially designed. In addition, the seized end fitting posed a special problem requiring the development several contingency tools and techniques. This paper is an account of the design and development of the removal system and the site experiences during the actual fuel channel removal. After the channel had been removed, it was confirmed that a corrosion seizure between the end fitting sleeve bearings was inhibiting normal channel elongation. (author)

Development of diaphragm automatic homing equipment

International Nuclear Information System (INIS)

Kobayashi, Hidetoshi; Yamada, Koji; Moriya, Shinichi; Koike, Jiro; Okabe, Masao; Oyama, Akihiro.

1996-01-01

In steam-turbine overhaul inspection, one of the most important processes is to remove rust and deposited contaminants on the surface of turbine parts, while the turbine is in operation, to recover thermal efficiency and prepare good surface conditions for color penetrant inspection. These processes generally are done by dry honing, but this generates dust. To protect laborers against these conditions, Hitachi, Ltd. has developed automatic honing equipment for the diaphragms of the nuclear steam turbine. This equipment was first used in the first annual inspection and overhaul of Hamaoka Nuclear Power Plant No.4 of Chubu Electric Power Inc. (author)

Efficient on-chip hotspot removal combined solution of thermoelectric cooler and mini-channel heat sink

International Nuclear Information System (INIS)

Hao, Xiaohong; Peng, Bei; Xie, Gongnan; Chen, Yi

2016-01-01

Highlights: • A combined solution of thermoelectric cooler (TEC) and mini-channel heat sink to remove the hotspot of the chip has been proposed. • The TEC's mathematical model is established to assess its work performance. • A comparative study on the proposed efficient On-Chip Hotspot Removal Combined Solution. - Abstract: Hotspot will significantly degrade the reliability and performance of the electronic equipment. The efficient removal of hotspot can make the temperature distribution uniform, and ensure the reliable operation of the electronic equipment. This study proposes a combined solution of thermoelectric cooler (TEC) and mini-channel heat sink to remove the hotspot of the chip in the electronic equipment. Firstly, The TEC's mathematical model is established to assess its work performance under different boundary conditions. Then, the hotspot removal capability of the TEC is discussed for different cooling conditions, which has shown that the combined equipment has better hotspot removal capability compared with others. Finally, A TEC is employed to investigate the hotspot removal capacity of the combined solution, and the results have indicated that it can effectively remove hotspot in the diameter of 0.5 mm, the power density of 600W/cm 2 when its working current is 3A and heat transfer thermal resistance is 0 K/W.

TMI-2 reactor vessel head removal

International Nuclear Information System (INIS)

Bengel, P.R.; Smith, M.D.; Estabrook, G.A.

1984-12-01

This report describes the safe removal and storage of the Three Mile Island Unit 2 reactor vessel head. The head was removed in July 1984 to permit the removal of the plenum and the reactor core, which were damaged during the 1979 accident. From July 1982, plans and preparations were made using a standard head removal procedure modified by the necessary precautions and changes to account for conditions caused by the accident. After data acquisition, equipment and structure modifications, and training the head was safely removed and stored and the internals indexing fixture and a work platform were installed on top of the vessel. Dose rates during and after the operation were lower than expected; lessons were learned from the operation which will be applied to the continuing fuel removal operations activities

TMI-2 reactor vessel head removal

International Nuclear Information System (INIS)

Bengel, P.R.; Smith, M.D.; Estabrook, G.A.

1985-09-01

This report describes the safe removal and storage of the Three Mile Island Unit 2 (TMI-2) reactor vessel head. The head was removed in July 1984 to permit the removal of the plenum and the reactor core, which were damaged during the 1979 accident. From July 1982, plans and preparations were made using a standard head removal procedure modified by the necessary precautions and changes to account for conditions caused by the accident. After data acquisition, equipment and structure modifications, and training, the head was safely removed and stored; and the internals indexing fixture and a work platform were installed on top of the vessel. Dose rates during and after the operation were lower than expected; lessons were learned from the operation which will be applied to the continuing fuel removal operations activities

Method of removing tritium in exhaust water in a nuclear equipment

Energy Technology Data Exchange (ETDEWEB)

Iwamoto, T

1976-05-12

A method is claimed to increase the efficiency of removing tritium from waste water through adsorption treatment. Steam is produced by heating waste water containing tritium, and it is passed through a tube filled with an adsorbent such as activated alumina, silica gel or zeolite. When a control limiting value is reached by the concentration of tritium within the steam, the flow of steam is stopped, and the adsorption tube is removed from the path of steam flow. Thereafter, another adsorption tube containing the afore-said adsorbent is provided in the steam flow path, and the steam is then allowed to flow again.

Light Guide Collector Prototype: Laboratory Testing

OpenAIRE

Jitka - Mohelnikova; Stanislav Darula; Ayodeji Omishore; Petr Mohelnik; Denis Micek

2017-01-01

The article reviews the potential of light guide system equipped by a concentrator device capturing daylight applicable for illumination of building interiors and presents results of experiments on performance of its prototype. The main goal is focused on the comparison of traditional solutions and newly developed prototype of the light guide system and presents examination of its light transmission efficiency based on the laboratory experiments.

Removal of focal atheromatous lesions by angioscopically guided high-speed rotary atherectomy. Preliminary experimental observations

International Nuclear Information System (INIS)

Ahn, S.S.; Auth, D.; Marcus, D.R.; Moore, W.S.

1988-01-01

A new high-speed rotary atherectomy device, inserted over a guide wire and directed with an angioscope, offers the potential of restoring patency of outflow vessels by boring out the atheromatous lesion of the orifices of runoff vessels. The device was tested on 68 cadaver arteries with atheromatous lesions involving the superficial femoral, popliteal, and tibial arteries. This was performed with either free segments or in situ with the device placed through a popliteal arteriotomy. The gross results of rotary atherectomy were assessed by angioscopy, angiography, or both. The luminal surfaces were studied with scanning electron microscopy and transverse sections of vessels were studied with light microscopy. The pulverized atheroma, in colloidal suspension, was analyzed for particle size by Coulter counter. The effect of a colloidal suspension of atheromatous particles on distal capillary circulation was measured in animal experiments. Obstructive lesions were successfully removed in 36 of 37 stenotic arteries (97%) and 18 of 31 completely occluded arteries (58%), an overall efficacy of 54 of 68 (79%). In successfully atherectomized arteries, angioscopy and angiography demonstrated a widely patent, smooth, polished surface. Light microscopy demonstrated removal of the diseased intima with maintenance of the outer media and adventitia. The pulverized atheroma particles were generally smaller than red blood cells and injection of the colloidal atheroma into canine femoral arteries failed to produce local tissue injury. We conclude that in the human cadaver this atherectomy device effectively enlarges and recanalizes obstructed superficial femoral, popliteal, and tibial arteries

Experience of iodine removal in Tokai reprocessing plant

International Nuclear Information System (INIS)

Kikuchi, K.; Komori, Y.; Takeda, K.

1985-01-01

In the Tokai reprocessing plant about 170 ton of irradiated fuels have been processed since the beginning of hot operations in 1977. There was no effective equipment for iodine removal from the off-gas except for alkaline scrubbers when the plant construction was completed. In order to reduce the iodine discharge to the atmosphere, silver-exchanged zeolite (AgX) filters were installed additionally in 1979 and 1980, and they have been effective. However, those decontamination factors (DFs) were not as high as expected, and increasing the reprocessing amount of spent fuels it became necessary to lower the iodine discharge to the atmosphere. Therefore, other iodine removal equipment is planned to be installed in the plant. Concerning these investigations and development of iodine removal techniques, the iodine concentration of actual off-gases was measured and useful data were obtained

Membrane Characteristics for Removing Particulates in PFC Wastes

International Nuclear Information System (INIS)

Kim, Gye Nam; Lee, Sung Yeol; Won, Hui Jun; Jung, Chong Hun; Oh, Won Zin; Park, Jin Ho

2005-01-01

Pc (Per fluorocarbon) decontamination process is one of best methods to remove hot particulate adhered at inside surface of hot cell and surface of equipment in hot cell. It was necessary to develop a particulate filtration equipment to reuse Pc solution used on Pc decontamination due to its high cost and to minimize the volume of second wastewater. Contamination characteristics of hot particulate were investigated and then a filtration process was presented to remove hot particulate in Pc solution generated through Pc decontamination process. The removal efficiency of Pvdf (Poly vinylidene fluoride), Pp (Polypropylene), Ceramic (Al 2 O 3 ) filter showed more than 95%. The removal efficiency of Pvdf filter was a little lower than those of other kiters at same pressure (3 psi). A ceramic filter showed a higher removal efficiency with other filters, while a little lower flux rate than other filters. Due to inorganic composition, a ceramic filter was highly stable against radio nuclides in comparison with Pvdf and Pp membrane, which generate H 2 gas in α-radioactivity atmosphere. Therefore, the adoption of ceramic filter is estimated to be suitable for the real nitration process.

Supplement to nuclear EQ sourcebook: A compilation of documents for nuclear equipment qualification

International Nuclear Information System (INIS)

Anon.

1993-01-01

In the nuclear power industry, environmental and seismic qualification of safety-related electrical and instrumentation equipment is collectively known as Equipment Qualification (EQ). Related technology, as well as regulatory requirements, have evolved rapidly during the last 15 years. For environmental qualification, what began in 1971 with one trial-use guide (IEEE Std 323-1971), now stands as a full complement of Nuclear Regulatory Commission (NRC) rules, guides, and industry standards. As the original 1992 version of the Nuclear EQ Sourcebook was compiled to serve the user-community need for a complete and exhaustive single source of nuclear EQ documentation, this Supplement is published to provide the user community with nuclear EQ documentation revisions and updates that have been published since the publication of the original volume in May of 1992. The first volume of this publication included documents issued before December, 1991. That first volume was well received and also prompted positive response from industry on its usefulness and on recommendations to improve the completeness and enhance the ease of use. This Supplement, therefore, includes new documents, revisions, and updates issued and published since December 1991 and up to and including March 1993. It incorporates various enhancements in order to better serve the user community. One such enhancement included in this Supplement is the new Equipment Classification Index that is described in the User Guide section of this publication. 37 papers, including Bulletins, Federal rules, Generic Letters, Notices, Regulatory Guides, IEEE Standards, IEEE Recommended Practices, and IEEE Guides, have been processed separately for inclusion on the data base

A media maniac's guide to removable mass storage media

Science.gov (United States)

Kempster, Linda S.

1996-01-01

This paper addresses at a high level, the many individual technologies available today in the removable storage arena including removable magnetic tapes, magnetic floppies, optical disks and optical tape. Tape recorders represented below discuss logitudinal, serpantine, logitudinal serpantine,and helical scan technologies. The magnetic floppies discussed will be used for personal electronic in-box applications.Optical disks still fill the role for dense long-term storage. The media capacities quoted are for native data. In some cases, 2 KB ASC2 pages or 50 KB document images will be referenced.

Light Guide Collector Prototype: Laboratory Testing

Directory of Open Access Journals (Sweden)

Jitka - Mohelnikova

2017-12-01

Full Text Available The article reviews the potential of light guide system equipped by a concentrator device capturing daylight applicable for illumination of building interiors and presents results of experiments on performance of its prototype. The main goal is focused on the comparison of traditional solutions and newly developed prototype of the light guide system and presents examination of its light transmission efficiency based on the laboratory experiments.

46 CFR 154.1435 - Medical first aid guide.

Science.gov (United States)

2010-10-01

... 46 Shipping 5 2010-10-01 2010-10-01 false Medical first aid guide. 154.1435 Section 154.1435 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) CERTAIN BULK DANGEROUS CARGOES SAFETY... Equipment § 154.1435 Medical first aid guide. Each vessel must have a copy of the IMO Medical First Aid...

Arrangement for guiding transport cables

International Nuclear Information System (INIS)

1981-01-01

This patent relates especially to x-ray equipment such as that used for computerized tomography, and in particular to an arrangement for guiding and supporting a plurality of power transmission cables and cooling hoses in a flexible manner. (U.K.)

Guide to Treatment of Tattoo Complications and Tattoo Removal.

Science.gov (United States)

Serup, Jørgen; Bäumler, Wolfgang

2017-01-01

Clinicians in the fields of general medicine, dermatology, and plastic surgery are in their work now and then confronted with tattoo complications. Recognizing the rather few important diagnostic groups and urgencies, the medical 'decision tree' of treatment becomes quite simple. Acute conditions are dominated by bacterial infections needing antibiotic treatment. Systemic infection is a matter of urgency and requires intravenous treatment in a hospital without delay to prevent septic shock. Inflammatory reactions are a real challenge. Chronic allergic reactions in red tattoos are mostly nonresponsive to topical corticoid and best treated with dermatome shaving with complete removal of the hapten concentrated in the outer dermis. Laser treatment of allergic reactions can boost the allergy with worsening and a potential risk of anaphylaxis and is thus not recommended in tattoo allergy. Chronic papulonodular reactions in black tattoos with pigment agglomeration can respond to local corticoid or be treated with dermatome shaving or lasers depending on availability. It is important to recognize sarcoidosis, which is strongly associated with reactions in black tattoos. Tattoo complications also include many rare but specific entities, which require individual treatment depending on the case and the disease mechanism. Removal of tattoos in individuals regretting their tattoo is performed using Q-switched nanosecond lasers and the recently introduced picosecond lasers. In view of the various tattoo pigments with different absorption spectra and the limited number of laser wavelengths, it is difficult to predict treatment outcome, and it is recommended to pretreat small test spots. Black and red colors are removed best, while other colors are difficult. Removal of large tattoos, especially when multicolored, is hardly achievable and not recommended. Clients often have unrealistic expectations, and informed consent and dialogue between the client and the laser surgeon before

Apparel. Teacher's Instructional Guide.

Science.gov (United States)

Rambo, Patti

This instructional guide for a one-half credit technological laboratory course for grades 10-12 focuses on apparel from the perspectives of personal decision making related to apparel, the apparel industry, and career preparation. Introductory materials are a course description; overview of course design; facilities, equipment, and resources; and…

Fluoroscopy-Guided Removal of Pull-Type Gastrostomy Tubes

International Nuclear Information System (INIS)

Ahlers, Christopher M.; Schneider, Jens; Lachmann, Ricarda; Herber, Sascha; Dueber, Christoph; Pitton, Michael B.

2008-01-01

These case reports demonstrate a radiologic interventional technique for removal of pull-type gastrostomy tubes. This approach proved to be a safe and efficient procedure in two patients. The procedure may be applicable in situations where endoscopic attempts fail.

Laser-based coatings removal

International Nuclear Information System (INIS)

Freiwald, J.G.; Freiwald, D.A.

1995-01-01

Over the years as building and equipment surfaces became contaminated with low levels of uranium or plutonium dust, coats of paint were applied to stabilize the contaminants in place. Most of the earlier paint used was lead-based paint. More recently, various non-lead-based paints, such as two-part epoxy, are used. For D ampersand D (decontamination and decommissioning), it is desirable to remove the paints or other coatings rather than having to tear down and dispose of the entire building. This report describes the use of pulse-repetetion laser systems for the removal of paints and coatings

Laser-based coatings removal

Energy Technology Data Exchange (ETDEWEB)

Freiwald, J.G.; Freiwald, D.A. [F2 Associates, Inc., Albuquerque, NM (United States)

1995-10-01

Over the years as building and equipment surfaces became contaminated with low levels of uranium or plutonium dust, coats of paint were applied to stabilize the contaminants in place. Most of the earlier paint used was lead-based paint. More recently, various non-lead-based paints, such as two-part epoxy, are used. For D&D (decontamination and decommissioning), it is desirable to remove the paints or other coatings rather than having to tear down and dispose of the entire building. This report describes the use of pulse-repetetion laser systems for the removal of paints and coatings.

Standard Waste Box Lid Screw Removal Option Testing

International Nuclear Information System (INIS)

Anast, Kurt Roy

2016-01-01

This report provides results from test work conducted to resolve the removal of screws securing the standard waste box (SWB) lids that hold the remediated nitrate salt (RNS) drums. The test work evaluated equipment and process alternatives for removing the 42 screws that hold the SWB lid in place. The screws were secured with a red Loctite thread locker that makes removal very difficult because the rivets that the screw threads into would slip before the screw could be freed from the rivet, making it impossible to remove the screw and therefore the SWB lid.

Standard Waste Box Lid Screw Removal Option Testing

Energy Technology Data Exchange (ETDEWEB)

Anast, Kurt Roy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-03-11

This report provides results from test work conducted to resolve the removal of screws securing the standard waste box (SWB) lids that hold the remediated nitrate salt (RNS) drums. The test work evaluated equipment and process alternatives for removing the 42 screws that hold the SWB lid in place. The screws were secured with a red Loctite thread locker that makes removal very difficult because the rivets that the screw threads into would slip before the screw could be freed from the rivet, making it impossible to remove the screw and therefore the SWB lid.

Removal, transportation and disposal of the Millstone 2 neutron thermal shield

International Nuclear Information System (INIS)

Snedeker, D.F.; Thomas, L.S.; Schmoker, D.S.; Cade, M.S.

1985-01-01

Some PWR reactors equipped with neutron thermal shields (NTS) have experienced severe neutron shield degradation to the extent that removal and disposal of these shields has become necessary. Due to the relative size and activation levels of the thermal shield, disposal techniques, remote material handling and transportation equipment must be carefully evaluated to minimize plant down time and maintain disposal costs at a minimum. This paper describes the techniques, equipment and methodology employed in the removal, transportation and disposal of the NTS at the Millstone 2 Nuclear Generating Station, a PWR facility owned and operated by Northeast Utilities of Hartford, CT. Specific areas addressed include: (1) remote underwater equipment and tooling for use in segmenting and loading the thermal shield in a disposal liner; (2) adaptation of the General Electric IF-300 Irradiated Fuel Cask for transportation of the NTS for disposal; (3) equipment and techniques used for cask handling and liner burial at the Low Level Radioactive Waste (LLRW) disposal facility

Manual on self-contained gamma irradiators (categories 1 and 3). Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1996-01-01

The document is the first revision of a previous one published in 1993 to provide guidance on the safe use and regulation of panoramic gamma irradiators (Co-60 or Cs-137 sources) in different fields of application. It includes three parts: Applications Guide, which describes the main applications of panoramic gamma irradiators, the type of equipment, including safety systems, operation and maintenance, and how to deal with incidents. Procedures Guide, which gives step by step instructions on how to carry out the practice. Basics Guide, which explains the fundamentals of radiation, the system of units, interaction of radiation with matter radiation detection, etc. and which is common to all documents in the series. The manual is aimed primarily at persons handling such radiation sources on a daily routine basis, as well as at the competent authorities for training of workers in radiation protection or for setting up local radiation protection rules

Study and development of equipment supervision technique system and its management software for nuclear electricity production

International Nuclear Information System (INIS)

Zhang Liying; Zou Pingguo; Zhu Chenghu; Lu Haoliang; Wu Jie

2008-01-01

The equipment supervision technique system, which standardized the behavior of supervision organizations in planning and implementing of equipment supervision, is built up based on equipment supervision technique documents, such as Quality Supervision Classifications, Special Supervision Plans and Supervision Guides. Furthermore, based on the research, the equipment supervision management information system is developed by Object Oriented Programming, which consists of supervision information, supervision technique, supervision implementation, quality statistics and analysis module. (authors)

L-038: EPR-First Responders: Forces / safety equipment. Action Guides

International Nuclear Information System (INIS)

2011-01-01

This conference is about the actions carry out by the forces and the safety equipment in a radiological emergency. The security area, the victims, the hospitals, the police vehicles area, the safety cordon, the evacuation, the contamination level and the risk of life are important aspects to be considered by the first responders.

Seismic qualification method of equipment for nuclear power plant

International Nuclear Information System (INIS)

Kim, J.S.; Choi, T.H.; Sulaimana, R.A.

1995-01-01

Safety related equipment installed in Korean Nuclear Power Plants are required to perform a safety function during and after a seismic event. To accomplish this safety function, they must be seismically qualified in accordance with the intent and requirements of the USNRC Reg. Guide 1.100 Rev. 02 and IEEE Std. 344-1987. This paper defines and summarizes acceptable criteria and procedures, based on the Korean experience, for seismic qualification of purchased equipment to be installed in a nuclear power plant. As such the paper is intended to be a concise reference by equipment designers, architectural engineering company and plant owners in uniform implementation of commitments to nuclear regulatory agencies such as the USNRC or Korea Institute of Nuclear Safety (KINS) relating to adequacy of seismic Category 1 equipment. Thus, the paper provides the methodologies which can be used for qualifying equipment for safely related service in Nuclear Power Plants in a cost effective manner

Storage options for Long Length Contaminated Equipment (LLCE) items

International Nuclear Information System (INIS)

Hodgson, R.D.

1994-11-01

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

Remote maintenance lessons learned on prototypical reprocessing equipment

International Nuclear Information System (INIS)

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

1990-01-01

A major objective of the Consolidated Fuel Reprocessing Program at the Oak Ridge National Laboratory is to develop and demonstrate the technology required to reprocess spent nuclear fuel. The Fuel Recycle Division, over the past 16 years, has undertaken this objective by designing and testing prototypical hardware representing essentially every major equipment item currently included in most fuel reprocessing plant conceptual designs. These designs are based on total remote maintenance to increase plant availability and reduce radiation exposure to plant operators. The designs include modular equipment to facilitate maintainability and the remote manipulation necessary to accomplish maintenance tasks. Prototypic equipment has been installed and tested in a cold mock-up of a reprocessing hot cell, called the remote operations and maintenance demonstration facility. The applied maintenance concept utilizes the dexterity and mobility of bridge-mounted, force-reflecting servomanipulators. Prototypic processing equipment includes a remote disassembly system, a remote shear system, a rotary dissolver, a remote automated sampler system, removable equipment racks to support chemical process equipment items, and the advanced servomanipulators. Each of these systems and a brief description of functions are discussed

Uranium material removing and recovering device

International Nuclear Information System (INIS)

Takita, Shin-ichi.

1997-01-01

A uranium material removing and recovering device for use in removing surplus uranium heavy metal (UO 2 ) generated in a uranium handling facility comprises a uranium material removing device and a uranium material recovering device. The uranium material removing device comprises an adsorbing portion filled with a uranium adsorbent, a control portion for controlling the uranium adsorbent of the uranium adsorbing portion by a controlling agent, a uranium adsorbing device connected thereto and a jetting device for jetting the adsorbing liquid to equipments deposited with uranium. The recovering device comprises a recovering apparatus for recovering uranium materials deposited with the adsorbent liquid removed by the jetting device and a recovering tank for storing the recovered uranium materials. The device of the present invention can remove surplus uranium simply and safely, mitigate body's load upon removing and recovering operations, facilitate the processing for the exchange of the adsorbent and reduces the radioactive wastes. (T.M.)

AX Tank Farm tank removal study

Energy Technology Data Exchange (ETDEWEB)

SKELLY, W.A.

1999-02-24

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

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

International Nuclear Information System (INIS)

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

1997-09-01

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

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

Development of filtration equipment to reuse PFC decontamination wastewater

International Nuclear Information System (INIS)

Kim, Gye Nam; Lee, Sung Yeol; Won, Hui Jun; Jung Chong Hun; Oh, Won Zin; Park, Jin Ho

2005-01-01

When PFC(Perfluorocarbonate) decontamination technology is applied to removal of radioactive contaminated particulate adhered at surface during the operation of nuclear research facilities, it is necessary to develop a filtration equipment to reuse of PFC solution due to high price, also to minimize the volume of second wastewater. Contaminated characteristics of hot particulate was investigated and a filtration process was presented to remove suspended radioactive particulate from PFC decontamination wastewater generated on PFC decontamination

Guide to post-earthquake investigation of lifelines

International Nuclear Information System (INIS)

Schiff, A.J.

1991-01-01

This book contains proceedings of the Guide to Post-Earthquake Investigation of Life Lines. Topics covered include: the type of facilities and equipment that were damaged and a count of each type, information needed to advance the state-of-the-art of seismic design of facilities and equipment, failure modes and factors contributing to them, the impacts of failures on system operations and the resources and time required to restore facilities, information on the response of the overall system, facilities and equipment to past earthquakes should be known

Removal of a broken guide wire entrapped in a fractured femoral neck

Directory of Open Access Journals (Sweden)

ZHU Qing-hua

2013-08-01

Full Text Available 【Abstract】Guide wire plays an important role in the fixation of femoral neck fracture with dynamic hip screw (DHS. Breakage of a guide wire during operation is a very rare condition. We met such a dilemma in DHS fixation of a 54-year-old male patient who sustained Garden type IV frac-ture of the right femoral neck. The distal end of the guide wire broke and was entrapped in the fractured femoral neck. We tried to get the broken part out by a cannulated drill. Reaming was started with the cannulated drill slowly rotat-ing around the guide K-wire until the reamer fully contained the target under fluoroscope. A bone curette was used to get the broken wire out but failed, so we had to use the cannuated drill to dredge this bone tunnel. Finally the bro-ken wire end was taken out, mixed with blood and bone fragments. Through the existing drilling channel, DHS fixa-tion was easily finished. The patient had an uneventful re-covery without avascular necrosis of femoral head or non-union of the fracture at one year’s follow-up. A few methods can be adopted to deal with the broken guide wire. The way used in our case is less invasive but technically challenging. When the guide wire is properly positioned, this method is very practical and useful. Key words: Femoral neck fractures; Bones wires; Complications

Gaze strategies during visually-guided versus memory-guided grasping.

Science.gov (United States)

Prime, Steven L; Marotta, Jonathan J

2013-03-01

Vision plays a crucial role in guiding motor actions. But sometimes we cannot use vision and must rely on our memory to guide action-e.g. remembering where we placed our eyeglasses on the bedside table when reaching for them with the lights off. Recent studies show subjects look towards the index finger grasp position during visually-guided precision grasping. But, where do people look during memory-guided grasping? Here, we explored the gaze behaviour of subjects as they grasped a centrally placed symmetrical block under open- and closed-loop conditions. In Experiment 1, subjects performed grasps in either a visually-guided task or memory-guided task. The results show that during visually-guided grasping, gaze was first directed towards the index finger's grasp point on the block, suggesting gaze targets future grasp points during the planning of the grasp. Gaze during memory-guided grasping was aimed closer to the blocks' centre of mass from block presentation to the completion of the grasp. In Experiment 2, subjects performed an 'immediate grasping' task in which vision of the block was removed immediately at the onset of the reach. Similar to the visually-guided results from Experiment 1, gaze was primarily directed towards the index finger location. These results support the 2-stream theory of vision in that motor planning with visual feedback at the onset of the movement is driven primarily by real-time visuomotor computations of the dorsal stream, whereas grasping remembered objects without visual feedback is driven primarily by the perceptual memory representations mediated by the ventral stream.

7 CFR 58.128 - Equipment and utensils.

Science.gov (United States)

2010-01-01

... cleaning and inspection. Any opening at the top of the tank or vat including the entrance of the shaft... equally noncorrosive metal it shall be properly tinned over the entire surface. Sanitary seal assemblies at the shaft ends of coil vats shall be of the removable type, except that existing equipment not...

Image guided prostate cancer treatments

Energy Technology Data Exchange (ETDEWEB)

Bard, Robert L. [Bard Cancer Center, Biofoundation for Angiogenesis Research and Development, New York, NY (United States); Fuetterer, Jurgen J. [Radboud Univ. Nijmegen, Medical Centre (Netherlands). Dept. of Radiology; Sperling, Dan (ed.) [Sperling Prostate Center, Alpha 3TMRI, New York, NY (United States)

2014-07-01

Systematic overview of the application of ultrasound and MRI in the diagnosis and treatment of diseases of the lower urinary tract. Detailed information on image-guided therapies, including focused ultrasound, photodynamic therapy, and microwave and laser ablation. Numerous high-quality illustrations based on high-end equipment. Represents the state of the art in Non Invasive Imaging and Minimally Invasive Ablation Treatment (MIAT). Image-Guided Prostate Cancer Treatments is a comprehensive reference and practical guide on the technology and application of ultrasound and MRI in the male pelvis, with special attention to the prostate. The book is organized into three main sections, the first of which is devoted to general aspects of imaging and image-guided treatments. The second section provides a systematic overview of the application of ultrasound and MRI to the diagnosis and treatment of diseases of the lower urinary tract. Performance of the ultrasound and MRI studies is explained, and the normal and abnormal pathological anatomy is reviewed. Correlation with the ultrasound in the same plane is provided to assist in understanding the MRI sequences. Biopsy and interventional procedures, ultrasound-MRI fusion techniques, and image-guided therapies, including focused ultrasound, photodynamic therapy, microwave and laser ablation, are all fully covered. The third section focuses on securing treatment effectiveness and the use of follow-up imaging to ensure therapeutic success and detect tumor recurrence at an early stage, which is vital given that prompt focal treatment of recurrence is very successful. Here, particular attention is paid to the role of Doppler ultrasound and DCE-MRI technologies. This book, containing a wealth of high-quality illustrations based on high-end equipment, will acquaint beginners with the basics of prostate ultrasound and MRI, while more advanced practitioners will learn new skills, means of avoiding pitfalls, and ways of effectively

Method and apparatus for removably mounting a top nozzle on a nuclear reactor fuel assembly

International Nuclear Information System (INIS)

Wilson, J.F.; Gjertsen, R.K.; Schallenberger, J.M.

1986-01-01

In a fuel assembly having a top nozzle and control rod guide thimbles, a method is described of removably mounting the top nozzle on the ends of the guide thimbles, comprising the steps of: (a) releasably mating hollow outer sockets defined in the top nozzle with hollow inner sockets defined on the ends of the guide thimbles. The inner sockets are movable between compressed conditions for removing and inserting the inner sockets from and into the outer sockets in mounting and removing the top nozzle on and from the guide thimbles and expanded conditions for mating the inner and outer sockets together and the top nozzle on the guide thimbles; (b) supporting elongated locking tubes such that end portions thereof extend into the outer sockets defined in the top nozzle; and (c) moving all of the locking tubes at the same time between unlocking and locking positions to displace their end portions axially within the outer sockets between first and second locations

Advances in technologies for decay heat removal

International Nuclear Information System (INIS)

Yadigaroglu, G.; Berkovich, V.; Bianchi, A.; Chen B.; Meseth, J.; Vecchiarelli, J.; Vidard, M.

1999-01-01

The various decay heat removal concepts that have been used for the evolutionary water reactor plant designs developed worldwide are examined and common features identified. Although interesting new features of the 'classical' plants are mentioned, the emphasis is on passive core and containment decay heat removal systems. The various systems are classified according to the function they have to accomplish; they often share common characteristics and similar equipment. (author)

After-heat removing system in FBR type reactor

International Nuclear Information System (INIS)

Ohashi, Yukio.

1990-01-01

The after-heat removing system of the present invention removes the after heat generated in a reactor core without using dynamic equipments such as pumps or blowers. There are disposed a first heat exchanger for heating a heat medium by the heat in a reactor container and a second heat exchanger situated above the first heat exchanger for spontaneously air-cooling the heat medium. Recycling pipeways connect the first and the second heat exchangers to form a recycling path for the heat medium. Then, since the second heat exchanger for spontaneously air-cooling the heat medium is disposed above the first heat exchanger and they are connected by the recycling pipeways, the heat medium can be circulated spontaneously. Accordingly, dynamic equipments such as pumps or blowers are no more necessary. As a result, the after-heat removing system of the FBR type reactor of excellent safety and reliability can be obtained. (I.S.)

Hot Spot Removal System: System description

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

Hazardous wastes contaminated with radionuclides, chemicals, and explosives exist across the Department of Energy complex and need to be remediated due to environmental concerns. Currently, an opportunity is being developed to dramatically reduce remediation costs and to assist in the acceleration of schedules associated with these wastes by deploying a Hot Spot Removal System. Removing the hot spot from the waste site will remove risk driver(s) and enable another, more cost effective process/option/remedial alternative (i.e., capping) to be applied to the remainder of the site. The Hot Spot Removal System consists of a suite of technologies that will be utilized to locate and remove source terms. Components of the system can also be used in a variety of other cleanup activities. This Hot Spot Removal System Description document presents technologies that were considered for possible inclusion in the Hot Spot Removal System, technologies made available to the Hot Spot Removal System, industrial interest in the Hot Spot Removal System`s subsystems, the schedule required for the Hot Spot Removal System, the evaluation of the relevant technologies, and the recommendations for equipment and technologies as stated in the Plan section.

