Development of neutron imaging beamline for NDT applications at Dhruva reactor, India

Science.gov (United States)

Shukla, Mayank; Roy, Tushar; Kashyap, Yogesh; Shukla, Shefali; Singh, Prashant; Ravi, Baribaddala; Patel, Tarun; Gadkari, S. C.

2018-05-01

Thermal neutron imaging techniques such as radiography or tomography are very useful tool for various scientific investigations and industrial applications. Neutron radiography is complementary to X-ray radiography, as neutrons interact with nucleus as compared to X-ray interaction with orbital electrons. We present here design and development of a neutron imaging beamline at 100 MW Dhruva research reactor for neutron imaging applications such as radiography, tomography and phase contrast imaging. Combinations of sapphire and bismuth single crystals have been used as thermal neutron filter/gamma absorber at the input of a specially designed collimator to maximize thermal neutron to gamma ratio. The maximum beam size of neutrons has been restricted to ∼120 mm diameter at the sample position. A cadmium ratio of ∼250 with L / D ratio of 160 and thermal neutron flux of ∼ 4 × 107 n/cm2 s at the sample position has been measured. In this paper, different aspects of the beamline design such as collimator, shielding, sample manipulator, digital imaging system are described. Nondestructive radiography/tomography experiments on hydrogen concentration in Zr-alloy, aluminium foam, ceramic metal seals etc. are also presented.

Determination of aluminium content in foodstuffs by neutron activation analysis utilizing PCF of Dhruva research reactor

International Nuclear Information System (INIS)

Nanda, B.B.; Biswal, R.R.; Acharya, R.; Pujari, P.K.; Shinde, A.

2014-01-01

Aluminium is one of the toxic elements in food and food products are the main sources of aluminium entering the human body. In the present study, Aluminium (Al) content of 25 samples (from market) including rice, rice products, wheat, spices, tea, tea products, and lentils were determined using instrumental neutron activation analysis (INAA). The concentrations of Al were in the range of 25-500 mg kg -1 in general except for tea and one spice sample. Samples were neutron irradiated using PCF of Dhruva reactor and 1779 keV γ-ray of 28 Al was analyzed using HPGe detector based γ-ray spectrometry. Three RMs was analyzed for method validation. The results obtained by INAA are discussed in this paper. (author)

Experiences in design up-gradation of mechanical seal cooling scheme of Dhruva PHT pumps

International Nuclear Information System (INIS)

Balakrishnan, K.T.P.

2002-01-01

Full text: Dhruva is a natural uranium fuelled high flux research reactor. Heavy water is used as coolant, moderator and reflector. Heat from the heavy water coolant is removed in heat exchangers by demineralised water. The heavy water coolant is re-circulated between the reactor core and the heat exchangers in three separate loops by three main coolant pumps (MCPs). The MCPs are high capacity centrifugal pumps and are rated for continuous service. The mechanical seal of the pump prevents leakage of the process fluid, which is heavy water, through the pump shaft. Continuous operation of the pump results in the heating up of the seal and necessitates sustained cooling. An integral cooling provision is made by tapping a 15 NB line from the discharge volute of the pump and feeding the process fluid itself as coolant to the seal. A non-indicating type flow-sensing device monitors flow through this line. Limiting values of flow are set and annunciated by a pair of magnetic reed type relays. This cooling line was a built in feature of the pumps as supplied by the manufacturer. This arrangement had the following inherent limitations: 1. There was no on line indication of the coolant flow. 2. The reed type magnetic relays initiated pump trips by spurious actuation, resulting in the interruption of reactor operation. Servicing a faulty flow switch involved lengthy procedures and necessitated draining, filling and venting of the pump. This entailed extended plant outages. Close proximity of these flow switches to a highly radioactive piping element imposed severe restrictions on the planned maintenance activity on them. Efforts were made to provide a suitable alternate cooling and flow measurement scheme to overcome the above-mentioned limitations. After evaluating the relative merits and demerits of several schemes, a turbine type flow sensor, on a modified cooling line was selected as the most suitable alternative. The alternate seal-cooling scheme was implemented for all

Experiences in design up-gradation of mechanical seal cooling scheme of Dhruva PHT pumps

International Nuclear Information System (INIS)

Balakrishnan, K.T.P.; Bharathan, R.

