Proceedings of the twelfth target fabrication specialists' meeting

International Nuclear Information System (INIS)

1999-01-01

Research in fabrication for inertial confinement fusion (ICF) comprises at least three broad categories: targets for high energy density physics on existing drivers, ignition capsule fabrication, and cryogenic fuel layer formation. The latter two are being pursued primarily for the National Ignition Facility (NIF). Scientists from over 14 laboratories, universities, and businesses contributed over 100 papers on all aspects of ICF target fabrication. The NIF is well along in construction and photos of poured concrete and exposed steel added to the technical excitement. It was clear from the meeting that there has been significant progress toward the fabrication of an ignition target for NIF and that new techniques are resulting in higher quality targets for high energy density research

Evaluation methodology for generator refurbishment decisions

International Nuclear Information System (INIS)

Moore, W.G.; Ulm, S.F.

1991-01-01

The Electrical Power Industry is undergoing tremendous change due to deregulation, aging equipment, environmental concerns, and investment/risk considerations. Public utility commissions, along with shareholders and end consumers, are closely monitoring utilities; decisions, especially in the area of costs-both Operation and Maintenance, and Capital. Increasing emphasis, within the conventional utility environment, has been and continue to be, placed on controlling expenditures. To be responsive to these industry and competitive pressures, utilities must make equipment refurbishment decisions. These decisions should be based on input from many sources, including the severity of the failure, cost of replacement versus refurbishment, risks and safety considerations, the expected remaining life of the unit, operational mode (base or peak), fuel type, initial costs, system capacity, available budgets, and financing options. Many times, however, refurbishment decisions are base don an abstract understanding of the above, but feel, or emotional attachment to a particular option. This paper describes a general methodology for refurbishment decision making, applied specifically to generators. Also included in a case history of one utility's progression through this process

Possible refurbishment of Point Lepreau

International Nuclear Information System (INIS)

White, R.M.; Groom, S.H.; Thompson, P.D.; Barclay, J.M.; Allen, P.J.

2001-01-01

In February 2000, the NB Power Board of Directors approved Phase one of a project to produce a business case including a detailed scope and estimate associated with the possible refurbishment of the Point Lepreau Generating Station (PLGS). The Preliminary plan for refurbishment projects an 18-month outage starting as early as the spring of 2006. If the station were to be refurbished, then it would be run for another 25 to 30 years. The decision on whether or not to refurbish PLGS has not been made and is not expected until the summer of 2002. The results of the first phase of the project will be used to prepare a detailed business case that will be presented to the NB Power board of directors in January of 2002. At that time a decision will be made as to whether to refurbish the unit, or obtain other means of replacing the energy produced by PLGS. The station currently produces about a third of the power generated within the province. If the business case is approved, all-380 Pressure Tubes and Calandria Tubes, along with their related End Fittings and Feeders would be replaced. This material would be stored in new storage vaults to be constructed at the existing on-site Waste Management Facility. Replacement of other station components will be performed as required, as determined from the results of a comprehensive Plant Condition Assessment. The condition assessments build on work done under the Plant Life Management Program. Point Lepreau Generating Station has operated well since start of commercial operation in early 1983. With a lifetime capacity factor of about 84% (up to the end of 2000), it has proven to be an economic and environmentally sound electricity provider. The station has also had a significant positive economic impact in Southern New Brunswick, employing over 600 people. However the Pressure Tubes and Feeders are nearing the point in time in which they will exceed their fitness for service criteria. Although tubes can be replaced on an

Possible refurbishment of Point Lepreau

International Nuclear Information System (INIS)

White, R.M.; Groom, S.H.; Thompson, P.D.; Barclay, J.M.; Allen, P.J.

2001-01-01

In February 2000, the NB Power Board of Directors approved Phase one of a project to produce a business case including a detailed scope and estimate associated with the possible refurbishment of the Point Lepreau Generating Station (PLGS). The Preliminary plan for refurbishment projects an 18-month outage starting as early as the spring of 2006. If the station were to be refurbished, then it would be run for another 25 to 30 years. The decision on whether or not to refurbish PLGS has not been made and is not expected until the summer of 2002. The results of the first phase of the project will be used to prepare a detailed business case that will be presented to the NB Power board of directors in January of 2002. At that time a decision will be made as to whether to refurbish the unit, or obtain other means of replacing the energy produced by PLGS. The station currently produces about a third of the power generated within the province. If the business case is approved, all-380 Pressure Tubes and Calandria Tubes, along with their related End Fittings and Feeders would be replaced. This material would be stored in new storage vaults to be constructed at the existing on-site Waste Management Facility. Replacement of other station components will be performed as required, as determined from the results of a comprehensive Plant Condition Assessment. The condition assessments build on work done under the Plant Life Management Program. Point Lepreau Generating Station has operated well since start of commercial operation in early 1983. With a lifetime capacity factor of about 84% (up to the end of 2000), it has proven to be an economic and environmentally sound electricity provider. The station has also had a significant positive economic impact in Southern New Brunswick, employing over 600 people. However the Pressure Tubes and Feeders are nearing the point in time in which they will exceed their fitness for service criteria. Although tubes can be replaced on an

FABRICATION AND CHARACTERIZATION OF FAST IGNITION TARGETS

International Nuclear Information System (INIS)

HILL, D.W; CASTILLO, E; CHEN, K.C; GRANT, S.E; GREENWOOD, A.L; KAAE, J.L; NIKROO, A; PAGUIO, S.P; SHEARER, C; SMITH, J.N Jr.; STEPHENS, R.B; STEINMAN, D.A; WALL, J.

2003-09-01

OAK-B135 Fast ignition is a novel scheme for achieving laser fusion. A class of these targets involves cone mounted CH shells. The authors have been fabricating such targets with shells with a wide variety of diameters and wall thicknesses for several years at General Atomics. In addition, recently such shells were needed for implosion experiments at Laboratory for Laser Energetics (LLE) that for the first time were required to be gas retentive. Fabrication of these targets requires producing appropriate cones and shells, assembling the targets, and characterization of the assembled targets. The cones are produced using micromachining and plating techniques. The shells are fabricated using the depolymerizable mandrel technique followed by micromachining a hole for the cone. The cone and the shell then need to be assembled properly for gas retention and precisely in order to position the cone tip at the desired position within the shell. Both are critical for the fast ignition experiments. The presence of the cone in the shell creates new challenges in characterization of the assembled targets. Finally, for targets requiring a gas fill, the cone-shell assembly needs to be tested for gas retention and proper strength at the glue joint. This paper presents an overview of the developmental efforts and technical issues addressed during the fabrication of fast ignition targets

Integration of remote refurbishment performed on ITER components

Energy Technology Data Exchange (ETDEWEB)

Dammann, A., E-mail: alexis.dammann@iter.org [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Antola, L. [AMEC, 31 Parc du Golf, CS 90519, 13596 Aix en Provence (France); Beaudoin, V. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Dremel, C. [Westinghouse, Electrique France/Astare, 122 Avenue de Hambourg, 13008 Marseille (France); Evrard, D. [SOGETI High Tech, 180 Rue René Descartes, 13851 Aix en Provence (France); Friconneau, J.P. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Lemée, A. [SOGETI High Tech, 180 Rue René Descartes, 13851 Aix en Provence (France); Levesy, B.; Pitcher, C.S. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France)

2015-10-15

Highlights: • System engineering approach to consolidate requirements to modify the layout of the Hot Cell. • Illustration of the loop between requirement and design. • Verification process. - Abstract: Internal components of the ITER Tokamak are replaced and transferred to the Hot Cell by remote handling equipment. These components include port plugs, cryopumps, divertor cassettes, blanket modules, etc. They are brought to the refurbishment area of the ITER Hot Cell Building for cleaning and maintenance, using remote handling techniques. The ITER refurbishment area will be unique in the world, when considering combination of size, quantity of complex component to refurbish in presence of radiation, activated dust and tritium. The refurbishment process to integrate covers a number of workstations to perform specific remote operations fully covered by a mast on crane system. This paper describes the integration of the Refurbishment Area, explaining the functions, the methodology followed, some illustrations of trade-off and safety improvements.

Multivariant design and multiple criteria analysis of building refurbishments

Energy Technology Data Exchange (ETDEWEB)

Kaklauskas, A.; Zavadskas, E. K.; Raslanas, S. [Faculty of Civil Engineering, Vilnius Gediminas Technical University, Vilnius (Lithuania)

2005-07-01

In order to design and realize an efficient building refurbishment, it is necessary to carry out an exhaustive investigation of all solutions that form it. The efficiency level of the considered building's refurbishment depends on a great many of factors, including: cost of refurbishment, annual fuel economy after refurbishment, tentative pay-back time, harmfulness to health of the materials used, aesthetics, maintenance properties, functionality, comfort, sound insulation and longevity, etc. Solutions of an alternative character allow for a more rational and realistic assessment of economic, ecological, legislative, climatic, social and political conditions, traditions and for better the satisfaction of customer requirements. They also enable one to cut down on refurbishment costs. In carrying out the multivariant design and multiple criteria analysis of a building refurbishment much data was processed and evaluated. Feasible alternatives could be as many as 100,000. How to perform a multivariant design and multiple criteria analysis of alternate alternatives based on the enormous amount of information became the problem. Method of multivariant design and multiple criteria of a building refurbishment's analysis were developed by the authors to solve the above problems. In order to demonstrate the developed method, a practical example is presented in this paper. (author)

Fabrication and replacement work of beryllium frame and gamma-ray shield

International Nuclear Information System (INIS)

Watahiki, Shunsuke; Hanawa, Yoshio; Asano, Norikazu; Hiyama, Kazuhisa; Ito, Sachito; Tsuboi, Kazuaki; Fukasaku, Akitomi

2012-03-01

This replacement work was carried out under refurbishment plan of JMTR for beryllium distortion draw to acceptable limit. And gamma-ray shield refurbishment was carried out the view point of prevention maintenance in consideration of operation plan. Fabrication of beryllium frame and gamma-ray shield was spent for two years it was finished in February, 2010. It took five months to replacement work from January 2010. In this report is presented fabrication and replacement work of beryllium frame and gamma-ray shield. (author)

Target fabrication using laser and spark erosion machining

International Nuclear Information System (INIS)

Clement, X.; Coudeville, A.; Eyharts, P.; Perrine, J.P.; Rouillard, R.

1982-01-01

Fabrication of laser fusion targets requires a number of special techniques. We have developed both laser and spark erosion machining to produce minute parts of complex targets. A high repetition rate YAG laser at double frequency is used to etch various materials. For example, marks or patterns are often necessary on structured or advanced targets. The laser is also used to thin down plastic coated stalks. A spark erosion system has proved to be a versatile tool and we describe current fabrication processes like cutting, drilling, and ultra precise machining. Spark erosion has interesting features for target fabrication: it is a highly controllable and reproducible technique as well as relatively inexpensive

Laser target fabrication, structure and method for its fabrication

Science.gov (United States)

Farnum, Eugene H.; Fries, R. Jay

1985-01-01

The disclosure is directed to a laser target structure and its method of fabrication. The target structure comprises a target plate containing an orifice across which a pair of crosshairs are affixed. A microsphere is affixed to the crosshairs and enclosed by at least one hollow shell comprising two hemispheres attached together and to the crosshairs so that the microsphere is juxtapositioned at the center of the shell.

Last PS magnet refurbished

CERN Multimedia

2009-01-01

PS Magnet Refurbishment Programme Completed. The 51st and final refurbished magnet was transported to the PS on Tuesday 3 February. The repair and consolidation work on the PS started back in 2003 when two magnets and a busbar connection were found to be faulty during routine high-voltage tests. The cause of the fault was a combination of age and radiation on electrical insulation. After further investigation the decision was taken to overhaul half of the PS’s 100 magnets to reduce the risk of a similar fault. As from 20 February the PS ring will start a five-week test programme to be ready for operation at the end of March.

Refurbishment of BR2 (Phases 4 and 5)

Energy Technology Data Exchange (ETDEWEB)

Gubel, P.; Dekeyser, J.; Van Der Auwera, J

1998-07-01

The BR2 is a materials testing reactor and is SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In phase 4 of the refurbishment programme, various activities were performed to allow reactor start-up. In phase 5, remaining refurbishment works were carried out as well as the extra studies and upgradings required by the licensing authorities. Major achievements in 1997 are described and discussed.

Refurbishment of BR2 (Phases 4 and 5)

International Nuclear Information System (INIS)

Gubel, P.; Dekeyser, J.; Van Der Auwera, J.

1998-01-01

The BR2 is a materials testing reactor and is SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In phase 4 of the refurbishment programme, various activities were performed to allow reactor start-up. In phase 5, remaining refurbishment works were carried out as well as the extra studies and upgradings required by the licensing authorities. Major achievements in 1997 are described and discussed

Refurbishment of BR2 (Phases 4 and 5)

Energy Technology Data Exchange (ETDEWEB)

Gubel, P; Dekeyser, J; Van Der Auwera, J

1998-07-01

The BR2 is a materials testing reactor and is SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In phase 4 of the refurbishment programme, various activities were performed to allow reactor start-up. In phase 5, remaining refurbishment works were carried out as well as the extra studies and upgradings required by the licensing authorities. Major achievements in 1997 are described and discussed.

I and C systems refurbishment projects for plant life extension

International Nuclear Information System (INIS)

Andrashov, A.A.; Sklyar, V.V.; Siora, A.A.

2012-01-01

This paper describes the approach to implementation of Nuclear Power Plants (NPPs) Instrumentation and Control (I and C) systems refurbishment projects using Field Programmable Gate Array (FPGA)-based platform. The analysis identifying advantages of refurbishment projects for NPPs is performed. The main goals of the utilities with respect to refurbishment of NPPs I and C systems are outlined. The advantages of FPGA technology application for NPP I and C systems are described. Regulatory framework of FPGA technology for NPPs I and C systems is presented. General principles which may be used for implementation of NPPs I and C system refurbishment projects are presented. The experience of Research and Production Corporation (RPC) Radiy in implementation of NPPs I and C system refurbishment projects is considered. (author)

Sustainable refurbishment of exterior walls and building facades. Final report, Part B - General refurbishment concepts

Energy Technology Data Exchange (ETDEWEB)

Vares, S.; Pulakka, S.; Toratti, T. [and others

2012-11-01

This report is the second part of the final report of Sustainable refurbishment of building facades and exterior walls (SUSREF). SUSREF project was a collaborative (small/medium size) research project within the 7th Framework Programme of the Commission and it was financed under the theme Environment (including climate change) (Grant agreement no. 226858). The project started in October 1st 2009 and ended in April 30th 2012. The project included 11 partners from five countries. SUSREF developed sustainable concepts and technologies for the refurbishment of building facades and external walls. This report together with SUSREF Final report Part B and SUSREF Final Report Part C introduce the main results of the project. Part A focuses on methodological issues. The descriptions of the concepts and the assessment results of the developed concepts are presented in SUSREF Final report part B (generic concepts) and SUSREF Final report Part C (SME concepts). The following list shows the sustainability assessment criteria defined by the SUSREF project. These are Durability; Impact on energy demand for heating; Impact on energy demand for cooling; Impact on renewable energy use potential; Impact on daylight; Environmental impact of manufacture and maintenance; Indoor air quality and acoustics; Structural stability; Fire safety; Aesthetic quality; Effect on cultural heritage; Life cycle costs; Need for care and maintenance; Disturbance to the tenants and to the site; Buildability. This report presents sustainability assessment results of general refurbishment concepts and gives recommendations on the basis of the results. The report covers the following refurbishment cases - External insulation - Internal insulation - Cavity wall insulation - Replacement Insulation during renovation.

Refurbishment of JMTR pure water facility

International Nuclear Information System (INIS)

Asano, Norikazu; Hanakawa, Hiroki; Kusunoki, Hidehiko; Satou, Shinichi

2012-05-01

In the refurbishment of JMTR, facilities were classified into which (1) were all updated, (2) were partly updated, and (3) were continuance used by the considerations of the maintenance history, the change parts availability and the latest technology. The JMTR pure water facility was classified into all updated facility based on the consideration. The Update construction was conducted in between FY2007 and FY2008. The refurbishment of JMTR pure water facility is summarized in this report. (author)

Modernization and refurbishment of the Central Interim Storage

International Nuclear Information System (INIS)

Mele, I.; Zeleznik, N.

2002-01-01

The Central Interim Storage for radioactive waste in Brinje, being put into operation in 1986, needs refurbishment and modernization in order to meet the up-to-date operational and safety requirements and to ensure the normal and undisturbed acceptance of radioactive waste from small producers in the future. Because of the waste, being already stored in the storage, the lack of reprocessing capacities and the lack of auxiliary room, the refurbishment and modernization is a complex problem, which needs to be addressed with care. The plan of refurbishment and modernization requires an integral approach, covering all different aspects of renewal and reconstruction. The implementation plan, however, must be based on the actual state of the storage and real conditions for the implementations: from technical to financial. In this paper the project for refurbishment and modernization of the storage, and some activities that have already been implemented, are presented.(author)

Reactor refurbishment options for a changing climate

Energy Technology Data Exchange (ETDEWEB)

McNeish, D. [Bruce Power, Tiverton, Ontario (Canada)

2012-07-01

As the industry looks ahead to another generation of reactor refurbishment, it is acknowledged that the traditional way of Retubing a reactor is a daunting prospect for our investors and stakeholders. Innovations are required to mitigate the long downtime and large one-time investment associated with previous reactor refurbishments. These can take the shape of improvements to the Retube processes or by fundamentally changing the approach, e.g., calandria/shield tank replacement or partial Retubes. This session presents technical challenges that utilities need help resolving to arrive at a more attractive reactor refurbishment model. This includes issues related to calandria vessel fitness-for-service, the fuel channel replacement process, the feeder replacement process, life extension of fuel channels and feeders and complexities involving interfacing systems. (author)

Reactor refurbishment options for a changing climate

International Nuclear Information System (INIS)

McNeish, D.

2012-01-01

As the industry looks ahead to another generation of reactor refurbishment, it is acknowledged that the traditional way of Retubing a reactor is a daunting prospect for our investors and stakeholders. Innovations are required to mitigate the long downtime and large one-time investment associated with previous reactor refurbishments. These can take the shape of improvements to the Retube processes or by fundamentally changing the approach, e.g., calandria/shield tank replacement or partial Retubes. This session presents technical challenges that utilities need help resolving to arrive at a more attractive reactor refurbishment model. This includes issues related to calandria vessel fitness-for-service, the fuel channel replacement process, the feeder replacement process, life extension of fuel channels and feeders and complexities involving interfacing systems. (author)

Evaluation of three refurbished Guralp CMG-3TB seismometers.

Energy Technology Data Exchange (ETDEWEB)

Hart, Darren M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Merchant, Bion J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-05-01

The overall objective of testing the Guralp CMG-3TB refurbished seismometers is to determine whether or not the refurbished sensors exhibit better data quality and require less maintenance when deployed than the original Guralp CMG-3TBs. SNL will test these 3 refurbished Guralps to verify performance specifications. The specifications that will be evaluated are sensitivity, bandwidth, self-noise, output impedance, clip-level, dynamic range over application passband, verify mathematical response and calibration response parameters for amplitude and phase.

Engineering study radioactive liquid waste treatment plant refurbishment

International Nuclear Information System (INIS)

Suazo, I.L.

1994-01-01

This feasibility study will investigate the opportunities, restrictions and cost impact to refurbish the existing Radioactive Liquid Waste Treatment Plant (RLWTP) while utilizing the same basic criteria that was used in the development of the new Radioactive Liquid Waste Treatment Facility (RLWTF). The objective of this study is to perform a more in-depth analysis of refurbishing the existing than has been done in the past so as to provide a basis for comparison between refurbishing the existing or constructing a new. The existing plant is located at Technical Area 50 (TA-50) within the Los Alamos National Laboratory (LANL). The initial structure was built in 1963. Over the ensuing years, the building has been modified and several additions have been constructed. In 1966, laboratories, ion exchange and pretreatment functions were added. The decontamination and decommissioning activities and ventilation equipment were added in 1984. The following assumptions are the basic parameters considered in the development of a design concept to refurbish the RLWTP: (1) Allow continued operation of the during retrofit construction. (2) Design the necessary expansion within the site constraints. (3) Satisfy National Pollutant Discharge Elimination System (NPDES) and National Emission Standards for Hazardous Air Pollutants (NESHAPS) permit conditions and other environmental regulations. (4) Comply with present DOE Orders and building code requirements. The refurbishment concept is a phased demolition and construction process

Loading Deformation Characteristic Simulation Study of Engineering Vehicle Refurbished Tire

Science.gov (United States)

Qiang, Wang; Xiaojie, Qi; Zhao, Yang; Yunlong, Wang; Guotian, Wang; Degang, Lv

2018-05-01

The paper constructed engineering vehicle refurbished tire computer geometry model, mechanics model, contact model, finite element analysis model, did simulation study on load-deformation property of engineering vehicle refurbished tire by comparing with that of the new and the same type tire, got load-deformation of engineering vehicle refurbished tire under the working condition of static state and ground contact. The analysis result shows that change rules of radial-direction deformation and side-direction deformation of engineering vehicle refurbished tire are close to that of the new tire, radial-direction and side-direction deformation value is a little less than that of the new tire. When air inflation pressure was certain, radial-direction deformation linear rule of engineer vehicle refurbished tire would increase with load adding, however, side-direction deformation showed linear change rule, when air inflation pressure was low; and it would show increase of non-linear change rule, when air inflation pressure was very high.

Nuclear target foil fabrication for the Romano Event

International Nuclear Information System (INIS)

Weed, J.W.; Romo, J.G. Jr.; Griggs, G.E.

1984-01-01

The Vacuum Processes Lab, of LLNL's M.E. Dept. - Material Fabrication Division, was requested to provide 250 coated Parylene target foils for a nuclear physics experiment titled the ROMANO Event. Due to the developmental nature of some of the fabrication procedures, approximately 400 coated foils were produced to satisfy the event's needs. The foils were used in the experiment as subkilovolt x-ray, narrow band pass filters, and wide band ultraviolet filters. This paper is divided into three sections describing: (1) nuclear target foil fabrication, (2) Parylene substrate preparation and production, and (3) foil and substrate inspections

Advanced instrumentation and control systems for CANDU refurbishment

International Nuclear Information System (INIS)

Sklyar, V.; Bakhmach, I.; Kharchenko, V.; Andrashov, A.; Baranova, O.

2011-01-01

The purpose of the work is to discuss opportunities to modernize I and C systems of CANDU reactors on the base of Radiy's digital safety platform. This paper discusses the following topics: a business model for CANDU, I and C systems refurbishment, FPGA technology issues, comparison of different approaches to refurbish obsolete I and C systems. (author)

LIFE Target Fabrication Research Plan Sept 2008

Energy Technology Data Exchange (ETDEWEB)

Miles, R; Biener, J; Kucheyev, S; Montesanti, R; Satcher, J; Spadaccini, C; Rose, K; Wang, M; Hamza, A; Alexander, N; Brown, L; Hund, J; Petzoldt, R; Sweet, W; Goodin, D

2008-11-10

The target-system for the baseline LIFE fast-ignition target was analyzed to establish a preliminary estimate for the costs and complexities involved in demonstrating the technologies needed to build a prototype LIFE plant. The baseline fast-ignition target upon which this analysis was developed is shown in Figure 1.0-1 below. The LIFE target-system incorporates requirements for low-cost, high throughput manufacture, high-speed, high accuracy injection of the target into the chamber, production of sufficient energy from implosion and recovery and recycle of the imploded target material residue. None of these functions has been demonstrated to date. Existing target fabrication techniques which lead to current 'hot spot' target costs of {approx}$100,000 per target and at a production rate of 2/day are unacceptable for the LIFE program. Fabrication techniques normally used for low-cost, low accuracy consumer products such as toys must be adapted to the high-accuracy LIFE target. This will be challenge. A research program resulting is the demonstration of the target-cycle technologies needed for a prototype LIFE reactor is expected to cost {approx}$51M over the course of 5 years. The effort will result in targets which will cost an estimated $0.23/target at a rep-rate of 20 Hz or about 1.73M targets/day.

High volume fabrication of laser targets using MEMS techniques

International Nuclear Information System (INIS)

Spindloe, C; Tomlinson, S; Green, J; Booth, N.; Tolley, M K; Arthur, G; Hall, F; Potter, R; Kar, S; Higginbotham, A

2016-01-01

The latest techniques for the fabrication of high power laser targets, using processes developed for the manufacture of Micro-Electro-Mechanical System (MEMS) devices are discussed. These laser targets are designed to meet the needs of the increased shot numbers that are available in the latest design of laser facilities. Traditionally laser targets have been fabricated using conventional machining or coarse etching processes and have been produced in quantities of 10s to low 100s. Such targets can be used for high complexity experiments such as Inertial Fusion Energy (IFE) studies and can have many complex components that need assembling and characterisation with high precision. Using the techniques that are common to MEMS devices and integrating these with an existing target fabrication capability we are able to manufacture and deliver targets to these systems. It also enables us to manufacture novel targets that have not been possible using other techniques. In addition, developments in the positioning systems that are required to deliver these targets to the laser focus are also required and a system to deliver the target to a focus of an F2 beam at 0.1Hz is discussed. (paper)

Analysis of Factors Influencing Building Refurbishment Project Performance

Directory of Open Access Journals (Sweden)

Ishak Nurfadzillah

2018-01-01

Full Text Available Presently, the refurbishment approach becomes favourable as it creates opportunities to incorporate sustainable value with other building improvement. In this regard, this approach needs to be implemented due to the issues on overwhelming ratio of existing building to new construction, which also can contribute to the environmental problem. Refurbishment principles imply to minimize the environmental impact and upgrading the performance of an existing building to meet new requirements. In theoretically, building project’s performance has a direct bearing on related to its potential for project success. However, in refurbishment building projects, the criteria for measure are become wider because the projects are a complex and multi-dimensional which encompassing many factors which reflect to the nature of works. Therefore, this impetus could be achieve by examine the direct empirical relationship between critical success factors (CSFs and complexity factors (CFs during managing the project in relation to delivering success on project performance. The research findings will be expected as the basis of future research in establish appropriate framework that provides information on managing refurbishment building projects and enhancing the project management competency for a better-built environment.

Analysis of Factors Influencing Building Refurbishment Project Performance

Science.gov (United States)

Ishak, Nurfadzillah; Aswad Ibrahim, Fazdliel; Azizi Azizan, Muhammad

2018-03-01

Presently, the refurbishment approach becomes favourable as it creates opportunities to incorporate sustainable value with other building improvement. In this regard, this approach needs to be implemented due to the issues on overwhelming ratio of existing building to new construction, which also can contribute to the environmental problem. Refurbishment principles imply to minimize the environmental impact and upgrading the performance of an existing building to meet new requirements. In theoretically, building project's performance has a direct bearing on related to its potential for project success. However, in refurbishment building projects, the criteria for measure are become wider because the projects are a complex and multi-dimensional which encompassing many factors which reflect to the nature of works. Therefore, this impetus could be achieve by examine the direct empirical relationship between critical success factors (CSFs) and complexity factors (CFs) during managing the project in relation to delivering success on project performance. The research findings will be expected as the basis of future research in establish appropriate framework that provides information on managing refurbishment building projects and enhancing the project management competency for a better-built environment.

Ion beam analysis of gas turbine blades: evaluation of refurbishment ...

Indian Academy of Sciences (India)

Scanning proton microscopy was employed to evaluate the quality of refurbishment process of gas turbine ... environment of hot combustion gases occur due to various processes, such as .... performance of refurbished blades.7. Due to the ...

Refurbishment and safety upgradation of research reactor Cirus

International Nuclear Information System (INIS)

Marik, S.K.; Rao, D.V.H.; Bhatnagar, A.; Pant, R.C.; Tikku, A.C.; Sankar, S.

2006-01-01

Cirus, a 40 MW t, vertical tank type research reactor, having wide range of research facilities, was commissioned in the year 1960. This research reactor, situated at Mumbai, India has been operated and utilized extensively for isotope production, material testing and neutron beam research for nearly four decades. With a view to assess the residual life of the reactor, detailed ageing studies were carried out during the early 1990s. Based on these studies, refurbishment of Cirus for its life extension was taken up. During refurbishment, additional safety features were incorporated in various systems to qualify them for the current safety standards. This paper gives the details of the operating experiences, utilization of the reactor along with methodologies followed for carrying out detailed ageing studies, refurbishment and safety upgradation for its life extension

Reactor protection system refurbishment at Paks

International Nuclear Information System (INIS)

Hetzmann, A.; Turi, T.

1997-01-01

The history and the milestones of the reactor protection system refurbishment are outlined. During the preparation phase of the refurbishment project, detailed requirements have been set up and specific technical solutions developed. The structure of the project documents prepared during these activities is shown in a figure. The life cycle of the project was divided into four phases: the preparatory phase; the design and manufacturing phase; the installation and commissioning phase; and the operation phase. For all four Paks units a time schedule for implementation was set up. The licensing process is dealt with; the principal license was issued in June 1996. (A.K.)

Coordination Devices in the Refurbishment Design Process: A Partial-Correlation Approach

Directory of Open Access Journals (Sweden)

Azlan Shah Ali

2009-12-01

Full Text Available Building refurbishment is an important sector in the Malaysian construction industry. The increase the number of building renovations, alterations, extensions and extensive repair works contributed to the high demand for refurbishment projects. However, refurbishment projects are more difficult to manage compared to new-built, due to uncertainty factors inherent in the projects. Therefore, this paper identifies factors that contributed to uncertainty and shows how it affects design performance of refurbishment projects. This paper was also extended to the used of coordination devices to improve design performance from the effect of uncertainty in the projects. Partial-correlation technique was used in data analysis to check any significant moderate effects of coordination devices to control the negative effect of uncertainty on design performance of refurbishment projects. Four (4 coordination devices involved in the partial-correlation tests. The results concluded that the use of lateral relations and architect’s characteristics are most likely reducing the uncertainty of client attributes towards design completeness before work started on site.

Refurbishment of the NPP Dukovany I and C System

International Nuclear Information System (INIS)

Karpeta, C.; Rosol, J.

2004-01-01

An overview of the NPP Dukovany Instrumentation and Control (I and C) refurbishment project is presented in this paper from the standpoint of both its management and technical aspects. Reasons for taking the decision to replace the original plant I and C system are outlined and the objectives set for the refurbishment project are stated. The paper is focusing on describing more in detail the first part of the refurbishment, i.e. replacement of the I and C portions of the plant systems important to nuclear safety and the process information system. This includes the reactor trip system, engineered safety features actuation system, reactor power limitation system, reactor power control system, post-accident monitoring system, reactor core monitoring system and unit data acquisition and processing system. Information is given on the main processes of the project, i.e. the bidding, design, manufacturing, installation and commissioning. Specific licensing process applied to this refurbishment project is also outlined. An account of the current status of the project implementation is given. (author)

Energetic Refurbishment of Historic Brick Buildings: Problems and Opportunities

Science.gov (United States)

Zagorskas, Jurgis; Paliulis, Gražvydas Mykolas; Burinskienė, Marija; Venckauskaitė, Jūratė

2013-12-01

Building standards for energy effectiveness are increasing constantly and the market follows these changes by constructing new buildings in accordance with standards and refurbishment of the existing housing stock. Comprehensive trends in European construction market show tremendous increase in building retrofit works. It can be predicted that after the end of this decade, more than half of the construction works in European cities will be taking place in existing buildings, pushing the construction of new buildings to a less important role. Such a growth in building refurbishment works is creating a demand for suitable materials, retrofitting techniques and research. The differences between refurbishment of new-build projects and historical or valuable buildings are insufficiently recognized - mostly the buildings without further cultural preservation requirements are studied. This article covers the theme of refurbishment measures in historical buildings - the specific measures like inside insulation which are allowed due to the valuable façade or other heritage preservation requirements. An overview of other innovative methods for energy saving in existing buildings and their potential is given.

Current status of JMTR refurbishment project

International Nuclear Information System (INIS)

Kaminaga, Masanori; Niimi, Motoji; Hori, Naohiko; Takahashi, Kunihiro; Kanno, Masaru; Nakagawa, Tetsuya; Nagao, Yoshiharu; Ishihara, Masahiro; Kawamura, Hiroshi

2010-02-01

The JMTR is a light water moderated and cooled, beryllium reflected tank- type reactor using LUE silicide plate-type fuels. Its thermal power is 50 MW, maximum thermal and fast neutron flux is 4x10 18 m -2 s -1 . First criticality was achieved in March 1968, and its operation was stopped from August, 2006 for the refurbishment. The refurbishment is scheduled from the beginning of FY2007 to the end of FY2010. The renewed and upgraded JMTR will be re-started from FY2011. An investigation on aged components (aged-investigation) was carried out for concrete structures of the JMTR reactor building, exhaust stack, etc., and for tanks in the primary cooling system, heat exchangers, pipes in the secondary cooling system, cooling tower, emergency generators and so on, in order to identify their integrity. The aged-investigation was carried out at the beginning of FY2007. As a result, some components were decided to replace from viewpoints of future maintenance and improvement of reliability, and some components or structures were decided to repair. A visual inspection of inner side of the pressure vessel was carried out using an underwater camera in FY2008, and no serious damage was observed. Up to now, refurbishment works are in progress according to the planned schedule. In FY2009, motors of primary cooling pumps, secondary cooling pumps, motors of drain pumps, pump in the primary water transfer line to the water purification system, beryllium reflector frame, low-voltage motor control centers are to be replaced. A nuclear instrumentation system, process control system, safety protection system and so on are to be replaced in FY2010. In this paper, current status of JMTR refurbishment project is presented. (author)

Refurbishment of BR2 (Phase 4 and 5)

International Nuclear Information System (INIS)

Gubel, P.; Dekeyser, J.; Van der Auwera, J.

1998-01-01

The extensive refurbishment of the BR-2 materials testing reactor should allow another 10 to 15 years of continued operation. The refurbishment programme is required in order to comply with modern safety standards, to enhance the reliability of operation, and to compensate for the ageing of the installations of a facility that has reached about 35 years of intensive service. The main objectives and achievements of phase 4 and 5 are described

LBNF 1.2 MW TARGET: CONCEPTUAL DESIGN & FABRICATION

Energy Technology Data Exchange (ETDEWEB)

Crowley, Cory F. [Fermilab; Ammigan, K. [Fermilab; Anderson, K. [Fermilab; Hartsell, B. [Fermilab; Hurh, P. [Fermilab; Hylen, J. [Fermilab; Zwaska, R. [Fermilab

2015-06-29

Fermilab’s Long-Baseline Neutrino Facility (LBNF) will utilize a modified design based on the NuMI low energy target that is reconfigured to accommodate beam operation at 1.2 MW. Achieving this power with a graphite target material and ancillary systems originally rated for 400 kW requires several design changes and R&D efforts related to material bonding and electrical isolation. Target cooling, structural design, and fabrication techniques must address higher stresses and heat loads that will be present during 1.2 MW operation, as the assembly will be subject to cyclic loads and thermal expansion. Mitigations must be balanced against compromises in neutrino yield. Beam monitoring and subsystem instrumentation will be updated and added to ensure confidence in target positioning and monitoring. Remote connection to the target hall support structure must provide for the eventual upgrade to a 2.4 MW target design, without producing excessive radioactive waste or unreasonable exposure to technicians during reconfiguration. Current designs and assembly layouts will be presented, in addition to current findings on processes and possibilities for prototype and final assembly fabrication.

LBNF 1.2 MW Target: Conceptual Design & Fabrication

Energy Technology Data Exchange (ETDEWEB)

Crowley, C. [Fermilab; Ammigan, K. [Fermilab; Anderson, K. [Fermilab; Hartsell, B. [Fermilab; Hurh, P. [Fermilab; Hylen, J. [Fermilab; Zwaska, R. [Fermilab

2015-06-01

Fermilab’s Long-Baseline Neutrino Facility (LBNF) will utilize a modified design based on the NuMI low energy target that is reconfigured to accommodate beam operation at 1.2 MW. Achieving this power with a graphite target material and ancillary systems originally rated for 400 kW requires several design changes and R&D efforts related to material bonding and electrical isolation. Target cooling, structural design, and fabrication techniques must address higher stresses and heat loads that will be present during 1.2 MW operation, as the assembly will be subject to cyclic loads and thermal expansion. Mitigations must be balanced against compromises in neutrino yield. Beam monitoring and subsystem instrumentation will be updated and added to ensure confidence in target positioning and monitoring. Remote connection to the target hall support structure must provide for the eventual upgrade to a 2.4 MW target design, without producing excessive radioactive waste or unreasonable exposure to technicians during reconfiguration. Current designs and assembly layouts will be presented, in addition to current findings on processes and possibilities for prototype and final assembly fabrication.

The BR2 refurbishment programme: achievements and two years operation feedback

International Nuclear Information System (INIS)

Gubel, P.; Dekeyser, J.; Koonen, E.; Van der Auwera, J.

1999-01-01

The BR2 reactor was shutdown end of June 1995 for an extensive refurbishment after more than 30 years utilization. The beryllium matrix needed to be replaced and the aluminium vessel inspected for an envisaged 15 year life extension. Other aspects of the refurbishment programme aimed at the reliability and availability of the installations, safety of operation and compliance with modern safety standards. The reactor was started again in' April '97 and operated only for three cycles in 1997. These first irradiation cycles were intended as a demonstration of the safety and reliability of all components and systems after refurbishment. Also during the extended shutdowns non-critical refurbishment tasks were allowed to be continued and finalized. At the request of the Safety Authorities, some modifications and studies are still in progress without perturbation of the reactor operation. (author)

An Overview of the Target Fabrication Operations at Lawrence Livermore National Laboratory

International Nuclear Information System (INIS)

Hibbard, R L; Bono, M J

2005-01-01

The Target Engineering team at Lawrence Livermore National Laboratory (LLNL) builds precision laser targets for the National Ignition Facility (NIF) and the Omega Laser in Rochester, NY, and other experimental facilities. The physics requirements demand precision in these targets, which creates a constant need for innovative manufacturing processes. As experimental diagnostics improve, there is greater demand for precision in fabrication, assembly, metrology, and documentation of as-built targets. The team specializes in meso-scale fabrication with core competencies in diamond turning, assembly, and metrology. Figure 1 shows a typical diamond turning center. The team builds over 200 laser targets per year in batches of five to fifteen targets. Thus, all are small-lot custom builds, and most are novel designs requiring engineering and process development. Component materials are metals, polymers and low density aerogel foams. Custom fixturing is used to locate parts on the Diamond Turning Machines (DTM) and assembly stations. This ensures parts can be repeatably located during manufacturing operations. Most target builds involve a series of fabricating one surface with features and then relocating the components on another fixture to finish the opposite side of the component. These components are then assembled to complete multiple-component targets. These targets are typically built one at a time. Cost and efficiency are issues with production of targets, and the team is developing batch processing techniques to meet precision target specifications and cost goals. Three example target builds will highlight some of the fabrication and material issues faced at LLNL. A low temperature Rayleigh Taylor target shows how multiple precision targets can be fabricated out of a single large disk. The ignition double shell targets highlight the required manufacturing complexity. A low density aerogel target highlights some material handling and assembly issues. The metrology

Status of the BR2 refurbishment programme

International Nuclear Information System (INIS)

Koonen, E.

1995-01-01

The operation of the BR2 reactor with its second beryllium matrix is foreseen up to mid-1995. A refurbishment programme has been established in order to allow for future operation during at least ten years. Recently a positive decision to effectively carry out this programme has been taken. The refurbishment action plan follows from a general assessment of the different systems of BR2, with respect to their actual status, the operational experience and the evolution of safety standards and criteria. Ageing considerations were of uppermost importance in those assessments, not only to assure safety of future operation, but also to guarantee future availability and reliability. (orig.)

The BR2 refurbishment: from concept to achievements

International Nuclear Information System (INIS)

Gubel, P.

2002-01-01

The BR2 reactor is one of the major research reactors in the world. It's operation started in the early 1960's. Two major refurbishments operation have been carried out since then. The report gives an overview of the methodology and inspections, which resulted in a refurbishment action plan. The main realizations and complementary actions required by the Licensing Authorities are summarized. Finally the operation experience feedback, four years now after start-up, is briefly discussed as well as the main aspects of the present safety reassessment [ru

Refurbishment and safety up-gradation of Cirus Reactor

International Nuclear Information System (INIS)

Rao, D.V.H.

2004-01-01

Cirus, a 40 MWth, vertical tank type research reactor, having a wide range of research facilities, was commissioned in 1960. This research facility has been operated and utilized extensively for nearly four decades. With a view to assess the residual life of the reactor, detailed ageing studies were carried out. Based on this, refurbishment work for life extension was undertaken. During this work, additional safety features were incorporated to improve the overall safety of the reactor. This lecture details the methodologies used for ageing studies and refurbishment activities for life extension with enhanced safety. (author)

System impact of energy efficient building refurbishment within a district heated region

International Nuclear Information System (INIS)

Lidberg, T.; Olofsson, T.; Trygg, L.

2016-01-01

The energy efficiency of the European building stock needs to be increased in order to fulfill the climate goals of the European Union. To be able to evaluate the impact of energy efficient refurbishment in matters of greenhouse gas emissions, it is necessary to apply a system perspective where not only the building but also the surrounding energy system is taken into consideration. This study examines the impact that energy efficient refurbishment of multi-family buildings has on the district heating and the electricity production. It also investigates the impact on electricity utilization and emissions of greenhouse gases. The results from the simulation of four energy efficiency building refurbishment packages were used to evaluate the impact on the district heating system. The packages were chosen to show the difference between refurbishment actions that increase the use of electricity when lowering the heat demand, and actions that lower the heat demand without increasing the electricity use. The energy system cost optimization modeling tool MODEST (Model for Optimization of Dynamic Energy Systems with Time-Dependent Components and Boundary Conditions) was used. When comparing two refurbishment packages with the same annual district heating use, this study shows that a package including changes in the building envelope decreases the greenhouse gas emissions more than a package including ventilation measures. - Highlights: • Choice of building refurbishment measures leads to differences in system impact. • Building refurbishment in district heating systems reduces co-produced electricity. • Valuing biomass as a limited resource is crucial when assessing global GHG impact. • Building envelope measures decrease GHG (greenhouse gas) emissions more than ventilation measures.

Refurbishment and safety management of JMTR in extended showdown

International Nuclear Information System (INIS)

Ide, Hiroshi; Hori, Naohiko; Gorai, Shigeru; Kusunoki, Tsuyoshi

2011-06-01

Japan Materials Testing Reactor (JMTR) is a testing reactor dedicated to the irradiation tests of materials and fuels. The reactor type of the JMTR is light water moderated and cooled tank type. It achieved first criticality in 1968. Operation was started in 1970. The JMTR had been being operated for 38 years from first criticality to the JMTR No.165 cycle finished. Periodic Safety Review (PSR) was carried out with confirming the integrity inspection of the JMTR reactor facilities. And the 10 years maintenance plan was made in 2004. After that, the restart of the JMTR has been strongly requested from various users as the only irradiation testing reactor in Japan. Finally, Japan Atomic Energy Agency (JAEA) decided the refurbishment and restart of the JMTR in December 2006, and the refurbishment works was started from FY 2007. The equipment to remain in use and that which needs replacing before the restart of the JMTR was selected after having been evaluated on its damage and wear due to aging significance in safety functions, past safety-related maintenance date, and the enhancement of facility operation. The renewal work of power supply system, boiler, radioactive waste facility, etc. was already carried out as scheduled. The renewal work of reactor control system, nuclear instrumentation system and so on is being carried out. As for the safety management during reactor operation, the facility periodical own inspection and daily inspection is carried out for the purpose of maintaining soundness and reliability of facilities and equipments. And it is confirmed that the performance of facilities and equipments is maintained. As for the radiation control, irradiation dose limit determined by the law is obeyed. Based on the Concept of radiation protection of the International Commission on Radiation Protection (ICRP), reduction of dose is endeavored. The safety management during reactor shutdown is also carried out as well as it of reactor operation term. However, the

Impact of flow accelerated corrosion (FAC) on feeder refurbishment planning

International Nuclear Information System (INIS)

Jyrkama, M.; Pandey, M.

2010-01-01

Feeder wall thinning due to flow accelerated corrosion (FAC) may result in a large number of feeder replacements in the future. In this study, the process of FAC is modelled using a probabilistic approach and used to predict the expected number of degraded feeders and their replacements in the future. Because of the high cost associated with feeder replacements, it may be optimal to replace the entire feeder population during a single refurbishment outage when the unit cost of replacement is likely to be less. The results of this study demonstrate, however, that the unit cost of feeder replacement must be sufficiently lower than the standard replacement cost and the refurbishment performed at an optimal time to realize the economic benefits associated with the refurbishment. (author)

Energetic Refurbishment of Historic Brick Buildings

DEFF Research Database (Denmark)

Zagorskas, Jurgis; Mykolas Paliulis, Grazvydas; Burinskiene, Marija

2013-01-01

Building standards for energy effectiveness are increasing constantly and the market follows these changes by constructing new buildings in accordance with standards and refurbishment of the existing housing stock. Comprehensive trends in European construction market show tremendous increase...

COST-EFFECTIVE TARGET FABRICATION FOR INERTIAL FUSION ENERGY

International Nuclear Information System (INIS)

GOODIN, D.T; NOBILE, A; SCHROEN, D.G; MAXWELL, J.L; RICKMAN, W.S

2004-03-01

A central feature of an Inertial Fusion Energy (IFE) power plant is a target that has been compressed and heated to fusion conditions by the energy input of the driver. The IFE target fabrication programs are focusing on methods that will scale to mass production, and working closely with target designers to make material selections that will satisfy a wide range of required and desirable characteristics. Targets produced for current inertial confinement fusion experiments are estimated to cost about $2500 each. Design studies of cost-effective power production from laser and heavy-ion driven IFE have found a cost requirement of about $0.25-0.30 each. While four orders of magnitude cost reduction may seem at first to be nearly impossible, there are many factors that suggest this is achievable. This paper summarizes the paradigm shifts in target fabrication methodologies that will be needed to economically supply targets and presents the results of ''nth-of-a-kind'' plant layouts and concepts for IFE power plant fueling. Our engineering studies estimate the cost of the target supply in a fusion economy, and show that costs are within the range of commercial feasibility for laser-driven and for heavy ion driven IFE

Embalse refurbishment - aging, safety assessment, and the path forward

International Nuclear Information System (INIS)

Sainz, R.; Fornero, D.; Diaz, G.; Gold, R.; Dam, R.; McCrea, L.

2009-01-01

The Embalse Nuclear Power Station has been engaged in Pre-refurbishment activities for two years. The primary focus has been on the first phase Pre-Project Condition Assessment Program (PCAP). This phase of the Refurbishment and Life Extension (RLE) project consists of all preparatory activities that are required to define the refurbishment scope and costs, and for input into the utility business case for the RLE project. As part of an overall Plant Life Management (PLiM) program, the following activities have been performed: 1. Systematic and rigorous condition assessments / life assessments (including Health Prognosis and Recommendations); 2. Assessment of design and safety analysis features at Embalse, relative to current technology and licensing practices; 3. Pre-Project activities related to: Retube, Steam Generator replacement, and Digital Control Computer (DCC) replacement. The program has been a joint effort of Embalse NPS-NASA, AECL, ANSALDO and several other support organizations. Details of the planned program were addressed previously in a paper presented at the 28th CNS Conference (2007), entitled 'Embalse Refurbishment - Pre-Project Condition Assessment Phase 1'. Since that time, significant progress has been made towards completing the assessment program and planning for the next steps. This paper presents the progress of Refurbishment and Life Extension (RLE) Program at Embalse Nuclear Power Station with specific emphasis on the PCAP efforts. This includes a discussion of the benefits and lessons learned from RLE project's perspective, and an overview of some key conclusions of the aging assessments. Finally, this paper outlines the path forward. It should be noted that results of assessments presented in this paper are very conservative. This is driven largely by the fact that there are currently uncertainties in equipment condition that can be addressed through the activities recommended as an outcome of these assessments. (author)

An integrated design process for a zero-energy refurbishment prototype for post-war residential buildings in the Netherlands

NARCIS (Netherlands)

Konstantinou, T.; Klein, T.; Guerra Santin, O.; Boess, S.U.; Silvester, S.

2015-01-01

Although refurbishment is a necessary step to reach the ambitious energy and decarbonisation targets for 2020 and 2050, which require an eventual reduction up to 90% in CO2 emissions, the rate of renovation is still relatively low. There is an increasing demand to upgrade both the physical condition

Development of an improved low profile hub seal refurbishment tool

International Nuclear Information System (INIS)

Wagg, L.

1997-01-01

The hub seal area of a fuel channel feeder coupling can be exposed to oxygen in the atmosphere if protective measures are not taken during maintenance outages. Exposure to oxygen can lead to pitting of the hub seal area. Although this is a rare occurrence, the resulting possibility of the feeder coupling leakage led to the development of a feeder hub refurbishment tool. To reduce time and man-rem exposure during feeder hub seal refurbishment, an improved low profile hub seat refurbishing tool has been developed. The improved tool design will allow for quick and controlled removal of material, and the restoration of a roll-burnished finish equivalent to the original requirements. The new tool can be used in maintenance operations, with the end fitting present, as well as under retube-type circumstances, with the end fitting removed. (author)

Laser fusion target fabrication. Status report, 30 April 1974

International Nuclear Information System (INIS)

Fries, R.J.; Farnum, E.H.

1974-11-01

The laser fusion target fabrication effort at Los Alamos Scientific Laboratory has been successful in producing targets of the general design requested by, and with a range of parameters acceptable to, the theoretical designers and to the laser/target interaction physics experimentalists. Many novel techniques for handling and measuring the properties of various types of hollow microballoons were developed. (U.S.)

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

International Nuclear Information System (INIS)

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

2008-01-01

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

Fabrication of implanted $^{22}$Na targets

CERN Multimedia

2002-01-01

A knowledge of the $^{22}$Na(p,$\\gamma$)$^{23}$ Mg reaction rate is of significant astrophysical interest. In order to complete previous studies of this reaction, radioactive $^{22}$Na targets of high purity are required. We ask for support to fabricate these targets via the implantation technique at ISOLDE GPS (off—line mode) using $^{22}$Na nuclides in an Al matrix produced in Nov. 1990 at the PSI (Zürich). The $^{22}$Na nuclides are released and ionized in a surface ionisation source, mass-analyzed at ISOLDE GPS, and implanted in a Ni-Ta backing and a C—foil in a special implantation setup.

Refurbishment of an Analytical Laboratory Hot Cell Facility

International Nuclear Information System (INIS)

Rosenberg, K.; Henslee, S.P.; Michelbacher, J.A.; Coleman, R.M.

1997-01-01

An Analytical Laboratory Hot Cell (ALHC) Facility at Argonne National Laboratory-West (ANL-W) was in service for nearly thirty years. In order to comply with DOE regulations governing such facilities and meet ANL-W programmatic requirements, a major refurbishment effort was undertaken. All penetrations within the facility were sealed; the ventilation system was redesigned, upgraded and replaced; the manipulators were replaced; the hot cell windows were removed, refurbished, and reinstalled; all hot cell utilities were replaced; a lead-shielded glovebox housing an Inductively Coupled Plasma - Atomic Emission Spectrometer (ICP-AES) System was interfaced with the hot cells, and a new CO2 fire suppression system and other ALHC support equipment were installed

BIM-Based Timber Structures Refurbishment of the Immovable Heritage Listed Buildings

Science.gov (United States)

Henek, Vladan; Venkrbec, Václav

2017-12-01

The use of Building information model (BIM) design tools is no longer an exception, but a common issue. When designing new buildings or complex renovations using BIM, the benefits have already been repeatedly published. The essence of BIM is to create a multidimensional geometric model of a planned building electronically on a computer, supplemented with the necessary information in advance of the construction process. Refurbishment is a specific process that combines both - new structures and demolished structures, or structures that need to be dismantled, repaired, and then returned to the original position. Often it can be historically valuable part of the building. BIM-based repairs and refurbishments of the constructions, especially complicated repairs of the structures of roof trusses of immovable heritage listed buildings, have not yet been credibly presented. However, the use of BIM tools may be advantageous in this area, because user can quickly response to the necessary changes that may be needed during refurbishments, but also in connection with the quick assessment and cost estimation of any unexpected additional works. The paper deals with the use of BIM in the field of repairs and refurbishment of the buildings in general. The emphasis on monumentally protected elements was priority. Advantage of the proposal research is demonstrated on case study of the refurbishment of the immovable heritage listed truss roof. According to this study, this construction was realized in the Czech Republic. Case study consists of 3D modelled truss parts and the connected technological workflow base. The project work was carried out in one common model environment.

EPIQR - a decision making tool for apartment building refurbishment

Energy Technology Data Exchange (ETDEWEB)

Caccavelli, D. [Centre Scientifique et Technique du Batiment, Cedex (France); Balaras, C. [National Observatory of Athens, Athens (Greece); Bluyssen, P. [TNO Building and Construction Research, Delft (Netherlands); Flourentzou, F. [Ecole Polytechnique Federale de Lausanne, Lausanne (France); Jaggs, M. [Building Research Establishment, Watford (United Kingdom); Wetzel, C. [Fraunhofer-Institut fur Bauphysik, Holzkirchen (Germany); Wittchen, K. [Danish Building Reasearch Institute, Hoersholm (Denmark)

1999-11-01

In a large majority of European countries, the amount of the maintenance and refurbishment works represents nearly 50% of the total amount spent in the building sector. New requirements are being added to the necessity of maintaining or re-establishing the building stock`s usage value. They are linked to the determination to reduce energy consumption, pollutant emissions, work site wastes, to improve the Indoor Environment Quality and all the modern conveniences inside apartment. Aware of this matter, the European Community has launched a two-year European research project, entitled EPIQR (Energy Performance, Indoor Environmental Quality, Retrofit) involving seven research institutions in the frame of the JOULE III programme. The purpose is to give architects and contracting authorities a multimedia tool to enable them to simultaneously grasp the whole process of apartment building refurbishment or retrofit. It has a number of functions: Assess the building`s degradation state based on a technical diagnosis after a standardised and complete inspection of the building; Prepare work proposals. These take into account not only the renovation of the building but also the improvement of the energy performance and IEQ; Estimate the costs corresponding to these works. A data base, containing the costs of 800 refurbishment works, provides a fast estimate of the total amount of the works being considered; Estimate the evolution of the degradation of the components if none of the works were to be carried out, as well as the refurbishment costs which would result. This paper provides an overview of the EPIQR methodology and the final deliverables of the project. (au)

Refurbishment of a Victorian terraced house for energy efficiency

Science.gov (United States)

Dimitriou, Angeliki

The impacts of global warming are now obvious. The international community has committed itself to reduce CO2 emissions, the main contributor to the greenhouse effect, both at international and national levels. In the Kyoto Protocol signed in 1997, countries have committed to reduce their greenhouse gases emissions below their 1990 levels by the period 2008-2012. The UK specifically should reduce those emissions by 12.5%. Format reason, the UK has introduced a package of policies, which promote not only the use of renewable energy resources, but most importantly the reduction in energy use, with energy efficiency. Refurbishment of existing houses has and will contribute to the reduction of energy consumption. A Victorian mid-terraced house was studied in this report, and different refurbishment measures were tested, using two software programmes: TAS and SAP. The targets were to achieve certain levels of thermal comfort, to comply with the Building Regulation for building thermal elements and to achieve a high SAP rating. Then, the cost of each measure was calculated and its CO2 emissions were compared. Heat losses were mainly through the walls and roof. Roof and mainly wall refurbishment measures reduce the heating loads the most. Ground floor insulation does not contribute to the reduction of the heating loads, on the contrary it has detrimental effect in summer, where the cooling effect coming from the ground is being reduced. Window replacement achieves a very good performance in summer resulting in the reduction of overheating. Wall and roof insulation increase the SAP rating the most, between the building elements, but boiler replacement and upgrading of heating controls increase it more. According to the SAP rating, CO2 annual emissions are reduced the most by boiler replacement and then by wall and roof. The results given by the two softwares concerning which measure is more leads more to energy efficiency, are the same. Finally, if the measures which lead

Fabrication technology for a series of cylindrical thin-wall cavity targets

CERN Document Server

Zheng Yong; Sun Zu Oke; Wang Ming Da; Zhou La; Zhou Zhi Yun

2002-01-01

Cylindrical thin-wall cavity targets have been fabricated to study the behavior of superthermal electrons and their effects on inertial confinement fusion (ICF). Self-supporting cavity targets having adjustable, uniform wall thickness, and low surface roughness were required. This required production of high-quality mandrels, coating them by sputtering or electroplating, developing techniques for measurement of wall thickness and other cavity parameters, improving the uniformity of rotation of the mandrels, and preventing damage to the targets during removal from the mandrels. Details of the fabrication process are presented. Experimental results from the use of these targets are presented. These results, in good agreement with simulations, indicate that the use of thin-wall cavity targets is an effective method for studying superthermal electrons in ICF.

Laser based refurbishment of steel mill components

CSIR Research Space (South Africa)

Kazadi, P

2006-03-01

Full Text Available Laser refurbishment capabilities were demonstrated and promising results were obtained for repair of distance sleeves, foot rolls, descaler cassette, idler rolls. Based on the cost projections and the results of the in-situ testing, components which...

The effects of acoustical refurbishment of classrooms on teachers’ perceived noise exposure and noise-related health symptoms

DEFF Research Database (Denmark)

Kristiansen, Jesper; Lund, Søren Peter; Persson, Roger

2015-01-01

lessons with circa 2 dB(A) in both schools. Conclusion: The acoustical refurbishment was associated with a reduction in classroom reverberation time and activity sound levels in both schools. The acoustical refurbishment was associated with a reduction in the teachers’ perceived noise exposure...... of RT and activity sound levels were measured before and after refurbishment. Data on perceived noise exposure, disturbance attributed to different noise sources, voice symptoms, and fatigue after work were collected over a year in a total of six consecutive questionnaires. Results: Refurbished......, the mean classroom reverberation time was 0.68 (school A) and 0.57 (school B) and 0.55 s in sham refurbished classrooms. After refurbishment, the RT was approximately 0.4 s in both schools. Activity sound level measurements confirmed that the intervention had reduced the equivalent sound levels during...

The influences of attributes, skills and knowledge of managers on refurbishment project performance

Science.gov (United States)

Ishak, Nurfadzillah

2018-02-01

Recently, the momentum on the growth of national building industry shows the increasing of the demand in refurbishment works becomes a trend spreading over the Malaysia. However, the potential of these activities normally related with the complexity in technical aspect compared to new build schemes. It will be reflecting on the unsatisfactory project performance. A competent manager is required to have the appropriate attributes, skills and knowledge in able to perform all the duties associated with managing the refurbishment building projects. Therefore, this paper is to identify the most appropriate attributes, skills and knowledge that required for managers to indicate the relationship between the influences on the refurbishment projects performance. This finding is indicate the importance of development the personal attributes, skills, and knowledge of managers and adds as benefit of raising the profile and image of managers in refurbishment building industry through a dissemination of the findings.

Refurbishment programme for the BR2-reactor

Energy Technology Data Exchange (ETDEWEB)

Koonen, E [Centre d' Etude de l' Energie Nucleaire, Studiecentrum voor Kernenergie, BR2 Department, Boeretang, Mol (Belgium)

1992-07-01

BR2 is a high flux engineering test reactor, which differs from comparable material testing reactors by its specific core array (fig. 1). It is a heterogeneous, thermal, tank-in-pool type reactor, moderated by beryllium and light water, which serves also as coolant. The fuel elements consist of cylindrical assemblies loaded in channels materialized by hexagonal beryllium prisms. The central 200 mm channel is vertical, while all others are inclined and form a hyperbolical arrangement around the central one. This feature combines a very compact core with the requirement of sufficient space for individual access to all channels through penetrations in the top cover of the aluminium pressure vessel. Each channel may hold a fuel element, a control rod, an experiment, an irradiation device or a beryllium plug. The refurbishment Program According to the present programme of C.E.N./S.C.K., BR2 will be in operation until 1996. At that time, the beryllium matrix will reach its foreseen end-of-life. In order to continue operation beyond this point, a thorough refurbishment of the reactor is foreseen, in addition to the unavoidable replacement of the matrix, to ensure quality of the installation and compliance with modern standards. Some fundamental options have been taken as a starting point: BR2 will continue to be used as a classical MTR, i.e. fuel and material irradiations and safety experiments with some additional service-activities. The present configuration is optimized for that use and there is no specific experimental requirement to change the basic concepts and performance characteristics. From the customers viewpoint, it is desirable to go ahead with the well-known features of BR2, to maintain a high degree of availability and reliability and to minimize the duration of the long shutdown. It is also important to limit the amount of nuclear liabilities. So the objective of the refurbishment programme is the life extension of BR2 for about 15 years, corresponding to

Refurbishment programme for the BR2-reactor

International Nuclear Information System (INIS)

Koonen, E.

1992-01-01

BR2 is a high flux engineering test reactor, which differs from comparable material testing reactors by its specific core array (fig. 1). It is a heterogeneous, thermal, tank-in-pool type reactor, moderated by beryllium and light water, which serves also as coolant. The fuel elements consist of cylindrical assemblies loaded in channels materialized by hexagonal beryllium prisms. The central 200 mm channel is vertical, while all others are inclined and form a hyperbolical arrangement around the central one. This feature combines a very compact core with the requirement of sufficient space for individual access to all channels through penetrations in the top cover of the aluminium pressure vessel. Each channel may hold a fuel element, a control rod, an experiment, an irradiation device or a beryllium plug. The refurbishment Program According to the present programme of C.E.N./S.C.K., BR2 will be in operation until 1996. At that time, the beryllium matrix will reach its foreseen end-of-life. In order to continue operation beyond this point, a thorough refurbishment of the reactor is foreseen, in addition to the unavoidable replacement of the matrix, to ensure quality of the installation and compliance with modern standards. Some fundamental options have been taken as a starting point: BR2 will continue to be used as a classical MTR, i.e. fuel and material irradiations and safety experiments with some additional service-activities. The present configuration is optimized for that use and there is no specific experimental requirement to change the basic concepts and performance characteristics. From the customers viewpoint, it is desirable to go ahead with the well-known features of BR2, to maintain a high degree of availability and reliability and to minimize the duration of the long shutdown. It is also important to limit the amount of nuclear liabilities. So the objective of the refurbishment programme is the life extension of BR2 for about 15 years, corresponding to

Refurbishing the BR2 materials testing reactor

International Nuclear Information System (INIS)

Baugnet, J.M.; Dekeyser, J.; Gubel, P.