Hot Spot Removal System: System description

International Nuclear Information System (INIS)

1997-09-01

Hazardous wastes contaminated with radionuclides, chemicals, and explosives exist across the Department of Energy complex and need to be remediated due to environmental concerns. Currently, an opportunity is being developed to dramatically reduce remediation costs and to assist in the acceleration of schedules associated with these wastes by deploying a Hot Spot Removal System. Removing the hot spot from the waste site will remove risk driver(s) and enable another, more cost effective process/option/remedial alternative (i.e., capping) to be applied to the remainder of the site. The Hot Spot Removal System consists of a suite of technologies that will be utilized to locate and remove source terms. Components of the system can also be used in a variety of other cleanup activities. This Hot Spot Removal System Description document presents technologies that were considered for possible inclusion in the Hot Spot Removal System, technologies made available to the Hot Spot Removal System, industrial interest in the Hot Spot Removal System''s subsystems, the schedule required for the Hot Spot Removal System, the evaluation of the relevant technologies, and the recommendations for equipment and technologies as stated in the Plan section

Maintainability design criteria for packaging of spacecraft replaceable electronic equipment.

Science.gov (United States)

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

1972-01-01

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

Safety Review related to Commercial Grade Digital Equipment in Safety System

International Nuclear Information System (INIS)

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

2013-01-01

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

40 CFR 267.116 - What must I do with contaminated equipment, structure, and soils?

Science.gov (United States)

2010-07-01

... equipment, structure, and soils? 267.116 Section 267.116 Protection of Environment ENVIRONMENTAL PROTECTION..., structure, and soils? You must properly dispose of or decontaminate all contaminated equipment, structures, and soils during the partial and final closure periods. By removing any hazardous wastes or hazardous...

Reusable locking tube insertion and removal fixture and method in a reconstitutable fuel assembly

International Nuclear Information System (INIS)

Shallenberger, J.M.; Ferlan, S.J.

1987-01-01

This patent describes a locking tube insertion and removal fixture for use with a reconstitutable fuel assembly. The process includes a top nozzle with an adapter plate having at least one passageway, at least one guide thimble with an upper end portion, and an attaching structure having a hollow locking tube insertable and removable into and from a locking position in the upper end portion of the guide thimble for releasably locking the upper end portion of the guide thimble within the passageway of the top nozzle and adapter plate

Criticality safety basics, a study guide

Energy Technology Data Exchange (ETDEWEB)

V. L. Putman

1999-09-01

This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates.

Criticality safety basics, a study guide

International Nuclear Information System (INIS)

Putman, V.L.

1999-01-01

This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates

Using combined system of shaft guides for buckets during shaft deepening

Energy Technology Data Exchange (ETDEWEB)

Durov, E.M.; Ivenskii, N.S.; Alekhin, P.I.

1981-06-01

This paper discusses a system of shaft guides used in the Krasnopol'evsk underground coal mine. The existing skip shaft 514 m deep is deepened to a depth of 700 m. Shaft design is adapted to a system of two pairs of skips, however, only one pair of skips is in operation and the other has been removed. The free space can be used to remove rock material from shaft bottom. It is noted that a system of buckets moving along elastic shaft guides made of rope or along rigid shaft guides can be used. Both solutions have numerous advantages. If rope guides are used time consuming installation of shaft guides is unnecessary in the zone close to the bottom. If rigid guides are used capacity of the bucket can be significantly increased. A system which combines advantages of both solutions is used: in the lower part of the shaft being deepened, buckets are guided by rope, and in the upper zone in which rigid shaft guides have been installed the bucket moves along rigid guides and rope guides simultaneously. Design of the element guiding the bucket is shown in two diagrams. It is noted that using the combined system of shaft guides increases capacity of the hoisting system by 1.5 times.

[Fundamental aspects for accrediting medical equipment calibration laboratories in Colombia].

Science.gov (United States)

Llamosa-Rincón, Luis E; López-Isaza, Giovanni A; Villarreal-Castro, Milton F

2010-02-01

Analysing the fundamental methodological aspects which should be considered when drawing up calibration procedure for electro-medical equipment, thereby permitting international standard-based accreditation of electro-medical metrology laboratories in Colombia. NTC-ISO-IEC 17025:2005 and GTC-51-based procedures for calibrating electro-medical equipment were implemented and then used as patterns. The mathematical model for determining the estimated uncertainty value when calibrating electro-medical equipment for accreditation by the Electrical Variable Metrology Laboratory's Electro-medical Equipment Calibration Area accredited in compliance with Superintendence of Industry and Commerce Resolution 25771 May 26th 2009 consists of two equations depending on the case; they are: E = (Ai + sigmaAi) - (Ar + sigmaAr + deltaAr1) and E = (Ai + sigmaAi) - (Ar + sigmaA + deltaAr1). The mathematical modelling implemented for measuring uncertainty in the Universidad Tecnológica de Pereira's Electrical Variable Metrology Laboratory (Electro-medical Equipment Calibration Area) will become a good guide for calibration initiated in other laboratories in Colombia and Latin-America.

A guide to radiation protection in the use of X-ray optics equipment

International Nuclear Information System (INIS)

Bines, W.P.

1986-01-01

A booklet has been produced by a Working Group convened by the Health and Safety Executive to provide practical guidance for all who might be involved in work with X-ray optics equipment, such as designers, manufacturers, users, maintenance workers, inspectors, radiation protection advisers and supervisors. The particular radiation protection aspects described include those in connection with enclosure design and inspection, inter locks, tube shields, shutters and cover plates, administrative controls, monitoring and repair and maintenance of equipment. (UK)

Study on the shipboard radar reconnaissance equipment azimuth benchmark method

Science.gov (United States)

Liu, Zhenxing; Jiang, Ning; Ma, Qian; Liu, Songtao; Wang, Longtao

2015-10-01

The future naval battle will take place in a complex electromagnetic environment. Therefore, seizing the electromagnetic superiority has become the major actions of the navy. Radar reconnaissance equipment is an important part of the system to obtain and master battlefield electromagnetic radiation source information. Azimuth measurement function is one of the main function radar reconnaissance equipments. Whether the accuracy of direction finding meets the requirements, determines the vessels successful or not active jamming, passive jamming, guided missile attack and other combat missions, having a direct bearing on the vessels combat capabilities . How to test the performance of radar reconnaissance equipment, while affecting the task as little as possible is a problem. This paper, based on radar signal simulator and GPS positioning equipment, researches and experiments on one new method, which povides the azimuth benchmark required by the direction-finding precision test anytime anywhere, for the ships at jetty to test radar reconnaissance equipment performance in direction-finding. It provides a powerful means for the naval radar reconnaissance equipments daily maintenance and repair work[1].

75 FR 54025 - Vessel and Facility Response Plans for Oil: 2003 Removal Equipment Requirements and Alternative...

Science.gov (United States)

2010-09-03

... responders for each vessel or facility with appropriate equipment and resources located in each zone of operation; specific lists of equipment that the resource providers will make available in case of an...

Radiation safety of sealed sources and equipment containing them

International Nuclear Information System (INIS)

1993-01-01

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

Reconstitutable nuclear reactor fuel assembly with unitary removable top nozzle subassembly

International Nuclear Information System (INIS)

Shallenberger, J.M.

1987-01-01

A reconstitutable fuel assembly is described having at least one control rod guide thimble and a top nozzle, the guide thimble including an upper extension, the top nozzle including at least one hold-down spring, an upper hold-down plate and a lower adapter plate, an improved attaching structure removably mounting the top nozzle as a unitary subassembly on the guide thimble. The attaching structure comprises: (a) a coupling member interfitting the lower adapter plate, the upper hold-down plate and the hold-down spring disposed between the plates so as to capture and retain the plates and spring together as a unitary subassembly in which the upper plate is slidably moveable along the coupling member relative to the lower plate with the spring biasing the upper plate away from the lower plate. The coupling member has spaced apart upper and lower portions with a central passageway extending for slidably receiving the upper extension of the guide thimble in a nonattached relationship in which the coupling member is slidably movable relative to the guide thimble extension for respectively inserting and removing the coupling member on and from the guide thimble extension

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

International Nuclear Information System (INIS)

1989-03-01

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

Piecewise Polynomial Fitting with Trend Item Removal and Its Application in a Cab Vibration Test

Directory of Open Access Journals (Sweden)

Wu Ren

2018-01-01

Full Text Available The trend item of a long-term vibration signal is difficult to remove. This paper proposes a piecewise integration method to remove trend items. Examples of direct integration without trend item removal, global integration after piecewise polynomial fitting with trend item removal, and direct integration after piecewise polynomial fitting with trend item removal were simulated. The results showed that direct integration of the fitted piecewise polynomial provided greater acceleration and displacement precision than the other two integration methods. A vibration test was then performed on a special equipment cab. The results indicated that direct integration by piecewise polynomial fitting with trend item removal was highly consistent with the measured signal data. However, the direct integration method without trend item removal resulted in signal distortion. The proposed method can help with frequency domain analysis of vibration signals and modal parameter identification for such equipment.

Status of the nondestructive examination equipment for the fuels and materials examination facility

International Nuclear Information System (INIS)

Frandsen, G.B.

1980-01-01

The present status of Nondestructive Examination (NDE) Equipment proposed for the Fuels and Materials Examination Facility (FMEF) now under construction at the Hanford Engineering Development Laboratory is discussed. Items discussed include the NDE cell receiving machine, the dismantling machine, the standard examination stage, profilometry, eddy current, wire wrap removal machine, surface examination, gamma scan and general NDE equipment

Quality assurance in the removal and transport of the TMI-2 [Three Mile Island Unit 2] core

International Nuclear Information System (INIS)

Hayes, G.R.; Marsden, J.F.

1988-01-01

The March 1979 accident at Three Mile Island Unit 2 (TMI-2) damaged the core of the reactor. One of the major cleanup activities involves removal of the damaged core from the reactor and transporting it from the TMI-2 site near Middletown, Pennsylvania, to the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho. Removal and transport of the damaged core necessitated the development of much specialized equipment. This paper focuses on the role quality assurance (QA) played in the design, fabrication, acceptance, and use of three important pieces of core debris removal and transportation equipment: (1) the core boring machine, (2) the fuel debris canisters, (3) the NuPac 125-B rail cask and handling equipment

Methods of removing uranium from drinking water. 1. A literature survey. 2. Present municipal water treatment and potential removal methods

International Nuclear Information System (INIS)

Drury, J.S.; Michelson, D.; Ensminger, J.T.; Lee, S.Y.; White, S.K.

1982-12-01

Literature was searched for methods of removing uranium from drinking water. U.S. manufacturers and users of water-treatment equipment and products were also contacted regarding methods of removing uranium from potable water. Based on the results of these surveys, it was recommended that untreated, partially treated, and finished water samples from municipal water-treatment facilities be analyzed to determine the extent of removal of uranium by presently used procedures, and that additional laboratory studies be performed to determine what changes are needed to maximize the effectiveness of treatments that are already in use in existing water-treatment plants

Breast lesions with imaging-histologic discordance during US-guided 14G automated core biopsy: can the directional vacuum-assisted removal replace the surgical excision? Initial findings

International Nuclear Information System (INIS)

Kim, Min Jung; Kim, Eun-Kyung; Lee, Ji Young; Youk, Ji Hyun; Oh, Ki Keun; Park, Byeong-Woo; Kim, Seung-Il; Kim, Haeryoung

2007-01-01

The purpose of this study was to determine the frequency of carcinoma at percutaneous directional vacuum-assisted removal (DVAR) in women with imaging-histologic discordance during ultrasound (US)-guided automated core needle biopsy, and to determine the role of DVAR in breast lesions with imaging-histologic discordance. A US-guided 14-gauge automated core needle biopsy was performed on 837 consecutive lesions. Imaging-histologic discordance was prospectively considered in 33 of 634 benign biopsies. DVAR was recommended in those lesions. Among the 33 lesions, 26 lesions that underwent subsequent DVAR or surgical excision made up our study population. Medical records, imaging studies, and histologic findings were reviewed. Among the 26 lesions, 18 lesions underwent subsequent US-guided DVAR, with 8-gauge probes for 15 of the lesions, and 11-gauge for three of the lesions. Two lesions were diagnosed as having carcinoma (2/18, 11.1% of upgrade rate; 3.1-32.8% CI). The remaining eight lesions underwent subsequent surgical excision, and carcinoma was diagnosed in one case (12.5% of upgrade rate; 2.2-47.1% CI). A US-guided DVAR of the breast mass with imaging-histologic discordance during US-guided 14-gauge automated core needle biopsy is a valuable alternative to surgery as a means of obtaining a definitive histological diagnosis. (orig.)

A Computerized Procedure linked to Virtual Equipment

International Nuclear Information System (INIS)

Jung, Yeon Sub; Song, Tae Young

2011-01-01

Digital, information, and communication technologies have change human's behavior. This is because human has limitation to memorize and process information. Human has to access other information and real time information for important decisions. Those technologies are playing important roles. Nuclear power plants cannot be exception. Many accidents in nuclear power plants result from absent or incorrect information. The information for nuclear personnel is context sensitive. They don't have enough time to verify the context sensitive information. Therefore they skip the information, as resulting in incident. Nuclear personnel are usually carrying static paper procedures during local task performance. The procedure guides them steps to follow. There is, however, no dynamic and context sensitive information in the paper. The effect of the work is evaluated once while getting permission of the work. Afterward they are not informed. The static paper is generally simplified, so that it does not show detail of equipment being manipulated. Particularly novice workers feel difficult to understand the procedure due to lack of detail. Pictures of equipment inserted in the procedure are not enough for comprehension. A computerized procedure linked with virtual equipment is one of the best solutions to increase the detail of procedure. Virtual equipment, however, has still limitation not to provide real time information, because the virtual equipment is not synchronized with real plants

Plasma atomic layer etching using conventional plasma equipment

International Nuclear Information System (INIS)

Agarwal, Ankur; Kushner, Mark J.

2009-01-01

The decrease in feature sizes in microelectronics fabrication will soon require plasma etching processes having atomic layer resolution. The basis of plasma atomic layer etching (PALE) is forming a layer of passivation that allows the underlying substrate material to be etched with lower activation energy than in the absence of the passivation. The subsequent removal of the passivation with carefully tailored activation energy then removes a single layer of the underlying material. If these goals are met, the process is self-limiting. A challenge of PALE is the high cost of specialized equipment and slow processing speed. In this work, results from a computational investigation of PALE will be discussed with the goal of demonstrating the potential of using conventional plasma etching equipment having acceptable processing speeds. Results will be discussed using inductively coupled and magnetically enhanced capacitively coupled plasmas in which nonsinusoidal waveforms are used to regulate ion energies to optimize the passivation and etch steps. This strategy may also enable the use of a single gas mixture, as opposed to changing gas mixtures between steps

Writer`s guide for technical procedures

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

A primary objective of operations conducted in the US Department of Energy (DOE) complex is safety. Procedures are a critical element of maintaining a safety envelope to ensure safe facility operation. This DOE Writer`s Guide for Technical Procedures addresses the content, format, and style of technical procedures that prescribe production, operation of equipment and facilities, and maintenance activities. The DOE Writer`s Guide for Management Control Procedures and DOE Writer`s Guide for Emergency and Alarm Response Procedures are being developed to assist writers in developing nontechnical procedures. DOE is providing this guide to assist writers across the DOE complex in producing accurate, complete, and usable procedures that promote safe and efficient operations that comply with DOE orders, including DOE Order 5480.19, Conduct of Operations for DOE Facilities, and 5480.6, Safety of Department of Energy-Owned Nuclear Reactors.

Design of segmental ultrasonic cleaning equipment for removing the sludge in a steam generator

International Nuclear Information System (INIS)

Kim, Seok Tae; Jeong, Woo Tae; Byeon, Min Suk; Lee, Ho One

2010-01-01

In nuclear power plants, the water in the coolant system is managed to be clean but metallic sludge is accumulated on the top of tube-sheet in a steam generator. The sludge causes the corrosion of the tubesheet. The electric utility company in Korea removes the sludge with a lancing system for every outage of nuclear power plants. But the sludge is not perfectly removed with lancing system because the pressurized water of the lancing system cannot reach all area in a steam generator. Therefore the steam generator cleaning system with ultrasonic energy has been developed in KEPCO Research Institute. In this paper, the ultrasonic cleaning system is designed for removing the sludge on the steam generator

Breath-hold after forced expiration before removal of the biopsy needle decreased the rate of pneumothorax in CT-guided transthoracic lung biopsy

Energy Technology Data Exchange (ETDEWEB)

Min, Lingfeng; Xu, Xingxiang [Subei People' s Hospital of Jiangsu Province, Clinical Medical School of Yangzhou University, Yangzhou 225001, Jiangsu (China); Song, Yong [Jinling Hospital, Nanjing University School of Medical, Nanjing 210002, Jiangsu (China); Issahar, Ben-Dov [Pulmonary Institute, Sheba Medical Center, Sackler Faculty of Medicine, Tel Aviv University, Tel Aviv (Israel); Wu, Jingtao; Zhang, Le; Huang, Qian [Subei People' s Hospital of Jiangsu Province, Clinical Medical School of Yangzhou University, Yangzhou 225001, Jiangsu (China); Chen, Mingxiang, E-mail: chenmx1129@126.com [Subei People' s Hospital of Jiangsu Province, Clinical Medical School of Yangzhou University, Yangzhou 225001, Jiangsu (China)

2013-01-15

Purpose: To assess the effect of a breath-hold after forced expiration on the rate of pneumothorax after computed tomography (CT)-guided transthoracic needle biopsy of pulmonary lesions. Materials and methods: Between January 2008 and December 2011, percutaneous CT-guided lung biopsy was performed in 440 patients. Two hundred and twenty-one biopsies were performed without (control group) and two hundred and nineteen biopsies were performed with (study group) the study maneuver – a breath-hold after forced expiratory approach. Multivariate analysis was performed between groups for risk factors for pneumothorax, including patient demographics, lesion characteristics, and biopsy technique. Results: A reduced number of pneumothoraces (18 [8.2%] vs 35 [15.8%]; P = 0.014) but no significant difference in rate of drainage catheter insertions (2 [0.9%] vs (4 [1.8%]; P = 0.418) were noted in the study group as compared with the control group. By logistic regression analysis, three factors significantly and independently affected the risk for pneumothorax including lesion size (transverse and longitudinal diameter), distance from pleura and utilizing or avoiding the breath-hold after deep expiration maneuver. Conclusion: Breath-holding after forced expiration before removal of the biopsy needle during the percutaneous CT-guided transthoracic lung biopsy almost halved the rate of overall pneumothorax. Small lesion size (longitudinal diameter) and the distance from pleura were also predictors of pneumothorax in our study.

Breath-hold after forced expiration before removal of the biopsy needle decreased the rate of pneumothorax in CT-guided transthoracic lung biopsy

International Nuclear Information System (INIS)

Min, Lingfeng; Xu, Xingxiang; Song, Yong; Issahar, Ben-Dov; Wu, Jingtao; Zhang, Le; Huang, Qian; Chen, Mingxiang

2013-01-01

Purpose: To assess the effect of a breath-hold after forced expiration on the rate of pneumothorax after computed tomography (CT)-guided transthoracic needle biopsy of pulmonary lesions. Materials and methods: Between January 2008 and December 2011, percutaneous CT-guided lung biopsy was performed in 440 patients. Two hundred and twenty-one biopsies were performed without (control group) and two hundred and nineteen biopsies were performed with (study group) the study maneuver – a breath-hold after forced expiratory approach. Multivariate analysis was performed between groups for risk factors for pneumothorax, including patient demographics, lesion characteristics, and biopsy technique. Results: A reduced number of pneumothoraces (18 [8.2%] vs 35 [15.8%]; P = 0.014) but no significant difference in rate of drainage catheter insertions (2 [0.9%] vs (4 [1.8%]; P = 0.418) were noted in the study group as compared with the control group. By logistic regression analysis, three factors significantly and independently affected the risk for pneumothorax including lesion size (transverse and longitudinal diameter), distance from pleura and utilizing or avoiding the breath-hold after deep expiration maneuver. Conclusion: Breath-holding after forced expiration before removal of the biopsy needle during the percutaneous CT-guided transthoracic lung biopsy almost halved the rate of overall pneumothorax. Small lesion size (longitudinal diameter) and the distance from pleura were also predictors of pneumothorax in our study

Information booklet on personal protective equipment: arm and hand protection

International Nuclear Information System (INIS)

1992-01-01

Fire, heat, cold, electro-magnetic and ionising radiation, electricity, chemicals, impacts, cuts, abrasion, etc. are the common hazards for arms and hands at work. The gloves chosen for protection of the arm and hand should cover those parts adequately and the material of the gloves should be capable of offering protection against the specific hazard involved. Criteria for choosing arm and hand protection equipment will be based on their shape and part of the arm and hand protected. Guide lines for choosing such personal protection equipment for nuclear facilities are given. (M.K.V.). 3 annexures, 1 appendix

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

Comparison between the indocyanine green fluorescence and blue dye methods for sentinel lymph node biopsy using novel fluorescence image-guided resection equipment in different types of hospitals.

Science.gov (United States)

He, Kunshan; Chi, Chongwei; Kou, Deqiang; Huang, Wenhe; Wu, Jundong; Wang, Yabing; He, Lifang; Ye, Jinzuo; Mao, Yamin; Zhang, Guo-Jun; Wang, Jiandong; Tian, Jie

2016-12-01

Sentinel lymph node biopsy (SLNB) has become a standard of care to detect axillary lymph metastasis in early-stage breast cancer patients with clinically negative axillary lymph nodes. Current SLNB detection modalities comprising a blue dye, a radioactive tracer, or a combination of both have advantages as well as disadvantages. Thus, near-infrared fluorescence imaging using indocyanine green (ICG) has recently been regarded as a novel method that has generated interest for SLNB around the world. However, the lack of appropriate fluorescence imaging systems has hindered further research and wide application of this method. Therefore, we developed novel fluorescence image-guided resection equipment (FIRE) to detect sentinel lymph nodes (SLNs). Moreover, to compare the ICG fluorescence imaging method with the blue dye method and to explore the universal feasibility of the former, a different type of hospital study was conducted. Ninety-nine eligible patients participated in the study at 3 different types of hospitals. After subcutaneous ICG allergy testing, all the patients were subcutaneously injected with methylene blue and ICG into the subareolar area. Consequently, 276 SLNs (range 1-7) were identified in 98 subjects (detection rate: 99%) by using the ICG fluorescence imaging method. In contrast, the blue dye method only identified 202 SLNs (range 1-7) in 91 subjects (detection rate: 91.92%). Besides, the results of the fluorescence imaging method were similar in the 3 hospitals. Our findings indicate the universal feasibility of the ICG fluorescence imaging method for SLNB using the fluorescence image-guided resection equipment in early breast cancer detection. Copyright © 2016 Elsevier Inc. All rights reserved.

Standard guide for radioactive pathway methodology for release of sites following decommissioning

International Nuclear Information System (INIS)

Anon.

1989-01-01

The purpose of this guide is to provide guidance in determining site-specific conversion factors for translating between dose limits and residual radioactive contamination levels on equipment structures, and land areas. This guide is to serve as a guide to acceptable methodology for translating the yet to be determined dose limits into allowable levels of residual radioactive materials that can be left at a site following decommissioning

Improving the efficiency of thermal power equipment based on technologies using surfactants

Science.gov (United States)

Nikolaeva, L. A.; Zueva, O. S.

2015-10-01

The formation of deposits on the functional surfaces of the equipment of heating systems and their corrosion are one of the major energetic problems. To improve the operational efficiency of thermal power equipment, surface-active agents (surfactants) are widely used, which are applied for the treatment of the working surfaces before use, during use, to prevent the parking corrosion, as well as while performing periodic chemical cleanings of power equipment. The tests have been performed, and the technology of application of Auge Neo Ac 56 acid product (MAHIM, Kazan) has been developed, designed to remove mineral deposits and scale from cooling and boiler systems without mechanical influence on them and without disassembly of technological equipment.

Equipment for extracting and conveying stratified minerals

Energy Technology Data Exchange (ETDEWEB)

Blumenthal, G.; Kunzer, H.; Plaga, K.

1991-08-14

This invention relates to equipment for extracting stratified minerals and conveying the said minerals along the working face, comprising a trough shaped conveyor run assembled from lengths, a troughed extraction run in lengths matching the lengths of conveyor troughing, which is linked to the top edge of the working face side of the conveyor troughing with freedom to swivel vertically, and a positively guided chain carrying extraction tools and scrapers along the conveyor and extraction runs.

Configuration Management Plan for Long Length Contaminated Equipment Receiver and Transport Trailers

International Nuclear Information System (INIS)

DALE, R.N.

2000-01-01

Long Length Contaminated Equipment Removal System Receiver Trailer and Transport Trailer require a configuration management plan for design, requirements and operations baseline documents. This report serves as the plan for the Trailers

Hot demonstration of proposed commercial nuclide removal technology

Energy Technology Data Exchange (ETDEWEB)

Lee, D.D.; Travis, J.R.; Gibson, M.R. [Oak Ridge National Lab., TN (United States)

1997-10-01

Cesium, strontium, and technetium radionuclides are a small fraction of the mainly sodium and potassium salts in storage tank supernatants at the Hanford, Oak Ridge, Savannah River, and Idaho sites that DOE must remediate. Radionuclide removal technologies supplied by the ESP-CP have been previously proposed and tested in small batch and column tests using simulated and a few actual supernatants. They must now be tested and the most appropriate ones selected using a flow system of a scale suitable to obtain engineering data that can be applied to the design of pilot-scale equipment. This task involves operation of an experimental unit designed and constructed to test radionuclide removal technologies during continuous operation on actual supernatants. The equipment diagram, consists of the tanks, pumps, tubing and fittings, filters, and intrumentation for testing radionuclide removal technologies in a continuous-flow system in an Oak Ridge National Laboratory (ORNL) hot cell. The task provides a test bed for investigating new technologies, such as 3M`s SLIG 644 WWL WEB and AEA Technology`s EIX electrochemical elution system, and complements ESP`s comprehensive supernatant task (TTPOR06C341) by using larger engineering-scale, continuous equipment to verify and expand that task`s batch studies. This task complements the Tanks Focus Area`s (TFA`s) Cesium Removal Demonstration (CsRD) at ORNL by providing sorbent selection information, evaluating and testing proposed sorbents, and providing operational experience and characteristics using the sorbent and supernatant to be used in the demonstration, followed by evaluating and comparing small-scale to demonstration-scale performance. The authors cooperate closely with other ESP-CP tasks and the TFA to ultimately transfer the technologies being developed to the end user.

Three-dimensional digitizer (neuronavigator): new equipment for computed tomography-guided stereotaxic surgery.

Science.gov (United States)

Watanabe, E; Watanabe, T; Manaka, S; Mayanagi, Y; Takakura, K

1987-06-01

A new device was invented as an adjunct for computed tomography (CT)-guided stereotaxic or open neurosurgery. It is composed of a multijoint three-dimensional digitizer (sensor arm) and a microcomputer, which indicates the place of the sensor arm tip on preoperative CT images. Computed tomography scan is performed preoperatively with three markers placed on the nasion and ears. At surgery, after fixing the patient's head and the sensor arm, sampling of the standard points was done to translate the position of the tip of the sensor arm onto the CT images displayed on a computer screen. In this way positional data from conventional preoperative CT scan can be directly transferred into the surgical field. This system has the unique feature of introducing CT-guided stereotaxis into conventional open neurosurgery.

Technical Requirements for Fabrication and Installation of Removable Shield for CNRF in HANARO

Energy Technology Data Exchange (ETDEWEB)

Ryu, Jeong Soo; Cho, Yeong Garp; Lee, Jung Hee; Shin, Jin Won

2008-04-15

This report details the technical requirements for the fabrication and installation of the removable shield for the Cold Neutron Research Facility (CNRF) in HANARO reactor hall. The removable shield is classified as non-nuclear safety (NNS), seismic category II, and quality class T. The main function of the removable shield is to do the biological shielding of neutrons and gamma from the CN port and the guides. The removable shield consists of block type walls and roofs that can be necessarily assembled, disassembled and moveable. These will be installed between the reactor pool wall and the CNS guide bunker in. This report describes technical requirements for the removable shield such as quality assurance, seismic analysis requirements, configuration, concrete compositions, fabrication and installation requirements, test and inspection, shipping, delivery, etc. Appendix is the technical specification of structural design and analysis. Attachments are composed of the technical specification for the fabrication of the removable shield, shielding design drawings and procurement quality requirements. These technical requirements will be provided to a contract for the manufacturing and installation.

Computer aided virtual manufacturing using Creo parametric easy to learn step by step guide

CERN Document Server

Kanife, Paul Obiora

2016-01-01

Providing a step-by-step guide for the implementation of virtual manufacturing using Creo Parametric software (formerly known as Pro-Engineer), this book creates an engaging and interactive learning experience for manufacturing engineering students. Featuring graphic illustrations of simulation processes and operations, and written in accessible English to promote user-friendliness, the book covers key topics in the field including: the engraving machining process, face milling, profile milling, surface milling, volume rough milling, expert machining, electric discharge machining (EDM), and area turning using the lathe machining process. Maximising reader insights into how to simulate material removal processes, and how to generate cutter location data and G-codes data, this valuable resource equips undergraduate, postgraduate, BTech and HND students in the fields of manufacturing engineering, computer aided design (CAD) and computer aided engineering (CAE) with transferable skills and knowledge. This book is...

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

Closed retrograde retrieval of the distal broken segment of femoral cannulated intramedullary nail using a ball-tipped guide wire.

Science.gov (United States)

Metikala, Sreenivasulu; Mohammed, Riazuddin

2011-07-01

Extracting broken segments of intramedullay nails from long bones can be an operative challenge, particularly from the distal end. We report a case series where a simple and reproducible technique of extracting broken femoral cannulated nails using a ball-tipped guide wire is described. This closed technique involves no additional equipment or instruments. Eight patients who underwent the described method were included in the study. The technique involves using a standard plain guide wire passed through the cannulated distal broken nail segment after extraction of the proximal nail fragment. The plain guide wire is then advanced distally into the knee joint carefully under fluoroscopy imaging. Over this wire, a 5-millimeter (mm) cannulated large drill bit is used to create a track up to the distal broken nail segment. Through the small knee wound, a ball-tipped guide wire is passed, smooth end first, till the ball engages the end of the nail. The guide wire is then extracted along with the broken nail through the proximal wound. The method was successfully used in all eight patients for removal of broken cannulated intramedullary nail from the femoral canal without any complications. All patients underwent exchange nailing with successful bone union in six months. None of the patients had any problems at the knee joint at the final follow-up. We report a technique for successful extraction of the distal fragment of broken femoral intramedullary nails without additional surgical approaches.

Removing arsenic from groundwater in Cambodia using high performance iron adsorbent.

Science.gov (United States)

Kang, Y; Takeda, R; Nada, A; Thavarith, L; Tang, S; Nuki, K; Sakurai, K

2014-09-01

In Cambodia, groundwater has been contaminated with arsenic, and purification of the water is an urgent issue. From 2010 to 2012, an international collaborative project between Japan and Cambodia for developing arsenic-removing technology from well water was conducted and supported by the foundation of New Energy and Industrial Technology Development Organization, Japan. Quality of well water was surveyed in Kandal, Prey Veng, and Kampong Cham Provinces, and a monitoring trial of the arsenic removal equipment using our patented amorphous iron (hydr)oxide adsorbent was performed. Of the 37 wells surveyed, arsenic concentration of 24 exceeded the Cambodian guideline value (50 μg L(-1)), and those of 27 exceeded the WHO guideline for drinking water (10 μg L(-1)). Levels of arsenic were extremely high in some wells (>1,000-6,000 μg L(-1)), suggesting that arsenic pollution of groundwater is serious in these areas. Based on the survey results, 16 arsenic removal equipments were installed in six schools, three temples, two health centers, four private houses, and one commune office. Over 10 months of monitoring, the average arsenic concentrations of the treated water were between 0 and 10 μg L(-1) at four locations, 10-50 μg L(-1) at eight locations, and >50 μg L(-1) at four locations. The arsenic removal rate ranged in 83.1-99.7%, with an average of 93.8%, indicating that the arsenic removal equipment greatly lower the risk of arsenic exposure to the residents. Results of the field trial showed that As concentration of the treated water could be reduced to condition. This is one of the succeeding As removal techniques that could reduce As concentration of water below the WHO guideline value for As in situ.

BWRVIP-123, Revision 1NP: BWR Vessel and Internals Project Removal and Analysis of Material Samples from Core Shroud and Top Guide at Susquehanna Unit 2

International Nuclear Information System (INIS)

Howell, D.; Haertel, T.; Lindberg, J.; Oliver, B.; Greenwood, L.