1995-01-01

SCK/CEN is refurbishing its BR2 reactor to allow its further operation during the next 15 years; in doing so, it chooses to keep BR2 available for future scientific and technological irradiation programs within an international context. (author) 2 figs

Foundation helps refurbish buildings

International Nuclear Information System (INIS)

Camenzind, B.

2006-01-01

This article looks at the activities of the Swiss 'Climate-Cent' foundation, which is helping support the energetic refurbishment of building envelopes. The conditions which have to be fulfilled to receive grants are explained. Work supported includes the replacement of windows and the insulation of roofs and attics as well as outside walls. Details on the financial support provided and examples of projects supported are given. The source of the finance needed to provide such support - a voluntary levy on petrol - and further support provided in certain Swiss cantons is commented on

Rotor pole refurbishment for hydrogenerators: insulation problems and solutions

International Nuclear Information System (INIS)

Reynolds, R.R.; Rux, L.

2005-01-01

Rotor poles for Unit 1 at Lower Granite Powerhouse were removed from the rotor and shipped to a repair facility for refurbishment. Upon inspection, it was found that all of the pole bodies exhibited a distinct bow, center to end, on the pole mounting surface. In some cases, the deflection was as much as 0.106 inch. Concerns were raised about how this condition might affect the ability to properly insulate and/or re-seat the poles. This paper presents details of the rotor pole and field winding evaluation, the problems encountered, and the solutions implemented to successfully refurbish the rotor poles and field winding. (author)

The impact of building orientation and discount rates on a Portuguese reference building refurbishment decision

International Nuclear Information System (INIS)

Brandão de Vasconcelos, Ana; Cabaço, António; Pinheiro, Manuel Duarte; Manso, Armando

2016-01-01

Refurbishment, as part of the construction industry, has a strong global impact, not only from the viewpoint of economies but also from social and energy-efficiency perspectives. A thermal refurbishment process, in particular, involves numerous decisions and choices; the decision-makers being ultimately confronted with two major questions: which criterion should be adopted in the choice of the refurbishment construction solutions and which refurbishment construction solutions should be chosen? In this paper, a criterion based on technical and economic points of view is proposed, aiming to identify the cost-optimal package of energy efficient solutions from among a set of possible refurbishment measures, within the life cycle of buildings. Sensitivity analyses are also performed so that the results may help the decision-maker choose the appropriate refurbishment solutions to be adopted when different discount rates and building orientations are taken into consideration. A total of seven scenarios, for a macroeconomic perspective, and nine, for a financial perspective, are performed. The costoptimal methodology adopted, following the Directive 2010/31/EU (2010) recommendations, is applied to a Portuguese reference building. The analysis carried out allows obtaining low global life cycle costs solutions and points towards nearly Zero Energy Building (nZEB) concept. The results are important for drawing national political instruments on buildings energy efficiency. - Highlights: •Building refurbishment decision based on technical and economic points of view. •35.000 Packages of thermal rehabilitation solutions considered. •Building orientation and discount rate impact on the cost-optimal package of solutions. •Portuguese reference building case base.

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

International Nuclear Information System (INIS)

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

2006-01-01

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

Analysis of the cost for the refurbishment of small hydropower plants

International Nuclear Information System (INIS)

Ogayar, B.; Vidal, P.G.; Hernandez, J.C.

2009-01-01

In view of all the concerns associated with fossil fuels and energy demand it is appropriate to investigate the large number of abandoned small hydropower plants. In order to solve the difficulty implied, by a viability study on the refurbishment of a small hydropower plant, a series of simple equations has been developed based on the economic optimization of the different elements. These equations can also be used for completely new hydropower plants. The result of this study will allow us to obtain quite approximate costs for the refurbishment of old hydropower plants, or the construction of new ones. These data on costs will act as a reference to examine real possibilities of refurbishment through different tools of financial and economic analysis. Although the equations developed have used unitary prices referring to Spain, they will be applicable to other countries just changing those prices for those of the country, required. (author)

Refurbishment of the Oregon State University rotating rack

International Nuclear Information System (INIS)

Higginbotham, J.F.

1991-01-01

TRIGA reactors have experienced operational difficulties with the rotating racks used for sample irradiation. The most common problem occurs when the rack seizes, and the corrective action taken is replacement of the rack assembly. This paper describes the symptoms leading to rack failure and a refurbishment procedure to correct the problem without replacing the rack at the Oregon State University TRIGA Reactor (OSTR) Facility. This procedure was accomplished with extraordinary results from an operational and a radiation protection standpoint. The refurbishment has extended the useful life of this reactor facility with minimal financial impact. Given the declining number of university-based research reactors, it is in the nation's best interest to maintain the currently operating research reactor facilities, and the described procedure can aid in achieving that goal

Study on identification method of auto refurbishment test

Science.gov (United States)

Jiang, Zhenfei; Feng, Qingfu; Wang, Zhengyu; Jiang, Suqin; Chen, Xing; Zheng, Shaoyuan; Li, Bokui

2018-04-01

In recent years, a large number of refurbished cars inflow into the market as new cars. The traditional methods to identify refurbished cars are mostly based on experience, the subjectivity is too high and the credibility is low. In the production of automobile, the state and the automobile industry set clear standards for the thickness of the automobile paint. There is a big difference between the thickness of machine spraying and manual spraying. By studying this difference and combining with the standard, it can be identified accurately whether the car has been renovated; during the second assembly process, the surface of some parts (such as bolts) will have obvious signs of wear and tear due to the regular assembly and disassembly, it can also be identified accurately through the study of these assembly traces.

Advanced laser fusion target fabrication research and development proposal

International Nuclear Information System (INIS)

Stupin, D.M.; Fries, R.J.

1979-05-01

A research and development program is described that will enable the fabrication of 10 6 targets/day for a laser fusion prototype power reactor in 2007. We give personnel and cost estimates for a generalized laser fusion target that requires the development of several new technologies. The total cost of the program between 1979 and 2007 is $362 million in today's dollars

Concepts for fabrication of inertial fusion energy targets

Energy Technology Data Exchange (ETDEWEB)

Nobile, A. (Arthur), Jr.; Hoffer, J. K. (James K.); Gobby, P. L. (Peter L.); Steckle, W. P. (Warren P.), Jr.; Goodin, D. T. (Daniel T.); Besenbruch, G. E. (Gottfried E.); Schultz, K. R. (Kenneth R.)

2001-01-01

Future inertial fusion energy (IFE) power plants will have a Target Fabrication Facility (TFF) that must produce approximately 500,000 targets per day. To achieve a relatively low cost of electricity, the cost to produce these targets will need to be less than approximately $0.25 per target. In this paper the status on the development of concepts for a TFF to produce targets for a heavy ion fusion (HIF) reactor, such as HYLIFE II, and a laser direct drive fusion reactor such as Sombrero, is discussed. The baseline target that is produced in the HIF TFF is similar to the close-coupled indirect drive target designed by Callahan-Miller and Tabak at Lawrence Livermore Laboratory. This target consists of a cryogenic hohlraum that is made of a metal case and a variety of metal foams and metal-doped organic foams. The target contains a DT-filled CH capsule. The baseline direct drive target is the design developed by Bodner and coworkers at Naval Research Laboratory. HIF targets can be filled with DT before or after assembly of the capsule into the hohlraum. Assembly of targets before filling allows assembly operations to be done at room temperature, but tritium inventories are much larger due to the large volume that the hohlraum occupies in the fill system. Assembly of targets cold after filling allows substantial reduction in tritium inventory, but this requires assembly of targets at cryogenic temperature. A model being developed to evaluate the tritium inventories associated with each of the assembly and fill options indicates that filling targets before assembling the capsule into the hohlraum, filling at temperatures as high as possible, and reducing dead-volumes in the fill system as much as possible offers the potential to reduce tritium inventories to acceptable levels. Use of enhanced DT ice layering techniques, such as infrared layering can reduce tritium inventories significantly by reducing the layering time and therefore the number of capsules being layered

Point Lepreau refurbishment - update 5

International Nuclear Information System (INIS)

White, R.M.; Eagles, E.R.; Hickman, C.N.; Baker, R.; Thompson, P.D.; Howieson, J.Q.; Ichiyen, N.

2005-01-01

NB Power Nuclear is planning to conduct a 18-month maintenance outage of the Point Lepreau Generating Station (PLGS) beginning in April 2008. The major activity would be the replacement of all 380 Fuel Channel and Calandria Tube assemblies and connecting feeder pipes. This activity is referred to as Retube. NB Power Nuclear would also take advantage of this outage to conduct a number of repairs, replacements, inspection and upgrades (such as rewinding or replacing the generator, replacement of shutdown system trip computers, replacement of certain valves and expansion joints, inspection of systems not normally accessible, etc.). These collective activities are referred to as Refurbishment. This would allow the station to operate for an additional 25 to 30 years. The scope or the project was determined [mm the outcome of a two year study involving a detailed condition assessment of the station which examined Issues relating to ageing and obsolescence, along with a detailed review or Safety and Licensing issues associated with extended operation. The Refurbishment outage would be preceded by a detailed Engineering Project Phase that would: Finalize details of the Retube process including modeling, tooling development, site facilities and training of personnel. Perform necessary engineering activities related to design modifications. Construct the new waste storage structures to house Retube Waste and other additional waste storage structures for the extended life of the station. Setup necessary temporary construction facilities (offices, storage areas, change moms, decontamination an maintenance areas) to support Retube. Procure equipment and components. Perform detailed outage planning. Initiate development of detailed commissioning as well as lay-up, monitoring and return to service procedures. At the present time, the NB Power Nuclear Board of Directors and the New Brunswick Provincial government are reviewing a proposal for a lease arrangement from Bruce Power

An Overview of Ageing Management and Refurbishment of Research Reactors at Trombay

Energy Technology Data Exchange (ETDEWEB)

Sharma, R. C.; Raina, V. K. [Bhabha Atomic Research Centre, Mumbai (India)

2014-08-15

Three nuclear research reactors have been in operation at Bhabha Atomic Research Centre, Mumbai, India. India has a rich experience of about 120 research reactor operating years including ageing management. A well structured programme is in force for plant life management, refurbishment and upgrading reactors in operation. Apsara, commissioned in August 1956, was the first research reactor. Apsara is a 1 MW{sub th} swimming pool type of reactor with a movable core loaded with enriched uranium fuel and immersed in demineralized light water pool, which serves as coolant, moderator and reflector besides providing radiation shielding. Apsara was shut down during May 2009 for partial decommissioning and upgrading to a 2 MW reactor with several safety upgrades, e.g. a LEU based reactor core with higher neutron flux, a new reactor building meeting seismic qualification criteria and two independent shutdown devices. Cirus, a 40 MW{sub th} tank type reactor utilizing heavy water as moderator, graphite as reflector, demineralized light water as primary coolant and natural uranium metal as fuel; has been in operation since 1960. After about three decade of operation, the availability factor started declining mainly due to outage of equipment exhibiting signs of ageing. After ageing studies and performance review, refurbishment requirements were identified. A programme for refurbishment was drawn that included safety upgrades like civil repairs to the emergency storage reservoir to meet seismic qualification criteria and a new iodine removal system for better efficiency. The reactor was shut down during 1997 for execution of this refurbishment programme. After completion of refurbishment, the reactor was brought back into operation during 2003. It has completed about seven years of safe operation after refurbishment with a significant increase in availability factor from 70% to about 90%. The reactor was permanently shut down during December 2010. The reactor core was unloaded

Fabrication and testing of W7-X pre-series target elements

International Nuclear Information System (INIS)

Boscary, J; Boeswirth, B; Greuner, H; Grigull, P; Missirlian, M; Plankensteiner, A; Schedler, B; Friedrich, T; Schlosser, J; Streibl, B; Traxler, H

2007-01-01

The assembly of the highly-loaded target plates of the WENDELSTEIN 7-X (W7-X) divertor requires the fabrication of 890 target elements (TEs). The plasma facing material is made of CFC NB31 flat tiles bonded to a CuCrZr copper alloy water-cooled heat sink. The elements are designed to remove a stationary heat flux and power up to 10 MW m -2 and 100 kW, respectively. Before launching the serial fabrication, pre-series activities aimed at qualifying the design, the manufacturing route and the non-destructive examinations (NDEs). High heat flux (HHF) tests performed on full-scale pre-series TEs resulted in an improvement of the design of the bond between tiles and heat sink to reduce the stresses during operation. The consequence is the fabrication of additional pre-series TEs to be tested in the HHF facility GLADIS. NDEs of this bond based on thermography methods are developed to define the acceptance criteria suitable for serial fabrication

IEC 61850 based refurbishment strategies for protection and automation systems

Energy Technology Data Exchange (ETDEWEB)

Tholomier, D. [Areva T and D Automation Canada Inc., Monteal, PQ (Canada); Hossenlopp, L. [Areva T and D Automation Inc., Paris (France); Apostolov, A. [Omicron Electronics, Houston, TX (United States)

2008-07-01

Electric utilities are currently facing the challenge of refurbishing aging transmission networks and power system infrastructure at a time of severe economic, environmental and competitive constraints. This paper addressed the issue of an appropriate approach to retrofit the hardware and software of substation secondary systems, and how IEC standards could be used to set up a long term strategy. The first part of the paper considered an asset management strategy for refurbishing substation secondary systems, while the second part of the paper addressed the strategies for refurbishing existing power plants. The final section of the paper analyzed refurbishment strategies designed to protect power distribution systems. The impact of IEC 61850 and how legacy devices can be integrated in substation automation systems were discussed. It was concluded that new SCADA systems are needed to handle new technology. Additional features like remote control, remote settings, remote disturbance records analysis and remote maintenance are also needed to properly operate the power system. The value of preventive maintenance using remote monitoring systems to determine the status of all the digital electronic devices installed in substation was also discussed. IEC 61850 offers several opportunities to improve grid operation and control. It supports interoperability between protective relays and control devices from different manufacturers in the substation, which is required in order to achieve substation level interlocking, protection and control functions and improve the efficiency of microprocessor based relays applications. This technology has now passed the initial stage of implementation and several projects are underway worldwide. 13 figs.

Fabrication of laser-target components by semiconductor technology

International Nuclear Information System (INIS)

Tindall, W.E.

1979-01-01

This paper describes the design and fabrication of a unique silicon substrate with which laser-target components can be mass produced. Different sizes and shapes of gold foils from 50 to 3000 microns in diameter and up to 25 microns thick have been produced with this process since 1976

Inertial Confinement Fusion Target Component Fabrication and Technology Development report

International Nuclear Information System (INIS)

Steinman, D.

1994-03-01

On December 30, 1990, the US Department of Energy entered into a contract with General Atomics (GA) to be the Inertial Confinement Fusion Target Component Fabrication and Technology Development Support contractor. This report documents the technical activities which took place under this contract during the period of October 1, 1992 through September 30, 1993. During this period, GA was assigned 18 tasks in support of the Inertial Confinement Fusion program and its laboratories. These tasks included ''Capabilities Activation'' and ''Capabilities Demonstration'' to enable us to begin production of glass and composite polymer capsules. Capsule delivery tasks included ''Small Glass Shell Deliveries'' and ''Composite Polymer Capsules'' for Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory (LANL). We also were asked to provide direct ''Onsite Support'' at LLNL and LANL. We continued planning for the transfer of ''Micromachining Equipment from Rocky Flats'' and established ''Target Component Micromachining and Electroplating Facilities'' at GA. We fabricated over 1100 films and filters of 11 types for Sandia National Laboratory and provided full-time onsite engineering support for target fabrication and characterization. We initiated development of methods to make targets for the Naval Research Laboratory. We investigated spherical interferometry, built an automated capsule sorter, and developed an apparatus for calorimetric measurement of fuel fill for LLNL. We assisted LANL in the ''Characterization of Opaque b-Layered Targets.'' We developed deuterated and UV-opaque polymers for use by the University of Rochester's Laboratory for Laser Energetics (UR/LLE) and devised a triple-orifice droplet generator to demonstrate the controlled-mass nature of the microencapsulation process

Ongoing refurbishment activities and strategy for the future operation of the BR2 reactor

International Nuclear Information System (INIS)

Koonen, E.; Gubel, P.

1994-01-01

The operation of the BR2 reactor with its second Be-matrix is foreseen up to mid-1995 or mid-1996. A life extension for another 15 years is envisaged considering programmatic, financial and technical aspects. At present, the second phase of the refurbishment programme is being executed. The major activities of this programme can be grouped under two headings: safety reassessment and ageing issues. The expected outcome end '93 is an assessment report defining extent, choosen options, prioritized activities, budget and a tentative planning for the preparation and execution of the refurbishment. These aspects together with the prospects of possible cooperation with other parties for the refurbishment programme and the future operation of BR2 will be evaluated by the CEN/SCK Board who has to take a decision early in 1994. Various scenarios are now being considered and evaluated for the refurbishment and the future BR2 operation regime. (author)

Ongoing refurbishment activities and strategy for the future operation of the BR2 reactor

Energy Technology Data Exchange (ETDEWEB)

Koonen, E; Gubel, P [BR2 Department, Belgian Nuclear Research Center, CEN/SCK, Mol (Belgium)

1993-07-01

The operation of the BR2 reactor with its second Be-matrix is foreseen up to mid-1995 or mid-1996. A life extension for another 15 years is envisaged considering programmatic, financial and technical aspects. At present, the second phase of the refurbishment programme is being executed. The major activities of this programme can be grouped under two headings: safety reassessment and ageing issues. The expected outcome end '93 is an assessment report defining extent, choosen options, prioritized activities, budget and a tentative planning for the preparation and execution of the refurbishment. These aspects together with the prospects of possible cooperation with other parties for the refurbishment programme and the future operation of BR2 will be evaluated by the CEN/SCK Board who has to take a decision early in 1994. Various scenarios are now being considered and evaluated for the refurbishment and the future BR2 operation regime. (author)

Ongoing refurbishment activities and strategy for the future operation of the BR2 reactor

International Nuclear Information System (INIS)

Koonen, E.; Gubel, P.

1993-01-01

The operation of the BR2 reactor with its second Be-matrix is foreseen up to mid-1995 or mid-1996. A life extension for another 15 years is envisaged considering programmatic, financial and technical aspects. At present, the second phase of the refurbishment programme is being executed. The major activities of this programme can be grouped under two headings: safety reassessment and ageing issues. The expected outcome end '93 is an assessment report defining extent, choosen options, prioritized activities, budget and a tentative planning for the preparation and execution of the refurbishment. These aspects together with the prospects of possible cooperation with other parties for the refurbishment programme and the future operation of BR2 will be evaluated by the CEN/SCK Board who has to take a decision early in 1994. Various scenarios are now being considered and evaluated for the refurbishment and the future BR2 operation regime. (author)

Simulated thermal energy demand and actual energy consumption in refurbished and non-refurbished buildings

Science.gov (United States)

Ilie, C. A.; Visa, I.; Duta, A.

2016-08-01

The EU legal frame imposes the Nearly Zero Energy Buildings (nZEB) status to any new public building starting with January 1st, 2019 and for any other new building starting with 2021. Basically, nZEB represents a Low Energy Building (LEB) that covers more than half of the energy demand by using renewable energy systems installed on or close to it. Thus, two steps have to be followed in developing nZEB: (1) reaching the LEB status through state- of-the art architectural and construction solutions (for the new buildings) or through refurbishing for the already existent buildings, followed by (2) implementing renewables; in Romania, over 65% of the energy demand in a building is directly linked to heating, domestic hot water (DHW), and - in certain areas - for cooling. Thus, effort should be directed to reduce the thermal energy demand to be further covered by using clean and affordable systems: solar- thermal systems, heat pumps, biomass, etc. or their hybrid combinations. Obviously this demand is influenced by the onsite climatic profile and by the building performance. An almost worst case scenario is approached in the paper, considering a community implemented in a mountain area, with cold and long winters and mild summers (Odorheiul Secuiesc city, Harghita county, Romania). Three representative types of buildings are analysed: multi-family households (in blocks of flats), single-family houses and administrative buildings. For the first two types, old and refurbished buildings were comparatively discussed.

Making the home consume less - putting energy efficiency on the refurbishment agenda

Energy Technology Data Exchange (ETDEWEB)

Stiess, Immanuel; Deffner, Jutta (Inst. for Social-Ecological Research ISOE GmbH (Germany)). e-mail: stiess@isoe.de; Zundel, Stefan (Lausitz Univ. of Applied Sciences (Germany))

2009-07-01

Private home owners can reduce their energy use significantly and move towards a low carbon lifestyle by retrofitting their homes in an energy efficient standard. Despite high awareness for energy efficiency and rising energy prices, home owners only slowly take this opportunity to cut down their personal energy use and carbon emission significantly. In many cases, maintenance and repair activities only result in incremental improvements of energy efficiency. Thus, the dynamics of refurbishment seems to have a conservative bias. Against this background, we will present results from an empirical survey, focussing on home owners' maintenance and refurbishment decisions. Drawing on approaches from social-psychology, lifestyle analysis and evolutionary economics, we will explore the impact of attitudes, lifestyle orientations, cognitive frameworks and social resources on refurbishment decision especially on energy efficient ones and present a model integrating the most important driving factors.

Addressing key science and technology issues for IFE chambers, target fabrication and target injection

International Nuclear Information System (INIS)

Meier, W.R.; Goodin, D.T.; Nobile, A.

2003-01-01

Significant progress has been made in the development of high repetition rate chambers, target fabrication and injection for inertial fusion energy (IFE) for both heavy ion and laser drivers. Research is being conducted in a coordinated manner by national laboratories, universities and industry. This paper provides an overview of U.S. research activities and discusses how interface considerations (such as beam propagation and target survival during injection) impact design choices. (author)

Investigation on cryogenic laser fusion targets: fabrication, characterization, and transport. Annual report, December 1, 1978-November 30, 1979

International Nuclear Information System (INIS)

Kim, K.

1979-01-01

The research has been directed toward fabrication, characterization, and positioning of cryogenic shell laser fusion targets, with particular emphasis on the development of a scheme which would allow for continuous fabrication, inspection, and delivery of the targets. Specifically, progress has been made in the following areas: (1) Fabrication of a uniform spherical shell of DT-condensate using a cold-wall target-freezing-cell. (2) Fabrication of a uniform spherical shell of liquid DT using a room-temperature wall target-freezing-cell. (3) Support-free cryogenic target fabrication using cold-gas-levitation. (4) Continuous fabrication of cryogenic targets using free-fall method. (5) Automatic characterization of DT-layer uniformity. (6) Sorting of DT-filled glass microshells using an interference microscope. (7) Development of an a-c interference microscope for accurate characterization of moving targets. (8) Development of a machine which is capable of producing a continuous stream of uniform DT spheres of controllable sizes. (9) Theoretical study on the behavior of liquid hydrogen contained in a spherical shell

Water electrolysis system refurbishment and testing

Science.gov (United States)

Greenough, B. M.

1972-01-01

The electrolytic oxygen generator for the back-up water electrolysis system in a 90-day manned test was refurbished, improved and subjected to a 182-day bench test. The performance of the system during the test demonstrated the soundness of the basic electrolysis concept, the high development status of the automatic controls which allowed completely hands-off operation, and the capability for orbital operation. Some design improvements are indicated.

BIM applied in historical building documentation and refurbishing

Science.gov (United States)

Cheng, H.-M.; Yang, W.-B.; Yen, Y.-N.

2015-08-01

Historical building conservation raises two important issues which are documentation and refurbishing. For the recording and documentation, we already have developed 3d laser scanner and such photogrammetry technology those represent a freeze object of virtual reality by digital documentation. On the other hand, the refurbished engineering of historic building is a challenge for conservation heritage which are not only reconstructing the damage part but also restoring tangible cultural heritage. 3D digital cultural heritage models has become a topic of great interest in recent years. One reason for this is the more widespread use of laser scanning and photogrammetry for recording cultural heritage sites. These technologies have made it possible to efficiently and accurately record complex structures remotely that would not have been possible with previous survey methods. In addition to these developments, digital information systems are evolving for the presentation, analysis and archival of heritage documentation.

Role of Fabrication on Materials Compatibility in APT Target/Blanket

International Nuclear Information System (INIS)

Iyer, N.; Louthan, M.R. Jr.; Dunn, K.; Fisher, D.L.

1998-09-01

This paper summarizes several of the options associated with the fabrication of selected target/blanket components. In addition, the materials characterization technologies required to validate these components performance is presented

Investigation on fabrication and positioning of cryogenic shell laser fusion targets. Annual report, October 1, 1977--November 30, 1978

International Nuclear Information System (INIS)

Kim, K.

1978-01-01

The research has been directed toward fabrication and positioning of cryogenic shell laser fusion targets, with particular emphasis on the development of a scheme which would allow for continuous fabrication, inspection, and delivery of the targets. Specifically, progress has been made in each of the following areas: (1) fabrication of a uniform layer of solid DT inside a glass microshell using a combination of helium gas jets and a heater wire; (2) levitation-freezing of a DT-filled glass microshell as a method for fabricating and positioning a cryogenic shell target; (3) a target fabrication system intended for continuous fabrication, inspection, and delivery of cryogenic targets; and (4) development of diagnostics for inspection, recording, and analysis of a solid DT layer inside a glass microshell, and for observing the parameters controlling the target freezing process

An Integrated Refurbishment Design Process to Energy Efficiency

NARCIS (Netherlands)

Konstantinou, T.; Knaack, U.

2013-01-01

Given the very low renewal rate of the building stock, the efforts to reduce energy demand must focus on the existing residential buildings. Even though awareness has been raised, the effect on energy efficiency is often neglected during the design phase of refurbishment projects. This paper

High-Rise Refurbishment: The Energy-Efficient Upgrade of Multi-Story Residences in the European Union

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

Some 36 million European households are in high-rise residences, one in six of all households, and yet many of the buildings are in urgent need of refurbishment. This study, which is one in a series being conducted on behalf of the International Energy Agency addressing the energy performance of the existing IEA-wide building stock, identifies a Europe-wide cost-effective energy saving potential of 28% from energy-efficient refurbishment of the high-rise residential building stock. Attainment of this potential would imply a 1.5% reduction of Europe's total final energy demand and annual CO2 emissions savings of 35 Mt. In practice only the less efficient buildings need to be refurbished to realise these stockaverage savings and for these buildings typical savings in heating energy from refurbishment of between 70 and 80% are identified. Buildings in general suffer from a variety of barriers that tend to prevent their occupants from maintaining and refurbishing them to levels of comfort and energy performance that would be justified over the longer term, but collective housing in general is particularly susceptible to market failures. Many occupants do not own the property while their landlords usually have little motivation to finance improvements. Refurbishment requires collective agreement on a capital investment, which is difficult to establish especially when some occupants expect to live in the building over the longer-term but others only for the short-term. Furthermore, in most cases the occupants of high-rise residences are not among the wealthier members of society and they find it difficult to raise capital for longer-term investments. It is not surprising, then, to find that this section of the building stock is the most neglected and that there remain significant cost-effective opportunities for it to be refurbished in a way that improves comfort, saves energy, reduces CO2 emissions and significantly improves the urban environment.

Fabrication of cryogenic inertial-confinement-fusion targets using target free-fall technique. Report No. 2-82

International Nuclear Information System (INIS)

Kim, K.; Murphy, M.J.

1982-04-01

Techniques for fabricating cryogenic inertial confinement fusion targets (i.e., spherical shells containing a uniform layer of DT ice) are investigated using target free-fall concept. Detection and characterization of the moving targets are effected by optoelectronic means, of which the principal is an RF ac-interferometer. This interferometer system demonstrates, for the first time, the speed capabilities of the phase-modulation ac-interferometry. New techiques developed for handling, holding, launching, and transporting targets are also described. Results obtained at both room and cryogenic temperatures are presented

LECA refurbishment project or how to get ready for the next ten years

Energy Technology Data Exchange (ETDEWEB)

Boussard, Francois; Bois, Dominique; Blanc, Jean Yves

2005-01-01

Around 1995, CEA decided a strategy for its hot laboratories: Closing LAMA - Grenoble and LHA - Saclay, after RM2 - Fontenay-aux-Roses. Refurbishing and gathering irradiated material studies in LECI - Saclay. Refurbishing LECA - Cadarache for irradiated fuel examinations. Reprocessing pilot experiments being located in Atalante - Marcoule. Started up in 1964, LECA has got an exploitation license up to August 2005. In 2001, safety authorities agreed to extend it up to 2015, provided an extensive refurbishment is undertaken which includes civil engineering works to achieve the building earthquake resistance, based on 3D-computations and withstanding maximum historically likely earthquake, improving confinement by decontaminating, adding steel boxes inside cells, changing ventilation system and creating a mobile upper cell on the cell roof, changing power supplies, shielded glasses and most manipulators, improving travelling crane, fire protection, radioactivity monitoring and alarms, installing a new device for characterizing and evacuating wastes, decreasing the fissile mass stored inside the facility (source term). Most of the work should be ended by the end of 2005. Afterwards five cells, which do not withstand earthquake, will be deconstructed within 3 years. By mid 2004, 60 % of tasks are completed and all contracts are awarded. The total final cost is 97 M Euro, 80% of which regarding the only LECA refurbishment. (Author)

Refurbishment of Railroad Crossties : A Technical and Economic Analysis

Science.gov (United States)

1977-12-01

An analysis of the principal modes of failure for wooden railroad crossties was conducted and an evaluation of the technical and economic feasibility of refurbishing these ties was conducted. Among the principal modes of structural deterioration, onl...

The fabrication techniques of Z-pinch targets. Techniques of fabricating self-adapted Z-pinch wire-arrays

International Nuclear Information System (INIS)

Qiu Longhui; Wei Yun; Liu Debin; Sun Zuoke; Yuan Yuping

2002-01-01

In order to fabricate wire arrays for use in the Z-pinch physical experiments, the fabrication techniques are investigated as follow: Thickness of about 1-1.5 μm of gold is electroplated on the surface of ultra-fine tungsten wires. Fibers of deuterated-polystyrene (DPS) with diameters from 30 to 100 microns are made from molten DPS. And two kinds of planar wire-arrays and four types of annular wire-arrays are designed, which are able to adapt to the variation of the distance between the cathode and anode inside the target chamber. Furthermore, wire-arrays with diameters form 5-24 μm are fabricated with tungsten wires, respectively. The on-site test shows that the wire-arrays can self-adapt to the distance changes perfectly

Darlington refurbishment - performance improvement programs goals and experience

Energy Technology Data Exchange (ETDEWEB)

Mitchell, N. [Ontario Power Generation, Toronto, ON (Canada)

2015-07-01

This paper discusses the refurbishment program at the Darlington site. The program focuses on safety, integrity, excellence and personnel. Worker safety and public safety are of the highest priority. Success resulted from collaborative engineering interface, collaborative front end planning, highly competent people and respectful relationship with partners and regulators.

Complete fabrication of target experimental chamber and implement initial target diagnostics to be used for the first target experiments in NDCX-1

International Nuclear Information System (INIS)

Bieniosek, F.M.; Bieniosek, F.M.; Dickinson, M.R.; Henestroza, E.; Katayanagi, T.; Jung, J.Y.; Lee, C.W.; Leitner, M.; Ni, P.; Roy, P.; Seidl, P.; Waldron, W.; Welch, D.

2008-01-01

The Heavy Ion Fusion Science Virtual National Laboratory (HIFS-VNL) has completed the fabrication of a new experimental target chamber facility for future Warm Dense Matter (WDM) experiments, and implemented initial target diagnostics to be used for the first target experiments in NDCX-1. The target chamber has been installed on the NDCX-I beamline. This achievement provides to the HIFS-VNL unique and state-of-the-art experimental capabilities in preparation for the planned target heating experiments using intense heavy ion beams

A State of the Art Report on the Case Study of Hot Cell Decontamination and Refurbishment

Energy Technology Data Exchange (ETDEWEB)

Won, H. J.; Jung, C. H.; Moon, J. K.; Park, G. I.; Song, K. C

2008-08-15

As the increase of the operation age of the domestic high radiation facilities such as IMEF, PIEF and DFDF, the necessity of decontamination and refurbishment of hot cells in these facilities is also increased. In the near future, the possibilities of refurbishment of hot cells in compliance with the new regulations, the reuse of hot cells for the other purposes and the decommissioning of the facilities also exist. To prepare against the decontamination and refurbishment of hot cells, the reports on the refurbishment, decommissioning and decontamination experiences of hot cells in USA, Japan, France, Belgium and Great Britain were investigated. ANL of USA performed the project on the decontamination of hot cells. The purpose of the project was to practically eliminate the radioactive emissions of Rn-220 to the environment and to restore the hot cells to an empty restricted use condition. The five hot cells were emptied and decontaminated for restricted use. Chemical processing facility in JAEA of Japan was used for the reprocessing study of spent fuels, hot cells in CPF were refurbished from 1995 for the tests of the newly developed reprocessing process. In a first stage, decommissioning and decontamination were fully performed by the remote operation Then, decommissioning and decontamination were performed manually. By the newly developed process, they reported that the radiation exposure of workers were satisfactorily reduced. In the other countries, they also make an effort for the refurbishment and decontamination of hot cells and it is inferred that they accumulate experiences in these fields.

Refurbishments of RF systems

International Nuclear Information System (INIS)

Baelde, J.L.

1998-01-01

This document describes the activities of the R.F. System group during the years 1995-1996 in the frame of the refurbishment of the control system at GANIL accelerator. Modifications concerning the following sub-assemblies are mentioned: 1. voltage standards; 2. link card between the step by step motor control and the local control systems; 3. polarization system; 4. computer software for different operations. Also reported is the installation of ECR 4 source for the CO2. In this period the R2 Regrouping system has been installed, tested and put into operation. Several problems concerning the mechanical installation of the coupling loop and other problems related to the electronics operation were solved. The results obtained with the THI machine are presented

Powder Metallurgy Fabrication of Molybdenum Accelerator Target Disks

Energy Technology Data Exchange (ETDEWEB)

Lowden, Richard Andrew [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Kiggans Jr., James O. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Nunn, Stephen D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Parten, Randy J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2015-07-01

Powder metallurgy approaches for the fabrication of accelerator target disks are being examined to support the development of Mo-99 production by NorthStar Medical Technologies, LLC. An advantage of powder metallurgy is that very little material is wasted and, at present, dense, quality parts are routinely produced from molybdenum powder. The proposed targets, however, are thin wafers, 29 mm in diameter with a thickness of 0.5 mm, with very stringent dimensional tolerances. Although tooling can be machined to very high tolerance levels, the operations of powder feed, pressing and sintering involve complicated mechanisms, each of which affects green density and shrinkage, and therefore the dimensions and shape of the final product. Combinations of powder morphology, lubricants and pressing technique have been explored to produce target disks with minimal variations in thickness and little or no distortion. In addition, sintering conditions that produce densities for optimum target dissolvability are being determined.

Understanding valve program complexity in a refurbishment environment - learning from the past

International Nuclear Information System (INIS)

Roth, H.E.

2012-01-01

The complexity of Valve Program development, planning, execution and management in a refurbishment environment is an enormous undertaking requiring the proper coordination and integration of many moving parts. As such, lack of attention and understanding of this complexity has led to significant cost and schedule overruns in past refurbishment projects in the province. OPEX indicates the challenges in completing valve scope during refurbishments are related but not limited to; lack of detailed condition assessments, improper scope development, insignificant strategic approach to work task planning, scheduling and procurement, absence of contingency planning for common ‘as found’ conditions during execution, lack of proper training requirements, etc. In addition, past contracting strategies to employ numerous companies in collaboration to complete such a complex and specialized program, has resulted in further complications surrounding the management and integration of multiple quality programs and internal company processes. Finally, the aftermath of such fragmented projects results in an absolute closeout nightmare, often times taking years to locate, sift through and re-integrate pertinent information back into customer systems. Valve Program complexity cannot be understood by just anyone, only those that have lived through a refurbishment project and experienced the challenges mentioned above have the knowledge, skill, and ability to appreciate how to tactically apply past learning to realize future improvements. Furthermore, effective contractor-customer collaboration is crucial; true and in-depth knowledge and understanding of the customer quality programs, engineering and work management processes, configuration management requirements, and most importantly the imperative significance of nuclear safety, are all essential components to ensure overall alignment and program success. (author)

Understanding valve program complexity in a refurbishment environment - learning from the past

Energy Technology Data Exchange (ETDEWEB)

Roth, H.E. [Babcock & Wilcox Canada Ltd., Cambridge, Ontario (Canada)

2012-07-01

The complexity of Valve Program development, planning, execution and management in a refurbishment environment is an enormous undertaking requiring the proper coordination and integration of many moving parts. As such, lack of attention and understanding of this complexity has led to significant cost and schedule overruns in past refurbishment projects in the province. OPEX indicates the challenges in completing valve scope during refurbishments are related but not limited to; lack of detailed condition assessments, improper scope development, insignificant strategic approach to work task planning, scheduling and procurement, absence of contingency planning for common ‘as found’ conditions during execution, lack of proper training requirements, etc. In addition, past contracting strategies to employ numerous companies in collaboration to complete such a complex and specialized program, has resulted in further complications surrounding the management and integration of multiple quality programs and internal company processes. Finally, the aftermath of such fragmented projects results in an absolute closeout nightmare, often times taking years to locate, sift through and re-integrate pertinent information back into customer systems. Valve Program complexity cannot be understood by just anyone, only those that have lived through a refurbishment project and experienced the challenges mentioned above have the knowledge, skill, and ability to appreciate how to tactically apply past learning to realize future improvements. Furthermore, effective contractor-customer collaboration is crucial; true and in-depth knowledge and understanding of the customer quality programs, engineering and work management processes, configuration management requirements, and most importantly the imperative significance of nuclear safety, are all essential components to ensure overall alignment and program success. (author)

Structural radioactive waste from 'retubing/refurbishment' of Embalse nuclear power plant. Regulatory perspective

International Nuclear Information System (INIS)

Alvarez, Daniela E.; Lee Gonzales, Horacio M.; Medici, Marcela A.; Piumetti, Elsa H.

2009-01-01

Unlike the building of a new nuclear reactor, the 'retubing / refurbishment' of nuclear reactors that have been in operation for many years, involves the replacement of components in a radioactive environment. This requires a carefully planned radiation protection program to ensure protection of workers, the public and the environment as well as a radioactive waste management program for those radioactive waste generated during the process, which go beyond those generated during the normal operation and maintenance of the plant. Nucleoelectrica Argentina Sociedad Anonima (NA-SA) is scheduled to conduct the Life Extension Process of Embalse Nuclear Power Plant (CNE) which essentially consist of 'retubing / refurbishment' of the installation. The Nuclear Regulatory Authority (ARN) will then have an important activity related to the above process. In particular, this paper will describe some points of interest related to the generation and management of radioactive waste during the 'retubing / refurbishment' of the CNE, from the regulatory point of view. (author)

The Role of Laser Additive Manufacturing Methods of Metals in Repair, Refurbishment and Remanufacturing - Enabling Circular Economy

Science.gov (United States)

Leino, Maija; Pekkarinen, Joonas; Soukka, Risto

Circular economy is an economy model where products, components, and materials are aimed to be kept at their highest utility and value at all times. Repair, refurbishment and remanufacturing processes are procedures aiming at returning the value of the product during its life cycle. Additive manufacturing (AM) is expected to be an enabling technology in circular economy based business models. One of AM process that enables repair, refurbishment and remanufacturing is Directed Energy Deposition. Respectively Powder Bed Fusion enables manufacturing of replacement components on demand. The aim of this study is to identify the current research findings and state of art of utilizing AM in repair, refurbishment and remanufacturing processes of metallic products. The focus is in identifying possibilities of AM in promotion of circular economy and expected environmental benefits based on the found literature. Results of the study indicate significant potential in utilizing AM in repair, refurbishment and remanufacturing activities.

Ion beam analysis of gas turbine blades: evaluation of refurbishment ...

Indian Academy of Sciences (India)

Abstract. Refurbishment of hot components of gas turbines damaged in the harsh working environments is neces- ... 3000 r.p.m. and fluid forces that can cause fracture, yield- ... 800, 1200 and 2000 grit by employing mechanical grinding.

Fabrication and characterization of cryogenic targets for inertial confinement fusion

International Nuclear Information System (INIS)

Rieger, H.; Kim, K.

1979-08-01

A new technique has been developed which is capable of fabricating uniform cryogenic targets for use in inertial confinement fusion. The essence of the technique is to directly wet a target with a cold helium gas jet, which results in freezing of the DT mixture contained in the target. A controlled amount of current is pulsed through a heater wire surrounding the target, giving rise to fast evaporation and refreezing of the DT-condensate into a uniform layer. Experiments, which have been performed with D 2 -filled glass microshells, successfully produce uniform layers of both liquid and solid D 2 inside the glass shells. A set of data illustrating the technique is presented and analyzed

Tenth target fabrication specialists' meeting: Proceedings

International Nuclear Information System (INIS)

Foreman, L.R.; Stark, J.C.

1995-01-01

This tenth meeting of specialists in target fabrication for inertial confinement is unique in that it is the first meeting that was completely unclassified. As a result of the new classification, we were able to invite more foreign participation. In addition to participants from the US, UK, and Canada, representatives from France, Japan, and two Russian laboratories attended, about 115 in all. This booklet presents full papers and poster sessions. Indirect and direct drive laser implosions are considered. Typical topics include: polymer or aluminium or resorcinol/formaldehyde shells, laser technology, photon tunneling microscopy as a characterization tool, foams, coatings, hohlraums, and beryllium capsules. Hydrogen, deuterium, tritium, and beryllium are all considered as fuels

Tenth target fabrication specialists` meeting: Proceedings

Energy Technology Data Exchange (ETDEWEB)

Foreman, L.R.; Stark, J.C. [comp.

1995-11-01

This tenth meeting of specialists in target fabrication for inertial confinement is unique in that it is the first meeting that was completely unclassified. As a result of the new classification, we were able to invite more foreign participation. In addition to participants from the US, UK, and Canada, representatives from France, Japan, and two Russian laboratories attended, about 115 in all. This booklet presents full papers and poster sessions. Indirect and direct drive laser implosions are considered. Typical topics include: polymer or aluminium or resorcinol/formaldehyde shells, laser technology, photon tunneling microscopy as a characterization tool, foams, coatings, hohlraums, and beryllium capsules. Hydrogen, deuterium, tritium, and beryllium are all considered as fuels.

Energy efficiency improvement target for SIC 34 - fabricated metal products. Revised target support document

Energy Technology Data Exchange (ETDEWEB)

Byrer, T. G.; Billhardt, C. F.; Farkas, M. S.

1977-02-15

In accordance with section 374 of the Energy Policy and Conservation Act (EPCA), Pub. L. 94-163, the Federal Energy Administration (FEA) proposed industrial energy efficiency improvement targets for the ten most energy-consumptive manufacturing industries in the U.S. Following public hearings and a review of the comments made, the final targets for Fabricated Metal Products (SIC 34) were established and are described. Using 1972 data on the energy consumed to produce specific metal products, it was concluded that a 24% reduction in energy consumption for SIC 34 is a viable goal for achievement by 1980. (ERA citation 04:045006)

Information-management data base for fusion-target fabrication processes

International Nuclear Information System (INIS)

Reynolds, J.

1982-01-01

A computer-based data-management system has been developed to handle data associated with target-fabrication processes including glass microballoon characterization, gas filling, materials coating, and storage locations. The system provides automatic data storage and computation, flexible data-entry procedures, fast access, automated report generation, and secure data transfer. It resides on a CDC CYBER 175 computer and is compatible with the CDC data-base-language Query Update, but is based on custom FORTRAN software interacting directly with the CYBER's file-management system. The described data base maintains detailed, accurate, and readily available records of fusion targets information

Information management data base for fusion target fabrication processes

International Nuclear Information System (INIS)

Reynolds, J.

1983-01-01

A computer-based data management system has been developed to handle data associated with target fabrication processes including glass microballoon characterization, gas filling, materials coating, and storage locations. The system provides automatic data storage and computation, flexible data entry procedures, fast access, automated report generation, and secure data transfer. It resides on a CDC CYBER 175 computer and is compatible with the CDC data base language Query Update, but is based on custom fortran software interacting directly with the CYBER's file management system. The described data base maintains detailed, accurate, and readily available records of fusion targets information

Experience feedback on the refurbishment of the LECA hot laboratory at Cadarache

International Nuclear Information System (INIS)

Grandjean, Jean-Paul; Autran, Bernard; Blanc, Jean-Yves

2007-01-01

Full text: After ten years of renovation work, the LECA hot laboratory refurbishment project has finally been completed which means it is now time to draw a few conclusions. Refurbishment of LECA was needed to enable PIE in this laboratory up to 2015. Improvements were made according to the laboratory safety assessment in March 2001. More than 400,000 working hours were clocked up without any serious accidents. The overall radiological record remained below 0.4 man.Sv for this period despite a high contamination level in the venting system and hot cells. The total fissile mass was decreased by a factor of three, and contamination was also considerably reduced. The project was finalised two years later than expected, mainly due to difficulties with two contracts on civil engineering work to improve seismic resistance and on inserting stainless steel casing into some hot cells. Renovation work on existing structures was underestimated, as was the time required to re-commission the cells. The fact that the total number of external staff working inside the facility at the same time was limited also slowed work down. This delay affected the research programmes mainly over the last two years. On the whole, 85 % of all experimentation activities were nevertheless continued during refurbishment. New steps for refurbishment have already been planned so as to extend the LECA service life once again. A line of lead-shielded cells - not designed to withstand current earthquake standards - will be demolished before the end of 2008, and civil engineering operations have been programmed for 2013-2014 so the facility will be able to withstand a maximum design earthquake. (authors)

Extended layup of steam generators during a refurbishment outage

International Nuclear Information System (INIS)

Marks, C.R.; Little, M.D.; Slade, J.; Gendron, T.

2009-01-01

In May 2008, Point Lepreau Generating Station (PLGS), owned and operated by New Brunswick Power Nuclear (NBPN), entered an extended refurbishment outage initially expected to last approximately 18 months. NBPN had the two inter-related goals with respect to layup of the steam generators during this period: equipment preservation and inspection interval modification. The steam generators were to be preserved such that there was no loss of operating life due to corrosion of either the tubing (Alloy 800NG) or other internal components (with carbon steel being the limiting material with respect to corrosion). Additionally, NBPN desired that the time in layup not count as operating time in setting the schedule for future inspections. That is, a key goal of the steam generator layup is that the future inspection interval be based on operating time, not calendar time. The NBPN approach consists of the following four steps: A review of industry operating experience with long outages (including both PWRs and PHWRs); The development of technically based layup strategies and procedures; A mid-outage review of the implementation of the layup strategies and procedures; and A post-outage review to determine if the actual conditions in the steam generators will support modification of the inspection interval. This paper discusses the results of the first three of these steps. At this time, the plant is still in the refurbishment outage. Throughout the outage evaluation process, the following issues have been the main focus of the reviews: The potential for degradation (pitting and cracking) of steam generator tubes; The potential for general corrosion of carbon and low alloy steel internals; Oxidation of deposits (which could subsequently lead to oxidizing conditions during operation, possibly leading to tube degradation). This paper discusses the industry operating experience reviewed, the pre-outage assessments, and the mid-outage assessments. Current outage planning places the

Energy efficiency improvement target for SIC 34 - fabricated metal products

Energy Technology Data Exchange (ETDEWEB)

Byrer, T. G.; Billhardt, C. F.; Farkas, M. S.

1977-03-15

A March 15, 1977 revision of a February 15, 1977 document on the energy improvement target for the Fabricated Metal Products industry (SIC 34) is presented. A net energy savings in 1980 of 24% as compared with 1972 energy consumption in SIC 34 is considered a realistic goal. (ERA citation 04:045008)

Ultra-hard AlMgB14 coatings fabricated by RF magnetron sputtering from a stoichiometric target

Science.gov (United States)

Grishin, A. M.; Khartsev, S. I.; Böhlmark, J.; Ahlgren, M.

2015-01-01

For the first time hard aluminum magnesium boride films were fabricated by RF magnetron sputtering from a single stoichiometric ceramic AlMgB14 target. Optimized processing conditions (substrate temperature, target sputtering power and target-to-substrate distance) enable fabrication of stoichiometric in-depth compositionally homogeneous films with the peak values of nanohardness 88 GPa and Young's modulus 517 GPa at the penetration depth of 26 nm and, respectively, 35 and 275 GPa at 200 nm depth in 2 μm thick film.

Refurbishment of the LECI

International Nuclear Information System (INIS)

Blanc, J. Y.; Cheron, C.

2001-01-01

The LECI is a hot laboratory built in Saclay in the early sixties for examinations on fuel rods, with 25 hot cells. Around 1995, a refurbishment programme up to 2004 was decided and started. It includes the renovation of about half of the cells of the existing building and the construction of a new building with about twenty lead-shielded hot cells for mechanical testing. At mid 2001, this paper presents the status of the project and the perspectives for the next years. These modifications aims: -To increase sample preparation and examination capacities on nuclear metals: mainly zirconium, steel and aluminium alloys. -To keep existing P. I. facilities on short P. W. R. fuel rod as support for ramp testing programmes in the nearby Osiris reactor and as support for new cladding development programmes. -To gather in LECI mechanical testing facilities which are up to now located in another facility to be shut down at the end of 2003. Concerning the existing building, most of the planned refurbishment has been performed and 10 cells have been cleaned and 8 of them will be reequipped at the end of 2001: a metallography line with new microscope, hardness testing, periscopes, TEM thin foil and EPMA preparation, two cells for tooling mechanical samples (milling machine, lathe, spark erosion), one cell for clad creep testing on long term storage conditions and a cell with a 250 kN tensile machine. The new building is built, the lead cells will be installed in 2002 and most of the scientific equipment have been ordered. They include: wire erosion machining 3 tensile machines with extensometry, 2 Charpy, different creep and internal pressure machines, autoclaves EPMA and Raman analysis. The schedule is to open this building to irradiated materials ( no fuel except on EPMA) at the end of 2003. Some difficulties such as the public enquires have been successfully overcome, some financial constraints have delayed the project of about one year, and technical difficulties have

Proposal for the risk management implementation phase in oil field development project by adding value on the refurbishment of critical equipment

Directory of Open Access Journals (Sweden)

Hamid Abdul

2017-01-01

Full Text Available Refurbishment process is a conceptual stage in product life cycle. It is utilized in existing equipment in the field by adding value to recondition and repaired equipment. The main interest of this paper is to implement and design risk management implementation phase in oil field development project on the refurbishment of critical equipment in oil and gas industry. This paper is provided base on research and experiences in risk management and learned from practical team in industry which matched by an application in oil field development project in refurbishment of critical equipment. A framework of implementation phase for risk management in oil field development project in refurbishment critical equipment were reviewed and added value on communication skills of the project team to the stakeholder and organization, which support to external body and vice-versa. Risk management framework can be used for reference of refurbishment process with simply process and developed with same concept for the next wide development project in industry.

Refurbishing of a Freeze Drying Machine, used in Nuclear Medicine for Radiopharmaceuticals Production

International Nuclear Information System (INIS)

Gaytan-Gallardo, E.; Desales-Galeana, G.

2006-01-01

The refurbishing of a freeze drying machine used in the radiopharmaceuticals production, applied in nuclear medicine in the Radioactive Materials Department of the Nuclear Research National Institute in Mexico (ININ in Spanish), is presented. The freeze drying machine was acquired in the 80's decade and some components started having problems. Then it was necessary to refurbish this equipment by changing old cam-type temperature controllers and outdated recording devices, developing a sophisticated software system that substitutes those devices. The system is composed by a freeze drying machine by Hull, AC output modules for improved temperature control, a commercial data acquisition card, and the software system

Airline fuel saving through JT9D engine refurbishment

Energy Technology Data Exchange (ETDEWEB)

Allison, J.W.; Weisel, D.R.

1981-01-01

Areas are identified in the JT9D engine where the potential exists for either further performance recovery following repair, or for improved performance retention. A number of new procedures and tools which will improve performance recovery are described. Improvements in inspection techniques are discussed. Operational techniques which will improve performance retention and impact degree of refurbishment required are also presented.

Report on participation of the operational dosimetry division in refurbishment of the RA reactor, Task 3.08/04-13

International Nuclear Information System (INIS)

Ninkovic, M.

1963-01-01

During the refurbishment of the RA reactor, from January to June 1963 the division of operational division had a very important role and comprehensive tasks. To enable safety of the staff it was necessary to provide protection clothes, personnel dosemeters; permanent monitoring of radiation doses; strict control of the procedures for completing the planned maintenance and repair operations to avoid contamination of the personnel and working space. The refurbishment activities described in this report are: removal of fuel from the core; refurbishment of the heavy water system; decontamination of the distillation equipment; repair of the gas system

Thermal protection and refurbishment of an old building. Lectures; Waermeschutz und Altbausanierung. Vortraege

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

Within the 22nd Hanseatic Reconstruction Symposium at the Baltic Seaside Heringsdorf/Usedom (Federal Republic of Germany) from 3rd to 5th November 2011, the following lectures were held: (1) Energetic refurbishment possibilities for building within existing properties by means of representative examples (F. Deitschum); (2) Constructional thermal insulation and indoor climate - for the good of the environment? (S. Groer); (3) Innovative insulating materials for the structural refurbishment? (O. Fechner); (4) Energetic half-timbering refurbishment (K. Lissner); (5) Wooden solar facades for existing buildings (U. Schwarz); (6) Timber beam bowls in a historic brickwork (U. Mueller); (7) Timber beam bowls and interior insulation (U. Ruisinger); (8) Innovative solutions for cavity filling insulations (A. Stefenelli); (9) Thermal insulating plaster - also for historical buildings (T. Stahl); (10) Experimental tension analysis of the structural behaviour of historical cross vaults (A.-J. Petereit); (10) Investigation of the increase of the flexural strength of stonework constructions with self-compacting steel fibre reinforced concrete (D. Haessler); (11) Dry and dense - the modified WTA leaflet 4-6, 'Subsequent sealing of components in contact with soil' - Content and innovations (R. Spirgatis); (12) What does the new standard DIN 68800 hold? (H. Willeitner); (13) News from the standard DIN 18195 waterproofing of buildings (H.-P. Sommer); (14) Liability of planning of the offering entrepreneur (H. Immoor); (15) Climate change and preservation of structures (W. Zillig); (16) Typical problems and deficiencies of the energetic refurbishment of old store buildings (H. Boehmer); (17) When do ex post horizontal sealings with injection agents make sense - Fundamentals for evaluation, planning and execution (F.-J. Hoelzen); (18) Drying up behaviour of stonework of different quality and at different variants of insulation (F. Antretter).

Process for the fabrication of aluminum metallized pyrolytic graphite sputtering targets

Science.gov (United States)

Makowiecki, Daniel M.; Ramsey, Philip B.; Juntz, Robert S.

1995-01-01

An improved method for fabricating pyrolytic graphite sputtering targets with superior heat transfer ability, longer life, and maximum energy transmission. Anisotropic pyrolytic graphite is contoured and/or segmented to match the erosion profile of the sputter target and then oriented such that the graphite's high thermal conductivity planes are in maximum contact with a thermally conductive metal backing. The graphite contact surface is metallized, using high rate physical vapor deposition (HRPVD), with an aluminum coating and the thermally conductive metal backing is joined to the metallized graphite target by one of four low-temperature bonding methods; liquid-metal casting, powder metallurgy compaction, eutectic brazing, and laser welding.

Space Telescope maintenance and refurbishment

Science.gov (United States)

Trucks, H. F.

1983-01-01

The Space Telescope (ST) represents a new concept regarding spaceborne astronomical observatories. Maintenance crews will be brought to the orbital worksite to make repairs and replace scientific instruments. For major overhauls the telescope can be temporarily returned to earth with the aid of the Shuttle. It will, thus, be possible to conduct astronomical studies with the ST for two decades or more. The five first-generation scientific instruments used with the ST include a wide field/planetary camera, a faint object camera, a faint object spectrograph, a high resolution spectrograph, and a high speed photometer. Attention is given to the optical telescope assembly, the support systems module, aspects of mission and science operations, unscheduled maintenance, contingency orbital maintenance, planned on-orbit maintenance, ground maintenance, ground refurbishment, and ground logistics.

RA Reactor operation and maintenance (I-IX), part VII, Task 3.08/04, Refurbishment of the RA reactor

International Nuclear Information System (INIS)

Zecevic, V.

1963-12-01

This volume covers the following reports concerned with the maintenance and repair work of the RA reactor: repair of the technical water system; maintenance of the transportation equipment; vacuuming and drying during refurbishment; repair and decontamination of the distillation device; and the report on participation of the operational dosimetry division in the RA reactor refurbishment activities

Physicochemical characteristics and occupational exposure to coarse, fine and ultrafine particles during building refurbishment activities

Energy Technology Data Exchange (ETDEWEB)

Azarmi, Farhad; Kumar, Prashant, E-mail: p.kumar@surrey.ac.uk, E-mail: prashant.kumar@cantab.net; Mulheron, Mike [University of Surrey, Department of Civil and Environmental Engineering, Faculty of Engineering and Physical Sciences (United Kingdom); Colaux, Julien L.; Jeynes, Chris [University of Surrey, Faculty of Engineering and Physical Sciences, Ion Beam Centre (United Kingdom); Adhami, Siavash; Watts, John F. [University of Surrey, The Surface Analysis Laboratory, Faculty of Engineering and Physical Sciences (United Kingdom)

2015-08-15

Understanding of the emissions of coarse (PM{sub 10} ≤10 μm), fine (PM{sub 2.5} ≤2.5 μm) and ultrafine particles (UFP <100 nm) from refurbishment activities and their dispersion into the nearby environment is of primary importance for developing efficient risk assessment and management strategies in the construction and demolition industry. This study investigates the release, occupational exposure and physicochemical properties of particulate matter, including UFPs, from over 20 different refurbishment activities occurring at an operational building site. Particles were measured in the 5–10,000-nm-size range using a fast response differential mobility spectrometer and a GRIMM particle spectrometer for 55 h over 8 days. The UFPs were found to account for >90 % of the total particle number concentrations and <10 % of the total mass concentrations released during the recorded activities. The highest UFP concentrations were 4860, 740, 650 and 500 times above the background value during wall-chasing, drilling, cementing and general demolition activities, respectively. Scanning electron microscopy, X-ray photoelectron spectroscopy and ion beam analysis were used to identify physicochemical characteristics of particles and attribute them to probable sources considering the size and the nature of the particles. The results confirm that refurbishment activities produce significant levels (both number and mass) of airborne particles, indicating a need to develop appropriate regulations for the control of occupational exposure of operatives undertaking building refurbishment.

Energy Efficiency Performance in Refurbishment Projects with Design Team Attributes As A Mediator: A Pilot Study

Science.gov (United States)

Sekak, Siti Nor Azniza Ahmad; Rahmat Dr, Ismail, Prof.; Yunus, Julitta; Saád, Sri Rahayu Mohd; Hanafi Azman Ong, Mohd

2017-12-01

The Energy Efficiency (EE) plays an important role over the building life cycle and the implementation of EE in refurbishment projects has a significant potential towards the reduction of greenhouse gas emissions. However, the involvement of the design team at the early stage of the refurbishment projects will determine the success of EE implementations. Thus, a pilot study was conducted at the initial stage of the data collection process of this research to validate and verify the questionnaires.

Refurbish research and test reactors corresponding to global age of nuclear energy

International Nuclear Information System (INIS)

Mishima, Kaichiro; Oyama, Yukio; Okamoto, Koji; Yamana, Hajime; Yamaguchi, Akira

2011-01-01

This special article featured arguments for refurbishment of research and test reactors corresponding to global age of nuclear energy, based on the report: 'Investigation of research facilities necessary for future joint usage' issued by the special committee of Atomic Energy Society of Japan (AESJ) in September 2010. It consisted of six papers titled as 'Introduction-establishment of AESJ special committee for investigation', 'State of research and test reactors in Japan', 'State of overseas research and test reactors', 'Needs analysis for research and test reactors', 'Proposal of AESJ special committee' and 'Summary and future issues'. In order to develop human resources and promote research and development needed in global age of nuclear energy, research and test reactors would be refurbished as an Asian regional center of excellence. (T. Tanaka)

Decision-making process to shut down, refurbish/modify, or decommission research reactors

International Nuclear Information System (INIS)

Stover, R.L.; Murphie, W.E.

1992-01-01

Most US research reactors were built more than 20 years ago and some more than 40 years ago. Many have undergone refurbishments and modifications to update their safety systems and experimental capabilities. But changing safety bases, social concerns, and budget constraints have required research reactor operators to continually make decisions to shut down or refurbish/modify their facilities. These decisions involve potential replacement of reactor equipment that has reached its lifetime limits. Changes in philosophy and operation of the reactors are also factors to be considered. In this paper, each of the four factors involved in the decision-making process are discussed in detail. Then, several examples from DOE research reactors in the United States are discussed. Finally, some general conclusions are given to aid in the decision-making process

Refurbishment and Automation of Thermal Vacuum Facilities at NASA/GSFC

Science.gov (United States)

Dunn, Jamie; Gomez, Carlos; Donohue, John; Johnson, Chris; Palmer, John; Sushon, Janet

1999-01-01

The thermal vacuum facilities located at the Goddard Space Flight Center (GSFC) have supported both manned and unmanned space flight since the 1960s. Of the eleven facilities, currently ten of the systems are scheduled for refurbishment or replacement as part of a five-year implementation. Expected return on investment includes the reduction in test schedules, improvements in safety of facility operations, and reduction in the personnel support required for a test. Additionally, GSFC will become a global resource renowned for expertise in thermal engineering, mechanical engineering, and for the automation of thermal vacuum facilities and tests. Automation of the thermal vacuum facilities includes the utilization of Programmable Logic Controllers (PLCs), the use of Supervisory Control and Data Acquisition (SCADA) systems, and the development of a centralized Test Data Management System. These components allow the computer control and automation of mechanical components such as valves and pumps. The project of refurbishment and automation began in 1996 and has resulted in complete computer control of one facility (Facility 281), and the integration of electronically controlled devices and PLCs in multiple others.

Computer Refurbishment

International Nuclear Information System (INIS)

Ichiyen, Norman; Chan, Dominic; Thompson, Paul

2004-01-01

The major activity for the 18-month refurbishment outage at the Point Lepreau Generating Station is the replacement of all 380 fuel channel and calandria tube assemblies and the lower portion of connecting feeder pipes. New Brunswick Power would also take advantage of this outage to conduct a number of repairs, replacements, inspections and upgrades (such as rewinding or replacing the generator, replacement of shutdown system trip computers, replacement of certain valves and expansion joints, inspection of systems not normally accessible, etc.). This would allow for an additional 25 to 30 years. Among the systems to be replaced are the PDC's for both shutdown systems. Assessments have been completed for both the SDS1 and SDS2 PDC's, and it has been decided to replace the SDS2 PDCs with the same hardware and software approach that has been used successfully for the Wolsong 2, 3, and 4 and the Qinshan 1 and 2 SDS2 PDCs. For SDS1, it has been decided to use the same software development methodology that was used successfully for the Wolsong and Qinshan called the I A and to use a new hardware platform in order to ensure successful operation for the 25-30 year station operating life. The selected supplier is Triconex, which uses a triple modular redundant architecture that will enhance the robustness/fault tolerance of the design with respect to equipment failures

Inertial confinement fusion target component fabrication and technology development support. Annual report 10/1/98 through 9/30/99

International Nuclear Information System (INIS)

Gibson, Jane

1999-01-01

General Atomics (GA) has served as the Inertial Confinement Fusion (ICF) Target Component Fabrication and Technology Development Support contractor for the U.S. Department of Energy since December 30, 1990. This report documents the technical activities of the period October 1, 1998 through September 30, 1999. During this period, GA and our partner Schafer Corporation were assigned 17 formal tasks in support of the ICF program and its five laboratories. A portion of the effort on these tasks included providing direct ''Onsite Support'' at Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), and Sandia National Laboratory (SNL). We fabricated and delivered over 1790 hohlraum mandrels and numerous other micromachined components to LLNL, LANL, and SNL. We produced more than 1380 glass and plastic target capsules over a wide range of sizes and designs (plus over 300 near target-quality capsules) for LLNL, LANL, SNL, and University of Rochester/Laboratory for Laser Energetic (UR/LLE). We also delivered various target foils and films for Naval Research Lab (NRL) and UWLLE in FY99. We fabricated a device to polish NIF-sized beryllium shells and prepared a laboratory for the safe operation of beryllium polishing activities. This report describes these target fabrication activities and the target fabrication and characterization development activities that made the deliveries possible. During FY99, the GA/Schafer portion of the GA/Schafer-UR/LLE-LANL team effort for design, procurement, installation, and testing of the OMEGA Cryogenic Target System (OCTS) that will field cryogenic targets on OMEGA was completed. All components of the OCTS were procured, fabricated, assembled, tested, and shipped to UR/LLE. Only minor documentation tasks remain to be done in FY00. The ICF program is anticipating experiments at the OMEGA laser and the National Ignition Facility (NIF) which will require targets containing cryogenic layered D2 or deuterium

Small might be beautiful, but bigger performs better: Scale economies in “green” refurbishments of apartment housing

International Nuclear Information System (INIS)

Michelsen, Claus; Rosenschon, Sebastian; Schulz, Christian

2015-01-01

The energy efficiency of the residential housing stock plays a key role in strategies to mitigate climate change and global warming. In this context, it is frequently argued that private investment and the quality of thermal upgrades are too low in the light of the challenges faced and the potential energy cost savings. While many authors address the potential barriers for investors to increase energy efficiency, studies on the capabilities of different investors to reduce energy requirements of their property are scarce. This study investigates potential advantages of housing company's size, i.e. economies of scale, economies of scope and institutional learning in thermal upgrades of residential housing. Based on unique data on energy consumption in 102,307 apartment buildings in Germany, we present new evidence for the advantages and disadvantages of a housing company's size in “green” retrofitting projects. Our estimations show, that large housing companies outperform private landlords by far in high effort refurbishment projects. In contrast, private landlords appear to have advantages in low effort, incremental refurbishment activities. We demonstrate that a substantial share of the advantages of larger firms can be associated with specialization (i.e. repeated projects). The results offer new options for policy makers to refine the support schemes toward a low carbon housing stock. - Highlights: • First study to analyze the effects of housing companies size on “green” refurbishment • Economies of scale, scope and learning all affect energy efficiency refurbishments. • Specialization on distinct refurbishments influences outcome of thermal upgrades. • Analysis based on a large and unique sample of apartment buildings in Germany

Bruce A refurbishment - preparatory work completed, major tasks to begin soon

International Nuclear Information System (INIS)

Boyd, F.

2006-01-01

Over the past year Bruce Power has been planning and organizing for an extensive refurbishment of the Units 1 and 2 of the Bruce A station. Now the company and its several major contractors are ready to proceed with the most challenging aspects of the actual work. The largest tasks are the replacement of the 8 steam generators and of the 480 complete fuel channels in each unit Bruce Power has created a separate website connected to their basic one to provide ongoing information about the progress of the work. The following brief note is intended to provide an outline of this challenging refurbishment program and to invite readers to visit this website to follow its progress. To provide background the writer was accorded an informative and interesting tour of the units by Rob Liddle, of Bruce Power, on September 28, 2006 the day after the ceremony commemorating the Douglas Point station held at the Bruce site. (author)

Design and Fabrication of Titanium Target for Portable Neutron Generator

International Nuclear Information System (INIS)

Lee, Cheol Ho; Oh, Byunghoon; Chang, Daesik; Jang, Dohyun; In Sang Yeol; Park, Jaewon; Hong, Kwangpyo

2014-01-01

For the neutron generator to produce a neutron flux of the above order, a target that produces fast neutrons in the generator plays an important role, and the target is used and applied to develop the generator due to its simplicity and inexpensive. Making suitable targets for neutron production, especially mono-energy neutrons, has always been of interest. These targets have been used for neutron production reaction studies, calibration of detectors, and neutron therapy. Different studies have been carried out on deuterium and tritium for making solid targets to produce mono-energy neutron from D-D and D-T reactions. A lot of investigations have been carried out on solid target properties such as lifetime, thermal stability, neutron yield, and energy. Vaporized zirconium and titanium layers on a high thermal conductivity substrate (Cu, Mo, Ag) have been used as deuterium and tritium absorbing metals. The density of titanium is smaller than zirconium and the range of charged particles in the titanium targets is more than that in zirconium targets. Thus, titanium targets have more neutron yield than zirconium targets in a low energy beam and titanium is usually used to make a target. The titanium target was designed and simulated to determine the suitable thickness of the target. As a result of the simulation, the target was fabricated to generate fast neutrons by the reaction. The thickness of the target was measured using a profiler. The thickness of the two targets is 2.108 and 2.190 μm. The target will be applied to produce neutrons in a neutron generator

Refurbishment of BR2 (Phase 4 and 5)[1997 Scientific Report of the Belgian Nuclear Research Centre

Energy Technology Data Exchange (ETDEWEB)

Gubel, P.; Dekeyser, J.; Van der Auwera, J.

1998-07-01

The extensive refurbishment of the BR-2 materials testing reactor should allow another 10 to 15years of continued operation. The refurbishment programme is required in order to comply with modern safety standards, to enhance the reliability of operation, and to compensate for the ageing of the installations of a facility that has reached about 35 years of intensive service. The main objectives and achievements of phase 4 and 5 are described.

The Efficacy of Waste Management Plans in Australian Commercial Construction Refurbishment Projects

Directory of Open Access Journals (Sweden)

Mary Hardie

2012-11-01

Full Text Available Renovation and refurbishment of the existingcommercial building stock is a growing area oftotal construction activity and a significantgenerator of waste sent to landfill in Australia. Awritten waste management plan (WMP is awidespread regulatory requirement forcommercial office redevelopment projects. Thereis little evidence, however, that WMPs actuallyincrease the quantity of waste that is ultimatelydiverted from landfill. Some reports indicate anabsence of any formal verification or monitoringprocess by regulators to assess the efficacy ofthe plans. In order to gauge the extent of theproblem a survey was conducted of twenty fourconsultants and practitioners involved incommercial office building refurbishment projectsto determine the state of current practice withregard to WMPs and to elicit suggestions withregard to ways of making the process moreeffective. Considerable variation in commitmentto recycling policies was encountered indicatinga need to revisit waste minimisation practices ifthe environmental performance of refurbishmentprojects is to be improved.

Building performance simulation as a design tool for refurbishment of buildings

NARCIS (Netherlands)

Hensen, J.L.M.; Bartak, M.; Drkal, F.; Dunovska, T.; Lain, M.; Matuska, T.; Schwarzer, J.; Sourek, B.; Bednar, T.

2004-01-01

This paper attempts to outline the current state-of-the-art regarding the use of building performance simulation as a design tool for refurbishment of buildings. This is illus-trated by means of three recent studies for conversion of historical buildings (an early 20th century factory, and a water

Target fabrication and development in the Centre d'Etudes de Limeil

International Nuclear Information System (INIS)

Clement, X.; Coudeville, A.; Eyharts, P.; Perrine, J.P.; Rouillard, R.

1983-10-01

The present state of research in Limeil laboratory for the production of inertial confinement fusion targets is described in this communication. A summary of typical areas, previously investigated, including new developments, is as follows: - production of hollow glass microspheres, having wide outside diameter range and aspect-ratio, using dried-alcogels, - preparation and fabrication of low density foams having plane or hemispherical shape, - deposition of a wide range of conductive materials as well as silicon and organic polymers, - development of laser and spark erosion machining which are useful tools for producing minute parts of complex targets, - characterization and analysis of plastic or coal metal coated targets, are done by using interferometry techniques and X-ray image analysis as well as X-ray absorption measurements

Inertial confinement fusion target component fabrication and technology development support: Annual report, October 1, 1997--September 30, 1998

Energy Technology Data Exchange (ETDEWEB)

Gibson, J. [ed.

1998-12-01

During this period, General Atomics (GA) and their partner Schafer Corporation were assigned 17 formal tasks in support of the Inertial Confinement Fusion (ICF) program and its five laboratories. A portion of the effort on these tasks included providing direct ``On-site Support`` at Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), and Sandia National Laboratory Albuquerque (SNLA). They fabricated and delivered over 1,200 hohlraum mandrels and numerous other micromachined components to LLNL, LANL, and SNLA. They produced more than 1,300 glass and plastic target capsules for LLNL, LANL, SNLA, and the University of Rochester/Laboratory for Laser Energetics (UR/LLE). They also delivered nearly 2,000 various target foils and films for Naval Research Lab (NRL) and UR/LLE in FY98. This report describes these target fabrication activities and the target fabrication and characterization development activities that made the deliveries possible. During FY98, great progress was made by the GA/Schafer-UR/LLE-LANL team in the design, procurement, installation, and testing of the OMEGA Cryogenic Target System (OCTS) that will field cryogenic targets on OMEGA. The design phase was concluded for all components of the OCTS and all major components were procured and nearly all were fabricated. Many of the components were assembled and tested, and some have been shipped to UR/LLE. The ICF program is anticipating experiments at the OMEGA laser and the National Ignition Facility (NIF) which will require targets containing cryogenic layered D{sub 2} or deuterium-tritium (DT) fuel. They are part of the National Cryogenic Target Program and support experiments at LLNL and LANL to generate and characterize cryogenic layers for these targets. They also contributed cryogenic support and developed concepts for NIF cryogenic targets. This report summarizes and documents the technical progress made on these tasks.

Inertial confinement fusion target component fabrication and technology development support: Annual report, October 1, 1997 - September 30, 1998

International Nuclear Information System (INIS)

Gibson, J.

1998-12-01

During this period, General Atomics (GA) and their partner Schafer Corporation were assigned 17 formal tasks in support of the Inertial Confinement Fusion (ICF) program and its five laboratories. A portion of the effort on these tasks included providing direct ''On-site Support'' at Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), and Sandia National Laboratory Albuquerque (SNLA). They fabricated and delivered over 1,200 hohlraum mandrels and numerous other micromachined components to LLNL, LANL, and SNLA. They produced more than 1,300 glass and plastic target capsules for LLNL, LANL, SNLA, and the University of Rochester/Laboratory for Laser Energetics (UR/LLE). They also delivered nearly 2,000 various target foils and films for Naval Research Lab (NRL) and UR/LLE in FY98. This report describes these target fabrication activities and the target fabrication and characterization development activities that made the deliveries possible. During FY98, great progress was made by the GA/Schafer-UR/LLE-LANL team in the design, procurement, installation, and testing of the OMEGA Cryogenic Target System (OCTS) that will field cryogenic targets on OMEGA. The design phase was concluded for all components of the OCTS and all major components were procured and nearly all were fabricated. Many of the components were assembled and tested, and some have been shipped to UR/LLE. The ICF program is anticipating experiments at the OMEGA laser and the National Ignition Facility (NIF) which will require targets containing cryogenic layered D 2 or deuterium-tritium (DT) fuel. They are part of the National Cryogenic Target Program and support experiments at LLNL and LANL to generate and characterize cryogenic layers for these targets. They also contributed cryogenic support and developed concepts for NIF cryogenic targets. This report summarizes and documents the technical progress made on these tasks

Refurbishment of the IEAR1 primary coolant system piping supports

International Nuclear Information System (INIS)

Fainer, Gerson; Faloppa, Altair A.; Oliveira, Carlos A. de; Mattar Neto, Miguel

2015-01-01

A partial replacement of the IEA-R1 piping system was concluded in 2014. This paper presents the study and the structural analysis of the IEA-R1 primary circuit piping supports, considering all the changes involved in the replacement. The IEA-R1 is a nuclear reactor for research purposes designed by Babcox-Willcox that is operated by IPEN since 1957. The reactor life management and modernization program is being conducted for the last two decades and already resulted in a series of changes, especially on the reactor coolant system. This set of components, divided in primary and secondary circuit, is responsible for the circulation of water into the core to remove heat. In the ageing management program that includes regular inspection, some degradation was observed in the primary piping system. As result, the renewing of the piping system was conducted in 2014. Moreover the poor condition of some original piping supports gave rise to the refurbishment of all piping supports. The aim of the present work is to review the design of the primary system piping supports taking into account the current conditions after the changes and refurbishment. (author)

Was It Really Worth Pain? Refurbishment of Mercedes-Benz Trucks by Botswana Defence Force

National Research Council Canada - National Science Library

Rangobana, Samuel A; Alkebaisi, Hussain K

2005-01-01

.... Logistics statistics, for refurbished trucks returned to user units, are also gathered from the asset management software database, Mincom Ellipse, in use by the Botswana Defence Force Mechanical...

The effectiveness of environment assessment tools to guide refurbishment of Australian residential aged care facilities: A systematic review.

Science.gov (United States)

Neylon, Samantha; Bulsara, Caroline; Hill, Anne-Marie

2017-06-01

To determine applicability of environment assessment tools in guiding minor refurbishments of Australian residential aged care facilities. Studies conducted in residential aged care settings using assessment tools which address the physical environment were eligible for inclusion in a systematic review. Given these studies are limited, tools which have not yet been utilised in research settings were also included. Tools were analysed using a critical appraisal screen. Forty-three publications met the inclusion criteria. Ten environment assessment tools were identified, of which four addressed all seven minor refurbishment domains of lighting, colour and contrast, sound, flooring, furniture, signage and way finding. Only one had undergone reliability and validity testing. There are four tools which may be suitable to use for minor refurbishment of Australian residential aged care facilities. Data on their reliability, validity and quality are limited. © 2017 AJA Inc.

Inertial confinement fusion target component fabrication and technology development support: Annual report, October 1, 1995--September 30, 1996

International Nuclear Information System (INIS)

Hoppe, M.

1997-02-01

On December 30, 1990, the U.S. Department of Energy entered into a contract with General Atomics (GA) to be the Inertial Confinement Fusion (ICF) Target Component Fabrication and Technology Development Support contractor. In September 1995 this contract ended and a second contract was issued for us to continue this ICF target support work. This report documents the technical activities of the period October 1, 1995 through September 30, 1996. During this period, GA and our partners WJ Schafer Associates (WJSA) and Soane Technologies, Inc. (STI) were assigned 14 formal tasks in support of the Inertial Confinement Fusion program and its five laboratories. A portion of the effort on these tasks included providing direct open-quotes Onsite Supportclose quotes at Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), and Sandia National Laboratory Albuquerque (SNLA). We fabricated and delivered over 800 gold-plated hohlraum mandrels to LLNL, LANL and SNLA. We produced nearly 1,200 glass and plastic target capsules for LLNL, LANL, SNLA and University of Rochester/Laboratory for Laser Energetics (UR/LLE). We also delivered over 100 flat foil targets for Naval Research Lab (NRL) and SNLA in FY96. This report describes these target fabrication activities and the target fabrication and characterization development activities that made the deliveries possible. The ICF program is anticipating experiments at the OMEGA laser and the National Ignition Facility (NIF) which will require capsules containing cryogenic layered D 2 or deuterium-tritium (DT) fuel. We are part of the National Cryogenic Target Program to create and demonstrate viable ways to generate and characterize cryogenic layers. Substantial progress has been made on ways to both create and characterize viable layers. During FY96, significant progress was made in the design of the OMEGA Cryogenic Target System that will field cryogenic targets on OMEGA

Refurbishment of the regulating and control equipment, Task 3.08/04-05

International Nuclear Information System (INIS)

Nikolic, M.; Popovic, B.

1963-01-01

In addition to the planned refurbishment and maintenance of the RA reactor control and regulating systems, this report describes the maintenance of the reactor protection and safety systems. According to the instructions included in this report the components of these systems were tested to verify their reliability

Investigation on shortening fabrication process of instrumented irradiation capsule of JMTR

International Nuclear Information System (INIS)

Nagata, Hiroshi; Inoue, Shuichi; Yamaura, Takayuki; Tsuchiya, Kunihiko; Nagao, Yoshiharu

2013-06-01

Refurbishment of The Japan Materials Testing Reactor (JMTR) was completed in FY2010. For damage caused by the 2011 off the Pacific coast of Tohoku Earthquake, the repair of facilities was completed in October 2012. Currently, the JMTR is in preparation for restart. Irradiation tests for LWRs safety research, science and technologies and production of RI for medical diagnosis medicine, etc. are expected after the JMTR restart. On the other hand, aiming at the attractive irradiation testing reactor, the usability improvement has been discussed. As a part of the usability improvement, shortening of turnaround time to get irradiation results from an application for irradiation use was discussed focusing on the fabrication process of irradiation capsules, where the fabrication process was analyzed and reviewed by referring a trial fabrication of the mockup capsule. As a result, it was found that the turnaround time can be shortened 2 months from fabrication period of 6 months with communize of irradiation capsule parts, application of ready-made instrumentation including the sheath heater, reconsideration of inspection process, etc. (author)

Fabrication and testing of gas filled targets for large scale plasma experiments on Nova

International Nuclear Information System (INIS)

Stone, G.F.; Spragge, M.; Wallace, R.J.; Rivers, C.J.

1995-01-01

An experimental campaign on the Nova laser was started in July 1993 to study one st of target conditions for the point design of the National Ignition Facility (NIF). The targets were specified to investigate the current NIF target conditions--a plasma of ∼3 keV electron temperature and an electron density of ∼1.0 E + 21 cm -3 . A gas cell target design was chosen to confine as gas of ∼0.01 cm 3 in volume at ∼ 1 atmosphere. This paper will describe the major steps and processes necessary in the fabrication, testing and delivery of these targets for shots on the Nova Laser at LLNL

Advances in target design and fabrication for experiments on NIF

Directory of Open Access Journals (Sweden)

Obrey K.

2013-11-01

Full Text Available The ability to build target platforms for National Ignition Facility (NIF is a key feature in LANL's (Los Alamos National Laboratory Target Fabrication Program. We recently built and manufactured the first LANL targets to be fielded on NIF in March 2011. Experiments on NIF require precision component manufacturing and accurate knowledge of the materials used in the targets. The characterization of foams and aerogels, the Be ignition capsule, and machining unique components are of main material focus. One important characterization metric the physics' have determined is that the knowledge of density gradients in foams is important. We are making strides in not only locating these density gradients in aerogels and foams as a result of how they are manufactured and machined but also quantifying the density within the foam using 3D confocal micro x-ray fluorescence (μXRF imaging and 3D x-ray computed tomography (CT imaging. In addition, collaborative efforts between General Atomics (GA and LANL in the characterization of the NIF Ignition beryllium capsule have shown that the copper in the capsule migrates radially from the capsule center.

Systems engineering aspects to installation of the phased multi-year LANSCE-refurbishment project

International Nuclear Information System (INIS)

Pieck, Martin; Erickson, John E.; Gulley, Mark S.; Jones, Kevin W.; Rybarcyk, Larry J.

2009-01-01

The LANSCE Refurbishment Project (LANSCE-R) is a phased, multiyear project. The project is scheduled to start refurbishment in the 2nd quarter of fiscal year 2011. Closeout will occur during the 4th quarter of FY2016. During the LANSCE-R project, installation of project components must be scheduled during six annual 6-month maintenance-outages and not conflict with annual LANSCE operational commitments to its user facilities. The project and operations schedules must be synchronized carefully. Therefore, the scheduled maintenance outages, functional testing (with beam off, by primarily project personnel) and commissioning (with beam on, by primarily Accelerator Operation Technology (AOT) personnel) must be managed to accommodate operation. Active and effective coordination and communication between the project and AOT personnel must be encouraged to identify, as early as possible, any operational issues. This paper will report on the systems engineering approach to the integration and control of engineering activities.

Research reactor modernization and refurbishment

International Nuclear Information System (INIS)

2009-08-01

Many recent, high profile research reactor unplanned shutdowns can be directly linked to different challenges which have evolved over time. The concept of ageing management is certainly nothing new to nuclear facilities, however, these events are highlighting the direct impact unplanned shutdowns at research reactors have on various stakeholders who depend on research reactor goods and services. Provided the demand for these goods and services remains strong, large capital projects are anticipated to continue in order to sustain future operation of many research reactors. It is within this context that the IAEA organized a Technical Workshop to launch a broader Agency activity on research reactor modernization and refurbishment (M and R). The workshop was hosted by the operating organization of the HOR Research Reactor in Delft, the Netherlands, in October 2006. Forty participants from twenty-three countries participated in the meeting: with representation from Africa, Asia Pacific, Eastern Europe, North America, South America and Western Europe. The specific objectives of this workshop were to present facility reports on completed, existing and planned M and R projects, including the project objectives, scope and main characteristics; and to specifically report on: - the project impact (planned or actual) on the primary and key supporting motivation for the M and R project; - the project impact (planned or actual) on the design basis, safety, and/or regulatory-related reports; - the project impact (planned or actual) on facility utilization; - significant lessons learned during or following the completion of M and R work. Contributions from this workshop were reviewed by experts during a consultancy meeting held in Vienna in December 2007. The experts selected final contributions for inclusion in this report. Requests were also distributed to some authors for additional detail as well as new authors for known projects not submitted during the initial 2006 workshop

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

International Nuclear Information System (INIS)

Nikolic, M.; Bratic, A.

1963-01-01

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

Design and fabrication of foam-insulated cryogenic target for wet-wall laser fusion reactor

International Nuclear Information System (INIS)

Norimatsu, T.; Takeda, T.; Nagai, K.; Mima, K.; Yamanaka, T.

2003-01-01

A foam insulated cryogenic target was proposed for use in a future laser fusion reactor with a wet wall. This scheme can protect the solid DT layer from melting due to surface heating by adsorption of metal vapor without significant reduction in the target gain. Design spaces for the injection velocity and the acceptable vapor pressure in the reactor are discussed. Basic technology to fabricate such structure was demonstrated by emulsion process. Concept of a cryogenic fast-ignition target with a gold guiding cone was proposed together with direct injection filling of liquid DT. (author)

Inertial confinement fusion target component fabrication and technology development support. Annual report, October 1, 1996 - September 30, 1997

International Nuclear Information System (INIS)

Gibson, J.

1998-03-01

This report documents the technical activities of the period October 1, 1996 through September 30, 1997. During this period, GA and their partner Schafer Corporation were assigned 13 formal tasks in support of the ICF program and its five laboratories. A portion of the effort on these tasks included providing direct open-quotes Onsite Supportclose quotes at Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), and Sandia National Laboratory Albuquerque (SNLA). Over 700 gold-plated hohlraum mandrels were fabricated and delivered to LLNL, LANL and SNLA. More than 1600 glass and plastic target capsules were produced for LLNL, LANL, SNLA and University of Rochester/Laboratory for Laser Energetics (UR/LLE). Nearly 2000 various target foils and films were delivered for Naval Research Lab (NRL) and UR/LLE in FY97. This report describes these target fabrication activities and the target fabrication and characterization development activities that made the deliveries possible. The ICF program is anticipating experiments at the OMEGA laser and the National Ignition Facility (NIF) which will require targets containing cryogenic layered D 2 or deuterium-tritium (DT) fuel. This project is part of the National Cryogenic Target Program and support experiments at LLNL and LANL to generate and characterize cryogenic layers for these targets. During FY97, significant progress was made in the design and component testing of the OMEGA Cryogenic Target System that will field cryogenic targets on OMEGA. This included major design changes, reduction in equipment, and process simplifications. This report summarizes and documents the technical progress made on these tasks

Inertial confinement fusion target component fabrication and technology development support. Annual report, October 1, 1996--September 30, 1997

Energy Technology Data Exchange (ETDEWEB)

Gibson, J. [ed.

1998-03-01

This report documents the technical activities of the period October 1, 1996 through September 30, 1997. During this period, GA and their partner Schafer Corporation were assigned 13 formal tasks in support of the ICF program and its five laboratories. A portion of the effort on these tasks included providing direct {open_quotes}Onsite Support{close_quotes} at Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), and Sandia National Laboratory Albuquerque (SNLA). Over 700 gold-plated hohlraum mandrels were fabricated and delivered to LLNL, LANL and SNLA. More than 1600 glass and plastic target capsules were produced for LLNL, LANL, SNLA and University of Rochester/Laboratory for Laser Energetics (UR/LLE). Nearly 2000 various target foils and films were delivered for Naval Research Lab (NRL) and UR/LLE in FY97. This report describes these target fabrication activities and the target fabrication and characterization development activities that made the deliveries possible. The ICF program is anticipating experiments at the OMEGA laser and the National Ignition Facility (NIF) which will require targets containing cryogenic layered D{sub 2} or deuterium-tritium (DT) fuel. This project is part of the National Cryogenic Target Program and support experiments at LLNL and LANL to generate and characterize cryogenic layers for these targets. During FY97, significant progress was made in the design and component testing of the OMEGA Cryogenic Target System that will field cryogenic targets on OMEGA. This included major design changes, reduction in equipment, and process simplifications. This report summarizes and documents the technical progress made on these tasks.

Corrosion inhibition measures in primary cooling water system during refurbishment of Cirus, re-commissioning and subsequent operation

International Nuclear Information System (INIS)

Rai, K.K.; Ramesh, N.; Sharma, R.C.

2008-01-01

Cirus is a 40 MWth, heavy water moderated, demineralized light water cooled, natural uranium fuelled research reactor. Reactor was commissioned in year 1960 and operated satisfactorily till 1990. After that availability factor started decreasing mainly due to equipment outage exhibiting signs of ageing. Based upon systematic ageing studies and assessment of condition of systems, structures and components, a refurbishment plan including safety upgrades was drawn up. Reactor was shut down in October 1997 for execution of jobs. After completion of refurbishment jobs reactor was started back in October 2002 and power operation was achieved in 2003. Primary cooling water (PCW) system consists of re-circulating pumps, heat exchangers, expansion tank, piping, valves, emergency storage reservoir (Ball Tank) and other components. Normally the fission heat from fuel is removed by re-circulating coolant in closed loop and transferred to seawater via heat exchangers. In case of outage of pumps, shut down cooling is provided by flow of water from Ball Tank under gravity to the underground dump tanks. The dissolved oxygen is maintained below 2 ppm and pH is maintained neutral to minimize corrosion of fuel cladding (Aluminum). This paper highlights the experience gained during segmentation of primary cooling water pipelines for pressure testing, measures taken to corrosion inhibition of primary cooling water lines to permit execution of refurbishment jobs, inspections and actions taken to repair/replace the corroded PCW pipe line segments, observations regarding corrosion related failures, re-commissioning of the system after refurbishment, assessment for safe reactor operation and experience during power operation. (author)

Refurbishment and upgrading of Iron Gates I Hydroelectric and Navigation System on the Danube River

International Nuclear Information System (INIS)

Scvortov, F.; Vasiliu, A.; Rosca, N.

1996-01-01

This work shows the problems of the refurbishing the hydroelectric units of the Iron Gates 1 Hydroelectric and Navigation System, operating since 1970. Their long and intensive utilization leads to the necessity of their refurbishment. One is demonstrated by detailed studies that it is sensible and efficient to perform both rehabilitation of the existent hydroelectric units and their power increasing from 175 MW to 190 MW, and prior to all these, as a first step, to install an additional hydroelectric unit (G7) for each system with a capacity of 190 MW. Complex technical and energetic-economical problems appear in realizing this objective due to the necessity of analysing a great volume of data in view of taking a correct decision. (author). 7 figs

Refurbishment of Point Lepreau Generating Station

International Nuclear Information System (INIS)

Thompson, P.D.; Jaitly, R.; Ichiyen, N.; Petrilli, M.A.

2004-01-01

NB Power is planning to conduct an 18-month maintenance outage of the Point Lepreau Generating Station (PLGS) beginning in April 2008. The major activity would be the replacement of all 380 Fuel Channel and Calandria Tube Assemblies and the connecting feeder pipes. This activity is referred to as Retube. NB Power would also take advantage of this outage to conduct a number of repairs, replacements, inspections and upgrades (such as rewinding or replacing the generator, replacement of shutdown system trip computers, replacement of certain valves and expansion joints, inspection of systems not normally accessible, etc). These collective activities are referred to as Refurbishment. This would allow the station to operate for an additional 25 to 30 years. The scope of the project was determined from the outcome of a two-year study involving a detailed condition assessment of the station that examined issues relating to ageing and obsolescence. The majority of the plant components were found to be capable of supporting extended operation without needing replacement or changes. In addition to the condition assessment, a detailed review of Safety and Licensing issues associated with extended operation was performed. This included a review of known regulatory and safety issues, comparison of the station against current codes and standards, and comparison of the station against safety related modifications made to more recent CANDU 6 units. Benefit cost analyses (BCA) were performed to assist the utility in determining which changes were appropriate to include in the project scope. As a Probabilistic Safety Assessment (PSA) for PLGS did not exist at the time, a risk baseline for the station had to be determined for use in the BCA. Extensive dialogue with the Canadian Nuclear Safety Commission staff was also undertaken during this phase. A comprehensive Licensing Framework was produced upon which the CNSC provided feedback to NB Power. This feedback was important in terms of

Analytical cell decontamination and shielding window refurbishment. Final report, March 1984-March 1985

International Nuclear Information System (INIS)

Smokowski, R.T.

1985-01-01

This is a report on the decontamination and refurbishment of five inactive contaminated analytical cells and six zinc bromide filled shielding windows. The analytical cells became contaminated during the nuclear fuel reprocessing carried out by Nuclear Fuel Services from 1966 to 1972. The decontamination and decommissioning (D and D) work was performed in these cells to make them useful as laboratories in support of the West Valley Demonstration Project. To accomplish this objective, unnecessary equipment was removed from these cells. Necessary equipment and the interior of each cell were decontaminated and repaired. The shielding windows, essentially tanks holding zinc bromide, were drained and disassembled. The deteriorated, opaque zinc bromide was refined to optical clarity and returned to the tanks. All wastes generated in this operation were characterized and disposed of properly. All the decontamination and refurbishment was accomplished within 13 months. The Analytical Hot Cell has been turned over to Analytical Chemistry for the performance high-level waste (HLW) characterization analysis

Exposure management in a hot-cell decontamination and refurbishment campaign

International Nuclear Information System (INIS)

Courtney, J.C.; Ferguson, K.R.; Chesnovar, D.L.; Huebner, M.F.

1984-01-01

We developed a minicomputer-based system to provide rapid access to personnel dosimetry data during a campaign to decontaminate and refurbish a hot-cell at the Hot Fuel Examination Facility (HFEF) Complex. This system allows project management to estimate doses for future tasks, assess the effectiveness of decontamination and personnel protection techniques, and balance exposures among members of various skill groups. As the campaign progresses, projected total exposures can be minimized by tradeoffs between estimated doses during decontamination and estimated dose savings during the refurbishment phase. The effectiveness of various dose-reduction procedures can be compared on the basis of data from a few cell entries before more extensive routine operations are scheduled. Because the radiation fields vary significantly with location in the cell, we find that measurements of whole-body, skin, and extremity doses are more valuable than dose-rate information. Penetrating and skin radiation doses to personnel can be compared to administrative guidelines. This helps us to select the most effective combination of protective clothing. For example, leaded gauntlets reduce the dose rate to the workers' hands, but their use can increase the time required for some in-cell tasks. Hence, use of gauntlets can lead to higher whole-body and skin doses. The program is written for the HFEF Complex Harris/6 minimainframe computer with a disk-monitor operating system

Refurbishment and modification of existing protective shipping packages (for 30-inch UF{sub 6} cylinders) per USDOT specification No. USA-DOT-21PF-1A

Energy Technology Data Exchange (ETDEWEB)

Housholder, W.R. [Nuclear Containers, Incorporated, Elizabethton, TN (United States)

1991-12-31

This paper addresses the refurbishment procedures for existing shipping containers for 30-inch diameter UF{sub 6} cylinders in accordance with DOT Specification 21PF-1 and the criteria used to determine rejection when such packages are unsuitable for refurbishment.

Fatigue load considerations and use of high efficiency materials in the nuclear refurbishment projects: a structural engineering perspective

Energy Technology Data Exchange (ETDEWEB)

Mohee, F. M., E-mail: fmm_p@yahoo.com [Univ. of Waterloo, ON (Canada)

2014-07-01

For the Darlington refurbishment project in Canada, fatigue load consideration is a very crucial component in the analysis and design of different structures in the nuclear facilities. New and innovative structural materials having much higher ultimate tensile strength and modulus of elasticity, that are free from corrosion, should be considered along with fatigue load during the analysis and design of the nuclear refurbishment projects. The structural analysis should include beam, column and slabs, vibrating, rotating and crane supporting structures, robotic structures, pipe supports, Serapid chain and associated automated gate structures, flask supporting structures, processing unit and lidding unit support structures. (author)

Fuel management during Cirus refurbishing and re-commissioning

International Nuclear Information System (INIS)

Rai, K.K.; Srivastava, Alok; Ramesh, N.; Sharma, R.C.

2006-01-01

Cirus is a Heavy water moderated and Demineralised water cooled 40 MW(th) research reactor. Graphite is used as reflector. Natural uranium in metallic form and clad in aluminium is used as fuel. After over three decades of operation, signs of ageing started surfacing up. Refurbishment plan was drawn up based upon ageing studies and performance review. Core unloading was the foremost requirement for jobs like assessment of integrity of primary coolant underground pipelines. Refuelling is carried out during reactor shut down with primary coolant pumps in operation. During the fuel unloading with the gradual removal of assemblies, reduction in the gross flow of primary coolant was also envisaged. The scheme for core unloading was formulated with emphasis on optimization of fuel utilization, cooling to the fuel assemblies during transit and overall safety of equipment and personnel. After completion of refurbishing jobs, it was decided to install dummy assemblies in pile to facilitate commissioning of primary coolant system. A lot of difficulty was faced due to release of iron oxide flakes from the surface of primary coolant pipelines. The inlet feeders, valves and dummy assemblies had to be periodically flushed to get rid of iron oxide flakes deposited during the period. Various efforts made to get rid of iron oxide flakes included increasing the velocity by bypassing the core, installation of hollow dummy assemblies and installation of strainer at core inlet. The decision of fuel loading was made based upon the experience feedback with dummy assemblies and assessment of the pattern of release of iron oxide flakes. The dummy assemblies were replaced with uranium fuel assemblies. Fuelling work was carried out with Reactor hall crane with additional precautions. This paper describes the experience with handling of irradiated fuel assemblies to facilitate core unloading, experience with dummy assemblies and loading of fuel into the core and subsequent performance

Investigation on non-glass laser fusion targets: their fabrication, characterization, and transport. Charged Particle Research Laboratory report No. 2-81, progress report, June 1, 1980-January 31, 1981

International Nuclear Information System (INIS)

Kim, K.

1981-01-01

A summary is presented of the research progress made under LLNL Subcontract 8320003 for the period of June 1, 1980 through January 31, 1981. The main theme of the research has continued to be the development of techniques for fabricating, characterizing, and transporting laser fusion targets on a continuous basis. The target fabrication techniques are intended mainly for non-glass spherical shell targets, both cryogenic and non-cryogenic. Specifically, progress has been made in each of the following categories. (1) Investigation of liquid hydrogen behavior inside a spherical laser fusion target. (2) Development of automated target characterization scheme. (3) Study of cryogenic target fabrication scheme utilizing cold-gas-levitation and electric field positioning. (4) Development of a cryogenic target fabrication system based on target free-fall method. (5) Generation of hydrogen powder using electro-hydrodynamic spraying. (6) Study of target-charging techniques for application to contactless cryogenic target fabrication. (7) Development of hollow metal sphere production technique. A brief summary of the research progress made in each category is presented

Industry partnership: adding value to nuclear refurbishment and maintenance

International Nuclear Information System (INIS)

Gibbins, T.; Bains, N.; Morikawa, D.

2008-01-01

The Point Lepreau Generating Station was the first CANDU 6 unit to be licensed for operation, beginning commercial operation in 1983. It is now become the first CANDU 6 to undergo full refurbishment. As part of the overall project, all 380 fuel channels and associated feeders will be removed and replaced. In order to undertake this project, it was necessary for AECL to design and develop over fifty 'first-of-a-kind tools' for fuel channel and calandria tube replacement. This paper outlines the complexity of the retube tooling project and the industry partnership strategy for the engineered tooling systems development. (author)

The probability safety assessment impact on the BR2 refurbishment

International Nuclear Information System (INIS)

Pouleur, Yvan

1995-01-01

The probabilistic safety assessment (PSA) study has proven its worth by establishing a sensitive safety screening of the reactor. It has focused engineering forces to technically improve safety systems and to measure the influence of functional modifications. In the future, the project will be developed in a living way, to reinforce the present structure along with continuous safety monitoring of the reactor and to develop engineers and operators safety skills. This paper presents the PSA impact on the BR2 (Belgian Reactor Two) refurbishment. (author)

Project Experiences in Research Reactor Ageing Management, Modernization and Refurbishment. Report of a Technical Meeting on Research Reactor Ageing Management, Modernization and Refurbishment

International Nuclear Information System (INIS)

2014-08-01

Research reactors have played an important role in several scientific fields for around 60 years: in the development of nuclear science and technology; in the valuable generation of radioisotopes for various applications; and in the development of human resources and skills. Moreover, research reactors have been effectively utilized to support sustainable development in more than 60 countries worldwide. More than half of all operating research reactors are now over 40 years old, with many exceeding their originally conceived design life. The majority of operating research reactors face challenges due to the negative impacts of component and system ageing, which manifest in a number of forms. This situation was highlighted by a serious medical isotope supply crisis which peaked in mid-2010, when several major producing reactors underwent prolonged shutdowns due to extensive necessary overhauls of various systems. Several facilities have established a proactive systematic approach to managing ageing or mitigating its impact on safety and availability of isotopes. Others have tried to prevent or remedy the drawbacks of ageing on a case by case basis. Overall, a large body of knowledge related to ageing issues exists in many Member States. Collecting and sharing this information within the research reactor community can provide a solid foundation to develop a more systematic approach — that is, an ageing management programme to prevent negative consequences of ageing on the safety, and the operability and lifetime of operating, or even future, reactors. It may also help organizations to manage research reactors that have been in an extended shutdown state by ensuring that any required systems are operated and maintained in a safe manner prior to final decommissioning and disposal of fuel to safe storage facilities. Sharing experiences from projects undertaken to refurbish or replace equipment and systems, satisfy safety and regulatory requirements, improve

Project Experiences in Research Reactor Ageing Management, Modernization and Refurbishment. Report of a Technical Meeting on Research Reactor Ageing Management, Modernization and Refurbishment

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-08-15

Research reactors have played an important role in several scientific fields for around 60 years: in the development of nuclear science and technology; in the valuable generation of radioisotopes for various applications; and in the development of human resources and skills. Moreover, research reactors have been effectively utilized to support sustainable development in more than 60 countries worldwide. More than half of all operating research reactors are now over 40 years old, with many exceeding their originally conceived design life. The majority of operating research reactors face challenges due to the negative impacts of component and system ageing, which manifest in a number of forms. This situation was highlighted by a serious medical isotope supply crisis which peaked in mid-2010, when several major producing reactors underwent prolonged shutdowns due to extensive necessary overhauls of various systems. Several facilities have established a proactive systematic approach to managing ageing or mitigating its impact on safety and availability of isotopes. Others have tried to prevent or remedy the drawbacks of ageing on a case by case basis. Overall, a large body of knowledge related to ageing issues exists in many Member States. Collecting and sharing this information within the research reactor community can provide a solid foundation to develop a more systematic approach — that is, an ageing management programme to prevent negative consequences of ageing on the safety, and the operability and lifetime of operating, or even future, reactors. It may also help organizations to manage research reactors that have been in an extended shutdown state by ensuring that any required systems are operated and maintained in a safe manner prior to final decommissioning and disposal of fuel to safe storage facilities. Sharing experiences from projects undertaken to refurbish or replace equipment and systems, satisfy safety and regulatory requirements, improve

The Prevelence of SBS and Absenteeism among Children in Urban Refurbished Private Preshools

Directory of Open Access Journals (Sweden)

Salleh Naziah Muhamad

2016-01-01

Full Text Available The preschool education is compulsory to children in Malaysia. This regulation has encouraged more premises to be refurbished as a pre-school building. This paper examines the pupils’ absenteeism and the prevalence of Sick Building Symptoms (SBS initiated in congested private preschool with different ventilation strategies. The study analysed data from the attendance record of 10 classrooms and the questionnaire surveys administered to 151 parents about their children health symptoms once they were leaving the schools building. Questions on SBS used 5-point likert scale with symptoms concern on nose, eye, head, throat, skin, breath and tiredness. The descriptive and chi-square test applied to obtain the association of SBS and ventilation strategies in the classrooms. With quantitative and qualitative explanation, the unhealthy environment in refurbished pre-schools explained. Running nose, coughing and sore throat frequently reported in air-conditioning (AC classrooms. The higher absent rate found in AC classrooms. These symptoms show there were weaknesses in ventilation performance and environment in the selected preschools. Further analyses on objective measurements in future research are strongly recommended.

Austro-Hungarian Public Building Refurbishment and Energy Efficiency Measures - A Case Study on a Public Building in Sarajevo

Science.gov (United States)

Salihbegović, Amira; Čaušević, Amir; Rustempašić, Nerman; Avdić, Dženis; Smajlović, Esad

2017-10-01

Among other pieces of architectural historical heritage in Sarajevo, and Bosnia-Herzegovina in general, the Austro-Hungarian architecture has preserved its original architectural, artistic and engineering characteristics. Both residential and public representative urban blocks, streets and squares are of distinguishable ambience in the architectural and urban image of the city and are testifying about our architectural past. A number of buildings is valorised and protected by law in terms of their architectural, artistic and historical value. In addition, these buildings have a distinct functional, ambiental, historical, and even aesthetical value. To make them last longer, refurbishment of these buildings is challenging and presents potential and multiple benefits for the city, and beyond. Refurbishing built environment through functional reorganizing, redesign and energy efficiency measures applications could result in prolonged longevity, architectural identity preservation and interior comfort improvement. Besides, implemented measures for energy efficiency, through the refurbishment process, should optimize the needs for energy consumption in treated buildings. This paper defines options in comfort improvements and redesign, without implying risks to the building longevity, analyses interventions and energy efficiency measures which would enable potential energy saving assessment in the refurbishment process of masonry buildings. This paper also discusses the different techniques that can be adopted for conservation and preservation of historical masonry buildings from the Austro-Hungarian period dealing with energy efficiency. The works were preceded by historical research and on-site investigations. This paper describes a methodology to quantify their vulnerability. A scheme of structural retrofitting is suggested following the research conducted. Revitalization of the building consisted in the reconstruction of the old building structure, creating the inner

Steam generator life-management, reliability, maintenance and refurbishment

International Nuclear Information System (INIS)

Spekkens, P.

2012-01-01

SGC 2012 is a different kind of a conference - it has its own focus, initiatives and objectives and differs from its predecessors. It originated as the Steam Generator and Heat Exchanger Conference in 1990 - a time when premature degradation of steam generators with Alloy 600 tubes was rampant world-wide, and some CANDU steam generators had started to experience significant fouling and corrosion issues. The six previous steam generator conferences were held on a regular cycle, in a very similar format and with a similar theme. We are now in a different era in steam generators. The Alloy 600 tubing has been largely replaced by more robust materials, and the CANDU steam generators have been brought under much more intense and effective life cycle management. Performance of steam generators has improved greatly, and they are no longer considered at risk of limiting the life of the units. Indeed, most Incoloy 800 steam generators in CANDU units are considered to be capable of operating reliably through the 'second life' of the units and are not being replaced during refurbishments. Given this changing environment, the scope of this conference has been expanded from one to three areas: steam generators and heat exchangers as before, but also; controls, valves and pumps, and; reactor components and systems, Programs A, B and C, respectively. The conference is targeting to address the needs and interests of the operating utilities, and to 'focus on what needs attention'. As a means of 'focusing on what needs attention' an 'Issue-Identification and Definition' program was initiated last winter. The Issue-Identification Team operating with COG President Bob Morrison as its Executive Lead, worked to identify issues requiring attention in the three areas of interest. Of the many issues identified by the Team and elaborated on by the Program Developers of this conference, four were recommended for special attention: A. 'Operate Clean - Build Clean - Plant Wide': Despite their

Refurbishment of Cirus in-core components

International Nuclear Information System (INIS)

Bhatnagar, A.; Sahu, A.K.; Rathore, K.K.; Subudhi, D.; Kharpate, A.V.; Tikku, A.C.

2006-01-01

Circus is a 40- MWt vertical tank type research reactor with natural uranium as fuel, demineralised light water as coolant, heavy water as moderator and graphite as reflector. The reactor was commissioned in the year 1960 and operated at an overage availability factor of over 70% till early nineties, when various systems, structures and components (SSCs) started showing signs of ageing. Detailed ageing studies were therefore carried out to assess the condition of various SSCs and refurbishing requirements were finalized towards extending the life of the reactor. In-core components, being non-replaceable generally, were critically examined to the extent possible. Detailed visual examination of a few reactor vessel (RV) tubes, made of aluminium, was carried out using micro video camera and in addition all the RV tubes were inspected using eddy current testing method. RV shell, also made of aluminium, was similarly visually inspected with micro video camera. To assess the effect of irradiation on the RV material, samples of similar tubes irradiated to comparable neutron fluence were tested. Towards assessment of fatigue life of RV expansion joint, made of aluminium, a finite element analysis using NISA computer code was performed. Theoretical assessment for stored Wigner energy in graphite reflector was carried out. Graphite block samples were also removed from the reactor and stored energy levels were measured to plan for any in-situ graphite annealing, if required. Visual inspection of approachable portions of steel and aluminium thermal shields was also carried out. These water-cooled thermal shields provided above and below the RV were hydro tested. The weld joint between coolant inlet pipe and top plate of upper aluminium shield showed minor leakage. A special metallic hollow plug was developed and remotely installed in the leaky pipe to isolate the leaky portion while maintaining the coolant flow in the pipe. Helium leak was found from flange joints located on

Development of a virtual training simulator for a challenging refurbishment task

International Nuclear Information System (INIS)

Mort, P.E.

1996-01-01

An overview is presented of the technology, developed by British Nuclear Fuels Limited (BNFL), to create a virtual training simulator for refurbishment tasks. It focuses on the Raffinate Project, a challenging plant modification take, performed remotely, during which component removal, welding and installation of new components are all undertaken. The Training Simulator developed required fast multiprocessor computing with system intercommunication. Operators responded well to the Training Simulator and further improvements to the system are underway. (UK)

Energy refurbishment of the Italian residential building stock: energy and cost analysis through the application of the building typology

International Nuclear Information System (INIS)

Ballarini, Ilaria; Corrado, Vincenzo; Madonna, Francesco; Paduos, Simona; Ravasio, Franco

2017-01-01

The European residential building stock is largely composed of buildings with poor energy performance, therefore basic retrofit actions could lead to significant energy savings. However, energy refurbishment measures should be identified in accurate way, taking into account the technical viability and aiming both to increase the building energy performance and to restrain the costs. The present article investigates the effects of different measures applied to the Italian residential building stock by using the building typology, which consists of 120 building types, representative of six construction ages, four building sizes and five climatic zones. A quasi-steady state model has been used to calculate the energy performance; the economic evaluation has been carried out as specified in the EU cost-optimal comparative methodology (Directive 2010/31/EU). The most effective measures and packages of measures, in terms of energy saving and global cost reduction, are identified and discussed. The results are addressed to important purposes for energy policy, as for instance: (a) to provide political authorities with the most effective energy efficiency measures as to encourage retrofit processes through the allocation of financial incentives, (b) to offer a knowledge-base for developing energy refurbishment scenarios of residential building stocks and forecasting future energy resource demand. - Highlights: • Investigation of energy savings and cost effectiveness of the Italian housing stock refurbishments. • Application of the building typology approach of the IEE-TABULA project. • Knowledge-base for bottom-up models of the building stock energy performance. • Supporting the political authorities to promote effective refurbishment measures.

Sustainable refurbishment of exterior walls and building facades. Final report, Part A - Methods and recommendations

Energy Technology Data Exchange (ETDEWEB)

Hakkinen, T. (ed.)

2012-11-01

This report is the final report of Sustainable refurbishment of building facades and exterior walls (SUSREF). SUSREF project was a collaborative (small/medium size) research project within the 7th Framework Programme of the Commission and it was financed under the theme Environment (including climate change) (Grant agreement no. 226858). The project started in October 1st 2009 and ended in April 30th 2012. The project included 11 partners from five countries. SUSREF developed sustainable concepts and technologies for the refurbishment of building facades and external walls. This report together with SUSREF Final report Part B and SUSREF Final Report Part C introduce the main results of the project. Part A focuses on methodological issues. The descriptions of the concepts and the assessment results of the developed concepts are presented in SUSREF Final report part B (generic concepts) and SUSREF Final report Part C (SME concepts). (orig.)

Estimation of radiation exposure for hot cell workers during DUPIC fuel fabrication process in IMEF M6 cell

Energy Technology Data Exchange (ETDEWEB)

Jeon, Yong Bum; Baek, Sang Yeol; Park, Dae Kyu

1997-06-01

DUPIC(Direct Use of spent PWR fuel In CANDU) fuel cycle to utilize the PWR spent fuel in fabricating CANDU fuel, which is expected to reduce not only the total amount of high level radwastes but the energy sources is underway. IMEF M6 cell to be used as DUPIC fuel fabrication facility is refurbished and retrofitted. Radiation exposure for the hot cell worker by dispersion of the radioactive materials during the DUPIC process were estimated on the basis of the hot cell design information. According to the estimation results, DUPIC fuel fabrication process could be run without any severe impacts to the hot cell workers when the ventilation system to maintain the sufficient pressure difference between hotcell and working area and radiation monitoring system is supports the hot cell operation properly. (author). 4 tabs., 6 figs.

Fabrication of 94Zr thin target for recoil distance doppler shift method of lifetime measurement

International Nuclear Information System (INIS)

Gupta, C.K.; Rohilla, Aman; Abhilash, S.R.; Kabiraj, D.; Singh, R.P.; Mehta, D.; Chamoli, S.K.

2014-01-01

A thin isotopic 94 Zr target of thickness 520μg/cm 2 has been prepared for recoil distance Doppler shift method (RDM) lifetime measurement by using an electron beam deposition method on tantalum backing of 3.5 mg/cm 2 thickness at Inter University Accelerator Center (IUAC), New Delhi. To meet the special requirement of smoothness of surface for RDM lifetime measurement and also to protect the outer layer of 94 Zr from peeling off, a very thin layer of gold has been evaporated on a 94 Zr target on a specially designed substrate holder. In all, 143 mg of 99.6% enriched 94 Zr target material was utilized for the fabrication of 94 Zr targets. The target has been successfully used in a recent RDM lifetime measurement experiment at IUAC

Fabrication of 94Zr thin target for recoil distance doppler shift method of lifetime measurement

Science.gov (United States)

Gupta, C. K.; Rohilla, Aman; Abhilash, S. R.; Kabiraj, D.; Singh, R. P.; Mehta, D.; Chamoli, S. K.

2014-11-01

A thin isotopic 94Zr target of thickness 520 μg /cm2 has been prepared for recoil distance Doppler shift method (RDM) lifetime measurement by using an electron beam deposition method on tantalum backing of 3.5 mg/cm2 thickness at Inter University Accelerator Center (IUAC), New Delhi. To meet the special requirement of smoothness of surface for RDM lifetime measurement and also to protect the outer layer of 94Zr from peeling off, a very thin layer of gold has been evaporated on a 94Zr target on a specially designed substrate holder. In all, 143 mg of 99.6% enriched 94Zr target material was utilized for the fabrication of 94Zr targets. The target has been successfully used in a recent RDM lifetime measurement experiment at IUAC.

Cost Modeling for Fabrication of Direct Drive Inertial Fusion Energy Targets

International Nuclear Information System (INIS)

Rickman, William Samuel; Goodin, Daniel T.

2003-01-01

Chemical engineering analyses are underway for a commercial-scale [1000-MW(electric)] divinyl benzene foam-based Inertial Fusion Energy (IFE) Target Fabrication Facility (TFF). This facility is designed to supply 500,000, 4-mm-outer diameter targets per day - coated via interfacial polycondensation, dried with supercritical CO 2 , sputter coated with Au and/or Pd, and filled with deuterium-tritium layered at cryogenic temperatures and injected into the fusion chamber. Such targets would be used in a direct-drive IFE power plant.The work uses manufacturing processes being developed in the laboratory, chemical engineering scaleup principles, and established cost-estimating methods. The plant conceptual design includes a process flow diagram, mass and energy balances, equipment sizing and sketches, storage tanks, and facility views.The cost estimate includes both capital and operating costs. Initial results for a TFF dedicated to one 1000-MW(electric) plant indicate that the costs per target are well within the commercially viable range. Larger TFF plants [3000 MW(electric)] are projected to lead to significantly reduced costs per injected target. Additional cost reductions are possible by producing dried, sputter-coated empty shells at a central facility that services multiple power plants.The results indicate that the installed capital cost is about $100 million and the annual operating costs will be about $20 million, for a cost per target of about $0.17 each. These design and cost projections assume that a significant process development and scaleup program is successfully completed for all of the basic unit operations included in the facility

A liquid hydrogen target for the calibration of the MEG and MEG II liquid xenon calorimeter

Energy Technology Data Exchange (ETDEWEB)

Signorelli, G., E-mail: giovanni.signorelli@pi.infn.it [INFN Sezione di Pisa, Largo B. Pontecorvo 3, 56127 Pisa (Italy); Baldini, A.M. [INFN Sezione di Pisa, Largo B. Pontecorvo 3, 56127 Pisa (Italy); Bemporad, C.; Cei, F.; Nicolò, D. [INFN Sezione di Pisa, Largo B. Pontecorvo 3, 56127 Pisa (Italy); Università di Pisa, Dipartimento di Fisica, Largo B. Pontecorvo 3, 56127 Pisa (Italy); Galli, L.; Gallucci, G.; Grassi, M. [INFN Sezione di Pisa, Largo B. Pontecorvo 3, 56127 Pisa (Italy); Papa, A. [Paul Scherrer Institut, 5232 Villigen (Switzerland); Sergiampietri, F. [INFN Sezione di Pisa, Largo B. Pontecorvo 3, 56127 Pisa (Italy); Venturini, M. [INFN Sezione di Pisa, Largo B. Pontecorvo 3, 56127 Pisa (Italy); Scuola Normale Superiore, Piazza dei Cavalieri 7, 56126 Pisa (Italy)

2016-07-11

We designed, built and operated a liquid hydrogen target for the calibration of the liquid xenon calorimeter of the MEG experiment. The target was used throughout the entire data taking period, from 2008 to 2013 and it is being refurbished and partly re-designed to be integrated and used in the MEG-II experiment.

Refurbishment and Automation of the Thermal/Vacuum Facilities at the Goddard Space Flight Center

Science.gov (United States)

Donohue, John T.; Johnson, Chris; Ogden, Rick; Sushon, Janet

1998-01-01

The thermal/vacuum facilities located at the Goddard Space Flight Center (GSFC) have supported both manned and unmanned space flight since the 1960s. Of the 11 facilities, currently 10 of the systems are scheduled for refurbishment and/or replacement as part of a 5-year implementation. Expected return on investment includes the reduction in test schedules, improvements in the safety of facility operations, reduction in the complexity of a test and the reduction in personnel support required for a test. Additionally, GSFC will become a global resource renowned for expertise in thermal engineering, mechanical engineering and for the automation of thermal/vacuum facilities and thermal/vacuum tests. Automation of the thermal/vacuum facilities includes the utilization of Programmable Logic Controllers (PLCs) and the use of Supervisory Control and Data Acquisition (SCADA) systems. These components allow the computer control and automation of mechanical components such as valves and pumps. In some cases, the chamber and chamber shroud require complete replacement while others require only mechanical component retrofit or replacement. The project of refurbishment and automation began in 1996 and has resulted in the computer control of one Facility (Facility #225) and the integration of electronically controlled devices and PLCs within several other facilities. Facility 225 has been successfully controlled by PLC and SCADA for over one year. Insignificant anomalies have occurred and were resolved with minimal impact to testing and operations. The amount of work remaining to be performed will occur over the next four to five years. Fiscal year 1998 includes the complete refurbishment of one facility, computer control of the thermal systems in two facilities, implementation of SCADA and PLC systems to support multiple facilities and the implementation of a Database server to allow efficient test management and data analysis.

A Guide to Energy Efficient Refurbishment. Maintenance and Renewal in Educational Buildings. Building Bulletin 73.

Science.gov (United States)

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

With little or relatively modest investment, schools being refurbished or undergoing maintenance can make disproportionately large gains in energy efficiency that can also result in large financial savings. This document offers guidance on the selection of appropriate measures that can improve a facility's energy efficiency, depending on the type…

Refurbishment of PSI-Hotlaboratory to comply with requested safety standards after 40 years of operation

International Nuclear Information System (INIS)

Bart, G.; Hofer, R.; Wiezel, L.

2001-01-01

The PSI Hotlaboratory has started its operation in 1962. From the very beginning the hotcell wing served for handling and gross PIE analysis of reactor core internals and highly active material from accelerator target stations. In the radiochemistry wing micro structural and chemical analyses of small, highly active samples were subsequently performed with equipment installed in individual lead shielded cells. The radiochemistry wing also served for radiopharmaceutical nuclide dispatching and actinide ceramics preparation. Several constructions and building enlargements have been added since 1962 and similarly, the safety infrastructure was improved case wise. In the course of reevaluating the principal safety documentation for the Hotlaboratory, during 1994-95 it was realized that the building concept with its class A radioactive areas did not comply any more with modern safely standards, in particular with fire protection regulations and operator safety. In accident scenario analyses it was further demonstrated that radio nuclide release to the environment could cause intolerable health risks to the surrounding population. It was therefore decided to principally refurbish the building infrastructure particularly with respect to fire protection, media, and laboratory instrumentation and control. The chosen concept consists in adding a so called media installation corridor on top and along the radiochemistry wing from which the individual labs, on two floors are reached by vertical media access channels. Since the reconstruction outage time had to be minimized and there was not enough storage capacity to remove the whole Hotlaboratory equipment at once, a stepwise reconstruction was planned with separation of specified blocks of labs which are freed from samples (but still contain specially encapsulated, internally contaminated glove boxes and lead shielded cells) and which are accessed from the building outside, while the rest of the labs are still (or again) in

Refurbishment of the rotating rack of the OSU TRIGA MKII reactor

International Nuclear Information System (INIS)

Higginbotham, J.F.; Dodd, B.; Pratt, D.S.; Anderson, T.V.

1992-01-01

Many TRIGA reactors have experienced operational difficulties with the rotating racks used for sample irradiation. Generally the rack gradually becomes more difficult to rotate until it finally seizes. The recommended action at that point is replacement of the entire facility at a significant cost. The purpose of this paper is to describe the symptoms leading to rack failure and to present the results of a refurbishment procedure that does not involve the use of solvents which create mixed chemical and radioactive hazardous waste. The primary reason for rack failure is the buildup of sludge produced through irradiation of lubrication oil. The refurbishment procedure involves using a commercially available degreasing solution which can be pumped into and out of the rack with the objective of removing this sludge. The solution used is sold under the trade name 'Simple Green'. No radioactive material was detected on smear or air samples taken of the work area during the reifurbishment activities and the rack rotates freely in both direction even after eighteen months of operation. The only disadvantage to performing this procedure has been the need to maintain a very aggressive contamination control program when unloading samples from the rack. A very fine particulate material attaches to the outside of tubes used to encapsulate samples. This material can produce contamination levels of 10,000 dpm/100 cm 2 in the worst cases but will typically produce local hot spots on the order of 1000 dpm. (author)

Application of the ALARP principle to a major refurbishment project at Sellafield

International Nuclear Information System (INIS)

Hendrickson, W.R.; Coates, R.

1989-01-01

A formalised structured approach to the ALARP principle has been developed and is being applied to occupational radiation exposure on a major refurbishment project at Sellafield. The processes consider the conceptual and subsequent detailed design stages, planning and operational control and incorporates a dose feedback and review system. The approach has led to significant dose savings so far on the project, with recorded doses being significantly less than the doses estimated at the preliminary assessment stage. (author)

Shakedown Tests for Refurbished and Upgraded Frames and Initiation of Alloy 709 Creep Rupture Tests

Energy Technology Data Exchange (ETDEWEB)

Wang, Hong [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Moser, Jeremy L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Hawkins, Charles S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Lara-Curzio, Edgar [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-09-01

This report describes the shakedown tests conducted on the upgraded frames, and initiation of creep rupture tests on refurbished frames. SS316H, a reference material for Alloy 709, was used in shakedown tests, and the tests were conducted at 816 degree C under three stress levels to accumulate 1% creep strain. 1/4” gage diameter specimen design was used. The creep rupture tests on Alloy 709 were initiated at 600 degree C under 330 MPa to target 1,500 h rupture time. 12 specimens with 3/8” gage diameter were prepared from the materials with 6 heat treatment conditions, 2 from each. The required mechanical load under 330MPa was calculated to be 5,286 lb for the 3/8” gage diameter specimen. Among the ART frames, 7 frames are equipped with 10,000 lb load cell including #5 to 8 and #88 to 90, and can be used. 7 tests were thus started in this stage of project, and remaining 5 will be continued whenever any of the 7 tests is completed.