2005-01-01

Fast and thermal fluence were determined by a laboratory analysis of the samples. Fluence in the upper regions of the shroud (between the H1 and H2 welds) was substantially lower than that in the belt line region (near the H4 weld). Fluence in the top guide was significantly higher than fluence on the core shroud. As expected, helium concentrations were highest in regions where fluence was highest. Estimates of the initial boron concentration were similar to measurements made on materials removed from other reactors. A technical justification evaluated the acceptability of the sampling process with respect to structural consequences of material removal and to increased cracking susceptibility due to the as-left condition. It was determined that the sampling process was acceptable on both counts

Disinfection for small water supplies: a technical guide

CSIR Research Space (South Africa)

Solsona, F

1990-01-01

Full Text Available This guide will present some disinfection systems, which will be useful in supporting disinfection programmes. The description of the different systems will provide a guideline for the selection of equipment base on balancing the simplicity...

Failed manual removal of the placenta after vaginal delivery

DEFF Research Database (Denmark)

Bjurström, Johanna; Collins, Sally; Langhoff-Roos, Jens

2018-01-01

PURPOSE: A retained placenta after vaginal delivery where manual removal of placenta fails is a clinical challenge. We present six cases that illustrate the heterogeneity of the condition and discuss the etiology and terminology as well as the clinical management. METHODS: Members of the European...... and the UK provide examples of various treatment strategies such as ultrasound-guided vaginal removal, removal of the placenta through a hysterotomy and just leaving the placenta in situ. The placentas were all retained, but it was only possible to diagnose abnormal invasion in the one case, which had...

Implementation of ISO guide 25 in a medical dosimetry secondary standards calibration laboratory

International Nuclear Information System (INIS)

DeWerd, L.A.

1995-01-01

Currently, there is a great deal of discussion among industry and government agencies about ISO 9000 accreditation. U.S. manufacturers with ISO 9000 accreditation are regarded more favorably by European countries. The principles behind the ISO 9000 accreditation are based on the Total Quality Management (TQM) principles that are being implemented in many U.S. industries. This paper will deal only with the calibration issue. There is a difference in the areas covered by ISO 9000 and ISO Guide 25 documents. ISO 9000, in particular ISO 9001 - ISO 9003, cover the open-quotes calibrationclose quotes of inspection, measuring and test equipment. This equipment is basically used for open-quotes factory calibrationsclose quotes to determine that equipment is performing within manufacturer specifications. ISO Guide 25 is specifically for open-quotes calibration and testing laboratories,close quotes generally laboratories that have painstaking procedures to reduce uncertainties and establish high accuracy of the transfer of calibration. The experience of the University of Wisconsin Accredited Dosimetry Calibration Laboratory in conforming to ISO Guide 25 will be outlined. The entire laboratory staff must become familiar with the process and an individual with direct authority must become the one to maintain the quality of equipment and calibrations in the role of open-quotes quality-assurance manager.close quotes

Removal of oil films from stainless steel tubes

Energy Technology Data Exchange (ETDEWEB)

Yan, J.F.; Saez, A.E.; Grant, C.S. [North Carolina State Univ., Raleigh, NC (United States). Dept. of Chemical Engineering

1997-01-01

The contamination of metal surfaces with oil is a widespread problem in the chemical, metalworking, and automotive industries. The main source of oil fouling comes from the process fluids in various operations. For example, in a heat exchanger, the oil contaminates the equipment surface causing a lower heat-transfer efficiency. The fouled equipment leads to increased costs due to added heat-transfer area, maintenance, energy, and production losses caused by unit downtime. The removal of oil films from the inner surface of a stainless steel tube cell using aqueous cleaning solutions was studied. The two oils used in the cleaning experiments, Sunquench 1042 and heavy mineral oil, contained P{sup 32} labeled tributyl phosphate (TBP) as a radioactive tracer. The {beta}{sup {minus}} particles emitted from the radioactive TBP were detected by a CaF{sub 2} scintillator and used as a measure of the amount of oil remaining in the tube cell. Cleaning experiments performed at different flow rates, surface treatment, and surfactant concentrations indicated that initially the oil films were removed rapidly. At the end of the experiments, the oil removal rate reduced significantly, eventually becoming negligible. The stainless steel morphology affected oil removal significantly, and the rougher tube tended to retard the oil removal. The rate and extent of the decontamination were significantly increased in the presence of sodium dodecyl sulfate, a nonionic surfactant. Experimental data were compared to a hydrodynamic model based on the removal of a liquid contaminant from a solid surface by an immiscible fluid. The model deviated from the experimental data due to the presence of instabilities at the oil-water interface.

Endoscopically guided removal of cloacal calculi in three African spurred tortoises (Geochelone sulcata).

Science.gov (United States)

Mans, Christoph; Sladky, Kurt K

2012-04-01

3 female African spurred tortoises (Geochelone sulcata) of various body weights (0.22, 0.77, and 2.86 kg [0.48, 1.69, and 6.29 lb]) were examined because of reduced food intake and lack of fecal output. Owners reported intermittent tenesmus in 2 of the tortoises. Physical examinations revealed no clinically important abnormalities in the tortoises. Cloacal calculi were diagnosed on the basis of radiography and cloacoscopy in all 3 tortoises. One tortoise had another calculus in the urinary bladder. Tortoises were anesthetized, and cloacal calculi were removed by use of a cutting burr (plain-fissure cutting burr and a soft tissue protector mounted to a dental handpiece that had a low-speed motor and a straight nose cone) and warm water irrigation with endoscopic guidance. Complete removal of calculus fragments was achieved by use of forceps and irrigation. In 1 tortoise, removal of the cloacal calculus was staged (2 separate procedures). In another tortoise, a second cloacal calculus (which had been located in the urinary bladder during the first examination) was successfully removed 25 days after removal of the first calculus. All 3 tortoises recovered uneventfully, and serious complications secondary to removal of the cloacal calculi were not detected. Cloacoscopy combined with the use of a low-speed dental drill and warm water irrigation should be considered a simple, safe, and nontraumatic treatment option for removal of obstructive cloacal calculi in tortoises.

Nuclear reactor fuel assembly with a removable top nozzle

International Nuclear Information System (INIS)

Shallenberger, J.M.; Ferlan, S.J.

1986-01-01

This patent describes a fuel assembly having at least one control rod guide thimble and a top nozzle, the top nozzle including a transversely extending adapter plate. An improved attaching structure is described for removably mounting the top nozzle on the guide thimble comprising: (a) means defining an outer socket in the top nozzle, the outer socket defining means including a passageway extending through the adapter plate and having a first mating element defined in the adapter plate within the passageway; (b) means on an upper end of the guide thimble defining an inner socket, the inner socket defining means including an elongated sleeve having an upper end portion. The upper end portion of the sleeve has a second mating element formed thereon and at least one elongated axial slot defined therein for permitting radial movement of the sleeve upper end portion between a compressed releasing position for removing and inserting the inner socket from and into the outer socket and an expanded locking position for locking the inner and outer sockets together

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

International Nuclear Information System (INIS)

Cunningham, J.; Shank, J.

2004-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

J. Cunningham and J. Shank

2004-11-01

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

Ultrasound guided synovial biopsy of the wrist

NARCIS (Netherlands)

van Vugt, R. M.; van Dalen, A.; Bijlsma, J. W.

1997-01-01

Seven patients (4 female and 3 male, mean age 46) with arthritis of the wrist (n = 7) without known etiology were evaluated. High-definition ultrasound equipment was used for localization of synovial hypertrophy, suitable for ultrasound guided biopsy without risk. A 18-gauge diameter Tru-cut biopsy

Technical evaluation of seismic qualification of safety-related equipment

Energy Technology Data Exchange (ETDEWEB)

Cho, Yang Hui; Park, Heong Gee; Park, Yeong Seok [Univ. of Incheon, Incheon (Korea, Republic of)

1994-04-15

This study is purposed to evaluate the technical acceptability of the procedures and techniques of seismic qualifications which were performed for the YGN 3 and 4 safety-related equipment.This study is also targeted to suggest a systematized technical procedure guide for the effective performance and review of the seismic qualification, which reflects the most up-to-date licensing requirements and state-of the-art.

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

CERN Document Server

AIChE

2013-01-01

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

Modifying the Heysham 2 and Torness guide tubes

International Nuclear Information System (INIS)

Salter, I.D.

1988-01-01

In 1986 the National Nuclear Corporation carried out the unfuelled engineering run on Torness Reactor One. Subsequent inspection revealed wear on the reactor control rods, following severe spinning caused by gas cross flow swirls at the guide tube castellated ring. The adopted solution was to machine 32 radial holes through the guide tube wall and blank off the existing castellated slots, however, man access to the guide tubes is extremely difficult. This paper describes how Taylor Hitec produced, in only 12 weeks, three remote drilling machines, together with associated debris collection systems, cleaning equipment and remote video/CCTV inspection systems, and then carried out the modifications to the reactors. (author)

DOUBLE SHELL TANK EMERGENCY PUMPING GUIDE

International Nuclear Information System (INIS)

REBERGER, D.W.

2006-01-01

This document provides preplanning necessary to expeditiously remove any waste that may leak from the primary tank to the secondary tank for Hanford's 28 DSTs. The strategy is described, applicable emergency procedures are referenced, and transfer routes and pumping equipment for each tank are identified

Hanford Site Tank 241-SY-101, damaged equipment removal

International Nuclear Information System (INIS)

Titzler, P.A.; Legare, D.E.; Barrus, H.G.

1993-11-01

Hanford Site Tank 241-SY-101 has a history of generating hydrogen-nitrous oxide gases. The gases are generated and trapped in the non-convective waste layer near the bottom of the 23-m- (75-ft-) diameter underground tank. Approximately every three months the pressure in the tank is relieved as the trapped gases are released through or around the surface crust into the tank dome. This process moves large amounts of liquid waste and crust material around in the tank. The moving waste displaced air lances and thermocouple assemblies (2-in. schedule-40 pipe) installed in four tank risers and permanently bent them to a maximum angle of 40 degrees. The bends were so severe that assemblies could not be removed from the tank using the originally designed hardware. Just after the tank releases the trapped gas, a 20-to-30-day work ''window'' opens

Conduct of Operations at Nuclear Power Plants. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide identifies the main responsibilities and practices of nuclear power plant (NPP) operations departments in relation to their responsibility for the safe functioning of the plant. The guide presents the factors to be considered in structuring the operations department of an NPP; setting high standards of performance; making safety related decisions in an effective manner; conducting control room and field activities in a thorough and professional manner; and maintaining an NPP within established operational limits and conditions. Contents: 1. Introduction; 2. Management and organization of plant operations; 3. Shift complement and functions; 4. Shift routines and operating practices; 5. Control of equipment and plant status; 6. Operations equipment and operator aids; 7. Work control and authorization.

Removable top nozzle and tool for a nuclear reactor fuel assembly

International Nuclear Information System (INIS)

Wilson, J.F.; Cerni, S.; Gjertsen, R.K.

1986-01-01

A fuel assembly is described for a nuclear reactor including a bottom nozzle, at least one longitudinally extending control rod guide thimble having an upper end and a lower end being attached to the bottom nozzle and projecting upwardly therefrom, transverse grids axially spaced along-the thimble for supporting an array of upstanding fuel rods, and a top nozzle subassembly removable mounted on the upper end of the guide thimble for obtaining top access to the fuel rods upon removal thereof. The top nozzle subassembly consists of: (a) a section integrally formed on the upper end of the guide thimble and having external threads thereon; (b) a lower adapter plate having a guide thimble hole for receiving the guide thimble so as to mount the adapter plate on the guide thimble for slidable movement therealong; (c) a retainer mounted on the guide thimble for restably supporting and limiting the downward movement of the adapter plate along the guide thimble; (d) an upper hold-down plate having a guide thimble passageway with an internal ledge for receiving the thimble so as to mount the hold-down plate on the thimble for slidable movement therealong; (e) spring means interposed between the upper hold-down plate and the lower adapter plate for biasing the hold-down plate upwardly when a downward force is applied thereon whereby the downward force is yieldably transmitted to the fuel assembly; and (f) a collar disposed within the passageway and in abutment with the ledge, the collar having an internal threaded section engageable with the externally threaded section to move the hold-down plate down against the spring means and thereby mounting of the subassembly on the guide thimble

Buyers guide of industrial furnaces and heating equipment. Bau und Ausruestung von Industrieoefen und industriellen Waermeanlagen: Bezugsquellenverzeichnis

Energy Technology Data Exchange (ETDEWEB)

Stepanek, J [comp.

1988-01-01

The book is a glossary as well as a dictionary (German, English, French, Spanish). It comprises the following chapters: 1. Trade directory. 2. Industrial furnaces and industrial heating equipment. 3. Index to thermal processes. 4. Index to industrial furnaces and industrial heating equipment. 5. General accessories. 6. Special accessories. 7. Accessories for firing equipment. 8. Addresses. 9. Codes of practice. (HW).

Seismic and environmental qualification of class IE equipment manufactured in Spain

International Nuclear Information System (INIS)

Gerini, P.; Lumbreras, A.; Naredo, F.

1978-01-01

Nuclear power plant instrumentation and control design is affected by several factors such as various plant operating conditions, transient response capability, safety requirements and changes in IEEE standards. Recent upgraded IEEE standards that call for Qualification of all Safety related I anc C equipment, namely IEEE 323 (Qualifying Class IE Electric Equipment for nuclear power generating stations) and its daughter Standard IEEE 344 (Recommended Practices for Seismic Qualification of Class IE Equipment for nuclear power generating stations) have been endorsed by the United States Nuclear Regulatory Commission through the issuance of corresponding Regulatory Guides. The author describes the Qualification requirements applicable to the Class IE I and C Components made in Spain for the different vintages of plants, and the programs implemented or plans established by Westinghouse to fulfill those requirements. (author)

Experience in decontamination of the equipment of NPP's with the WWER-440 reactors

International Nuclear Information System (INIS)

Balaban-Irmenin, Yu.V.

1981-01-01

Different methods of decontamination at NPPs are briefly characterized. Decontamination of the removable part of the main circulation pump (MCP) of the WWER-440 reactor is considered as an example of removable equipment decontamination. A design of the decontamination bath of the removable MCP elements and the applied chemical agents are described. A decontamination flowsheet of the Novovoronezh NPP steam generator (SG) is considered as an example of the autonomic decontamination system. The SG decontamination modes, principal flowsheets of a hydromonitor, steam-ejection sprayer and steam-emulsion device are described [ru

Laser-based coatings removal

International Nuclear Information System (INIS)

Freiwald, J.G.; Freiwald, D.

1995-01-01

Over the years as building and equipment surfaces became contaminated with low levels of uranium or plutonium dust, coats of paint were applied to stabilize the contaminants in place. Most of the earlier paint used was lead-based paint. More recently, various non-lead-based paints, such as two-part epoxy, are used. For D ampersand D (decontamination and decommissioning), it is desirable to remove the paints or other coatings rather than having to tear down and dispose of the entire building

K basins sludge removal sludge pretreatment system

International Nuclear Information System (INIS)

Chang, H.L.

1997-01-01

The Spent Nuclear Fuels Program is in the process of planning activities to remove spent nuclear fuel and other materials from the 100-K Basins as a remediation effort for clean closure. The 105 K- East and K-West Basins store spent fuel, sludge, and debris. Sludge has accumulated in the 1 00 K Basins as a result of fuel oxidation and a slight amount of general debris being deposited, by settling, in the basin water. The ultimate intent in removing the sludge and fuel is to eliminate the environmental risk posed by storing fuel at the K Basins. The task for this project is to disposition specific constituents of sludge (metallic fuel) to produce a product stream through a pretreatment process that will meet the requirements, including a final particle size acceptable to the Tank Waste Remediation System (TWRS). The purpose of this task is to develop a preconceptual design package for the K Basin sludge pretreatment system. The process equipment/system is at a preconceptual stage, as shown in sketch ES-SNF-01 , while a more refined process system and material/energy balances are ongoing (all sketches are shown in Appendix C). Thus, the overall process and 0535 associated equipment have been conservatively selected and sized, respectively, to establish the cost basis and equipment layout as shown in sketches ES- SNF-02 through 08

Chloride removal from plutonium alloy

International Nuclear Information System (INIS)

Holcomb, H.P.

1983-01-01

SRP is evaluating a program to recover plutonium from a metallic alloy that will contain chloride salt impurities. Removal of chloride to sufficiently low levels to prevent damaging corrosion to canyon equipment is feasible as a head-end step following dissolution. Silver nitrate and mercurous nitrate were each successfully used in laboratory tests to remove chloride from simulated alloy dissolver solution containing plutonium. Levels less than 10 ppM chloride were achieved in the supernates over the precipitated and centrifuged insoluble salts. Also, less than 0.05% loss of plutonium in the +3, +4, or +6 oxidation states was incurred via precipitate carrying. These results provide impetus for further study and development of a plant-scale process to recover plutonium from metal alloy at SRP

ESRC guide vanes of hydraulic turbine for Three Gorges project

Directory of Open Access Journals (Sweden)

Rui CHEN

2005-05-01

Full Text Available The mechanical properties and internal quality of low carbon martensite Electroslag Remelting Casting (ESRCstainless steel castings are superior to that of sand casting ones. The key technologies for the equipments and ESRC processes have been resolved during the experimental research period of guide vanes of hydraulic turbines for Three Gorges project. And ESRC guide vanes of hydraulic turbines for Three Gorges project have been produced successfully.

Color Parameters of the Chromascop Shade Guide

Directory of Open Access Journals (Sweden)

William J. O'Brien

2012-12-01

Full Text Available The purposes of this study are: (1 determine the color of the twenty shades in the Ivoclar’s Chromascop shade guide, (2 determine the color representation of the shade guide described as coverage error (CE, and (3 compare this shade guide with the Vita Classical and Bioform shade guides. The spectral data was collected using Beckman model DU reflectance spectrophotometer equipped with an integrating sphere. Commission International de l’Eclairage (CIE chromaticity coordinates were calculated using CIE illuminant C and 1931 observer data, then converted to CIE L*a*b* and Munsell notation. Each shade was spectrophotometrically compared to the published colors of 335 human teeth. The minimum CIE L*a*b* color difference was calculated for each tooth and the average of these color differences was defined as the CE. The measured colors of the Chromascop guide had a CIE L* range of 79.67 to 65.61, an a* range of -0.71 to 3.85, and a b* range of 14.58 to 27.69. The average CE of the Chromascop shade guide was 3.38. The Chromascop shade guide has similar colors and a CE compared with the Bioform and Vita Classical shade guides, but with some shades of higher red and yellow components.

Engineering Surfaces for Enhanced Nucleation and Droplet Removal During Dropwise Condensation

Science.gov (United States)

Dutta, Sanmitra; Khan, Sameera; Anand, Sushant

2017-11-01

Condensation plays critical role in numerous industrial applications, such as condensers, HVAC,etc In the most applications, fast formation (i.e. high nucleation) and subsequent removal of water droplets is critical for enhancing the efficiencies of their associated systems. Significant focus has been placed on the aspect of droplet removal from surfaces. This has led to, development of superhydrophobic surfaces with special textures on which droplets are self-removed after coalescence. However,because of their inherent low surface energy, nucleation energy barriers are also high on such surfaces. In contrast to conventional superhydrophobic surfaces, here we show that surfaces can be engineered such that the simultaneous benefits of high nucleation rates and fast droplet removal can be obtained during the condensation process.These benefits are obtained by impregnating a superhydrophobic surface with an oil that despite its defect-free interface provides low nucleation energy barrier during condensation. At the same time, the oil facilitates high droplet shedding rates by providing a lubricating layer below the droplets due to which droplets have negligible contact angle hysteresis. We provide a guide to choose oils that lead to enhanced nucleation, and provide experimental evidence supporting the proposed guide. We discuss the importance of different oil properties in affecting the droplet growth and subsequent removal of water droplets.

Radiation effects on electronic equipment: a designers'/users' guide for the nuclear power industry

International Nuclear Information System (INIS)

Sharp, R.E.; Garlick, D.R.

1994-01-01

The Designers'/Users' Guide to the effects of radiation on electronics is published by the Radiation Testing Service of AEA Technology. The aim of the Guide is to document the available information that we have generated and collected over some ten years whilst operating as a radiation effects and design consultancy to the nuclear power industry. We hope that this will enable workers within the industry better to understand the likely effects of radiation on the system or plant being designed and so minimise the problems that can arise. (Author)

One piece reactor removal

International Nuclear Information System (INIS)

Chia, Wei-Min; Wang, Song-Feng

1993-01-01

The strategy of Taiwan Research Reactor Renewal plan is to remove the old reactor block with One Piece Reactor Removal (OPRR) method for installing a new research reactor in original building. In this paper, the engineering design of each transportation works including the work method, the major equipments, the design policy and design criteria is described and discussed. In addition, to ensure the reactor block is safety transported for storage and to guarantee the integrity of reactor base mat is maintained for new reactor, operation safety is drawn special attention, particularly under seismic condition, to warrant safe operation of OPRR. ALARA principle and Below Regulatory Concern (BRC) practice were also incorporated in the planning to minimize the collective dose and the total amount of radioactive wastes. All these activities are introduced in this paper. (J.P.N.)

Monte Carlo program for the cold neutron beam guide

International Nuclear Information System (INIS)

Yoshiki, H.

1985-02-01

A Monte Carlo program for the transport of cold neutrons through beam guides has been developed assuming that the neutrons follow the specular reflections. Cold neutron beam guides are normally used to transport cold neutrons (4 ∼ 10 Angstrom) to experimental equipments such as small angle scattering apparatus, TOF measuring devices, polarized neutron spectrometers, and ultra cold neutron generators, etc. The beam guide is about tens of meters in length and is composed from a meter long guide elements made up from four pieces of Ni coated rectangular optical glass. This report describes mathematics and algorithm employed in the Monte Carlo program together with the display of the results. The source program and input data listings are also attached. (Aoki, K.)

Experiments of Long-range Inspection Method in Straight Pipes using Ultrasonic Guided Waves

International Nuclear Information System (INIS)

Eom, H. S.; Lim, S. H.; Kim, J. H.; Joo, Y.S.

2006-02-01

This report describes experimental results of a long-range inspection method of pipes using ultrasonic guided waves. In chapter 2, theory of guided wave was reviewed. In chapter 3, equipment and procedures which were used in the experiments were described. Detailed specifications of the specimens described in chapter 4. In chapter 5, we analyzed characteristics of guided wave signals according to shapes and sizes of defects and presents results of various signal processing methods

Long Length Contaminated Equipment Retrieval System Receiver Trailer and Transport Trailer Operations and Maintenance Manual

International Nuclear Information System (INIS)

DALE, R.N.

2000-01-01

A system to accommodate the removal of long-length contaminated equipment (LLCE) from Hanford underground radioactive waste storage tanks was designed, procured, and demonstrated, via a project activity during the 1990s. The system is the Long Length Contaminated Equipment Removal System (LLCERS). LLCERS will be maintained and operated by Tank Farms Engineering and Operations organizations and other varied projects having a need for the system. The responsibility for the operation and maintenance of the LLCERS Receiver Trailer (RT) and Transport Trailer (TT) resides with the RPP Characterization Project Operations organization. The purpose of this document is to provide vendor supplied operating and maintenance (O and M) information for the RT and TT in a readily retrievable form. This information is provided this way instead of in a vendor information (VI) file to maintain configuration control of the operations baseline as described in RPP-6085, ''Configuration Management Plan for Long Length Contaminated Equipment Receiver and Transport Trailers''. Additional Operations Baseline documents are identified in RPP-6085

Firefighter Down! How to Rapidly Remove Turnout Gear.

Science.gov (United States)

ALexander, John G

2016-04-01

The rescue of an injured colleague--and probably a good friend--is an emotionally charged event. A common initial response could be to remove everything as quickly as possible. Keep in mind that we have accepted practices for the removal of motorcycle equipment and football gear. There are also procedures for removing a patient from a vehicle or swimming pool. These all exist to protect a patient from further injury. We now have established practices for removing a firefighter from a window, or down a ladder. Why then do the procedures stop? Once a firefighter is rescued from a hot zone, he deserves the same level of consideration a football player, motorcycle rider or any other patient receives. We should not be in such a hurry that we don't care how we remove a protective ensemble. The injured firefighter deserves a system, or a procedure, that may be practiced by others and reduce the chance of further injury during

Fire Safety. Managing School Facilities, Guide 6.

Science.gov (United States)

Department for Education and Employment, London (England). Architects and Building Branch.

This booklet discusses how United Kingdom schools can manage fire safety and minimize the risk of fire. The guide examines what legislation school buildings must comply with and covers the major risks. It also describes training and evacuation procedures and provides guidance on fire precautions, alarm systems, fire fighting equipment, and escape…

Removal of natural radionuclides from drinking water from private wells in Finland

International Nuclear Information System (INIS)

Huikuri, Pia; Salonen, Laina; Turtiainen, Tuukka

1999-01-01

Removal of natural radionuclides is often necessary in Finland when household water is taken from a drilled well. Removal of radionuclides by various methods from Finnish groundwaters were studied in a EU-research project, TENAWA. The results indicated that radon can be removed very efficiently (up to 99%) by applying aeration or granular activated carbon (GAC) filtration. Uranium and radium were also removed (over 94%) by using strong base anion (SBA) and strong acid cation (SAC) resins. The capability of reverse osmosis (RO) equipment to remove radionuclides was over 90% for uranium, radium and polonium. The water quality analyses indicated that water quality remained mostly good during the water treatment. (au)

Simple and inexpensive method for CT-guided stereotaxy

Energy Technology Data Exchange (ETDEWEB)

Wester, K; Sortland, O; Hauglie-Hanssen, E

1981-01-01

A simple and inexpensive method for CT-guided stereotaxy is described. The method requires neither sophisticated computer programs nor additional stereotactic equipment, such as special head holders for the CT, and can be easily obtained without technical assistance. The method is designed to yield the vertical coordinates.

Seismic qualification of equipment for the TA-55 Plutonium Processing Facility

International Nuclear Information System (INIS)

Pellette, P.R.; Endebrock, E.G.; Giles, P.M.; Shaw, R.H.

1977-04-01

The techniques employed by the Los Alamos Scientific Laboratory (LASL) for the seismic qualification of internal equipment for the TA-55 Plutonium Facility are discussed. The structural analysis of the plutonium building and critical associated structures was performed by the Architect-Engineer (A-E), and the calculations were checked by LASL. The specifications and procedures used by LASL produced dramatic improvement in the responses by qualified vendors to the seismic requirements. There was an increase from about a 20% bid ratio to greater than 90% because prospective vendors could be competitive without having had previous seismic experience with their equipment. The equipment seismic qualification for TA-55 is in compliance with the Code of Federal Regulations, Nuclear Regulatory Commission (NRC) Guides, Energy Research and Development Administration (ERDA) Manual Chapters and Appendices, and Institute of Electrical and Electronic Engineers (IEEE) Standard 344

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.)

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

ALS beamline design requirements: A guide for beamline designers

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

This manual is written as a guide for researchers in designing beamlines and endstations acceptable for use at the ALS. It contains guidelines and policies related to personnel safety and equipment and vacuum protection. All equipment and procedures must ultimately satisfy the safety requirements set aside in the Lawrence Berkeley National Laboratory (LBNL) Health and Safety Manual (PUB-3000) which is available from the ALS User Office or on the World WideWeb from the LBNL Homepage (http:// www.lbl.gov).

75 FR 63434 - Availability of Compliance Guide for the Use of Video or Other Electronic Monitoring or Recording...

Science.gov (United States)

2010-10-15

...] Availability of Compliance Guide for the Use of Video or Other Electronic Monitoring or Recording Equipment in... the availability of a compliance guide on the use of video or other electronic monitoring or recording... providing this draft guide to advise establishments that video or other electronic monitoring or recording...

A walk through the heavens a guide to stars and constellations and their legends

CERN Document Server

Heifetz, Milton D

2004-01-01

A Walk through the Heavens is a beautiful and easy-to-use guide to the constellations of the northern hemisphere. Written for the complete beginner, this practical guide introduces the patterns of the starry skies in a memorable way. No equipment is needed, apart from normal sight and clear skies.

Control rod guide tube assemblies

International Nuclear Information System (INIS)

Jabsen, F.S.

1979-01-01

A nuclear fuel assembly including sleeves telescoped over end portions of control rod guide tubes which bear against internal shoulders of the sleeves. Upper ends of the sleeves protrude beyond a control rod guide tube spider and are locked in place by means of a resilient cellular lattice or lock that is seated in mating grooves in the outer surfaces of the sleeves. A grapple is provided for disengaging the entire lock structure spider and associated washers, springs and a grill from the end of the fuel assembly in order to enable these components to be removed and subsequently replaced on the fuel assembly after inspection and repair. (UK)

Proportioning equipment for vibration filling and compacting of grain materials in pipe containers, especially of fuel elements

International Nuclear Information System (INIS)

Pinkas, V.; Filip, Z.; Beranek, J.

1981-01-01

The equipment consists of a base plate to which are attached the fastening collar fo the pipe container and the guide column with the height-adjustable support. The filling pipe is fixed to the support. The proportioning equipment prevents particles of grain material from segregation, thus allowing to achieve homogeneity of the material in the whole volume to be compacted. It also allows determining the height of the column of material in the pipe container without destructive effects on the stacked material. The equipment is designed for the manufacture of shortened fuel elements. (J.B.)

Separately removable tubes in heavy duty heat exchanger assemblies

International Nuclear Information System (INIS)

Neudeck, G.T.

1980-01-01

The invention is directed to removable heat exchanger tube assemblies in heavy duty equipment radiators in which the tubes are each separately removable if they become defective in service. An inwardly facing annular ledge or abutment is molded into the inside diameter of each upper and lower sealing member to receive the respective ends of the tubes and prevent vertical movement of the tubes in service. A flange or shoulder is also provided on the lower portions of each tube and engages the inside of the lower sealing member to further restrain downward movement of the tubes in service. Each tube may be removed by pushing the tube upwardly to overcome the upper ledge abutment and thereby lift the tube free of the lower seal. Each tube may then be removed sidewise from the radiator. Variations of the removable sealing arrangement can be made and are described herein

Magneticresonanceimaging-guided percutaneouscryoablationofhepatocellular carcinomainspecialregions

Institute of Scientific and Technical Information of China (English)

Bin Wu; Yue-Yong Xiao; Xiao Zhang; Ai-Lian Zhang; Hong-Jun Li; Deng-Fa Gao

2010-01-01

BACKGROUND:Local cryoablation guided by CT or ultrasound has been widely applied in the treatment of hepatocellular carcinoma. However, it is still dififcult to apply this technique in certain regions such as the diaphragm dome, the ifrst hepatic hilum, and regions adjacent to the gallbladder. This study aimed to evaluate the safety and efifcacy of using magnetic resonance imaging (MRI)-guided percutaneous cryoablation as well as the effect of using an open MRI system in guiding and monitoring the treatment of hepatocellular carcinoma in these regions. METHODS:Cryoablation, guided by an open 0.35T MRI scanner and with the assistance of an MRI-compatible optical navigation system, was performed on 32 patients with hepatocellular carcinoma at the diaphragm dome, the ifrst hepatic hilum, and regions adjacent to the gallbladder. Each patient had one or two tumors. The total number of tumors treated was 36. The tumor diameters ranged from 2.5 to 10.0 cm (mean 4.7±1.8 cm). The cryosurgical system was MRI-compatible and equipped with cryoprobes 1.47 mm in outside diameter. Under the guidance of MRI in combination with the optical navigation system, the cryoprobes were introduced percutaneously into a tumor at the planned targeting points while critical organs or tissues were avoided. Each cryoablation procedure included two freezing-thawing cycles, and MRI images were acquired dynamically to monitor the ablation of the tumor from time to time during the operation. In order to investigate the therapeutic effects of a cryoablation procedure, AFP measurements and liver-enhanced MRI or CT-enhanced scans were performed at regular times. RESULTS:MRI and optical navigation system-guided cryo-ablation procedures were successfully performed on all 32 patients (36 tumor sites) and no serious complications occurred. The follow-up period ranged from 5 to 12 months. The 6-and 12-month overall survival rates were 96.8%and 90.6%, respectively. According to the diagnosis of liver

Overview of Remote Retrieval Equipment and the Strategy for removal of Radon Bearing Waste from Silos 1 and 2 at the Fernald Site

International Nuclear Information System (INIS)

Rinker, Michael W.; Samuel, Todd J.

2001-01-01

This document provides an overview of the remote retrieval equipment and strategy for the retrieval of waste from Silos 1 and 2 at the Department of Energy's Fernald site in southwestern Ohio. The scope of this paper is limited to general descriptions of remote equipment specifically related in-silo retrieval. The retrieval strategy describes how the contractor team is planning to utilize the various remote subsystems to efficiently remove the waste from the silos from a philosophical standpoint as opposed to a procedural and operational standpoint. The retrieval strategy and approach is based upon the successful tank retrieval operations conducted at DOE's Oak Ridge and Hanford Sites. Lessons learned from these previous operations have been utilized in planning an approach for the Fernald Silo Retrieval Project. The equipment overview includes discussion of the retrieval system configurations together with descriptions of the robotic arm and retrieval end effectors, the conditioning and transfer pumping system, the sluicer and sluicing pump, as well as the debris retrieval system. A unique challenge being addressed as part of this project is the waste contents. Silos 1 and 2 contain two distinct layers of material that need to be retrieved. The first layer is a Bentonite (trade name BentogroutTM) cap that was placed in the silos to prevent radon migration into the dome space and out of the silos. The Bentonite layer varies, but in general it is approximately six inches deep in the center of the silo and thirty-six inches near the silo walls. The material may have dried out on the surface, and may still be wetted near the bottom of the bentonite layer. The K-65 ore tailings, which were slurried into the silos, are the remainder of the waste that is over 20' in depth. This paper provides an overview of the retrieval strategies, technologies, and techniques that will be used to safely and efficiently retrieve the waste from the Fernald Silos

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

International Nuclear Information System (INIS)

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

1984-01-01

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

Fire extinguishing of electrical equipment under voltage at nuclear power plants

International Nuclear Information System (INIS)

Capek, Josef

2009-01-01

Fire extinguishing on equipment that is under voltage is always hazardous. Conventional fire fighting equipment applicable to this task includes powder and gas extinguishers, which, however, have some drawbacks. Therefore, attention has been increasingly devoted to high-pressure fire extinguishing, whose assets include better heat removal as compared to a full water flow where the majority of the water runs off without any cooling effect. This article describes the testing of some types and combinations of extinguishing techniques and their interpretation based on earth-leakage current measurement and determination of a safe distance for fire extinguishing. Methodology described in CSN IEC 60-1:1994 and CSN EN 3-7:2004 was applied. To meet the criterion, none of the tests was to exhibit an earth-leakage current higher than 0.5 mA. In the accredited laboratory test room setup, 3 extinguishing equipment arrangements proved to extinguish fire on electrical equipment under voltage at a safe distance of 1 m (or 3 m). (orig.)

Neuronavigator-guided glioma surgery.

Science.gov (United States)

Du, Guhong; Zhou, Liangfu; Mao, Ying

2003-10-01

To evaluate the effectiveness of neuronavigator-guided surgery for the resection of gliomas. A total of 80 patients with gliomas underwent surgical treatment under the StealthStation neuronavigator to estimate the extent of the tumors. In 27 cases, the measurements of brain shifts at the dura, cortical surface and lesion margin were recorded during the operations. A technique termed "micro-catheter fence post" was used in superficial gliomas to compensate for brain shift. Mean fiducial error and predicted accuracy in the 80 cases were 2.03 mm +/- 0.89 mm and 2.43 mm +/- 0.99 mm, respectively. The shifts at the dura, cortical surface and lesion margin were 3.44 mm +/- 2.39 mm, 7.58 mm +/- 3.75 mm, and 6.55 mm +/- 3.19 mm, respectively. Although neuronavigation revealed residual tumors, operations were discontinued in 5 cases of deep-seated gliomas. In the other 75 cases, total tumor removals were achieved in 62 (82.7%), and subtotal removals were achieved in 13 (17.3%). Post-operation, neurological symptoms were improved or unchanged in 68 cases (85.0%), and worsened in 12 (15.0%). No deaths occurred during the operations and post-operations. Intraoperative brain shifts mainly contribute to the fail of spatial accuracy during neuronavigator-guided glioma surgery. The "micro-catheter fence post" technique used for glioma surgery is shown to be useful for compensating for intraoperative brain shifts. This technique, thus, contributes to an increase in total tumor removal and a decrease in surgical complications.

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

The development of remote repairing system, decontamination and in-cell remote inspection equipment

International Nuclear Information System (INIS)

Ishibashi, Yuzo; Toyoda, Osamu; Haginoya, Isao; Yamamoto, Ryuichi; Tanaka, Yasumasa

1993-01-01

PNC has been developing remote repair and inspection technologies for in-cell components in reprocessing Plants. In this report, several remote technologies such as remote dismantling and removal, decontamination, remote pipe maintenance and remote in-cell inspection equipment are described. (author)

Design of the Mechanical Parts for the Neutron Guide System at HANARO

International Nuclear Information System (INIS)

Shin, J. W.; Cho, Y. G.; Cho, S. J.; Ryu, J. S.

2008-01-01

The research reactor HANARO (High-flux Advanced Neutron Application ReactOr) in Korea will be equipped with a neutron guide system, in order to transport cold neutrons from the neutron source to the neutron scattering instruments in the neutron guide hall near the reactor building. The neutron guide system of HANARO consists of the in-pile plug assembly with in-pile guides, the primary shutter with in-shutter guides, the neutron guides in the guide shielding room with dedicated secondary shutters, and the neutron guides connected to the instruments in the neutron guide hall. Functions of the in-pile plug assembly are to shield the reactor environment from nuclear radiation and to support the neutron guides and maintain them precisely oriented. The primary shutter is a mechanical structure to be installed just after the in-pile plug assembly, which stops neutron flux on demand. This paper describes the design of the in-pile assembly and the primary shutter for the neutron guide system at HANARO. The design of the guide shielding assembly for the primary shutter and the neutron guides is also presented

Guide wire extension for shape memory polymer occlusion removal devices

Science.gov (United States)

Maitland, Duncan J [Pleasant Hill, CA; Small, IV, Ward; Hartman, Jonathan [Sacramento, CA

2009-11-03

A flexible extension for a shape memory polymer occlusion removal device. A shape memory polymer instrument is transported through a vessel via a catheter. A flexible elongated unit is operatively connected to the distal end of the shape memory polymer instrument to enhance maneuverability through tortuous paths en route to the occlusion.

Removal of overburden soils from buried waste sites

International Nuclear Information System (INIS)

Rice, P.M.

1994-01-01

Transuranic (TRU) waste buried in pits and trenches is covered with a soil cap, or overburden, to shed water. During retrieval operations, the overburden (expected to be clean) must be removed carefully to avoid breaching the soil/waste matrix within a pit or trench and to confine any possible local spot contamination. This necessitates removal in precise (7.6- to 15.25-cm) increments with a high degree of accuracy. In addition, during overburden removal the overburden must be characterized to a depth that exceeds each cut of soil. A field demonstration was conducted to evaluate a technology for removing overburden soils a the Radioactive Waste Management Complex (RWMC), Subsurface Disposal Area (SDA) at the Idaho National Engineering Laboratory (INEL). The demonstration evaluated equipment performance and techniques for removing overburden soil and controlling contamination and dust. To evaluate the performance of these techniques during removal operations, personnel took air particulate samples, physical measurements of the soil cuts, maneuverability measurements, and rate of soil removal data. The overburden was spiked at specific locations and depths with rare earth tracers to provide a medium for evaluating samples. Analysis to determine the precision and accuracy of the soil removal, amount of dust generated, and potential spread of contamination was performed

Remote target removal for the Oak Ridge 86-inch Cyclotron

International Nuclear Information System (INIS)

Walls, A.A.

1982-01-01

A remotely operated target remover has been plaed in operation at the 86-Inch Cyclotron located in Oak Ridge. The system provides for the remote removal of a target from inside the cyclotron, loading it into a cask, and the removal of the cask from the 1.5 m (5-ft) shielding walls. The remote system consists of multiple electrical and pneumatically operated equipment which is designed for controlled step-by-step operation, operated with an electrical control panel, and monitored by a television system. The target remover has reduced the radiation exposures to operating personnel at the facility and has increased the effective operating time. The system is fast, requires a minimum of skill to operate, and has demonstrated both reliability and durability

Using a Motion Sensor-Equipped Smartphone to Facilitate CT-Guided Puncture

International Nuclear Information System (INIS)

Hirata, Masaaki; Watanabe, Ryouhei; Koyano, Yasuhiro; Sugata, Shigenori; Takeda, Yukie; Nakamura, Seiji; Akamune, Akihisa; Tsuda, Takaharu; Mochizuki, Teruhito

2017-01-01

PurposeTo demonstrate the use of “Smart Puncture,” a smartphone application to assist conventional CT-guided puncture without CT fluoroscopy, and to describe the advantages of this application.Materials and MethodsA puncture guideline is displayed by entering the angle into the application. Regardless of the angle at which the device is being held, the motion sensor ensures that the guideline is displayed at the appropriate angle with respect to gravity. The angle of the smartphone’s liquid crystal display (LCD) is also detected, preventing needle deflection from the CT slice image. Physicians can perform the puncture procedure by advancing the needle using the guideline while the smartphone is placed adjacent to the patient. In an experimental puncture test using a sponge as a target, the target was punctured at 30°, 50°, and 70° when the device was tilted to 0°, 15°, 30°, and 45°, respectively. The punctured target was then imaged with a CT scan, and the puncture error was measured.ResultsThe mean puncture error in the plane parallel to the LCD was less than 2°, irrespective of device tilt. The mean puncture error in the sagittal plane was less than 3° with no device tilt. However, the mean puncture error tended to increase when the tilt was increased.ConclusionThis application can transform a smartphone into a valuable tool that is capable of objectively and accurately assisting CT-guided puncture procedures.

Using a Motion Sensor-Equipped Smartphone to Facilitate CT-Guided Puncture

Energy Technology Data Exchange (ETDEWEB)

Hirata, Masaaki, E-mail: masaaki314@gmail.com [Matsuyama Shimin Hospital, Department of Radiology (Japan); Watanabe, Ryouhei; Koyano, Yasuhiro [Matsuyama Shimin Hospital, Department of Surgery (Japan); Sugata, Shigenori; Takeda, Yukie [Ehime Prefectural Imabari Hospital, Department of Radiology (Japan); Nakamura, Seiji; Akamune, Akihisa [Matsuyama Shimin Hospital, Department of Radiology (Japan); Tsuda, Takaharu; Mochizuki, Teruhito [Ehime University Graduate School of Medicine, Department of Radiology (Japan)

2017-04-15

PurposeTo demonstrate the use of “Smart Puncture,” a smartphone application to assist conventional CT-guided puncture without CT fluoroscopy, and to describe the advantages of this application.Materials and MethodsA puncture guideline is displayed by entering the angle into the application. Regardless of the angle at which the device is being held, the motion sensor ensures that the guideline is displayed at the appropriate angle with respect to gravity. The angle of the smartphone’s liquid crystal display (LCD) is also detected, preventing needle deflection from the CT slice image. Physicians can perform the puncture procedure by advancing the needle using the guideline while the smartphone is placed adjacent to the patient. In an experimental puncture test using a sponge as a target, the target was punctured at 30°, 50°, and 70° when the device was tilted to 0°, 15°, 30°, and 45°, respectively. The punctured target was then imaged with a CT scan, and the puncture error was measured.ResultsThe mean puncture error in the plane parallel to the LCD was less than 2°, irrespective of device tilt. The mean puncture error in the sagittal plane was less than 3° with no device tilt. However, the mean puncture error tended to increase when the tilt was increased.ConclusionThis application can transform a smartphone into a valuable tool that is capable of objectively and accurately assisting CT-guided puncture procedures.

Riser equipment decontamination engineering task plan

International Nuclear Information System (INIS)

BOGER, R.M.

1999-01-01

On October 15, 1998, two Characterization Project Operations (CPO) employees were found to have contaminated clothing. An operator had 300,000-dpm/100cm2 beta/gamma, no alpha, contamination on his coat sleeve and a Radiation Control Technician (RCT) had 10,000 dpm/100cm2 beta/gamma, no alpha, on his shirt sleeve. The CPO swing shift crew was working in TX tank farm, performing sampling activities at 241-TX-113. TX tank farm is a ''clean farm'' and does not require anti-contamination clothing for entry. The CPO personnel were dressed in normal work clothes. An operator and an RCT were performing a pre-job survey that involved removing bagging around the riser equipment. When the RCT saw that the contamination readings from smear samples of the riser equipment were greater than expected, the job was suspended. Crew members were then directed to areas of lower background radiation for personnel surveys. During personnel surveys, reportable contamination was found on the coat sleeve of the operator who had been involved in the pre-job survey and on the shirt sleeve of the RCT who had been involved in the pre-job survey. No other personnel were found to be contaminated. Because of this off normal event Characterization Engineering was given the following corrective action: Examine the process methodology used for core sampling operations to determine practicality and potential long-term advantages of reducing personnel contact with contaminated equipment. This Engineering Task Plan ensures that LMHC 1998a, Corrective Action No.7 is completely addressed by Characterization Engineering. The deliverable is an Engineering Study that evaluates decontamination of riser equipment components and considers additional engineered features to reduce potential exposure to workers operating the riser equipment. This engineering study shall also address any released design features that have failed to be implemented

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

Science.gov (United States)

Hilley, Robert

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

Neutron scattering equipments in JAERI. Current status

International Nuclear Information System (INIS)

Hamaguchi, Yoshikazu; Minakawa, Nobuaki

2003-01-01

24 neutron scattering instruments are installed in the JRR-3M research reactor. Among them JAERI has 12 neutron scattering instruments. Those instruments are HRPD for high-resolution structural analysis, TAS-1 and TAS-2 for elastic and inelastic scattering and for magnetic scattering measurements by the polarized neutron, LTAS for elastic and inelastic scattering measurement at a low energy region, and for neutron device development, PNO for topography and for very small angle scattering measurement in a small Q range, NRG for neutron radiography, RESA for internal strain measurements, SANS for the molecule and semi-macroscopic magnetic structural analysis, BIX-2 and BIX-3 for the biological structural analysis research, and PGA for the research of prompt gamma-ray analysis. The university groups have 12 neutron scattering instruments. Since those instruments were installed at the period when JRR-3M was completed, about 10 years have passed. In order to match the old control systems with the progress of recent computer technologies, and peripheral equipment, numbers of instruments are being renewed. In the neutron guide hall of JRR-3M, the Ni mirror guide tube was replaced by a super mirror guide tube to increase neutron flux. The intensity of 2A flux was increased by a factor of about two. (J.P.N.)

A concise guide to effective management of the public works equipment fleet

OpenAIRE

De Armas, Vicente.

1996-01-01

CIVINS (Civilian Institutions) Thesis document Approved for public release ; distribution is unlimited The purpose of this report is to present in a concise form the principles and fundamentals of managing the public works equipment fleet, providing a basis from which to develop an effective fleet management program. The report begins with a review of today's trends in fleet management, including, organization, privatization, effects of environmental regulations and a discussion on info...

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

High pressure freon decontamination of remote equipment

International Nuclear Information System (INIS)

Wilson, C.E.

1987-01-01

A series of decontamination tests using high pressure FREON 113 was conducted in the 200 Area of the Hanford site. The intent of these tests was to evaluate the effectiveness of FREON 113 in decontamination of manipulator components, tools, and equipment items contaminated with mixed fission products. The test results indicated that high pressure FREON 113 is very effective in removing fissile material from a variety of objects and can reduce both the quantity and the volume of the radioactive waste material presently being buried

Classification of methods and equipment recovery secondary waters

Directory of Open Access Journals (Sweden)

G. V. Kalashnikov

2017-01-01

Full Text Available The issues of purification of secondary waters of industrial production have an important place and are relevant in the environmental activities of all food and chemical industries. For cleaning the transporter-washing water of beet-sugar production the key role is played by the equipment of treatment plants. A wide variety of wastewater treatment equipment is classified according to various methods. Typical structures used are sedimentation tanks, hydrocyclones, separators, centrifuges. In turn, they have a different degree of purification, productivity through the incoming suspension and purified secondary water. This is equipment is divided into designs, depending on the range of particles to be removed. A general classification of methods for cleaning the transporter-washing water, as well as the corresponding equipment, is made. Based on the analysis of processes and instrumentation, the main methods of wastewater treatment are identified: mechanical, physicochemical, combined, biological and disinfection. To increase the degree of purification and reduce technical and economic costs, a combined method is widely used. The main task of the site for cleaning the transporter-washing waters of sugar beet production is to provide the enterprise with water in the required quantity and quality, with economical use of water resources, taking into account the absence of pollution of surface and groundwater by industrial wastewater. In the sugar industry is currently new types of washing equipment of foreign production are widely used, which require high quality and a large amount of purified transporter-washing water for normal operation. The proposed classification makes it possible to carry out a comparative technical and economic analysis when choosing the methods and equipment for recuperation of secondary waters. The main equipment secondary water recovery used at the beet-sugar plant is considered. The most common beet processing plant is a

Guide to good practices for developing and conducting case studies: DOE handbook

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-01

Learning from experience is often very costly to a facility in terms of injured personnel, damaged equipment, and wasted time. Learning from the experience gained at the facility and from industry can prevent repeating costly mistakes. This guide contains a method for learning from experience to prevent mistakes from occurring; that method is the case study. This guide describes how to develop and present case studies. This guide provides the instructional developer insight on the best kind of case study to use and includes examples of the various types of case studies.

Voltage surges induced in transformer secondaries with loads characterized by sensitive electronic equipment

Energy Technology Data Exchange (ETDEWEB)

Cogo, Joao Roberto [GSI Engenharia e Consultoria Ltda., Taubate, SP (Brazil)], Email: gsi@gsiconsultoria.com.br; Dommel, Hermann Wilhelm [University of British Columbia, Vancouver (Canada)], Email: hermannd@ece.ubc.ca

2007-07-01

The grounding of sensitive electronic equipment such as computers, programmable logic controllers (PLC), process control systems, and other electronic equipment is one of the most important considerations towards obtaining an efficient operation of such systems. Such equipment, which for the purposes of this work is called 'Sensitive Electronic Equipment - SEE' is very sensitive to faults and low intensity random voltages which have no effect upon the electrical power equipment and upon human beings. In this work, the grounding problem is evaluated, to guide the user on the proper installation of SEEs, so as to prevent them from being damaged. The following items will be discussed: voltages which SEEs are subject to during incidence of atmospheric surges in the distribution overhead lines to which they are connected; sustained voltage that the high voltage supply of SEEs must be able to withstand during line-to-ground faults that originate from atmospheric surges that reach the transmission lines which are connected to the electrical power self producers (or electrical power independent producers). (author)

Trunnion Collar Removal Machine - Gap Analysis Table

International Nuclear Information System (INIS)

Johnson, M.

2005-01-01

The purpose of this document is to review the existing the trunnion collar removal machine against the ''Nuclear Safety Design Bases for License Application'' (NSDB) [Ref. 10] requirements and to identify codes and standards and supplemental requirements to meet these requirements. If these codes and standards can not fully meet these requirements then a ''gap'' is identified. These gaps will be identified here and addressed using the ''Trunnion Collar Removal Machine Design Development Plan'' [Ref. 15]. The codes and standards, supplemental requirements, and design development requirements for the trunnion collar removal machine are provided in the gap analysis table (Appendix A, Table 1). Because the trunnion collar removal machine is credited with performing functions important to safety (ITS) in the NSDB [Ref. 10], design basis requirements are applicable to ensure equipment is available and performs required safety functions when needed. The gap analysis table is used to identify design objectives and provide a means to satisfy safety requirements. To ensure that the trunnion collar removal machine performs required safety functions and meets performance criteria, this portion of the gap analysis tables supplies codes and standards sections and the supplemental requirements and identifies design development requirements, if needed

Removal of radionuclides from household water

International Nuclear Information System (INIS)

Vesterbacka, P.; Turtiainen, T.; Haemaelaeinen, K.; Salonen, L.; Arvela, H.

2007-02-01

particles than larger particles. Testing simultaneous removal of radon, iron and magnesium by two commercial devices gave promising results: radon removal efficiency was over 98%. Furthermore, it was found that certain fluoride removal equipment can be applied to simultaneous removal of uranium, radium, lead and polonium. (orig.)

Development of a SAXS equipment for the nanomaterials characterization

Energy Technology Data Exchange (ETDEWEB)

Costa, Rauni Coelho; Campos, Jose Brant de; Amaral, Jorge Luis Machado, E-mail: rauni.coelho@gmail.com [Universidade do Estado do Rio de Janeiro (UERJ), RJ (Brazil); Lima Junior, Herman Pessoa; Cardoso, Rodrigo Felix [Centro Brasileiro de Pesquisas Fisicas (CBPF), Rio de Janeiro, RJ (Brazil)

2016-07-01

Full text: The increase use of nanomaterials requires the creation of techniques and the associated equipment to allow the property evaluation at the nanometer scale. SAXS (Small Angle X-Ray Scattering), technique allows the analysis of nanomaterials and the determination of various parameters such as particle size, density and morphology of nanoparticles [1,2]. The SAXS equipment is a powerful tool in development and research at the nanoscale in order to improve understanding of the different properties of these materials and its comparison with the microscopic properties. But due to its costs, such equipment are extremely scarce in developing countries, because they are marketed with high values. This work aims at the development of collimating optics of a SAXS equipment, based on the geometry of a goniometer in a diffractometer Seifert HZG 4. The xray scattered signal reception is performed using bidimensional X-ray detector developed and manufactured at Laboratorio de Sistemas de Deteccao of Centro Brasileiro de Pesquisas Fisicas, RJ, Brazil (LSD/CBPF). In the present work, it will be presented the X-ray collimation system design and the first results of SAXS operation. Those results show the geometric characteristics of the X-ray beam in the SAXS equipment, received in the bidimensional detector, after traveling the entire optical path. [1] O. Glatter and O. Kratky (edts.), Small-Angle X-ray Scattering (Academic, London, 1982). [2] Heimo Schnablegger and Yashveer Singh. The SAXS Guide. Getting acquainted with the principles. 3.edition. (author)

Building America Best Practices Series Volume 14 - HVAC. A Guide for Contractors to Share with Homeowners

Energy Technology Data Exchange (ETDEWEB)

Baechler, Michael C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gilbride, Theresa L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hefty, Marye G. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hand, James R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Love, Pat M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2011-08-01

This guide, which is part of a series of Best Practices guides produced by DOE’s Building America program, describes ways homeowners can reduce their energy costs and improve the comfort, health, and safety of their homes by upgrading their heating, ventilation, and air conditioning (HVAC) equipment.

Automotive and Construction Equipment for Arctic Use, Materials Problems

Science.gov (United States)

1991-11-01

followed. Nitrile rubber ( NBR ) is one of the most common materials used in seal manufacture. It is a copolymer of butadiene and acrylonitrile and is... rubber and other elastomers, and many plastics. This problem is exacerbated, especially in equipment with diesel engines, because the engines run...their original condition in a short time on removal of the stress. The group includes natural rubbers as well as synthetic polymers. Many of these

Long Length Contaminated Equipment Retrieval System Receiver Trailer and Transport Trailer Operations and Maintenance Manual

Energy Technology Data Exchange (ETDEWEB)

DALE, R.N.

2000-05-01

A system to accommodate the removal of long-length contaminated equipment (LLCE) from Hanford underground radioactive waste storage tanks was designed, procured, and demonstrated, via a project activity during the 1990s. The system is the Long Length Contaminated Equipment Removal System (LLCERS). LLCERS will be maintained and operated by Tank Farms Engineering and Operations organizations and other varied projects having a need for the system. The responsibility for the operation and maintenance of the LLCERS Receiver Trailer (RT) and Transport Trailer (TT) resides with the RPP Characterization Project Operations organization. The purpose of this document is to provide vendor supplied operating and maintenance (O & M) information for the RT and TT in a readily retrievable form. This information is provided this way instead of in a vendor information (VI) file to maintain configuration control of the operations baseline as described in RPP-6085, ''Configuration Management Plan for Long Length Contaminated Equipment Receiver and Transport Trailers''. Additional Operations Baseline documents are identified in RPP-6085.

Guided Acoustic and Optical Waves in Silicon-on-Insulator for Brillouin Scattering and Optomechanics

Science.gov (United States)

2016-08-01

APL PHOTONICS 1, 071301 (2016) Guided acoustic and optical waves in silicon-on- insulator for Brillouin scattering and optomechanics Christopher J...is possible to simultaneously guide optical and acoustic waves in the technologically important silicon on insulator (SOI) material system. Thin...high sound velocity — makes guiding acoustic waves difficult, motivating the use of soft chalcogenide glasses and partial or complete releases (removal

Guide to Treatment of Tattoo Complications and Tattoo Removal

DEFF Research Database (Denmark)

Serup, Jørgen; Bäumler, Wolfgang

2017-01-01

Clinicians in the fields of general medicine, dermatology, and plastic surgery are in their work now and then confronted with tattoo complications. Recognizing the rather few important diagnostic groups and urgencies, the medical 'decision tree' of treatment becomes quite simple. Acute conditions...... to topical corticoid and best treated with dermatome shaving with complete removal of the hapten concentrated in the outer dermis. Laser treatment of allergic reactions can boost the allergy with worsening and a potential risk of anaphylaxis and is thus not recommended in tattoo allergy. Chronic...

US-guided preoperative hook-wire localization of nonpalpable breast lesions

International Nuclear Information System (INIS)

Shin, Tae Beom; Lee, Sang Kwon; Kim, Hye Jung; Ryeom, Hun Kyu; Kim, Tae Hun; Kim, Yong Ju; Kang, Duk Sik; Lee, Young Ha; Park, Ho Yong

2000-01-01

To evaluate the feasibility and efficacy of US-guided preoperative wire localization of nonpalpable breast lesions. US-guided preoperative wire localization was performed upon 45 nonpalpable breast lesions including 14 nonpalpable masses, 11 nonpalpable masses with microcalcifications, 11 ductal lesions, 9 with microcalcifications. No local anesthesia was performed during the localization procedure. Under the US-guidance, the needle with the hook-wire was inserted into the lesion until the hook of the wire reached 1 cm beyond the posterior margin of the lesion. Precise wire positioning was confirmed by mammography. Specimen radiography or specimen ultrasonography was performed in all cases. US-guided preoperative wire localization was successfully achieved in all cases. The time required for US-guided wire localization was less than five minutes. All lesions were successfully removed by surgical excision. Successful removal was confirmed by specimen radiography or specimen ultrasonography, gross findings of the specimen and consistency between radiographic and pathologic findings. The histologic diagnosis of 45 lesions were 7 ductal carcinoma in situ, 8 invasive ductal carcinoma, 6 fibroadenoma, 8 intraductal papilloma, 2 atypical ductal hyperplasia, and 14 fibrocystic changes. No complications were occurred during and after the procedure. US-guided preoperative wire localization for excisional biopsy is simple, safe, and accurate method in the histologic diagnosis of nonpalpable breast lesions detectable with ultrasonography.

US-guided preoperative hook-wire localization of nonpalpable breast lesions

Energy Technology Data Exchange (ETDEWEB)

Shin, Tae Beom; Lee, Sang Kwon; Kim, Hye Jung; Ryeom, Hun Kyu; Kim, Tae Hun; Kim, Yong Ju; Kang, Duk Sik; Lee, Young Ha; Park, Ho Yong [Kyungpook National University College of Medicine, Taegu (Korea, Republic of)

2000-12-15

To evaluate the feasibility and efficacy of US-guided preoperative wire localization of nonpalpable breast lesions. US-guided preoperative wire localization was performed upon 45 nonpalpable breast lesions including 14 nonpalpable masses, 11 nonpalpable masses with microcalcifications, 11 ductal lesions, 9 with microcalcifications. No local anesthesia was performed during the localization procedure. Under the US-guidance, the needle with the hook-wire was inserted into the lesion until the hook of the wire reached 1 cm beyond the posterior margin of the lesion. Precise wire positioning was confirmed by mammography. Specimen radiography or specimen ultrasonography was performed in all cases. US-guided preoperative wire localization was successfully achieved in all cases. The time required for US-guided wire localization was less than five minutes. All lesions were successfully removed by surgical excision. Successful removal was confirmed by specimen radiography or specimen ultrasonography, gross findings of the specimen and consistency between radiographic and pathologic findings. The histologic diagnosis of 45 lesions were 7 ductal carcinoma in situ, 8 invasive ductal carcinoma, 6 fibroadenoma, 8 intraductal papilloma, 2 atypical ductal hyperplasia, and 14 fibrocystic changes. No complications were occurred during and after the procedure. US-guided preoperative wire localization for excisional biopsy is simple, safe, and accurate method in the histologic diagnosis of nonpalpable breast lesions detectable with ultrasonography.

Memory-guided saccades show effect of a perceptual illusion whereas visually guided saccades do not.

Science.gov (United States)

Massendari, Delphine; Lisi, Matteo; Collins, Thérèse; Cavanagh, Patrick

2018-01-01

The double-drift stimulus (a drifting Gabor with orthogonal internal motion) generates a large discrepancy between its physical and perceived path. Surprisingly, saccades directed to the double-drift stimulus land along the physical, and not perceived, path (Lisi M, Cavanagh P. Curr Biol 25: 2535-2540, 2015). We asked whether memory-guided saccades exhibited the same dissociation from perception. Participants were asked to keep their gaze centered on a fixation dot while the double-drift stimulus moved back and forth on a linear path in the periphery. The offset of the fixation was the go signal to make a saccade to the target. In the visually guided saccade condition, the Gabor kept moving on its trajectory after the go signal but was removed once the saccade began. In the memory conditions, the Gabor disappeared before or at the same time as the go-signal (0- to 1,000-ms delay) and participants made a saccade to its remembered location. The results showed that visually guided saccades again targeted the physical rather than the perceived location. However, memory saccades, even with 0-ms delay, had landing positions shifted toward the perceived location. Our result shows that memory- and visually guided saccades are based on different spatial information. NEW & NOTEWORTHY We compared the effect of a perceptual illusion on two types of saccades, visually guided vs. memory-guided saccades, and found that whereas visually guided saccades were almost unaffected by the perceptual illusion, memory-guided saccades exhibited a strong effect of the illusion. Our result is the first evidence in the literature to show that visually and memory-guided saccades use different spatial representations.

Tourists in space a practical guide

CERN Document Server

Seedhouse, Erik

2014-01-01

Forget Hawaii or the Mediterranean. Soon – very soon – you’ll be able to add a much more exotic stamp to your passport: space. How will you get there, what will the trip be like, and how much training will you need? All you need to know is right here in this guide. Tourists in Space: A Practical Guide supplies all the advice and information you need to make your spaceflight the most rewarding experience of your life. This definitive, real-world guide is packed with helpful facts and suggestions on everything from training, equipment, safety, and in-flight procedures to techniques for avoiding space motion sickness and bone demineralization. You’ll also find: • Advice on choosing your training agency • Techniques for minimizing the risk of space motion sickness • Information you need to prepare for your medical examination, training, and flight • Tips on activities near your training location And much more.

User guide to power management for PCs and monitors

Energy Technology Data Exchange (ETDEWEB)

Nordman, B.; Piette, M.A.; Kinney, K.; Webber, C. [Lawrence Berkeley National Lab., CA (United States). Environmental Energy Technologies Div.

1997-01-01

Power management of personal computers (PCs) and monitors has the potential to save significant amounts of electricity as well as deliver other economic and environmental benefits. The Environmental Protection Agency`s ENERGY STAR{reg_sign} program has transformed the PC market so that equipment capable of power management is now widely available. However, previous studies have found that many Energy Star compliant computer systems are not accomplishing energy savings. The principal reasons for this are systems not being enabled for power management or a circumstance that prevents power management from operating. This guide is intended to provide information to computer support workers to increase the portion of systems that successfully power manage. The guide introduces power management concepts and the variety of benefits that power management can bring. It then explains how the parts of a computer system work together to enter and leave power management states. Several common computer system types are addressed, as well as the complications that networks bring to power management. Detailed instructions for checking and configuring several system types are provided, along with trouble shooting advice. The guide concludes with a discussion of how to purchase Energy Star compliant systems and future directions for power management of PCs and related equipment.

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

International Nuclear Information System (INIS)

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

1995-09-01

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

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

Rust dissolution and removal by iron-reducing bacteria: A potential rehabilitation of rusted equipment

International Nuclear Information System (INIS)

Starosvetsky, J.; Kamari, R.; Farber, Y.; Bilanović, D.; Armon, R.

2016-01-01

Highlights: • The present study demonstrated the high reductive capacity of both strains: the collection S. oneidensis and the wild strain Geobacter spp. (soil isolate). • The experimental strains were successful in Fe 3+ reduction for both states: soluble and crystalline (originally prepared from rust). • Rust dissolution can be improved by: addition of AFC at low concentration (0.2 g/l), increasing bacterial initial inoculum and rust reactive surface. • Both experimental IRB strains were able to completely remove previously formed rust on carbon steel coupons. • Additional results (not showed) revealed that culture S. oneidensis and the environmental isolate Geobacter spp., apparently have a different mechanism of iron reduction that requires further study. - Abstract: Iron reducing bacteria (IRB), to be used in rust dissolution and removal, have been isolated and enriched from different environmental sources. Comparative measurements revealed that a soil isolate (Geobacter sulfurreducens sp.) had the highest reductive activity equivalent to Shewanella oneidensis (strain CIP 106686, pure culture). Both reductive microorganisms can use Fe 3+ ions as electron acceptors from soluble as well as from crystalline sources. In nutrient medium containing soluble Fe 3+ , the highest reductive activity obtained for G. sulfurreducens sp. and S. oneidensis was 93 and 97% respectively. Successful removal of rust from carbon steel coupons has been achieved with both experimental bacteria.