French experience on renewing I and C systems in NPPs. Feedback from assessing nuclear instrumentation system (RPN) refurbishment at French CP0-series plants

International Nuclear Information System (INIS)

Elsensohn, O.; Fradet, F.; Peron, J.C.; Soubies, B.

2003-01-01

In 1996, the utility operating France's nuclear power plants launched feasibility studies for the refurbishment of the nuclear instrumentation system (RPN classed category A) installed in its CPO-series (900 MWe) units. The system was ultimately upgraded with digital I and C system, using a SPINLINE 3 platform. This article describes feedback from an evaluation conducted on the refurbishment by the Institute of Radiological Protection and Nuclear Safety (IRSN), technical support arm of the Directorate General for Nuclear Safety and Radiological Protection (DGSNR). The study begins with a historical overview of the refurbishing operation, then discusses the IRSN assessment method and the lessons learned from this first major revamp of an I and C system in the French nuclear reactor series. Based on its previous experience in evaluating I and C systems for P4/P'4 (1300 MWe) and N4 (1450 MWe) plants and to account for the first-ever aspect of such an upgrade, IRSN partitioned its assessment into four phases. This approach enabled taking into account the impact of RPN refurbishment at every level - system, hardware and qualification, software, operation, onsite requalification, health physics, fire protection and human factors. All six units in the CPO series have now been equipped with the new digital RPN. (authors)

Refurbishment of industrial buildings

International Nuclear Information System (INIS)

Gustafsson, Stig-Inge

2006-01-01

When a building is subject for refurbishment, there is a golden opportunity to change its behavior as an energy system. This paper shows the importance of careful investigations of the processes, the climate shield and the heating systems already present in the building before measures are implemented in reality. A case study is presented dealing with a carpentry factory. The building is poorly insulated according to standards today, and initially it was assumed that a better thermal shield would be of vital importance in order to reach optimal conditions. Instead, it is shown that the main problem is the ordinary heating system. This uses steam from a wood chips boiler and the wood chips come from the manufacturing processes. These wood chips are, therefore, a very cheap fuel. The boiler had, during decades of use, slowly degraded into a poor state. Hence, aero-tempers using expensive electricity have been installed to remedy the situation. These use not only expensive kWh but also very expensive kW due to the electricity tariff. It is shown that electricity for heating purposes must be abandoned and further, that this could be achieved at a surprisingly small cost. By stopping a large waste of steam, it was possible to find resources, in the form of unspent money, for further mending the existing heating system. Not only economy but also environmental hazards in the form of CO 2 emissions urges us to abandon electricity and instead use heat from cheap biomass fired boilers. Such equipment saves environment at the same time it saves money

On Stakeholders and the Decision Making Process Concerning Sustainable Renovation and Refurbishment in Sweden, Denmark and Cyprus

DEFF Research Database (Denmark)

Gohardani, Navid; Björk, Folke; Jensen, Per Anker

2013-01-01

This article examines the decision making process related to sustainable renovation and refurbishment in buildings. The utilized methodology identifies three distinct phases in order to instigate an engagement in sustainable renovation, by means of questionnaires and semi-structured interviews...

Fabrication of {sup 94}Zr thin target for recoil distance doppler shift method of lifetime measurement

Energy Technology Data Exchange (ETDEWEB)

Gupta, C.K.; Rohilla, Aman [Department of Physics and Astrophysics, University of Delhi, Delhi 110007 (India); Abhilash, S.R.; Kabiraj, D.; Singh, R.P. [Inter University Accelerator Centre, Aruna Asaf Ali Marg, New Delhi 110067 (India); Mehta, D. [Department of Physics, Panjab University, Chandigarh 160014 (India); Chamoli, S.K., E-mail: skchamoli@physics.du.ac.in [Department of Physics and Astrophysics, University of Delhi, Delhi 110007 (India)

2014-11-11

A thin isotopic {sup 94}Zr target of thickness 520μg/cm{sup 2} has been prepared for recoil distance Doppler shift method (RDM) lifetime measurement by using an electron beam deposition method on tantalum backing of 3.5 mg/cm{sup 2} thickness at Inter University Accelerator Center (IUAC), New Delhi. To meet the special requirement of smoothness of surface for RDM lifetime measurement and also to protect the outer layer of {sup 94}Zr from peeling off, a very thin layer of gold has been evaporated on a {sup 94}Zr target on a specially designed substrate holder. In all, 143 mg of 99.6% enriched {sup 94}Zr target material was utilized for the fabrication of {sup 94}Zr targets. The target has been successfully used in a recent RDM lifetime measurement experiment at IUAC.

Refurbishment of small hydropower plants in Romania; Sanierung von Kleinwasserkraftwerken in Rumaenien

Energy Technology Data Exchange (ETDEWEB)

Gmeinbauer, Joerg [Wien Energie GmbH, Wien (Austria)

2010-07-01

In 2008 Wien Energie subsidiary Wienstrom GmbH participated in three public auctions of Hidroelectrica S.A. for the sale of old small hydro power plants in Romania. Together with strategic partners Wienstrom could successfully compete against local and international competition and acquired 31 small hydro power plants with a total installed capacity of around 20 MW. The plants were integrated into the newly established Vienna Energy Forta Naturala Srl. and are being completely refurbished at the moment. Wien Energie consequently is already the third largest operator of small hydro power plants in Romania. (orig.)

Fabricator opens next chapter in style

International Nuclear Information System (INIS)

Knott, Terry.

1997-01-01

The evolution of two offshore fabrication yards over twenty five years at Nigg and Ardersier on the Cromarty and Moray Firths in Scotland is traced. For most of the period since opening in 1972, the two yards operated as separate competing entities under the ownership of the construction companies Brown and Root and McDermott. In the early 1990s, market demand was shifting from the yard's traditional base of fixed platforms to floating and subsea technology while competition in the fabrication industry was growing in Europe. In response to this market challenge, in 1995 the two companies entered into a joint venture to operate the two yards as one entity, Barmac. Within three months of the formation of Barmac, the decision was taken to focus participation in the traditional offshore market at Ardersier and redevelop Nigg to take advantage of the rapidly expanding marine business. The key to this has been the transformation of Nigg's dormant graving dock into a dry dock capable of handling new market applications such as floating production systems, production jackups and semi-submersibles as newbuild, conversions or refurbishment. Two major construction contracts using the dock have already been secured by Barmac and other opportunities are opening up. Meanwhile, performance improvements have also been made in the traditional business at Ardersier. (UK)

Overview of refurbishment project of JMTR

Energy Technology Data Exchange (ETDEWEB)

Izumo, Hironobu; Hori, Naohiko; Kaminaga, Masanori; Kusunoki, Tsuyoshi; Ishihara, Masahiro; Komori, Yoshihiro; Suzuki, Masahide; Kawamura, Hiroshi [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan)

2012-03-15

The refurbishment project of the JMTR from the beginning of JFY 2007 was promoted with two subjects; the one is the replacement of reactor components, and the other is the construction of new irradiation facilities. On the replacement of reactor components, an investigation on aged components (aged-investigation) was carried out, for concrete structures, tanks, tubes in order to identify their integrity. After the investigation, some components were decided to replace from viewpoints of future maintenance and improvement of reliability. On the construction of new irradiation facilities, corresponding to the user's irradiation request, new irradiation facilities, such as irradiation test facilities and equipments for LWRs materials/fuels, were installed in the JMTR. Furthermore, in June 2010, 'birth of the nuclear techno-park with the JMTR' was selected by Japanese Government. The new project is to install new irradiation facilities, such as irradiation facility and equipments for Mo-99 production and PIE equipments to JMTR until JFY2012. The New JMTR will be utilized fully by wide fields of users. Moreover, the JMTR will also contribute the promotion on research and development of the nuclear energy from basic to applied fields as an internationally utilized facility under the international/Asian network collaborations. (author)

Motier church - refurbishment of heating system; Kirche Motier Sanierung der Raumheizung

Energy Technology Data Exchange (ETDEWEB)

Grizzetti, V.

2003-07-01

This final report for the Swiss Federal Office for Energy describes the refurbishment of the space heating system of the historical church in Motier, Switzerland. The 50-year old, inefficient electrical direct heating system of the church, which is a listed building, and the new, heat pump-based system are described. Heating energy is distributed via a warm-air system, geothermal energy provides the primary heat source for the heat pump. Technical details of the heating characteristics and energy consumption of the old and new heating systems are presented in the form of tables and diagrams. The maintenance of the heating system's ventilation unit is also discussed.

Refurbishing the reactor protection systems of VVER-440/230 and VVER-1000/320 nuclear power plants with exclusively digital IandC systems

International Nuclear Information System (INIS)

Martin, M.

1997-01-01

The refurbishment of reactor protection systems of nuclear power plants is based on two sets of requirements: engineering aspects such as performance, qualification and licensing, as well as interfaces to other systems; and cost-benefit relationships, ease of service and maintenance as well as installation during scheduled outages. A number of WWER-440 and WWER-1000 nuclear plants have announced their intention to refurbish their protection systems. Since 1994, these plants have been placing orders with Siemens for new protection systems, including the neutron flux monitoring system utilizing the advanced system TELEPERM XS. This exclusively digital IandC system provides an excellent foundation for the remaining plant service life

Refurbishment of the gas system, Task 3.08/04-07; Podzadatak 3.08/04-07 Remont sistema gasa

Energy Technology Data Exchange (ETDEWEB)

Nikolic, M; Bratic, A [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

1963-12-15

During the period planned for maintenance and refurbishment of the RA reactor gas system in the RA reactor building was inspected and tested, the components were cleaned and decontaminated. This report describes detailed instructions and actions concerning repair and decontamination of the gas system components.

Fabrication of aerogel capsule, bromine-doped capsule, and modified gold cone in modified target for the Fast Ignition Realization Experiment (FIREX) Project

Science.gov (United States)

Nagai, Keiji; Yang, H.; Norimatsu, T.; Azechi, H.; Belkada, F.; Fujimoto, Y.; Fujimura, T.; Fujioka, K.; Fujioka, S.; Homma, H.; Ito, F.; Iwamoto, A.; Jitsuno, T.; Kaneyasu, Y.; Nakai, M.; Nemoto, N.; Saika, H.; Shimoyama, T.; Suzuki, Y.; Yamanaka, K.; Mima, K.

2009-09-01

The development of target fabrication for the Fast Ignition Realization EXperiment (FIREX) Project is described in this paper. For the first stage of the FIREX Project (FIREX-I), the previously designed target has been modified by using a bromine-doped ablator and coating the inner gold cone with a low-density material. A high-quality bromine-doped capsule without vacuoles was fabricated from bromine-doped deuterated polystyrene. The gold surface was coated with a low-density material by electrochemical plating. For the cryogenic fuel target, a brand new type of aerogel material, phloroglucinol/formaldehyde (PF), was investigated and encapsulated to meet the specifications of 500 µm diameter and 20 µm thickness, with 30 nm nanopores. Polystyrene-based low-density materials were investigated and the relationship between the crosslinker content and the nanopore structure was observed.

Applying a CPLD for Refurbishment of a Multi-channel Pulse Height Analyzer

International Nuclear Information System (INIS)

Leetragunpichitchai, Supalerk; Thong-Aram, Decho; Ploykrachang, Kamontip

2007-08-01

Full text: This research applied a CPLD for construction of a 100 MHz, 2048 channel, Wilkinson type analog to digital converter (ADC) circuits for refurbishment of an original multi-channel pulse height analyzer (PHA) ADC. Introduction of the CPLD could reduce the complexity of the circuits, equipment size and also the power consumption while the operation speed was increased. The linearity test of the ADC was found to be excellent with an R2 = 0.9995 and a maximum pulse rate of 48.828 k cps could be converted in this system. Therefore the developed system was appropriate for replacing the original ADC

Targets and processes for fabricating same

Science.gov (United States)

Adams, Jesse D; Malekos, Steven; Le Galloudec, Nathalie; Korgan, Grant; Cowan, Thomas; Sentoku, Yasuhiko

2016-05-17

In particular embodiments, the present disclosure provides targets including a metal layer and defining a hollow inner surface. The hollow inner surface has an internal apex. The distance between at least two opposing points of the internal apex is less than about 15 .mu.m. In particular examples, the distance is less than about 1 .mu.m. Particular implementations of the targets are free standing. The targets have a number of disclosed shaped, including cones, pyramids, hemispheres, and capped structures. The present disclosure also provides arrays of such targets. Also provided are methods of forming targets, such as the disclosed targets, using lithographic techniques, such as photolithographic techniques. In particular examples, a target mold is formed from a silicon wafer and then one or more sides of the mold are coated with a target material, such as one or more metals.

Targets and processes for fabricating same

Science.gov (United States)

Cowan, Thomas [Dresden, DE; Malekos, Steven [Reno, NV; Korgan, Grant [Reno, NV; Adams, Jesse [Reno, NV; Sentoku, Yasuhiko [Reno, NV; Le Galloudec, Nathalie [Reno, NV; Fuchs, Julien [Paris, FR

2012-07-24

In particular embodiments, the present disclosure provides targets including a metal layer and defining a hollow inner surface. The hollow inner surface has an internal apex. The distance between at least two opposing points of the internal apex is less than about 15 .mu.m. In particular examples, the distance is less than about 1 .mu.m. Particular implementations of the targets are free standing. The targets have a number of disclosed shaped, including cones, pyramids, hemispheres, and capped structures. The present disclosure also provides arrays of such targets. Also provided are methods of forming targets, such as the disclosed targets, using lithographic techniques, such as photolithographic techniques. In particular examples, a target mold is formed from a silicon wafer and then one or more sides of the mold are coated with a target material, such as one or more metals.

Refurbishment, Modernization and Ageing Management Program of The 3MW TRIGA Mark-II Research Reactor of Bangladesh

International Nuclear Information System (INIS)

Salam, M. A.

2013-01-01

The 3 MW TRIGA MK-II research reactor of Bangladesh Atomic Energy Commission (BAEC) achieved its first criticality on 14 September 1986. The reactor has been used for manpower training, radioisotope production and various R and D activities in the field of neutron activation analysis, neutron radiography and neutron scattering. Reactor Operation and Maintenance Unit (ROMU) is responsible for operation and maintenance of the research reactor. During the past twenty seven years ROMU carried out several refurbishments, replacement, modification and modernization activities in the reactor facility. The major tasks carried out under refurbishment program were replacement of the corrosion damaged N-16 decay tank by a new one, replacement of the fouled shell and tube type heat exchanger by a plate type one, modification of the shielding arrangements around the N-16 decay tank and ECCS system and solving the radial beam port-1 leakage problem. All of these refurbishment activities were performed under an annual development project (ADP) funded by Bangladesh government. BAEC research reactor (RR) was operated by analogue console system from its commissioning to July, 2011. Old analog based console has been replaced by digital console on June, 2012. Modernization program for the reactor control console due to obsolescence and unavailability of spare parts of I and C system was vital to restore the safe operation of the reactor. Considering these facts, installation of a digital control console and I and C system based on the state-of-the-art digital technology became necessary. Reactor digital console system installation tasks were performed under another ADP funded project by Bangladesh government. Now the reactor is operating with the digital control system. Besides this, the Neutron Radiography (NR) facility has been modernized by the addition of a digital neutron radiography set-up at the tangential beam port. The Neutron Scattering (NS) facility also has been upgraded

Refurbishment, Modernization and Ageing Management Program of The 3MW TRIGA Mark-II Research Reactor of Bangladesh

Energy Technology Data Exchange (ETDEWEB)

Salam, M. A. [Atomic Energy Research Establishment, Dhaka (Bangladesh)

2013-07-01

The 3 MW TRIGA MK-II research reactor of Bangladesh Atomic Energy Commission (BAEC) achieved its first criticality on 14 September 1986. The reactor has been used for manpower training, radioisotope production and various R and D activities in the field of neutron activation analysis, neutron radiography and neutron scattering. Reactor Operation and Maintenance Unit (ROMU) is responsible for operation and maintenance of the research reactor. During the past twenty seven years ROMU carried out several refurbishments, replacement, modification and modernization activities in the reactor facility. The major tasks carried out under refurbishment program were replacement of the corrosion damaged N-16 decay tank by a new one, replacement of the fouled shell and tube type heat exchanger by a plate type one, modification of the shielding arrangements around the N-16 decay tank and ECCS system and solving the radial beam port-1 leakage problem. All of these refurbishment activities were performed under an annual development project (ADP) funded by Bangladesh government. BAEC research reactor (RR) was operated by analogue console system from its commissioning to July, 2011. Old analog based console has been replaced by digital console on June, 2012. Modernization program for the reactor control console due to obsolescence and unavailability of spare parts of I and C system was vital to restore the safe operation of the reactor. Considering these facts, installation of a digital control console and I and C system based on the state-of-the-art digital technology became necessary. Reactor digital console system installation tasks were performed under another ADP funded project by Bangladesh government. Now the reactor is operating with the digital control system. Besides this, the Neutron Radiography (NR) facility has been modernized by the addition of a digital neutron radiography set-up at the tangential beam port. The Neutron Scattering (NS) facility also has been upgraded

Fabrication of a nanocarrier system through self-assembly of plasma protein and its tumor targeting

International Nuclear Information System (INIS)

Gong Guangming; Zhi Feng; Wang Kaikai; Tang Xiaolei; Yuan Ahu; Zhao Lili; Ding Dawei; Hu Yiqiao

2011-01-01

Human serum albumin (HSA) nanoparticles hold great promise as a nanocarrier system for targeted drug delivery. The objective of this study was to explore the possibility of preparing size controllable albumin nanoparticles using the disulfide bond breaking reagent β-mercaptoethanol (β-ME). The results showed that the protein concentration and temperature had positive effects on the sizes of the albumin nanoparticles, while pH had a negative effect on the rate of nanoparticle formation. The addition of β-ME induced changes in HSA secondary structure and exposed the hydrophobic core of HSA, leading to the formation of nanoparticles. Human serum albumin nanoparticles could be internalized by MCF-7 cells and mainly accumulated in cytoplasm. After injection in tumor bearing mice, the HSA nanoparticles accumulated in tumor tissues, demonstrating the targeting ability of the nanoparticles. Therefore, human serum albumin can be fabricated into nanoparticles by breaking the disulfide bonds and these nanoparticles exhibit high tumor targeting ability. Human serum albumin nanoparticles could be ideal for the targeted delivery of pharmacologically active substances.

Design and fabrication of a CH/Al dual-layer perturbation target for hydrodynamic instability experiments in ICF

Energy Technology Data Exchange (ETDEWEB)

Tang, Jun [Shanghai Key Laboratory of Special Artificial Microstructure Materials and Technology, School of Physics Science and Engineering, Tongji University, Shanghai 200092 (China); Xie, Zhiyong [Shanghai Institute of Laser Plasma, Shanghai 201800 (China); Du, Ai [Shanghai Key Laboratory of Special Artificial Microstructure Materials and Technology, School of Physics Science and Engineering, Tongji University, Shanghai 200092 (China); Ye, Junjian [Shanghai Institute of Laser Plasma, Shanghai 201800 (China); Zhang, Zhihua; Shen, Jun [Shanghai Key Laboratory of Special Artificial Microstructure Materials and Technology, School of Physics Science and Engineering, Tongji University, Shanghai 200092 (China); Zhou, Bin, E-mail: zhoubin863@tongji.edu.cn [Shanghai Key Laboratory of Special Artificial Microstructure Materials and Technology, School of Physics Science and Engineering, Tongji University, Shanghai 200092 (China)

2014-04-15

Highlights: • Sinusoidal perturbed Al foil was prepared by single-point diamond turning. • Perturbed Al foil was measured by surface profiler and white light interferometer. • Perturbed Al foil and CH layer adhered with each other via a hot-press process. • Parameters and cross-section of the CH–Al perturbation target was characterized. - Abstract: A polystyrene (CH)/aluminum (Al) dual-layer perturbation target for hydrodynamic instability experiments in inertial confinement fusion (ICF) was designed and fabricated. The target was composed of a perturbed 40 μm Al foil and a CH layer. The detailed fabrication method consisted of four steps. The 40 μm Al foil was first prepared by roll and polish process; the perturbation patterns were then introduced on the surface of the Al foil by the single-point diamond turning (SPDT) technology; the CH layer was prepared via a simple method which called spin-coating process; finally, the CH layer was directly coated on the perturbation surface of Al foil by a hot-press process to avoid the use of a sticker and to eliminate the gaps between the CH layer and the Al foil. The parameters of the target, such as the perturbation wavelength (T) and perturbation amplitude (A), were characterized by a QC-5000 tool microscope, an alpha-step 500 surface profiler and a NT1100 white light interferometer. The results showed that T and A of the target were about 52 μm and 7.34 μm, respectively. Thickness of the Al foil (H1), thickness of the CH layer (H2), and cross-section of the dual-layer target were characterized by a QC-5000 tool microscope and a scanning electron microscope (SEM). H1 and H2 were about 40 μm and 15 μm, respectively, the cross-sectional photographs of the target showed that the CH layer and the Al foil adhered perfectly with each other.

Biased Target Ion Beam Deposition and Nanoskiving for Fabricating NiTi Alloy Nanowires

Science.gov (United States)

Hou, Huilong; Horn, Mark W.; Hamilton, Reginald F.

2016-12-01

Nanoskiving is a novel nanofabrication technique to produce shape memory alloy nanowires. Our previous work was the first to successfully fabricate NiTi alloy nanowires using the top-down approach, which leverages thin film technology and ultramicrotomy for ultra-thin sectioning. For this work, we utilized biased target ion beam deposition technology to fabricate nanoscale (i.e., sub-micrometer) NiTi alloy thin films. In contrast to our previous work, rapid thermal annealing was employed for heat treatment, and the B2 austenite to R-phase martensitic transformation was confirmed using stress-temperature and diffraction measurements. The ultramicrotome was programmable and facilitated sectioning the films to produce nanowires with thickness-to-width ratios ranging from 4:1 to 16:1. Energy dispersive X-ray spectroscopy analysis confirmed the elemental Ni and Ti make-up of the wires. The findings exposed the nanowires exhibited a natural ribbon-like curvature, which depended on the thickness-to-width ratio. The results demonstrate nanoskiving is a potential nanofabrication technique for producing NiTi alloy nanowires that are continuous with an unprecedented length on the order of hundreds of micrometers.

Inertial confinement fusion target component fabrication and technology development support: Annual report, October 1, 1993--September 30, 1994

Energy Technology Data Exchange (ETDEWEB)

Hoppe, M. [ed.

1995-04-01

On December 30, 1990, the US Department of Energy entered into a contract with General Atomics (GA) to be the Inertial Confinement Fusion (ICF) Target Component Fabrication and Technology Development Support contractor. During the period, GA was assigned 17 tasks in support of the Inertial Confinement Fusion program and its laboratories. This year they achieved full production capabilities for the micromachining, dimensional characterization and gold plating of hohlraums. They fabricated and delivered 726 gold-plated mandrels of 27 different types to LLNL and 48 gold-plated mandrels of two different types to LANL. They achieved full production capabilities in composite capsule production ad delivered in excess of 240 composite capsules. They continuously work to improve performance and capabilities. They were also directed to dismantle, remove, and disposition all equipment at the previous contractor (KMSF) that had radioactive contamination levels low enough that they could be exposed to the general public without radiological constraints. GA was also directed to receive and store the tritium fill equipment. They assisted LANL in the development of techniques for characterization of opaque targets. They developed deuterated and UV-opaque polymers for use by the University of Rochester`s Laboratory for Laser Energetics (UR/LLE) and devised a triple-orifice droplet generator to demonstrate the controlled-mass nature of the microencapsulation process. The ICF program is anticipating experiments at NIF and the Omega Upgrade. Both facilities will require capsules containing layered D{sub 2} or D-T fuel. They continued engineering and assembly of equipment for a cryogenic target handling system for UR/LLE that will fill, transport, layer, and characterize targets filled with cryogenic deuterium or deuterium-tritium fuel, and insert these cryogenic targets into the OMEGA Upgrade target chamber for laser implosion experiments.

Inertial confinement fusion target component fabrication and technology development support: Annual report, October 1, 1993--September 30, 1994

International Nuclear Information System (INIS)

Hoppe, M.

1995-04-01

On December 30, 1990, the US Department of Energy entered into a contract with General Atomics (GA) to be the Inertial Confinement Fusion (ICF) Target Component Fabrication and Technology Development Support contractor. During the period, GA was assigned 17 tasks in support of the Inertial Confinement Fusion program and its laboratories. This year they achieved full production capabilities for the micromachining, dimensional characterization and gold plating of hohlraums. They fabricated and delivered 726 gold-plated mandrels of 27 different types to LLNL and 48 gold-plated mandrels of two different types to LANL. They achieved full production capabilities in composite capsule production ad delivered in excess of 240 composite capsules. They continuously work to improve performance and capabilities. They were also directed to dismantle, remove, and disposition all equipment at the previous contractor (KMSF) that had radioactive contamination levels low enough that they could be exposed to the general public without radiological constraints. GA was also directed to receive and store the tritium fill equipment. They assisted LANL in the development of techniques for characterization of opaque targets. They developed deuterated and UV-opaque polymers for use by the University of Rochester's Laboratory for Laser Energetics (UR/LLE) and devised a triple-orifice droplet generator to demonstrate the controlled-mass nature of the microencapsulation process. The ICF program is anticipating experiments at NIF and the Omega Upgrade. Both facilities will require capsules containing layered D 2 or D-T fuel. They continued engineering and assembly of equipment for a cryogenic target handling system for UR/LLE that will fill, transport, layer, and characterize targets filled with cryogenic deuterium or deuterium-tritium fuel, and insert these cryogenic targets into the OMEGA Upgrade target chamber for laser implosion experiments

Products, practices and processes: exploring the innovation potential for low-carbon housing refurbishment among small and medium-sized enterprises (SMEs) in the UK construction industry

International Nuclear Information System (INIS)

Killip, Gavin

2013-01-01

Scenario-based studies agree that the technical potential for CO 2 emissions reduction from the housing stock is large. This paper explores how a market might be developed for the refurbishment activities assumed in these scenarios, taking the existing market for repair, maintenance and improvement (RMI) as its starting point. Interviews with 16 small and medium-sized enterprises (SMEs) in the construction industry reveal the interdependence of products, practices and processes in housing renovation activities. Conservative practice as well as innovation can be understood as the outcome of multi-lateral influences on firms from other firms, clients, the material buildings and products in their working lives, and from regulations and regulators. Contractors' openness to innovation is contingent on an informal approach to risk assessment, taking account of cost, time efficiency, client demands, and installer confidence in the reliability of the resulting work. The implications of the research are discussed in relation to the need for new practices and processes on refurbishment projects, raising questions for future research on key questions of quality assurance, performance over time, the application of standards, and vocational training. -- Highlights: •Repair, maintenance and improvement works are triggers for low-carbon refurbishment. •Millions of property owners and small firms make for fragmented decision-making. •Actor-Network Theory is used to frame decision-making processes for refurbishment. •Small builders can be innovative if clients allow time and money for experimentation. •Energy policy for existing homes needs to engage with the construction sector

Refurbishment and extension of the terrace of Restaurant No.1

CERN Multimedia

2009-01-01

Work to refurbish and extend part of the terrace of Restaurant No.1 started in the first week of October and should last about two months. This is just a small part of the wide-ranging site infrastructure consolidation programme that began in April 2009. The new terrace, covering a surface area of 1770 m2 (compared with 1650 m2 today), is scheduled to be completed by the end of 2010 and will run all the way around the Restaurant No.1 extension. Work on the latter will affect part of Building 501 during the period from April to October 2010. The new dining room will seat some 275 additional customers (see picture). Part of the Cedars car-park will remain closed until some time in December to provide site access for trucks transporting construction materials, plant, etc. CERN Bulletin

OSIRIS. Refurbishment and management of ageing effects

International Nuclear Information System (INIS)

Joly, C.; Guidez, J.; Contenson, G. de; Marin, J.P.

1995-01-01

OSIRIS, one of the French CEA research reactors (Saclay, France), achieved criticality for the first time on July 1966. During the 29 running years OSIRIS was mainly devoted to production and technological irradiations. To satisfy these objectives, OSIRIS is equipped by different test facilities allowing: the long time irradiation of different material including fuel rods, reactor vessel materials, fusion reactor components; the power ramps of fuel rods; the activation analysis; the neutron-radiography of materials and test sections... All the foreseen irradiation programmes will only be possible if safety and high performances of the reactor are guaranteed. That is why a continuous maintenance and improvement programme has taken place during the whole life of the reactor. This paper gives an overview of this programme, mainly about the part conducted during the last years. Details about characteristics of the reactor, history of experiments, maintenance programme, instrumentation and control system, electrotechnical low voltage supply network, decay tanks and water purification system are summarized. The paper focuses on the refurbishment or the replacement of the main components connected to the continuous maintenance programme to guarantee the reliability, the safety and the high performances of the reactor. (J.S.). 2 refs., 8 figs., 2 tabs

Home-made refurbishment of the instrumentation and control system of the TRIGA reactor of the University of Pavia

International Nuclear Information System (INIS)

Borio di Tigliole, A.; Cagnazzo, M.; Magrotti, G.; Manera, S.; Salvini, A.; Musitelli, G.; Nardo, R.

2008-01-01

The Instrumentation and Control (I and C) System of the TRIGA reactor of the University of Pavia was dated and, in order to grant a safe and continuous reactor operation for the future, it became necessary to substitute or to upgrade the system. Since the substitution of the I and C system with a new-made one was very difficult to be performed due to long authorization procedures, an home-made refurbishment was planned. Using commercial components of high quality, almost a complete substitution, channel-by-channel, of the I and C system was realized without changing the operating and safety logics. The system includes: - the Reactor Linear Power Channel and Chart Recorder; - the Reactor Percent Power Safety Channel; - the High Voltage and Low Voltage Power Supply; - the Automatic Reactor Power Control; - the Fuel Elements and Cooling-Water Temperatures Measuring Channels; - the Water Conductivity Measuring Channel. The refurbished I and C system shows a very good operational behavior and reliability and will assure a continuous operation of the reactor for the future

Conception and fabrication of innovative Am-Based targets: the ca mix/Cochix experiment

International Nuclear Information System (INIS)

Schmidt, N.; Croixmarie, Y.; Abonneau, E.; Ottaviani, J.P.; Donnet, L.; Desmouliere, F.; Konings, R.J.M.; Fernandez, A.

2003-01-01

A large experimental programme has been planned to be carried out in the French PHENIX reactor. The purpose is to evaluate the technical feasibility of minor actinide transmutation in fast reactors. Two major series of experiments have been designed for the heterogeneous transmutation mode. The first one, the MATINA (Matrices for Incineration of Actinides) series, aims at testing both different inert matrices in a fast flux and different concepts. The study is generic and focuses on the material behaviour under representative irradiation conditions. Targets are free of minor actinides to make the fabrication and design steps easier and faster. The second one, ECRIX, CAMIX (Compounds of Americium in PHENIX) and COCHIX (Concept Optimized microstructure in PHENIX), is a further step in the demonstration phase of the ''once-through'' transmutation and deals with Am-bearing targets irradiated in a fast neutron spectrum ''locally'' moderated. The moderator materials tested will be calcium hydride CaH 2-x (cases of ECRIX-H, CAMIX and COCHIX) and boron carbide 11 B 4 C (case of ECRIX-B) in order to accelerate the process of transmutation significantly. (author)

Densifying the city: urban recycle as a strategic system to refurbish the built environment

Directory of Open Access Journals (Sweden)

Vittorino Belpoliti

2015-11-01

Full Text Available The persisting economic crisis and the necessity for more sustainable construction processes imply the need for innovative strategies to reuse the existing building stock. Retrofit and recycling plans are already active for whole city districts, adopting the urban densification strategy to reduce the consumption of resources, promoting the functional, technological, and energy refurbishment of the existing city districts The study introduces considerations and tools to increase the efficiency of retrofit action onto abandoned and degraded area through the improvement of their energy and environmental performances. 

RA Reactor operation and maintenance (I-IX), part VII, Task 3.08/04, Refurbishment of the RA reactor; Pogon i odrzavanje reaktora (I-IX), VII Deo, Zadatak 3.08/04 Remont reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

1963-12-15

This volume covers the following reports concerned with the maintenance and repair work of the RA reactor: repair of the technical water system; maintenance of the transportation equipment; vacuuming and drying during refurbishment; repair and decontamination of the distillation device; and the report on participation of the operational dosimetry division in the RA reactor refurbishment activities.

Pre-series and testing route for the serial fabrication of W7-X target elements

International Nuclear Information System (INIS)

Boscary, J.; Greuner, H.; Friedrich, T.; Traxler, H.; Mendelevitch, B.; Boeswirth, B.; Schlosser, J.; Smirnow, M.; Stadler, R.

2009-01-01

The fabrication of the actively cooled high-heat flux divertor of the WENDELSTEIN 7-X stellarator (W7-X) requires the delivery of 890 target elements, which are designed to withstand a stationary heat flux of 10 MW/m 2 . The organization of the manufacturing and testing route for the serial fabrication is the result of the pre-series activities. Flat CFC Sepcarb NB31 tiles are bonded to CuCrZr copper alloy cooling structure in consecutive steps. A copper layer is active metal cast to CFC tiles, and then an OF-copper layer is added by hot isostatic pressing to produce bi-layer tiles. These tiles are bonded by electron beam welding onto the cooling structure, which was manufactured independently. The introduction of the bi-layer technology proved to be a significant improvement of the bond reliability under thermal cycling loading. This result is also the consequence of the improved bond inspections throughout the manufacturing route performed in the ARGUS pulsed thermography facility of PLANSEE. The repairing process by electron beam welding of the bonding was also qualified. The extended pre-series activities related to the qualification of fabrication processes with the relevant non-destructive examinations aim to minimize the risks for the serial manufacturing and to guarantee the steady-state operation of the W7-X divertor.

Targets development at Sandia National Laboratories

International Nuclear Information System (INIS)

Smith, M.L.; Hebron, D.; Derzon, M.; Olson, R.; Alberts, T.

1997-01-01

For many years, Sandia National Laboratories under contract to the Department of Energy has produced targets designed to understand complex ion beam and z-pinch plasma physics. This poster focuses on the features of target designs that make them suitable for Z-pinch plasma physics applications. Precision diagnostic targets will prove critical in understanding the plasma physics model needed for future ion beam and z-pinch design. Targets are designed to meet specific physics needs; in this case the authors have fabricated targets to maximize information about the end-on versus side-on x-ray emission and z-pinch hohlraum development. In this poster, they describe the fabrication and characterization techniques. They include discussion of current targets under development as well as target fabrication capabilities. Advanced target designs are fabricated by Sandia National Laboratories in cooperation with General Atomics of San Diego, CA and W.J. Schafer Associates, Inc. of Livermore, CA

Target support for inertial confinement fusion

International Nuclear Information System (INIS)

Schultz, K.R.

1995-08-01

General Atomics (GA) plays an important industrial support role for the US Inertial Confinement Fusion (ICF) program in the area of target technology. This includes three major activities: target fabrication support, target handling systems development, and target chamber design. The work includes target fabrication for existing ICF experiments, target and target system development for future experiments, and target research and target chamber design for experiments on future machines, such as the National Ignition Facility (NIF)

Report on participation of the operational dosimetry division in refurbishment of the RA reactor, Task 3.08/04-13; Podzadatak 3.08/04-13 Izvestaj o ucescu Odseka operativne dozimetrije RZ u remontnim radovima na Reaktoru RA

Energy Technology Data Exchange (ETDEWEB)

Ninkovic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

1963-12-15

During the refurbishment of the RA reactor, from January to June 1963 the division of operational division had a very important role and comprehensive tasks. To enable safety of the staff it was necessary to provide protection clothes, personnel dosemeters; permanent monitoring of radiation doses; strict control of the procedures for completing the planned maintenance and repair operations to avoid contamination of the personnel and working space. The refurbishment activities described in this report are: removal of fuel from the core; refurbishment of the heavy water system; decontamination of the distillation equipment; repair of the gas system.

Status of FRJ-2 refurbishment of tank pipes and essential results of aging analysis

International Nuclear Information System (INIS)

Hansen, G.; Thamm, G.; Thome, M.

1993-01-01

An aging evaluation program for FRJ-2 (DIDO) of the Forschungszentrum Juelich GmbH has been developed and is currently executed in cooperation with the licensing and regulatory and TUV experts in order to determine the overall life expectancy of the facility and to identify critical systems and components that need to be upgraded or refurbished for future safe reactor operation. In Phase A (completed) a so called master list of the FRJ-2 mechanical, electrical and structural components was compiled on a system-by system basis and the operational documentation with respect to regular inspections, maintenance, repair and unusual occurences was carefully examined. Critical components were selected and their ageing respectively life limiting mechanisms identified. In Phase (currently under way) special inspections, examinations and tests for critical systems/components are being elaborated, executed and evaluated. Current work is being concentrated on non replaceable components (e.g. reactor aluminium tank (RAT) and the connecting pipes to the primary cooling circuit, the reactor steel tank and pipe work inside the concrete reactor block). As a consequence of first results of the aging evaluation program and due to leaks in the weir and drain pipes of the RAT a repair/refurbishment program was set up for the Al-RAT pipes (risers, downcomers weir and drain pipes) and the steel guide tubes. Details of the r/r program which is in far progress and first essential results of the aging evaluation will be presented. The results achieved until today are encouraging with respect to safe reactor operation on short and medium term. (author)

Status of FRJ-2 Refurbishment of tank pipes and essential results of aging analysis

International Nuclear Information System (INIS)

Hansen, G.; Thamm, G.; Thome, M.

1994-01-01

An aging evaluation program for FRJ-2 (DIDO) of the Forschungszentrum Juelich GmbH has been developed and is currently executed in cooperation with the licensing and regulatory and TUEV experts in order to determine the overall life expectancy of the facility and to identify critical systems and components that need to be upgraded or refurbished for future safe reactor operation. In Phase A (completed) a so called master list of the FRJ-2 mechanical, electrical and structural components was compiled on a system-by system basis and the operational documentation with respect to regular inspections, maintenance, repair and unusual occurrences was carefully examined. Critical components were selected and their ageing respectively life limiting mechanisms identified. In Phase B (currently under way) special inspections, examinations and tests for critical systems/components are being elaborated, executed and evaluated. Current work is being concentrated on non replaceable components (e.g. reactor aluminium tank (RAT) and the connecting pipes to the primary cooling circuit, the reactor steel tank and pipe work inside the concrete reactor block). As a consequence of first results of the aging evaluation program and due to leaks in the weir and drain pipes of the RAT a repair/refurbishment program was set up for the Al-RAT pipes (risers, downcomers, weir and drain pipes) and the steel guide tubes. Details of the r/r program which is in far progress and first essential results of the aging evaluation will be presented. The results achieved until today are encouraging with respect to safe reactor operation on short and medium term. (J.P.N.)

An Effort to Improve U Foil Fabrication Technology of Roll-casting for Fission Mo Target

Energy Technology Data Exchange (ETDEWEB)

Kim, Chang Kyu; Woo, Yun Myeong; Kim, Ki Hwan; Oh, Jong Myeong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Sim, Moon Soo [Chungnam University, Green Energy Technology, Daejeon (Korea, Republic of)

2010-10-15

Mo-99 isotope has been produced mainly by extracting fission products of {sup 235}U. The targets for irradiating in reactor have used as stainless tube coated with highly enriched UO{sub 2} at the inside surface and highly enriched UAlx plate cladded with aluminum. In connection with non-proliferation policy the RERTR program developed a new process of Mo-99 using low enriched uranium (LEU) instead of highly enriched uranium (HEU). LEU should be put about five times more quantity than HEU because the {sup 235}U contents of LEU and HEU are 20% and higher than 90%, respectively. Accordingly pure uranium metal foil target was adopted as a promising target material due to high uranium density. ANL and BATAN developed a Cintichem process using uranium metal foil target of 130 {mu}m in thickness jointly and the RERTR program is trying to disseminate the new process world-widely. However, uranium foil is made by lots of times rolling work on uranium plate, which is laborious and tedious. In order to avoid this difficulty KAERI developed a new process of making foil directly from uranium melt by roll casting. This process is very much simple, productive, and cost-effective. But the outside surface of foil is generally very rough. A typical transverse cross section had a minimum thickness of 65 {mu}m and a maximum thickness of 205 {mu}m. This roughness could affect (1) target fabrication, where the U foil, or the Ni foil might be damaged during drawing, and (2) irradiation behavior, where gaps between the target walls and the U metal might affect cooling of the target

Fabrication of the wing and vertical target dummy armour prototypes of the ITER divertor

Energy Technology Data Exchange (ETDEWEB)

Grattarola, M. E-mail: gratta@ari.ansaldo.it; Bet, M.; Biagiotti, B.; Gandini, G.; Merola, M.; Ottonello, G.B.; Riccardi, B.; Vieider, G.; Zacchia, F

2000-11-01

The dummy armour prototypes are identical to the reference components in terms of geometry, cooling circuit and material except for the armour material, which is replaced by an equivalent thickness of copper alloy. The main objectives of the dummy armour prototypes are the demonstration of the overall engineering concept of the Divertor, the integration in a 3 deg. cassette together with components manufactured by the other ITER Home Teams and the successive thermo-hydraulic tests on the whole Divertor module. This paper describes the realization of both the wing and the vertical target dummy armour prototypes focusing on the critical aspects of the fabrication and their impact on a further industrialization of the components.

Fabrication of the wing and vertical target dummy armour prototypes of the ITER divertor

International Nuclear Information System (INIS)

Grattarola, M.; Bet, M.; Biagiotti, B.; Gandini, G.; Merola, M.; Ottonello, G.B.; Riccardi, B.; Vieider, G.; Zacchia, F.

2000-01-01

The dummy armour prototypes are identical to the reference components in terms of geometry, cooling circuit and material except for the armour material, which is replaced by an equivalent thickness of copper alloy. The main objectives of the dummy armour prototypes are the demonstration of the overall engineering concept of the Divertor, the integration in a 3 deg. cassette together with components manufactured by the other ITER Home Teams and the successive thermo-hydraulic tests on the whole Divertor module. This paper describes the realization of both the wing and the vertical target dummy armour prototypes focusing on the critical aspects of the fabrication and their impact on a further industrialization of the components

Fabrication Method of the Mo-99 Target with Advanced Planar Flow Casting

International Nuclear Information System (INIS)

Sim, M. S.; Lee, J. H.; Kim, C. K.; Kim, W. J.

2011-01-01

Mo-99 is a parent isotope of Tc-99m for medical diagnosis and very significant owing to its large fraction over 80% of the whole demand of medical radioisotopes in the all countries. Mo-99 isotope has been produced mainly by 235 U which is extracting fission products. All the major providers of fission Mo have used HEU as a target material. But RERTR program that is nonproliferation policy encourages using HEU to LEU. KAERI has developed a processing to be able to produce a uranium foil continuously at one go. This processing gave an opportunity for LEU target using uranium foil to be commercialized. It correspond RERTR program. KAERI developed a new process of making foil directly from uranium melt by PFC. This process is simple, productive, and cost-effective. But the foil's air-side surface is generally very rough. A typical transverse cross section had a minimum thickness of 65 μm and a maximum thickness of 205 μm. This roughness could affect target fabrication and irradiation behavior. After issuing this problem KAERI launched a further effort since 2008. A new equipment was designed and manufactured in the industry in 2009. While the new equipment being test-operating, some occurrence of appearing problems appeared. Since 2010, Equipment was moved to KAERI, we performed many experiments using depleted uranium, and go get satisfied some results. We have got interesting results and manufactured uranium foil. A typical transverse cross section had a minimum thickness of 87 μm and a maximum thickness of 194 μm. The average thickness is 120 μm as a result of calculation

Refurbishment of damaged tools using the combination of GTAW and laser beam welding

Directory of Open Access Journals (Sweden)

J. Tušek

2014-10-01

Full Text Available This paper presents the use of two welding processes for the refurbishment of damaged industrial tools. In the first part the problem is presented followed by the comparison of GTAW and laser welding in terms of repair welding of damaged tools. The macrosections of the welds show the difference between both welding processes in repairing of damaged tools. At the conclusion the main findings are presented. In many cases it is useful to use both welding processes in order to achieve better weld quality and to make welding more economical. The order of the technology used depends on the tool material, the use of the tool and the tool damage.

Recent Developments in Fabrication of Direct Drive Cylinder Targets for Hydrodynamics Experiments at the OMEGA Laser

International Nuclear Information System (INIS)

Nobile, A.; Balkey, M.M.; Bartos, J.J.; Batha, S.H.; Day, R.D.; Elliott, J.E.; Elliott, N.E.; Gomez, V.M.; Hatch, D.J.; Lanier, N.E.; Fincke, J.R.; Manzanares, R.; Pierce, T.H.; Sandoval, D.L.; Schmidt, D.W.; Steckle, W.P.

2004-01-01

Experimental campaigns are being conducted at the 60 beam OMEGA laser at the University of Rochester's Laboratory for Laser Energetics to acquire data to validate hydrodynamic models in the high energy-density regime. This paper describes targets that have been developed and constructed for these experimental campaigns. Targets are 860 μm inner diameter by 2.2 mm length cylinders with 70 μm thick polymer ablator. On the ablator inner surface and located halfway along the axis of the cylinder is a 500 μm wide Al marker band. Band thicknesses in the range 8-16 microns are used. CH foam with densities in the range 30-90 mg/cc fills the inside of the cylinder. While these targets have been fabricated for years, several new improvements and features have recently been developed. Improvements include the use of epoxy instead of polystyrene for the ablator, and the use of electrodeposited Al for the marker band. A critical feature of the target is the surface feature that is placed on the marker band. Experiments are aimed at understanding the hydrodynamic behavior of imploding cylinders as a function of this surface feature. Recent development work has focused on production of engineered surface features on the target marker band. Using a fast tool servo on a diamond turning lathe, a wide range of specified surface features have been produced. This paper will address improvements to the cylinder targets as well as current development efforts

Refurbishment and retrofitting of SF6 gas storage tanks of the pelletron accelerator

International Nuclear Information System (INIS)

Reddy, G.R.; Datar, V.M.; Parulekar, Y.M.

2015-01-01

The BARC-TIFR Pelletron Accelerator Facility has completed more than twenty six years of successful round-the-clock operation, serving diverse users from institutions within and outside DAE. The main accelerating structure and associated subsystems are housed in the accelerator tank under SF 6 gas medium. During maintenance of the accelerator, the SF 6 gas present in the accelerator tank is transferred in the four storage tanks located on the terrace of the building open to outside environment. These four storage tanks (with ∼ 1/4th of the main tank volume each) are ∼ 4.27 m in diameter and ∼ 10 m in height each and are supported on RCC ring beams which are monolithically connected with the RCC structure below. Over the years, the anchor bolts and the base plates of support structure of storage tanks were found corroded and the foundation RCC ring beam indicated a few corrosion cracks. Health assessment of relevant structures and components were carried out. Considering the limitations of existing anchorage and also giving due considerations for reparability and replaceability, a new anchorage system was designed. The entire refurbishment and retrofitting works pertaining to the four SF 6 gas storage tanks was executed in a time bound manner to comply with the then PASC (Particle Accelerator Safety Committee) recommendations successfully, without disrupting the operations of the round-the-clock running Pelletron Accelerator facility. In addition, the thickness measurements for the storage tanks were performed. The relief valves and rupture disc assemblies across the storage tanks were replaced and reinstalled after introducing appropriate manual valves as suggested by the PASC. A new test set up was fabricated to perform pneumatic testing at the recommended pressure off-line for these relief valves and rupture disc assemblies prior to reinstallation. This paper describes the comprehensive rehabilitation and retrofitting procedures that were carried out at the

Gentilly-2 refurbishment pre-project

International Nuclear Information System (INIS)

Pageau, Rene; Doyon, Martial; Rheaume, M.R.

2002-01-01

The conceptual design life of Gentilly-2 station is 30 years and the station was put in service in 1982. Hydro-Quebec has initiated a project to assess the refurbishment of the station in the horizon 2008-2010 and for an expected life extension of 25 years. The reactor has been successfully operated since its first full-power operation in early 80's, nearly 20 years ago. Although the overall performance of Gentilly-2 continues to be very good, it is reasonable to expect that age-related degradation of key plant components will have an increasing impact on operations as the plant continues to age. The replacement of the reactor channels component is required around 2008-2009. The replacement of the reactor tubes is a major activity and it is necessary to assess the capability of the station to operate safely and reliably for a an extended period of 25 years bringing the design life of the station to over 50 years. The challenges associated with extended life operation until at least 2030-33 horizon are to maintain the margin of safety for plant operations by ensuring reliability of safety-related systems, to reduce plant unavailability due to age-related component failures, and to minimize the costs for repairs and replacement of aging components. As shown on the next figure, the overall project is expected to spread over an 8 years period starting in 2001. A project feasibility study (phase-1) of four (4) years has been planned to assess the plant condition and to make an overall safety review. This project phase will confirm the economical viability of extended operation. A period of thirty-nine (39) months would be necessary for the procurement and manufacturing of all the reactor components, and for the engineering work related to safety and economic improvements. Reactor channel replacement is planned for an outage not exceeding 18 months. (author)

Refurbishment implications on long-term waste management strategies at Point Lepreau

International Nuclear Information System (INIS)

Hickman, C.

2011-01-01

This paper discusses Point Lepreau Generating Station's waste management experiences during the Refurbishment outage. In short, Point Lepreau GS has been challenged during the outage due to the amount of low and intermediate level waste that has been generated compared to that which was expected, which has driven the need to develop a new waste management strategy in the middle of the outage. The paper presents an overview of pre-outage waste handling, what process changes and schedule changes occurred during the outage, and provides a discussion of the operational and financial consequences of those changes. Key issues highlighted by the paper include the need for adequate provision of waste management facilities during large outages, the importance of ensuring that contractors have a stake in waste minimization activities, and long term waste management implications that need to be considered for large outages.

Recent advances in the utilization and the irradiation technology of the refurbished BR2 reactor

International Nuclear Information System (INIS)

Dekeyser, J.; Benoit, P.; Decloedt, C.; Pouleur, Y.; Verwimp, A.; Weber, M.; Vankeerberghen, M.; Ponsard, B.

1999-01-01

Operation and utilization of the materials testing reactor BR2 at the Belgian Nuclear Research Centre (SCK·CEN) has since its start in 1963 always followed closely the needs and developments of nuclear technology. In particular, a multitude of irradiation experiments have been carried out for most types of nuclear power reactors, existing or under design. Since the early 1990s and increased focus was directed towards more specific irradiation testing needs for light water reactor fuels and materials, although other areas of utilization continued as well (e.g. fusion reactor materials, safety research, ...), including also the growing activities of radioisotope production and silicon doping. An important milestone was the decision in 1994 to implement a comprehensive refurbishment programme for the BR2 reactor and plant installations. The scope of this programme comprised very substantial studies and hardware interventions, which have been completed in early 1997 within planning and budget. Directly connected to this strategic decision for reactor refurbishment was the reinforcement of our efforts to requalify and upgrade the existing irradiation facilities and to develop advanced devices in BR2 to support emerging programs in the following fields: - LWR pressure vessel steel, - LWR irradiation assisted stress corrosion cracking (IASCC), - reliability and safety of high-burnup LWR fuel, - fusion reactor materials and blanket components, - fast neutron reactor fuels and actinide burning, - extension and diversification of radioisotope production. The paper highlights these advances in the areas of BR2 utilisation and the ongoing development activities for the required new generation of irradiations devices. (author)

Factors relevant to the recycling or reuse of components arising from the decommissioning and refurbishment of nuclear facilities

International Nuclear Information System (INIS)

1988-01-01

The decommissioning and decontamination of nuclear facilities is a topic of great interest to many Member States of the International Atomic Energy Agency (IAEA) because of the large number of older nuclear facilities which are or soon will be retired from service. To assist in the development of the required decommissioning expertise, the IAEA is developing reports and recommendations which will eventually form an integrated information base covering in a systematic way the wide range of topics associated with decommissioning. This information is required so that Member States can decommission their nuclear facilities in a safe, timely and cost effective manner and the IAEA can effectively respond to requests for assistance. One area which warrants more detailed analyses is an assessment of the factors important to the recycling or reuse of components arising from the refurbishment or decommissioning of nuclear plants, the topic of the present report. The document provides an up to date review of the engineering, social, scientific and administrative factors relevant to the safe recycling or reuse of components arising from decommissioning or refurbishment of nuclear facilities. This report should be of interest to owners, operators, policy makers and regulators involved with nuclear facilities, especially those in developing countries. Refs, figs and tabs

Description of ECRI (CNEA'S MTR fuel fabrication plant)

International Nuclear Information System (INIS)

Echenique, P.; Fabro, J.; Podesta, D.; Restelli, M.; Rossi, G.; Alvarez, L.; Adelfang, P.

2002-01-01

The ECRI Plant is dedicated to the development and fabrication of high-density fuel elements and targets for 99 Mo. In this sector had been done the start up Fuel Elements for the Reactors of Peru, Iran, Algeria and Egypt. All of them were made with U 3 O 8 . The targets for 99 Mo using HEU were fabricated too in the last years. The new material of high-density for Fuel Elements as U 3 Si 2 were done in this sector, three prototypes were fabricated, two are still under irradiation. (P06 and P07). As new developments we are working with U-Mo (7%) Fuel Plates with both material Korean and HMD. This work is under the RERTR Program and two fuel elements, manufactured by us, with both powders, will be irradiated in Petten. For 99 Mo targets, we are fabricating miniplates of LEU with an AlUx powder by pulvi-metallurgy technique. And it is under development the foils targets under the RERTR Program. A general view of the fabrication facilities and control sector will be shown. The different operations that are done in each sector will be explained. All our activities will be certified under the ISO 9000 and we are working hard to get it in the middle of 2003. (author)

Fabrication Method of the Mo-99 Target with Advanced Planar Flow Casting

Energy Technology Data Exchange (ETDEWEB)

Sim, M. S.; Lee, J. H. [Chungnam University, Green Energy Technology, Daejeon (Korea, Republic of); Kim, C. K.; Woo, Y. M. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2011-05-15

Mo-99 is a parent isotope of Tc-99m for medical diagnosis and very significant owing to its large fraction over 80% of the whole demand of medical radioisotopes in the all countries. Mo-99 isotope has been produced mainly by {sup 235}U which is extracting fission products. All the major providers of fission Mo have used HEU as a target material. But RERTR program that is non-proliferation policy encourages using HEU to LEU. KAERI has developed a processing to be able to produce a uranium foil continuously at one go. This processing gave an opportunity for LEU target using uranium foil to be commercialized. It correspond RERTR program. KAERI developed a new process of making foil directly from uranium melt by PFC. This process is simple, productive, and cost-effective. But the foil{center_dot}{center_dot}{center_dot}s air-side surface is generally very rough. A typical transverse cross section had a minimum thickness of 65 {mu}m and a maximum thickness of 205 {mu}m. This roughness could affect target fabrication and irradiation behavior. After issuing this problem KAERI launched a further effort since 2008. A new equipment was designed and manufactured in the industry in 2009. While the new equipment being test-operating, some occurrence of appearing problems appeared. Since 2010, Equipment was moved to KAERI, we performed many experiments using depleted uranium, and go get satisfied some results. We have got interesting results and manufactured uranium foil. A typical transverse cross section had a minimum thickness of 87 {mu}m and a maximum thickness of 194 {mu}m. However, the average thickness is 130 {mu}m as a result of measurement by a micrometer

Refurbishment of the transportation equipment, Task 3.08/04-10; Podzadatak 3.08/04-10 Remont transportnih uredjaja

Energy Technology Data Exchange (ETDEWEB)

Nikolic, M; Bratic, A [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

1963-12-15

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

Acoustical qualification of Teatro Nuovo in Spoleto before refurbishing works

Science.gov (United States)

Cocchi, Alessandro; Cesare Consumi, Marco; Shimokura, Ryota

2004-05-01

To qualify the acoustical quality of an opera house two different approaches are now available: one is based on responses of qualified listeners (subjective judgments) compared with objective values of selected parameters, the other on comparison tests conducted in suited rooms and on a model of the auditory brain system (preference). In the occasion of the refurbishment of an opera house known for the Two Worlds Festival edited yearly by the Italian Composer G. C. Menotti, a large number of measurements were taken with different techniques, so it is possible to compare the different methods and also the results with some geometrical criterion, based on the most simple rules of musical harmony, now neglected as our attention is attracted to computer simulations, computer aided measurement techniques and similar modern methods. From this work some link between well known acoustical parameters (not known at the time when architects sketched the shape of ancient opera houses) and geometrical criteria (well known at the time when ancient opera houses were built) will be shown.

Current progress in NIF target concepts

International Nuclear Information System (INIS)

Gobby, P.L.; Foreman, L.R.; Thoma, D.J.; Jacobson, L.A.; Hollis, R.V.; Barrera, J.; Mitchell, M.A.; Salazar, M.A.; Salzer, L.J.

1996-01-01

Target concepts for the National Ignition Facility (NIF) require progress in the art and science of target fabrication. Three distinct issues are addressed: beryllium fuel capsules, foam-buffered direct drive, and high-density gas-filled hohlraums. In all cases experiments on the existing Nova laser at LLNL are either in progress or planned for the near future to test the various concepts. Consequently, target fabrication must be able to deliver targets appropriate for each

Choosing the Energy Sources Needed for Utilities in the Design and Refurbishment of Buildings

Directory of Open Access Journals (Sweden)

Pavel Atănăsoae

2018-03-01

Full Text Available This paper presents a method for choosing the energy sources that are needed for the following building utilities following building: lighting, domestic hot water, heating, ventilation, and air conditioning. The novelty of this paper consists of applying the concept of the energy hub and considering the cost of carbon dioxide emissions when selecting the available energy sources in the building’s location. The criterion for selecting the energy sources is the minimum overall cost of all forms of energy that are consumed in the building over its estimated lifetime. In order to estimate the overall costs, it is necessary to know the power that is installed and provided by the energy production technologies that are inside the building, as well as the capacity of energy that is required from outside energy sources. An office building that was proposed for refurbishment has been investigated as a case study. In the paper, we have analysed four scenarios. The results indicate that more favourable alternative solutions can be obtained compared to the traditional scenario (Scenario 4—heat and electricity by public utility networks. The overall costs are 46.17% (212,671 EUR lower in Scenario 1, 25.35% (116,770 EUR lower in Scenario 2, and 10.89% (50,150 EUR lower in Scenario 3. Additionally, the carbon dioxide emissions are 22.98% (49 tonnes CO2/year lower in Scenario 1 and 8.91% (19 tonnes CO2/year lower in Scenario 2. Thus, renewable energy sources can occupy a growing share of the total energy consumption of the building. The proposed algorithm can be used for both the refurbishment of existing buildings and the design of new buildings.

Heavy-ion targets

International Nuclear Information System (INIS)

Adair, H.L.; Kobisk, E.H.

1985-01-01

This chapter examines the characteristics of targets required in heavy-ion accelerator physics experiments. The effects of target parameters on heavy-ion experimental results are reviewed. The target fabrication and characterization techniques used to minimize experimental problems during heavy-ion bombardment are described. Topics considered include target thickness and uniformity, target lifetime, target purity, substrate materials, Doppler shift effects, metal preparations, and target preparation methods

HRP facility for fabrication of ITER vertical target divertor full scale plasma facing units

International Nuclear Information System (INIS)

Visca, Eliseo; Roccella, S.; Candura, D.; Palermo, M.; Rossi, P.; Pizzuto, A.; Sanguinetti, G.P.; Mancini, A.; Verdini, L.; Cacciotti, E.; Cerri, V.; Mugnaini, G.; Reale, A.; Giacomi, G.

2015-01-01

Highlights: • R&D activities for the manufacturing of ITER divertor high heat flux plasma-facing components (HHFC). • ENEA and Ansaldo have jointly manufactured several actively cooled monoblock mock-ups and prototypical components. • ENEA and ANSALDO NUCLEARE jointly participate to the European program for the qualification of the manufacturing technology for the ITER divertor IVT. • Successful manufacturing by HRP (Hot Radial Pressing) of first full-scale full-W armored IVT qualification prototype. - Abstract: ENEA and Ansaldo Nucleare S.p.A. (ANN) have being deeply involved in the European development activities for the manufacturing of the ITER Divertor Inner Vertical Target (IVT) plasma-facing components. During normal operation the heat flux deposited on the bottom segment of divertor is 5–10 MW/m 2 but the capability to remove up to 20 MW/m 2 during transient events of 10 s must also be demonstrated. In order to fulfill ITER requirements, ENEA has set up and widely tested a manufacturing process, named Hot Radial Pressing (HRP). The last challenge is now to fabricate full-scale prototypes of the IVT, aimed to be qualified for the next step, i.e. the series production. On the basis of the experience of manufacturing hundreds of small mock-ups, ENEA designed and installed a new suitable HRP facility. The objective of getting a final shaped plasma facing unit (PFU) that satisfies these requirements is an ambitious target because tolerances set by ITER/F4E are very tight. The setting-up of the equipment started with the fabrication of full scale and representative ‘dummies’ in which stainless steel instead of CFC or W was used for monoblocks. The results confirmed that dimensions were compliant with the required tolerances. The paper reports a brief description of the innovative HRP equipment and the dimensional check results after HRP of the first full-scale full-W PFU.