Auxiliary equipment cooling circuit in nuclear reactors

International Nuclear Information System (INIS)

Yanagisawa, Ko.

1986-01-01

Purpose: To prevent the propagation of bacterias that transform NO 2 into NO 3 in auxiliary equipment coolants using corrosion inhibitors of nitrite type in BWR type reactors. Method: In auxiliary equipments coolant systems, water quality is controlled by using purified water as supplement water and nitrite such as Na 2 NO 2 as the corrosion inhibitors. However, in the circumstance where dissolved oxygen is present, bacteria propagate to oxidize NO 2 into NO 3 . Thus, NO 2 at 200 ppm is reduced to 20 ppm. In view of the above, a surge tank supplied from water supplement line is connected in series and a deaeration device is disposed thereto. Since the presence of dissolved oxygen causes the bacteria to propagate it is desired that the dissolved oxygen density in the supplement water is less than 5 ppm. Deaeration and pressure reduction in the surge tank can remove the dissolved oxygen, prevent NO 3 increase and also prevent stress corrosion cracks in the system pipeways. (Horiuchi, T.)

27 CFR 25.1 - Production and removal of beer.

Science.gov (United States)

2010-04-01

... beer. 25.1 Section 25.1 Alcohol, Tobacco Products and Firearms ALCOHOL AND TOBACCO TAX AND TRADE BUREAU, DEPARTMENT OF THE TREASURY LIQUORS BEER Scope of Regulations § 25.1 Production and removal of beer. The regulations in this part relate to beer and cereal beverages and cover the location, construction, equipment...

Westinghouse radiological containment guide

International Nuclear Information System (INIS)

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

1994-03-01

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

Westinghouse radiological containment guide

Energy Technology Data Exchange (ETDEWEB)

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

1994-03-01

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

K.s. Micro-implant placement guide.

Science.gov (United States)

Sharma, K; Sangwan, A

2014-09-01

A one of the greatest concerns with orthodontic mini-implants is risk of injury to dental roots during placement is, especially when they are inserted between teeth. Many techniques have been used to facilitate safe placement of interradicular miniscrews. Brass Wires or metallic markers are easy to place in the interproximal spaces, but because their relative positions may be inconsistent in different radio -graphic views, they are not always accurate. K.S. micro implant placement guide suggested in this article is simple design and easy in fabrication, required minimal equipment for fabrication and does not disturb the existing appliance system, clearly located in the radiograph and the mini-screw can be easily inserted through the guide reducing the chance of implant misplacement.

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

Science.gov (United States)

Hilley, Robert

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

Information booklet on personal protective equipment: eye and face protection

International Nuclear Information System (INIS)

1992-01-01

In all work places where hazards of various kinds are present and the same cannot be totally controlled by engineering methods, suitable personal protective equipment (PPE) shall be used. There are several types of eye and face protection devices available in the market and it is important that employees use the proper type for the particular job. The main classes of eye and face protection devices required for the industrial operations are as follows: (a) eye protection devices which includes: (i) safety goggles (ii) safety spectacles (iii) safety clipons and eye and face protection devices which are (i) eye shield, (ii) face shield, (iii) wire mesh screen guard. Guide lines for selecting appropriate ear and face protection equipment for nuclear installations are given. (M.K.V.). 4 annexures, 1 appendix

Spirit-guided care: Christian nursing for the whole person.

Science.gov (United States)

Murphy, Lyn S; Walker, Mark S

2013-01-01

Healthcare today is challenged to provide care that goes beyond the medical model of meeting physical needs. Despite a strong historical foundation in spiritual whole person care, nurses struggle with holistic caring. We propose that for the Christian nurse, holistic nursing can be described as Spirit-guided care--removing oneself as the moiatiating force and allowing Christ, in the furm of the Holy Spirit, to flow through and guide the nurse in care of patients and families.

[Markers of dental children`s health in the application of therapeutic orthodontic equipment].

Science.gov (United States)

Пачевська, Аліса В; Білошицька, Аліна В

Treatment of teeth anomalies using removable and non-removable orthodontic devices in children leads to complications such as caries, gingivitis, periodontitis, oral mucosa hyperplasia. Etiopathogenetical of these diseases can be associated with biochemical changes in the composition of saliva. To determine the activity of lysozyme and amylase in oral fluid in children when using a fixed and removable orthodontic devices. Amylase and lysozyme were studied in oral fluid. Analyzed the biochemical composition of the freshly samples of oral fluid that was obtained in the control, experimental group 1 and 2 (children ages 7-18 years, which were used medical non-removable and removable orthodontic devices). Saliva was collected at the beginning of the therapeutic use of orthodontic devices (the first day of treatment), on 3 and 6 months of treatment. Assessment of lysozyme activity was carried nephelometric method on the ability of lysozyme to dissolve indicator organism Micrococcus lysodeicticus. To construct a calibration graph using dry lysozyme company Sigma. Salivary amylase activity was determined by hydrolysis of starch. The results were subjected to statistical analysis by standard methods. Data processed using software packages applied statistical analysis Statistica 6.0, Microsoft Excel, 2003. The use of a fixed and removable orthodontic equipment led to a decrease in saliva amylase, major changes are observed on the 6th month of treatment. The activity of lysozyme in saliva decreased the mostin patients with a permanent equipment. Major changes were also recorded on the 6th month of treatment. Complications of orthodontic treatment teeth anomalies in children (caries, gingivitis, periodontitis) caused by changes in the biochemical composition of saliva. For the prevention of the emergence and development of these complications is necessary to control the level of amylase and lysozyme in the mouth.

The use of small (2.7 mm) screws for arthroscopically guided repair of carpal chip fractures.

Science.gov (United States)

Wright, I M; Smith, M R W

2011-05-01

Removal of large chip fractures of the carpal bones and the osteochondral deficits that result, have been associated with a worse prognosis than removal of small fragments in similar locations. Reducing the articular defects by repair of large osteochondral fragments may have advantages over removal. Horses with osteochondral chip fractures that were of sufficient size and infrastructure to be repaired with small (2.7 mm diameter) AO/ASIF cortex screws were identified and repair effected by arthroscopically guided internal fixation. Thirty-three horses underwent surgery to repair 35 fractures of the dorsodistal radial carpal bone (n = 25), the dorsal margin of the radial facet of the third carpal bone (n = 9) and the intermediate facet of the distal radius (n = 1). There were no surgical complications and fractures healed satisfactorily in 26 of 28 horses and 23 horses returned to racing performance. Arthroscopically guided repair of carpal chip fractures with small diameter cortex screws is technically feasible and experiences with 33 cases suggest that this may have advantages over fragment removal in managing such cases. Surgeons treating horses with large chip fractures of the carpal bones should consider arthroscopically guided internal fixation as an alternative to removal. © 2010 EVJ Ltd.

Implications of NUREG-1150 for equipment qualification

International Nuclear Information System (INIS)

Siu, R.P.; Sarram, M.

1988-01-01

Current USNRC regulations in 10CFR50 requires that structures, systems and components important to safety in a nuclear power plant are to be designed to accommodate the effects of harsh environments associated with potential accidents. Detailed regulatory requirements are as discussed in Regulatory Guide 1.89. Some of these regulatory requirements have been based upon rather outdated understanding of the phenomenology of severe accidents -- e.g., the radiation source terms for equipment qualification can be traced to TID-14844 which was originally published in 1962. Furthermore, the definition of important-to-safety in these regulatory requirements is rather broad, usually resulting in a long Q-list of equipment to be qualified for the design-basis Large LOCA. In the past few years, extensive research/analysis on severe accidents have been conducted -- from the IREP/NREP activities, the IDCOR programs, to the NUREG-1150 efforts. This paper reports that as a result of all these PRA-related activities, a much-improved understanding of the phenomenology and environmental conditions associated with severe accidents has been gained

Ontario hydro radioactive material transportation field guide

International Nuclear Information System (INIS)

Howe, W.

1987-01-01

The recent introduction of both the AECB Transport Packaging of Radioactive Material Regulations and Transport Canada's Transportation of Dangerous Goods Regulations have significantly altered the requirements for transporting radioactive material in Canada. Extensive additional training as well as certification of several hundred Ontario Hydro employees has been necessary to ensure compliance with the additional and revised regulatory requirements. To assist in the training of personnel, an 'active' corporate Ontario Hydro Field Guide for Radioactive Material Transport document has been developed and published. The contents of this Field Guide identify current Ontario Hydro equipment and procedures as well as the updated relevant regulatory requirements within Canada. In addition, to satisfying Ontario Hydro requirements for this type of information over two thousand of these Field Guides have been provided to key emergency response personnel throughout the province of Ontario to assist in their transportation accident response training

Influence of Removable Devices' Heterouse on the Propagation of Malware

Directory of Open Access Journals (Sweden)

Xie Han

2013-01-01

Full Text Available The effects of removable devices’ heterouse in different areas on the propagation of malware spreading via removable devices remain unclear. As a result, in this paper, we present a model incorporating the heterogeneous use of removable devices, obtained by dividing the using rate into local area’s rate, neighbour area’s rate and global area’s rate, and then getting the final rate by multiplying the corresponding area ratio. The model’s equilibria and their stability conditions are obtained mathematically and verified by deterministic and stochastic simulations. Simulation results also indicate that the heterogeneity in using rate significantly changes the prospective propagation course of malware. Additionally, the thresholds of removable devices’ using rate in neighbour area are given, which can guide us in designing effective countermalware method.

Magnetic Field Measurements in Beam Guiding Magnets

CERN Document Server

Henrichsen, K N

1998-01-01

Electromagnets used as beam guiding elements in particle accelerators and colliders require very tight tole-rances on their magnetic fields and on their alignment along the particle path. This article describes the methods and equipment used for magnetic measurements in beam transport magnets. Descriptions are given of magnetic resonance techniques, various induction coil methods, Hall generator measurements, the fluxgate magnetometer as well as the recently developed method of beam based alignment. References of historical nature as well as citations of recent work are given. The present commercial availability of the different sensors and asso-ciated equipment is indicated. Finally we shall try to analyze possible future needs for developments in those fields.

Acceptance of the institutions and the organs of inspection for the nuclear under pressure equipment

International Nuclear Information System (INIS)

2006-05-01

The candidate companies in the acceptance have to justify their competence in inspection on one hand, in nuclear pressure equipment on the other hand. The guide defines the conditions of the acceptance (competence and modes of proof), the contents of the demand of acceptance, the procedure of instruction as well as the conditions of the preservation of the acceptance. The general direction of the nuclear safety and the radiation protection implements the control of the companies and the organs of inspection for their activities in nuclear equipment under pressure. (N.C.)

Radio-guided occult lesion localisation using iodine-125 seeds ('ROLLIS') for removal of impalpable breast lesions: first Australian experience

International Nuclear Information System (INIS)

Taylor, Donna B.; Bourke, Anita G.; Westcott, Eliza

2015-01-01

Approximately one-third of breast cancers are impalpable and require pre-operative image-guided localisation. Hook-wire localisation (HWL) is commonly used but has several disadvantages. Use of a low-activity radioactive iodine-125 seed is a promising alternative technique used in the USA and the Netherlands. This pilot study describes the first use of this in Australia. In this prospective pilot study, 21 participants with biopsy-proven breast cancer underwent radio guided occult lesion localisation using iodine-125 seed(s) (ROLLIS) with insertion of a hook-wire for back up. Sentinel node biopsy was performed where indicated. Ease of hook-wire and seed insertion, duration of the procedure, dependence on the seed versus hook-wire during surgery, lesion location within the specimen, histopathology including size of radial margins, the ease of seed retrieval in pathology, and safe return of seeds for disposal were documented. Radiation dosimetry of staff was performed. All seeds were placed within 3.5 mm of the lesion. All lesions and seeds were removed. One participant needed re-excision for involved margins. Radiologists and surgeons both preferred ROLLIS. Surgeons were able to depend on the seed for localisation in all but one case. Sentinel node biopsy was successfully performed when required. Pathologists found seed retrieval quick and easy, with no detrimental effect on tissue processing. No radiation doses measurably above background were received by staff. ROLLIS is an easily learnt, safe and effective alternative technique to standard HWL.

Technical basis for removal of 221-T tunnel from airborne radiological area status

International Nuclear Information System (INIS)

Geuther, W.J.

1996-01-01

This document provides the technical basis for removal of the 221-T Tunnel from airborne radiological control. T Plant Radiological Control has evaluated air sampling data and engineering controls, and determined the necessary administrative controls to make this transition. With these administrative controls (specified within document) in place, the tunnel can be removed from Airborne Radioactive Area status. The removal of the tunnel from airborne status will allow work to be performed within the tunnel under controlled conditions, as outlined in this technical basis, without the use of respiratory protection equipment

A new guide of mechanical engineering

International Nuclear Information System (INIS)

1993-01-01

This book introduces a new guide of mechanical engineering which deals with basic thing such as mathematical formula, dynamics, material dynamics, industrial materials, machine design like screws and rivets, gears and springs, the method of machine such as drilling machine and its work, planar, shaper and slotter and their work, honing and super finishing machine and their work, measuring of machine, test and machine, hydraulics and hydraulic machine and telecommunication equipment and automation.

Removal of radionuclides from household water

International Nuclear Information System (INIS)

Vesterbacka, P.; Turtiainen, T.; Haemaelaeinen, K.; Salonen, L.; Arvela, H.

2003-10-01

than larger particles. Testing simultaneous removal of radon, iron and magnesium by two commercial devices gave promising results: radon removal efficiency was over 98%. Furthermore, it was found that certain fluoride removal equipment can be applied to simultaneous removal of uranium, radium, lead and polonium. This research has been funded by the National Technology Agency of Finland (TEKES). (orig.)

Electric Ground Support Equipment at Airports

Energy Technology Data Exchange (ETDEWEB)

2017-12-12

Airport ground support equipment (GSE) is used to service airplanes between flights. Services include refueling, towing airplanes or luggage/freight carts, loading luggage/freight, transporting passengers, loading potable water, removing sewage, loading food, de-icing airplanes, and fire-fighting. Deploying new GSE technologies is a promising opportunity in part because the purchasers are generally large, technologically sophisticated airlines, contractors, or airports with centralized procurement and maintenance departments. Airlines could particularly benefit from fuel diversification since they are highly exposed to petroleum price volatility. GSE can be particularly well-suited for electrification because it benefits from low-end torque and has frequent idle time and short required ranges.

Optimum Remediation Conditions of Vertical Electrokinetic-Flushing Equipment to Decontaminate a Radioactive Soil

International Nuclear Information System (INIS)

Kim, Gye Nam; Yang, Byeong IL; Moon, Jei Kwon; Lee, Kune Woo

2009-01-01

Vertical electrokintic-flushing remediation equipment was developed for the remediation of a radioactive soil near nuclear facilities. An optimum reagent was selected to decontaminate the radioactive soil near nuclear facilities with the developed vertical electrokintic-flushing remediation equipment, and the optimum remediation conditions were established to obtain a higher remediation efficiency. Namely, acetic acid was selected as an optimum reagent due to its higher remediation efficiency. When the electrokinetic remediation and the electrokinetic-flushing remediation results were compared, the removal efficiency of 4.6% and the soil waste solution volume of 1.5 times were increased in the electrokinetic remediation. When the potential gradient within an electrokinetic soil cell was increased by two times (4.0 V/cm), the removal efficiencies of Co 2+ and Cs + were increased by about 4.3%( Co 2+ : 98.9%, Cs + : 96.7%). Also, when the reagent concentration was increased from 0.01 M to 0.05 M, the removal efficiency of Co 2+ was increased but that of Cs + was decreased. Therefore, the optimum remediation conditions were that the acetic concentration was 0.01 M ∼ 0.05 M, the potential gradient was 4 V/cm, the injection of reagent 2.4 ml/g, and the remediation period was 20 days.

Low Temperature Catalyst for NH3 Removal

Science.gov (United States)

Monje, Oscar; Melendez, Orlando

2013-01-01

Air revitalization technologies maintain a safe atmosphere inside spacecraft by the removal of C02, ammonia (NH3), and trace contaminants. NH3 onboard the International Space Station (ISS) is produced by crew metabolism, payloads, or during an accidental release of thermal control refrigerant. Currently, the ISS relies on removing NH3 via humidity condensate and the crew wears hooded respirators during emergencies. A different approach to cabin NH3 removal is to use selective catalytic oxidation (SCO), which builds on thermal catalytic oxidation concepts that could be incorporated into the existing TCCS process equipment architecture on ISS. A low temperature platinum-based catalyst (LTP-Catalyst) developed at KSC was used for converting NH3 to H20 and N2 gas by SCO. The challenge of implementing SCO is to reduce formation of undesirable byproducts like NOx (N20 and NO). Gas mixture analysis was conducted using FTIR spectrometry in the Regenerable VOC Control System (RVCS) Testbed. The RVCS was modified by adding a 66 L semi-sealed chamber, and a custom NH3 generator. The effect of temperature on NH3 removal using the LTP-Catalyst was examined. A suitable temperature was found where NH3 removal did not produce toxic NO, (NO, N02) and N20 formation was reduced.

Helmet and shoulder pad removal in football players with unstable cervical spine injuries.

Science.gov (United States)

Dahl, Michael C; Ananthakrishnan, Dheera; Nicandri, Gregg; Chapman, Jens R; Ching, Randal P

2009-05-01

Football, one of the country's most popular team sports, is associated with the largest overall number of sports-related, catastrophic, cervical spine injuries in the United States (Mueller, 2007). Patient handling can be hindered by the protective sports equipment worn by the athlete. Improper stabilization of these patients can exacerbate neurologic injury. Because of the lack of consensus on the best method for equipment removal, a study was performed comparing three techniques: full body levitation, upper torso tilt, and log roll. These techniques were performed on an intact and lesioned cervical spine cadaveric model simulating conditions in the emergency department. The levitation technique was found to produce motion in the anterior and right lateral directions. The tilt technique resulted in motions in the posterior left lateral directions, and the log roll technique generated motions in the right lateral direction and had the largest amount of increased instability when comparing the intact and lesioned specimen. These findings suggest that each method of equipment removal displays unique weaknesses that the practitioner should take into account, possibly on a patient-by-patient basis.

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

Riser equipment decontamination engineering task plan; TOPICAL

International Nuclear Information System (INIS)

BOGER, R.M.

1999-01-01

On October 15, 1998, two Characterization Project Operations (CPO) employees were found to have contaminated clothing. An operator had 300,000-dpm/100cm2 beta/gamma, no alpha, contamination on his coat sleeve and a Radiation Control Technician (RCT) had 10,000 dpm/100cm2 beta/gamma, no alpha, on his shirt sleeve. The CPO swing shift crew was working in TX tank farm, performing sampling activities at 241-TX-113. TX tank farm is a ''clean farm'' and does not require anti-contamination clothing for entry. The CPO personnel were dressed in normal work clothes. An operator and an RCT were performing a pre-job survey that involved removing bagging around the riser equipment. When the RCT saw that the contamination readings from smear samples of the riser equipment were greater than expected, the job was suspended. Crew members were then directed to areas of lower background radiation for personnel surveys. During personnel surveys, reportable contamination was found on the coat sleeve of the operator who had been involved in the pre-job survey and on the shirt sleeve of the RCT who had been involved in the pre-job survey. No other personnel were found to be contaminated. Because of this off normal event Characterization Engineering was given the following corrective action: Examine the process methodology used for core sampling operations to determine practicality and potential long-term advantages of reducing personnel contact with contaminated equipment. This Engineering Task Plan ensures that LMHC 1998a, Corrective Action No.7 is completely addressed by Characterization Engineering. The deliverable is an Engineering Study that evaluates decontamination of riser equipment components and considers additional engineered features to reduce potential exposure to workers operating the riser equipment. This engineering study shall also address any released design features that have failed to be implemented

Seismic design of equipment and piping systems for nuclear power plants in Japan

International Nuclear Information System (INIS)

Minematsu, Akiyoshi

1997-01-01

The philosophy of seismic design for nuclear power plant facilities in Japan is based on 'Examination Guide for Seismic Design of Nuclear Power Reactor Facilities: Nuclear Power Safety Committee, July 20, 1981' (referred to as 'Examination Guide' hereinafter) and the present design criteria have been established based on the survey of governmental improvement and standardization program. The detailed design implementation procedure is further described in 'Technical Guidelines for Aseismic Design of Nuclear Power Plants, JEAG4601-1987: Japan Electric Association'. This report describes the principles and design procedure of the seismic design of equipment/piping systems for nuclear power plant in Japan. (J.P.N.)

Seismic design of equipment and piping systems for nuclear power plants in Japan

Energy Technology Data Exchange (ETDEWEB)

Minematsu, Akiyoshi [Tokyo Electric Power Co., Inc. (Japan)

1997-03-01

The philosophy of seismic design for nuclear power plant facilities in Japan is based on `Examination Guide for Seismic Design of Nuclear Power Reactor Facilities: Nuclear Power Safety Committee, July 20, 1981` (referred to as `Examination Guide` hereinafter) and the present design criteria have been established based on the survey of governmental improvement and standardization program. The detailed design implementation procedure is further described in `Technical Guidelines for Aseismic Design of Nuclear Power Plants, JEAG4601-1987: Japan Electric Association`. This report describes the principles and design procedure of the seismic design of equipment/piping systems for nuclear power plant in Japan. (J.P.N.)

Performance Enhancement of the In-Line Fan Equipped with the Guiding Vane and the Tail Body

Directory of Open Access Journals (Sweden)

Hung-Cheng Yen

2014-02-01

Full Text Available This integrated numerical and experimental study intends to enhance the performance of an in-line fan with the implement of the guiding vane and the tail body. At first the flow flied associated with the original in-line fan is simulated and analyzed within the framework of CFD code Fluent, in which the finite volume method is applied. Next, the guiding vane is constructed based on the calculated flow characteristics, and attached in the downstream of rotor to smoothen the flow pattern. An appropriate guiding vane with high-performance and low-noise features can be achieved after several design iterations. In addition, the tail body connected to the motor is introduced for further enhancing the fan performance by reducing the sizes of wake and reversed flow behind the hub. Thereafter, to manufacture the mockup for experimental verification, the modified fan with guiding vane is plotted in the CAD/CAM format for mockup fabrication via the rapid-prototype technique. Moreover, a set of relations correlating the performance and noise of this fan prototype are executed inside AMCA test chamber and semianechoic chamber, respectively. Consequently, the feasibility of design scheme and numerical system can be verified according to these experimental results. In summary, this work provides a systematic scheme for designing and analyzing the in-line fan.

Decontamination of the Scrap Removal Room at the West Valley Demonstration Project

International Nuclear Information System (INIS)

Bridenbaker, W.A.; Clemons, L.

1987-02-01

This report describes the decontamination and decommissioning (D and D) of the Scrap Removal Room (SRR) at the West Valley Demonstration Project (WVDP). The SRR is an area in the former reprocessing plant that is required for use in support of D and D for other plant areas. The SRR contained a 6.8 Mg (7.5-ton) crane for loading waste material into a shielded truck cask. It became radioactively contaminated during fuel reprocessing from 1966 to 1972. This report describes the work performed to accomplish the D and D objectives of removing existing piping and equipment and of reducing radiation and contamination levels, to As-Low-As-Reasonably-Achievable (ALARA) levels for the installation of new equipment. Also reported are pre- and post-radiological conditions, personnel exposure, radioactive waste volume collected, cost and schedule data, and lessons learned

Technical innovation: Wire guided ductography

International Nuclear Information System (INIS)

Aslam, Muhammad Ovais; Ramadan, Salwa; Al-Adwani, Muneera

2012-01-01

To introduce an easy and improved technique for performing ductography using inexpensive easily available intravenous cannula. Guide wire: Prolene/Surgipro 3-0 (Polypropylene mono filament non-absorbable surgical suture). A plastic 26 G intravenous cannula. Disposable syringe 2 ml. Non-ionic contrast (low density like Omnipaque 240 mg I/I). The guide wire (Prolene 3-0) is introduced into the orifice of the duct heaving discharge and 26 G intravenous plastic cannula is then passed over the guide wire. The cannula is advanced in the duct over guide wire by spinning around it. When the cannula is in place the guide wire is removed. Any air bubbles present in the hub of the cannula can be displaced by filling the hub from bottom upwards with needle attached to contrast filled syringe. 0.2–0.4 ml non-ionic contrast is gently injected. Injection is stopped if the patient has pain or burning. Magnified cranio-caudal view is obtained with cannula tapped in place and gentle compression is applied with the patient sitting. If duct filling is satisfactory a 90* lateral view is obtained. A successful adaptation of the technique for performing ductography is presented. The materials required for the technique are easily available in most radiology departments and are inexpensive, thus making the procedure comfortable for the patient and radiologist with considerable cost effectiveness.

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

Improving Efficiency with 3-D Imaging: Technology Essential in Removing Plutonium Processing Equipment from Plutonium Finishing Plant Gloveboxes

International Nuclear Information System (INIS)

Crow, Stephen H.; Kyle, Richard N.; Minette, Michael J.

2008-01-01

The Plutonium Finishing Plant at Hanford, Washington began operations in 1949 to process plutonium and plutonium products. Its primary mission was to produce plutonium metal, fabricate weapons parts, and stabilize reactive materials. These operations, and subsequent activities, were performed in remote production lines, consisting primarily of hundreds of gloveboxes. Over the years these gloveboxes and processes have been continuously modified. The plant is currently inactive and Fluor Hanford has been tasked to clean out contaminated equipment and gloveboxes from the facility so it can be demolished in the near future. Approximately 100 gloveboxes at PFP have been cleaned out in the past four years and about 90 gloveboxes remain to be cleaned out. Because specific commitment dates for this work have been established with the State of Washington and other entities, it is important to adopt work practices that increase the safety and speed of this effort. The most recent work practice to be adopted by Fluor Hanford D and D workers is the use of 3-D models to improve the efficiency of cleaning out radioactive gloveboxes at the plant. The use of 3-D models has significantly improved the work planning process by providing workers with a clear image of glovebox construction and composition, which is then used to determine cleanout methods and work sequences. The 3-D visual products enhance safety by enabling workers to more easily identify hazards and implement controls. In addition, the ability to identify and target the removal of radiological materials early in the D and D process provides substantial dose reduction for the workers

Experimental study on scale removal from special-shaped conduits through underwater electrical discharge

International Nuclear Information System (INIS)

Cao, Y; Wang, Z Q; Li, G F; Wu, Y; Zhou, J J

2013-01-01

Underwater electrical discharge technology is an innovative technique that can be used to enhance the stress intensity of water and improve the load addition. The technique enlarges the section area and compresses the surrounding water using a high-powered shock wave, which is induced by an underwater electrical discharge. This paper investigates the effectiveness of scale removal for special-shaped conduits employing underwater electrical discharge. Experimental results show that the pressure wave generated by underwater electrical discharge is capable of eliminating scale in special-shaped conduits. The data indicates that when the capacitance of the parallel-pulsed capacitors was 4 μF, the high pulsed power voltage was 33 kV and the primary discharge gap was 48 mm, the result of scale removal was remarkable. In laboratory tests, the scale of special equipment was removed to a great extent by this method. Because of its effectiveness and low cost, this method improves the practice and extends the lifetime of such equipment, and thus has potential application and economic value.

T Plant removal of PWR Chiller Subsystem

International Nuclear Information System (INIS)

Dana, C.M.

1994-01-01

The PWR Pool Chiller System is not longer required for support of the Shippingport Blanket Fuel Assemblies Storage. The Engineering Work Plan will provide the overall coordination of the documentation and physical changes to deactivate the unneeded subsystem. The physical removal of all energy sources for the Chiller equipment will be covered under a one time work plan. The documentation changes will be covered using approved Engineering Change Notices and Procedure Change Authorizations as needed

EFFICIENCY OF DOMESTIC REVERSE OSMOSIS IN REMOVAL OF TRIHALOMETHANES FROM DRINKING WATER

Directory of Open Access Journals (Sweden)

S. Mazloomi ، R. Nabizadeh ، S. Nasseri ، K. Naddafi ، S. Nazmara ، A. H. Mahvi

2009-10-01

Full Text Available The reaction of disinfectants with natural organic matters existing in water lead to the formation of Disinfection By-Products. Potentially hazardous and carcinogenic characteristics of trihalomethanes (THMs are recognized. Thus removal of THMs or its precursors are necessary for human health. The aim of this study was to study the efficiency of domestic reverse osmosis (RO in removal of trihalomethanes from drinking water. A pilot scale of RO system with Polyamide membrane as Spiral-Wound, Tape wrapping module was used. Feed solution was made by using of pure chloroform. The samples containing chloroform were analyzed using a gas chromatograph equipped with a flame ionization detector. By increasing the flow, the removal rate of chloroform decreased and with declining removal of EC, the removal of chloroform declined too. In this research, at the worst condition, the efficiency of the pilot scale reverse osmosis reached to 80 % removal of chloroform.

Managing EHS of PV-Related Equipment at the National Renewable Energy Laboratory: Preprint

Energy Technology Data Exchange (ETDEWEB)

McCuskey, T.; Nelson, B. P.

2012-06-01

Managing environment, health, and safety (EHS) risks at a national laboratory, or university, can be intimidating to a researcher who is focused on research results. Laboratory research and development (R&D) operations are often driven by scientists with limited engineering support and lack well-refined equipment development resources. To add to the burden for a researcher, there is a plethora of codes, standards, and regulations that govern the safe installation and operation of photovoltaic-related R&D equipment -- especially those involving hazardous production materials. To help guide the researcher through the vast list of requirements, the EHS office at NREL has taken a variety of steps. Organizationally, the office has developed hazard-specific laboratory-level procedures to govern particular activities. These procedures are a distillation of appropriate international codes, fire agencies, SEMI standards, U.S. Department of Energy orders, and other industry standards to those necessary and sufficient to govern the safe operation of a given activity. The EHS office works proactively with researchers after a concept for a new R&D capability is conceived to help guide the safe design, acquisition, installation, and operation of the equipment. It starts with a safety assessment at the early stages such that requirements are implemented to determine the level of risk and degree of complexity presented by the activity so appropriate controls can be put in place to manage the risk. As the equipment requirements and design are refined, appropriate equipment standards are applied. Before the 'to-build' specifications are finalized, a process hazard analysis is performed to ensure that no single-point failure presents an unacceptable risk. Finally, as the tool goes through construction and installation stages, reviews are performed at logical times to ensure that the requisite engineering controls and design are in place and operational. Authorization to

Uranium enrichment export control guide: Gaseous diffusion

Energy Technology Data Exchange (ETDEWEB)

1989-09-01

This document was prepared to serve as a guide for export control officials in their interpretation, understanding, and implementation of export laws that relate to the Zangger International Trigger List for gaseous diffusion uranium enrichment process components, equipment, and materials. Particular emphasis is focused on items that are especially designed or prepared since export controls are required for these by States that are party to the International Nuclear Nonproliferation Treaty.

Passive heat removal characteristics of SMART

Energy Technology Data Exchange (ETDEWEB)

Seo, Jae Kwang; Kang, Hyung Seok; Yoon, Joo Hyun; Kim, Hwan Yeol; Cho, Bong Hyun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1998-12-31

A new advanced integral reactor of 330 MWt thermal capacity named SMART (System-Integrated Modular Advanced Reactor) is currently under development in Korea Atomic Energy Research Institute (KAERI) for multi-purpose applications. Modular once-through steam generator (SG) and self-pressurizing pressurizer equipped with wet thermal insulator and cooler are essential components of the SMART. The SMART provides safety systems such as Passive Residual Heat Removal System (PRHRS). In this study, a computer code for performance analysis of the PRHRS is developed by modeling relevant components and systems of the SMART. Using this computer code, a performance analysis of the PRHRS is performed in order to check whether the passive cooling concept using the PRHRS is feasible. The results of the analysis show that PRHRS of the SMART has excellent passive heat removal characteristics. 2 refs., 4 figs., 1 tab. (Author)

Bioprocess design guided by in situ substrate supply and product removal: process intensification for synthesis of (S)-1-(2-chlorophenyl)ethanol.

Science.gov (United States)

Schmölzer, Katharina; Mädje, Katharina; Nidetzky, Bernd; Kratzer, Regina

2012-03-01

We report herein on bioprocess development guided by the hydrophobicities of substrate and product. Bioreductions of o-chloroacetophenone are severely limited by instability of the catalyst in the presence of aromatic substrate and (S)-1-(2-chlorophenyl)ethanol. In situ substrate supply and product removal was used to protect the utilized Escherichia coli whole cell catalyst based on Candida tenuis xylose reductase during the reaction. Further engineering at the levels of the catalyst and the reaction media was matched to low substrate concentrations in the aqueous phase. Productivities obtained in aqueous batch reductions were 21-fold improved by addition of 20% (v/v) hexane, NAD(+), expression engineering, cell permeabilization and pH optimization. Reduction of 300 mM substrate was accomplished in 97% yield and use of the co-solvent hexane in subsequent extraction steps led to 88% recovery. Product loss due to high catalyst loading was minimized by using the same extractant in bioreduction and product isolation. Copyright © 2012 Elsevier Ltd. All rights reserved.

Safety evaluation for packaging transportation of equipment for tank 241-C-106 waste sluicing system

International Nuclear Information System (INIS)

Calmus, D.B.

1994-01-01

A Waste Sluicing System (WSS) is scheduled for installation in nd waste storage tank 241-C-106 (106-C). The WSS will transfer high rating sludge from single shell tank 106-C to double shell waste tank 241-AY-102 (102-AY). Prior to installation of the WSS, a heel pump and a transfer pump will be removed from tank 106-C and an agitator pump will be removed from tank 102-AY. Special flexible receivers will be used to contain the pumps during removal from the tanks. After equipment removal, the flexible receivers will be placed in separate containers (packagings). The packaging and contents (packages) will be transferred from the Tank Farms to the Central Waste Complex (CWC) for interim storage and then to T Plant for evaluation and processing for final disposition. Two sizes of packagings will be provided for transferring the equipment from the Tank Farms to the interim storage facility. The packagings will be designated as the WSSP-1 and WSSP-2 packagings throughout the remainder of this Safety Evaluation for Packaging (SEP). The WSSP-1 packagings will transport the heel and transfer pumps from 106-C and the WSSP-2 packaging will transport the agitator pump from 102-AY. The WSSP-1 and WSSP-2 packagings are similar except for the length

105-N Basin sediment removal subcontract acquisition strategy plan

International Nuclear Information System (INIS)

Wilsey, D.J.

1997-01-01

The 105-N Basin Sediment Removal Subcontract Acquisition Strategy Plan provides a detailed set of actions to specify and procure services and equipment for removal of approximately 400 ft 3 (wet) of radioactive sediment. The plan outlines a cost-effective approach to remove this sediment safely and within an aggressive schedule. This 105-N Basin Sediment Removal Strategy Plan includes the following key elements: a current vendor survey of capabilities and interest in this type of work, confirming that qualified, competitive sources are available, and in the time frame required; a systematic review of the various options for sediment disposal in enough detail to exhaustively uncover pros and cons of each approach; use of a workshop approach to assess different ways to accomplish the work and ensure the disposal options considered are cost and schedule effective; integration of the complicated sampling and characterization process, which is essential to successful execution of the procurement scheme; review of the various subcontracting options to maximize the use of existing technology, existing equipment, and specialized expertise; detailed early planning and strategizing for early identification of problems that can be solved early before they become restraints or potential added costs; tailored design schedule to cover three alternate approaches so that sample characterization will not delay engineering preparation for disposal; support required from various organizations onsite as well as subcontractors, well in advance of the need for that support, improving availability of the proper personnel to support schedule and cost objectives; and provides the possible opportunity to process the sediment in the valve pit and pump pit through this same subcontractor's process

Development of floor design response spectra for seismic design of floor-supported equipment or components, Revision 1, February 1978

International Nuclear Information System (INIS)

Anon.

1979-01-01

This guide presents an acceptable method for developing two horizontal and one vertical floor design response spectra at various floor or other equipment-support locations from the time-history motions resulting from the dynamic analysis of the supporting structure. These floor design response spectra are used in the dynamic analysis of systems or equipment supported at various locations of the supporting structure. Consulation has been provided by the Advisory Committee on Reactor Safeguards

Guided Modern Endodontic Surgery: A Novel Approach for Guided Osteotomy and Root Resection.

Science.gov (United States)

Strbac, Georg D; Schnappauf, Albrecht; Giannis, Katharina; Moritz, Andreas; Ulm, Christian

2017-03-01

Continuous improvements in techniques, instruments, and materials have established modern endodontic microsurgery as a state-of-the-art treatment method. The purpose of this approach was to introduce a new surgical endodontic technique by using a three-dimensional printed template for guided osteotomy and root resection. A 38-year-old patient was diagnosed with periapical lesions of teeth #3 and #4 and extruded gutta-percha material. Three-dimensional radiographic and optical scan files were imported into surgical planning software designed for guided implant surgery. Within the adapted software program the periapical lesions and the extruded gutta-percha were visualized and marked. With the aid of virtually positioned surgical pins and piezoelectric instruments, the osteotomy size, the apical resection level, and the bevel angle were defined before treatment. Three-dimensional surgical templates for each tooth were designed within the software program for a guided treatment approach. This approach comprised the treatment of periapical lesions of teeth #3 and #4 with root-end fillings and the detection and complete removal of the extruded gutta-percha material without perforation of sinus membrane. There were no postoperative complications, and clinical and radiologic assessments verified complete healing of the teeth. The guided microsurgical endodontic treatment presented appears to be a viable technique that allows for predefined osteotomies and root resections. Copyright © 2016 American Association of Endodontists. Published by Elsevier Inc. All rights reserved.

Water harvesting and soil moisture retention: A study guide for farmer field schools

OpenAIRE

Duveskog, D.

2001-01-01

Metadata only record Since a majority of individuals in Sub-Saharan Africa depend on rainfed agriculture, it is necessary to provide tools that will better equip these individuals to increase their yields and improve their farming techniques. This study guide is intended to assist farmers in learning and experimenting on improved soil and water management. The target groups for the study guide are Farmer Field Schools, village farmers groups and local agricultural extension staff. Avail...

Course of Study for Electronic Music I. An Instructional Guide.

Science.gov (United States)

Montgomery County Public Schools, Rockville, MD. Dept. of Curriculum and Instruction.

The booklet is a guide for music teachers and administrators who wish to incorporate electronic music into the junior or senior high curriculum. It defines program objectives and suggests goals, teaching strategies, materials, and equipment. Reasons for teaching electronic music include its popularity with the younger generation, its capability to…

Wall thinning inspection technique for large-diameter piping using guided wave

International Nuclear Information System (INIS)

Miki, Masahiro; Nagashima, Yoshiaki; Endou, Masao; Kodaira, Kojiro; Maniwa, Kazuhiko

2009-01-01

Guided wave inspection technique is effective for detecting defects like corrosion in piping, because it can perform long range inspection. It is possible to expect this inspection as a method that leads to the decrease of the inspection process and its cost, because the incidental work can be reduced. Especially, the contraction effect of the inspection work is extensive in large-diameter piping inspection. In this paper, we introduce the guided wave inspection system to large-diameter piping. The feature is a guided wave sensor that can freely transform according to the curvature of inspection object, and portable inspection equipment. We discuss the result of detection examination for artificial wall-thinning in large-diameter piping using this system. (author)

Glance traceability – Web system for equipment traceability and radiation monitoring for the ATLAS experiment

CERN Document Server

Ramos de Azevedo Evora, L H; Pommes, K; Galvão, K K; Maidantchik, C

2010-01-01

During the operation, maintenance, and dismantling periods of the ATLAS Experiment, the traceability of all detector equipment must be guaranteed for logistic and safety matters. The running of the Large Hadron Collider will expose the ATLAS detector to radiation. Therefore, CERN must follow specific regulations from both the French and Swiss authorities for equipment removal, transport, repair, and disposal. GLANCE Traceability, implemented in C++ and Java/Java3D, has been developed to fulfill the requirements. The system registers and associates each equipment part to either a functional position in the detector or a zone outside the underground area through a 3D graphical user interface. Radiation control of the equipment is performed using a radiation monitor connected to the system: the local background gets stored and the threshold is automatically calculated. The system classifies the equipment as non radioactive if its radiation dose does not exceed that limit value. History for both location traceabi...

Decontamination and Decommissioning Equipment Tracking System (DDETS)

International Nuclear Information System (INIS)

Cook, S.

1994-07-01

At the request of the Department of Energy (DOE)(EM-50), the Scientific Computing Unit developed a prototype system to track information and data relevant to equipment and tooling removed during decontamination and decommissioning activities. The DDETS proof-of-concept tracking system utilizes a one-dimensional (1D) and two-dimensional (2D) bar coding technology to retain and track information such as identification number, manufacturer, requisition information, and various contaminant information, etc. The information is encoded in a bar code, printed on a label and can be attached to corresponding equipment. The DDETS was developed using a proven relational database management system which allows the addition, modification, printing, and deletion of data. In addition, communication interfaces with bar code printers and bar code readers were developed. Additional features of the system include: (a) Four different reports available for the user (REAPS, transaction, and two inventory), (b) Remote automated inventory tracking capabilities, (c) Remote automated inventory tracking capability (2D bar codes allow equipment to be scanned/tracked without being linked to the DDETS database), (d) Edit, update, delete, and query capabilities, (e) On-line bar code label printing utility (data from 2D bar codes can be scanned directly into the data base simplifying data entry), and (f) Automated data backup utility. Compatibility with the Reportable Excess Automated Property System (REAPS) to upload data from DDETS is planned

Treatment techniques for removing natural radionuclides from drinking water. Final report of the TENAWA project

International Nuclear Information System (INIS)

Annanmaeki, M.; Turtiainen, T.

2000-01-01

TENAWA project (Treatment Techniques for Removing Natural Radionuclides from Drinking Water) was carried out on a cost-shared basic with the European Commission (CEC) under the supervision of Directorate-General XII, Radiation Protection Unit. TENAWA project was started because in several European countries ground water supplies may contain high amounts of natural radionuclides. During the project both laboratory and field research was performed in order to test the applicability of different equipment and techniques for removing natural radionuclides from drinking water. The measurable objectives of the project were: to give recommendations on the most suitable methods for removing radon ( 222 Rn), uranium ( 238,234 U), radium ( 226 , 228 Ra), lead ( 210 Pb) and polonium ( 210 Po) from drinking water of different qualities (i.e. soft, hard, iron-, manganese- and humus-rich, acidic) to test commercially available equipment for its ability to remove radionuclides; to find new materials, absorbents and membranes effective in the removal of radionuclides and to issue guidelines for the treatment and disposal of radioactive wastes produced in water treatment. Radon could be removed efficiently (>95%) from domestic water supplies by both aeration and granular activated carbon (GAC) filtration. Defects in technical reliability or radon removal efficiency were observed in some aerators. The significant drawback of GAC filtration was the elevated gamma dose rates (up to 120 μSv/h) near the filter and the radioactivity of spent GAC. Aeration was found to be a suitable method for removing radon at waterworks, too. The removal efficiencies at waterworks where the aeration process was designed to remove radon or carbon dioxide were 67-99%. If the aeration process was properly designed, removal efficiencies higher than 95% could be attained. Uranium could best be removed (>95%) with strong basic anion exchange resins and radium by applying strong acidic cation exchange resins

Treatment techniques for removing natural radionuclides from drinking water. Final report of the TENAWA project

Energy Technology Data Exchange (ETDEWEB)

Annanmaeki, M.; Turtiainen, T. [eds.

2000-01-01

TENAWA project (Treatment Techniques for Removing Natural Radionuclides from Drinking Water) was carried out on a cost-shared basic with the European Commission (CEC) under the supervision of Directorate-General XII, Radiation Protection Unit. TENAWA project was started because in several European countries ground water supplies may contain high amounts of natural radionuclides. During the project both laboratory and field research was performed in order to test the applicability of different equipment and techniques for removing natural radionuclides from drinking water. The measurable objectives of the project were: to give recommendations on the most suitable methods for removing radon ({sup 222}Rn), uranium ({sup 238,234}U), radium ({sup 226}, {sup 228}Ra), lead ({sup 210}Pb) and polonium ({sup 210}Po) from drinking water of different qualities (i.e. soft, hard, iron-, manganese- and humus-rich, acidic) to test commercially available equipment for its ability to remove radionuclides; to find new materials, absorbents and membranes effective in the removal of radionuclides and to issue guidelines for the treatment and disposal of radioactive wastes produced in water treatment. Radon could be removed efficiently (>95%) from domestic water supplies by both aeration and granular activated carbon (GAC) filtration. Defects in technical reliability or radon removal efficiency were observed in some aerators. The significant drawback of GAC filtration was the elevated gamma dose rates (up to 120 {mu}Sv/h) near the filter and the radioactivity of spent GAC. Aeration was found to be a suitable method for removing radon at waterworks, too. The removal efficiencies at waterworks where the aeration process was designed to remove radon or carbon dioxide were 67-99%. If the aeration process was properly designed, removal efficiencies higher than 95% could be attained. Uranium could best be removed (>95%) with strong basic anion exchange resins and radium by applying strong

Feasibility of turbidity removal by high-gradient superconducting magnetic separation.

Science.gov (United States)

Zeng, Hua; Li, Yiran; Xu, Fengyu; Jiang, Hao; Zhang, Weimin

2015-01-01

Several studies have focused on pollutant removal by magnetic seeding and high-gradient superconducting magnetic separation (HGSMS). However, few works reported the application of HGSMS for treating non-magnetic pollutants by an industrial large-scale system. The feasibility of turbidity removal by a 600 mm bore superconducting magnetic separation system was evaluated in this study. The processing parameters were evaluated by using a 102 mm bore superconducting magnetic separation system that was equipped with the same magnetic separation chamber that was used in the 600 mm bore system. The double-canister system was used to process water pollutants. Analytical grade magnetite was used as a magnetic seed and the turbidity of the simulated raw water was approximately 110 NTU, and the effects of polyaluminum chloride (PAC) and magnetic seeds on turbidity removal were evaluated. The use of more PAC and magnetic seeds had few advantages for the HGSMS at doses greater than 8 and 50 mg/l, respectively. A magnetic intensity of 5.0 T was beneficial for HGSMS, and increasing the flow rate through the steel wool matrix decreased the turbidity removal efficiency. In the breakthrough experiments, 90% of the turbidity was removed when 100 column volumes were not reached. The processing capacity of the 600 mm bore industry-scale superconducting magnetic separator for turbidity treatment was approximately 78.0 m(3)/h or 65.5 × 10(4) m(3)/a. The processing cost per ton of water for the 600 mm bore system was 0.1 $/t. Thus, the HGSMS separator could be used in the following special circumstances: (1) when adequate space is not available for traditional water treatment equipment, especially the sedimentation tank, and (2) when decentralized sewage treatment HGSMS systems are easier to transport and install.

Computer-guided laser for neurosurgery.

Science.gov (United States)

Koivukangas, J; Louhisalmi, Y

1990-01-01

On the basis of over 40 neurosurgical laser operations, including CO2, Nd-YAG and simultaneous CO2/Nd-YAG laser procedures, a computer-guided system for spatial control of the laser beam has been developed. The pilot laser has several modes: it can direct the neurosurgeon along the central axis of the surgical microscope to stereotactically determined point-like targets or outline selected layers of underlying volume targets onto superficial surfaces such as scalp and cortex and onto the tissue at the appropriate depth. The active treatment laser can be guided by preoperative CT/MRI or intraoperative ultrasound image data for layer-by-layer resection of tumor. The laser system can be connected to the surgical field by rigid stereotactic means or by neuronavigator. In the present system, a special brain surgery adapter coordinates the imaging system and laser to the surgical field. Thus, the laser system can be used for image-guided surgical orientation, for demarcation of lesions and for actual layer-by-layer removal of tumor.

SLOPE STABILITY EVALUATION AND EQUIPMENT SETBACK DISTANCES FOR BURIAL GROUND EXCAVATIONS

Energy Technology Data Exchange (ETDEWEB)

MCSHANE DS

2010-03-25

After 1970 Transuranic (TRU) and suspect TRU waste was buried in the ground with the intention that at some later date the waste would be retrieved and processed into a configuration for long term storage. To retrieve this waste the soil must be removed (excavated). Sloping the bank of the excavation is the method used to keep the excavation from collapsing and to provide protection for workers retrieving the waste. The purpose of this paper is to document the minimum distance (setback) that equipment must stay from the edge of the excavation to maintain a stable slope. This evaluation examines the equipment setback distance by dividing the equipment into two categories, (1) equipment used for excavation and (2) equipment used for retrieval. The section on excavation equipment will also discuss techniques used for excavation including the process of benching. Calculations 122633-C-004, 'Slope Stability Analysis' (Attachment A), and 300013-C-001, 'Crane Stability Analysis' (Attachment B), have been prepared to support this evaluation. As shown in the calculations the soil has the following properties: Unit weight 110 pounds per cubic foot; and Friction Angle (natural angle of repose) 38{sup o} or 1.28 horizontal to 1 vertical. Setback distances are measured from the top edge of the slope to the wheels/tracks of the vehicles and heavy equipment being utilized. The computer program utilized in the calculation uses the center of the wheel or track load for the analysis and this difference is accounted for in this evaluation.

Slope Stability Evaluation And Equipment Setback Distances For Burial Ground Excavations

International Nuclear Information System (INIS)

Mcshane, D.S.

2010-01-01

After 1970 Transuranic (TRU) and suspect TRU waste was buried in the ground with the intention that at some later date the waste would be retrieved and processed into a configuration for long term storage. To retrieve this waste the soil must be removed (excavated). Sloping the bank of the excavation is the method used to keep the excavation from collapsing and to provide protection for workers retrieving the waste. The purpose of this paper is to document the minimum distance (setback) that equipment must stay from the edge of the excavation to maintain a stable slope. This evaluation examines the equipment setback distance by dividing the equipment into two categories, (1) equipment used for excavation and (2) equipment used for retrieval. The section on excavation equipment will also discuss techniques used for excavation including the process of benching. Calculations 122633-C-004, 'Slope Stability Analysis' (Attachment A), and 300013-C-001, 'Crane Stability Analysis' (Attachment B), have been prepared to support this evaluation. As shown in the calculations the soil has the following properties: Unit weight 110 pounds per cubic foot; and Friction Angle (natural angle of repose) 38 o or 1.28 horizontal to 1 vertical. Setback distances are measured from the top edge of the slope to the wheels/tracks of the vehicles and heavy equipment being utilized. The computer program utilized in the calculation uses the center of the wheel or track load for the analysis and this difference is accounted for in this evaluation.

Experiments on aerosol removal by high-pressure water spray

Energy Technology Data Exchange (ETDEWEB)

Corno, Ada del, E-mail: delcorno@rse-web.it [RSE, Power Generation Technologies and Materials Dept, via Rubattino 54, I-20134 Milano (Italy); Morandi, Sonia, E-mail: morandi@rse-web.it [RSE, Power Generation Technologies and Materials Dept, via Rubattino 54, I-20134 Milano (Italy); Parozzi, Flavio, E-mail: parozzi@rse-web.it [RSE, Power Generation Technologies and Materials Dept, via Rubattino 54, I-20134 Milano (Italy); Araneo, Lucio, E-mail: lucio.araneo@polimi.it [Politecnico di Milano, Department of Energy, via Lambruschini 4A, I-20156 Milano (Italy); CNR-IENI, via Cozzi 53, I-20125 Milano (Italy); Casella, Francesco, E-mail: francesco2.casella@mail.polimi.it [Politecnico di Milano, Department of Energy, via Lambruschini 4A, I-20156 Milano (Italy)

2017-01-15

Highlights: • Experimental research to measure the efficiency of high-pressure sprays in capturing aerosols if applied to a filtered containment venting system in case of severe accident. • Cloud of monodispersed SiO{sub 2} particles with sizes 0.5 or 1.0 μm and initial concentration in the range 2–90 mg/m{sup 3}. • Carried out in a chamber 0.5 × 1.0 m and 1.5 m high, with transparent walls equipped with a high pressure water spray with single nozzle. • Respect to low-pressure sprays, removal efficiency turned out significant: the half-life for 1 μm particles with a removal high-pressure spray system is orders of magnitude shorter than that with a low-pressure sprays system. - Abstract: An experimental research was managed in the framework of the PASSAM European Project to measure the efficiency of high-pressure sprays in capturing aerosols when applied to a filtered containment venting system in case of severe accident. The campaign was carried out in a purposely built facility composed by a scrubbing chamber 0.5 × 1.0 m and 1.5 m high, with transparent walls to permit the complete view of the aerosol removal process, where the aerosol was injected to form a cloud of specific particle concentration. The chamber was equipped with a high pressure water spray system with a single nozzle placed on its top. The test matrix consisted in the combination of water pressure injections, in the range 50–130 bar, on a cloud of monodispersed SiO{sub 2} particles with sizes 0.5 or 1.0 μm and initial concentration ranging between 2 and 99 mg/m{sup 3}. The spray was kept running for 2 min and the efficiency of the removal was evaluated, along the test time, using an optical particle sizer. With respect to low-pressure sprays, the removal efficiency turned out much more significant: the half-life for 1 μm particles with a removal high-pressure spray system is orders of magnitude shorter than that with a low-pressure spray system. The highest removal rate was

Experiments on aerosol removal by high-pressure water spray

International Nuclear Information System (INIS)

Corno, Ada del; Morandi, Sonia; Parozzi, Flavio; Araneo, Lucio; Casella, Francesco

2017-01-01

Highlights: • Experimental research to measure the efficiency of high-pressure sprays in capturing aerosols if applied to a filtered containment venting system in case of severe accident. • Cloud of monodispersed SiO_2 particles with sizes 0.5 or 1.0 μm and initial concentration in the range 2–90 mg/m"3. • Carried out in a chamber 0.5 × 1.0 m and 1.5 m high, with transparent walls equipped with a high pressure water spray with single nozzle. • Respect to low-pressure sprays, removal efficiency turned out significant: the half-life for 1 μm particles with a removal high-pressure spray system is orders of magnitude shorter than that with a low-pressure sprays system. - Abstract: An experimental research was managed in the framework of the PASSAM European Project to measure the efficiency of high-pressure sprays in capturing aerosols when applied to a filtered containment venting system in case of severe accident. The campaign was carried out in a purposely built facility composed by a scrubbing chamber 0.5 × 1.0 m and 1.5 m high, with transparent walls to permit the complete view of the aerosol removal process, where the aerosol was injected to form a cloud of specific particle concentration. The chamber was equipped with a high pressure water spray system with a single nozzle placed on its top. The test matrix consisted in the combination of water pressure injections, in the range 50–130 bar, on a cloud of monodispersed SiO_2 particles with sizes 0.5 or 1.0 μm and initial concentration ranging between 2 and 99 mg/m"3. The spray was kept running for 2 min and the efficiency of the removal was evaluated, along the test time, using an optical particle sizer. With respect to low-pressure sprays, the removal efficiency turned out much more significant: the half-life for 1 μm particles with a removal high-pressure spray system is orders of magnitude shorter than that with a low-pressure spray system. The highest removal rate was detected with 1 �

Eliminating line of sight in elliptic guides using gravitational curving

International Nuclear Information System (INIS)

Kleno, Kaspar H.; Willendrup, Peter K.; Knudsen, Erik; Lefmann, Kim

2011-01-01

Eliminating fast neutrons (λ<0.5A) by removing direct line of sight between the source and the target sample is a well established technique. This can be done with little loss of transmission for a straight neutron guide by horizontal curving. With an elliptic guide shape, however, curving the guide would result in a breakdown of the geometrical focusing mechanism inherent to the elliptical shape, resulting in unwanted reflections and loss of transmission. We present a new and yet untried idea by curving a guide in such a way as to follow the ballistic curve of a neutron in the gravitational field, while still retaining the elliptic shape seen from the accelerated reference frame of the neutron. Analytical calculations and ray-tracing simulations show that this method is useful for cold neutrons at guide lengths in excess of 100 m. We will present some of the latest results for guide optimization relevant for instrument design at the ESS, in particular an off-backscattering spectrometer which utilizes the gravitational curving, for 6.66 A neutrons over a guide length of 300 m.

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)

Guideline on dependability management for the power industry: detailed description of international power plant equipment dependability indicators; Guide de gestion de la surete de fonctionnement dans l`industrie electrique: description detaillee d`indicateurs de surete de fonctionnement internationaux

Energy Technology Data Exchange (ETDEWEB)

Procaccia, H.; Silberberg, S.

1997-10-01

Dependability Management involves the management of reliability, availability maintainability and maintenance support, and in the power industry is necessary to ensure that plant meets the Reliability, Availability and Maintainability (RAM) targets set by the Utilities. In 1993, a joint (Standard on Dependability Programme Management - Part 1: Dependability Programme Management), ISO 9000-`: 1993 (Quality Management and Quality Assurance Standards - Part 4: Guide to Dependability Programme Management). UNIPEDE established a group of experts (Nulethermaint) to produce guidelines on its implementation specifically for use in the power industry. The present document comprises Part 2 OF THE UNIPEDE plant performance indicators and can be applied to both nuclear and fossil plant. There are five different equipment dependability indicators, all relating to equipment maintenance activities and the impact that these activities have on the loss of both system function and unit capability. Per year, each of the indicators can be applied separately to both preventive maintenance and corrective maintenance, giving rise to as many as ten indicator values for each item of equipment. Used in this way, the indicators provide a comprehensive picture of the maintenance strategy employed for key pieces of equipment, and its effectiveness. They are, therefore, a valuable managerial tool for improving maintenance activities at the unit level within a utility. This document provides guidance on the division of both nuclear and fossil power plant into their component parts and in each case the types of equipment having the most dominant effect on dependability are identified. These are the items which merit the greatest attention with regard to the equipment dependability indicators. (authors).

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)

Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

International Nuclear Information System (INIS)

Korsah, K.; Wood, R.T.; Hassan, M.; Tanaka, T.J.

1998-01-01

This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Hassan, M. [Brookhaven National Lab., Upton, NY (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States)

1998-01-01

This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.

The Definitive Guide to SQLite

CERN Document Server

Owens, Mike

2010-01-01

Outside of the world of enterprise computing there is one database that enables a huge range of software and hardware to flex relational database capabilities, without the baggage and cost of traditional database management systems. That database is SQLite - an embeddable database with an amazingly small footprint, yet it can handle databases of enormous size. SQLite comes equipped with an array of powerful features available through a host of programming and development environments. It is supported by languages such as C, Java, Perl, PHP, Python, Ruby, TCL, and more. The Definitive Guide to

Wave-guide type photo reactor for water purification

International Nuclear Information System (INIS)

Nobuaki, Negishi; Feng, He; Sadao, Matsuzawa; Koji, Takeuchi; Kayo, Ohno

2006-01-01

A wave-guide type photo-catalytic rod that is consisting of a glass tube with transparent TiO 2 (outside) and an optical wave-guide rod (inside) was designed and examined its performance. A model of polluted water, which contains 100 ppm of toluene or phenol, was taken in a 500 ml of beaker and the performance of this unit was evaluated by the removal rate of pollutants in water under photo-irradiation. Acrylic rod with 6-mm diameter was used as the wave-guide of light. One end of acrylic rod 50 mm had a frosted part or a screw thread for increasing seep out of the light. For the glass tube with transparent TiO 2 , four kinds with different film thickness were prepared by the dip-coating method. The wave-guide type photo-catalytic rods effectively eliminated toluene and phenol and the total amount of intermediates formation was low. (authors)

Implementation of the project of equipment reliability in the nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Rios O, J. E.; Martinez L, A. G.

2008-01-01

A equipment is reliable if it fulfills the function for which was designed and when it is required. To implement a project of reliability in a nuclear power plant this associate to a process of continuous analysis of the operation, of the conditions and faults of the equipment. The analysis of the operation of a system, of the equipment of the same faults and the parts that integrate to equipment take to identify the potential causes of faults. The predictive analysis on components and equipment allow to rectify and to establish guides to optimize the maintenance and to guarantee the reliability and function of the same ones. The reliability in the equipment is without place to doubts a wide project that embraces from the more small component of the equipment going by the proof of the parts of reserve, the operation conditions until the operative techniques of analysis. Without place of doubt for a nuclear power plant the taking of decisions based on the reliability of their systems and equipment will be the appropriate for to assure the operation and reliability of the same one. In this work would appear the project of reliability its processes, criteria, indicators action of improvement and the interaction of the different disciplines from the Nuclear Power Plant of Laguna Verde like a fundamental point for it put in operation. (Author)

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

Science.gov (United States)

R. Edward Thomas; Urs Buehlmann; Urs Buehlmann

2003-01-01

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

Italian WEEE management system and treatment of end-of-life cooling and freezing equipments for CFCs removal.

Science.gov (United States)

Sansotera, M; Navarrini, W; Talaeemashhadi, S; Venturini, F

2013-06-01

This study presents and analyzes the data of the Italian system for take-back and recovery of waste electrical and electronic equipments (WEEEs) in the start-up period 2008-2010. The analysis was focused particularly on the data about the treatment of end-of-life cooling and freezing equipments. In fact, the wastes of cooling and freezing equipments have a high environmental impact. Indeed, in their compressor oil and insulation polyurethane (PU) foams chlorofluorocarbon (CFC) ozone-depleting gases are still present. In the period 2001-2004 Northern Italy resulted the main source in Europe of CFCs. The European Directive on WEEE management was enacted in 2002, but in Italy it was implemented by the legislative Decree in 2005 and it became operational in 2008. Actually, in 2008 the national WEEE Coordination Centre was founded in order to organize the WEEE pick-up process and to control collection, recovery and recycling targets. As a result, in 2010 the average WEEE collection per capita exceeded the threshold of more than 4 kg per inhabitant, as well as cooling and freezing appliances represented more than one fourth of the Italian WEEE collection stream. During the treatment of end-of-life cooling and freezing equipments, CFCs were recovered and disposed principally by burner methods. The analyses of defined specimens collected in the treatment facilities were standardized to reliably determine the amount of recovered CFCs. Samples of alkaline solid salt, alkaline saline solution, polyurethane matrix and compressor oil collected during the audit assessment procedure were analyzed and the results were discussed. In particular, the analysis of PU samples after the shredding and the warm pressing procedures measured a residual CFCs content around 500-1300 mg/kg of CFCs within the foam matrix. Copyright © 2013 Elsevier Ltd. All rights reserved.

A newly developed technique of wireless remote controlled visual inspection system for neutron guides of cold neutron research facilities at HANARO

International Nuclear Information System (INIS)

Huh, Hyung; Cho, Yeong Garp; Kim, Jong In

2012-01-01

KAERI developed a neutron guide system for cold neutron research facilities at HANARO from 2003 to 2010. In 2008, the old plug shutter and instruments were removed, and a new plug and primary shutter were installed as the first cold neutron delivery system at HANARO. At the beginning of 2010, all the neutron guides and accessories had been successfully installed as well. The neutron guide system of HANARO consists of the in pile plug assembly with in pile guides, the primary shutter with in shutter guides, the neutron guides in the guide shielding room with secondary shutter, and the neutron guides in the neutron guide hall. Three kinds of glass materials were selected with optimum lengths by considering their lifetime, shielding, maintainability and cost as well. Radiation damage of the guides can occur on the coating and glass by neutron capturing in the glass. It is a big challenge to inspect a guide failure because of the difficult surrounding environment, such as high level radiation, limited working space, and massive hard work for removing and reinstalling the shielding blocks as shown in Fig 1. Therefore, KAERI has developed a wireless remote controlled visual inspection system for neutron guides using an infrared light camera mounted on the vehicle moving in the guide

Guide tube insert assembly for use in a nuclear reactor

International Nuclear Information System (INIS)

Hopkins, R.J.; Land, J.T.

1992-01-01

This patent describes an internals assembly for a nuclear reactor of the type including an upper support plate and an upper core plate, each having apertures for conducting control rod assemblies into an out of fuel assemblies with the apertures of the upper support plate being aligned with the apertures of the upper core plate, a guide tube insert assembly comprising: an elongated tubular body extending between at least one of the aligned apertures formed in the upper support plate and the upper core plate; guide plates within the elongated tubular body, each of the guide plates having a planar surface extending substantially perpendicular to an axial direction of the tubular body; at least one interconnecting means for interconnecting the guide plates into a guide tube insert assembly such that the guide plates are simultaneously mountable within and removable from the elongated body, and the periphery of each of the guide plates is spaced apart from the inner walls of the elongated tubular body at every point when the insert assembly is mounted within the tubular body, and a stabilizing means for securing the lowermost guide plate of the guide tube insert assembly within the elongated tubular body to prevent rotational and lateral movement between the guide tube insert assembly and the tubular body

Illustrated Guide to Astronomical Wonders From Novice to Master Observer

CERN Document Server

Thompson, Robert

2011-01-01

With the advent of inexpensive, high-power telescopes priced at under 250, amateur astronomy is now within the reach of anyone, and this is the ideal book to get you started. The Illustrated Guide to Astronomical Wonders offers you a guide to the equipment you need, and shows you how and where to find hundreds of spectacular objects in the deep sky -- double and multiple stars as well as spectacular star clusters, nebulae, and galaxies. You get a solid grounding in the fundamental concepts and terminology of astronomy, and specific advice about choosing, buying, using, and maintaining the eq

Generation of equipment response spectrum considering equipment-structure interaction

International Nuclear Information System (INIS)

Lee, Sang Hoon; Yoo, Kwang Hoon

2005-01-01

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

Prophylactic and thermovision measurements of electric machines and equipment

International Nuclear Information System (INIS)

Jedlicka, R.; Brestovansky, L.