HRP facility for fabrication of ITER vertical target divertor full scale plasma facing units

Energy Technology Data Exchange (ETDEWEB)

Visca, Eliseo, E-mail: eliseo.visca@enea.it [Unità Tecnica Fusione, ENEA C. R. Frascati, via E. Fermi 45, IT-00044 Frascati (Roma) (Italy); Roccella, S. [Unità Tecnica Fusione, ENEA C. R. Frascati, via E. Fermi 45, IT-00044 Frascati (Roma) (Italy); Candura, D.; Palermo, M. [Ansaldo Nucleare S.p.A., Corso Perrone 25, IT-16152 Genova (Italy); Rossi, P.; Pizzuto, A. [Unità Tecnica Fusione, ENEA C. R. Frascati, via E. Fermi 45, IT-00044 Frascati (Roma) (Italy); Sanguinetti, G.P. [Ansaldo Nucleare S.p.A., Corso Perrone 25, IT-16152 Genova (Italy); Mancini, A.; Verdini, L.; Cacciotti, E.; Cerri, V.; Mugnaini, G.; Reale, A.; Giacomi, G. [Unità Tecnica Fusione, ENEA C. R. Frascati, via E. Fermi 45, IT-00044 Frascati (Roma) (Italy)

2015-10-15

Highlights: • R&D activities for the manufacturing of ITER divertor high heat flux plasma-facing components (HHFC). • ENEA and Ansaldo have jointly manufactured several actively cooled monoblock mock-ups and prototypical components. • ENEA and ANSALDO NUCLEARE jointly participate to the European program for the qualification of the manufacturing technology for the ITER divertor IVT. • Successful manufacturing by HRP (Hot Radial Pressing) of first full-scale full-W armored IVT qualification prototype. - Abstract: ENEA and Ansaldo Nucleare S.p.A. (ANN) have being deeply involved in the European development activities for the manufacturing of the ITER Divertor Inner Vertical Target (IVT) plasma-facing components. During normal operation the heat flux deposited on the bottom segment of divertor is 5–10 MW/m{sup 2} but the capability to remove up to 20 MW/m{sup 2} during transient events of 10 s must also be demonstrated. In order to fulfill ITER requirements, ENEA has set up and widely tested a manufacturing process, named Hot Radial Pressing (HRP). The last challenge is now to fabricate full-scale prototypes of the IVT, aimed to be qualified for the next step, i.e. the series production. On the basis of the experience of manufacturing hundreds of small mock-ups, ENEA designed and installed a new suitable HRP facility. The objective of getting a final shaped plasma facing unit (PFU) that satisfies these requirements is an ambitious target because tolerances set by ITER/F4E are very tight. The setting-up of the equipment started with the fabrication of full scale and representative ‘dummies’ in which stainless steel instead of CFC or W was used for monoblocks. The results confirmed that dimensions were compliant with the required tolerances. The paper reports a brief description of the innovative HRP equipment and the dimensional check results after HRP of the first full-scale full-W PFU.

Vacuuming and drying during refurbishment, Task 3.08/04-11; Podzadatak 3.08/04-11 Vakuumiranje i susenje u toku remonta

Energy Technology Data Exchange (ETDEWEB)

Nikolic, M; Crnilovic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

1963-12-15

The following tasks were completed during RA reactor refurbishment: vacuuming the gas system; vacuuming of the heavy water system for collecting the leftover heavy water; drying the heavy water system to remove the demineralized water; drying the distillation system; vacuuming the heavy water system before filling with heavy water; leak testing of the complete reactor system.

Refurbishment of the regulating and control equipment, Task 3.08/04-05; Zadatak 3.08/04-05 Remont uredjaja za regulaciju i upravljanje

Energy Technology Data Exchange (ETDEWEB)

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

1963-12-15

In addition to the planned refurbishment and maintenance of the RA reactor control and regulating systems, this report describes the maintenance of the reactor protection and safety systems. According to the instructions included in this report the components of these systems were tested to verify their reliability.

Synthesis of the studies on fuels and transmutation targets (fabrication, design, irradiation damage and dissolution) realized in the framework of the Bataille law

International Nuclear Information System (INIS)

Pillon, S.

2004-12-01

This document presents the different studied fuels and targets for the transmutation of the minor actinides and of the long life fission products for PWR/EPR and Fast neutron Reactor/EFR of today technology; the results of studies on the behavior under ions irradiation and in experimental nuclear reactor; the knowledge in terms of design, simulation and sizing; the development in terms of fabrication; the knowledge on the dissolution aptitude of these fuels and targets. (A.L.B.)

Double-shell inertial confinement fusion target fabrication

International Nuclear Information System (INIS)

Hatcher, C.W.; Lorensen, L.E.; Weinstein, B.W.

1980-01-01

First generation hemishells, from which spherical shells are constructed, were fabricated by micromachining coated mandrels and by molding. The remachining of coated mandrels are described in detail. Techniques were developed for coating the microsized mandrels with polymeric and metallic materials by methods including conformal coating, vapor deposition, plasma polymerization and thermoforming. Micropositioning equipment and bonding techniques have also been developed to assemble the hemishells about a fuel pellet maintaining a spherical concentricity of better than 2 μm and voids in the hemishell bonding line of a few hundred angstroms or less

Fabrication and evaluation of tumor-targeted positive MRI contrast agent based on ultrasmall MnO nanoparticles.

Science.gov (United States)

Huang, Haitao; Yue, Tao; Xu, Ke; Golzarian, Jafar; Yu, Jiahui; Huang, Jin

2015-07-01

Gd(III) chelate is currently used as positive magnetic resonance imaging (MRI) contrast agent in clinical diagnosis, but generally induces the risk of nephrogenic systemic fibrosis (NSF) due to the dissociated Gd(3+) from Gd(III) chelates. To develop a novel positive MRI contrast agent with low toxicity and high sensitivity, ultrasmall MnO nanoparticles were PEGylated via catechol-Mn chelation and conjugated with cRGD as active targeting function to tumor. Particularly, the MnO nanoparticles with a size of ca. 5nm were modified by α,β-poly(aspartic acid)-based graft polymer containing PEG and DOPA moieties and, meanwhile, conjugated with cRGD to produce the contrast agent with a size of ca. 100nm and a longitudinal relaxivity (r1) of 10.2mM(-1)S(-1). Such nanoscaled contrast agent integrated passive- and active-targeting function to tumor, and its efficient accumulation behavior in tumor was verified by in vivo distribution study. At the same time, the PEG moiety played a role of hydrophilic coating to improve the biocompatibility and stability under storing and physiological conditions, and especially might guarantee enough circulation time in blood. Moreover, in vivo MRI revealed a good and long-term effect of enhancing MRI signal for as-fabricated contrast agent while cell viability assay proved its acceptable cytotoxicity for MRI application. On the whole, the as-fabricated PEGylated and cRGD-functionalized contrast agent based on ultrasmall MnO nanoparticles showed a great potential to the T1-weighted MRI diagnosis of tumor. Crown Copyright © 2015. Published by Elsevier B.V. All rights reserved.

A containment analysis for SBLOCA in the refurbished Wolsong-1 Nuclear Power Plant

International Nuclear Information System (INIS)

Kim, Tech-Mo; Park, Jong-Ho

2011-01-01

Highlights: → The CANDU safety analysis has been accomplished for the refurbished Wolsong-1 NPP. → GOTHIC and SMART-IST codes and new methodology are used for the containment analysis. → The parametric studies for Iodine Chemistry (IMOD-2) model are performed. → And, IMOD-2 model is very sensitive to paint thickness and dousing water pH. → The radioactive doses to the public in SBLOCA event are far below the acceptable limits. - Abstract: A small break leading to a loss of coolant accident (SBLOCA), being one of the topic accidents in the nuclear plant diagnosis in recent years, has been analysed and evaluated for the refurbished Wolsong-1 Nuclear Power Plant (NPP). The Industry Standard Toolset (IST) codes developed by CANDU (Canadian Deuterium Uranium reactor) Owners Group and updated models including design change parameters are applied newly to the event analyses. The GOTHIC code has been used for the containment thermal-hydraulic analysis of Wolsong-1. Also, the SMART-IST code fitted in the Iodine Chemistry (IMOD-2) model has been used to predict nuclide behavior within the containment considering various aspects. The IMOD-2 was incorporated into SMART-IST as a module dealing with chemical transformations and mass transfer of iodine species in containment. IMOD-2 model is very sensitive to paint and chemicals. The parametric studies for the IMOD-2 model are performed to decide the analysis value set. The iodine release amount increases as the paint thickness increases. But, the iodine release amount increases as the water pH (dousing and primary heat transport (PHT)) decreases. The developed containment analysis methodology and the results of SBLOCA without Emergency Coolant Injection (ECI) are presented herein. Under the most heat-up conditions, the radionuclide release from the failed fuel into the containment and subsequently to the environment is such that the radioactive doses to the public are below the acceptable limits.

Inertial confinement fusion target component fabrication and technology development support. Annual report, October 1, 1994--September 30, 1995

International Nuclear Information System (INIS)

Hoppe, M.

1996-05-01

On December 30, 1990, the US Department of Energy entered into a contract with General Atomics (GA) to be the Inertial Confinement Fusion (ICF) Target Component Fabrication and Technology Development Support contractor. This report documents the technical activities of the period October 1, 1994 through September 30, 1995. During this period, GA was assigned 15 tasks in support of the Inertial Confinement Fusion program and its laboratories. A portion of the effort on these tasks included providing direct ''Onsite Support'' at Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), and Sandia National Laboratory Albuquerque (SNLA). The ICF program is anticipating experiments at the National Ignition Facility (NIF) and the OMEGA Upgrade. Both facilities will require capsules containing layered D 2 or deuterium-tritium (D-T) fuel. The authors are part of the National Cryogenic Target Program to create and demonstrate viable ways to generate and characterize cryogenic layers. Progress has been made on ways to both create viable layers and to characterize them. They continued engineering, assembly and testing of equipment for a cryogenic target handling system for University of Rochester's Laboratory for Laser Energetics (UR/LLE) that will fill, transport, layer, and characterize targets filled with cryogenic fuel, and insert these cryogenic targets into the OMEGA Upgrade target chamber for laser implosion experiments. This report summarizes and documents the technical progress made on these tasks

Inertial confinement fusion target component fabrication and technology development support. Annual report, October 1, 1994--September 30, 1995

Energy Technology Data Exchange (ETDEWEB)

Hoppe, M. [ed.

1996-05-01

On December 30, 1990, the US Department of Energy entered into a contract with General Atomics (GA) to be the Inertial Confinement Fusion (ICF) Target Component Fabrication and Technology Development Support contractor. This report documents the technical activities of the period October 1, 1994 through September 30, 1995. During this period, GA was assigned 15 tasks in support of the Inertial Confinement Fusion program and its laboratories. A portion of the effort on these tasks included providing direct ``Onsite Support`` at Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), and Sandia National Laboratory Albuquerque (SNLA). The ICF program is anticipating experiments at the National Ignition Facility (NIF) and the OMEGA Upgrade. Both facilities will require capsules containing layered D{sub 2} or deuterium-tritium (D-T) fuel. The authors are part of the National Cryogenic Target Program to create and demonstrate viable ways to generate and characterize cryogenic layers. Progress has been made on ways to both create viable layers and to characterize them. They continued engineering, assembly and testing of equipment for a cryogenic target handling system for University of Rochester`s Laboratory for Laser Energetics (UR/LLE) that will fill, transport, layer, and characterize targets filled with cryogenic fuel, and insert these cryogenic targets into the OMEGA Upgrade target chamber for laser implosion experiments. This report summarizes and documents the technical progress made on these tasks.

Current status of operation, utilization and refurbishment of the Dalat nuclear research reactor

International Nuclear Information System (INIS)

Pham Duy Hien.

1993-01-01

The reconstructed nuclear research reactor at Dalat, Vietnam has been put into operation since March 1984. Up to present a cumulative operation time of 13,172 hrs at nominal power (500 kW) has been recorded. Production of radioisotopes for medical uses, element analysis by using activation techniques, as well as fundamental and applied research with filtered neutrons are the main activities of reactor utilizations. The problems facing Dalat Nuclear Research Institute are the ageing of the re-used TRIGA-MARK-II reactor components (especially the corrosion of the reactor tank), as well as the obsolescence of many equipment and components of the reactor control and instrumentation system. Refurbishment works are being in process with the technical and financial supports from the Vietnam government and the IAEA. (author). 7 refs, 2 tabs, 10 figs

Refurbishment, core conversion and safety analysis of Apsara reactor

Energy Technology Data Exchange (ETDEWEB)

Raina, V.K.; Sasidharan, K.; Sengupta, S. [Bhabha Atomic Research Centre, Mumbai (India)]. E-mail: nram@@apsara.barc.ernet.in

1998-07-01

Apsara, a 1 MWt pool type reactor using HEU fuel has been in operation at the Bhabha Atomic Research Centre, Trombay since 1956. In view of the long service period seen by the reactor it is now planned to carry out extensive refurbishment of the reactor with a view to extend its useful life. It is also proposed to modify the design of the reactor wherein the core will be surrounded by a heavy water reflector tank to obtain a good thermal neutron flux over a large radial distance from the core. Beam holes and the majority of the irradiation facilities will be located inside the reflector tank. The coolant flow direction through the core will be changed from the existing upward flow to downward flow. A delay tank, located inside the pool, is provided to facilitate decay of short lived radioactivity in the coolant outlet from the core in order to bring down radiation field in the operating areas. Analysis of various anticipated operational occurrences and accident conditions like loss of normal power, core coolant flow bypass, fuel channel blockage and degradation of primary coolant pressure boundary have been performed for the proposed design. Details of the proposed design modifications and the safety analyses are given in the paper. (author)

Fabrication of targets for transmutation of americium : synthesis of inertial matrix by sol-gel method. Procedure study on the infiltration of a radioactive solutions

International Nuclear Information System (INIS)

Fernandez Carretero, A.

2002-01-01

Transmutation and incineration are innovative options in the management and disposal of fission products and actinides. nevertheless, the fabrication of targets for transmutation and incineration of actinides and fission products require a reconsideration of conventional processes (mechanical blending) and the development of new procedures compatible with the high activity of these materials. This work presents th R and D of a new fabrication method called INRAM (Infiltration of Radioactive Materials) based on the infiltration of an actinide solution in a porous non radiotoxic material in the form of a pellet (up to 12% An), or beads (up to 40% An) produced by sol-gel. The first method have been used for the fabrication of spinel (MgAl 2 O 4 ) targets containing 11% Am, which have been irradiated in HFR-Petten (358.4 full power days). Post-test burn-up calculations showed that at the end of the irradiation the initial Am-241 concentration was reduced to 4%. The fraction of the initial americum atoms that have been fissioned is 28%. The main advantage of the INRAM method is that matrices with low or zero activity can be fabricated and formed into the required shape in an unshielded facility. This method offers other advantages over conventional ones, such as the active wastes are reduced, is easy to automate, adoptable to telemanipulation and dust free, which facilitate operator intervention and minimise radiation exposure to the personal. In addition, the infiltrant needs only be present in liquid form, i. e. it could be transferred directly from the reprocessing plant for fabrication into targets without conversion into-solid form. In order to optimise the infiltration process in depth investigations of all important process parameters, e. g. infiltration kinetics and metal (pu, Am) concentration in the feed solution, and also on extensive study or powder metallurgy parameters for the preparation of high quality fuel pellets with a high density, have been made. In

Indium oxide co-doped with tin and zinc: A simple route to highly conducting high density targets for TCO thin-film fabrication

Science.gov (United States)

Saadeddin, I.; Hilal, H. S.; Decourt, R.; Campet, G.; Pecquenard, B.

2012-07-01

Indium oxide co-doped with tin and zinc (ITZO) ceramics have been successfully prepared by direct sintering of the powders mixture at 1300 °C. This allowed us to easily fabricate large highly dense target suitable for sputtering transparent conducting oxide (TCO) films, without using any cold or hot pressing techniques. Hence, the optimized ITZO ceramic reaches a high relative bulk density (˜ 92% of In2O3 theoretical density) and higher than the well-known indium oxide doped with tin (ITO) prepared under similar conditions. All X-ray diagrams obtained for ITZO ceramics confirms a bixbyte structure typical for In2O3 only. This indicates a higher solubility limit of Sn and Zn when they are co-doped into In2O3 forming a solid-solution. A very low value of electrical resistivity is obtained for [In2O3:Sn0.10]:Zn0.10 (1.7 × 10-3 Ω cm, lower than ITO counterpart) which could be fabricated to high dense ceramic target suing pressure-less sintering.

Modernization and Refurbishment of the RECH-1 Reactor

Energy Technology Data Exchange (ETDEWEB)

Daie, J. [Nuclear Application Department, Chilean Nuclear Energy Commission (CCHEN), Santiago (Chile)

2014-08-15

The Chilean Nuclear Energy Commission (Comisión Chilena de Energía Nuclear, or CCHEN) has operated the RECH-1 research reactor since 1974. This reactor is located at La Reina Nuclear Centre in Santiago, Chile. It is a pool type reactor using LEU MTR fuel assemblies, light water as moderator and coolant, and beryllium as reflector. The reactor has been operated at the nominal power of 5 MW in a continuous shift of 20 hours per week, 48 weeks per year. The main utilizations of the RECH-1 reactor are radioisotope production and neutron activation analysis. Among the most relevant refurbishment and modernization campaigns undertaken at the reactor are: full core conversion to the use of LEU fuel, replacement of the cooling tower, improvement of the containment building by changing the doors and gates and by a better sealant for the penetrations, introduction of an additional source of water by connecting the raw water supply system to the emergency cooling system, improvement of the emergency ventilation system, introduction of a fire detection and alarm system for detection and mitigation to protect the I&C racks, introduction of a radioactive liquid release for those generated at the reactor, introduction of a delay tank degasification system and renewal of the environmental monitoring system. At present we are assessing the possibility of replacing the old analog electronics of control for new digital systems. Detailed descriptions of these diverse activities are presented in the paper. (author)

Scout house in Koeniz - Refurbishment of the heating system; Pfadiheim Weiermatt, Sanierung Waermeversorgung - Schlussbericht

Energy Technology Data Exchange (ETDEWEB)

Messerli, A. [Neuenschwander - Neutair AG, Berne (Switzerland); Jenni, H. [Heimverein Falkenstein, Koeniz (Switzerland)

2004-07-01

This final report for the Swiss Federal Office of Energy (SFOE) presents the results of a project carried out in Koeniz, Switzerland. The report examines how the energy situation at the local scout house was improved. The work included the refurbishment of the heating system using solar collectors, intelligently controlled heat pumps, a photovoltaics installation and even solar-powered street lighting. The project, which received a substantial echo from the general public, is described. The scouts were directly involved in the project and, in part, in the construction work. This, according to the authors, enhanced the educational aspect of the project. The report presents details on the various installations and is illustrated with schematics and photos. Also, the results of monitoring and measurements made are presented.

Task 3.08/04-04, refurbishment of the dosimetry control equipment; Zadatak 3.08/04-04 Remont uredjaja dozimetrijske kontrole

Energy Technology Data Exchange (ETDEWEB)

Nikolic, M; Milosevic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

1963-12-15

During three years of operation the designed RA dosimetry system showed satisfactory performance. During the period planned for maintenance and refurbishment of the RA reactor the functionality of the dosimetry system was tested and verified, the components were cleaned and calibrated. The system was operated for 24 hours for testing the reliability of components and whole system. This report describes detailed instructions and actions performed for these activities.

Fabrication of high specificity hollow mesoporous silica nanoparticles assisted by Eudragit for targeted drug delivery.

Science.gov (United States)

She, Xiaodong; Chen, Lijue; Velleman, Leonora; Li, Chengpeng; Zhu, Haijin; He, Canzhong; Wang, Tao; Shigdar, Sarah; Duan, Wei; Kong, Lingxue

2015-05-01

Hollow mesoporous silica nanoparticles (HMSNs) are one of the most promising carriers for effective drug delivery due to their large surface area, high volume for drug loading and excellent biocompatibility. However, the non-ionic surfactant templated HMSNs often have a broad size distribution and a defective mesoporous structure because of the difficulties involved in controlling the formation and organization of micelles for the growth of silica framework. In this paper, a novel "Eudragit assisted" strategy has been developed to fabricate HMSNs by utilising the Eudragit nanoparticles as cores and to assist in the self-assembly of micelle organisation. Highly dispersed mesoporous silica spheres with intact hollow interiors and through pores on the shell were fabricated. The HMSNs have a high surface area (670 m(2)/g), small diameter (120 nm) and uniform pore size (2.5 nm) that facilitated the effective encapsulation of 5-fluorouracil within HMSNs, achieving a high loading capacity of 194.5 mg(5-FU)/g(HMSNs). The HMSNs were non-cytotoxic to colorectal cancer cells SW480 and can be bioconjugated with Epidermal Growth Factor (EGF) for efficient and specific cell internalization. The high specificity and excellent targeting performance of EGF grafted HMSNs have demonstrated that they can become potential intracellular drug delivery vehicles for colorectal cancers via EGF-EGFR interaction. Copyright © 2014 Elsevier Inc. All rights reserved.

Technological energy and environmental refurbishment of historical Italian libraries

Directory of Open Access Journals (Sweden)

Alessandra Battisti

2014-10-01

Full Text Available Active libraries in Italy are around 13.000 and, taken as a whole, the property and management relate mainly to public institutions such as the state, regions, local authorities, cultural institutions, universities, and partly to religious institutions and individuals. In this paper is presented the work of studies and research, commissioned to the authors by the General Direction for Libraries of the Ministry of Heritage and Culture (Mibac, which ended recently, addressing the architectural, energy and environmental refurbishment of national historic libraries distributed on the Italian territory, with special focus on 4 among 46 owned by the Ministry of Culture (the Nazionale Centrale di Roma, the Nazionale Centrale in Florence, the national University of Turin and the Angelica in Rome believed by the authors and client as examples of recurring issues and ideals to lend itself to the construction of a model of intervention replicable on other historical Italian libraries.The main objective of the project is the identification of physical and perceptual factors of wear2, which threaten the conservation of the historical and artistic heritage of the historic center of Venice, with a particular focus on the effects of anthropogenic pressure linked to tourism, and the evaluation of their level of danger. A further objective is the recognition of measurable parameters (indicators for monitoring and, subsequently, mitigation strategies for the most significant phenomena.

Major Refurbishment of the University of Florida Training Reactor

International Nuclear Information System (INIS)

Joradn, Kelly; Berglund, Matthew; Shea, Brian

2013-01-01

The research reactor fleet is aging with few replacements being built. At the same time the technology for refurbishment of the older reactors has advanced well beyond that of currently installed equipment. The disparity between new and old technology results in an inability to find simple replacements for the older, highly integrated components. The lack of comprehensive guidance for digital equipment adds to the technical problems of installing individual replacement parts. Up to this point, no U. S. facilities have attempted a complete modernization effort because of the time commitment, financial burden, and licensing required for a total upgrade. The University of Florida Training Reactor is tackling this problem with a replacement of nearly all of the major facility sub-systems, including electrical distribution, reactor controls, nuclear instrumentation, security, building management, and environmental controls. This approach offers increased flexibility over the piece-by-piece replacement method by leveraging modern control systems based on global standards and capable of good data interchange with higher levels of redundancy. The UFTR reviewed numerous technologies to arrive at the final system architecture and this 'clean-slate' installation methodology. It is this concept of total system replacement and strict use of modular, open-standards technology that has allowed for a facility design that will be easy to install, maintain, and build upon over time

Major Refurbishment of the University of Florida Training Reactor

Energy Technology Data Exchange (ETDEWEB)

Joradn, Kelly; Berglund, Matthew; Shea, Brian [Univ., of Florida, Florida (United States)

2013-07-01

The research reactor fleet is aging with few replacements being built. At the same time the technology for refurbishment of the older reactors has advanced well beyond that of currently installed equipment. The disparity between new and old technology results in an inability to find simple replacements for the older, highly integrated components. The lack of comprehensive guidance for digital equipment adds to the technical problems of installing individual replacement parts. Up to this point, no U. S. facilities have attempted a complete modernization effort because of the time commitment, financial burden, and licensing required for a total upgrade. The University of Florida Training Reactor is tackling this problem with a replacement of nearly all of the major facility sub-systems, including electrical distribution, reactor controls, nuclear instrumentation, security, building management, and environmental controls. This approach offers increased flexibility over the piece-by-piece replacement method by leveraging modern control systems based on global standards and capable of good data interchange with higher levels of redundancy. The UFTR reviewed numerous technologies to arrive at the final system architecture and this 'clean-slate' installation methodology. It is this concept of total system replacement and strict use of modular, open-standards technology that has allowed for a facility design that will be easy to install, maintain, and build upon over time.

Rapid fabrication and characterization of sine wave targets

International Nuclear Information System (INIS)

Day, R.D.; Armijo, E.; Gobby, P.; Hatch, D.; Rivera, G.; Salzer, L.; Townsend, J.

1997-01-01

The effect of surface perturbations on Inertial Confinement Fusion target performance is currently being researched at Los Alamos National Laboratory (LANL). These perturbations can cause hydrodynamic instabilities which in turn reduce the targets' yield. To systematically measure the growth of these instabilities requires targets to be produced which have perturbations of a known amplitude and spatial frequency. The authors have recently assembled hardware onto one of their diamond turning lathes which enables them to machine and measure these sine waves in about 15 minutes. This is a significant reduction in time from the two and one half hours required by the previous method. This paper discusses the hardware, how it works, and how well the system is working for them to produce these targets

Case study of a not-so-ordinary building - the Cowra Shire administration building ESD refurbishment

Energy Technology Data Exchange (ETDEWEB)

Halperin, M.; Arch, B. [Mahalath Halperin Architects Pty Ltd., Armidale (Australia). RAIA Country Division

2004-07-01

In refurbishing the Cowra Administration Building, Mahalath Halperin Architects transformed a concrete and glass building of the 1960s into an energy efficient and environmentally responsible building, yet looks to all intents and purposes like an 'ordinary building'. To some, it is simply a newer, nicer building with bright colours, open spaces and a pleasant work environment. But whilst not necessarily being outwardly different in issues of being a 'green building', the resultant building shows that there are many small yet easily achievable ways to be green. That it is not hard, and is in fact beneficial, to reduce energy consumption and overheads, take advantage of the sun (despite its poor orientation) and take on environmental responsibility. (orig.)

Performance evaluation of operational energy use in refurbishment, reuse, and conservation of heritage buildings for optimum sustainability

Directory of Open Access Journals (Sweden)

O.K. Akande

2016-09-01

Full Text Available The operational phase of a building project has increasingly gained importance with their energy performance becoming valuable and determining their operational excellence. In most heritage building projects (HBPs, the operational energy use aspects are less considered, and a systematic way of analyzing their energy performance following project delivery is often lacking. The aim of this study is to evaluate the operational performance of refurbishment and reuse of UK listed church projects. The objective is to assess the operational energy use with a view to optimizing their sustainable performance. The methodology includes eight selected case study buildings refurbished and converted for multipurpose use. The case study approach provided qualitative insights into how the study contributes to a more structured requirements for energy management in HBPs with specific attention to energy-efficient building operations. The findings show the need to focus on fundamental areas of operational management (i.e. by developing and implementing more focused policy on operational energy performance of heritage buildings to minimize the energy required to operate them. The challenges of implementing changes in operational energy performance improvement of heritage buildings are addressed in the form of recommendations that could lead to real results. The study concludes that leveraging these areas requires commitment from all heritage building stakeholders because they all have substantial roles in harmonizing the requirement for the project׳s sustainability and not just the building operators. Meanwhile, baseline project planning, periodic updating, monitoring, and managing the energy use pattern are suggested as measures that could greatly facilitate better energy performance to optimizing their sustainable reuse compared with the traditional approach of trying to improve their thermal performance.

Materials considerations in accelerator targets

International Nuclear Information System (INIS)

Peacock, H.B. Jr.; Iyer, N.C.; Louthan, M.R. Jr.

1994-01-01

Future nuclear materials production and/or the burn-up of long lived radioisotopes may be accomplished through the capture of spallation produced neutrons in accelerators. Aluminum clad-lead and/or lead alloys has been proposed as a spallation target. Aluminum was the cladding choice because of the low neutron absorption cross section, fast radioactivity decay, high thermal conductivity, and excellent fabricability. Metallic lead and lead oxide powders were considered for the target core with the fabrication options being casting or powder metallurgy (PM). Scoping tests to evaluate gravity casting, squeeze casting, and casting and swaging processes showed that, based on fabricability and heat transfer considerations, squeeze casting was the preferred option for manufacture of targets with initial core cladding contact. Thousands of aluminum clad aluminum-lithium alloy core targets and control rods for tritium production have been fabricated by coextrusion processes and successfully irradiated in the SRS reactors. Tritium retention in, and release from the coextruded product was modeled from experimental and operational data. Newly produced tritium atoms were trapped by lithium atoms to form a lithium tritide. The effective tritium pressure required for trap or tritide stability was the equilibrium decomposition pressure of tritium over a lithium tritide-aluminum mixture. The temperature dependence of tritium release was determined by the permeability of the cladding to tritium and the local equilibrium at the trap sites. The model can be used to calculate tritium release from aluminum clad, aluminum-lithium alloy targets during postulated accelerator operational and accident conditions. This paper describes the manufacturing technologies evaluated and presents the model for tritium retention in aluminum clad, aluminum-lithium alloy tritium production targets

Autonomous Rover Traverse and Precise Arm Placement on Remotely Designated Targets

Science.gov (United States)

Felder, Michael; Nesnas, Issa A.; Pivtoraiko, Mihail; Kelly, Alonzo; Volpe, Richard

2011-01-01

Exploring planetary surfaces typically involves traversing challenging and unknown terrain and acquiring in-situ measurements at designated locations using arm-mounted instruments. We present field results for a new implementation of an autonomous capability that enables a rover to traverse and precisely place an arm-mounted instrument on remote targets. Using point-and-click mouse commands, a scientist designates targets in the initial imagery acquired from the rover's mast cameras. The rover then autonomously traverse the rocky terrain for a distance of 10 - 15 m, tracks the target(s) of interest during the traverse, positions itself for approaching the target, and then precisely places an arm-mounted instrument within 2-3 cm from the originally designated target. The rover proceeds to acquire science measurements with the instrument. This work advances what has been previously developed and integrated on the Mars Exploration Rovers by using algorithms that are capable of traversing more rock-dense terrains, enabling tight thread-the-needle maneuvers. We integrated these algorithms on the newly refurbished Athena Mars research rover and fielded them in the JPL Mars Yard. We conducted 43 runs with targets at distances ranging from 5 m to 15 m and achieved a success rate of 93% for placement of the instrument within 2-3 cm.

The Plasma-Facing Components Transporter (PFCT) : a Prototype System for PFC Replacement on the new ITER 2001 Cassette Mock-up

International Nuclear Information System (INIS)

Micciche, G.; Lorenzelli, L.; Muro, L.; Irving, M.

2006-01-01

The remote maintainability of the early ITER divertor cassette (based on the ITER 1998 design) was successfully proved during test campaigns carried out in the Divertor Refurbishment Platform (DRP) at the ENEA research centre at Brasimone over the period 1999-2003. Due to subsequent major modifications in the ITER divertor cassette design, the main focus over the past few years has been on the design and manufacture of the various components, devices and tools needed for refurbishment of the new ITER 2001 Divertor Cassette. The design of this new cassette differs substantially from the earlier version: in particular the shape, weight and attachment system of the Plasma Facing Components (PFC's) has been completely revised, and this also entailed a review of the procedures adopted for its refurbishment. One of the major requirements of the cassette refurbishment process is removal and replacement of the three PFC's. In the old cassette concept, target replacement was performed by means of a purpose-built '' C '' frame slung from a standard bridge crane. The 2001 cassette design precludes such handling methods for a number of reasons, notably because of the extremely tight inter-PFC clearances, and the need for controlled inclination of the target in addition to normal translational movements, both impossible with a simple Cartesian crane. To demonstrate the refurbishment feasibility operations for the new ITER Divertor 2001 cassettes, an experimental machine known as the Plasma-Facing Component Transporter (PFCT) has been designed, fabricated and commissioned in the years 2004-5. This full six degree-of-freedom system has been designed to handle payloads of up to 5 tonnes with good positional accuracy, and axes capable of very low joint velocities, including inclination of the PFC's over the range of ± 10 o in both horizontal axes, and controlled rotation about the vertical axis. Preliminary trials carried out during the commissioning phase have proved its

Start-up of Cirus after refurbishment outage and observations during approach to criticality

International Nuclear Information System (INIS)

Singh, Tej; Singh, Kanchhi; Sengupta, S.N.

2004-10-01

The report presents various physics related aspects of the startup of Cirus reactor after the prolonged refurbishment outage. The special nuclear instrumentation scheme adopted to ensure safe startup of the reactor is described. Salient observations made and physics measurements carried out during various approaches to criticality are covered. One of the significant observations concerned a major reactivity anomaly during the approach to criticality. After due investigations the cause of the anomaly was attributed to the inadvertent wetting of the graphite reflector which houses the reactor regulating and protection system ion chambers. The report also includes salient observations during raising of reactor power to high levels. The wet reflector also resulted in a significant difference measured between the thermal and neutronic power of the reactor. In view of the reactivity anomaly, the core reactivity variation with time was closely followed and compared with computations. As expected the reactivity anomaly reduced gradually with time. (author)

Saving money on rig refurbishments through foreign trade zones or duty-drawback

International Nuclear Information System (INIS)

Ward, R.J. Jr.

1997-01-01

The recent boom in day rates for rigs capable of drilling in deep water and harsh environments has created a frenzy of rig refurbishment activity in shipyards located in US Gulf states. In most instances, the destination for the rigs upon completion is the US Outer Continental Shelf (USOCS) in the Gulf of Mexico. The problem faced by contractors/operators planning to use US shipyards is that this circumstance has caused difficulty in shielding rigs and their foreign-sourced components from US Customs duties. Under US Customs law, a bona fide exportation requires severance from US commerce and joining to the commerce of some foreign country or, in the case of a vessel supply, a qualifying international voyage. The USOCS does not qualify as an exportation, nor do movements to drilling sites located on it qualify as an international voyage. Described here are two possible solutions to this economic dilemma and an example of how the foreign trade zone solution was applied by Global marine in its plans for upgrading some of its semisubmersible drilling rigs for deepwater USOCS work

Effect of positively charged particles on sputtering damage of organic electro-luminescent diodes with Mg:Ag alloy electrodes fabricated by facing target sputtering

Directory of Open Access Journals (Sweden)

Kouji Suemori

2017-04-01

Full Text Available We investigated the influence of the positively charged particles generated during sputtering on the performances of organic light-emitting diodes (OLEDs with Mg:Ag alloy electrodes fabricated by sputtering. The number of positively charged particles increased by several orders of magnitude when the target current was increased from 0.1 A to 2.5 A. When a high target current was used, many positively charged particles with energies higher than the bond energy of single C–C bonds, which are typically found in organic molecules, were generated. In this situation, we observed serious OLED performance degradation. On the other hand, when a low target current was used, OLED performance degradation was not observed when the number of positively charged particles colliding with the organic underlayer increased. We concluded that sputtering damage caused by positively charged particles can be avoided by using a low target current.

Advanced fuel fabrication

International Nuclear Information System (INIS)

Bernard, H.

1989-01-01

This paper deals with the fabrication of advanced fuels, such as mixed oxides for Pressurized Water Reactors or mixed nitrides for Fast Breeder Reactors. Although an extensive production experience exists for the mixed oxides used in the FBR, important work is still needed to improve the theoretical and technical knowledge of the production route which will be introduced in the future European facility, named Melox, at Marcoule. Recently, the feasibility of nitride fuel fabrication in existing commercial oxide facilities was demonstrated in France. The process, based on carbothermic reduction of oxides with subsequent comminution of the reaction product, cold pressing and sintering provides (U, Pu)N pellets with characteristics suitable for irradiation testing. Two experiments named NIMPHE 1 and 2 fabricated in collaboration with ITU, Karlsruhe, involve 16 nitride and 2 carbide pins, operating at a linear power of 45 and 73 kW/m with a smear density of 75-80% TD and a high burn-up target of 15 at%. These experiments are currently being irradiated in Phenix, at Marcoule. (orig.)

Development of a coating technique for inertial confinement fusion plastic targets

International Nuclear Information System (INIS)

Kubo, U.; Tsubakihara, H.

1986-01-01

Deuterated polystyrene as a target material offers several advantages over other polymers because of the following: (1) it is chemically and physically stable at ordinary conditions, (2) it can be easily formed into spherical shells, and (3) it has a very high fraction of D 2 /H 2 (above approx.99%). As in our previous studies, the fabrication method was basically a utilization of the emulsion technique. This method is well suited to mass-producing the polymer targets without microprocessing techniques. We have developed a fabrication method for single shell targets and an extension of this technique also enables us to fabricate double shell targets. This new method is faster and less labor intensive than previous techniques. The development of ICF experiments requires multilayer structure targets; we have developed, moreover, a new fabrication technique called the multicoating method. The polymer coating can be fabricated by the application of an emulsion technique. On the other hand, with metal coating, a nonelectroplating method was used, and nickel was employed as the coating metal. The thickness of the polymer coating layer can be controlled with the rotational speed of a stirrer in the emulsion. In the case of nickel coating, it is achieved by controlling the plating bath temperature and immersion time during the plating process. The experiment resulted in the development of a new technique for the fabrication of multilayer targets and low density, thick polymer-layer-coated targets

Main refurbishment activities on electronic and electrical equipment for the FRG-1 research reactor

International Nuclear Information System (INIS)

Blom, K.H.; Krull, W.

1997-01-01

As GKSS intends to operate the research reactor FRG-1 safely and reliably for many years to come, the plant is constantly refurbished and upgraded both in the interests of safety and operational reasons. The following electronic and electrical systems have been replaced or improved since 1990: Information and signalling systems; Emergency power plant (permit applied for); External and internal lightning protection system; Reactor protection system (in part); Safety lighting; Alarm and staff locating system; Control room telephone system; Closed-circuit television system; Beam tube controls; Storage plant for radioactive liquid waste; Ambient dose rate measuring system; Meteorological measuring system; Control and measuring system for the primary cooling circuit; Control rod drives; Control rod control system; Soft start for the secondary pumps; Control and switching devices for the emergency power plant; Trailing cable installation for the reactor bridge; Main-voltage distribution systems/cable routes. (author). 13 figs, 1 tab

Fabrication and calibration of FORTIS

Science.gov (United States)

Fleming, Brian T.; McCandliss, Stephan R.; Kaiser, Mary Elizabeth; Kruk, Jeffery; Feldman, Paul D.; Kutyrev, Alexander S.; Li, Mary J.; Rapchun, David A.; Lyness, Eric; Moseley, S. H.; Siegmund, Oswald; Vallerga, John; Martin, Adrian

2011-09-01

The Johns Hopkins University sounding rocket group is entering the final fabrication phase of the Far-ultraviolet Off Rowland-circle Telescope for Imaging and Spectroscopy (FORTIS); a sounding rocket borne multi-object spectro-telescope designed to provide spectral coverage of 43 separate targets in the 900 - 1800 Angstrom bandpass over a 30' x 30' field-of- view. Using "on-the-fly" target acquisition and spectral multiplexing enabled by a GSFC microshutter array, FORTIS will be capable of observing the brightest regions in the far-UV of nearby low redshift (z ~ 0.002 - 0.02) star forming galaxies to search for Lyman alpha escape, and to measure the local gas-to-dust ratio. A large area (~ 45 mm x 170 mm) microchannel plate detector built by Sensor Sciences provides an imaging channel for targeting flanked by two redundant spectral outrigger channels. The grating is ruled directly onto the secondary mirror to increase efficiency. In this paper, we discuss the recent progress made in the development and fabrication of FORTIS, as well as the results of early calibration and characterization of our hardware, including mirror/grating measurements, detector performance, and early operational tests of the microshutter arrays.

Target technologies for laser inertial confinement fusion: state-of-the-art and future perspective

International Nuclear Information System (INIS)

Zhang Lin; Du Kai

2013-01-01

Targets are physical base of the laser inertial confinement fusion (ICF) researches. The quality of the targets has extremely important influences on the reliabilities and degree of precision of the ICF experimental results. The characteristics of the ICF targets, such as complexity and microscale, high precision, determine that the target fabrication process must be a system engineering. This paper presents progresses on the fabrication technologies of ICF targets. The existing problem and the future needs of ICF target fabrication technologies are also discussed. (authors)

Acidic aqueous uranium electrodeposition for target fabrication

International Nuclear Information System (INIS)

Saliba-Silva, A.M.; Oliveira, E.T.; Garcia, R.H.L.; Durazzo, M.

2013-01-01

Direct irradiation of targets inside nuclear research or multiple purpose reactors is a common route to produce 99 Mo- 99m Tc radioisotopes. The electroplating of low enriched uranium over nickel substrate might be a potential alternative to produce targets of 235 U. The electrochemistry of uranium at low temperature might be beneficial for an alternative route to produce 99 Mo irradiation LEU targets. Electrodeposition of uranium can be made using ionic and aqueous solutions producing uranium oxide deposits. The performance of uranium electrodeposition is relatively low because a big competition with H 2 evolution happens inside the window of electrochemical reduction potential. This work explores possibilities of electroplating uranium as UO 2 2+ (Uranium-VI) in order to achieve electroplating uranium in a sufficient amount to be commercially irradiated in the future Brazilian RMB reactor. Electroplated nickel substrate was followed by cathodic current electrodeposition from aqueous UO 2 (NO 3 ) 2 solution. EIS tests and modeling showed that a film formed differently in the three tested cathodic potentials. At the lower level, (-1.8V) there was an indication of a double film formation, one overlaying the other with ionic mass diffusion impaired at the interface with nickel substrate as showed by the relatively lower admittance of Warburg component. (author)

Refurbishment and optimisation of the district heating system and the Morettina central heating station in Locarno, Switzerland; Sanierung und Optimierung des Waermeverbundes und der Heizzentrale Morettina in Locarno. Erfolgskontrolle der Betriebsoptimierung

Energy Technology Data Exchange (ETDEWEB)

Lanz, S. [Dr. Eicher und Pauli AG, Berne (Switzerland); Ceschi, P. A. [Calore SA, c/o S.E.S., Locarno (Switzerland)

2004-07-01

This final report for the Swiss Federal Office of Energy (SFOE) discusses the successful operational optimisation of a district heating system in Locarno in southern Switzerland. The system supplies various public and private buildings with heat and cold. This pilot installation features boilers fired with liquefied gas, a combined heat and power unit and a combined heat-pump/refrigeration system. The refurbishment of the installations after three years of operation is described, which included changes to the system's hydraulics and control system as well as improvements to various sub-stations in the heating network. The results of the refurbishment, including better co-ordination of the various aggregates and lower operating temperatures, are discussed. Recommendations are also made on the planning, organisation and operation of future projects of this type.

Clean energy for a new generation. Steam generator life cycle management and Bruce restart

International Nuclear Information System (INIS)

Newman, G.W.

2009-01-01

-existing piping and four common steam drums were inspected, qualified and reattached to the 16 new steam generators. The design and fabrication of these new 'boilers' reflect lessons learned which includes world-wide first generator Alloy 600 challenges. At the core of the new boilers, the proven industry workhorse, Alloy 800 tube material, is being deployed with corresponding best practises within tube alloy specification, tube bundle fabrication and general boiler configuration / fabrication best practises. Coupled with this refined technology is the realization that in-service practises are key to ensuring that this significant investment is preserved and thoughtfully managed over the target 25 year operating life. As part of the larger refurbishment effort, this new technology is bequeathed to our heirs and represents a significant undertaking. With this in mind, recent initiation of an Alloy 800 User Group is viewed as a key initiative to ensure that this significant asset continues to be thoughtfully managed. Beyond Bruce Units 1 and 2, Bruce Power L.P. is involved with industry and provincial agencies regarding the 'next steps.' Refurbishment of the remaining provincial reactors is a critical discussion that is currently underway and Bruce Power L.P. is keenly aware of the responsibility it has to the balance of the industry to continue to provide continued leadership to refurbishment of both the Bruce Power L.P. and balance of the Ontario reactor fleet.

Target fabrication using laser and spark erosion machining

International Nuclear Information System (INIS)

Clement, X.; Coudeville, A.; Eyharts, P.; Perrine , J.P.; Rouillard, R.

1981-11-01

Lasers and E.D.M. (electrical discharge machining) are both extremely useful tools for machining the small targets needed in inertial confinement studies. Lasers are currently used in a wide range of target problems and it appears that E.D.M. has a still wider range of applications for plane and spherical targets. The problems of material deformation and tool breaking are practically eliminated as the electrode and the machined part are not in mechanical contact. In comparison with laser micromachining E.D.M. offers: larger versatility with the possibility of new developments and applications; higher production speed for thin conducting materials; lower initial and operating costs; the processes are well controlled, reproducible and can be easily automated; the operation is safe without the dangers associted with lasers

The NNR requirements to address modification, modernization, refurbishment and ageing management

International Nuclear Information System (INIS)

Thugwane, Samuel

2013-01-01

The National Nuclear Regulator (NNR) is a national competent authority in South African which has been mandated under Act 47 of 1999 to provide for the protection of property people and environment. The NNR achieves its mandated by issuing Nuclear Authorisations in case of Nuclear Installations and Certificate of registration for the mining industry. Currently SAFARI-1 Research Reactor at Pelindaba site is the only Research Reactor that is licensed by NNR through a Process based licensing. SAFARI-1 is a 20 MW research reactor and has been in operation since 1965 and is approaching its full lifetime. Regular, periodic and systematic examination, inspection, maintenance and testing of all plant, systems, structures and components have been developed and implemented. Modification and refurbishment has been implemented over years since its construction. Ageing of structural components and obsolescence is now becoming a challenge; as a result, Ageing Management Programme has been developed to address these issues. In accordance with the NNR requirements any modification that the licensee plan to implement, must comply with NNR approved processes and procedures relating to control of such modification to the design of existing plant, facility or system design, including modifications that may be of a temporary nature

Refurbishment of the Primary Cooling System of the Puspati Triga Reactor

Energy Technology Data Exchange (ETDEWEB)

Ramli, S.; Zakaria, M. F.; Masood, Z. [Malaysian Nuclear Agency, Kajang (Malaysia)

2014-08-15

The refurbishment of the 27 year old primary cooling system of the 1 MW PUSPATI TRIGA reactor was completed in April 2010 over an eight month outage. The project was implemented with the dual objective of meeting current user needs as well as a future reactor core power upgrade. Hence the cooling system was partly modernized to cater for a 3 MW{sub th} reactor by installing higher capacity heat exchangers and pumps while maintaining the piping and valve sizes. The old 1 MW tube and shell heat exchanger, which had lost 25% of its heat exchange capacity, was replaced with two 1.5 MW plate type heat exchangers. Several manually operated valves were replaced with motorized units to allow remote operation from the control room. The installed cooling system was flushed with distilled water and then subjected to hydrostatic pressure tests. In the cold run test, the system was operated for an hour for every pump and heat exchanger combination while all operating parameters were checked. In the hot run test, the same was done at four levels of increasing reactor power, and dose measurements were also recorded. The paper gives the design, installation, testing and commissioning details of the project. (author)

The NNR requirements to address modification, modernization, refurbishment and ageing management

Energy Technology Data Exchange (ETDEWEB)

Thugwane, Samuel [National Nuclear Regulator, Pretoria (South Africa)

2013-07-01

The National Nuclear Regulator (NNR) is a national competent authority in South African which has been mandated under Act 47 of 1999 to provide for the protection of property people and environment. The NNR achieves its mandated by issuing Nuclear Authorisations in case of Nuclear Installations and Certificate of registration for the mining industry. Currently SAFARI-1 Research Reactor at Pelindaba site is the only Research Reactor that is licensed by NNR through a Process based licensing. SAFARI-1 is a 20 MW research reactor and has been in operation since 1965 and is approaching its full lifetime. Regular, periodic and systematic examination, inspection, maintenance and testing of all plant, systems, structures and components have been developed and implemented. Modification and refurbishment has been implemented over years since its construction. Ageing of structural components and obsolescence is now becoming a challenge; as a result, Ageing Management Programme has been developed to address these issues. In accordance with the NNR requirements any modification that the licensee plan to implement, must comply with NNR approved processes and procedures relating to control of such modification to the design of existing plant, facility or system design, including modifications that may be of a temporary nature.

Fabrication of Foam Shells for ICF Experiments

Science.gov (United States)

Czechowicz, D. G.; Acenas, O.; Flowers, J. S.; Nikroo, A.; Paguio, R. R.; Schroen, D. G.; Streit, J.; Takagi, M.

2004-11-01

The General Atomics/Schafer team has developed processes to fabricate foam shells targets suitable for ICF experiments. The two most common chemical systems used to produce foam shells have been resorcinol-formaldehyde (R/F) aerogel and divinylbenzene (DVB). Spherical targets have been made in the form of shells and beads having diameters ranging from approximately 0.5 mm to 4.0 mm, and having densities from approximately 100 mg/cc to 250 mg/cc. The work on R/F foam shells has been concentrated on 1) shell fabrication process improvement to obtain high yields ( ˜25%) and 2) depositing a reliable permeation barrier to provide shells for ongoing direct drive experiments at LLE. Development of divinylbenzene foam shells has been mainly directed towards Inertial Fusion Energy applications (at densities as low as 30 mg/cc) and recently for shells for experiments at LLE. Details of the relevant metrology and properties of these foams as well as the range of targets currently available will be discussed.

Fabrication of inert matrices for heterogeneous transmutation. EFTTRA-T2 (RAS 2) irradiation programme

International Nuclear Information System (INIS)

Boshoven, J.G.; Hein, H.; Konings, R.J.M.

1996-07-01

This report describes the fabrication of targets containing inert matrices for the heterogeneous transmutation of plutonium and minor actinides. These targets will be irradiated in the EFTTRA-T2 (RAS-2) irradiation programme. The selection, preparation and characterization of the inert matrices and fabrication and loading of the irradiation capsules are discussed. (orig.)

Evaluation of magnetostrictive composite coated fabric as a fragment barrier material

International Nuclear Information System (INIS)

Son, Kwon Joong; Fahrenthold, Eric P

2012-01-01

Over the last decade a surge in fragment barrier research has led to investigation of numerous materials and material augmentations in the attempt to improve the ballistic performance of systems designed to protect personnel, vehicles or infrastructure from impact and blast loads. One widely studied material augmentation approach is the use of coatings, often polymers, to enhance the performance of protection systems constructed from metal, concrete, composite and fabric materials. In recent research the authors have conducted the first experimental study of the ballistic performance of fabrics coated with a magnetically responsive polymer. Zero field impact experiments on coated fabric targets showed a 61% increase in impact energy dissipation, although the coated targets were not competitive with neat fabrics on a protection per unit mass basis. Under an applied field of 110 kA m −1 , the ballistic performance of the coated fabric was reduced. The reduction in performance may be attributed to a reduction in material damping and an increase in material modulus for the magnetostrictive component of the coating. Analysis of the coated fabric response to magnetic preloads suggests that coating tensile stresses and coating–fabric interface stresses induced by the applied field may also adversely affect ballistic performance. (paper)

Indoor PM2.5 exposure in London's domestic stock: Modelling current and future exposures following energy efficient refurbishment

Science.gov (United States)

Shrubsole, C.; Ridley, I.; Biddulph, P.; Milner, J.; Vardoulakis, S.; Ucci, M.; Wilkinson, P.; Chalabi, Z.; Davies, M.

2012-12-01

Simulations using CONTAM (a validated multi-zone indoor air quality (IAQ) model) are employed to predict indoor exposure to PM2.5 in London dwellings in both the present day housing stock and the same stock following energy efficient refurbishments to meet greenhouse gas emissions reduction targets for 2050. We modelled interventions that would contribute to the achievement of these targets by reducing the permeability of the dwellings to 3 m3 m-2 h-1 at 50 Pa, combined with the introduction of mechanical ventilation and heat recovery (MVHR) systems. It is assumed that the current mean outdoor PM2.5 concentration of 13 μg m-3 decreased to 9 μg m-3 by 2050 due to emission control policies. Our primary finding was that installation of (assumed perfectly functioning) MVHR systems with permeability reduction are associated with appreciable reductions in PM2.5 exposure in both smoking and non-smoking dwellings. Modelling of the future scenario for non-smoking dwellings show a reduction in annual average indoor exposure to PM2.5 of 18.8 μg m-3 (from 28.4 to 9.6 μg m-3) for a typical household member. Also of interest is that a larger reduction of 42.6 μg m-3 (from 60.5 to 17.9 μg m-3) was shown for members exposed primarily to cooking-related particle emissions in the kitchen (cooks). Reductions in envelope permeability without mechanical ventilation produced increases in indoor PM2.5 concentrations; 5.4 μg m-3 for typical household members and 9.8 μg m-3 for cooks. These estimates of changes in PM2.5 exposure are sensitive to assumptions about occupant behaviour, ventilation system usage and the distributions of input variables (±72% for non-smoking and ±107% in smoking residences). However, if realised, they would result in significant health benefits.

Renewable-based low-temperature district heating for existing buildings in various stages of refurbishment

DEFF Research Database (Denmark)

Brand, Marek; Svendsen, Svend

2013-01-01

Denmark is aiming for a fossil-free heating sector for buildings by 2035. Judging by the national heating plan, this will be achieved mainly by a further spread of DH (district heating) based on the renewable heat sources. To make the most cost-effective use of these sources, the DH supply...... and, for 98% of the year, to below 60 °C. However for the temperatures below 60 °C a low-temperature DH substation is required for DHW (domestic hot water) heating. This research shows that renewable sources of heat can be integrated into the DH system without problems and contribute to the fossil...... temperature should be as low as possible. We used IDA–ICE software to simulate a typical Danish single-family house from the 1970s connected to DH at three different stages of envelope and space heating system refurbishment. We wanted to investigate how low the DH supply temperature can be without reducing...

CACAO facility. Radioactive targets at Orsay

International Nuclear Information System (INIS)

Bacri, C.O.; Petitbon-Thevenet, V.; Mottier, J.; Lefort, H.; Durnez, A.; Fortuna, F.

2014-01-01

CACAO, Chimie des Actinides et Cibles radioActives a Orsay (actinide chemistry and radioactive targets at Orsay), is a new laboratory dedicated to the fabrication and characterization of radioactive targets. It is supported by the radiochemistry group and the stable target service of the IPNO. The recurring needs of physicists working in the nuclear fuel cycle physics and the growing difficulties to obtain radioactive targets elsewhere were the main motivating factors behind the construction of this new laboratory. The first targets of 235,238 U and 232 Th have already been prepared although the full operating licenses still need to be obtained. In this paper, the installation and the equipment of CACAO will be described. An extensive study of a U test target fabricated by the CACAO laboratory has been performed and results are reported here. The different techniques used to characterize the deposit are presented and the outcome is discussed. (author)

Minor Actinide Laboratory at JRC-ITU: Fuel fabrication facility

International Nuclear Information System (INIS)

Fernandez, A.; McGinley, J.; Somers, J.

2008-01-01

The Minor Actinide Laboratory (MA-lab) of the Institute for Transuranium Elements is a unique facility for the fabrication of fuels and targets containing minor actinides (MA). It is of key importance for research on Partitioning and Transmutation in Europe, as it is one of the only dedicated facilities for the fabrication of MA containing materials, either for property measurements or for the production of test pins for irradiation experiments. In this paper a detailed description of the MA-Lab facility and the fabrication processes developed to fabricate fuels and samples containing high content of minor actinides is given. In addition, experience gained and improvements are also outlined. (authors)

Materials considerations in accelerator targets

International Nuclear Information System (INIS)

Peacock, H. B. Jr.; Iyer, N. C.; Louthan, M. R. Jr.

1995-01-01

Future nuclear materials production and/or the burn-up of long lived radioisotopes may be accomplished through the capture of spallation produced neutrons in accelerators. Aluminum clad-lead and/or lead alloys has been proposed as a spallation target. Aluminum was the cladding choice because of the low neutron absorption cross section, fast radioactivity decay, high thermal conductivity, and excellent fabricability. Metallic lead and lead oxide powders were considered for the target core with the fabrication options being casting or powder metallurgy (PM). Scoping tests to evaluate gravity casting, squeeze casting, and casting and swaging processes showed that, based on fabricability and heat transfer considerations, squeeze casting was the preferred option for manufacture of targets with initial core cladding contact. Thousands of aluminum clad aluminum-lithium alloy core targets and control rods for tritium production have been fabricated by coextrusion processes and successfully irradiated in the SRS reactors. Tritium retention in, and release from, the coextruded product was modeled from experimental and operational data. The model assumed that tritium atoms, formed by the 6Li(n,a)3He reaction, were produced in solid solution in the Al-Li alloy. Because of the low solubility of hydrogen isotopes in aluminum alloys, the irradiated Al-Li rapidly became supersaturated in tritium. Newly produced tritium atoms were trapped by lithium atoms to form a lithium tritide. The effective tritium pressure required for trap or tritide stability was the equilibrium decomposition pressure of tritium over a lithium tritide-aluminum mixture. The temperature dependence of tritium release was determined by the permeability of the cladding to tritium and the local equilibrium at the trap sites. The model can be used to calculate tritium release from aluminum clad, aluminum-lithium alloy targets during postulated accelerator operational and accident conditions. This paper describes

A New Invention Method to Determine the Reduction Factor for Low Fabric Tension Properties for Head Garment Fabrication

Directory of Open Access Journals (Sweden)

Aiman A.F

2016-01-01

Full Text Available This paper proposes a new method to determine the reduction factor for producing a head garment with specified targeted pressure output. Pressure garment fabric mostly supplied to the local hospitals with no information of the material properties and the fabrication method generally used a single reduction factor at various body segments. Reduction factor defined as the percentage of reducing the garment size from the original circumference of the body part which contributes to the compression. The objective of this study is to compare the fabrication method of head garment using reduction factor equation from previous research with the new proposed method. The equation to predict the reduction factor requires the parameter of the fabric tension which is obtained from tensile test and radius of curvature of the human body parts. In the new proposed method, a 3D scanning was used for data acquisition to obtain the geometry of the head area. The pressure outputs are measured by a pressure measurement system developed from Flexiforce sensor and Arduino circuit board. By using the equation, the result shows the calculated reduction factor produced an extremely tight head garment compared to the conducted experiments which manage to produce an adequate reduction factor with a targeted pressure output of 20mmHg. The result of the experiment indicates that the reduction factor ranging from 17% to 23% compared to the equation which produces 20% to 47% of reduction factor. As an additional, the proposed experimental method can be used for different type of pressure garment fabrics in order to obtain the relationship between the reduction factor and the circumference of the body parts.

A Closed-Loop Supply Chain under Retail Price and Quality Dependent Demand with Remanufacturing and Refurbishing

Science.gov (United States)

Christy, A. Y.; Fauzi, B. N.; Kurdi, N. A.; Jauhari, W. A.; Saputro, D. R. S.

2017-06-01

The demand of a product is linearly dependent on the retail price and quality of the product. We address a closed-loop supply chain where the manufacturer manufactures products according to the demand and sells them through a retailer in the market. A third party collects the used products from costumers and sends to the manufacturer to increase the quality. If the products can retrieve the original quality, thus the process is called remanufacturing. Not every products can retrieve the original quality, thus manufacturer refurbish this products with lower price. We construct four different scenarios - centralized and decentralized led by manufacturer, retailer, and third party. From the comparison of the result obtained in the numerical example, we conclude that the joint profit obtained under centralized, manufacturer-led, and retailer-led policies is higher than third party-led policy.

Evaluation of magnetorheological fluid augmented fabric as a fragment barrier material

International Nuclear Information System (INIS)

Son, Kwon Joong; Fahrenthold, Eric P

2012-01-01

The augmentation of high strength fabrics with non-Newtonian fluids has been suggested as a means for improving the ballistic performance of fragment barrier materials widely used in fan blade containment, body armor, orbital debris shielding, and other applications. Magnetorheological (MR) fluids have attracted particular interest, in view of their controllability and proven effectiveness in a variety of damping applications. In a basic research investigation of the MR fluid augmented fabric barrier concept, the authors have fabricated MR fluid saturated Kevlar targets and measured the ballistic performance of these targets both with and without an applied magnetic field. The experimental results show that magnetization of the MR fluid does, when considered in isolation, improve the ability of the augmented fabric to absorb impact energy. However, the benefits of plastic and viscous energy dissipation in the magnetized semi-solid are more than offset by the detrimental effects of yarn lubrication associated with the fluid’s hydrocarbon carrier. An analytical model developed to assist in the interpretation of the experimental data suggests that frictional interaction of the yarns is significantly more effective than magnetorheological augmentation of the fabric in distributing projectile loads away from the point of impact. (paper)

An Ethology of Urban Fabric(s)

DEFF Research Database (Denmark)

Fritsch, Jonas; Thomsen, Bodil Marie Stavning

2014-01-01

The article explores a non-metaphorical understanding of urban fabric(s), shifting the attention from a bird’s eye perspective to the actual, textural manifestations of a variety of urban fabric(s) to be studied in their real, processual, ecological and ethological complexity within urban life. We...... effectuate this move by bringing into resonance a range of intersecting fields that all deal with urban fabric(s) in complementary ways (interaction design and urban design activism, fashion, cultural theory, philosophy, urban computing)....

PLANS FOR WARM DENSE MATTER EXPERIMENTS AND IFE TARGET EXPERIMENTS ON NDCX-II

International Nuclear Information System (INIS)

Waldron, W.L.; Barnard, J.J.; Bieniosek, F.M.; Friedman, A.; Henestroza, E.; Leitner, M.; Logan, B.G.; Ni, P.A.; Roy, P.K.; Seidl, P.A.; Sharp, W.M.

2008-01-01

The Heavy Ion Fusion Science Virtual National Laboratory (HIFS-VNL) is currently developing design concepts for NDCX-II, the second phase of the Neutralized Drift Compression Experiment, which will use ion beams to explore Warm Dense Matter (WDM) and Inertial Fusion Energy (IFE) target hydrodynamics. The ion induction accelerator will consist of a new short pulse injector and induction cells from the decommissioned Advanced Test Accelerator (ATA) at Lawrence Livermore National Laboratory (LLNL). To fit within an existing building and to meet the energy and temporal requirements of various target experiments, an aggressive beam compression and acceleration schedule is planned. WDM physics and ion-driven direct drive hydrodynamics will initially be explored with 30 nC of lithium ions in experiments involving ion deposition, ablation, acceleration and stability of planar targets. Other ion sources which may deliver higher charge per bunch will be explored. A test stand has been built at Lawrence Berkeley National Laboratory (LBNL) to test refurbished ATA induction cells and pulsed power hardware for voltage holding and ability to produce various compression and acceleration waveforms. Another test stand is being used to develop and characterize lithium-doped aluminosilicate ion sources. The first experiments will include heating metallic targets to 10,000 K and hydrodynamics studies with cryogenic hydrogen targets

Management of unconverted light for the National Ignition Facility target chamber

International Nuclear Information System (INIS)

Anderson, A. T.; Bletzer, K.; Burnham, A. K.; Dixit, S.; Genin, F. Y.; Hibbard, W.; Norton, J.; Scott, J. M.; Whitman, P. K.

1998-01-01

The NIF target chamber beam dumps must survive high x-ray, laser, ion, and shrapnel exposures without excessive generation of vapors or particulate that will contaminate the final optics debris shields, thereby making the debris shields susceptible to subsequent laser damage. The beam dumps also must be compatible with attaining and maintaining the required target chamber vacuum and must not activate significantly under high neutron fluxes. Finally, they must be developed, fabricated, and maintained for a reasonable cost. The primary challenge for the beam dump is to survive up to 20 J/cm 2 of lpm light and 1 - 2 J/cm 2 of nominally 200 - 350 eV blackbody temperature x rays. Additional threats include target shrapnel, and other contamination issues. Designs which have been evaluated include louvered hot-pressed boron carbide (B 4 C) or stainless steel (SS) panels, in some cases covered with transparent Teflon film, and various combinations of inexpensive low thermal expansion glasses backed by inexpensive absorbing glass. Louvered designs can recondense a significant amount of ablated material that would otherwise escape into the target chamber. Transparent Teflon was evaluated as an alternative way to capture ablated material. The thin Teflon sheet would need to be replaced after each shot since it exhibits both laser damage and considerable x- ray ablation with each shot. Uncontaminated B 4 C, SS, and low thermal expansion glasses have reasonably small x-ray and laser ablation rates, although the glasses begin to fail catastrophically after 100 high fluence shots. Commercially available absorbing glasses require a pre-shield of either Teflon or low thermal expansion glass to prevent serious degradation by the x-ray fluence. Advantages of the hot-pressed B 4 C and SS over glass are their performance against microshrapnel, their relative indifference to contamination, and their ability to be refurbished by aggressive cleaning using CO 2 pellets, glass beads, high

A study of design features of civil works of nuclear installations facilitating their eventual refurbishing, renewal, dismantling or demolition

International Nuclear Information System (INIS)

Paton, A.A.; Benwell, P.; Irwin, T.F.; Hunter, I.

1984-03-01

This report describes a study that has been carried out to identify civil engineering features which could be incorporated in future gas cooled and light water cooled nuclear power plants to facilitate their decommissioning. The report reviews the problems likely to be met in decommissioning present day nuclear power plants and concludes that there is a number of such features which could be introduced in future designs to overcome or eliminate the problems. The report identifies and describes these features and recommends that further work be carried out to confirm their feasibility. The study briefly considered the possibility of refurbishing nuclear plants and concluded that this is not a realistic option in present circumstances. (author)

Inertial-confinement-fusion targets

International Nuclear Information System (INIS)

Hendricks, C.D.

1981-01-01

Inertial confinement fusion (ICF) targets are made as simple flat discs, as hollow shells or as complicated multilayer structures. Many techniques have been devised for producing the targets. Glass and metal shells are made by using drop and bubble techniques. Solid hydrogen shells are also produced by adapting old methods to the solution of modern problems. Some of these techniques, problems and solutions are discussed. In addition, the applications of many of the techniques to fabrication of ICF targets is presented

National Ignition Facility Target Chamber

International Nuclear Information System (INIS)

Wavrik, R W; Cox, J R; Fleming, P J

2000-01-01

On June 11, 1999 the Department of Energy dedicated the single largest piece of the National Ignition Facility (NIF) at Lawrence Livermore National Laboratory (LLNL) in Livermore, California. The ten (10) meter diameter aluminum target high vacuum chamber will serve as the working end of the largest laser in the world. The output of 192 laser beams will converge at the precise center of the chamber. The laser beams will enter the chamber in two by two arrays to illuminate 10 millimeter long gold cylinders called hohlraums enclosing 2 millimeter capsule containing deuterium, tritium and isotopes of hydrogen. The two isotopes will fuse, thereby creating temperatures and pressures resembling those found only inside stars and in detonated nuclear weapons, but on a minute scale. The NIF Project will serve as an essential facility to insure safety and reliability of our nation's nuclear arsenal as well as demonstrating inertial fusion's contribution to creating electrical power. The paper will discuss the requirements that had to be addressed during the design, fabrication and testing of the target chamber. A team from Sandia National Laboratories (SNL) and LLNL with input from industry performed the configuration and basic design of the target chamber. The method of fabrication and construction of the aluminum target chamber was devised by Pitt-Des Moines, Inc. (PDM). PDM also participated in the design of the chamber in areas such as the Target Chamber Realignment and Adjustment System, which would allow realignment of the sphere laser beams in the event of earth settlement or movement from a seismic event. During the fabrication of the target chamber the sphericity tolerances had to be addressed for the individual plates. Procedures were developed for forming, edge preparation and welding of individual plates. Construction plans were developed to allow the field construction of the target chamber to occur parallel to other NIF construction activities. This was

ICF target technology at the Russian Federal Nuclear Center

International Nuclear Information System (INIS)

Veselov, A.V.; Drozhin, V.S.; Druzhinin, A.A.; Izgorodin, V.M.; Iiyushechkin, B.N.; Kirillov, G.A.; Komleva, G.V.; Korochkin, A.M.; Medvedev, E.F.; Nikolaev, G.P.; Pikulin, I.V.; Pinegin, A.V.; Punin, V.T.; Romaev, V.N.; Sumatokhin, V.L.; Tarasova, N.N.; Tachaev, G.V.; Cherkesova, I.N.

1995-01-01

The main effort of the ICF target fabrication group is support of the experiments performed on the 'ISKRA-4' and 'ISKRA-5' laser systems. The main types of targets used in these experiments are direct drive, inverted corona, and indirect drive. For production of direct drive targets, manufacturing techniques have been developed for both hollow glass and polystyrene microspheres. Hollow glass microspheres are fabricated by free-fall of liquid glass drops or dry gel in a 4 meter vertical kiln. These methods allow us to manufacture glass microspheres with diameters from 50 μm to 1 mm, wall thicknesses from 0.5 to 10 μm, and aspect ratios (radius/ wall) from 20 to 500. The microspheres have a thickness inhomogeneity less than 5% and non-sphericity less than 1%. Polystyrene microspheres are fabricated from polystyrene particles with a blowing agent in a similar vertical kiln. Polystyrene microspheres are fabricated with diameter up to 800 μm and wall thicknesses from 1 to 10 μm. 15 refs., 8 figs

Intrinsic ZnO films fabricated by DC sputtering from oxygen-deficient targets for Cu(In,Ga)Se2 solar cell application

Institute of Scientific and Technical Information of China (English)

Chongyin Yang; DongyunWan; Zhou Wang; Fuqiang Huang

2011-01-01

Intrinsic zinc oxide films, normally deposited by radio frequency (RF) sputtering, are fabricated by direct current (DC) sputtering. The oxygen-deficient targets are prepared via a newly developed double crucible method. The 800-nm-thick film obtaines significantly higher carrier mobility compareing with that of the 800-nm-thick ZnO film. This is achieved by the widely used RF sputtering, which favors the prevention of carrier recombination at the interfaces and reduction of the series resistance of solar cells. The optimal ZnO film is used in a Cu (In, Ga) Se2 (CIGS) solar cell with a high efficiency of 11.57%. This letter demonstrates that the insulating ZnO films can be deposited by DC sputtering from oxygen-deficient ZnO targets to lower the cost of thin film solar cells.%Intrinsic zinc oxide films,normally deposited by radio frequency (RF) sputtering,are fabricated by direct current (DC) sputtering.The oxygen-deficient targets are prepared via a newly developed double crucible method.The 800-nm-thick film obtaines significantly higher carrier mobility compareing with that of the 800-nm-thick ZnO film.This is achieved by the widely used RF sputtering,which favors the prevention of carrier recombination at the interfaces and reduction of the series resistance of solar cells.The optimal ZnO film is used in a Cu (In,Ga) Se2 (C1GS) solar cell with a high efficiency of 11.57％.This letter demonstrates that the insulating ZnO films can be deposited by DC sputtering from oxygen-deficient ZnO targets to lower the cost of thin film solar cells.High resistance transparent intrinsic zinc oxide (i-ZnO)thin film has been widely nsed as the front electrode in transparent electronics and photovoltaic devices because of its low cost and nontoxicity.Owing to its unique characteristics of high transparency and adjustable resistivity in a certain range,the use of i-ZnO thin films as diffusion barrier layers of a-Si/μc-Si,CdTe,and CIGS thin-film solar cells has been advantageous

Materials processing in space: ICF target fabrication implications

International Nuclear Information System (INIS)

Hendricks, C.D.

1982-01-01

During the last quarter of 1982, the Novette laser will become operational at Lawrence Livermore National Laboratory. The primary characteristics of the Novette laser are shown. In many ways, the new laser will serve as a proving ground and test bed for the Nova laser which is also under construction and should be operational in early 1985. Tables provide the Nova operational characteristics. The advent of the two new lasers, Novette and Nova, will make it possible to study many new and exciting aspects of laser-target interactions and of many implosion physics experiments which have previously not been possible. Some of the most interesting and exciting work will be the exploration of the parameters critical to the ignition of a significant thermonuclear burn in the deuterium-tritium fuel in the targets

Fabricated Elastin.

Science.gov (United States)

Yeo, Giselle C; Aghaei-Ghareh-Bolagh, Behnaz; Brackenreg, Edwin P; Hiob, Matti A; Lee, Pearl; Weiss, Anthony S

2015-11-18

The mechanical stability, elasticity, inherent bioactivity, and self-assembly properties of elastin make it a highly attractive candidate for the fabrication of versatile biomaterials. The ability to engineer specific peptide sequences derived from elastin allows the precise control of these physicochemical and organizational characteristics, and further broadens the diversity of elastin-based applications. Elastin and elastin-like peptides can also be modified or blended with other natural or synthetic moieties, including peptides, proteins, polysaccharides, and polymers, to augment existing capabilities or confer additional architectural and biofunctional features to compositionally pure materials. Elastin and elastin-based composites have been subjected to diverse fabrication processes, including heating, electrospinning, wet spinning, solvent casting, freeze-drying, and cross-linking, for the manufacture of particles, fibers, gels, tubes, sheets and films. The resulting materials can be tailored to possess specific strength, elasticity, morphology, topography, porosity, wettability, surface charge, and bioactivity. This extraordinary tunability of elastin-based constructs enables their use in a range of biomedical and tissue engineering applications such as targeted drug delivery, cell encapsulation, vascular repair, nerve regeneration, wound healing, and dermal, cartilage, bone, and dental replacement. © 2015 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Fabrication of recyclable superhydrophobic cotton fabrics

Science.gov (United States)

Han, Sang Wook; Park, Eun Ji; Jeong, Myung-Geun; Kim, Il Hee; Seo, Hyun Ook; Kim, Ju Hwan; Kim, Kwang-Dae; Kim, Young Dok

2017-04-01

Commercial cotton fabric was coated with SiO2 nanoparticles wrapped with a polydimethylsiloxane (PDMS) layer, and the resulting material surface showed a water contact angle greater than 160°. The superhydrophobic fabric showed resistance to water-soluble contaminants and maintained its original superhydrophobic properties with almost no alteration even after many times of absorption-washing cycles of oil. Moreover, superhydrophobic fabric can be used as a filter to separate oil from water. We demonstrated a simple method of fabrication of superhydrophobic fabric with potential interest for use in a variety of applications.

Nanodiamond targets for accelerator X-ray experiments

Energy Technology Data Exchange (ETDEWEB)

Lobko, A., E-mail: lobko@inp.bsu.by [Research Institute for Nuclear Problems, 11 Bobrujskaya Str., Minsk 220030 (Belarus); Golubeva, E. [Belarusian State University, 4 Nezavisimosti Prosp., Minsk 220030 (Belarus); Kuzhir, P.; Maksimenko, S. [Research Institute for Nuclear Problems, 11 Bobrujskaya Str., Minsk 220030 (Belarus); Ryazan State RadioEngineering University, 59/1 Gagarina Street, Ryazan 390005 (Russian Federation); Paddubskaya, A. [Research Institute for Nuclear Problems, 11 Bobrujskaya Str., Minsk 220030 (Belarus); Shenderova, O. [International Technology Center, 8100 Brownleigh Dr., S. 120, Raleigh, NC 27617 (United States); Uglov, V. [Belarusian State University, 4 Nezavisimosti Prosp., Minsk 220030 (Belarus); Valynets, N. [Research Institute for Nuclear Problems, 11 Bobrujskaya Str., Minsk 220030 (Belarus)

2015-07-15

Results of fabrication of a nanodiamond target for accelerator X-ray experiments are reported. Nanodiamond film with dimensions 5 × 7 mm and thickness of 500 nm has been made of the high pressure high temperature nanodiamonds using a filtration method. The average crystallite size of primary nanodiamond particles varies around 100 nm. Source nanodiamonds and fabricated nanodiamond film were characterized using Raman spectroscopy, electron microscopy, and X-ray diffractometry. Preliminary results show that targets made of nanodiamonds are perspective in generating crystal-assisted radiation by the relativistic charged particles, such as parametric X-rays, diffracted transition radiation, diffracted Bremsstrahlung, etc.

Nanodiamond targets for accelerator X-ray experiments

International Nuclear Information System (INIS)

Lobko, A.; Golubeva, E.; Kuzhir, P.; Maksimenko, S.; Paddubskaya, A.; Shenderova, O.; Uglov, V.; Valynets, N.

2015-01-01

Results of fabrication of a nanodiamond target for accelerator X-ray experiments are reported. Nanodiamond film with dimensions 5 × 7 mm and thickness of 500 nm has been made of the high pressure high temperature nanodiamonds using a filtration method. The average crystallite size of primary nanodiamond particles varies around 100 nm. Source nanodiamonds and fabricated nanodiamond film were characterized using Raman spectroscopy, electron microscopy, and X-ray diffractometry. Preliminary results show that targets made of nanodiamonds are perspective in generating crystal-assisted radiation by the relativistic charged particles, such as parametric X-rays, diffracted transition radiation, diffracted Bremsstrahlung, etc

Life extension studies and refurbishing of C and I systems of Cirus

International Nuclear Information System (INIS)

Awale, P.K.; Sumanth, P.; Roy, Kallol; Bharadwaj, G.

2005-01-01

Effects of ageing and component obsolescence of C and I systems of Cirus has been studied, by classifying the C and I systems as (a) those which may affect the operating life of the plant and cannot be repaired/replaced without core-unloading and dismantling the reactor structure. (Group-A), (b) those components which can be repaired/replaced but with considerable difficulty (Group-B) and (c) those which do not affect plant operations and can be easily repaired or replaced (Group-C). Life extension studies included performance assessment, reliability centred evaluation, parametric deviations from base-line characteristics and identification of specific ageing phenomenon and examination of internals. Based on these studies a comprehensive ageing mitigation programme was evolved, necessitating suitable modifications, instrumentation upgradation and component repair/replacement. A major modification job has been to provide an alternate failed fuel detection (FFD) system, since the success rate of the present system, had been decreasing over the years. Further, taking advantage of the available refurbishing outage, a number of instruments and accessories, pertaining to Group-C, were also replaced with state-of-the-art, components. Consideration is also given to requirements of special reactor start-up instrumentation for sensing the initial low neutron count in presence of a high gamma background, during the ensuing reactor start-up with fresh fuel. (author)

Power plant production of inertial confinement fusion targets

International Nuclear Information System (INIS)

Hendricks, C.D.; Johnson, W.L.

1979-01-01

Many of the current techniques for fabricating experimental targets appear to be directly extendable to the high-rate, low-cost production of reactor targets. This report describes several new techniques that, in conjunction with the expansion of existing techniques, can constitute a target factory. We have evaluated this concept on the basis of a generalized reactor target design and the projected specifications of reactor-grade targets

RA Reactor operation and maintenance (I-IX), part VI, Task 3.08/04, Refurbishment of the RA reactor; Pogon i odrzavanje reaktora (I-IX), VI Deo, Zadatak 3.08/04 Remont reaktora RA

Energy Technology Data Exchange (ETDEWEB)

Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

1963-12-15

During the period planned for maintenance and refurbishment of the RA reactor the gas reactor system including the ventilation system was inspected and tested, the components were cleaned. This report describes detailed instructions and actions concerning repair and decontamination of the gas and ventilation systems components.

Effect of dopants and thermal treatment on properties of Ga-Al-ZnO thin films fabricated by hetero targets sputtering system

International Nuclear Information System (INIS)

Hong, JeongSoo; Matsushita, Nobuhiro; Kim, KyungHwan

2013-01-01

In this study, we fabricated Ga and Al doped ZnO (Ga-Al-ZnO; GAZO) thin films by using the facing targets sputtering system under various conditions such as input current and thermal treatment temperature. The properties of the as-deposited GAZO thin films were examined by four-point, UV/Vis spectrometry, X-ray diffraction, atomic force microscopy and field-emission scanning electron microscopy. The result showed that the lowest sheet resistance of the films was 59.3 ohm/sq and transmittance was about 85%. After thermal treatment, the properties of GAZO thin films were improved. The lowest sheet resistance (47.3 ohm/sq) of the GAZO thin films were obtained at thermal treatment temperature of 300 °C, considered to be the result of continuous substitutions by dopants and improved crystallinity by the thermal treatment. - Highlights: ► Ga and Al doped ZnO thin films were prepared by hetero targets sputtering system. ► Free electrons were increased due to the continuous substitutions of Ga and Al. ► Crystallinity was improved by recombination of particles with increasing of temperature

Laser ``M'egajoule'' cryogenic target program: from target fabrication to conformation of the deuterium-tritium ice layer

Science.gov (United States)

Collier, Rémy; Durut, Frédéric; Reneaume, Benoît; Chicane, Cédric; Théobald, Marc; Breton, Olivier; Martin, Michel; Fleury, Emmanuel; Vincent-Viry, Olivier; Bachelet, Franck; Jeannot, Laurent; Geoffray, Isabelle; Botrel, Ronan; Dauteuil, Christophe; Hermerel, Cyril; Choux, Alexandre; Bednarczyk, Sophie; Legaie, Olivier

2008-11-01

For the French inertial confinement fusion (ICF) experiments, cryogenic target assemblies (CTAs) for the LMJ program are manufactured and filled at CEA Valduc (Dijon) in the cryogenic targets filling station (IRCC). They will be moved at about 20 K into a transport cryostat for cryogenic targets and will be driven from CEA/Valduc to CEA/CESTA (Bordeaux). Cryogenic targets will then be transferred by several cryogenic grippers on the cryogenic target positioner before shots. The CTA has to meet severe specifications and involves a lot of challenging tasks for its manufacture. To fill CTAs by permeation with deuterium-tritium (DT), the IRCC need to meet strict thermal, mechanical and dimensional specifications. To obtain a good combustion yield, a very homogenous DT ice layer and very smooth roughness at 1.5 K below the DT triple point are also required. This paper deals with the up to date main issues in the different fields of the LMJ cryogenic target program.

Synthesis, processing and characterization of shear thickening fluid (STF) impregnated fabric composites

International Nuclear Information System (INIS)

Hassan, Tarig A.; Rangari, Vijay K.; Jeelani, Shaik

2010-01-01

Shear thickening is a non-Newtonian fluid behavior defined as the increase of viscosity with the increase in the applied shear rate. The shear thickening fluid (STF) is a combination of hard metal oxide particles suspended in a liquid polymer. This mixture of flowable and hard components at a particular composition, results in a material with remarkable properties. In this manuscript the shear thickening fluid (STF) was prepared by ultrasound irradiation of silica nanoparticles dispersed in liquid polyethylene glycol polymer. The as-prepared STFs have been tested for their rheological and thermal properties. Kevlar and Nylon fabrics were soaked in STF/ethanol solution to make STF/fabric composite. Knife threats and quasistatic penetration tests were performed on the neat fabrics and STF/fabric composite targets for both engineered spike and knife on areal density basis. The results showed that STF impregnated fabrics have better penetration resistance as compared to neat fabrics without affecting the fabric flexibility. This indicates that the addition of STF to the fabric have enhanced the fabric performance and can be used in liquid body armor applications.

Fuels and targets for incineration and transmutation of actinides: the ITU programme

International Nuclear Information System (INIS)

Fernandez, A.; Glatz, J.P.; Haas, D.; Konings, R.J.M.; Somers, J.; Toscano, E.; Walker, C.T.; Wegen, D.

2000-01-01

The ITU programme for the development of fuels and targets for transmutation of actinides is presented. The fabrication of various types of oxide fuels/targets by dust-free processes is described. Selected results of post-irradiation examinations of irradiation experiments (SUPERFACT, TRABANT-1, EFTTRA-T4) are presented to demonstrate the irradiation behaviour of these fuels/targets. Finally, the future developments at ITU in this field are described, including the new shielded facility (the MA lab) for fabrication of minor actinide fuels. (authors)

Fuels and targets for incineration and transmutation of actinides: the ITU programme

Energy Technology Data Exchange (ETDEWEB)

Fernandez, A.; Glatz, J.P.; Haas, D.; Konings, R.J.M.; Somers, J.; Toscano, E.; Walker, C.T.; Wegen, D. [Eurpean Commission, Joint Research Centre, Institute for Transuranium Elements, Kurlsruhe (Germany)

2000-07-01

The ITU programme for the development of fuels and targets for transmutation of actinides is presented. The fabrication of various types of oxide fuels/targets by dust-free processes is described. Selected results of post-irradiation examinations of irradiation experiments (SUPERFACT, TRABANT-1, EFTTRA-T4) are presented to demonstrate the irradiation behaviour of these fuels/targets. Finally, the future developments at ITU in this field are described, including the new shielded facility (the MA lab) for fabrication of minor actinide fuels. (authors)

Structure and properties of nanoparticles fabricated by laser ablation of Zn metal targets in water and ethanol

Science.gov (United States)

Svetlichnyi, V. A.; Lapin, I. N.

2013-10-01

Size characteristics, structure, and spectral and luminescent properties of nanoparticles fabricated by laser ablation of zinc metal targets in water and ethanol are experimentally investigated upon excitation by Nd:YAG-laser radiation (1064 nm, 7 ns, and 15 Hz). It is demonstrated that zinc oxide nanoparticles with average sizes of 10 nm (in water) and 16 nm (in ethanol) are formed in the initial stage as a result of ablation. The kinetics of the absorption and luminescence spectra, transmission electron microscopy, and x-ray structural analysis demonstrate that during long storage of water dispersions and their drying, nanoparticles efficiently interact with carbon dioxide gas of air that leads to the formation of water-soluble Zn(CO3)2(OH)6. In ethanol, Zn oxidation leads to the formation of stable dispersions of ZnO nanoparticles with 99% of the wurtzite phase; in this case, the fluorescence spectra of ZnO nanoparticles change with time, shifting toward longer wavelength region from 550 to 620 nm, which is caused by the changed nature of defects.

Criteria for selection of target materials and design of high-efficiency-release targets for radioactive ion beam generation

CERN Document Server

Alton, G D; Liu, Y

1999-01-01

In this report, we define criteria for choosing target materials and for designing, mechanically stable, short-diffusion-length, highly permeable targets for generation of high-intensity radioactive ion beams (RIBs) for use at nuclear physics and astrophysics research facilities based on the ISOL principle. In addition, lists of refractory target materials are provided and examples are given of a number of successful targets, based on these criteria, that have been fabricated and tested for use at the Holifield Radioactive Ion Beam Facility (HRIBF).

Investigation of Micro Square Structure Fabrication by Applying Textured Cutting Tool in WEDM

Directory of Open Access Journals (Sweden)

Jianguo Zhang

2015-09-01

Full Text Available This paper studies micro structure fabrication by means of a textured tool cutting edge, which is manufactured by applying the wire cut electrical discharge machining (WEDM. Machining performance of the square structure fabrication on the tool cutting edge is investigated in the WEDM process, and the machining accuracy is explored in experimental analyses. In this proposed method, undesired overcut comes from the discharge between the processing debris and the side wall of the target structure. Furthermore, by applying the textured cutting tool, the target square structure is directly fabricated on the alumina workpiece with just a simple turning process, which verifies the feasibility of the proposed tool cutting edge textured method by applying the WEDM. This technology is expected to become a potential method for the mass production of micro structure surfaces in the future.

A triple axes multiple target holder assembly

International Nuclear Information System (INIS)

Tribedi, L.C.; Narvekar, S.D.; Pillay, R.G.; Tandon, P.N.

1993-01-01

We have designed and fabricated a rotatable target holder assembly capable of accommodating 27 targets. The target foils are mounted along two concentric circles on a ss wheel. On the outer circle 18 targets can be mounted each 20deg apart, and on the inner circle the remaining targets are positioned each 40deg apart. The self supporting or carbon backed targets are mounted on thin frames and are placed concentrically at the targets are mounted on thin frames and are placed concentrically at the target position on the wheel. Three degrees of freedom are provided to the target holder assembly. (author). 1 fig

Recent trends in repair and refurbishing of steam turbine components

Indian Academy of Sciences (India)

M. Senthilkumar (Newgen Imaging) 1461 1996 Oct 15 13:05:22

be adequately addressed at various stages of its design and fabrication. ... lead to plant shutdown, loss in production and productivity, fire explosion, radiation or gas ..... component manufacturers, there is a growing necessity for in-house ...

Foil fabrication for the ROMANO event. Revision 1

International Nuclear Information System (INIS)

Romo, J.G. Jr.; Weed, J.W.; Griggs, G.E.; Brown, T.G.; Tassano, P.L.

1984-01-01

The Vacuum Processes Lab (VPL), of LLNL's M.E. Dept. - Material Fabrication Division (MFD), conducted various vacuum related support activities for the ROMANO nuclear physics experiment. This report focuses on the foil fabrication activities carried out between July and November 1983 for the ROMANO event. Other vacuum related activities for ROMANO, such as outgassing tests of materials, are covered in separate documentation. VPL was asked to provide 270 coated Parylene foils for the ROMANO event. However, due to the developmental nature of some of the procedures, approximately 400 coated foils were processed. In addition, VPL interacted with MFD's Plastics Shop to help supply Parylene substrates to other organizations (i.e., LBL and commercial vendors) which had also been asked to provide coated foils for ROMANO. The purposes of this report are (A) to document the processes developed and the techniques used to produce the foils, and (B) to suggest future directions. The report is divided into four sections describing: (1) nuclear target foil fabrication, (2) Parylene substrate preparation and production, (3) calibration foil fabrication, and (4) foil and substrate inspections

Development of uranium metal targets for 99Mo production

International Nuclear Information System (INIS)

Wiencek, T.C.; Hofman, G.L.

1993-10-01

A substantial amount of high enriched uranium (HEU) is used for the production of medical-grade 99 Mo. Promising methods of producing irradiation targets are being developed and may lead to the reduction or elimination of this HEU use. To substitute low enriched uranium (LEU) for HEU in the production of 99 Mo, the target material may be changed to uranium metal foil. Methods of fabrication are being developed to simplify assembly and disassembly of the targets. Removal of the uranium foil after irradiation without dissolution of the cladding is a primary goal in order to reduce the amount of liquid radioactive waste material produced in the process. Proof-of-concept targets have been fabricated. Destructive testing indicates that acceptable contact between the uranium foil and the cladding can be achieved. Thermal annealing tests, which simulate the cladding/uranium diffusion conditions during irradiation, are underway. Plans are being made to irradiate test targets

Longitudinal gas-density profilometry for plasma-wakefield acceleration targets

Science.gov (United States)

Schaper, Lucas; Goldberg, Lars; Kleinwächter, Tobias; Schwinkendorf, Jan-Patrick; Osterhoff, Jens

2014-03-01

Precise tailoring of plasma-density profiles has been identified as one of the critical points in achieving stable and reproducible conditions in plasma wakefield accelerators. Here, the strict requirements of next generation plasma-wakefield concepts, such as hybrid-accelerators, with densities around 1017 cm-3 pose challenges to target fabrication as well as to their reliable diagnosis. To mitigate these issues we combine target simulation with fabrication and characterization. The resulting density profiles in capillaries with gas jet and multiple in- and outlets are simulated with the fluid code OpenFOAM. Satisfactory simulation results then are followed by fabrication of the desired target shapes with structures down to the 10 μm level. The detection of Raman scattered photons using lenses with large collection solid angle allows to measure the corresponding longitudinal density profiles at different number densities and allows a detection sensitivity down to the low 1017 cm-3 density range at high spatial resolution. This offers the possibility to gain insight into steep density gradients as for example in gas jets and at the plasma-to-vacuum transition.

Energy Refurbishment of an Office Building with Hybrid Photovoltaic System and Demand-Side Management

Directory of Open Access Journals (Sweden)

Giovani Almeida Dávi

2017-08-01

Full Text Available On-site photovoltaic (PV and battery systems intend to improve buildings energy performance, however battery costs and monetary incentives are a major drawback for the introduction of these technologies into the electricity grids. This paper proposes an energy refurbishment of an office building based on multi-objective simulations. An innovative demand-side management approach is analyzed through the PV and battery control with the purpose of reducing grid power peaks and grid imported energy, as well as improving the project economy. Optimization results of load matching and grid interaction parameters, complemented with an economic analysis, are investigated in different scenarios. By means of battery use, the equivalent use of the grid connection is reduced by 12%, enhancing the grid interaction potential, and 10% of load matching rates can be increased. Project improvements indicate the grid connection capacity can be reduced by 13% and significant savings of up to 48% are achieved on yearly bills. The economy demonstrates the grid parity is only achieved for battery costs below 100 €/kWh and the payback period is large: 28 years. In the case with only PV system, the grid parity achieves better outcomes and the payback time is reduced by a half, making this a more attractive option.

A containment analysis for SBLOCA without ECI in the refurbished Wolsong-1 Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Kim, T.M.; Moon, B.J.; Bae, C.J.; Lee, S.H.; Choi, C.J.; Lee, D.S. [NSSS, Korea Power Engineering Company, Inc., Daejeon (Korea, Republic of); Kim, S.M. [NETEC, Korea Hydro and Nuclear Power Company, Inc., Daejeon (Korea, Republic of)

2010-07-01

A small break leading to loss of coolant accident (SBLOCA), being one of the topic accidents in the nuclear plant diagnosis in recent years, has been analyzed and evaluated for the refurbished Wolsong-1 Nuclear Power Plant (NPP). The industry standard toolset (IST) codes developed by CANDU Owners Group and updated models including design change parameters are applied to the event analyses. GOTHIC code has been used for the containment analysis of Wolsong-1. Also, SMART-IST code fitted in the Iodine Chemistry (IMOD-2) model has been used to predict nuclide behavior within the containment considering various aspects. IMOD-2 was incorporated into SMART-IST as a module dealing the chemical transformations and mass transfer of iodine species in containment. IMOD-2 model is very sensitive to paint and chemicals. The parameter studies for IMOD-2 model are performed to decide the analysis value set. The developed methodology and the results of SBLOCA without ECI are presented herein. Under the most heat-up conditions, the radionuclide release from the failed fuel into the containment and subsequently to the environment is such that the radioactive doses to the public are below the acceptable limits. (author)

Point Lepreau refurbishment project programmable digital comparator (PDC) replacement for SDS1 and SDS2

International Nuclear Information System (INIS)

Ichiyen, N.M.; Chan, D.; Thompson, P.D.

2003-01-01

NB Power is tentatively planning to conduct an 18-month maintenance outage of the Point Lepreau Generating Station (PLGS) starting in April 2007. The scope of the outage was determined from the outcome of a two year study (Phase 1) involving a detailed condition assessment of the station which examined issues relating to ageing and obsolescence, along with a detailed review of Safety and Licensing issues associated with extended operation. In order to minimize schedule and regulatory risk for the Refurbishment project, pre-project work was initiated in early 2002. This program is called Phase 2 ESA (Early Start Activities). As part of the Phase 1 assessments it was concluded that replacement of the PDCs (Programmable Digital Comparators) for both shutdown systems was required in order to ensure operation of the plant for a further 25-30 years. Critical tasks were identified related to PDC replacement as part of the Phase 2 ESA program. This paper describes the activities that have taken place in the Phase 2 ESA program as well as the plan for future work for the PDC replacement for SDS 1 (Shutdown System Number One) and SDS2 (Shutdown System Number Two). (author)

Copper deposition on fabrics by rf plasma sputtering for medical applications

International Nuclear Information System (INIS)

Segura, G; Guzmán, P; Barrantes, Y; Navarro, G; Asenjo, J; Guadamuz, S; Vargas, VI; Zuñiga, P; Chaves, S; Chaves, J

2015-01-01

The present work is about preparation and characterization of RF sputtered Cu films on cotton by the usage of a Magnetron Sputter Source and 99.995% purity Cu target at room temperature. Cotton fabric samples of 1, 2 and 4 min of sputtering time at discharge pressure of 1×10 −2 Torr and distance between target and sample of 8 cm were used. The main goal was to qualitatively test the antimicrobial action of copper on fabrics. For that purpose, a reference strain of Escherichia Coli ATCC 35218 that were grown in TSA plates was implemented. Results indicated a decrease in the growth of bacteria by contact with Cu; for fabric samples with longer sputtering presented lower development of E. coli colonies. The scope of this research focused on using these new textiles in health field, for example socks can be made with this textile for the treatment of athlete's foot and the use in pajamas, sheets, pillow covers and robes in hospital setting for reducing the spread of microorganisms. (paper)

Fabrication of a tantalum-clad tungsten target for KENS

International Nuclear Information System (INIS)

Kawai, Masayoshi; Kikuchi, Kenji; Kurishita, Hiroaki; Li, J.-F.; Furusaka, Michihiro

2001-01-01

Since the cold neutron source intensity of KENS (the spallation neutron source at High Energy Accelerator Research Organization) was decreased into about a third of the designed value because a cadmium liner at the cold neutron source deformed and obstructed the neutron beam line, the target-moderator-and-reflector assembly (TMRA) has been replaced by a new one aimed at improving the neutron performance and recovering the cold neutron source. The tantalum target has also been replaced by a tantalum-clad tungsten one. In order to bond the tantalum-clad with the tungsten block, a hot isostatic press (HIP) process was applied and optimized. It was found that gaseous interstitial impurity elements severely attacked tantalum and embrittled, and that the getter materials such as zirconium and tantalum were effective to reduce the embrittlement

dena refurbishment investigation. Pt. 1. Efficiency of energetic modernization in the inventory of rented apartments. Accompanying research according to the dena project: ''Existing low-energy house''; dena-Sanierungsstudie. T. 1. Wirtschaftlichkeit energetischer Modernisierung im Mietwohnungsbestand. Begleitforschung zum dena-Projekt ''Niedrigenergiehaus im Bestand''. Bericht 2010

Energy Technology Data Exchange (ETDEWEB)

Discher, Henning [Deutsche Energie-Agentur GmbH, Berlin (Germany); Hinz, Eberhard; Enseling, Andreas [Institut Wohnen und Umwelt GmbH (IWU), Darmstadt (Germany)

2010-12-08

Due to the world-wide increasing energy demand, the strongly varying energy prices and not at least due to the effects of the climate change, politics, economics and science face great challenges. Energy efficiency in the building sector plays an important role in the reduction of energy consumption. An energetic modernization of the existing buildings is crucial toward achieving the goals of climate protection. Nevertheless there still exist caveas toward energy-efficient building and refurbishment. For the future, market constraints must purposefully be reduced and the chances of energy-efficient refurbishments have to be used.

Development of Low-Cost Method for Fabrication of Metal Neutron Guides

Energy Technology Data Exchange (ETDEWEB)

Engelhaupt, Darell [Dawn Research Inc., Madison, AL (United States); Khaykovich, Boris [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Romaine, Suzanne [Harvard-Smithsonian Center for Astrophysics, Cambridge, MA (United States)

2017-12-19

Neutron scattering is one of the most useful methods of studying the structure and dynamics of matter. US DOE neutron scattering research facilities at Oak Ridge National Laboratory are among the World’s most advanced, providing researchers with unmatched capabilities for probing the structure and properties of materials, including engineering and biological systems. This task is to develop a lower cost process to optimize and produce the required neutron guides capable of efficiently delivering neutron beams for tens of meters between neutron moderators and instruments. Therefore, our effort is to improve the performance and lower the production cost of neutron guides. Our approach aims at improving guide quality while controlling their rising costs by adopting a novel electroforming replication approach to their fabrication. These guides will be especially advantageous when used near the neutron source since the radiation resistance of nickel is superior to glass. Additionally, we are depositing low-stress nickel from an extremely low impurity solution completely free of stress-reducing agents, which nominally contain and impart sulfur, carbon and other elements that potentially activate in the neutron environment. This is achieved by using a pulsed periodically reversed current methodology. The best guides quote waviness of 0.1 mrad. It is reasonable to prepare just one mandrel of about 0.5 m long, for production of tens of guide segments, saving both the cost and supply time of guides to neutron facilities. We estimate that we can fabricate a single mandrel for the current cost of an individual one-meter guide, but from this, we can produce tens of meters of guide very inexpensively without mandrel refurbishment. While a multilayer coating will add to the overall cost, we expect this will be less than that of commercially available guides today. Therefore, we will produce higher quality guides, which are less susceptible to radiation damage, at the lower cost

DESIGN, FABRICATION, AND TESTING OF AN ADVANCED, NON-POLLUTING TURBINE DRIVE GAS GENERATOR

International Nuclear Information System (INIS)

Unknown

2002-01-01

The objectives of this report period were to complete the development of the Gas Generator design, which was done; fabricate and test of the non-polluting unique power turbine drive gas Gas Generator, which has been postponed. Focus during this report period has been to complete the brazing and bonding necessary to fabricate the Gas Generator hardware, continue making preparations for fabricating and testing the Gas Generator, and continuing the fabrication of the Gas Generator hardware and ancillary hardware in preparation for the test program. Fabrication is more than 95% complete and is expected to conclude in early May 2002. the test schedule was affected by relocation of the testing to another test supplier. The target test date for hot fire testing is now not earlier than June 15, 2002

Characterization studies of prototype ISOL targets for the RIA

International Nuclear Information System (INIS)

Greene, John P.; Burtseva, Tatiana; Neubauer, Janelle; Nolen, Jerry A.; Villari, Antonio C.C.; Gomes, Itacil C.

2005-01-01

Targets employing refractory compounds are being developed for the rare isotope accelerator (RIA) facility to produce ion species far from stability. With the 100 kW beams proposed for the production targets, dissipation of heat becomes a challenging issue. In our two-step target design, neutrons are generated in a refractory primary target, inducing fission in the surrounding uranium carbide. The interplay of density, grain size, thermal conductivity and diffusion properties of the UC 2 needs to be well understood before fabrication. Thin samples of uranium carbide were prepared for thermal conductivity measurements using an electron beam to heat the sample and an optical pyrometer to observe the thermal radiation. Release efficiencies and independent thermal analysis on these samples are being undertaken at Oak Ridge National Laboratory (ORNL). An alternate target concept for RIA, the tilted slab approach promises to be simple with fast ion release and capable of withstanding high beam intensities while providing considerable yields via spallation. A proposed small business innovative research (SBIR) project will design a prototype tilted target, exploring the materials needed for fabrication and testing at an irradiation facility to address issues of heat transfer and stresses within the target

Characterization studies of prototype ISOL targets for the RIA

Science.gov (United States)

Greene, John P.; Burtseva, Tatiana; Neubauer, Janelle; Nolen, Jerry A.; Villari, Antonio C. C.; Gomes, Itacil C.

2005-12-01

Targets employing refractory compounds are being developed for the rare isotope accelerator (RIA) facility to produce ion species far from stability. With the 100 kW beams proposed for the production targets, dissipation of heat becomes a challenging issue. In our two-step target design, neutrons are generated in a refractory primary target, inducing fission in the surrounding uranium carbide. The interplay of density, grain size, thermal conductivity and diffusion properties of the UC2 needs to be well understood before fabrication. Thin samples of uranium carbide were prepared for thermal conductivity measurements using an electron beam to heat the sample and an optical pyrometer to observe the thermal radiation. Release efficiencies and independent thermal analysis on these samples are being undertaken at Oak Ridge National Laboratory (ORNL). An alternate target concept for RIA, the tilted slab approach promises to be simple with fast ion release and capable of withstanding high beam intensities while providing considerable yields via spallation. A proposed small business innovative research (SBIR) project will design a prototype tilted target, exploring the materials needed for fabrication and testing at an irradiation facility to address issues of heat transfer and stresses within the target.

Refurbishment programme of the reactor and progress of work

International Nuclear Information System (INIS)

Astruc, J.M.

1992-01-01

During 20 years of operation, since its start-up the ILL there have been some problems, like ruptured heavy water collector, in the upper part of the reflector tank, replacement of all the beam tubes due to the evolution of the mechanical characteristics of the aluminium alloy under irradiation. Some days after regular shutdown for maintenance, an inspection of the internal elements of the reactor discovered cracks on the grids which ensure the regular flow of cooling water. The investigations showed that the cracks are due to a design fault, aggravated by the effects of mechanical fatigue on highly irradiated material. It was not possible to repair the cracked grid, and it had to be replaced. This involved the dismantling of the internals parts of the reactor tank. The reactor refurbishment programme was set up. It provides for the replacement of the reactor block, the coupling sleeves, the anti turbulence grids and the diffuser, and of the ancillary elements. The main items to be replaced are: the reactor block consisting of the reactor vessel and its cover, known as the 'upper structure'; the heavy water collectors; connecting sleeves between the reactor block and the flanges of the various beam tubes. These three items constitute the primary circuit in the swimming pool. It is also planned to replace some internal parts of the reactor tank, such as the beam-tubes, the grid and diffuser and the chimney. Some parts of the present reactor, which are not at the end of their life, would be reused, for instance the two cold sources, the safety rods, and some other pieces. The parts replaced would be cut up and packaged in accordance with current standards and disposed of. All items are in principle to be replaced by identical equipment. This concerns in particular performance, mechanical characteristics and the choice of materials. The replacement of the reactor block necessitates a complete dismantling of the equipment in the reactor block, and of the structures in

Minor Actinide Recycle in Sodium Cooled Fast Reactors Using Heterogeneous Targets

International Nuclear Information System (INIS)

Bays, Samuel; Medvedev, Pavel; Pope, Michael; Ferrer, Rodolfo; Forget, Benoit; Asgari, Mehdi

2009-01-01

This paper investigates the plausible design of transmutation target assemblies for minor actinides (MA) in Sodium Fast Reactors (SFR). A heterogeneous recycling strategy is investigated, whereby after each reactor pass, un-burned MAs from the targets are blended with MAs produced by the driver fuel and additional MAs from Spent Nuclear Fuel (SNF). A design iteration methodology was adopted for customizing the core design, target assembly design and matrix composition design. The overall design was constrained against allowable peak or maximum in-core performances. While respecting these criteria, the overall design was adjusted to reduce the total number of assemblies fabricated per refueling cycle. It was found that an inert metal-hydride MA-Zr-Hx target matrix gave the highest transmutation efficiency, thus allowing for the least number of targets to be fabricated per reactor cycle.

Does demolition or refurbishment of old and inefficient homes help to increase our environmental, social and economic viability?

International Nuclear Information System (INIS)

Power, Anne

2008-01-01

The issue of whether to demolish or refurbish older housing has been debated for over a century. It has been an active policy area since the late 1880s, when the Government first authorised the statutory demolition of insanitary slums. In the 1960s, revulsion at the scale of 'demolition blight' and new building caused a rethink, leading to a major reinvestment in inner city neighbourhoods of older housing. In the past 5 years, debate on demolition and new building has been intensified by the Government's Sustainable Communities Plan of 2003, with its proposals for large-scale clearance and building. Environmental arguments about renovating the existing stock have gained increasing prominence as people have sought to defend their communities from demolition. The evidence on whether demolition would reduce the amount of greenhouse gases we emit into the atmosphere is unclear and disputed. This paper summarises the evidence and arguments, and attempts to clarify the most realistic, achievable route to major reductions in energy use in homes

The Architectural and Environmental Refurbishment of Industrialised Residential Construction. The example of the Selva Cafaro Quarter in Naples

Directory of Open Access Journals (Sweden)

Massimo Perriccioli

2012-10-01

Full Text Available This essay presents the experimental research conducted over the past years by the CHED (Concept House and Environmental Design Research Unit at the “Eduardo Vittoria” School of Architecture and Design in Ascoli Piceno, focused on the theme of Social Housing. The CHED is a temporary research team that proposes a union between diverse know-how, cultures, skills and specialisations, working towards a method of theoretical and conceptual investigation and design and building experiments in the field of innovative construction for sustainable dwelling. In particular, the experience outlined in this text relates to a design experiment completed between 2010 and 2011 and outside the borders of the Marche region, in agreement with the City of Naples' Assessorato all’Edilizia e al Centro Storico (Department of Building and the Historical Centre and focused on the architectural and environmental refurbishment of the residential quarter of Selva Cafaro in San Pietro a Patierno (Naples.

Reforming Shapes for Material-aware Fabrication

KAUST Repository

Yang, Yongliang; Wang, Jun; Mitra, Niloy J.

2015-01-01

© 2015 The Eurographics Association and John Wiley & Sons Ltd. Published by John Wiley & Sons Ltd. As humans, we regularly associate shape of an object with its built material. In the context of geometric modeling, however, this inter-relation between form and material is rarely explored. In this work, we propose a novel data-driven reforming (i.e.; reshaping) algorithm that adapts an input multi-component model for a target fabrication material. The algorithm adapts both the part geometry and the inter-part topology of the input shape to better align with material-aware fabrication requirements. As output, we produce the reshaped model along with respective part dimensions and inter-part junction specifications. We evaluate our algorithm on a range of man-made models and demonstrate a variety of model reshaping examples focusing only on metal and wooden materials.

Reforming Shapes for Material-aware Fabrication

KAUST Repository

Yang, Yongliang

2015-08-10

© 2015 The Eurographics Association and John Wiley & Sons Ltd. Published by John Wiley & Sons Ltd. As humans, we regularly associate shape of an object with its built material. In the context of geometric modeling, however, this inter-relation between form and material is rarely explored. In this work, we propose a novel data-driven reforming (i.e.; reshaping) algorithm that adapts an input multi-component model for a target fabrication material. The algorithm adapts both the part geometry and the inter-part topology of the input shape to better align with material-aware fabrication requirements. As output, we produce the reshaped model along with respective part dimensions and inter-part junction specifications. We evaluate our algorithm on a range of man-made models and demonstrate a variety of model reshaping examples focusing only on metal and wooden materials.

FPGA fabric specific optimization for RLT design

International Nuclear Information System (INIS)

Perwaiz, A.; Khan, S.A.

2010-01-01

This paper proposes a technique custom to the optimization requirements suited for a particular family of Field Programmable Gate Arrays (FPGAs). As FPGAs have introduced re configurable black boxes there is a need to perform optimization across FPGAs slice fabric in order to achieve optimum performance. Though the Register Transfer Level (RTL) Hardware Descriptive Language (HDL) code should be technology independent but in many design instances it is imperative to understand the target technology especially once the target device embeds dedicated arithmetic blocks. No matter what the degree of optimization of the algorithm is, the configuration of target device plays an important role as far as the device utilization and path delays are concerned Index Terms: Field Programmable Gate Arrays (FPGA), Compression Tree, Bit Width Reduction, Look Ahead Pipelining. (author)

Longitudinal gas-density profilometry for plasma-wakefield acceleration targets

Energy Technology Data Exchange (ETDEWEB)

Schaper, Lucas, E-mail: lschaper01@qub.ac.uk [Universität Hamburg, FB Physik, Institut für Experimentalphysik, Luruper Chaussee 149, 22761 Hamburg (Germany); Deutsches Elektronen-Synchrotron DESY, Notkestraße 85, 22607 Hamburg (Germany); Goldberg, Lars; Kleinwächter, Tobias; Schwinkendorf, Jan-Patrick; Osterhoff, Jens [Deutsches Elektronen-Synchrotron DESY, Notkestraße 85, 22607 Hamburg (Germany)

2014-03-11

Precise tailoring of plasma-density profiles has been identified as one of the critical points in achieving stable and reproducible conditions in plasma wakefield accelerators. Here, the strict requirements of next generation plasma-wakefield concepts, such as hybrid-accelerators, with densities around 10{sup 17} cm{sup −3} pose challenges to target fabrication as well as to their reliable diagnosis. To mitigate these issues we combine target simulation with fabrication and characterization. The resulting density profiles in capillaries with gas jet and multiple in- and outlets are simulated with the fluid code OpenFOAM. Satisfactory simulation results then are followed by fabrication of the desired target shapes with structures down to the 10 µm level. The detection of Raman scattered photons using lenses with large collection solid angle allows to measure the corresponding longitudinal density profiles at different number densities and allows a detection sensitivity down to the low 10{sup 17} cm{sup −3} density range at high spatial resolution. This offers the possibility to gain insight into steep density gradients as for example in gas jets and at the plasma-to-vacuum transition.

Point Lepreau Refurbishment Project. Programmable digital comparator (PDC) replacement for SDS1 and SDS2 - update 1

International Nuclear Information System (INIS)

Fraser, K.G.; Ichiyen, N.M.; Condor, A.E.; Thompson, P.D.

2005-01-01

NB Power is tentatively planning to conduct an 18-month maintenance outage of the Point Lepreau Generating Station starting in April 2008. The scope of the outage was determined from the outcome of a two year study (Phase 1) involving a detailed condition assessment of the station which examined issues relating to ageing and obsolescence, along with a detailed review of Safety and Licensing issues associated with extended operation. In order to minimize schedule and regulatory risk for the Refurbishment project, pre-project work was initiated in early 2002. This program is called Phase 2 ESA (Early Start Activities). As part of the Phase 1 assessments it was concluded that replacement of the Programmable Digital Comparators for both shutdown systems was required in order to ensure operation of the plant for a further 25-30 years. Critical tasks were identified related to PDC replacement as part of the Phase 2 ESA program. This paper describes the progress of the Phase 2 ESA program as well as the planned future (Phase 2) work for the PDC replacement for both shutdown systems. (author)

The Ignition Target for the National Ignition Facility

International Nuclear Information System (INIS)

Atherton, L J; Moses, E I; Carlisle, K; Kilkenny, J

2007-01-01

The National Ignition Facility (NIF) is a 192 beam Nd-glass laser facility presently under construction at Lawrence Livermore National Laboratory (LLNL) for performing inertial confinement fusion (ICF) and experiments studying high energy density (HED) science. When completed in 2009, NIF will be able to produce 1.8 MJ, 500 TW of ultraviolet light for target experiments that will create conditions of extreme temperatures (>10 8 K), pressures (10-GBar) and matter densities (> 100 g/cm 3 ). A detailed program called the National Ignition Campaign (NIC) has been developed to enable ignition experiments in 2010, with the goal of producing fusion ignition and burn of a deuterium-tritium (DT) fuel mixture in millimeter-scale target capsules. The first of the target experiments leading up to these ignition shots will begin in 2008. Targets for the National Ignition Campaign are both complex and precise, and are extraordinarily demanding in materials fabrication, machining, assembly, cryogenics and characterization. An overview of the campaign for ignition will be presented, along with technologies for target fabrication, assembly and metrology and advances in growth and x-ray imaging of DT ice layers. The sum of these efforts represents a quantum leap in target precision, characterization, manufacturing rate and flexibility over current state-of-the-art

COATING AND MANDREL EFFECTS ON FABRICATION OF GLOW DISCHARGE POLYMER NIF SCALE INDIRECT DRIVE CAPSULES

International Nuclear Information System (INIS)

NIKROO, A.; PONTELANDOLFO, J.M.; CASTILLO, E.R.

2002-01-01

OAK A271 COATING AND MANDREL EFFECTS ON FABRICATION OF GLOW DISCHARGE POLYMER NIF SCALE INDIRECT DRIVE CAPSULES. Targets for the National Ignition Facility (NIF) need to be about 200 (micro)m thick and 2 mm in diameter. These dimensions are well beyond those currently fabricated on a routine basis. They have investigated fabrication of near NIF scale targets using the depolymerizable mandrel technique. Poly-alpha-methylstyrene (PAMS) mandrels, about 2 mm in diameter, of varying qualities were coated with as much as 125 (micro)m of glow discharge polymer (GDP). The surface finish of the final shells was examined using a variety of techniques. A clear dependence of the modal spectrum of final GDP shell on the quality of the initial PAMS mandrels was observed. isolated features were found to be the greatest cause for a shell not meeting the NIF standard

New fabrication techniques for the nuclear fuels of tomorrow

International Nuclear Information System (INIS)

Babelot, J.F.; Bokelund, H.; Gerontopoulos, P.; Gueugnon, J.F.; Richter, K.

1995-01-01

The shift of the emphasis of the work at the Institute for Transuranium Elements (ITU) from the development of fuels based on uranium and plutonium to safety aspects concerning the use of plutonium and other of actinides, necessitates the production of targets containing appreciable amounts of minor actinides for irradiation experiments. The handling of minor actinides requires additional protective measures, combined with improved fuel fabrication techniques. The boundary conditions for a suitable process are flexibility, adaptability to remote control, and minimization of dust formation. A method based on the sol-gel fabrication technique meets these criteria, and was selected for the present developments at ITU. (author)

Polymorphous computing fabric

Science.gov (United States)

Wolinski, Christophe Czeslaw [Los Alamos, NM; Gokhale, Maya B [Los Alamos, NM; McCabe, Kevin Peter [Los Alamos, NM

2011-01-18

Fabric-based computing systems and methods are disclosed. A fabric-based computing system can include a polymorphous computing fabric that can be customized on a per application basis and a host processor in communication with said polymorphous computing fabric. The polymorphous computing fabric includes a cellular architecture that can be highly parameterized to enable a customized synthesis of fabric instances for a variety of enhanced application performances thereof. A global memory concept can also be included that provides the host processor random access to all variables and instructions associated with the polymorphous computing fabric.

Preparation of thin nuclear targets

International Nuclear Information System (INIS)

Muggleton, A.H.F.

1979-03-01

Thin film backings, sources and targets are needed for many applications in low energy nuclear physics and nuclear chemistry experiments. A survey of techniques used in the preparation of nuclear targets is first briefly discussed. These are classified as chemical, mechanical and physical preparations. Vacuum evaporation, being the most generally used technique, is discussed in detail. It is highly desirable to monitor the film thickness and control the deposition rate during evaporation and to measure the final target thickness after deposition has concluded. The relative merits of various thickness measuring techniques are described. Stages in the fabrication and mounting of self-supporting foils are described in detail, with emphasis given to the preparation of thin self-supporting carbon foils used as target backings and stripper foils. Various target backings, and the merits of the more generally used release agents are described in detail. The preparations of more difficult elemental targets are discussed, and a comprehensive list of the common targets is presented

Microencapsulation and fabrication of fuel pellets for inertial confinement fusion

International Nuclear Information System (INIS)

Nolen, R.L. Jr.; Kool, L.B.

1981-01-01

Various microencapsulation techniques were evaluated for fabrication of thermonuclear fuel pellets for use in existing experimental facilities studying inertial confinement fusion and in future fusion-power reactors. Coacervation, spray drying, in situ polymerization, and physical microencapsulation methods were employed. Highly spherical, hollow polymeric shells were fabricated ranging in size from 20 to 7000 micron. In situ polymerization microencapsulation with poly(methyl methacrylate) provided large shells, but problems with local wall defects still must be solved. Extension to other polymeric systems met with limited success. Requirements for inertial confinement fusion targets are described, as are the methods that were used

Design & fabrication of cantilever array biosensors

DEFF Research Database (Denmark)

Boisen, Anja; Thundat, T

2009-01-01

Surface immobilization of functional receptors on microfabricated cantilever arrays offers a new paradigm for the development of biosensors based on nanomechanics. Microcantilever-based systems are capable of real-time, multiplexed detection of unlabeled disease markers in extremely small volumes......, electronic processing, and even local telemetry on a single chip have the potential of satisfying the need for highly sensitive and selective multiple-target detection in very small samples. Here we will review the design and fabrication process of cantilever-based biosensors....

Targets with thin ferromagnetic layers for transient field experiments

International Nuclear Information System (INIS)

Gallant, J.L.; Dmytrenko, P.

1982-01-01

Multilayer targets containing a central layer sufficiently thin so that all recoil nuclei can traverse it and subsequently stop in a suitable cubic environment have been prepared. Such targets are required in experiments making use of a magnetic field acting on an ion moving through a ferromagnetic material. The preparation and annealing of the ferromagnetic foils (iron and gadolinium) and the fabrication of the multilayer targets are described. (orig.)

Summary abstract: microspot target development with seeded and patterned plasma polymers

International Nuclear Information System (INIS)

Letts, S.A.; Miller, D.E.; Corley, R.A.; Tillotson, T.M.; Witt, L.A.

1985-01-01

In inertial confinement fusion (ICF) energy is transferred from the laser to the target through the interaction of extremely high intensity laser light with the target plasma. To better understand laser-plasma interactions, a new class of targets was designed to study long scale-length plasmas (many hundred times the laser wavelength) by measurement of the temperature and density of the plasma as a function of time. The specifications for the target called for a freestanding hydrocarbon polymer (CH) film with a sharply defined spot (microspot) in the center seeded with either silicon or sulfur. The target film was fabricated using a three-step procedure which consisted of deposition of the hydrocarbon film, definition of the microspot, and then deposition of a seeded spot through a mask. In the final assembly step, the film containing the microspot was mounted over a 1.5 mm diam hole in a support. The support was either a plastic ring or a copper foil electroplated with 3 μm of gold. The fabrication of this type of target is described

Conductive cooling of high-power RIB targets

International Nuclear Information System (INIS)

Talbert, W.L.; Drake, D.M.; Wilson, M.T.; Lenz, J.W.; Hsu, H.-H.

2002-01-01

A short review is presented of target cooling approaches suggested for targets irradiated by intense high-energy proton beams to produce radioactive species for use in a broad range of physics studies. This work reports on conductive cooling approaches for operation at temperatures lower than effective for radiative cooling. The possibilities for conductive cooling are discussed, and a prototype test target is described. This target was constructed for an experiment, designed to validate the numerical analysis approaches, at the TRIUMF/ISAC facility. Fabrication issues and the results of the experiment are presented, followed by a discussion of the implications of the experiment outcome for future development of targets to produce intense beams of radioactive ions

Gel Fabrication of Molybdenum “Beads”

Energy Technology Data Exchange (ETDEWEB)

Lowden, Richard Andrew [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division; Armstrong, Beth L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division; Cooley, Kevin M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division

2016-11-01

Spherical molybdenum particles or “beads” of various diameters are of interest as feedstock materials for the additive manufacture of targets and assemblies used in the production of ⁹⁹Mo medical isotopes using accelerator technology. Small metallic beads or ball bearings are typically fabricated from wire; however, small molybdenum spheres cannot readily be produced in this manner. Sol-gel processes are often employed to produce small dense microspheres of metal oxides across a broad diameter range that in the case of molybdenum could be reduced and sintered to produce metallic spheres. These Sol-gel type processes were examined for forming molybdenum oxide beads; however, the molybdenum trioxide was chemically incompatible with commonly used gelation materials. As an alternative, an aqueous alginate process being assessed for the fabrication of oxide spheres for catalyst applications was employed to form molybdenum trioxide beads that were successfully reduced and sintered to produce small molybdenum spheres.

Fabrication technology and characteristics of AmO2-MgO cercer materials for transmutation

International Nuclear Information System (INIS)

Croixmarie, Y.; Mocellin, A.; Warin, D.

2000-01-01

This paper deals with the fabrication technology and the physico-chemical properties of target materials prepared for the ECRIX experiment in the French PHENIX reactor. The ECRIX target materials consist of pellets made of a ceramic-ceramic type composite in which particles of americium oxide are microdispersed in an inert matrix of magnesium oxide

Preparation of targets using electron gun systems

International Nuclear Information System (INIS)

Maier-Komor, P.

1975-01-01

Most targets of isotopes with very low vapor pressure can only be fabricated by vacuum deposition using an electron gun system or a heavy ion sputtering system. Heavy ion sputtering is a very new technique with many unsolved problems. Therefore it seems to be easier to work with an electron gun. Different commercially available electron guns, which are all designed for the high evaporation rates used in industry, are examined for their qualification in processing small amounts of material as used in fabrication of isotope targets. Electron backscattering and the associated efficiency of the electron beam power is strongly dependent on the atomic number Z of the evaporant and the incident angle of the electron beam on the surface of the evaporant. This dependence leads also to the undesired effects to the target layers from electrons and ions. Some precautions are necessary against the effects of the electrons and ions, which are formed in the plasma directly over the beam impact point. Beam power and beam density have to be chosen to get a constant evaporation rate and a low enough condensation rate in order not to overheat the target substrates. To evaporate some metals it may be helpful to pulse the electron beam

Developing Fabrication Technologies to Provide On Demand Manufacturing for Exploration of the Moon and Mars

Science.gov (United States)

Hammond, Monica S.; Good, James E.; Gilley, Scott D.; Howard, Richard W.

2006-01-01

NASA's human exploration initiative poses great opportunity and risk for manned and robotic missions to the Moon, Mars, and beyond. Engineers and scientists at the Marshall Space Flight Center (MSFC) are developing technologies for in situ fabrication capabilities during lunar and Martian surface operations utilizing provisioned and locally refined materials. Current fabrication technologies must be advanced to support the special demands and applications of the space exploration initiative such as power, weight and volume constraints. In Situ Fabrication and Repair (ISFR) will advance state-of-the-art technologies in support of habitat structure development, tools, and mechanical part fabrication. The repair and replacement of space mission components, such as life support items or crew exercise equipment, fall within the ISFR scope. This paper will address current fabrication technologies relative to meeting ISFR targeted capabilities, near-term advancement goals, and systematic evaluation of various fabrication methods.

Overview on the target fabrication facilities at ELI-NP and ongoing strategies

Science.gov (United States)

Gheorghiu, C. C.; Leca, V.; Popa, D.; Cernaianu, M. O.; Stutman, D.