1996-01-01

High-voltage measurements of generators, unit and service transformers and some significant motor drives used at a nuclear power plant are described in this paper. Thermovision measurements of electric machines and distribution systems are dealt with in the second part of the paper. Power electric equipment represent one of the most significant components of a nuclear power plant. Turbine mechanical energy is converted into the electrical energy within these equipment. Power generated by generators is transformed by transformers so that it can achieve appropriate parameters for both the transmission over the distribution system and the power plant service power supply. The service power supply switchboards and cables provide supply to motors and other consumers necessary for the nuclear power plant technological process. The whole complex of equipment has to be maintained in good technical conditions. It is necessary to make thermovision and prophylactic measurements to identify and verify the electric equipment technical condition. The mentioned measurements warn the operation staff in advance against both gradual deterioration of power connection contact resistances, i.e. power connections overheating, and the machine insulation systems condition deterioration. The operation staff try to prevent the electric equipment operation accidents by early removing the detected failures, thus, improving the nuclear safety. In order to provide the above-mentioned activities a special prophylactic measurement group was established at the NPP Bohunice in 1983. The group specialists make following types of measurements. 1. Prophylactic measurements of electric machines. Prophylactics of 220 MW generators and 6 MW service power generators; Prophylactics of both unit and service transformers and VHV bushings; Prophylactics of major 6 kV motor drives. 2. Thermovision measurements of current connections. Measurements enumarated in paragraph 1 are made on disconnected electric

Generic precise augmented reality guiding system and its calibration method based on 3D virtual model.

Science.gov (United States)

Liu, Miao; Yang, Shourui; Wang, Zhangying; Huang, Shujun; Liu, Yue; Niu, Zhenqi; Zhang, Xiaoxuan; Zhu, Jigui; Zhang, Zonghua

2016-05-30

Augmented reality system can be applied to provide precise guidance for various kinds of manual works. The adaptability and guiding accuracy of such systems are decided by the computational model and the corresponding calibration method. In this paper, a novel type of augmented reality guiding system and the corresponding designing scheme are proposed. Guided by external positioning equipment, the proposed system can achieve high relative indication accuracy in a large working space. Meanwhile, the proposed system is realized with a digital projector and the general back projection model is derived with geometry relationship between digitized 3D model and the projector in free space. The corresponding calibration method is also designed for the proposed system to obtain the parameters of projector. To validate the proposed back projection model, the coordinate data collected by a 3D positioning equipment is used to calculate and optimize the extrinsic parameters. The final projecting indication accuracy of the system is verified with subpixel pattern projecting technique.

A Guide for the Safe Handling of Engineered and Fabricated Nanomaterials

Science.gov (United States)

Greaves-Holmes, Wanda L.

2009-01-01

In the absence of scientific clarity regarding the potential health effects of occupational exposure to nanoparticles, there is a need for guidance in making decisions about hazards, risks, and controls (Schulte & Salmanca-Buentello, 2007). Presently, no guiding principles have been universally accepted for personal protective equipment that is…

Percutaneous Retrieval of a Dislodged Guide Wire by Dormia Basket in a 98-year-old Patient, Still a Safe and Feasible Approach

Directory of Open Access Journals (Sweden)

Gh Soltani

2010-06-01

Full Text Available Since the first report of percutaneous retrieval of intravascular foreign body in 1964, it has been accepted as a favorite approach for intravascular foreign body removal. Various instruments such as snares, biopsy forceps, dormia basket or tip deflecting wires are available for this approach. Herein, we report percutaneous retrieval of a dislodged guide-wire by dormia basket. The Patient was a 98-year-old female who was admitted in the Intensive care unit due to confusional state. The physian incharge left the guide-wire in her subclavian vein during central venous catheter insertion. He realized his fault immediately, so he started anti-coagulation therapy and requested surgical consult. Because of the patient’s high risk of surgery, the surgeon referred the patient to cardiologist for non-invasive guide wire removal. The guide wire was apprpached through femoral vein by a dormia basket (4/6 F and it was removed without any difficulties or complications. Utilization of baskets for intravascular foreign body removal is frequently reported and has been successful with low complication rates; In addition, the low cost of the device makes it less of a burden to the patient and the hospital.

Beyond the complications: medium-term anatomical, sexual and functional outcomes following removal of trocar-guided transvaginal mesh. A retrospective cohort study.

Science.gov (United States)

Jeffery, Stephen T; Nieuwoudt, Andri

2012-10-01

The aims of this study were to assess the anatomical, sexual and functional outcomes of women undergoing surgical intervention for complications of the trocar-guided transvaginal mesh (TVM) procedure. This was a retrospective analysis of a clinical database of women who had developed a complication following a TVM procedure. This included dyspareunia, mesh erosion, urinary symptoms, mesh contraction and prolapse recurrence. Pre- and post-operatively, we assessed the women for prolapse, stress incontinence, urgency, defecatory difficulty, digitation, pain, dyspareunia and apareunia. We also recorded the Pelvic Organ Prolapse Quantification (POP-Q) score. The TVM was removed and a Biodesign graft was used in the majority of cases to prevent further prolapse. Follow-up was at 6 weeks, 6 months, 1 and 2 years. In our cohort of 21 women, 18 required surgery for pain and/or dyspareunia; 20 women had reached the 6-week follow-up at the time of analysis. At 6 weeks, two women still had pain and required a second intervention. Fifteen women had reached a 6-month follow-up and only one woman had persistent pain requiring repeat surgery. Of the 15 women, 7 were sexually active and in 6 cases the dyspareunia had resolved completely with 1 woman retaining an element of pain at intercourse. Six women had been seen at 12 months and all four of the sexually active women had no dyspareunia. There were no symptoms relating to prolapse in any of the women at 6 weeks, 6, 12 or 24 months. We report satisfactory outcomes following removal of a complicated TVM kit.

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

Science.gov (United States)

2010-01-01

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

Development of In-pile Plug Assembly and Primary Shutter for Cold Neutron Guide System

Energy Technology Data Exchange (ETDEWEB)

Shin, Jin Won; Cho, Yeong Garp; Ryu, Jeong Soo; Lee, Jung Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-12-15

The HANARO, a 30 MW multi-purpose research reactor in Korea, will be equipped with a neutron guide system, in order to transport cold neutrons from the neutron source to the neutron scattering instruments in the neutron guide hall near the reactor building. The neutron guide system of HANARO consists of the in-pile plug assembly with in-pile guides, the primary shutter with in-shutter guides, the neutron guides in the guide shielding room with dedicated secondary shutters, and the neutron guides connected to the instruments in the neutron guide hall. The functions of the in-pile plug assembly are to shield the reactor environment from a nuclear radiation and to support the neutron guides and maintain them precisely oriented. The primary shutter is a mechanical device to be installed just after the in-pile plug assembly, which stops neutron flux on demand. This report describes the mechanical design, fabrication, and installation procedure of the in-pile plug assembly and the primary shutter for the neutron guide system at HANARO. A special tool and procedure for a replacement of in-pile plug and guide cassette is also presented with the interface condition in the reactor hall.

Localization of intraductal mass through the ostium of the duct using wire guided ductography technique

International Nuclear Information System (INIS)

Aslam, M.

2014-01-01

To localize intraductal mass (Papilloma) before surgery Materials Guide wire 10-15 cm length of 2/3-0 Prolene/Surgipro Plastic 26G to 20G I/V cannulas Kopans breast lesion localization hook wire Disposable syringe heaving 2ml non-ionic contrast High intensity light and magnified glass. Methods: Prepare patient in sitting or lying position adjust high intensity light clean the nipple with antiseptic lotion. Elicit the discharge with gentle periareolar pressure or ask the patient to bring the discharge. If the opening with discharge is not clearly visualize use magnified glass or loop. Slowly inserted the wire into the duct orifice, it should pass freely into the duct. Introduce the 26G I/V plastic cannula coaxially over the guide wire and remove the guide wire. Gently inject 0.2-0.4 ml contrast, remove and the syringe and apply stopper. The cannula stopper assembly is secured to the breast with tape. Magnified craniocaudal view of the breast is taken, the 26G cannula removed and bigger length 22/20G cannula gradually passed over the guide wire according to distance of lesion from the ostium. Intraductal mass location is verified the hook wire is replaced with guide wire, the position of hook confirmed by mammographic film. The wire is cut 2cms from the nipple and pt. send to operation theater Results:Hook localization has been successfully carried out in six patients. Conclusion:This is a new method of localization of intraductal mass it enables the surgeon to do microductectomy with minimal cosmetic effects to the breast. (author)

Equipment considerations

International Nuclear Information System (INIS)

Anon.

1992-01-01

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

Ultrasound-guided antegrade access during laparoscopic pyeloplasty in infants less than one year of age: A point of technique

Directory of Open Access Journals (Sweden)

Arvind Ganpule

2012-01-01

Full Text Available Background: Access to urethras and ureters of infants may be hazardous and injurious through an endoscopic route. Placement and removal of stents in infants requires anaesthesia and access through these small caliber urethras. We describe our technique of placing antegrade splint during a laparoscopic pyeloplasty in these infants. Materials and Methods: An ultrasound-guided percutaneous renal access is obtained. Telescopic metal two part needle is passed into the kidney over a guide wire. A second guide wire is passed through the telescopic metal two part needle. The tract is dilated with 14 Fr screw dilator. Over one guide wire, a 5 Fr ureteric catheter is passed and coiled in the renal pelvis. Over the other wire, a 14 Fr malecot catheter is placed as nephrostomy. Laparoscopic pyeloplasty is then done. During pyelotomy, the ureteric catheter is pulled and advanced through the ureter before the pyeloplasty is completed. The ureteric catheter thus acts as a splint across the anastomosis. Ureteric catheter is removed on the 3 rd post operative day and nephrostomy is clamped. Nephrostomy is removed on 4 th post operative day if child is asymptomatic. The modified technique was successfully done in five patients aged less than one year old. All patients tolerated the procedure well. Post operative period was uneventful in all. Conclusion: Ultrasound-guided ante grade nephroureteral ureteral splint for infant laparoscopic pyeloplasty is safe. It avoids the need for urethral instrumentation for insertion and removal of stents in these small patients.

Quality Assurance in the removal and transport of the TMI-2 core

International Nuclear Information System (INIS)

Hayes, G.R.; Marsden, J.F.

1988-01-01

EG ampersand G Idaho, acting on behalf of the US Department of Energy (DOE), is cooperating with the owner of the TMI-2 plant, General Public Utilities Nuclear (GPUN), in the removal and transport of the damaged TMI-2 core to the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho. Quality Assurance (QA) played an important role in the removal and transport of the damaged TMI-2 core. To illustrate, the authors have chosen to discuss some of the important quality assurance techniques utilized in the design, fabrication, acceptance, and use of the three different types of equipment; the core boring machine, the core debris canisters, and the transport casks. Rather than a thorough discussion of the QA aspects of each task, the authors have purposely chosen to present only the key applications of quality assurance principles and methodology unique to each piece of equipment. The intent of this approach is to effectively communicate the importance of ''task teamwork'' in QA

Vocational Home Economics Curriculum Guide for Occupational Home and Institutional Services.

Science.gov (United States)

Dewald, Margaret R.

The training program outlined in this guide focuses upon the development of students for gainful employment through a two-year course of study in home and institutional services. Instructional topics are provided in nine areas: orientation to home and institutional services, cleaning supplies and equipment, cleaning surfaces, cleaning clothes and…

Percutaneous antegrade ureteric stent removal using a rigid alligator forceps.

LENUS (Irish Health Repository)

Given, M F

2008-12-01

To evaluate the safety and efficacy of percutaneous antegrade ureteric stent removal using a rigid alligator forceps. Twenty patients were included in our study. Indications for ureteric stent insertion included stone disease (n = 7), malignancy (n = 8) and transplant anastomotic strictures (n = 5). Stent retrieval was carried out for proximal stent placement\\/migration in seven patients and encrustation in the remaining 13. Twenty-two stents were successfully retrieved in 20 patients. There was one technical failure (5%). There were no major complications. We had four minor complications, which included nephrostomy site pain (n = 2), periprocedural sepsis (n = 1) and a small urinoma (n = 1). All patients settled with conservative management. Percutaneous radiologically guided antegrade ureteric stent removal with an alligator forceps is safe and effective, particularly when initial surgical removal has failed.

Medical Issues: Equipment

Science.gov (United States)

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

The Design and Experiment of the Track-Type Equipment for Feeding Dairy Cows

Directory of Open Access Journals (Sweden)

Yaping LI

2014-06-01

Full Text Available As one of the effective ways of reducing the cost and increase the revenue, feeding dairy cows with individual precision in quantity could further develop the production potential of high- yield dairy cows and improve the milk yield of every dairy cow. Therefore, based on three kinds of technologies of radio frequency identification technology, wireless transmission technology and infrared technology and grounded on the foundation of previous studies, this thesis has completed the track- type equipment for feeding dairy cows with individual precision in quantity. The equipment takes the computer as the information management platform, adopts the singly chip microcomputer as the control platform, uses the wireless module and U disk to conduct the transmission of individual feeding data of dairy cows and guides the whole process with the track. This kind of equipment could advance automatically, identify and feed dairy cows precisely during the feeding process. This thesis also designs the matching feeding technology of the equipment, and accomplishes the test of feeding outside the cowshed, which takes “TMR + precise feeding with concentrated feed” as the feeding model, so that the feeding process could be more effective and further steady.

Repeated subretinal surgery and removal of subretinal decalin is well tolerated

DEFF Research Database (Denmark)

Sørensen, Nina Buus; Klemp, Kristian; Kjær, Troels Wesenberg

2017-01-01

flexible tube. Two weeks after removal, a control mfERG was recorded, the pigs were enucleated and sacrificed and eyes were examined histologically. All statistics were carried out with a paired t-test in SAS Enterprise Guide 7.1® (SAS Institute Inc., Cary, NC, USA). RESULTS: There was no significant...

Radium removal processes capital and operating cost estimates

International Nuclear Information System (INIS)

Kelly, F.J.

1979-09-01

An estimate of the fixed capital and operating costs for two alternative processes for the removal of dissolved Ra-226 from uranium mill effluent in Elliot Lake, Ontario is presented. Process 1 consists of barium-radium coprecipitation followed by coagulation, flocculation and sedimentation. Process 2 consists of barium-radium coprecipitation followed by gravity media filtration, sand filter backwashing and sedimentation. Cost estimates were prepared for 18 different plant configurations designed to treat 1000 and 4000 imperial gallons per minute (ig/m) of effluent, 24 hrs per day, 7 days per week and 365 days per year with several equipment options. The estimated fixed capital costs for plants equipped with gravity filters were less than those equipped with circular clarifiers. The capital costs ranged from $552,000 with a flow rate of 1000 ig/m to $2,578,000 with a flow rate of 4000 ig/m. Estimated annual operating costs, based on a plant life of 10 years, ranged from $298,000 with a flow rate of 1000 ig/m to $1,061,000 with a flow rate of 4000 ig/m

Removal of sodium from the component of the sodium purification loop

International Nuclear Information System (INIS)

Kim, Byung Ho; Jeong, Kyung Chai; Jeong, Ji Young; Kim, Jong Man; Choi, Byung Hae; Nam, Ho Yun

2005-01-01

The purpose of a cleaning process is to remove the residual sodium adhering to the component walls once it has been properly drained. It is necessary to clean and decontaminate a component, especially the large components of the primary coolant system; such as the intermediate heat exchangers and the primary pump. Improper and inadequate cleaning has in a number of cases resulted in problems in the storage, handling, and reuse of components. Several types of failures due to improper cleaning procedures have been defined in the past. Inadequate and incomplete removal of sodium results in residues which may contain metallic sodium and alkaline compounds such as sodium hydroxide, sodium oxide, sodium carbonate, and various types of alcoholates. Reinsertion of components containing these compounds into a high-temperature sodium system can result in either the intergranular penetration characteristic of a high-oxygen sodium or an accelerated corrosion due to oxygen. The methods used for cleaning sodium equipment depend on the condition and types of equipment to be cleaned and whether the equipment is to be reused. Cleaning methods are needed that will avoid a deleterious local overheating, material surface degradation or deposits, chemical, physical, or mechanical damage, and external effects. This paper discusses a steam-nitrogen gas cleaning method for the routine applications that permits the reuse of the cold trap in sodium

Indoor pollutants emitted by office equipment: A review ofreported data and information needs

Energy Technology Data Exchange (ETDEWEB)

Destaillats, Hugo; Maddalena, Randy L.; Singer, Brett C.; Hodgson, Alfred T.; McKone, Thomas E.

2007-02-01

There is concern that potentially harmful pollutants may be emitted from office equipment. Although office equipment has been a focal point for governmental efforts to promote energy efficiency through programs such as the US EPA's Energy Star, little is known about the relationship between office equipment use and indoor air quality, and information on pollutant emissions is sparse. In this review, we summarize available information on emission rates and/or ambient concentrations of various pollutants that are related to office equipment use. Experimental methods used in the characterization of emissions are briefly described. The office equipment evaluated in this review includes computers (desktops and notebooks), printers (laser, ink-jet and all-in-one machines) and photocopy machines. Reported emission rates of the following pollutant groups are summarized: volatile organic chemicals (VOCs), ozone, particulate matter and several semivolatile organic chemicals (SVOCs). The latter include phthalate esters, brominated flame retardants, organophosphate flame retardants and polycyclic aromatic hydrocarbons (PAHs). We also review studies reporting airborne concentrations in indoor environments where office equipment was present and thought to be a significant contributor to the total pollutant burden (offices, residences, schools, electronics recycling plants). For certain pollutants, such as organophosphate flame retardants, the link between emission by office equipment and indoor air concentrations is relatively well established. However, indoor VOCs, ozone, PAHs and phthalate esters can originate from a variety of sources, and their source apportionment is less straightforward. This literature review identifies substances of toxicological significance, with the purpose of serving as a guide to evaluate their potential importance with respect to human exposures.

Prophylactic and thermovision measurements of electric machines and equipment

Energy Technology Data Exchange (ETDEWEB)

Jedlicka, R; Brestovansky, L [Atomova Elektraren Bohunice, Jaslovske Bohunice (Slovakia)

1997-12-31

High-voltage measurements of generators, unit and service transformers and some significant motor drives used at a nuclear power plant are described in this paper. Thermovision measurements of electric machines and distribution systems are dealt with in the second part of the paper. Power electric equipment represent one of the most significant components of a nuclear power plant. Turbine mechanical energy is converted into the electrical energy within these equipment. Power generated by generators is transformed by transformers so that it can achieve appropriate parameters for both the transmission over the distribution system and the power plant service power supply. The service power supply switchboards and cables provide supply to motors and other consumers necessary for the nuclear power plant technological process. The whole complex of equipment has to be maintained in good technical conditions. It is necessary to make thermovision and prophylactic measurements to identify and verify the electric equipment technical condition. The mentioned measurements warn the operation staff in advance against both gradual deterioration of power connection contact resistances, i.e. power connections overheating, and the machine insulation systems condition deterioration. The operation staff try to prevent the electric equipment operation accidents by early removing the detected failures, thus, improving the nuclear safety. In order to provide the above-mentioned activities a special prophylactic measurement group was established at the NPP Bohunice in 1983. The group specialists make following types of measurements. 1. Prophylactic measurements of electric machines. Prophylactics of 220 MW generators and 6 MW service power generators; Prophylactics of both unit and service transformers and VHV bushings; Prophylactics of major 6 kV motor drives. 2. Thermovision measurements of current connections. (Abstract Truncated)

Scientific Equipment Division - Overview

International Nuclear Information System (INIS)

Halik, J.

2001-01-01

Full text: The Scientific Equipment Division consists of the Design Group and the Mechanical Workshop. The activity of the Division includes the following: - designing of devices and equipment for experiments in physics, their mechanical construction and assembly. In particular, there are vacuum chambers and installations for HV and UHV; - maintenance and upgrading of the existing installations and equipment in our Institute; - participation of our engineers and technicians in design works, equipment assembly and maintenance for experiments in foreign laboratories. The Design Group is equipped with PC-computers and AutoCAD graphic software (release 2000 and Mechanical Desktop 4.0) and a AO plotter, what allows us to make drawings and 2- and 3-dimensional mechanical documentation to the world standards. The Mechanical Workshop can offer a wide range of machining and treatment methods with satisfactory tolerances and surface quality. It offers the following possibilities: - turning - cylindrical elements of a length up to 2000 mm and a diameter up to 400 mm, and also disc-type elements of a diameter up to 600 mm and a length not exceeding 300 mm; - milling - elements of length up to 1000 mm and gear wheels of diameter up to 300 mm; - grinding - flat surfaces of dimensions up to 300 mm x 1000 mm and cylindrical elements of a diameter up to 200 mm and a length up to 800 mm; - drilling - holes of a diameter up to 50 mm; - welding - electrical and gas welding, including TIG vacuum-tight welding; - soft and hard soldering; - mechanical works including precision engineering; - plastics treatment - machining and polishing using diamond milling, modelling, lamination of various shapes and materials, including plexiglas, scintillators and light-guides; - painting - paint spraying with possibility of using furnace-fred drier of internal dimensions of 800 mm x 800 mm x 800 mm. Our workshop posses CNC milling machine which can be used for machining of work-pieces up to 500 kg

Surgical strategy for malignant gliomas involving pyramidal tracts guided by functional neuronavigation and 5-ALA fluorescence navigation

International Nuclear Information System (INIS)

Sato, Ken-ichi; Ito, Tamio; Seo, Yoshinobu; Sunohara, Tadashi; Maeda, Masana; Sasaki, Takehiko; Nakagawara, Jyoji; Nakamura, Hirohiko

2009-01-01

For patients with malignant glioma invading pyramidal tracts, maximal resections are difficult to accomplish while preserving their motor function. We used tractography-integrated functional neuronavigation and 5-aminolevulinic acid (5-ALA) fluorescence-guided resection for removal of malignant gliomas involving pyramidal tract. In this study, we analyzed postoperative motor function and extent of resection in a series of patients who underwent surgery in our department. Ten patients with malignant glioma invading pyramidal tracts underwent radical surgery. To preserve pyramidal tracts, we developed a functional neuronavigation-guided fence-post procedure to avoid the problem of brain shift, a disadvantage of the existing neuronavigation systems. Furthermore we have achieved precise resection of tumors using 5-ALA fluorescence navigation. Intraoperatively, tumor fluorescence was visualized using a modified operating microscope. All fluorescing tumor tissue was resected. Motor function was preserved after appropriate tumor resection in all cases. Postoperatively, improvement of motor weakness was observed in seven patients, whereas transient mild motor weakness occurred in two patients. Gross total removals were accomplished in seven patients, and subtotal removal was accomplished in one patient, and partial removal was accomplished in two patients. Combined use of tractography-integrated functional neuronavigation and 5-ALA fluorescence-guided resection contributes to maximal safe resection of malignant gliomas with pyramidal tract involvement. (author)

Energy Conversion Alternatives Study (ECAS), Westinghouse phase 1. Volume 3: Combustors, furnaces and low-BTU gasifiers. [used in coal gasification and coal liquefaction (equipment specifications)

Science.gov (United States)

Hamm, J. R.

1976-01-01

Information is presented on the design, performance, operating characteristics, cost, and development status of coal preparation equipment, combustion equipment, furnaces, low-Btu gasification processes, low-temperature carbonization processes, desulfurization processes, and pollution particulate removal equipment. The information was compiled for use by the various cycle concept leaders in determining the performance, capital costs, energy costs, and natural resource requirements of each of their system configurations.

At Home in the Office. A Guide for the Home Worker.

Science.gov (United States)

Thomas, Neil; And Others

This guide provides information to persons interested in establishing a work-at-home program, specifically those in clerical or support staff positions who use modern automated office equipment. The text is divided into two sections. The Home Worker section provides a summary of the At Home in the Office Project, personality characteristics…

Training simulator for advanced gas-cooled reactor (AGR) shutdown sequence equipment

International Nuclear Information System (INIS)

Shankland, J.P.; Nixon, G.L.

1978-01-01

Successful shutdown of nuclear plant is of prime importance for both safety and economic reasons and large sums of money are spent on equipment to make shutdowns fully automatic, thus removing the possibility of operator errors. While this aim can largely be realized, one must consider the possibility of automatic equipment or plant failures when operators are required to take manual action, and off-line training facilities should be available to operating staff to minimize the risk of incorrect actions being taken. This paper presents the practice adopted at Hunterston 'B' Nuclear Power Station to solve this problem and concerns the computer-based training simulator for the Reactor Shutdown Sequence Equipment (RSSE) which was commissioned in January 1977. The plant associated with shutdown is briefly described and the reasoning which shows the need for a simulator is outlined. The paper also gives details of the comprehensive facilities available on the simulator and goes on to describe the form that shutdown training takes and the experience gained at this time. (author)

Pegasus International, Inc. coating removal systems

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-02-01

The Pegasus Coating Removal System (PCRS) was demonstrated at Florida International University (FIU) where it was being evaluated for efficiency and cost. In conjunction with the FIU testing demonstration, a human factors assessment was conducted to assess the hazards and associated safety and health issues of concern for workers utilizing this technology. The PCRS is a chemical paste that is applied to the surface using a brush, roller, or airless sprayer. After the type of PCRS, thickness, and dwell time have been determined, a laminated backed material is placed on top of the chemical paste to slow down the drying process and to provide a mechanism to strip-off the chemical. After the dwell time is reached, the chemical substrate can be removed. Scrapers may be used to break-loose the layers as necessary or to break-loose the layers that are not removed when the laminated paper is picked up. Residue may also be cleaned off of the surface with a damp sponge with an agitating motion, absorbent sponges, or a vacuum, as needed. The paint and removal agent is then placed in drums for disposal at a later time. During the assessment sampling was conducted for organic vapors and general observational techniques were conducted for ergonomics. Recommendations for improved worker safety and health during application and removal of the PCRS include: (1) work practices that reflect avoidance of exposure or reducing the risk of exposure; (2) assuring all PPE and equipment are compatible with the chemicals being used; (3) work practices that reduce the worker`s need to walk on the slippery surface caused by the chemical or the use of special anti-slip soles; (4) careful control of overspray (if a spray application is used); and (5) the use of ergonomically designed long-handled tools to apply and remove the chemical (to alleviate some of the ergonomic concerns).

[Guided bone regeneration: general survey].

Science.gov (United States)

Cosyn, Jan; De Bruyn, Hugo

2009-01-01

The principle of 'guided bone regeneration' was first described in 1988 on the basis of animal-experimental data. Six weeks after transmandibular defects had been created and protected by non-resorbable teflonmembranes, complete bone regeneration was found. The technique was based on the selective repopulation of the wound: every infiltration of cells outside the neighbouring bone tissue was prevented by the application of the membrane. Additional animal experiments showed that guided bone regeneration was a viable treatment option for local bone defects surrounding dental implants. Clinical practice, however, showed that premature membrane exposure was a common complication, which was responsible for a tremendous reduction in regenerated bone volume. In addition, a second surgical intervention was always necessary to remove the membrane. As a result, resorbable alternatives were developed. Since these are less rigid, bone fillers are usually used simultaneously. These comprise autogenous bone chips and bone substitutes from allogenic or xenogenic origine. Also alloplastic materials could be used for this purpose. Based on their characteristics this article provides an overview of the biomaterials that could be considered for guided bone regeneration. Specific attention goes to their application in clinical practice.

Absolute air filtering equipment in the nuclear industrie. Design - Safety - Experience

International Nuclear Information System (INIS)

Lucas, J.C.

1977-01-01

The problems encountered in the design of absolute filters (HEPA FILTERS) are presented: glass-fibre filter papers; standards and characteristics: efficiency, fire-resistance, humidity-resistance, radiation-resistance, etc; various types of paper folding: deep folds and small folds, dihedrally mounted; filtering elements; designs; characteristics and quality control; The design of filtration equipment is also analysed: mounting in metal or concrete casings. French and American designs (Regulatory Guide 1-52); and gas-tight casings allowing contaminated filters to be renewed without breaking the gas-tight seal

Handling tool for, and method of use of, ice basket removable cruciform

International Nuclear Information System (INIS)

Scrabis, C.M.; Mazza, G.E.; Golick, L.R.; Pomaibo, P.

1987-01-01

This patent describes a method for selectively installing and removing a removable cruciform of a resiliently compressible type, in and from the interior of a generally cylindrical, elongated and vertically oriented ice containment structure, which interior is accessible from an open, upper and thereof. Each such removable cruciform comprises a central housing defining an axis of compression and expansion, means normally biasing the housing in the direction of expansion, legs extending from the housing in a generally radially oriented direction and means on the outer edges of the legs configured to engage a corresponding stiffenning ring rigidly secured on the interior of the cylindrical sidewall of the ice basket, comprising: providing a handling tool having an elongated frame defining an axis, guide means connected to the frame and comprising at least first and second guide fingers extending radially from the axis and angularly displaced thereabout and selectively moveable between retracted and extended positions, and clamping means mounted to the frame and extending axially outwardly therefrom, positioning the tool, with the clamping shoes in the disengaged positions, in axial alignment with and disposed radially outwardly about the central housing of a removable cruciform of the resiliently compressible type; selectively actuating the clamping means to the engaged positions of the clamping shoes for engaging and compressing the central housing of the cruciform and retracting the legs thereof; lowering the tool with the cruciform engaged thereby, axially downwardly through the ice basket to a desired elevation

Division of Scientific Equipment - Overview

International Nuclear Information System (INIS)

Halik, J.

2002-01-01

Full text: The Scientific Equipment Division consists of the Design Group and the Mechanical Workshop. The activity of the Division includes the following: * designs of devices and equipment for experiments in physics; their mechanical construction and assembly. In particular, these are vacuum chambers and installations for HV and UHV;* maintenance and upgrading of the existing installations and equipment in our Institute; * participation of our engineers and technicians in design works, equipment assembly and maintenance for experiments in foreign laboratories. The Design Group is equipped with PC-computers and AutoCAD graphic software (release 2000 and Mechanical Desktop 4.0) and an A0 plotter, which allow us to make drawings and 2- and 3-dimensional mechanical documentation to the world standards. The Mechanical Workshop offers a wide range of machining and treatment methods with satisfactory tolerances and surface quality. They include: * turning - cylindrical elements of a length up to 2000 mm and a diameter up to 400 mm, and also disc type elements of a diameter up to 600 mm and a length not exceeding 300 mm, * milling - elements of length up to 1000 mm and gear wheels of diameter up to 300 mm, * grinding - flat surfaces of dimensions up to 300 mm x 1000 mm and cylindrical elements of a diameter up to 200 mm and a length up to 800 mm, * drilling - holes of a diameter up to 50 mm, * welding - electrical and gas welding, including TIG vacuum-tight welding, * soft and hard soldering, * mechanical works including precision engineering, * plastics treatment - machining and polishing using diamond milling, modelling, lamination of various shapes and materials, including plexiglas, scintillators and light-guides, * painting - paint spraying with possibility of using furnace-fired drier of internal dimensions of 800 mm x 800 mm x 800 mm. Our workshop is equipped with the CNC milling machine which can be used for machining of work pieces up to 500 kg. The machine

Disinfection of a probe used in ultrasound-guided prostate biopsy.

Science.gov (United States)

Rutala, William A; Gergen, Maria F; Weber, David J

2007-08-01

Transrectal ultrasound (TRUS)-guided prostate biopsies are among the most common outpatient diagnostic procedures in urology clinics and carry the risk of introducing pathogens that may lead to infection. To investigate the effectiveness of procedures for disinfecting a probe used in ultrasound-guided prostate biopsy. The effectiveness of disinfection was determined by inoculating 10(7) colony forming units (cfu) of Pseudomonas aeruginosa at the following 3 sites on the probe: the interior lumen of the biopsy needle guide, the outside surface of the biopsy needle guide, and the interior lumen of the ultrasound probe where the needle guide passes through the transducer. Each site was investigated separately. After inoculation, the probe was immersed in 2% glutaraldehyde for 20 minutes and then assessed for the level of microbial contamination. The results demonstrated that disinfection (ie, a reduction in bacterial load of greater than 7 log(10) cfu) could be achieved if the needle guide was removed from the probe. However, if the needle guide was left in the probe channel during immersion in 2% glutaraldehyde, disinfection was not achieved (ie, the reduction was approximately 1 log(10) cfu). Recommendations for probe disinfection are provided and include disassembling the device and immersing the probe and the needle guide separately in a high-level disinfectant.