2016-10-01

Along with the development of petawatt class laser systems, the interaction between high power lasers and matter flourished an extensive research, with high-interest applications like: laser nuclear physics, proton radiography or cancer therapy. The new ELI-NP (Extreme Light Infrastructure - Nuclear Physics) petawatt laser facility, with 10PW and ~ 1023W/cm2 beam intensity, is one of the innovative projects that will provide novel research of fundamental processes during light-matter interaction. As part of the ELI-NP facility, Targets Laboratory will provide the means for in-house manufacturing and characterization of the required targets (mainly solid ones) for the experiments, in addition to the research activity carried out in order to develop novel target designs with improved performances. A description of the Targets Laboratory with the main pieces of equipment and their specifications are presented. Moreover, in view of the latest progress in the target design, one of the proposed strategies for the forthcoming experiments at ELI-NP is also described, namely: ultra-thin patterned foil of diamond-like carbon (DLC) coated with a carbon-based ultra-low density layer. The carbon foam which behaves as a near-critical density plasma, will allow the controlled-shaping of the laser pulse before the main interaction with the solid foil. Particular emphasis will be directed towards the target's design optimization, by simulation tests and tuning the key-properties (thickness/length, spacing, density foam, depth, periodicity etc.) which are expected to have a crucial effect on the laser-matter interaction process.

Light-ion spectroscopy with exotic targets

International Nuclear Information System (INIS)

Struble, G.L.; Lanier, R.G.

1992-01-01

Understanding the rich and diverse aspects underlying the physics of nuclear structure requires a variety of experimental techniques. In our laboratory, we have concentrated on experimental techniques using light-ion probes and isotopes that are technically difficult to fabricate into targets. In particular, our studies of p-, d-, and t-induced nuclear reactions on the radioactive targets of 152,154 Eu and 148 Gd have illuminated some very specific and very interesting features of nuclear structure near the N = 89 shape-transition region

Electroforming copper targets for RTNS-II

International Nuclear Information System (INIS)

Kelley, W.K.; Dini, J.W.; Logan, C.M.

1981-01-01

Copper targets used in RTNS II, which is the world's most intense 14-MeV neutron source, contain water cooling channels for temperature control. There are two methods for fabricating these targets: (1) diffusion bonding a copper panel containing photoetched channels to another copper panel, and (2) an electroforming technique which involves filling the photoetched channels with wax, plating thick copper to seal over the channels and then removing the wax. Development of this latter process and results obtained with it are described

Fabrication of 94Zr thin target for RDM lifetime measurement

International Nuclear Information System (INIS)

Gupta, Chandan Kumar; Rohilla, Aman; Chamoli, S.K.; Abhilash, S.R.; Kabiraj, D.; Singh, R.P.; Mehta, D.

2013-01-01

The aim of the activity was to make a thin target of isotopically enriched 94 Zr for lifetime measurement experiment to be done with the plunger setup at the Inter University Accelerator Center (IUAC) Delhi

Fabrication and characterization of UV-emitting nanoparticles as novel radiation sensitizers targeting hypoxic tumor cells

Science.gov (United States)

Squillante, Michael R.; Jüstel, Thomas; Anderson, R. Rox; Brecher, Charles; Chartier, Daniel; Christian, James F.; Cicchetti, Nicholas; Espinoza, Sara; McAdams, Daniel R.; Müller, Matthias; Tornifoglio, Brooke; Wang, Yimin; Purschke, Martin

2018-06-01

Radiation therapy is one of the primary therapeutic techniques for treating cancer, administered to nearly two-thirds of all cancer patients. Although largely effective in killing cancer cells, radiation therapy, like other forms of cancer treatment, has difficulty dealing with hypoxic regions within solid tumors. The incomplete killing of cancer cells can lead to recurrence and relapse. The research presented here is investigating the enhancement of the efficacy of radiation therapy by using scintillating nanoparticles that emit UV photons. UV photons, with wavelengths between 230 nm and 280 nm, are able to inactivate cells due to their direct interaction with DNA, causing a variety of forms of damage. UV-emitting nanoparticles will enhance the treatment in two ways: first by generating UV photons in the immediate vicinity of cancer cells, leading to direct and oxygen-independent DNA damage, and second by down-converting the applied higher energy X-rays into softer X-rays and particles that are more efficiently absorbed in the targeted tumor region. The end result will be nanoparticles with a higher efficacy in the treatment of hypoxic cells in the tumor, filling an important, unmet clinical need. Our preliminary experiments show an increase in cell death using scintillating LuPO4:Pr nanoparticles over that achieved by the primary radiation alone. This work describes the fabrication of the nanoparticles, their physical characterization, and the spectroscopic characterization of the UV emission. The work also presents in vitro results that demonstrate an enhanced efficacy of cell killing with x-rays and a low unspecific toxicity of the nanoparticles.

In-Space Repair and Refurbishment of Thermal Protection System Structures for Reusable Launch Vehicles

Science.gov (United States)

Singh, M.

2007-01-01

Advanced repair and refurbishment technologies are critically needed for the thermal protection system of current space transportation systems as well as for future launch and crew return vehicles. There is a history of damage to these systems from impact during ground handling or ice during launch. In addition, there exists the potential for in-orbit damage from micrometeoroid and orbital debris impact as well as different factors (weather, launch acoustics, shearing, etc.) during launch and re-entry. The GRC developed GRABER (Glenn Refractory Adhesive for Bonding and Exterior Repair) material has shown multiuse capability for repair of small cracks and damage in reinforced carbon-carbon (RCC) material. The concept consists of preparing an adhesive paste of desired ceramic with appropriate additives and then applying the paste to the damaged/cracked area of the RCC composites with an adhesive delivery system. The adhesive paste cures at 100-120 C and transforms into a high temperature ceramic during reentry conditions. A number of plasma torch and ArcJet tests were carried out to evaluate the crack repair capability of GRABER materials for Reinforced Carbon-Carbon (RCC) composites. For the large area repair applications, Integrated Systems for Tile and Leading Edge Repair (InSTALER) have been developed and evaluated under various ArcJet testing conditions. In this presentation, performance of the repair materials as applied to RCC is discussed. Additionally, critical in-space repair needs and technical challenges are reviewed.

Utility-vendor partnerships for refurbishment projects

Energy Technology Data Exchange (ETDEWEB)

Newman, G.; Hall, H. [Bruce Power, Tiverton, Ontario (Canada)

2012-07-01

closely with our Vendor community to ensure that our policies, programs and procedures are rigorous, transparent and well understood such that these requirements can be implemented in a timely and cost effective manner. At Bruce Power we value the skills and products that our Vendor community brings to our business and it is our intention to work carefully through this process to ensure that we collectively achieve the quality level required to ensure safe, reliable operation of our plants. In the context of Utility – Vendor Partnerships from a commercial perspective; Bruce Power has established a Vendor Performance Management System (VPMS) to support a structured approach to identify supplier strengths and weaknesses and to assist in the selection and management of our vendor base. Utilizing field initiated Station Condition Reports (SCR’s) and Non Conformance Reports (NCR’s) to establish good, average and substandard performance data points by commodity and contract, the VPMS facilitates data mining of performance information to establish a profile of how a supplier performs. SCR’s and NCR’s are backstopped by commercially generated SCAR Supplier Corrective Action Reports which allows Bruce Power to monitor vendor corrective actions.The VPMS approach permits Bruce Power to have a data based evaluation vs. an opinion based performance scorecard. Although in it’s preliminary stages this system will eventually help Bruce Power verify by commodity how vendors are performing which will in turn allow Bruce Power to enable an exit strategy for a poor performing vendor while strategically developing vendors to fill identified gaps. This capability will act as a cornerstone segment in our approach to Utility – Vendor Partnerships for Refurbishment by establishing performance data points on cost, quality and schedule delivery. Our success in being able to strategically apply this model will depend upon stable outage, generation and capital improvement plans as well

Utility-vendor partnerships for refurbishment projects

International Nuclear Information System (INIS)

Newman, G.; Hall, H.

2012-01-01

closely with our Vendor community to ensure that our policies, programs and procedures are rigorous, transparent and well understood such that these requirements can be implemented in a timely and cost effective manner. At Bruce Power we value the skills and products that our Vendor community brings to our business and it is our intention to work carefully through this process to ensure that we collectively achieve the quality level required to ensure safe, reliable operation of our plants. In the context of Utility – Vendor Partnerships from a commercial perspective; Bruce Power has established a Vendor Performance Management System (VPMS) to support a structured approach to identify supplier strengths and weaknesses and to assist in the selection and management of our vendor base. Utilizing field initiated Station Condition Reports (SCR’s) and Non Conformance Reports (NCR’s) to establish good, average and substandard performance data points by commodity and contract, the VPMS facilitates data mining of performance information to establish a profile of how a supplier performs. SCR’s and NCR’s are backstopped by commercially generated SCAR Supplier Corrective Action Reports which allows Bruce Power to monitor vendor corrective actions.The VPMS approach permits Bruce Power to have a data based evaluation vs. an opinion based performance scorecard. Although in it’s preliminary stages this system will eventually help Bruce Power verify by commodity how vendors are performing which will in turn allow Bruce Power to enable an exit strategy for a poor performing vendor while strategically developing vendors to fill identified gaps. This capability will act as a cornerstone segment in our approach to Utility – Vendor Partnerships for Refurbishment by establishing performance data points on cost, quality and schedule delivery. Our success in being able to strategically apply this model will depend upon stable outage, generation and capital improvement plans as well

Fabrication of superhydrophobic cotton fabrics using crosslinking polymerization method

Science.gov (United States)

Jiang, Bin; Chen, Zhenxing; Sun, Yongli; Yang, Huawei; Zhang, Hongjie; Dou, Haozhen; Zhang, Luhong

2018-05-01

With the aim of removing and recycling oil and organic solvent from water, a facile and low-cost crosslinking polymerization method was first applied on surface modification of cotton fabrics for water/oil separation. Micro-nano hierarchical rough structure was constructed by triethylenetetramine (TETA) and trimesoyl chloride (TMC) that formed a polymeric layer on the surface of the fabric and anchored Al2O3 nanoparticles firmly between the fabric surface and the polymer layer. Superhydrophobic property was further obtained through self-assembly grafting of hydrophobic groups on the rough surface. The as-prepared cotton fabric exhibited superoleophilicity in atmosphere and superhydrophobicity both in atmosphere and under oil with the water contact angle of 153° and 152° respectively. Water/oil separation test showed that the as-prepared cotton fabric can handle with various oil-water mixtures with a high separation efficiency over 99%. More importantly, the separation efficiency remained above 98% over 20 cycles of reusing without losing its superhydrophobicity which demonstrated excellent reusability in oil/water separation process. Moreover, the as-prepared cotton fabric possessed good contamination resistance ability and self-cleaning property. Simulation washing process test showed the superhydrophobic cotton fabric maintained high value of water contact angle above 150° after 100 times washing, indicating great stability and durability. In summary, this work provides a brand-new way to surface modification of cotton fabric and makes it a promising candidate material for oil/water separation.

In search of a holistic, sustainable and replicable model for complete energy refurbishment in historic buildings

Directory of Open Access Journals (Sweden)

Marija S. Todorović

2012-12-01

Full Text Available The reduction of greenhouse gas emissions in buildings offers one of the most promising opportunities for developed and developing countries to cooperate in achieving the realization of significant energy efficiency improvements. However, achieving sustainability is not an easy task unless there is synergy with/between energy efficiency improvement and renewable energy sources (RES - these are not at present in widespread dissemination and use. This paper recognizes the synergetic relationship between conservation and sustainability. At present, the role of heritage conservation in achieving sustainability has not yet been fully recognized, nor have heritage needs been well integrated into sustainability initiatives. Historic buildings are inherently sustainable. Preservation maximizes the use of existing materials and infrastructures, reduces waste, and preserves the historical character of older towns and cities. Sustainability begins with preservation. Taking into account the original climatic adaptations of historic buildings, today’s sustainable technology can supplement inherent sustainable features without compromising their unique historical character. Furthermore, a number of paper reviews and case studies with related methodologies outline the need to implement the latest current knowledge and technologies (BPS - Building Performance Simulation and CFD - Computational Fluid Dynamics for use in the refurbishment design process, as well as highlighting the crucial importance of sustainability, relevant benchmarking and rating system development.

An inexpensive and fast method for infiltration coating of complex geometry matrices for ISOL production target applications

International Nuclear Information System (INIS)

Kawai, Y.; Alton, G.D.; Bilheux, J.-C.

2005-01-01

An inexpensive, fast, and close to universal infiltration coating technique has been developed for fabricating fast diffusion-release ISOL targets. Targets are fabricated by deposition of finely divided (∼1μm) compound materials in a paint-slurry onto highly permeable, complex structure reticulated-vitreous-carbon-foam (RVCF) matrices, followed by thermal heat treatment. In this article, we describe the coating method and present information on the physical integrity, uniformity of deposition, and matrix adherence of SiC, HfC and UC 2 targets, destined for on-line use as targets at the Holifield Radioactive Ion Beam Facility (HRIBF)

INFLUENCE OF FABRIC TIGHTNESS ON SPIRALITY OF WEFTKNITTED PLAIN COTTON FABRIC

Directory of Open Access Journals (Sweden)

A.K.M. Mobarok Hossain

2011-01-01

Full Text Available Global demand for knitted garments is growing at a faster rate than that of woven items.Currently around 50% of clothing needs in the developed countries is met by knit goods. So ensuring the required quality in a knitted fabric is a vital issue for the manufacturer. One of the major problems encountered in knitted fabric is spirality. It affects particularly single jersey fabric and presents a serious problem during garment confection and use. So controlling spirality is a basic requirement for producing quality knitted fabric. Though there are several factors that contribute to knitted fabric spirality, yarn twist and relative tightness of the fabric are said tobe the most significant ones. In this work the basic single jersey fabric, i.e. plain jersey cotton fabrics were produced by a Hosiery knitting machine and spirality values were observed for different yarn T.P.I. and tightness factor at relaxed state. It was found that tightness factor has a direct influence on knitted fabric spirality with a high degree of correlation. The work thus gives an idea to deal this problem by controlling the knitting parameters.

Fabrication of small-orifice fuel injectors for diesel engines.

Energy Technology Data Exchange (ETDEWEB)

Woodford, J. B.; Fenske, G. R.

2005-04-08

Diesel fuel injector nozzles with spray hole diameters of 50-75 {micro}m have been fabricated via electroless nickel plating of conventionally made nozzles. Thick layers of nickel are deposited onto the orifice interior surfaces, reducing the diameter from {approx}200 {micro}m to the target diameter. The nickel plate is hard, smooth, and adherent, and covers the orifice interior surfaces uniformly.

Control of the interaction strength of photonic molecules by nanometer precise 3D fabrication.

Science.gov (United States)

Rawlings, Colin D; Zientek, Michal; Spieser, Martin; Urbonas, Darius; Stöferle, Thilo; Mahrt, Rainer F; Lisunova, Yuliya; Brugger, Juergen; Duerig, Urs; Knoll, Armin W

2017-11-28

Applications for high resolution 3D profiles, so-called grayscale lithography, exist in diverse fields such as optics, nanofluidics and tribology. All of them require the fabrication of patterns with reliable absolute patterning depth independent of the substrate location and target materials. Here we present a complete patterning and pattern-transfer solution based on thermal scanning probe lithography (t-SPL) and dry etching. We demonstrate the fabrication of 3D profiles in silicon and silicon oxide with nanometer scale accuracy of absolute depth levels. An accuracy of less than 1nm standard deviation in t-SPL is achieved by providing an accurate physical model of the writing process to a model-based implementation of a closed-loop lithography process. For transfering the pattern to a target substrate we optimized the etch process and demonstrate linear amplification of grayscale patterns into silicon and silicon oxide with amplification ratios of ∼6 and ∼1, respectively. The performance of the entire process is demonstrated by manufacturing photonic molecules of desired interaction strength. Excellent agreement of fabricated and simulated structures has been achieved.

Facile fabrication of a superhydrophobic fabric with mechanical stability and easy-repairability.

Science.gov (United States)

Zhu, Xiaotao; Zhang, Zhaozhu; Yang, Jin; Xu, Xianghui; Men, Xuehu; Zhou, Xiaoyan

2012-08-15

The poor mechanical stability of superhydrophobic fabrics severely hindered their use in practical applications. Herein, to address this problem, we fabricated a superhydrophobic fabric with both mechanical stability and easy-repairability by a simple method. The mechanical durability of the obtained superhydrophobic fabric was evaluated by finger touching and abrasion with sandpaper. The results show that rough surface textures of the fabric were retained, and the fabric surface still exhibited superhydrophobicity after tests. More importantly, when the fabric lost its superhydrophobicity after a long-time abrasion, it can be easily rendered with superhydrophobicity once more by a regeneration process. Copyright © 2012 Elsevier Inc. All rights reserved.

Material engineering to fabricate rare earth erbium thin films for exploring nuclear energy sources

Science.gov (United States)

Banerjee, A.; Abhilash, S. R.; Umapathy, G. R.; Kabiraj, D.; Ojha, S.; Mandal, S.

2018-04-01

High vacuum evaporation and cold-rolling techniques to fabricate thin films of the rare earth lanthanide-erbium have been discussed in this communication. Cold rolling has been used for the first time to successfully fabricate films of enriched and highly expensive erbium metal with areal density in the range of 0.5-1.0 mg/cm2. The fabricated films were used as target materials in an advanced nuclear physics experiment. The experiment was designed to investigate isomeric states in the heavy nuclei mass region for exploring physics related to nuclear energy sources. The films fabricated using different techniques varied in thickness as well as purity. Methods to fabricate films with thickness of the order of 0.9 mg/cm2 were different than those of 0.4 mg/cm2 areal density. All the thin films were characterized using multiple advanced techniques to accurately ascertain levels of contamination as well as to determine their exact surface density. Detailed fabrication methods as well as characterization techniques have been discussed.

Preparation of Au cone for fast ignition target

International Nuclear Information System (INIS)

Du Kai; Zhou Lan; Zhang Lin; Wan Xiaobo; Xiao Jiang

2005-01-01

Cone-shell target is typically used for the fast ignition experiments of inertial confinement fusion. In order to fabricate cone-shell target the Au cones with different angles were produced by electroplating and precise machining. The Au electroplating process was introduced in the paper, and the dependence of coating quality on the parameters, such as composition, temperature, pH of electroplating bath, current density and tip effect, were discussed. (author)

Investigation of methods for fabricating, characterizing, and transporting cryogenic inertial-confinement-fusion tartets

Energy Technology Data Exchange (ETDEWEB)

Fanning, J.J.; Kim, K.

1981-01-01

The objective of this work is to investigate methods for fabricating, characterizing and transporting cryogenic inertial confinement fusion targets on a continuous basis. A microprocessor-based data acquisition system has been built that converts a complete target image to digital data, which are then analyzed by automated software procedures. The low temperatures required to freeze the hydrogen isotopes contained in a target is provided by a cryogenic cold chamber capable of attaining 15 K. A new method for target manipulation and positioning is studied that employs molecular gas beams to levitate a target and an electrostatic quadrupole structure to provide for its lateral containment. Since the electrostatic target-positioning scheme requires that the targets be charged, preliminary investigation has been carried out for a target-charging mechanism based on ion-bombardment.

Investigation of methods for fabricating, characterizing, and transporting cryogenic inertial-confinement-fusion tartets

International Nuclear Information System (INIS)

Fanning, J.J.; Kim, K.

1981-01-01

The objective of this work is to investigate methods for fabricating, characterizing and transporting cryogenic inertial confinement fusion targets on a continuous basis. A microprocessor-based data acquisition system has been built that converts a complete target image to digital data, which are then analyzed by automated software procedures. The low temperatures required to freeze the hydrogen isotopes contained in a target is provided by a cryogenic cold chamber capable of attaining 15 K. A new method for target manipulation and positioning is studied that employs molecular gas beams to levitate a target and an electrostatic quadrupole structure to provide for its lateral containment. Since the electrostatic target-positioning scheme requires that the targets be charged, preliminary investigation has been carried out for a target-charging mechanism based on ion-bombardment

Electroless plating technology of integral hohlraum Cu target

International Nuclear Information System (INIS)

Liu Jiguang; Fu Qu; Wan Xiaobo; Zhou Lan; Xiao Jiang

2005-01-01

The electroless plating method of making integral hohlraum Cu target and corrosion-resistant technology of target's surface were researched. The actual process was as follows, choosing plexiglass (PMMA) as arbor, taking cationic activation and electroless plating Cu on the arbor surface, taking arbor surface passivation and chemical etching by C 6 H 5 N 3 solution. The technology is easy to realize and its cost is lower, so it is of great reference value for fabricating other integral hohlraum metal or alloy targets used for inertial confinement fusion study. (author)

The development of uranium foil farication technology utilizing twin roll method for Mo-99 irradiation target

CERN Document Server

Kim, C K; Park, H D

2002-01-01

MDS Nordion in Canada, occupying about 75% of global supply of Mo-99 isotope, has provided the irradiation target of Mo-99 using the rod-type UAl sub x alloys with HEU(High Enrichment Uranium). ANL (Argonne National Laboratory) through co-operation with BATAN in Indonesia, leading RERTR (Reduced Enrichment for Research and Test Reactors) program substantially for nuclear non-proliferation, has designed and fabricated the annular cylinder of uranium targets, and successfully performed irradiation test, in order to develop the fabrication technology of fission Mo-99 using LEU(Low Enrichment Uranium). As the uranium foils could be fabricated in laboratory scale, not in commercialized scale by hot rolling method due to significant problems in foil quality, productivity and economic efficiency, attention has shifted to the development of new technology. Under these circumstances, the invention of uranium foil fabrication technology utilizing twin-roll casting method in KAERI is found to be able to fabricate LEU or...

Fabrication and characterization of tungsten and graphite based PFC for divertor target elements of ITER like tokamak application

Energy Technology Data Exchange (ETDEWEB)

Khirwadkar, S.S., E-mail: sameer@ipr.res.in [Institute For Plasma Research, Bhat, Gandhinagar, Gujarat (India); Singh, K.P.; Patil, Y.; Khan, M.S.; Buch, J.J.U.; Patel, Alpesh; Tripathi, Sudhir [Institute For Plasma Research, Bhat, Gandhinagar, Gujarat (India); Jaman, P.M.; Rangaraj, L.; Divakar, C. [Materials Science Division, National Aerospace Laboratories, CSIR, Bangalore, Karnataka (India)

2011-10-15

The development of the fabrication technology of macro-brush configuration of tungsten (W) and carbon (graphite and CFC) plasma facing components (PFCs) for ITER like tokamak application is presented. The fabrication of qualified joint of PFC is a requirement for fusion tokamak. Vacuum brazing method has been employed for joining of W/CuCrZr and C/CuCrZr. Oxygen free high conductivity (OFHC) copper casting on W tiles was performed followed by machining, polishing and ultrasonic cleaning of the samples prior to vacuum brazing. The W/CuCrZr and graphite/CuCrZr based test mockups were vacuum brazed using silver free alloys. The mechanical shear and tensile strengths were evaluated for the W/CuCrZr and graphite/CuCrZr brazed joint samples. The micro-structural examination of the joints showed smooth interface. The details of fabrication and characterization procedure for macro-brush tungsten and carbon based PFC test mockups are presented.

Fabric circuits and method of manufacturing fabric circuits

Science.gov (United States)

Chu, Andrew W. (Inventor); Dobbins, Justin A. (Inventor); Scully, Robert C. (Inventor); Trevino, Robert C. (Inventor); Lin, Greg Y. (Inventor); Fink, Patrick W. (Inventor)

2011-01-01

A flexible, fabric-based circuit comprises a non-conductive flexible layer of fabric and a conductive flexible layer of fabric adjacent thereto. A non-conductive thread, an adhesive, and/or other means may be used for attaching the conductive layer to the non-conductive layer. In some embodiments, the layers are attached by a computer-driven embroidery machine at pre-determined portions or locations in accordance with a pre-determined attachment layout before automated cutting. In some other embodiments, an automated milling machine or a computer-driven laser using a pre-designed circuit trace as a template cuts the conductive layer so as to separate an undesired portion of the conductive layer from a desired portion of the conductive layer. Additional layers of conductive fabric may be attached in some embodiments to form a multi-layer construct.

Fabrication Facilities

Data.gov (United States)

Federal Laboratory Consortium — The Fabrication Facilities are a direct result of years of testing support. Through years of experience, the three fabrication facilities (Fort Hood, Fort Lewis, and...

Energy analysis and refurbishment proposals for public housing in the city of Bari, Italy

International Nuclear Information System (INIS)

Di Turi, Silvia; Stefanizzi, Pietro

2015-01-01

From the perspectives of the energy and the environment, building stock should be considered a useful resource in the struggle against greenhouse gas emissions and scarcity of energy resources. The aim of this work is to provide an example of the application of a methodology to evaluate the energy needs of the building stock of a city and to determine the possible strategies for energy planning. This paper aims to obtain an estimate, on an urban scale, of the energy needs and CO 2 emissions of the public residential buildings of Bari. This estimate is achieved by evaluating the critical issues of the built heritage, the most common architectural typologies and the heating systems in the territory of the city of Bari in southern Italy, as well as the possible strategies for upgrading energy efficiency, through the combined use of energy software and geo-referenced systems. Furthermore, several possible interventions are assumed to improve the energy performance of buildings in not only environmental terms but also economic terms through the instrument of cost–benefit analysis. The ultimate goal is to compare the different intervention strategies to determine which demonstrate greater cost effectiveness and feasibility for future energy planning. - Highlights: • An evaluation of the energy needs of existing buildings in a city in Southern Italy is provided. • Possible refurbishment strategies are evaluated. • An economic analysis is carried out to understand the feasibility of interventions. • An estimate on an urban scale of the energy-saving potential of public housing in Bari is provided

Engineering structure design and fabrication process of small sized China helium-cooled solid breeder test blanket module

International Nuclear Information System (INIS)

Wang Zeming; Chen Lu; Hu Gang

2014-01-01

Preliminary design and analysis for china helium-cooled solid breeder (CHHC-SB) test blanket module (TBM) have been carried out recently. As partial verification that the original size module was reasonable and the development process was feasible, fabrication work of a small sized module was to be carried out targetedly. In this paper, detailed design and structure analysis of small sized TBM was carried out based on preliminary design work, fabrication process and integrated assembly process was proposed, so a fabrication for the trial engineering of TBM was layed successfully. (authors)

High pressure deuterium-tritium gas target vessels for muon-catalyzed fusion experiments

International Nuclear Information System (INIS)

Caffrey, A.J.; Spaletta, H.W.; Ware, A.G.; Zabriskie, J.M.; Hardwick, D.A.; Maltrud, H.R.; Paciotti, M.A.

1989-01-01

In experimental studies of muon-catalyzed fusion, the density of the hydrogen gas mixture is an important parameter. Catalysis of up to 150 fusions per muon has been observed in deuterium-tritium gas mixtures at liquid hydrogen density; at room temperature, such densities require a target gas pressure of the order of 1000 atmospheres (100 MPa, 15,000 psi). We report here the design considerations for hydrogen gas target vessels for muon-catalyzed fusion experiments that operate at 1000 and 10,000 atmospheres. The 1000 atmosphere high pressure target vessels are fabricated of Type A-286 stainless steel and lined with oxygen-free, high-conductivity (OFHC) copper to provide a barrier to hydrogen permeation of the stainless steel. The 10,000 atmosphere ultrahigh pressure target vessels are made from 18Ni (200 grade) maraging steel and are lined with OFHC copper, again to prevent hydrogen permeation of the steel. In addition to target design features, operating requirements, fabrication procedures, and secondary containment are discussed. 13 refs., 3 figs., 1 tab

Polyester fabric coated with Ag/ZnO composite film by magnetron sputtering

Energy Technology Data Exchange (ETDEWEB)

Yuan, Xiaohong, E-mail: yxhong1981_2004@126.com [Key Laboratory of Eco-Textiles, Ministry of Education, Jiangnan University, Wuxi 214122, Jiangsu (China); Faculty of Clothing and Design, Minjiang University, Fuzhou 350121, Fujian (China); Xu, Wenzheng, E-mail: xwz8199@126.com [Key Laboratory of Eco-Textiles, Ministry of Education, Jiangnan University, Wuxi 214122, Jiangsu (China); Huang, Fenglin, E-mail: windhuang325@163.com [Key Laboratory of Eco-Textiles, Ministry of Education, Jiangnan University, Wuxi 214122, Jiangsu (China); Chen, Dongsheng, E-mail: mjuchen@126.com [Faculty of Clothing and Design, Minjiang University, Fuzhou 350121, Fujian (China); Wei, Qufu, E-mail: qfwei@jiangnan.edu.cn [Key Laboratory of Eco-Textiles, Ministry of Education, Jiangnan University, Wuxi 214122, Jiangsu (China)

2016-12-30

Highlights: • Ag/ZnO composite film was successfully deposited on polyester fabric by magnetron sputtering technique. • Ag film was easily oxidized into Ag{sub 2}O film in high vacuum oxygen environment. • The zinc film coated on the surface of Ag film before RF reactive sputtering could protect the silver film from oxidation. • Polyester fabric coated with Ag/ZnO composite film can obtained structural color. • The anti-ultraviolet and antistatic properties of polyester fabric coated with Ag/ZnO composite film all were good. - Abstract: Ag/ZnO composite film was successfully deposited on polyester fabric by using direct current (DC) magnetron sputtering and radio frequency (RF) magnetron reaction sputtering techniques with pure silver (Ag) and zinc (Zn) targets. X-ray photoelectron spectroscopy (XPS) and X-ray diffraction (XRD) were used to examine the deposited film on the fabric. It was found that the zinc film coated on Ag film before RF reactive sputtering could protect the silver film from oxidation. Anti-ultraviolet property and antistatic property of the coated samples using different magnetron sputtering methods were also investigated. The experimental results showed that Ag film was oxidized into in Ag{sub 2}O film in high vacuum oxygen environment. The deposition of Zn film on the surface of the fabric coated with Ag film before RF reactive sputtering, could successfully obtained Ag/ZnO composite film, and also generated structural color on the polyester fabric.

Simple method to generate and fabricate stochastic porous scaffolds

Energy Technology Data Exchange (ETDEWEB)

Yang, Nan, E-mail: y79nzw@163.com; Gao, Lilan; Zhou, Kuntao

2015-11-01

Considerable effort has been made to generate regular porous structures (RPSs) using function-based methods, although little effort has been made for constructing stochastic porous structures (SPSs) using the same methods. In this short communication, we propose a straightforward method for SPS construction that is simple in terms of methodology and the operations used. Using our method, we can obtain a SPS with functionally graded, heterogeneous and interconnected pores, target pore size and porosity distributions, which are useful for applications in tissue engineering. The resulting SPS models can be directly fabricated using additive manufacturing (AM) techniques. - Highlights: • Random porous structures are constructed based on their regular counterparts. • Functionally graded random pores can be constructed easily. • The scaffolds can be directly fabricated using additive manufacturing techniques.

Recent developments in laser-fusion target coatings

International Nuclear Information System (INIS)

Fries, R.J.; Catlett, D.S.; Fossey, D.; Mayer, A.; McCreary, W.J.; Powell, B.W.; Simonsic, G.A.

1976-01-01

Techniques to fabricate hollow, spherical, multilayered laser-fusion targets are described. The first is a glow discharge polymerization process for plastic coating. A chemical vapor deposition process for depositing Mo/Re alloys is also discussed along with some new techniques for electrodeless plating and for electroplating a wide variety of metals

Preventing Clogging In A Vacuum Plasma Spray Gun

Science.gov (United States)

Krotz, Phillip D.; Daniel, Ronald L., Jr.; Davis, William M.

1994-01-01

Modification of powder-injection ports enables lengthy, high-temperature deposition operations. Graphite inserts prevent clogging of ports through which copper powder injected into vacuum plasma spray (VPS) gun. Graphite liners eliminate need to spend production time refurbishing VPS gun, reducing cost of production and increasing productivity. Concept also applied to other material systems used for net-shape fabrication via VPS.

DUPIC facility engineering

International Nuclear Information System (INIS)

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

2002-03-01

With starting DUPIC fuel fabrication experiment by using spent fuels, 1) operation and refurbishment for DFDF (DUPIC fuel development facility), and 2) operation and improvement of transportation equipment for radioactive materials between facilities became the objectives of this study. This report describes objectives of the project, necessities, state of related technology, R and D scope, R and D results, proposal for application etc

An investigation on preparation of CIGS targets by sintering process

Energy Technology Data Exchange (ETDEWEB)

Zhang Ning, E-mail: zhn98@126.co [Department of Mechanical Engineering, Tsinghua University, Beijing 100084 (China); Zhuang Daming; Zhang Gong [Department of Mechanical Engineering, Tsinghua University, Beijing 100084 (China)

2010-01-15

Pressureless sintering process was used to fabricate CIGS targets with Cu{sub 2}Se, In{sub 2}Se{sub 3}, and Ga{sub 2}Se{sub 3} as raw powders mixed according to the stoichiometry of CuIn{sub 0.72}Ga{sub 0.28}Se{sub 2} (CIGS). The results showed that only CuIn{sub 0.7}Ga{sub 0.3}Se{sub 2} phase can be detected in the sintered targets. The pores in sintered specimen become smaller and distribute more homogeneously under the conditions of finer powders and higher cold pressure. Both mass loss caused by the formation of volatile phase relating to Ga and volume expansion occur during the sintering process, which result in the decrease of density. The tendency of anti-densification becomes stronger under the conditions of coarser powders and higher cold pressure. The sintering process and causes for anti-densification were discussed. Finally, a hot pressing process was carried out, which was proved to be fairly effective to increase the density of CIGS target. The fabricated target can be used for magnetron-sputtering deposition of CIGS absorbers.

Progress on LMJ targets for ignition

Energy Technology Data Exchange (ETDEWEB)

Cherfils-Clerouin, C; Boniface, C; Bonnefille, M; Dattolo, E; Galmiche, D; Gauthier, P; Giorla, J; Laffite, S; Liberatore, S; Loiseau, P; Malinie, G; Masse, L; Masson-Laborde, P E; Monteil, M C; Poggi, F; Seytor, P; Wagon, F; Willien, J L, E-mail: catherine.cherfils@cea.f [CEA, DAM, DIF, F-91297 Arpajon (France)

2009-12-15

Targets designed to produce ignition on the Laser Megajoule (LMJ) are being simulated in order to set specifications for target fabrication. The LMJ experimental plans include the attempt of ignition and burn of an ICF capsule with 160 laser beams, delivering up to 1.4 MJ and 380 TW. New targets needing reduced laser energy with only a small decrease in robustness have then been designed for this purpose. Working specifically on the coupling efficiency parameter, i.e. the ratio of the energy absorbed by the capsule to the laser energy, has led to the design of a rugby-ball shaped cocktail hohlraum; with these improvements, a target based on the 240-beam A1040 capsule can be included in the 160-beam laser energy-power space. Robustness evaluations of these different targets shed light on critical points for ignition, which can trade off by tightening some specifications or by preliminary experimental and numerical tuning experiments.

Progress on LMJ targets for ignition

International Nuclear Information System (INIS)

Cherfils-Clerouin, C; Boniface, C; Bonnefille, M; Dattolo, E; Galmiche, D; Gauthier, P; Giorla, J; Laffite, S; Liberatore, S; Loiseau, P; Malinie, G; Masse, L; Masson-Laborde, P E; Monteil, M C; Poggi, F; Seytor, P; Wagon, F; Willien, J L

2009-01-01

Targets designed to produce ignition on the Laser Megajoule (LMJ) are being simulated in order to set specifications for target fabrication. The LMJ experimental plans include the attempt of ignition and burn of an ICF capsule with 160 laser beams, delivering up to 1.4 MJ and 380 TW. New targets needing reduced laser energy with only a small decrease in robustness have then been designed for this purpose. Working specifically on the coupling efficiency parameter, i.e. the ratio of the energy absorbed by the capsule to the laser energy, has led to the design of a rugby-ball shaped cocktail hohlraum; with these improvements, a target based on the 240-beam A1040 capsule can be included in the 160-beam laser energy-power space. Robustness evaluations of these different targets shed light on critical points for ignition, which can trade off by tightening some specifications or by preliminary experimental and numerical tuning experiments.

Fabrication of 121Sb isotopic targets for the study of nuclear high spin features

Science.gov (United States)

Devi, K. Rojeeta; Kumar, Suresh; Kumar, Neeraj; Abhilash, S. R.; Kabiraj, D.

2018-06-01

Isotopic 121Sb targets with 197Au backing have been prepared by Physical Vapor Deposition (PVD) method using the diffusion pump based coating unit at target laboratory, Inter University Accelerator Centre (IUAC), New Delhi, India. The target thickness was measured by stylus profilo-meter and the purity of the targets was investigated by Energy Dispersive X-ray Analysis (EDXA). One of these targets has been used in an experiment which was performed at IUAC for nuclear structure study through fusion evaporation reaction. The excitation function of the 121Sb(12C, yxnγ) reaction has been performed for energies 58 to 70 MeV in steps of 4 MeV. The experimental results were compared with the calculations of statistical models : PACE4 and CASCADE. The methods adopted to achieve best quality foils and good deposition efficiency are reported in this paper.

Development of IFE target systems on the NIF

International Nuclear Information System (INIS)

Schultz, K.R.; Fagaly, R.L.; Bernat, T.; Meier, W.; Petzoldt, R.; Foreman, L.

1995-01-01

The Target Systems session of the Workshop on NIF Experiments for IFE developed a list of critical issues for inertial fusion energy (IFE) target systems, and considered the potential of the National Ignition Facility (NIF) to help in the resolution of these issues and in the development of IFE target systems. This paper describes the IFE Target System issues, categorized into target fabrication issues and target transport issues, describes potential NIF IFE target systems experiments, considers the impact of these experiments on the NIF and discusses the development required before these experiments could be done. Most target systems issues must be resolved by development in the laboratory, not in the NIF, and some must be resolved before the NIF can be successful. However, experiments done in the NIF could play a valuable role in developing target systems for IFE. These experiments should have modest impact on the basic design of the NIF, but could require several hundred dedicated, high yield shots

Fabrication of high-quality single-crystal Cu thin films using radio-frequency sputtering.

Science.gov (United States)

Lee, Seunghun; Kim, Ji Young; Lee, Tae-Woo; Kim, Won-Kyung; Kim, Bum-Su; Park, Ji Hun; Bae, Jong-Seong; Cho, Yong Chan; Kim, Jungdae; Oh, Min-Wook; Hwang, Cheol Seong; Jeong, Se-Young

2014-08-29

Copper (Cu) thin films have been widely used as electrodes and interconnection wires in integrated electronic circuits, and more recently as substrates for the synthesis of graphene. However, the ultra-high vacuum processes required for high-quality Cu film fabrication, such as molecular beam epitaxy (MBE), restricts mass production with low cost. In this work, we demonstrated high-quality Cu thin films using a single-crystal Cu target and radio-frequency (RF) sputtering technique; the resulting film quality was comparable to that produced using MBE, even under unfavorable conditions for pure Cu film growth. The Cu thin film was epitaxially grown on an Al2O3 (sapphire) (0001) substrate, and had high crystalline orientation along the (111) direction. Despite the 10(-3) Pa vacuum conditions, the resulting thin film was oxygen free due to the high chemical stability of the sputtered specimen from a single-crystal target; moreover, the deposited film had >5× higher adhesion force than that produced using a polycrystalline target. This fabrication method enabled Cu films to be obtained using a simple, manufacturing-friendly process on a large-area substrate, making our findings relevant for industrial applications.

IFR fuel cycle process equipment design environment and objectives

International Nuclear Information System (INIS)

Rigg, R.H.

1993-01-01

Argonne National laboratory (ANL) is refurbishing the hot cell facility originally constructed with the EBR-II reactor. When refurbishment is complete, the facility win demonstrate the complete fuel cycle for current generation high burnup metallic fuel elements. These are sodium bonded, stainless steel clad fuel pins of U-Zr or U-Pu-Zr composition typical of the fuel type proposed for a future Integral Fast Reactor (IFR) design. To the extent possible, the process equipment is being built at full commercial scale, and the facility is being modified to incorporate current DOE facility design requirements and modem remote maintenance principles. The current regulatory and safety environment has affected the design of the fuel fabrication equipment, most of which will be described in greater detail in subsequent papers in this session

Fabrication and characterisation of composite targets for the transmutation of actinides

International Nuclear Information System (INIS)

Naestren, C.; Haas, D.; Fernandez, A.; Somers, J.

2006-01-01

Transmutation of transuranic elements separated from spent fuel is a way to reduce the toxicity of long-lived nuclides in the waste before disposal. Plutonium and the minor actinides (MA) are reintroduced into the fuel cycle for further irradiation and incineration. Currently CERMET fuel forms, in which a ceramic actinide is dispersed in a matrix, are considered for MA transmutation. In a first step, PuO 2 beads are produced by a sol gel method in which a Pu nitrate solution is converted to solid, dust-free, particles. These porous beads are then infiltrated with an americium nitrate solution to the incipient wetness point and calcined to give the (PuAm)O 2 beads, which are blended with a metal matrix and compacted and sintered to form the final fuel pellet. The matrix used is molybdenum due to its high thermal conductivity and low neutron capture cross section, if it is enriched in 92 Mo. In this work, optimization of the bead porosity is investigated to achieve a higher Am content by infiltration. Addition of carbon to the mother solution in the sol gel step increases the bead porosity but it also changes both bead and final fuel pellet microstructure. A surrogate fuel, with cerium simulating the actinides has been fabricated and its mechanical stability and bead characteristics investigated as a function of carbon content and thermal treatment. The characterization of the surrogate fuel by ceramography, density, porosity, bead-quality, etc., is a necessary step in the process optimization, to be transferred to the production of the actinide samples. This process is now at an advanced stage and is being used for the production of fuels for irradiation tests in the Phenix (Futurix) and HFR-Petten (HELIOS) reactors. In parallel, studies on the dissolution of the fuel pellets, with the aim of dissolving the Mo-matrix while keeping the CeO 2 beads intact, have been initiated. Thus, Mo can be recycled for further fuel fabrication either from production scraps or from

Digital fabrication

CERN Document Server

2012-01-01

The Winter 2012 (vol. 14 no. 3) issue of the Nexus Network Journal features seven original papers dedicated to the theme “Digital Fabrication”. Digital fabrication is changing architecture in fundamental ways in every phase, from concept to artifact. Projects growing out of research in digital fabrication are dependent on software that is entirely surface-oriented in its underlying mathematics. Decisions made during design, prototyping, fabrication and assembly rely on codes, scripts, parameters, operating systems and software, creating the need for teams with multidisciplinary expertise and different skills, from IT to architecture, design, material engineering, and mathematics, among others The papers grew out of a Lisbon symposium hosted by the ISCTE-Instituto Universitario de Lisboa entitled “Digital Fabrication – A State of the Art”. The issue is completed with four other research papers which address different mathematical instruments applied to architecture, including geometric tracing system...

Impact of neutron and gamma radiation on the design of NIF diagnostics and target-bay systems

Energy Technology Data Exchange (ETDEWEB)

Eder, D.C.; Song, P.M.; Latkowski, J.F.; Reyes, S.; O' Brien, D.W.; Lee, F.D.; Young, B.K.; Koch, J.A.; Moran, M.J.; Watts, P.W.; Kimbrough, J.R.; Ng, E.W.; Landen, O.L.; MacGowan, B.J. [Lawrence Livermore National Lab., Livermore, CA (United States)

2006-06-15

The design of a wide range of components in and near the target bay of the National Ignition Facility (NIF) must allow for significant radiation from neutrons and gammas. Detailed 3-dimensional Monte Carlo simulations are critical to determine neutron and gamma fluxes for all target-bay components to allow optimization of location and auxiliary shielding. Demonstration of ignition poses unique challenges because of the large range (about 3 orders of magnitude) in the yield for any given attempt at ignition. Some diagnostics will provide data independent of yield, while others will provide data for lower yields and only survive high yields with little or no damage. In addition, for a given yield there is a more than 10 orders of magnitude range in neutron and gamma fluxes depending on location in the facility. For example, sensitive components in the diagnostic mezzanines and switchyards require auxiliary shielding for high-yield shots even though they are greater than 17 meters from target chamber center (TCC) and shielded by the 2 m-thick target-bay wall. In contrast, there are components 0.2 to 2 m from TCC with little or no shielding. For these components, particular attention is being made to use low-activation material because of the extremely high neutron loading levels. Many of the components closest to target center are designed to be single use to reduce worker dose from having to refurbish highly activated components. The cryogenic target positioner is an example where activation and ease of component replacement is an important part of the design. We are developing a design process for all target-bay systems that will assure reliable operation for the full range of planned yields. (authors)

Impact of neutron and gamma radiation on the design of NIF diagnostics and target-bay systems

Science.gov (United States)

Eder, D. C.; Song, P. M.; Latkowski, J. F.; Reyes, S.; O'Brien, D. W.; Lee, F. D.; Young, B. K.; Koch, J. A.; Moran, M. J.; Watts, P. W.; Kimbrough, J. R.; Ng, E. W.; Landen, O. L.; MacGowan, B. J.

2006-06-01

The design of a wide range of components in and near the target bay of the National Ignition Facility (NIF) must allow for significant radiation from neutrons and gammas. Detailed 3D Monte Carlo simulations are critical to determine neutron and gamma fluxes for all target-bay components to allow optimization of location and auxiliary shielding. Demonstration of ignition poses unique challenges because of the large range (˜ 3 orders of magnitude) in the yield for any given attempt at ignition. Some diagnostics will provide data independent of yield, while others will provide data for lower yields and only survive high yields with little or no damage. In addition, for a given yield there is a more than 10 orders of magnitude range in neutron and gamma fluxes depending on location in the facility. For example, sensitive components in the diagnostic mezzanines and switchyards require auxiliary shielding for high-yield shots even though they are greater than 17 meters from target chamber center (TCC) and shielded by the 2 m-thick target-bay wall. In contrast, there are components 0.2 to 2 m from TCC with little or no shielding. For these components, particular attention is being made to use low-activation material because of the extremely high neutron loading levels. Many of the components closest to target center are designed to be single use to reduce worker dose from having to refurbish highly activated components. The cryogenic target positioner is an example where activation and ease of component replacement is an important part of the design. We are developing a design process for all target-bay systems that will assure reliable operation for the full range of planned yields.

Target developments program to prepare LMJ campaigns

Energy Technology Data Exchange (ETDEWEB)

Collier, R; Bachelet, F; Botrel, R; Breton, O; Chicanne, C; Dauteuil, C H; Durut, F; Fleury, E; Guillot, L; Hermerel, C; Jeannot, L; Legaie, O; Legay, G; Martin, M; Reneaume, B; Theobald, M; Vincent-Viry, O, E-mail: remy.collier@cea.f [Commissariat a l' Energie Atomique, Direction des Applications Militaires, Valduc, F-21120 Is-sur-Tille (France)

2010-08-01

To carry out laser plasma experiments on CEA laser facilities, a R and D program was set up and is still under way to deliver complex targets. For a decade, specific developments are also dedicated to 'Ligne d'Integration Laser' (LIL) in France and Omega facilities (USA). To prepare the targets intended for the first experiments on the Laser 'Megajoule' (LMJ) facility, new developments are required, such as cocktail hohlraum fabrication, gas barrier coating and foam shells developments. For fusion experiments on LMJ, an important program is also under way to elaborate the Cryogenic Target Assembly (CTA), to fill and transport the CTA and to study the conformation process of the DT layer.

Fabric based supercapacitor

International Nuclear Information System (INIS)

Yong, S; Tudor, M J; Beeby, S P; Owen, J R

2013-01-01

Flexible supercapacitors with electrodes coated on inexpensive fabrics by the dipping technique. This paper present details of the design, fabrication and characterisation of fabric supercapacitor. The sandwich structured supercapacitors can achieve specific capacitances of 11.1F/g, area capacitance 105 mF.cm −2 and maintain 95% of the initial capacitance after cycling the device for more than 15000 times

Pulsed-laser-deposited YBCO thin films using modified MTG processed targets

CERN Document Server

Kim, C H; Kim, I T; Hahn, T S

1999-01-01

YBCO thin films were deposited by pulsed laser deposition from targets fabricated using the modified melt-textured growth (MTG) method and the solid-state sintering (SSS) method. All of the films showed c-axis orientations, but the films from the MTG targets had better crystallinity than those from the SSS targets. As the substrate temperature was increased, T sub c and J sub c of the films increased. The films from the MTG targets showed better superconducting properties than those from the SSS targets. From the composition analysis of the targets, the Y-richer vapor species arriving at the substrate from the MTG targets are thought to form a thermodynamically more stable YBCO phase with less cation disorder.

Fabrication of cotton fabric with superhydrophobicity and flame retardancy.

Science.gov (United States)

Zhang, Ming; Wang, Chengyu

2013-07-25

A simple and facile method for fabricating the cotton fabric with superhydrophobicity and flame retardancy is described in the present work. The cotton fabric with the maximal WCA of 160° has been prepared by the covalent deposition of amino-silica nanospheres and the further graft with (heptadecafluoro-1,1,2,2-tetradecyl) trimethoxysilane. The geometric microstructure of silica spheres was measured by transmission electron microscopy (TEM). The cotton textiles before and after treatment were characterized by using scanning electron microscope (SEM) and X-ray photoelectron spectroscopy (XPS). The wetting behavior of cotton samples was investigated by water contact angle measurement. Moreover, diverse performances of superhydrophobic cotton textiles have been evaluated as well. The results exhibited the outstanding superhydrophobicity, excellent waterproofing durability and flame retardancy of the cotton fabric after treatment, offering a good opportunity to accelerate the large-scale production of superhydrophobic textiles materials for new industrial applications. Copyright © 2013 Elsevier Ltd. All rights reserved.

Mars 2020 Rover SHERLOC Calibration Target

Science.gov (United States)

Graff, Trevor; Fries, Marc; Burton, Aaron; Ross, Amy; Larson, Kristine; Garrison, Dan; Calaway, Mike; Tran, Vinh; Bhartia, Roh; Beegle, Luther

2016-01-01

The Scanning Habitable Environments with Raman & Luminescence for Organics & Chemicals (SHERLOC) instrument is a deep ultraviolet (UV) Raman Fluorescence instrument selected as part of the Mars 2020 rover instrument suite. SHERLOC will be mounted on the rover arm and its primary role is to identify carbonaceous species in martian samples. The SHERLOC instrument requires a calibration target which is being designed and fabricated at JSC as part of our continued science participation in Mars robotic missions. The SHERLOC calibration target will address a wide range of NASA goals to include basic science of interest to both the Science Mission Directorate and Human Exploration and Operations Mission Directorate.

Nuclear Fabrication Consortium

Energy Technology Data Exchange (ETDEWEB)

Levesque, Stephen [EWI, Columbus, OH (United States)

2013-04-05

This report summarizes the activities undertaken by EWI while under contract from the Department of Energy (DOE) Office of Nuclear Energy (NE) for the management and operation of the Nuclear Fabrication Consortium (NFC). The NFC was established by EWI to independently develop, evaluate, and deploy fabrication approaches and data that support the re-establishment of the U.S. nuclear industry: ensuring that the supply chain will be competitive on a global stage, enabling more cost-effective and reliable nuclear power in a carbon constrained environment. The NFC provided a forum for member original equipment manufactures (OEM), fabricators, manufacturers, and materials suppliers to effectively engage with each other and rebuild the capacity of this supply chain by : Identifying and removing impediments to the implementation of new construction and fabrication techniques and approaches for nuclear equipment, including system components and nuclear plants. Providing and facilitating detailed scientific-based studies on new approaches and technologies that will have positive impacts on the cost of building of nuclear plants. Analyzing and disseminating information about future nuclear fabrication technologies and how they could impact the North American and the International Nuclear Marketplace. Facilitating dialog and initiate alignment among fabricators, owners, trade associations, and government agencies. Supporting industry in helping to create a larger qualified nuclear supplier network. Acting as an unbiased technology resource to evaluate, develop, and demonstrate new manufacturing technologies. Creating welder and inspector training programs to help enable the necessary workforce for the upcoming construction work. Serving as a focal point for technology, policy, and politically interested parties to share ideas and concepts associated with fabrication across the nuclear industry. The report the objectives and summaries of the Nuclear Fabrication Consortium

Proceedings of JSPS-CAS core university program seminar on target materials

International Nuclear Information System (INIS)

Gu, Z.Z.; Norimatsu, T.

2008-02-01

China-Japan Bilateral Collaboration on the Study of Ultrahigh Density Plasma has been established since 2001 and its second phase is conducting from 2006. Target materials are key issue of the Study of Ultrahigh Density Plasma, and the second of target fabrication was opened at the 2005 Workshop on Ultrahigh Density Plasma Production, Application and theory for Laser Fusion at Nine Village Valley, Sichuan. It achieved great successes in high-level academic exchange and efficient presentation of state-of-the-art development in this research field. However, in order to attract greater attention and participation of more scientists in these fields, the organizing committee decided to further specify and enlarge the scale of the workshop to be China-Japan Bilateral Seminar on Target Materials 2007 in Huang Shan in southern Anhui Province of east China. The seminar had more than 20 participants from 7 universities and 3 institutes in Japan and China. They exchanged state-of-the-art development in nanomaterials, capsule fabrication and low density materials toward target of high power laser. This issue is the collection of the paper presented at the seminar. The 17 of the presented papers are indexed individually. (J.P.N.)

New polymorphous computing fabric

International Nuclear Information System (INIS)

Wolinski, Christophe; Gokhale, Maya; McCabe, Kevin P.

2002-01-01

This paper introduces a new polymorphous computing Fabric well suited to DSP and Image Processing and describes its implementation on a Configurable System on a Chip (CSOC). The architecture is highly parameterized and enables customization of the synthesized Fabric to achieve high performance for a specific class of application. For this reason it can be considered to be a generic model for hardware accelerator synthesis from a high level specification. Another important innovation is the Fabric uses a global memory concept, which gives the host processor random access to all the variables and instructions on the Fabric. The Fabric supports different computing models including MIMD, SPMD and systolic flow and permits dynamic reconfiguration. We present a specific implementation of a bank of FIR filters on a Fabric composed of 52 cells on the Altera Excalibur ARM running at 33 MHz. The theoretical performance of this Fabric is 1.8 GMACh. For the FIR application we obtain 1.6 GMAC/s real performance. Some automatic tools have been developed like the tool to provide a host access utility and assembler.

Secure Automated Fabrication: an overview of remote breeder fuel fabrication

International Nuclear Information System (INIS)

Nyman, D.H.; Graham, R.A.

1983-10-01

The Secure Automated Fabrication (SAF) line is an automated, remotely controlled breeder fuel pin fabrication process which is to be installed in the Fuels and Materials Examination Facility (FMEF). The FMEF is presently under construction at Hanford and is scheduled for completion in 1984. The SAF line is scheduled for startup in 1987 and will produce mixed uranium-plutonium fuel pins for the Fast Flux Test Facility (FFTF) and the Clinch River Breeder Reactor Plant (CRBRP). The fabrication line and support systems are described

Design and fabrication of self-powered in-core neutron flux monitor assembly

International Nuclear Information System (INIS)

Chung, M.K.; Cho, S.W.; Kang, H.D.; Cho, K.K.; Cho, B.S.; Kang, S.S.

1980-01-01

This is the final report on the prototypical fabrication of an in-core neutron flux monitor detector assembly for a specific power reactor conducted by KAERI from July 1, 1978 to December 31, 1979. It is well known that power reactors require a large number of in-core neutron flux detector for reactor regulation and the structures of detector assemblies are different from reactor to reactor. Therefore, from the nature of this project, it should be noted here that the target model of the prototypical farbrication of an in-core neutron flux monitor detector assembly is a VFD-2 System for Wolsung CANDU. It is concluded that fabrication of in-core neutron flux monitor detector assembly for CANDU reactor is technically feasible and will bring economical benefit as much as 50 % of the unit price if they are fabricated in Korea by using partially materials which are available from local market. (author)

Fabric Reconstruction Based on Sustainable Development: Take the Type of Fabric Recycling as an Example

Directory of Open Access Journals (Sweden)

Zhangting Guan

2017-07-01

Full Text Available Sustainable development is a very important concept of our time, it wants to do is to live in harmony with people, to protect the environment where our human survival. Fabric recycling refers to the use of a variety of traditional and high-tech means of the existing fabric fabric design and processing. So that the surface of a rich visual texture and tactile texture "through the fabric recycling approach. However, the fabric form and clothing design coordination between the clothing design is essential to the link! Garment fabric is not only the material basis of clothing modeling But also an important form of plastic arts. Fabric recycling art has gradually become a new breakthrough point of fashion design! And become an important means to increase the added value of clothing products. But at the same time fabric recycling also follow the concept of sustainable development. This paper analyzes the relationship between fabric reengineering and sustainable development. Combined with practice to explore the fabric processing technology and its creative ideas and some of its environmental performance.

Single-step laser-based fabrication and patterning of cell-encapsulated alginate microbeads

International Nuclear Information System (INIS)

Kingsley, D M; Dias, A D; Corr, D T; Chrisey, D B

2013-01-01

Alginate can be used to encapsulate mammalian cells and for the slow release of small molecules. Packaging alginate as microbead structures allows customizable delivery for tissue engineering, drug release, or contrast agents for imaging. However, state-of-the-art microbead fabrication has a limited range in achievable bead sizes, and poor control over bead placement, which may be desired to localize cellular signaling or delivery. Herein, we present a novel, laser-based method for single-step fabrication and precise planar placement of alginate microbeads. Our results show that bead size is controllable within 8%, and fabricated microbeads can remain immobilized within 2% of their target placement. Demonstration of this technique using human breast cancer cells shows that cells encapsulated within these microbeads survive at a rate of 89.6%, decreasing to 84.3% after five days in culture. Infusing rhodamine dye into microbeads prior to fluorescent microscopy shows their 3D spheroidal geometry and the ability to sequester small molecules. Microbead fabrication and patterning is compatible with conventional cellular transfer and patterning by laser direct-write, allowing location-based cellular studies. While this method can also be used to fabricate microbeads en masse for collection, the greatest value to tissue engineering and drug delivery studies and applications lies in the pattern registry of printed microbeads. (paper)

Design and Fabrication of DebriSat - A Representative LEO Satellite for Improvements to Standard Satellite Breakup Models

Science.gov (United States)

Clark, S.; Dietrich, A.; Fitz-Coy, N.; Weremeyer, M.; Liou, J.-C.

2012-01-01

This paper discusses the design and fabrication of DebriSat, a 50 kg satellite developed to be representative of a modern low Earth orbit satellite in terms of its components, materials used, and fabrication procedures. DebriSat will be the target of a future hypervelocity impact experiment to determine the physical characteristics of debris generated after an on-orbit collision of a modern LEO satellite. The major ground-based satellite impact experiment used by DoD and NASA in their development of satellite breakup models was SOCIT, conducted in 1992. The target used for that experiment was a Navy transit satellite (40 cm, 35 kg) fabricated in the 1960's. Modern satellites are very different in materials and construction techniques than those built 40 years ago. Therefore, there is a need to conduct a similar experiment using a modern target satellite to improve the fidelity of the satellite breakup models. To ensure that DebriSat is truly representative of typical LEO missions, a comprehensive study of historical LEO satellite designs and missions within the past 15 years for satellites ranging from 1 kg to 5000 kg was conducted. This study identified modern trends in hardware, material, and construction practices utilized in recent LEO missions. Although DebriSat is an engineering model, specific attention is placed on the quality, type, and quantity of the materials used in its fabrication to ensure the integrity of the outcome. With the exception of software, all other aspects of the satellite s design, fabrication, and assembly integration and testing will be as rigorous as that of an actual flight vehicle. For example, to simulate survivability of launch loads, DebriSat will be subjected to a vibration test. As well, the satellite will undergo thermal vacuum tests to verify that the components and overall systems meet typical environmental standards. Proper assembly and integration techniques will involve comprehensive joint analysis, including the precise

Production and characterization of thin 7Li targets fabricated by ion implantation

International Nuclear Information System (INIS)

Cruz, J.; Fonseca, M.; Luis, H.; Mateus, R.; Marques, H.; Jesus, A.P.; Ribeiro, J.P.; Teodoro, O.M.N.D.; Rolfs, C.

2009-01-01

Very high fluence implantation of 7 Li + ions was used to promote the formation of a thin and high density 7 Li target in the surface region of Al samples. The implanted volume was characterized by particle induced gamma-ray emission, Rutherford backscattering spectrometry, X-ray photoelectron spectroscopy and nuclear reaction analysis, revealing that the implanted surface is a combination of Li 2 CO 3 , metallic lithium, LiOH and C, with almost no Al present. Radiation damage effects by proton beams were studied by observing the evolution of the 7 Li(p, α) 4 He nuclear reaction yield with the accumulated charge, at different proton energies, revealing high stability of the produced Li target.

Optimum processing parameters for the fabrication of twill flax fabric-reinforced polypropylene (PP) composites

Science.gov (United States)

Zuhudi, Nurul Zuhairah Mahmud; Minhat, Mulia; Shamsuddin, Mohd Hafizi; Isa, Mohd Dali; Nur, Nurhayati Mohd

2017-12-01

In recent years, natural fabric thermoplastic composites such as flax have received much attention due to its attractive capabilities for structural applications. It is crucial to study the processing of flax fabric materials in order to achieve good quality and cost-effectiveness in fibre reinforced composites. Though flax fabric has been widely utilized for several years in composite applications due to its high strength and abundance in nature, much work has been concentrated on short flax fibre and very little work focused on using flax fabric. The effectiveness of the flax fabric is expected to give higher strength performance due to its structure but the processing needs to be optimised. Flax fabric composites were fabricated using compression moulding due to its simplicity, gives good surface finish and relatively low cost in terms of labour and production. Further, the impregnation of the polymer into the fabric is easier in this process. As the fabric weave structure contributes to the impregnation quality which leads to the overall performance, the processing parameters of consolidation i.e. pressure, time, and weight fraction of fabric were optimized using the Taguchi method. This optimization enhances the consolidation quality of the composite by improving the composite mechanical properties, three main tests were conducted i.e. tensile, flexural and impact test. It is observed that the processing parameter significantly affected the consolidation and quality of composite.

Fabrication of three-dimensional scaffolds using precision extrusion deposition with an assisted cooling device.

Science.gov (United States)

Hamid, Q; Snyder, J; Wang, C; Timmer, M; Hammer, J; Guceri, S; Sun, W

2011-09-01

In the field of biofabrication, tissue engineering and regenerative medicine, there are many methodologies to fabricate a building block (scaffold) which is unique to the target tissue or organ that facilitates cell growth, attachment, proliferation and/or differentiation. Currently, there are many techniques that fabricate three-dimensional scaffolds; however, there are advantages, limitations and specific tissue focuses of each fabrication technique. The focus of this initiative is to utilize an existing technique and expand the library of biomaterials which can be utilized to fabricate three-dimensional scaffolds rather than focusing on a new fabrication technique. An expanded library of biomaterials will enable the precision extrusion deposition (PED) device to construct three-dimensional scaffolds with enhanced biological, chemical and mechanical cues that will benefit tissue generation. Computer-aided motion and extrusion drive the PED to precisely fabricate micro-scaled scaffolds with biologically inspired, porosity, interconnectivity and internal and external architectures. The high printing resolution, precision and controllability of the PED allow for closer mimicry of tissues and organs. The PED expands its library of biopolymers by introducing an assisting cooling (AC) device which increases the working extrusion temperature from 120 to 250 °C. This paper investigates the PED with the integrated AC's capabilities to fabricate three-dimensional scaffolds that support cell growth, attachment and proliferation. Studies carried out in this paper utilized a biopolymer whose melting point is established to be 200 °C. This polymer was selected to illustrate the newly developed device's ability to fabricate three-dimensional scaffolds from a new library of biopolymers. Three-dimensional scaffolds fabricated with the integrated AC device should illustrate structural integrity and ability to support cell attachment and proliferation.

Fabrication of three-dimensional scaffolds using precision extrusion deposition with an assisted cooling device

International Nuclear Information System (INIS)

Hamid, Q; Snyder, J; Wang, C; Guceri, S; Sun, W; Timmer, M; Hammer, J

2011-01-01

In the field of biofabrication, tissue engineering and regenerative medicine, there are many methodologies to fabricate a building block (scaffold) which is unique to the target tissue or organ that facilitates cell growth, attachment, proliferation and/or differentiation. Currently, there are many techniques that fabricate three-dimensional scaffolds; however, there are advantages, limitations and specific tissue focuses of each fabrication technique. The focus of this initiative is to utilize an existing technique and expand the library of biomaterials which can be utilized to fabricate three-dimensional scaffolds rather than focusing on a new fabrication technique. An expanded library of biomaterials will enable the precision extrusion deposition (PED) device to construct three-dimensional scaffolds with enhanced biological, chemical and mechanical cues that will benefit tissue generation. Computer-aided motion and extrusion drive the PED to precisely fabricate micro-scaled scaffolds with biologically inspired, porosity, interconnectivity and internal and external architectures. The high printing resolution, precision and controllability of the PED allow for closer mimicry of tissues and organs. The PED expands its library of biopolymers by introducing an assisting cooling (AC) device which increases the working extrusion temperature from 120 to 250 deg. C. This paper investigates the PED with the integrated AC's capabilities to fabricate three-dimensional scaffolds that support cell growth, attachment and proliferation. Studies carried out in this paper utilized a biopolymer whose melting point is established to be 200 deg. C. This polymer was selected to illustrate the newly developed device's ability to fabricate three-dimensional scaffolds from a new library of biopolymers. Three-dimensional scaffolds fabricated with the integrated AC device should illustrate structural integrity and ability to support cell attachment and proliferation.

International light water nuclear fuel fabrication supply. Are fabrication services assured?

International Nuclear Information System (INIS)

Rothwell, Geoffrey

2010-01-01

This paper examines the cost structure of fabricating light water reactor (LWR) fuel with low-enriched uranium (LEU, with less than 5% enrichment). The LWR-LEU fuel industry is decades old, and (except for the high entry cost of designing and licensing a fuel fabrication facility and its fuel), labor and additional fabrication lines can be added at Nth-of-a-Kind cost to the maximum capacity allowed by a site license. The industry appears to be competitive: nuclear fuel fabrication capacity is assured with many competitors and reasonable prices. However, nuclear fuel assurance has become an important issue for nations now to considering new nuclear power plants. To provide this assurance many proposals equate 'nuclear fuel banks' (which would require fuel for specific reactors) with 'LEU banks' (where LEU could be blended into nuclear fuel with the proper enrichment) with local fuel fabrication. The policy issues (which are presented, but not answered in this paper) become (1) whether the construction of new nuclear fuel fabrication facilities in new nuclear power nations could lead to the proliferation of nuclear weapons, and (2) whether nuclear fuel quality can be guaranteed under current industry arrangements, given that fuel failure at one reactor can lead to forced shutdowns at many others. (author)

Fabrication of Ultrasensitive Field-Effect Transistor DNA Biosensors by a Directional Transfer Technique Based on CVD-Grown Graphene.

Science.gov (United States)

Zheng, Chao; Huang, Le; Zhang, Hong; Sun, Zhongyue; Zhang, Zhiyong; Zhang, Guo-Jun

2015-08-12

Most graphene field-effect transistor (G-FET) biosensors are fabricated through a routine process, in which graphene is transferred onto a Si/SiO2 substrate and then devices are subsequently produced by micromanufacture processes. However, such a fabrication approach can introduce contamination onto the graphene surface during the lithographic process, resulting in interference for the subsequent biosensing. In this work, we have developed a novel directional transfer technique to fabricate G-FET biosensors based on chemical-vapor-deposition- (CVD-) grown single-layer graphene (SLG) and applied this biosensor for the sensitive detection of DNA. A FET device with six individual array sensors was first fabricated, and SLG obtained by the CVD-growth method was transferred onto the sensor surface in a directional manner. Afterward, peptide nucleic acid (PNA) was covalently immobilized on the graphene surface, and DNA detection was realized by applying specific target DNA to the PNA-functionalized G-FET biosensor. The developed G-FET biosensor was able to detect target DNA at concentrations as low as 10 fM, which is 1 order of magnitude lower than those reported in a previous work. In addition, the biosensor was capable of distinguishing the complementary DNA from one-base-mismatched DNA and noncomplementary DNA. The directional transfer technique for the fabrication of G-FET biosensors is simple, and the as-constructed G-FET DNA biosensor shows ultrasensitivity and high specificity, indicating its potential application in disease diagnostics as a point-of-care tool.

Preparation of homogeneous isotopic targets with rotating substrate

International Nuclear Information System (INIS)

Xu, G.J.; Zhao, Z.G.

1993-01-01

Isotopically enriched accelerator targets were prepared using the evaporation-condensation method from a resistance heating crucible. For high collection efficiency and good homogeneity the substrate was rotated at a vertical distance of 1.3 to 2.5 cm from the evaporation source. Measured collection efficiencies were 13 to 51 μg cm -2 mg -1 and homogeneity tests showed values close to the theoretically calculated ones for a point source. Targets, selfsupporting or on backings, could be fabricated with this method for elements and some compounds with evaporation temperatures up to 2300 K. (orig.)

UBERA-6 project: Achievements of 4 working years

International Nuclear Information System (INIS)

Blaumann, H; Fernandez, C; Dell Occhio, L; D Ovidio, C; Fabro, J; Miceli, M; Novara O; Perez, A; Taboada, H

2009-01-01

On May 2005 the President of CNEA created the UBERA-6 project, belonging to the former Technology and Environmental Management, with the aim to convert to Low Enriched Uranium (LEU) the RA-6 reactor core, to swap with the US Department of Energy (US-DoE) equivalent inventories of High Enriched Uranium (HEU) for LEU, to export to USA the spent HEU core and to recover and downblend to LEU remnant HEU inventories contained in fuel and irradiation target scraps. By means of two contracts signed by CNEA and US-DoE, acquisition of consumables and graphite reflectors, the fabrication of LEU core replacement, conditioning, transport and exportation of spent HEU core and subsequent supply of fresh LEU for fuel and irradiation targets used in our research reactors were costed. During July, 2006 468 HEU based fresh plates were exported to USA. On June 30th, 2007 the RA-6 reactor temporarily stopped working and its personnel remover the HEU core to the auxiliary pool. On November 7th the former spent HEU based core was exported to USA. During May and July, 2008 the new RA-6 reactor LEU based core and control assemblies were provided. During March, 2009 the RA-6 reactor became critical. For recovering and blending down of remnant HEU inventories, the Triple Height Laboratory (LTA) was refurbished. A Supplemental Agreement to one of the original contract between CNEA and US-DoE will financially support the refurbishment of the Radiochemical Facility Laboratory (LFR) and so reprocess irradiated HEU retained in radioisotope production filters to downblend into LEU, as well as the separation of the pair Sr90-Y90 and of Cs137 inventories for further application in Nuclear Medicine. [es

NIF Target Assembly Metrology Methodology and Results

Energy Technology Data Exchange (ETDEWEB)

Alger, E. T. [General Atomics, San Diego, CA (United States); Kroll, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dzenitis, E. G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Montesanti, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hughes, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Swisher, M. [IAP, Livermore, CA (United States); Taylor, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Segraves, K. [IAP, Livermore, CA (United States); Lord, D. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Reynolds, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Castro, C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Edwards, G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2011-01-01

During our inertial confinement fusion (ICF) experiments at the National Ignition Facility (NIF) we require cryogenic targets at the 1-cm scale to be fabricated, assembled, and metrologized to micron-level tolerances. During assembly of these ICF targets, there are physical dimensmetrology is completed using optical coordinate measurement machines that provide repeatable measurements with micron precision, while also allowing in-process data collection for absolute accuracy in assembly. To date, 51 targets have been assembled and metrologized, and 34 targets have been successfully fielded on NIF relying on these metrology data. In the near future, ignition experiments on NIF will require tighter tolerances and more demanding target assembly and metrology capability. Metrology methods, calculations, and uncertainty estimates will be discussed. Target diagnostic port alignment, target position, and capsule location results will be reviewed for the 2009 Energetics Campaign. The information is presented via control charts showing the effect of process improvements that were made during target production. Certain parameters, including capsule position, met the 2009 campaign specifications but will have much tighter requirements in the future. Finally, in order to meet these new requirements assembly process changes and metrology capability upgrades will be necessary.

Fabrication and Final Field Tuning of Copper Cavity Models for a High-Current SRF ERL at 703.75 MHz

CERN Document Server

Cole, Michael; Burger, Al; Falletta, Michael; Holmes, Douglas; Peterson, Ed; Wong, Robert

2005-01-01

Advanced Energy Systems is currently under contract to BNL to fabricate a five cell superconducting cavity and cryomodule for the RHIC eCooler SRF Energy Recovery Linac (ERL) program.* The cavity is designed and optimized for ampere class SRF ERL service. As part of this program, we have fabricated two low power copper models of the RF cavities. During the fabrication process a series of frequency measurements were made and compared to the frequency expected at that point in the fabrication process. Where possible, the cavity was modified either before or during, the next fabrication step to tune the cavity frequency toward the target frequency. Following completion of the cavities they were tuned for field flatness and frequency. This paper will review the measurements made, frequency tuning performed, and discuss discrepancies between the expected and measured results. We will also review the as fabricated field profiles and the results of the tuning steps. Further, the cost and benefits of extensive in pro...

Fabrication and wireless micromanipulation of magnetic-biocompatible microrobots using microencapsulation for microrobotics and microfluidics applications.

Science.gov (United States)

Li, Hui; Zhang, Jinyong; Zhang, Nannan; Kershaw, Joe; Wang, Lei

2016-12-01

It is important to fabricate biocompatible and chemical-resistant microstructures that can be powered and controlled without a tether in fluid environment for applications when contamination must be avoided, like cell manipulation, and applications where connecting the power source to the actuator would be cumbersome, like targeted delivery of chemicals. In this work, a novel fabrication method was described to encapsulate magnetic composite into pure SU-8 structures, enabling the truly microscale ferromagnetic microrobots biocompatible and chemical resistant. The microrobots were developed using the simple multilayer photolithography that allows us to mass produce and were actuated contact-free by external magnetic field to complete micromanipulations of micro-objects. The microrobots were actuated moving along a preplanned path to transport a glass microsphere object at an approximately average speed of 1.1 mm/sec and can be operated to rotate, aim at targets and collect objects.

Electrolytic coating of microparticles for laser fusion targets

International Nuclear Information System (INIS)

Mayer, A.; Catlett, D.S.

1977-04-01

An electroplating apparatus for applying uniform metallic coatings that have excellent surface finishes to discrete microparticles is described. The device is used to electrodeposit metals onto thin-walled metal, metallized glass, or plastic mandrels. The apparatus and process were developed for fabrication of microsphere pressure vessels to be used as targets in laser fusion research

A facile fabrication of multifunctional knit polyester fabric based on chitosan and polyaniline polymer nanocomposite

Energy Technology Data Exchange (ETDEWEB)

Tang, Xiaoning [College of Textiles, Qingdao University, Qingdao, Shandong 266071 (China); Laboratory of New Fiber Materials and Modern Textile, The Growing Base for State Key Laboratory, Qingdao University, Qingdao, Shandong 266071 (China); Tian, Mingwei [College of Textiles, Qingdao University, Qingdao, Shandong 266071 (China); Laboratory of New Fiber Materials and Modern Textile, The Growing Base for State Key Laboratory, Qingdao University, Qingdao, Shandong 266071 (China); Collaborative Innovation Center for Marine Biomass Fibers, Materials and Textiles of Shandong Province, Qingdao University, Qingdao, Shandong 266071 (China); Qu, Lijun, E-mail: lijunqu@126.com [College of Textiles, Qingdao University, Qingdao, Shandong 266071 (China); Laboratory of New Fiber Materials and Modern Textile, The Growing Base for State Key Laboratory, Qingdao University, Qingdao, Shandong 266071 (China); Collaborative Innovation Center for Marine Biomass Fibers, Materials and Textiles of Shandong Province, Qingdao University, Qingdao, Shandong 266071 (China); Zhu, Shifeng [College of Textiles, Qingdao University, Qingdao, Shandong 266071 (China); Laboratory of New Fiber Materials and Modern Textile, The Growing Base for State Key Laboratory, Qingdao University, Qingdao, Shandong 266071 (China); Guo, Xiaoqing [College of Textiles, Qingdao University, Qingdao, Shandong 266071 (China); Laboratory of New Fiber Materials and Modern Textile, The Growing Base for State Key Laboratory, Qingdao University, Qingdao, Shandong 266071 (China); Collaborative Innovation Center for Marine Biomass Fibers, Materials and Textiles of Shandong Province, Qingdao University, Qingdao, Shandong 266071 (China); Han, Guangting [Laboratory of New Fiber Materials and Modern Textile, The Growing Base for State Key Laboratory, Qingdao University, Qingdao, Shandong 266071 (China); Collaborative Innovation Center for Marine Biomass Fibers, Materials and Textiles of Shandong Province, Qingdao University, Qingdao, Shandong 266071 (China); and others

2014-10-30

Highlights: • Multifunctional knit polyester fabric was facile fabricated by the combination of pad-dry-cure process and in situ chemical polymerization route. • High electrical conductivity and efficient water-repellent properties were endowed to the polymer nanocomposite coated fabric. • The polymer nanocomposite coated fabric also performed efficient and durable photocatalytic activities under the illumination of ultraviolet light. - Abstract: Knit polyester fabric was successively modified and decorated with chitosan layer and polyaniline polymer nanocomposite layer in this paper. The fabric was firstly treated with chitosan to form a stable layer through the pad-dry-cure process, and then the polyaniline polymer nanocomposite layer was established on the outer layer by in situ chemical polymerization method using ammonium persulfate as oxidant and chlorhydric acid as dopant. The surface morphology of coated fabric was characterized by scanning electron microscopy (SEM), and the co-existence of chitosan layer and granular polyaniline polymer nanocomposite was confirmed and well dispersed on the fabric surface. The resultant fabric was endowed with remarkable electrical conductivity properties and efficient water-repellent capability, which also have been found stable after water laundering. In addition, the photocatalytic decomposition activity for reactive red dye was observed when the multifunctional knit polyester fabric was exposed to the illumination of ultraviolet lamp. These results indicated that chitosan and polyaniline polymer nanocomposite could form ideal multifunctional coatings on the surface of knit polyester fabric.

A facile fabrication of multifunctional knit polyester fabric based on chitosan and polyaniline polymer nanocomposite

International Nuclear Information System (INIS)

Tang, Xiaoning; Tian, Mingwei; Qu, Lijun; Zhu, Shifeng; Guo, Xiaoqing; Han, Guangting

2014-01-01

Highlights: • Multifunctional knit polyester fabric was facile fabricated by the combination of pad-dry-cure process and in situ chemical polymerization route. • High electrical conductivity and efficient water-repellent properties were endowed to the polymer nanocomposite coated fabric. • The polymer nanocomposite coated fabric also performed efficient and durable photocatalytic activities under the illumination of ultraviolet light. - Abstract: Knit polyester fabric was successively modified and decorated with chitosan layer and polyaniline polymer nanocomposite layer in this paper. The fabric was firstly treated with chitosan to form a stable layer through the pad-dry-cure process, and then the polyaniline polymer nanocomposite layer was established on the outer layer by in situ chemical polymerization method using ammonium persulfate as oxidant and chlorhydric acid as dopant. The surface morphology of coated fabric was characterized by scanning electron microscopy (SEM), and the co-existence of chitosan layer and granular polyaniline polymer nanocomposite was confirmed and well dispersed on the fabric surface. The resultant fabric was endowed with remarkable electrical conductivity properties and efficient water-repellent capability, which also have been found stable after water laundering. In addition, the photocatalytic decomposition activity for reactive red dye was observed when the multifunctional knit polyester fabric was exposed to the illumination of ultraviolet lamp. These results indicated that chitosan and polyaniline polymer nanocomposite could form ideal multifunctional coatings on the surface of knit polyester fabric

Photopatternable Magnetic Hollowbots by Nd-Fe-B Nanocomposite for Potential Targeted Drug Delivery Applications

Directory of Open Access Journals (Sweden)

Hui Li

2018-04-01

Full Text Available In contrast to traditional drug administration, targeted drug delivery can prolong, localize, target and have a protected drug interaction with the diseased tissue. Drug delivery carriers, such as polymeric micelles, liposomes, dendrimers, nanotubes, and so on, are hard to scale-up, costly, and have short shelf life. Here we show the novel fabrication and characterization of photopatternable magnetic hollow microrobots that can potentially be utilized in microfluidics and drug delivery applications. These magnetic hollowbots can be fabricated using standard ultraviolet (UV lithography with low cost and easily accessible equipment, which results in them being easy to scale up, and inexpensive to fabricate. Contact-free actuation of freestanding magnetic hollowbots were demonstrated by using an applied 900 G external magnetic field to achieve the movement control in an aqueous environment. According to the movement clip, the average speed of the magnetic hollowbots was estimated to be 1.9 mm/s.

Optimal and Sustainable Plant Refurbishment in Historical Buildings: A Study of an Ancient Monastery Converted into a Showroom in Florence

Directory of Open Access Journals (Sweden)

Carla Balocco

2013-04-01

Full Text Available The aim of this research is to study the possibility and sustainability of retrofit and refurbishment design solutions on historical buildings converted to different uses and often clashing with their original purpose and architectural features. The building studied is an ancient monastery located in the historical center of Florence (Italy. Today the original cloister is covered over by a single glazed pitched roof and used as a fashion showroom. Our proposed solution concerns a reversible and sustainable plant design integrated with an active transparent building casing. The existing glazed pitched roof was reconsidered and re-designed as part of the existing heating, ventilation and air conditioning (HVAC plant system, based on the functioning of an active thermal buffer to control the high heat flow rates and external thermal loads due to solar radiation. Hourly whole building energy analysis was carried out to check the effectiveness and energy sustainability of our proposed solution. Results obtained showed, from the historical-architectural, energy and environmental points of view, its sustainability due to the building-plant system integration and interaction with its location, the external climatic conditions and defined expected uses, in particular with reference to indoor thermal comfort.

Refurbishment priorities at the Russian coal-fired power sector for cleaner energy production-Case studies

International Nuclear Information System (INIS)

Grammelis, P.; Koukouzas, N.; Skodras, G.; Kakaras, E.; Tumanovsky, A.; Kotler, V.

2006-01-01

The paper aims to present the current status of the coal-fired power sector in Russia, the prospects for renovation activities based on Clean Coal Technologies (CCT) and two case studies on potential refurbishment projects. Data were collected for 180 thermoelectric units with capacity higher than 100 MWe and the renovation needs of the power sector, among the retrofitting, repowering and reconstruction options, were estimated through a multi-criteria analysis. The most attractive system to renovate a power plant between the Supercritical Combustion (SC) and the Fluidized Bed Combustion (FBC) technologies was evaluated. The application of each of the aforementioned technologies at the Kashirskaya and Shaturskaya power plants was studied and their replication potential in the Russian coal-fired power plant park was examined. Nowadays, the installed capacity of coal-fired power plants in the Russian Federation is 29.3 GWe, while they account for about 19% of the total electricity generation in the area. The low efficiency and especially the advanced age are the determinant factors for renovation applications at the Russian units. Even in the more conservative modernization scenario, over 30% of the thermoelectric units have to be repowered or reconstructed. Concrete proposals about the profitable and reliable operation of two Russian thermoelectric units with minimized environmental effects were elaborated. A new unit of 315 MWe with supercritical steam parameters and reburning for NO x abatement is envisaged to upgrade Unit 1 of Kashirskaya power station, while new Circulating Fluidized Bed (CFB) boilers of the same steam generation is the most promising renovation option for the boilers of Unit 1 in Shaturskaya power station

Refurbishment priorities at the Russian coal-fired power sector for cleaner energy production case studies

Energy Technology Data Exchange (ETDEWEB)

P. Grammelis; N. Koukouzas; G. Skodras; E. Kakaras; A. Tumanovsky; V. Kotler [Centre for Research and Technology Hellas/Institute of Solid Fuels Technology and Applications (CERTH/ISFTA), Ptolemaida (Greece)

2006-11-15

The paper reviews the current status of the coal-fired power sector in Russia, the prospects for renovation activities based on Clean Coal Technologies (CCT) and presents two case studies on potential refurbishment projects. Data were collected for 180 thermoelectric units with capacity higher than 100 MWe and the renovation needs of the power sector, among the retrofitting, repowering and reconstruction options, were estimated through a multi-criteria analysis. The most attractive system to renovate a power plant between the Supercritical Combustion (SC) and the Fluidized Bed Combustion (FBC) technologies was evaluated. The application of each of the aforementioned technologies at the Kashirskaya and Shaturskaya power plants was studied and their replication potential in the Russian coal-fired power plant park was examined. Nowadays, the installed capacity of coal-fired power plants in the Russian Federation is 29.3 GWe, while they account for about 19% of the total electricity generation in the area. The low efficiency and especially the advanced age are the determinant factors for renovation applications at the Russian units. Even in the more conservative modernization scenario, over 30% of the thermoelectric units have to be repowered or reconstructed. Concrete proposals about the profitable and reliable operation of two Russian thermoelectric units with minimized environmental effects were elaborated. A new unit of 315 MWe with supercritical steam parameters and reburning for NOx abatement is envisaged to upgrade Unit 1 of Kashirskaya power station, while new circulating fluidized bed (CFB) boilers of the same steam generation is the most promising renovation option for the boilers of Unit 1 in Shaturskaya power station. 11 refs., 15 figs., 7 tabs.

Refurbishment priorities at the Russian coal-fired power sector for cleaner energy production-Case studies

Energy Technology Data Exchange (ETDEWEB)

Grammelis, P. [Centre for Research and Technology Hellas/Institute of Solid Fuels Technology and Applications (CERTH/ISFTA), 4 km N.R. Ptolemaida-Kozani, P.O. Box 95, Ptolemaida 50200 (Greece) and Laboratory of Steam Boilers and Thermal Plants, Mechanical Engineering Department, National Technical University of Athens, Athens (Greece)]. E-mail: pgra@central.ntua.gr; Koukouzas, N. [Centre for Research and Technology Hellas/Institute of Solid Fuels Technology and Applications (CERTH/ISFTA), 4 km N.R. Ptolemaida-Kozani, P.O. Box 95, Ptolemaida 50200 (Greece); Skodras, G. [Centre for Research and Technology Hellas/Institute of Solid Fuels Technology and Applications (CERTH/ISFTA), 4 km N.R. Ptolemaida-Kozani, P.O. Box 95, Ptolemaida 50200 (Greece); Kakaras, E. [Centre for Research and Technology Hellas/Institute of Solid Fuels Technology and Applications (CERTH/ISFTA), 4 km N.R. Ptolemaida-Kozani, P.O. Box 95, Ptolemaida 50200 (Greece); Laboratory of Steam Boilers and Thermal Plants, Mechanical Engineering Department, National Technical University of Athens, Athens (Greece); Tumanovsky, A. [VTI All Russia Thermal Engineering Institute (Russian Federation); Kotler, V. [VTI All Russia Thermal Engineering Institute (Russian Federation)

2006-11-15

The paper aims to present the current status of the coal-fired power sector in Russia, the prospects for renovation activities based on Clean Coal Technologies (CCT) and two case studies on potential refurbishment projects. Data were collected for 180 thermoelectric units with capacity higher than 100 MWe and the renovation needs of the power sector, among the retrofitting, repowering and reconstruction options, were estimated through a multi-criteria analysis. The most attractive system to renovate a power plant between the Supercritical Combustion (SC) and the Fluidized Bed Combustion (FBC) technologies was evaluated. The application of each of the aforementioned technologies at the Kashirskaya and Shaturskaya power plants was studied and their replication potential in the Russian coal-fired power plant park was examined. Nowadays, the installed capacity of coal-fired power plants in the Russian Federation is 29.3 GWe, while they account for about 19% of the total electricity generation in the area. The low efficiency and especially the advanced age are the determinant factors for renovation applications at the Russian units. Even in the more conservative modernization scenario, over 30% of the thermoelectric units have to be repowered or reconstructed. Concrete proposals about the profitable and reliable operation of two Russian thermoelectric units with minimized environmental effects were elaborated. A new unit of 315 MWe with supercritical steam parameters and reburning for NO {sub x} abatement is envisaged to upgrade Unit 1 of Kashirskaya power station, while new Circulating Fluidized Bed (CFB) boilers of the same steam generation is the most promising renovation option for the boilers of Unit 1 in Shaturskaya power station.

Drip bloodstain appearance on inclined apparel fabrics: Effect of prior-laundering, fibre content and fabric structure.

Science.gov (United States)

de Castro, Therese C; Carr, Debra J; Taylor, Michael C; Kieser, Jules A; Duncan, Warwick

2016-09-01

The interaction of blood and fabrics is currently a 'hot topic', since the understanding and interpretation of these stains is still in its infancy. A recent simplified perpendicular impact experimental programme considering bloodstains generated on fabrics laid the foundations for understanding more complex scenarios. Blood rarely impacts apparel fabrics perpendicular; therefore a systematic study was conducted to characterise the appearance of drip stains on inclined fabrics. The final drip stain appearance for 45° and 15° impact angles on torso apparel fabrics (100% cotton plain woven, 100% polyester plain woven, a blend of polyester and cotton plain woven and 100% cotton single jersey knit) that had been laundered for six, 26 and 52 cycles prior to testing was investigated. The relationship between drop parameters (height and volume), angle and the stain characteristics (parent stain area, axis 1 and 2 and number of satellite stains) for each fabric was examined using analysis of variance. The appearance of the drip stains on these fabrics was distorted, in comparison to drip stains on hard-smooth surface. Examining the parent stain allowed for classification of stains occurring at an angle, however the same could not be said for the satellite stains produced. All of the dried stains visible on the surface of the fabric were larger than just after the impacting event, indicating within fabric spreading of blood due to capillary force (wicking). The cotton-containing fabrics spread the blood within the fabrics in all directions along the stain's circumference, while spreading within the polyester plain woven fabric occurred in only the weft (width of the fabric) and warp (length) directions. Laundering affected the formation of bloodstain on the blend plain woven fabric at both impact angles, although not all characteristics were significantly affected for the three impact conditions considered. The bloodstain characteristics varied due to the fibre content

Laval nozzles for cluster-jet targets

Energy Technology Data Exchange (ETDEWEB)

Grieser, Silke; Bonaventura, Daniel; Hergemoeller, Ann-Katrin; Hetz, Benjamin; Koehler, Esperanza; Lessmann, Lukas; Khoukaz, Alfons [Institut fuer Kernphysik, Westfaelische Wilhelms-Universitaet Muenster, 48149 Muenster (Germany)

2016-07-01

Cluster-jet targets are highly suited for storage ring experiments due to the fact that they provide high and constant beam densities. Therefore, a cluster-jet target is planned to be the first internal target for the PANDA experiment at FAIR. A cluster source generates a continuous flow of cryogenic solid clusters by the expansion of pre-cooled gases within fine Laval nozzles. For the production of clusters the geometry of the nozzle is crucial. The production of such nozzles with their complex inner geometry represents a major technical challenge. The possibility to produce new fine Laval nozzles ensures the operation of cluster-jet targets, e.g. for the PANDA experiment, and opens the way for future investigations on the cluster production process to match the required targets performance. Optimizations on the recently developed production process and the fabrication of new glass nozzles were done. Initial measurements of these nozzles at the PANDA cluster-jet target prototype and the investigation of the cluster beam origin within the nozzle will be presented and discussed. For the future more Laval nozzles with different geometries will be produced and additional measurements with these new nozzles at the PANDA cluster-jet target prototype towards higher performance will be realized.

Influence of Fabric Parameters on Thermal Comfort Performance of Double Layer Knitted Interlock Fabrics

Directory of Open Access Journals (Sweden)

Afzal Ali

2017-03-01

Full Text Available The aim of this study was to analyse the effects of various fabric parameters on the thermal resistance, thermal conductivity, thermal transmittance, thermal absorptivity and thermal insulation of polyester/cotton double layer knitted interlock fabrics. It was found that by increasing fibre content with higher specific heat increases the thermal insulation while decreases the thermal transmittance and absorptivity of the fabric. It was concluded that double layer knitted fabrics developed with higher specific heat fibres, coarser yarn linear densities, higher knitting loop length and fabric thickness could be adequately used for winter clothing purposes.

A facile method to fabricate superhydrophobic cotton fabrics

Science.gov (United States)

Zhang, Ming; Wang, Shuliang; Wang, Chengyu; Li, Jian

2012-11-01

A facile and novel method for fabricating superhydrophobic cotton fabrics is described in the present work. The superhydrophobic surface has been prepared by utilizing cationic poly (dimethyldiallylammonium chloride) and silica particles together with subsequent modification of (heptadecafluoro-1,1,2,2-tetradecyl) trimethoxysilane. The size distribution of silica particles was measured by Particle Size Analyzer. The cotton textiles before and after treatment were characterized by using scanning electron microscope (SEM) and X-ray photoelectron spectroscopy (XPS). The wetting behavior of cotton samples was investigated by water contact angle measurement. Moreover, the superhydrophobic durability of coated cotton textiles has been evaluated by exposure, immersion and washing tests. The results show that the treated cotton fabrics exhibited excellent chemical stability and outstanding non-wettability with the WCA of 155 ± 2°, which offers an opportunity to accelerate the large-scale production of superhydrophobic textiles materials for new industrial applications.

Cryogenic hydrogen fuel for controlled inertial confinement fusion (formation of reactor-scale cryogenic targets)

Energy Technology Data Exchange (ETDEWEB)

Aleksandrova, I. V.; Koresheva, E. R., E-mail: elena.koresheva@gmail.com; Krokhin, O. N. [Russian Academy of Sciences, Lebedev Physical Institute (Russian Federation); Osipov, I. E. [Power Efficiency Centre, Inter RAO UES (Russian Federation)

2016-12-15

In inertial fusion energy research, considerable attention has recently been focused on low-cost fabrication of a large number of targets by developing a specialized layering module of repeatable operation. The targets must be free-standing, or unmounted. Therefore, the development of a target factory for inertial confinement fusion (ICF) is based on methods that can ensure a cost-effective target production with high repeatability. Minimization of the amount of tritium (i.e., minimization of time and space at all production stages) is a necessary condition as well. Additionally, the cryogenic hydrogen fuel inside the targets must have a structure (ultrafine layers—the grain size should be scaled back to the nanometer range) that supports the fuel layer survivability under target injection and transport through the reactor chamber. To meet the above requirements, significant progress has been made at the Lebedev Physical Institute (LPI) in the technology developed on the basis of rapid fuel layering inside moving free-standing targets (FST), also referred to as the FST layering method. Owing to the research carried out at LPI, unique experience has been gained in the development of the FST-layering module for target fabrication with an ultrafine fuel layer, including a reactor- scale target design. This experience can be used for the development of the next-generation FST-layering module for construction of a prototype of a target factory for power laser facilities and inertial fusion power plants.

Fabrication of three-dimensional scaffolds using precision extrusion deposition with an assisted cooling device

Energy Technology Data Exchange (ETDEWEB)

Hamid, Q; Snyder, J; Wang, C; Guceri, S; Sun, W [Department of Mechanical Engineering and Mechanics, Drexel University, Philadelphia, PA (United States); Timmer, M; Hammer, J, E-mail: sunwei@drexel.edu [Advanced Technologies and Regenerative Medicine, Somerville, NJ (United States)

2011-09-15

In the field of biofabrication, tissue engineering and regenerative medicine, there are many methodologies to fabricate a building block (scaffold) which is unique to the target tissue or organ that facilitates cell growth, attachment, proliferation and/or differentiation. Currently, there are many techniques that fabricate three-dimensional scaffolds; however, there are advantages, limitations and specific tissue focuses of each fabrication technique. The focus of this initiative is to utilize an existing technique and expand the library of biomaterials which can be utilized to fabricate three-dimensional scaffolds rather than focusing on a new fabrication technique. An expanded library of biomaterials will enable the precision extrusion deposition (PED) device to construct three-dimensional scaffolds with enhanced biological, chemical and mechanical cues that will benefit tissue generation. Computer-aided motion and extrusion drive the PED to precisely fabricate micro-scaled scaffolds with biologically inspired, porosity, interconnectivity and internal and external architectures. The high printing resolution, precision and controllability of the PED allow for closer mimicry of tissues and organs. The PED expands its library of biopolymers by introducing an assisting cooling (AC) device which increases the working extrusion temperature from 120 to 250 deg. C. This paper investigates the PED with the integrated AC's capabilities to fabricate three-dimensional scaffolds that support cell growth, attachment and proliferation. Studies carried out in this paper utilized a biopolymer whose melting point is established to be 200 deg. C. This polymer was selected to illustrate the newly developed device's ability to fabricate three-dimensional scaffolds from a new library of biopolymers. Three-dimensional scaffolds fabricated with the integrated AC device should illustrate structural integrity and ability to support cell attachment and proliferation.

3D Bioprinting for Tissue and Organ Fabrication.

Science.gov (United States)

Zhang, Yu Shrike; Yue, Kan; Aleman, Julio; Moghaddam, Kamyar Mollazadeh; Bakht, Syeda Mahwish; Yang, Jingzhou; Jia, Weitao; Dell'Erba, Valeria; Assawes, Pribpandao; Shin, Su Ryon; Dokmeci, Mehmet Remzi; Oklu, Rahmi; Khademhosseini, Ali

2017-01-01

The field of regenerative medicine has progressed tremendously over the past few decades in its ability to fabricate functional tissue substitutes. Conventional approaches based on scaffolding and microengineering are limited in their capacity of producing tissue constructs with precise biomimetic properties. Three-dimensional (3D) bioprinting technology, on the other hand, promises to bridge the divergence between artificially engineered tissue constructs and native tissues. In a sense, 3D bioprinting offers unprecedented versatility to co-deliver cells and biomaterials with precise control over their compositions, spatial distributions, and architectural accuracy, therefore achieving detailed or even personalized recapitulation of the fine shape, structure, and architecture of target tissues and organs. Here we briefly describe recent progresses of 3D bioprinting technology and associated bioinks suitable for the printing process. We then focus on the applications of this technology in fabrication of biomimetic constructs of several representative tissues and organs, including blood vessel, heart, liver, and cartilage. We finally conclude with future challenges in 3D bioprinting as well as potential solutions for further development.

3D Bioprinting for Tissue and Organ Fabrication

Science.gov (United States)

Zhang, Yu Shrike; Yang, Jingzhou; Jia, Weitao; Dell’Erba, Valeria; Assawes, Pribpandao; Shin, Su Ryon; Dokmeci, Mehmet Remzi; Oklu, Rahmi; Khademhosseini, Ali

2016-01-01

The field of regenerative medicine has progressed tremendously over the past few decades in its ability to fabricate functional tissue substitutes. Conventional approaches based on scaffolding and microengineering are limited in their capacity of producing tissue constructs with precise biomimetic properties. Three-dimensional (3D) bioprinting technology, on the other hand, promises to bridge the divergence between artificially engineered tissue constructs and native tissues. In a sense, 3D bioprinting offers unprecedented versatility to co-deliver cells and biomaterials with precise control over their compositions, spatial distributions, and architectural accuracy, therefore achieving detailed or even personalized recapitulation of the fine shape, structure, and architecture of target tissues and organs. Here we briefly describe recent progresses of 3D bioprinting technology and associated bioinks suitable for the printing process. We then focus on the applications of this technology in fabrication of biomimetic constructs of several representative tissues and organs, including blood vessel, heart, liver, and cartilage. We finally conclude with future challenges in 3D bioprinting as well as potential solutions for further development. PMID:27126775

Recent advances in indirect drive ICF target physics at LLNL

International Nuclear Information System (INIS)

Hammel, B.A.; Bernat, T.P.; Collins, G.W.; Haan, S.; Landen, O.L.; MacGowan, B.J.; Suter, L.J.

1999-01-01

In preparation for ignition on the National Ignition Facility, the Lawrence Livermore National Laboratory's Inertial Confinement Fusion Program, working in collaboration with Los Alamos National Laboratory, Commissariat a l'Energie Atomique (CEA), and Laboratory for Laser Energetics at the University of Rochester, has performed a broad range of experiments on the Nova and Omega lasers to test the fundamentals of the NIF target designs. These studies have refined our understanding of the important target physics, and have led to many of the specifications for the NIF laser and the cryogenic ignition targets. Our recent work has been focused in the areas of hohlraum energetics, symmetry, shock physics, and target design optimization and fabrication. (author)

Fabric Reconstruction Based on Sustainable Development: Take the Type of Fabric Recycling as an Example

OpenAIRE

Zhangting Guan

2017-01-01

Sustainable development is a very important concept of our time, it wants to do is to live in harmony with people, to protect the environment where our human survival. Fabric recycling refers to the use of a variety of traditional and high-tech means of the existing fabric fabric design and processing. So that the surface of a rich visual texture and tactile texture "through the fabric recycling approach. However, the fabric form and clothing design coordination between the clothing design is...

Does demolition or refurbishment of old and inefficient homes help to increase our environmental, social and economic viability?

Energy Technology Data Exchange (ETDEWEB)

Power, Anne [London School of Economics, Houghton Street, London WC2A 2AE (United Kingdom); Sustainable Development Commission, Room 101, 55 Whitehall, c/o 3-8 Whitehall Place, London SW1A 2HH (United Kingdom)

2008-12-15

The issue of whether to demolish or refurbish older housing has been debated for over a century. It has been an active policy area since the late 1880s, when the Government first authorised the statutory demolition of insanitary slums. In the 1960s, revulsion at the scale of 'demolition blight' and new building caused a rethink, leading to a major reinvestment in inner city neighbourhoods of older housing. In the past 5 years, debate on demolition and new building has been intensified by the Government's Sustainable Communities Plan of 2003, with its proposals for large-scale clearance and building. Environmental arguments about renovating the existing stock have gained increasing prominence as people have sought to defend their communities from demolition. The evidence on whether demolition would reduce the amount of greenhouse gases we emit into the atmosphere is unclear and disputed. This paper summarises the evidence and arguments, and attempts to clarify the most realistic, achievable route to major reductions in energy use in homes. The arguments that apply to housing also apply to most other buildings and therefore to the overall built environment, which accounts for half of all carbon emissions. Three main sources of evidence have helped in the development of this paper, but there are many other studies we draw on in the discussion.

Metallic Reactor Fuel Fabrication for SFR

Energy Technology Data Exchange (ETDEWEB)

Song, Hoon; Kim, Jong-Hwan; Ko, Young-Mo; Woo, Yoon-Myung; Kim, Ki-Hwan; Lee, Chan-Bock [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

The metal fuel for an SFR has such advantages such as simple fabrication procedures, good neutron economy, high thermal conductivity, excellent compatibility with a Na coolant, and inherent passive safety 1. U-Zr metal fuel for SFR is now being developed by KAERI as a national R and D program of Korea. The fabrication technology of metal fuel for SFR has been under development in Korea as a national nuclear R and D program since 2007. The fabrication process for SFR fuel is composed of (1) fuel slug casting, (2) loading and fabrication of the fuel rods, and (3) fabrication of the final fuel assemblies. Fuel slug casting is the dominant source of fuel losses and recycled streams in this fabrication process. Fabrication on the rod type metallic fuel was carried out for the purpose of establishing a practical fabrication method. Rod-type fuel slugs were fabricated by injection casting. Metallic fuel slugs fabricated showed a general appearance was smooth.

One-pot fabrication and antimicrobial properties of novel PET nonwoven fabrics

International Nuclear Information System (INIS)

Lin Song; Wang Zheng; Qi Jiancheng; Wu Jinhui; Tian Tao; Hao Limei; Yang Jingquan; Hou Lili

2011-01-01

Recently, with the ever-growing demand for healthy living, more and more research is focused on materials capable of killing harmful microorganisms around the world. It is believed that designing such protective materials for hygienic and biomedical applications can benefit people in professional areas and daily life. Thus, in this paper, one novel kind of antibacterial poly(ethylene terephthalate) (PET) nonwoven fabrics was conveniently one-pot prepared, with the combined immobilization of two biological antimicrobial agents, i.e. ε-polylysine and natamycin, by using the soft methacrylate nonwoven fabrics adhesives. Then, the antimicrobial activities of the functional fabrics were investigated by using the standard shaking-flask method, showing excellent antibacterial efficiency (AE) against both Escherichia coli (8099) and Staphylococcus aureus (ATCC 6538) (AE > 99.99%) compared with untreated PET nonwoven fabrics. The anti-bioaerosol tests also showed similar trends. Meantime, scanning electron microscopy analysis indicated that the bacteria on the antibacterial PET appeared to be partly bacteriolyzed and showed much less viability than those on the pristine ones. Moreover, the long residual biocidal action of such modified PET fabrics was also evaluated, and the antibacterial activity of antibacterial fibers was unaffected by the 3 month artificially accelerated aging.

One-pot fabrication and antimicrobial properties of novel PET nonwoven fabrics

Energy Technology Data Exchange (ETDEWEB)

Lin Song; Wang Zheng; Qi Jiancheng; Wu Jinhui; Tian Tao; Hao Limei; Yang Jingquan [Institute of Medical Equipment, Academy of Military Medical Sciences, Tianjin 300161 (China); Hou Lili, E-mail: yjq789@sohu.com [National Bio-protection Engineering Center, Tianjin 300161 (China)

2011-08-15

Recently, with the ever-growing demand for healthy living, more and more research is focused on materials capable of killing harmful microorganisms around the world. It is believed that designing such protective materials for hygienic and biomedical applications can benefit people in professional areas and daily life. Thus, in this paper, one novel kind of antibacterial poly(ethylene terephthalate) (PET) nonwoven fabrics was conveniently one-pot prepared, with the combined immobilization of two biological antimicrobial agents, i.e. {epsilon}-polylysine and natamycin, by using the soft methacrylate nonwoven fabrics adhesives. Then, the antimicrobial activities of the functional fabrics were investigated by using the standard shaking-flask method, showing excellent antibacterial efficiency (AE) against both Escherichia coli (8099) and Staphylococcus aureus (ATCC 6538) (AE > 99.99%) compared with untreated PET nonwoven fabrics. The anti-bioaerosol tests also showed similar trends. Meantime, scanning electron microscopy analysis indicated that the bacteria on the antibacterial PET appeared to be partly bacteriolyzed and showed much less viability than those on the pristine ones. Moreover, the long residual biocidal action of such modified PET fabrics was also evaluated, and the antibacterial activity of antibacterial fibers was unaffected by the 3 month artificially accelerated aging.

Fabrication of integrated metallic MEMS devices

DEFF Research Database (Denmark)

Yalcinkaya, Arda Deniz; Ravnkilde, Jan Tue; Hansen, Ole

2002-01-01

A simple and complementary metal oxide semiconductor (CMOS) compatible fabrication technique for microelectromechanical (MEMS) devices is presented. The fabrication technology makes use of electroplated metal layers. Among the fabricated devices, high quality factor microresonators are characteri......A simple and complementary metal oxide semiconductor (CMOS) compatible fabrication technique for microelectromechanical (MEMS) devices is presented. The fabrication technology makes use of electroplated metal layers. Among the fabricated devices, high quality factor microresonators...

Optics fabrication technical challenges

International Nuclear Information System (INIS)

Chabassier, G.; Ferriou, N.; Lavastre, E.; Maunier, C.; Neauport, J.; Taroux, D.; Balla, D.; Fornerod, J.C.

2004-01-01

Before the production of all the LMJ (MEGAJOULE laser) optics, the CEA had to proceed with the fabrication of about 300 large optics for the LIL (laser integration line) laser. Thanks to a fruitful collaboration with high-tech optics companies in Europe, this challenge has been successfully hit. In order to achieve the very tight requirements for cleanliness, laser damage threshold and all the other high demanding fabrication specifications, it has been necessary to develop and to set completely new fabrication process going and to build special outsize fabrication equipment. Through a couple of examples, this paper gives an overview of the work which has been done and shows some of the results which have been obtained: continuous laser glass melting, fabrication of the laser slabs, rapid-growth KDP (potassium dihydrogen phosphate) technology, large diffractive transmission gratings engraving and characterization. (authors)

Design of ignition targets for the National Ignition Facility

International Nuclear Information System (INIS)

Haan, S.W.; Dittrich, T.R.; Marinak, M.M.; Hinkel, D.E.

1999-01-01

This is a brief update on the work being done to design ignition targets for the National Ignition Facility. Updates are presented on three areas of current activity : improvements in modeling, work on a variety of targets spanning the parameter space of possible ignition targets ; and the setting of specifications for target fabrication and diagnostics. Highlights of recent activity include : a simulation of the Rayleigh-Taylor instability growth on an imploding capsule, done in 3D on a 72degree by 72degree wedge, with enough zones to resolve modes out to 100 ; and designs of targets at 250eV and 350eV, as well as the baseline 300 eV ; and variation of the central DT gas density, which influences both the Rayleigh-Taylor growth and the smoothness of the DT ice layer

Fabricating architectural volume

DEFF Research Database (Denmark)

Feringa, Jelle; Søndergaard, Asbjørn

2015-01-01

The 2011 edition of Fabricate inspired a number of collaborations, this article seeks to highlight three of these. There is a common thread amongst the projects presented: sharing the ambition to close the rift between design and fabrication while incorporating structural design aspects early on...

Fabrication and properties of yttrium doped barium titanate film by RF sputtering

International Nuclear Information System (INIS)

Igarashi, H.; Yuasa, M.; Okazaki, K.

1985-01-01

Semiconductive barium titanate films were fabricated by RF sputtering on fused quartz, alumina and barium titanate ceramic substrates using barium titanate ceramic with a small amount of yttria as a target. The films on the barium titanate substrates turned blue color and showed a small PTC effect by heat-treating at 1000 0 C in the air after deposition at the substrate temperature of 600 0 C

Fabrication of targets for transmutation of americium : synthesis of inertial matrix by sol-gel method. Procedure study on the infiltration of a radioactive solutions; Fabricacion de blancos para la transmutacion de americio: sintesis de matrices inertes por el metodo sol-gel. Estudio del procedimiento de infiltracion de disoluciones radiactivas

Energy Technology Data Exchange (ETDEWEB)

Fernandez Carretero, A [Universidad Complutense de Madrid (Spain)

2002-07-01

Transmutation and incineration are innovative options in the management and disposal of fission products and actinides. nevertheless, the fabrication of targets for transmutation and incineration of actinides and fission products require a reconsideration of conventional processes (mechanical blending) and the development of new procedures compatible with the high activity of these materials. This work presents th R and D of a new fabrication method called INRAM (Infiltration of Radioactive Materials) based on the infiltration of an actinide solution in a porous non radiotoxic material in the form of a pellet (up to 12% An), or beads (up to 40% An) produced by sol-gel. The first method have been used for the fabrication of spinel (MgAl{sub 2}O{sub 4}) targets containing 11% Am, which have been irradiated in HFR-Petten (358.4 full power days). Post-test burn-up calculations showed that at the end of the irradiation the initial Am-241 concentration was reduced to 4%. The fraction of the initial americum atoms that have been fissioned is 28%. The main advantage of the INRAM method is that matrices with low or zero activity can be fabricated and formed into the required shape in an unshielded facility. This method offers other advantages over conventional ones, such as the active wastes are reduced, is easy to automate, adoptable to telemanipulation and dust free, which facilitate operator intervention and minimise radiation exposure to the personal. In addition, the infiltrant needs only be present in liquid form, i. e. it could be transferred directly from the reprocessing plant for fabrication into targets without conversion into-solid form. In order to optimise the infiltration process in depth investigations of all important process parameters, e. g. infiltration kinetics and metal (pu, Am) concentration in the feed solution, and also on extensive study or powder metallurgy parameters for the preparation of high quality fuel pellets with a high density, have been

A honeycomb sandwich structure vacuum jacket for cryogenic targets

International Nuclear Information System (INIS)

Harada, M.; Kasai, S.; Kato, S.

1988-11-01

Cryogenic targets (H 2 , D 2 and 4 He) have been built for use in the study of photonuclear reactions with π sr spectrometer, TAGX at the 1.3 GeV Tokyo electron synchrotron. A new type of vacuum jacket fabricated from plastic honeycomb core and Mylar skins has been used in the target system for more than 5000 hours. The average radiation thickness and the average density of this jacket are measured to be 3.3 x 10 -3 X 0 and 0.15 g/cm 3 , respectively. (author)

Life extension of boilers using weld overlay protection

Energy Technology Data Exchange (ETDEWEB)

Lai, G; Hulsizer, P [Welding Services Inc., Norcross, GA (United States); Brooks, R [Welding Services Inc., Welding Services Europe, Spijkenisse (Netherlands)

1999-12-31

The presentation describes the status of modern weld overlay technology for refurbishment, upgrading and life extension of boilers. The approaches to life extension of boilers include field overlay application, shop-fabricated panels for replacement of the worn, corroded waterwall and shop-fabricated overlay tubing for replacement of individual tubes in superheaters, generating banks and other areas. The characteristics of weld overlay products are briefly described. Also discussed are successful applications of various corrosion-resistant overlays for life extension of boiler tubes in waste-to-energy boilers, coal-fired boilers and chemical recovery boilers. Types of corrosion and selection of weld overlay alloys in these systems are also discussed. (orig.) 14 refs.

Life extension of boilers using weld overlay protection

Energy Technology Data Exchange (ETDEWEB)

Lai, G.; Hulsizer, P. [Welding Services Inc., Norcross, GA (United States); Brooks, R. [Welding Services Inc., Welding Services Europe, Spijkenisse (Netherlands)

1998-12-31

The presentation describes the status of modern weld overlay technology for refurbishment, upgrading and life extension of boilers. The approaches to life extension of boilers include field overlay application, shop-fabricated panels for replacement of the worn, corroded waterwall and shop-fabricated overlay tubing for replacement of individual tubes in superheaters, generating banks and other areas. The characteristics of weld overlay products are briefly described. Also discussed are successful applications of various corrosion-resistant overlays for life extension of boiler tubes in waste-to-energy boilers, coal-fired boilers and chemical recovery boilers. Types of corrosion and selection of weld overlay alloys in these systems are also discussed. (orig.) 14 refs.

Availability of enriched isotopic material for accelerator targets

International Nuclear Information System (INIS)

Newman, E.

1982-01-01

The electromagnetic isotope enrichment facility at ORNL provides a broad spectrum of highly enriched stable isotopes to the worldwide scientific community. The continued timely availability of these materials is of vital importance in many areas of basic research and, in particular, as source material for the fabrication of accelerator targets. A brief description of the facility and its capabilities and limitations is presented

Concept and experimental studies on fuel and target for minor actinides and fission products transmutation

Energy Technology Data Exchange (ETDEWEB)

Prunier, C; Guerin, Y [CEA Centre d` Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d` Etudes des Combustibles; Salvatores, M [CEA Centre d` Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Direction des Reacteurs Nucleaires; Zaetta, A [CEA Centre d` Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d` Etudes des Reacteurs

1994-12-31

High activity long-lived radionuclides in nuclear wastes, namely minor actinides (americium and neptunium) are in large amount generated by current nuclear reactive. The destruction of these radionuclides is a part of the French SPIN (Partitioning and Burning) program consistent with the determination to send a minimum amount of harmful products for final storage. Transmutation concepts are defined for neptunium and americium taking into account fuel cycle strategies. Neptunium destruction does not pose any major problems. It`s a by-product of uranium consumption, as plutonium and in despite of a slight gamma activity due to the protactinium 233 it`s quite easy to handle. Diluting neptunium in the mixed oxide fuels (MOX) should not be an obstacle for fabrication, in-pile behaviour and reprocessing either. Consequently we make the proposal of homogeneous mode of neptunium in MOX which should be soon explored in the experimental OSIRIS reactor and in the Phenix and Superphenix reactors. The analysis is more complex for the multi isotope americium. Its destruction is difficult because of gamma radioactivity which complicates fabrication. Experiments in Phenix and calculation showed that Phenix reactor offers a good potential for americium incineration, but similar data do not exist for PWR. It will remain a well known difficulty for fabrication and reprocessing. In this case we have to put a real new face to the fabrication flow-sheet of americium compounds and we propose to develop the heterogeneous mode. Targets choice are defined in term of: -safety, considering fuel reaction with cladding and water sodium, -transmutation rate, limited by target behaviour, in FR`s (Phenix), PWR`s (OSIRIS) and HFR (Petten), -reprocessing, checking the solubility of such targets by Purex process. So, at the beginning of our program the account has been on improving fuel and targets properties related to safety and fuel cycle. (authors). 4 figs.

Fabrication of Durably Superhydrophobic Cotton Fabrics by Atmospheric Pressure Plasma Treatment with a Siloxane Precursor

Directory of Open Access Journals (Sweden)

Jing Yang

2018-04-01

Full Text Available The surface treatment of fabrics in an atmospheric environment may pave the way for commercially viable plasma modifications of fibrous matters. In this paper, we demonstrate a durably superhydrophobic cotton cellulose fabric prepared in a single-step graft polymerization of hexamethyldisiloxane (HMDSO by N2 and O2 atmospheric pressure plasma. We systematically investigated effects on contact angle (CA and surface morphology of the cotton fabric under three operational parameters: precursor value; ionization gas flow rate; and plasma cycle time. Surface morphology, element composition, chemical structure and hydrophobic properties of the treated fabric were characterized by scanning electron microscope (SEM, EDS, FTIR and CA on the fabrics. The results indicated that a layer of thin film and nano-particles were evenly deposited on the cotton fibers, and graft polymerization occurred between cellulose and HMDSO. The fabric treated by O2 plasma exhibited a higher CA of 162° than that treated by N2 plasma which was about 149°. Furthermore, the CA of treated fabrics decreased only 0°~10° after storing at the ambient conditions for four months, and treated fabrics could also endure the standard textile laundering procedure in AATCC 61-2006 with minimum change. Therefore, this single-step plasma treatment method is shown to be a novel and environment-friendly way to make durable and superhydrophobic cotton fabrics.

Techniques for fabricating an infrared optical pyrometry system for pulsed electron beam diagnostics

International Nuclear Information System (INIS)

Ouellette, A.L.

1976-01-01

A description is given of an infrared optical pyrometry system which was designed to make fast time resolved temperature measurements. The purpose of this equipment is to determine the amount of energy from an electron beam or some other type of pulsed energy deposition that is absorbed in a target. The system is capable of measuring energy deposition levels up to 4000 J/g in carbon, which corresponds to a graphite target temperature of 2200 0 C. Methods of fabrication, alignment, and calibration are presented. The measurement of absorbed energy in a target as a function of position and depth is discussed as a possible application, and several measurements are described which permit a comparison of results from this system with those taken by other methods

Refurbishment of uranium hexafluoride cylinder storage yards C-745-K, L, M, N, and P and construction of a new uranium hexafluoride cylinder storage yard (C-745-T) at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky

International Nuclear Information System (INIS)

1996-07-01

The Paducah Gaseous Diffusion Plant (PGDP) is a uranium enrichment facility owned by the US Department of Energy (DOE). A residual of the uranium enrichment process is depleted uranium hexafluoride (UF6). Depleted UF6, a solid at ambient temperature, is stored in 32,200 steel cylinders that hold a maximum of 14 tons each. Storage conditions are suboptimal and have resulted in accelerated corrosion of cylinders, increasing the potential for a release of hazardous substances. Consequently, the DOE is proposing refurbishment of certain existing yards and construction of a new storage yard. This environmental assessment (EA) evaluates the impacts of the proposed action and no action and considers alternate sites for the proposed new storage yard. The proposed action includes (1) renovating five existing cylinder yards; (2) constructing a new UF6 storage yard; handling and onsite transport of cylinders among existing yards to accommodate construction; and (4) after refurbishment and construction, restacking of cylinders to meet spacing and inspection requirements. Based on the results of the analysis reported in the EA, DOE has determined that the proposed action is not a major Federal action that would significantly affect the quality of the human environment within the context of the National Environmental Policy Act of 1969. Therefore, DOE is issuing a Finding of No Significant Impact. Additionally, it is reported in this EA that the loss of less than one acre of wetlands at the proposed project site would not be a significant adverse impact

Refurbishment of uranium hexafluoride cylinder storage yards C-745-K, L, M, N, and P and construction of a new uranium hexafluoride cylinder storage yard (C-745-T) at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

The Paducah Gaseous Diffusion Plant (PGDP) is a uranium enrichment facility owned by the US Department of Energy (DOE). A residual of the uranium enrichment process is depleted uranium hexafluoride (UF6). Depleted UF6, a solid at ambient temperature, is stored in 32,200 steel cylinders that hold a maximum of 14 tons each. Storage conditions are suboptimal and have resulted in accelerated corrosion of cylinders, increasing the potential for a release of hazardous substances. Consequently, the DOE is proposing refurbishment of certain existing yards and construction of a new storage yard. This environmental assessment (EA) evaluates the impacts of the proposed action and no action and considers alternate sites for the proposed new storage yard. The proposed action includes (1) renovating five existing cylinder yards; (2) constructing a new UF6 storage yard; handling and onsite transport of cylinders among existing yards to accommodate construction; and (4) after refurbishment and construction, restacking of cylinders to meet spacing and inspection requirements. Based on the results of the analysis reported in the EA, DOE has determined that the proposed action is not a major Federal action that would significantly affect the quality of the human environment within the context of the National Environmental Policy Act of 1969. Therefore, DOE is issuing a Finding of No Significant Impact. Additionally, it is reported in this EA that the loss of less than one acre of wetlands at the proposed project site would not be a significant adverse impact.

LEMA facility and equipments for minor actinides compounds fabrication and characterisation

Energy Technology Data Exchange (ETDEWEB)

Donnet, L. [Commissariat a l' Energie Atomique - CEA, CEA/DEN/VRH/DTEC/SDTC/LEMA (France)

2008-07-01

The LEMA (Actinide based materials study laboratory) is mainly involved in minor actinides materials development and fabrication, from raw materials choice and synthesis to finished products including pin assembly. The aim of the technological analyses is to establish choices of raw materials and manufacturing techniques. The LEMA is located in the ATALANTE facility in Marcoule. It consists in two shielded chains (one specific for neutrons) and three hot laboratories. The laboratory has various apparatuses in hot cells such as: ball mills, press, dilatometer, TGA (thermo-gravimetry analyser), calcination and sintering furnaces (2000 deg. C). The laboratory has also characterisation apparatuses such as XRD and SEM (scanning electron microscopy) dedicated to structural and microstructural studies. Thanks to the diversity of its equipment, the LEMA has well established worldwide collaborations and takes part in international fuels/target fabrication and irradiation experiments. (author)

LEMA facility and equipments for minor actinides compounds fabrication and characterisation

International Nuclear Information System (INIS)

Donnet, L.

2008-01-01

The LEMA (Actinide based materials study laboratory) is mainly involved in minor actinides materials development and fabrication, from raw materials choice and synthesis to finished products including pin assembly. The aim of the technological analyses is to establish choices of raw materials and manufacturing techniques. The LEMA is located in the ATALANTE facility in Marcoule. It consists in two shielded chains (one specific for neutrons) and three hot laboratories. The laboratory has various apparatuses in hot cells such as: ball mills, press, dilatometer, TGA (thermo-gravimetry analyser), calcination and sintering furnaces (2000 deg. C). The laboratory has also characterisation apparatuses such as XRD and SEM (scanning electron microscopy) dedicated to structural and microstructural studies. Thanks to the diversity of its equipment, the LEMA has well established worldwide collaborations and takes part in international fuels/target fabrication and irradiation experiments. (author)

Refurbishment of Pakistan research reactor (PARR-1) for stainless steel lining of the reactor pool

International Nuclear Information System (INIS)

Salahuddin, A.; Israr, M.; Hussain, M.

2002-01-01

Pakistan Research Reactor-1 (PARR-1) is a pool-type research reactor. Reactor aging has resulted in the increase of water seepage from the concrete walls of the reactor pool. To stop the seepage, it was decided to augment the existing pool walls with an inner lining of stainless steel. This could be achieved only if the pool walls could be accessed unhindered and without excessive radiation doses. For this purpose a partial decommissioning was done by removing all active core components including standard/control fuel elements, reflector elements, beam tubes, thermal shield, core support structure, grid plate and the pool's ceramic tiles, etc. An overall decommissioning program was devised which included procedures specific to each item. This led to the development of a fuel transport cask for transportation, and an interim fuel storage bay for temporary storage of fuel elements (until final disposal). The safety of workers and the environment was ensured by the use of specially designed remote handling tools, appropriate shielding and pre-planned exposure reduction procedures based on the ALARA principle. During the implementation of this program, liquid and solid wastes generated were legally disposed of. It is felt that the experience gained during the refurbishment of PARR-1 to install the stainless steel liner will prove useful and better planning and execution for the future decommissioning of PARR-1, in particular, and for other research reactors like PARR-2 (27 kW MNSR), in general. Furthermore, due to the worldwide activities on decommissioning, especially those communicated through the IAEA CRP on 'Decommissioning Techniques for Research Reactors', the importance of early planning has been well recognized. This has made possible the implementation of some early steps like better record keeping, rehiring of trained manpower, and creation of interim and final waste storage. (author)

Integrating Life Cycle Energy into the Design of Façade Refurbishment for a Post-War Residential Building in The Netherlands