Self-designed femoral neck guide pin locator for femoral neck fractures.

Science.gov (United States)

Xia, Shengli; Wang, Ziping; Wang, Minghui; Wu, Zuming; Wang, Xiuhui

2014-01-01

Closed reduction and fixation with 3 cannulated screws is a widely accepted surgery for the treatment of femoral neck fractures. However, how to obtain optimal screw placement remains unclear. In the current study, the authors designed a guide pin positioning system for femoral neck fracture cannulated screw fixation and examined its application value by comparing it with freehand guide needle positioning and with general guide pin locator positioning provided by equipment manufacturers. The screw reset rate, screw parallelism, triangle area formed by the link line of the entry point of 3 guide pins, and maximum vertical load bearing of the femoral neck after internal fixation were recorded. As expected, the triangle area was largest in the self-designed positioning group, followed by the general positioning group and the freehand positioning group. The difference among the 3 groups was statistically significant (P.05). The authors’ self-designed guide pin positioning system has the potential to accurately insert cannulated screws in femoral neck fractures and may reduce bone loss and unnecessary radiation.

Hot demonstration of proposed commercial nuclide removal technology

International Nuclear Information System (INIS)

Lee, D.

1996-01-01

This task covers the development and operation of an experimental test unit located in a Building 4501 hot cell within Building 4501 at Oak Ridge National Laboratory (ORNL). This equipment is designed to test radionuclides removal technologies under continuous operatoin on actual ORNL Melton Valley Storage Tank (MVST) supernatant, Savannah River high-level waste supernatant, and Hanford supernatant. The latter two may be simulated by adding the appropriate chemicals and/or nuclides to the MVST supernatant

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)

Semiconductor Manufacturing equipment introduction

International Nuclear Information System (INIS)

Im, Jong Sun

2001-02-01

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

SU-8 Guiding Layer for Love Wave Devices

Directory of Open Access Journals (Sweden)

Michael I. Newton

2007-11-01

Full Text Available SU-8 is a technologically important photoresist used extensively for thefabrication of microfluidics and MEMS, allowing high aspect ratio structures to beproduced. In this work we report the use of SU-8 as a Love wave sensor guiding layerwhich allows the possibility of integrating a guiding layer with flow cell during fabrication.Devices were fabricated on ST-cut quartz substrates with a single-single finger design suchthat a surface skimming bulk wave (SSBW at 97.4 MHz was excited. SU-8 polymer layerswere successively built up by spin coating and spectra recorded at each stage; showing afrequency decrease with increasing guiding layer thickness. The insertion loss andfrequency dependence as a function of guiding layer thickness was investigated over thefirst Love wave mode. Mass loading sensitivity of the resultant Love wave devices wasinvestigated by deposition of multiple gold layers. Liquid sensing using these devices wasalso demonstrated; water-glycerol mixtures were used to demonstrate sensing of density-viscosity and the physical adsorption and removal of protein was also assessed usingalbumin and fibrinogen as model proteins.

The efficacy of Elekta Synergy image-guided radiotherapy

International Nuclear Information System (INIS)

Takamatsu, Shigeyuki; Takanaka, Tsuyoshi; Kumano, Tomoyasu

2008-01-01

We evaluated the efficacy of Elekta Synergy image-guided radiotherapy (IGRT) system equipped with cone beam CT (CBCT) for high accuracy radiation therapy. In cases set up with body marking who had large set up error could be adjusted by this system within 1 mm error. IGRT with CBCT correction provided precise set up. Elekta Synergy IGRT system is useful for high accuracy set up and will facilitate novel precise radiotherapy techniques. (author)

Safety analysis report for packaging onsite long-length contaminated equipment transport system

International Nuclear Information System (INIS)

McCormick, W.A.

1997-01-01

This safety analysis report for packaging describes the components of the long-length contaminated equipment (LLCE) transport system (TS) and provides the analyses, evaluations, and associated operational controls necessary for the safe use of the LLCE TS on the Hanford Site. The LLCE TS will provide a standardized, comprehensive approach for the disposal of approximately 98% of LLCE scheduled to be removed from the 200 Area waste tanks

Safety analysis report for packaging, onsite, long-length contaminated equipment transport system

Energy Technology Data Exchange (ETDEWEB)

McCormick, W.A.

1997-05-09

This safety analysis report for packaging describes the components of the long-length contaminated equipment (LLCE) transport system (TS) and provides the analyses, evaluations, and associated operational controls necessary for the safe use of the LLCE TS on the Hanford Site. The LLCE TS will provide a standardized, comprehensive approach for the disposal of approximately 98% of LLCE scheduled to be removed from the 200 Area waste tanks.

Vertical removable filters in shielded casing for radioactive cells and process gaseous wastes

International Nuclear Information System (INIS)

Prinz, M.

1983-01-01

The installation of shielded filtration casing is necessary for highly contaminated active cells and process gaseous wastes containing active aerosols. SGN and COGEMA have developed two filtration casings (for 500 and 3000 m 3 /h flow rates) equipped with a vertically removable filter element. The filter elements fitted with high efficiency glass fiber media, are cylindrical in shape. The top flange of the filter is equipped with a gasket to ensure sealing between the filter element and its casing. The filter element is blindly installed and removed and its orientation, inside the casing, is immaterial. The shielding casing is made of a cast iron, or steel, shielding slab under which is secured the filtration casing itself. This shielding slab is settled on side shielding walls made of concrete or cast iron. The filter element, integral with a plug, is placed in the horizontal slab. The attachment of the filter element under the plug is necessary so that the plug and filter may be removed as one unit, and to keep the filter on its sealing surfaces, according to sealing and seismic resistance requirements. Filter removal is performed with the help of an intervention cask, centered over a removable trap door provided on the shielding slab of the casing. First, the plug and filter element assembly is raised into the cask. Then, the filtering element may be separated from the plug which is decontaminated and salvaged. The whole plug and filter assembly may also be sent to the conditioning waste storage. The installation of a clean filter element in the casing, is also performed with the help of the intervention cask, proceeding as above, but in reverse order. The same intervention cask may also be used to remove the upstream and downstream dampers from the top of the casing

Heavenly bodies the photographer's guide to astrophotography

CERN Document Server

Krages, Esq, Bert P

2003-01-01

Detailing the photographic equipment and astronomical instruments needed to capture celestial images, this guide shows how astrophotography can be accessible to all photographers. Included is a detailed introduction to basic astronomy with information on mapping the sky, locating celestial bodies, and planning an expedition to photograph astronomical phenomena. Photographers learn how to determine the color sensitivity of various films and achieve the best possible exposure, how to ensure a captivating composition, and how commercially processed prints can support their artistic vision. Whethe

Endovascular treatment of iliofemoral deep vein thrombosis in pregnancy using US-guided percutaneous aspiration thrombectomy.

Science.gov (United States)

Gedikoglu, Murat; Oguzkurt, Levent

2017-01-01

We aimed to describe ultrasonography (US)-guided percutaneous aspiration thrombectomy in pregnant women with iliofemoral deep vein thrombosis. This study included nine pregnant women with acute and subacute iliofemoral deep vein thrombosis, who were severe symptomatic cases with massive swelling and pain of the leg. Patients were excluded from the study if they had only femoropopliteal deep vein thrombosis or mild symptoms of deep vein thrombosis. US-guided percutaneous aspiration thrombectomy was applied to achieve thrombus removal and uninterrupted venous flow. The treatment was considered successful if there was adequate venous patency and symptomatic relief. Complete or significant thrombus removal and uninterrupted venous flow from the puncture site up to the iliac veins were achieved in all patients at first intervention. Complete relief of leg pain was achieved immediately in seven patients (77.8%). Two patients (22.2%) had a recurrence of thrombosis in the first week postintervention. One of them underwent a second intervention, where percutaneous aspiration thrombectomy was performed again with successful removal of thrombus and establishment of in line flow. Two patients were lost to follow-up after birth. None of the remaining seven patients had rethrombosis throughout the postpartum period. Symptomatic relief was detected clinically in these patients. Endovascular treatment with US-guided percutaneous aspiration thrombectomy can be considered as a safe and effective way to remove thrombus from the deep veins in pregnant women with acute and subacute iliofemoral deep vein thrombosis.

Guiding flying-spot laser transepithelial phototherapeutic keratectomy with optical coherence tomography.

Science.gov (United States)

Li, Yan; Yokogawa, Hideaki; Tang, Maolong; Chamberlain, Winston; Zhang, Xinbo; Huang, David

2017-04-01

To analyze transepithelial phototherapeutic keratectomy (PTK) results using optical coherence tomography (OCT) and develop a model to guide the laser dioptric and depth settings. Casey Eye Institute, Portland, Oregon, USA. Prospective nonrandomized case series. Patients with superficial corneal opacities and irregularities had transepithelial PTK with a flying-spot excimer laser by combining wide-zone myopic and hyperopic astigmatic ablations. Optical coherence tomography was used to calculate corneal epithelial lenticular masking effects, guide refractive laser settings, and measure opacity removal. The laser ablation efficiency and the refractive outcome were investigated using multivariate linear regression models. Twenty-six eyes of 20 patients received PTK to remove opacities and irregular astigmatism due to scar, dystrophy, radial keratotomy, or previous corneal surgeries. The uncorrected distance visual acuity and corrected distance visual acuity were significantly improved (P laser ablation depths were 31.3% (myopic ablation) and 63.0% (hyperopic ablation) deeper than the manufacturer's nomogram. The spherical equivalent of the corneal epithelial lenticular masking effect was 0.73 diopter ± 0.61 (SD). The refractive outcome highly correlated to the laser settings and epithelial lenticular masking effect (Pearson R = 0.96, P < .01). The ablation rate of granular dystrophy opacities appeared to be slower. Smoothing ablation under masking fluid was needed to prevent focal steep islands in these cases. The OCT-measured ablation depth efficiency could guide opacity removal. The corneal epithelial lenticular masking effect could refine the spherical refractive nomogram to achieve a better refractive outcome after transepithelial ablation. Copyright © 2017 ASCRS and ESCRS. Published by Elsevier Inc. All rights reserved.

Investigational research on welfare equipment needs/seeds adaptation; Fukushi kiki needs seeds tekigo chosa kenkyu

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-03-01

At the advent of the aging society, investigated are images of welfare equipment to be developed. In the range where the use of welfare equipment is to be studied, the following are included: self care, excretion, transfer, and support of work other than care, as assistance to daily life; exercise function, communication function, and environment arrangement, as assistance to social participation. Of the images of the welfare equipment classified by the overall evaluation, the following are cited as what supports daily life: a lift usable even in the existing houses, a bump remover by which bumps in the house are removed without making large repairs, a urine collector for females, a training device to prevent urinary incontinence, reduction in the bed-fast elderly, a device to prevent bedsore, a system for safely watching demented old people, a system in which clothes are automatically washed, dried, and hanged on a hanger, etc. What supports social participation are a system for sports experience by virtual reality, sound user interface, etc. For the aged to be healthy physically and mentally, it is essential to be taken good care of and create things to live for by participating the society. For this, it is necessary that the government establish the public policies and that a people be conscious of welfare. 9 figs., 33 tabs.

Cutting of Control Rod Guide Tubes and Jet Pumps at Wuergassen NPP/ Germany

International Nuclear Information System (INIS)

Ralf Loock

2006-01-01

KWW Nuclear Power Plant has been erected and put into operation in the time period 1968 to end of 1971. In 23 years of operation about 73 billions kWh electric power have been generated. The electric rated power was 670 MW. In May 1995 the decommission was started for economical reasons, since April 1997 the demolition is in progress. In autumn 2003 FANP has been called upon to cut the Control Rod Guide Tubes and Jet Pumps. After a 10 months preparatory phase, cutting of the Control Rod Guide Tubes and Jet Pumps was started in September 2004. For radiation protection reasons the Control Rod Guide Tubes and Jet Pumps were cut and packed remote controlled under water. The cutting process had been selected particularly under consideration of radiation protection aspects. A combination of the technologies band sawing and nibbling was assigned for cutting of the Control Rod Guide Tubes and Jet Pumps. The band saw consists of a substructure and of a feed system installed on it. The feed system can be equipped with one or two band saws optionally. A turntable is integrated in the substructure. It is used to support the CRGT respectively the residual piece of the CRGT and to move it out of the cut position after finishing the cutting. After getting the agreement to the specification, the equipment has been designed and manufactured according to the specification preferences. After finishing the internal testing, the factory acceptance test as well as acceptance and functional tests of every facility were carried out. After cold testing being performed successfully, the cutting equipment was installed in the NPP and checked for operational safety additionally. Cutting of the Control Rod Guide Tubes and Jet Pumps has been carried out on two working places inside the fuel element storage pool. During the total project duration on site the processing has been supervised by the radiation protection staff permanently. As a result 110 Control Rod Guide Tubes and 18 Jet Pumps were

Y.E.S. International Entomology Resource Guide. Second Edition. Special Publication No. 2.

Science.gov (United States)

Dunn, Gary A., Comp.

This resource guide is designed to provide Young Entomologists' Society (Y.E.S.) members and other interested entomologists with information on people and companies that sell entomological equipment, supplies, services, preserved and dried specimens, livestock, books, publications, slides and other visuals, gift or novelty items, and…

Development of a fast-water field guide

International Nuclear Information System (INIS)

Hansen, K.A.

2001-01-01

There are several manuals for oil spill response, but few have information on fast-water conditions. Between 1992 and 1997, approximately 58 per cent of all the oil spilled by volume in the United States happened in waterways with currents exceeding one knot, and the Coast Guard recognized the absence of standard terminology that could be used for fast-water responses. For that reason, an initiative was undertaken to create a document that addresses only fast-water issues. The resulting field guide can be used for training or responding to spills in fast-water. The user must rely on other manuals for issues on toxicity and shoreline cleanup as well as local contingency and site safety plans. The fast-water guide allows on-scene commanders and area supervisors the ability to define techniques and terminology for the responders in the field. It is particularly useful for Coast Guard Marine Safety Units when working with Coast Guard operational units during an emergency response. The current version of the guide that is under review by the working group contains 9 chapters and 9 appendices. The guide includes a decision-matrix that identifies various fat-water scenarios and provides recommended strategies. It then links to other sections of the document that contain details about the necessary equipment configurations. Photographs are provided to reinforce the concepts. The guide includes a checklist of the issues that must be addressed in any spill, such as weather and nature of the spill with some fast water issues added. Links to appropriate Internet sites are also included in the guide. Information within the guide can be condensed to one sheet for use in the field. 9 refs., 4 tabs., 11 figs

Space Heating Equipment

Energy Technology Data Exchange (ETDEWEB)

Rafferty, Kevin D.

1998-01-01

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

Italian WEEE management system and treatment of end-of-life cooling and freezing equipments for CFCs removal

Energy Technology Data Exchange (ETDEWEB)

Sansotera, M., E-mail: maurizio.sansotera@polimi.it [Dipartimento di Chimica, Materiali e Ingegneria Chimica, Politecnico di Milano, via Mancinelli 7, I-20131 Milano (Italy); Istituto Nazionale di Scienza e Tecnologia dei Materiali (INSTM), via Giusti 9, I-50121 Firenze (Italy); Navarrini, W. [Dipartimento di Chimica, Materiali e Ingegneria Chimica, Politecnico di Milano, via Mancinelli 7, I-20131 Milano (Italy); Istituto Nazionale di Scienza e Tecnologia dei Materiali (INSTM), via Giusti 9, I-50121 Firenze (Italy); Talaeemashhadi, S.; Venturini, F. [Dipartimento di Chimica, Materiali e Ingegneria Chimica, Politecnico di Milano, via Mancinelli 7, I-20131 Milano (Italy)

2013-06-15

Highlights: • Italian data about WEEE management in the period 2005–2010 have been reported. • In 2001–2004 CFC release was monitored and Po Valley resulted as main source region. • The Italian directive on WEEE management was enacted in 2005 but took effect in 2008. • The CFC analytic procedures of the audit assessments have been discussed. - Abstract: This study presents and analyzes the data of the Italian system for take-back and recovery of waste electrical and electronic equipments (WEEEs) in the start-up period 2008–2010. The analysis was focused particularly on the data about the treatment of end-of-life cooling and freezing equipments. In fact, the wastes of cooling and freezing equipments have a high environmental impact. Indeed, in their compressor oil and insulation polyurethane (PU) foams chlorofluorocarbon (CFC) ozone-depleting gases are still present. In the period 2001–2004 Northern Italy resulted the main source in Europe of CFCs. The European Directive on WEEE management was enacted in 2002, but in Italy it was implemented by the legislative Decree in 2005 and it became operational in 2008. Actually, in 2008 the national WEEE Coordination Centre was founded in order to organize the WEEE pick-up process and to control collection, recovery and recycling targets. As a result, in 2010 the average WEEE collection per capita exceeded the threshold of more than 4 kg per inhabitant, as well as cooling and freezing appliances represented more than one fourth of the Italian WEEE collection stream. During the treatment of end-of-life cooling and freezing equipments, CFCs were recovered and disposed principally by burner methods. The analyses of defined specimens collected in the treatment facilities were standardized to reliably determine the amount of recovered CFCs. Samples of alkaline solid salt, alkaline saline solution, polyurethane matrix and compressor oil collected during the audit assessment procedure were analyzed and the results

PWR fuel monitoring: recent progress with hot cells' examination equipment

International Nuclear Information System (INIS)

Chenebault, P.

1989-01-01

The 'hot' laboratories set up by the French Atomic Energy Authority (CEA) in its nuclear research centers at Saclay and Grenoble, and by the French Electricity Board (EDF) on the Chinon nuclear power station site, are used for dismantling and examining fuel rod assemblies irradiated in PWRs. This article is limited to a description of a number of new or totally updated items of equipment in these laboratories. Nuclear industry companies are also participating in the development of new examination techniques. As an example, the use of wave-guides for remote transmission of signals in a radioactive environment is described. 2 figs

Safety inspection guide, Mod III (a systematic approach to conducting a safety inspection)

International Nuclear Information System (INIS)

Davidson, J.E.

1977-06-01

This guide was developed as a comprehensive/systematic approach to the problem of performing a safety inspection. Five basic sections (categories) are considered in the guide: physical work place; machines/mechanical equipment; hazardous materials/processes/environments; energy sources; and management hazard . control factors. The basic concept is that one starts evaluating hazard potentials from the physical work place and continues considering other elements as they are added to the physical work place. This approach provides a better understanding of the interfaces of each section to the entire group. The guide is supported by an Area Safety Inspection Result form to record defects or conditions found, the evaluation (best estimate) of the urgency or priority for correcting deficiencies or areas of noncompliance, and the status of corrective action. Additionally, the guide serves as an educational tool in accident prevention for supervisors and employees

Criticality safety aspects of K-25 Building uranium deposit removal

International Nuclear Information System (INIS)

Haire, M.J.; Jordan, W.C.; Ingram, J.C. III; Stinnet, E.C. Jr.

1995-01-01

The K-25 Building of the Oak Ridge Gaseous Diffusion Plant (now the K-25 Site) went into operation during World War II as the first large scale production plant to separate 235 U from uranium by the gaseous diffusion process. It operated successfully until 1964, when it was placed in a stand-by mode. The Department of Energy has initiated a decontamination and decommissioning program. The primary objective of the Deposit Removal (DR) Project is to improve the nuclear criticality safety of the K-25 Building by removing enriched uranium deposits from unfavorable-geometry process equipment to below minimum critical mass. The method utilized to accomplish this are detailed in this report

Criticality safety aspects of K-25 Building uranium deposit removal

Energy Technology Data Exchange (ETDEWEB)

Haire, M.J.; Jordan, W.C. [Oak Ridge National Lab., TN (United States); Ingram, J.C. III; Stinnet, E.C. Jr. [Oak Ridge K-25 Site, TN (United States)

1995-12-31

The K-25 Building of the Oak Ridge Gaseous Diffusion Plant (now the K-25 Site) went into operation during World War II as the first large scale production plant to separate {sup 235}U from uranium by the gaseous diffusion process. It operated successfully until 1964, when it was placed in a stand-by mode. The Department of Energy has initiated a decontamination and decommissioning program. The primary objective of the Deposit Removal (DR) Project is to improve the nuclear criticality safety of the K-25 Building by removing enriched uranium deposits from unfavorable-geometry process equipment to below minimum critical mass. The method utilized to accomplish this are detailed in this report.

Theoretical Analysis and Experimental Study on the Coating Removal from Passenger-Vehicle Plastics for Recycling by Using Water Jet Technology

Science.gov (United States)

Zhang, Hongshen; Chen, Ming

2015-11-01

The recovery and utilization of automotive plastics are a global concern because of the increasing number of end-of-life vehicles. In-depth studies on technologies for the removal of coatings from automotive plastics can contribute to the high value-added levels of the recycling and utilization of automotive plastic. The liquid waste generated by removing chemical paint by using traditional methods is difficult to handle and readily produces secondary pollution. Therefore, new, clean, and highly efficient techniques of paint removal must be developed. In this article, a method of coating removal from passenger-vehicle plastics was generated based on high-pressure water jet technology to facilitate the recycling of these plastics. The established technology was theoretically analyzed, numerically simulated, and experimentally studied. The high-pressure water jet equipment for the removal of automotive-plastic coatings was constructed through research and testing, and the detailed experiments on coating removal rate were performed by using this equipment. The results showed that high-pressure water jet technology can effectively remove coatings on the surfaces of passenger-vehicle plastics. The research also revealed that the coating removal rate increased as jet pressure ( P) increased and then decreased when jet moving speed ( Vn) increased. The rate decreased as the distance from nozzle to work piece ( S nw ) and the nozzle angle ( Φ) increased. The mathematical model for the rate of removal of coatings from bumper surfaces by water jet was derived based on the experiment data and can effectively predict coating removal rate under different operating conditions.

Enhanced removal of radioactive particles by fluorocarbon surfactant solutions

International Nuclear Information System (INIS)

Kaiser, R.; Harling, O.K.

1993-08-01

The proposed research addressed the application of ESI's particle removal process to the non-destructive decontamination of nuclear equipment. The cleaning medium used in this process is a solution of a high molecular weight fluorocarbon surfactant in an inert perfluorinated liquid which results in enhanced particle removal. The perfluorinated liquids of interest, which are recycled in the process, are nontoxic, nonflammable, and environmentally compatible, and do not present a hazard to the ozone layer. The information obtained in the Phase 1 program indicated that the proposed ESI process is technically effective and economically attractive. The fluorocarbon surfactant solutions used as working media in the ESI process survived exposure of up to 10 Mrad doses of gamma rays, and are considered sufficiently radiation resistant for the proposed process. Ultrasonic cleaning in perfluorinated surfactant solutions was found to be an effective method of removing radioactive iron (Fe 59) oxide particles from contaminated test pieces. Radioactive particles suspended in the process liquids could be quantitatively removed by filtration through a 0.1 um membrane filter. Projected economics indicate a pre-tax pay back time of 1 month for a commercial scale system

Careers in Industrial Sewing for the Apparel Manufacturing Industry: Teacher-Student Guide.

Science.gov (United States)

American Apparel Manufacturers Association, Arlington, VA. Education Committee.

The teacher-student guide has been developed as a service to schools in an effort to help them organize and operate meaningful courses in apparel manufacturing. For the school it furnishes practical information in implementing the course, such as facility design, equipment requirements, and teacher selection. For the teacher it provides a…

The Campcraft Book: A Beginner's Guide to Outdoor Living Skills. Revised Edition.

Science.gov (United States)

Hammett, Catherine T.

This handbook contains information designed to help develop campcraft skills. This basic guide to outdoor living contains the following chapters: (1) Come On Out; (2) On the Trail; (3) Your Own Outdoor Equipment; (4) Campcraft Skills; (5) Fire Building and Fireplaces; (6) Outdoor Food; (7) Knotcraft; (8) Lashing; (9) Toolcraft; (10) Finding Your…

Watershed restoration: planning and implementing small dam removals to maximize ecosystem services

Science.gov (United States)

Tonitto, C.; Riha, S. J.

2016-12-01

River restoration and enhancing watershed connectivity is of growing concern in industrialized nations. The past two decades have seen a number of small dam removals, though many removals remain unstudied and poorly documented. We summarize socio-economic and biophysical lessons learned during the past two decades of accelerated activity regarding small dam removals throughout the United States. We present frameworks for planning and implementing removals developed by interdisciplinary engagement. Toward the goal of achieving thorough dam removal planning, we present outcomes from well-documented small dam removals covering ecological, chemical, and physical change in rivers post-dam removal, including field observation and modeling methodologies. Guiding principles of a dam removal process should include: 1) stakeholder engagement to navigate the complexity of watershed landuse, 2) an impacts assessment to inform the planning process, 3) pre- and post-dam removal observations of ecological, chemical and physical properties, 4) the expectation that there are short- and long-term ecological dynamics with population recovery depending on whether dam impacts were largely related to dispersion or to habitat destruction, 5) an expectation that changes in watershed chemistry are dependent on sediment type, sediment transport and watershed landuse, and 6) rigorous assessment of physical changes resulting from dam removal, understanding that alteration in hydrologic flows, sediment transport, and channel evolution will shape ecological and chemical dynamics, and shape how stakeholders engage with the watershed.

HyRAM V1.0 User Guide

Energy Technology Data Exchange (ETDEWEB)

Groth, Katrina M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Zumwalt, Hannah Ruth [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Clark, Andrew Jordan [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-03-01

Hydrogen Risk Assessment Models (HyRAM) is a prototype software toolkit that integrates data and methods relevant to assessing the safety of hydrogen fueling and storage infrastructure. The HyRAM toolkit integrates deterministic and probabilistic models for quantifying accident scenarios, predicting physical effects, and characterizing the impact of hydrogen hazards, including thermal effects from jet fires and thermal pressure effects from deflagration. HyRAM version 1.0 incorporates generic probabilities for equipment failures for nine types of components, and probabilistic models for the impact of heat flux on humans and structures, with computationally and experimentally validated models of various aspects of gaseous hydrogen release and flame physics. This document provides an example of how to use HyRAM to conduct analysis of a fueling facility. This document will guide users through the software and how to enter and edit certain inputs that are specific to the user-defined facility. Description of the methodology and models contained in HyRAM is provided in [1]. This User’s Guide is intended to capture the main features of HyRAM version 1.0 (any HyRAM version numbered as 1.0.X.XXX). This user guide was created with HyRAM 1.0.1.798. Due to ongoing software development activities, newer versions of HyRAM may have differences from this guide.

High Temperature Calcination - MACT Upgrade Equipment Pilot Plant Test

Energy Technology Data Exchange (ETDEWEB)

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

2004-02-01

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

The ViewRay system: magnetic resonance-guided and controlled radiotherapy.

Science.gov (United States)

Mutic, Sasa; Dempsey, James F

2014-07-01

A description of the first commercially available magnetic resonance imaging (MRI)-guided radiation therapy (RT) system is provided. The system consists of a split 0.35-T MR scanner straddling 3 (60)Co heads mounted on a ring gantry, each head equipped with independent doubly focused multileaf collimators. The MR and RT systems share a common isocenter, enabling simultaneous and continuous MRI during RT delivery. An on-couch adaptive RT treatment-planning system and integrated MRI-guided RT control system allow for rapid adaptive planning and beam delivery control based on the visualization of soft tissues. Treatment of patients with this system commenced at Washington University in January 2014. Copyright © 2014 Elsevier Inc. All rights reserved.

10 CFR 50.34a - Design objectives for equipment to control releases of radioactive material in effluents-nuclear...

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Design objectives for equipment to control releases of... out in appendix I to this part provide numerical guidance on design objectives for light-water-cooled... unrestricted areas be kept as low as is reasonably achievable. These numerical guides for design objectives and...

Recent developments in methodology for dynamic qualification of nuclear plant equipment

International Nuclear Information System (INIS)

Kana, D.D.; Pomerening, D.J.

1984-01-01

Dynamic qualification of nuclear plant electrical and mechanical equipment is performed basically under guidelines given in IEEE Standards 323 and 344, and a variety of NRC regulatory guides. Over the last fifteen years qualification methodology prescribed by these documents has changed significantly as interpretations, equipment capability, and imagination of the qualification engineers have progressed. This progress has been sparked by concurrent NRC and industry sponsored research programs that have identified anomalies and developed new methodologies for resolving them. Revisions of the standards have only resulted after a lengthy debate of all such new information and subsequent judgment of its validity. The purpose of this paper is to review a variety of procedural improvements and developments in qualification methodology that are under current consideration as revisions to the standards. Many of the improvements and developments have resulted from recent research programs. All are very likely to appear in one type of standard or another in the near future

Export control guide: Spent nuclear fuel reprocessing and preparation of plutonium metal

International Nuclear Information System (INIS)

1993-10-01

The international Treaty on the Non-Proliferation of Nuclear Weapons, also referred to as the Non-Proliferation Treaty (NPT), states in Article III, paragraph 2(b) that open-quotes Each State Party to the Treaty undertakes not to provide . . . equipment or material especially designed or prepared for the processing, use or production of special fissionable material to any non-nuclear-weapon State for peaceful purposes, unless the source or special fissionable material shall be subject to the safeguards required by this Article.close quotes This guide was prepared to assist export control officials in the interpretation, understanding, and implementation of export laws and controls relating to the international Trigger List for irradiated nuclear fuel reprocessing equipment, components, and materials. The guide also contains information related to the production of plutonium metal. Reprocessing and its place in the nuclear fuel cycle are described briefly; the standard procedure to prepare metallic plutonium is discussed; steps used to prepare Trigger List controls are cited; descriptions of controlled items are given; and special materials of construction are noted. This is followed by a comprehensive description of especially designed or prepared equipment, materials, and components of reprocessing and plutonium metal processes and includes photographs and/or pictorial representations. The nomenclature of the Trigger List has been retained in the numbered sections of this document for clarity

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

Directory of Open Access Journals (Sweden)

Richard C. Millar

2012-01-01

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

Review of Real-Time 3-Dimensional Image Guided Radiation Therapy on Standard-Equipped Cancer Radiation Therapy Systems: Are We at the Tipping Point for the Era of Real-Time Radiation Therapy?

Science.gov (United States)

Keall, Paul J; Nguyen, Doan Trang; O'Brien, Ricky; Zhang, Pengpeng; Happersett, Laura; Bertholet, Jenny; Poulsen, Per R

2018-04-14

To review real-time 3-dimensional (3D) image guided radiation therapy (IGRT) on standard-equipped cancer radiation therapy systems, focusing on clinically implemented solutions. Three groups in 3 continents have clinically implemented novel real-time 3D IGRT solutions on standard-equipped linear accelerators. These technologies encompass kilovoltage, combined megavoltage-kilovoltage, and combined kilovoltage-optical imaging. The cancer sites treated span pelvic and abdominal tumors for which respiratory motion is present. For each method the 3D-measured motion during treatment is reported. After treatment, dose reconstruction was used to assess the treatment quality in the presence of motion with and without real-time 3D IGRT. The geometric accuracy was quantified through phantom experiments. A literature search was conducted to identify additional real-time 3D IGRT methods that could be clinically implemented in the near future. The real-time 3D IGRT methods were successfully clinically implemented and have been used to treat more than 200 patients. Systematic target position shifts were observed using all 3 methods. Dose reconstruction demonstrated that the delivered dose is closer to the planned dose with real-time 3D IGRT than without real-time 3D IGRT. In addition, compromised target dose coverage and variable normal tissue doses were found without real-time 3D IGRT. The geometric accuracy results with real-time 3D IGRT had a mean error of real-time 3D IGRT methods using standard-equipped radiation therapy systems that could also be clinically implemented. Multiple clinical implementations of real-time 3D IGRT on standard-equipped cancer radiation therapy systems have been demonstrated. Many more approaches that could be implemented were identified. These solutions provide a pathway for the broader adoption of methods to make radiation therapy more accurate, impacting tumor and normal tissue dose, margins, and ultimately patient outcomes. Copyright © 2018

The telescopic tourist's guide to the Moon

CERN Document Server

May, Andrew

2017-01-01

Whether you’re interested in visiting Apollo landing sites or the locations of classic sci-fi movies, this is the tourist guide for you! This tourist guide has a twist – it is a guide to a whole different world, which you can visit from the comfort of your backyard with the aid of nothing more sophisticated than an inexpensive telescope. It tells you the best times to view the Moon, the most exciting sights to look out for, and the best equipment to use, allowing you to snap stunning photographs as well as view the sights with your own eyes. Have you ever been inspired by stunning images from the Hubble telescope, or the magic of sci-fi special effects, only to look through a small backyard telescope at the disappointing white dot of a planet or faint blur of a galaxy? Yet the Moon is different. Seen through even a relatively cheap telescope, it springs into life like a real place, with mountains and valleys and rugged craters. With a bit of imagination, you can even picture yourself as a sightseeing visi...