2002-01-01

Full text: Dhruva is a natural uranium fuelled high flux research reactor. Heavy water is used as coolant, moderator and reflector. Heat from the heavy water coolant is removed in heat exchangers by demineralised water. The heavy water coolant is re-circulated between the reactor core and the heat exchangers in three separate loops by three main coolant pumps (MCPs). The MCPs are high capacity centrifugal pumps and are rated for continuous service. The mechanical seal of the pump prevents leakage of the process fluid, which is heavy water, through the pump shaft. Continuous operation of the pump results in the heating up of the seal and necessitates sustained cooling. An integral cooling provision is made by tapping a 15 NB line from the discharge volute of the pump and feeding the process fluid itself as coolant to the seal. A non-indicating type flow-sensing device monitors flow through this line. Limiting values of flow are set and annunciated by a pair of magnetic reed type relays. This cooling line was a built in feature of the pumps as supplied by the manufacturer. This arrangement had the following inherent limitations : 1. There was no on line indication of the coolant flow. 2. The reed type magnetic relays initiated pump trips by spurious actuation, resulting in the interruption of reactor operation. Servicing a faulty flow switch involved lengthy procedures and necessitated draining, filling and venting of the pump. This entailed extended plant outages. Close proximity of these flow switches to a highly radioactive piping element imposed severe restrictions on the planned maintenance activity on them. Efforts were made to provide a suitable alternate cooling and flow measurement scheme to overcome the above-mentioned limitations. After evaluating the relative merits and demerits of several schemes, a turbine type flow sensor, on a modified cooling line was selected as the most suitable alternative. The alternate seal-cooling scheme was implemented for all

Fault tolerant microcomputer based alarm annunciator for Dhruva reactor

International Nuclear Information System (INIS)

Chandra, A.K.

1988-01-01

The Dhruva alarm annunciator displays the status of 624 alarm points on an array of display windows using the standard ringback sequence. Recognizing the need for a very high availability, the system is implemented as a fault tolerant configuration. The annunciator is partitioned into three identical units; each unit is implemented using two microcomputers wired in a hot standby mode. In the event of one computer malfunctioning, the standby computer takes over control in a bouncefree transfer. The use of microprocessors has helped built-in flexibility in the system. The system also provides built-in capability to resolve the sequence of occurrence of events and conveys this information to another system for display on a CRT. This report describes the system features, fault tolerant organisation used and the hardware and software developed for the annunciation function. (author). 8 figs

Instrumentation for PSD based neutron diffractometers at Dhruva reactor

International Nuclear Information System (INIS)

Pande, S.S.; Borkar, S.P.; Prafulla, S.; Srivastava, V.D.; Behare, A.; Mukhopadhyay, P.K.; Ghodgaonkar, M.D.; Kataria, S.K.

2004-01-01

Linear position sensitive detectors (PSDs) are widely used to configure neutron diffractometers and other instruments. Necessary front-end electronics and a data acquisition system is developed to cater to such instruments built around the Dhruva research reactor in BARC. These include three diffractometers with multiple PSDs and four with single PSD. The front-end electronics consists of high voltage units, preamplifiers, shaping amplifiers, ratio ADCs (RDC). The data acquisition system consists of an interface card and software. Commercially available hardware like temperature controller or stepper motor controller connected over GPIB or RS232 are also integrated in the data acquisition system. The data acquisition is automated so that it can continue unattended for control parameter like temperature, thus enabling optimum utilization of available beam time. The instrumentation is scalable and can be easily configured for various instrumental requirements. The front-end electronics and the data acquisition system are described here. (author)

Instrumentation for PSD-based neutron diffractometers at Dhruva reactor

Science.gov (United States)

Pande, S. S.; Borkar, S. P.; Prafulla, S.; Srivastava, V. D.; Behare, A.; Mukhopadhyay, P. K.; Ghodgaonkar, M. D.; Kataria, S. K.

2004-08-01

Linear position sensitive detectors (PSDs) are widely used to configure neutron diffractometers and other instruments. Necessary front-end electronics and a data acquisition system [1] is developed to cater to such instruments built around the Dhruva research reactor in BARC. These include three diffractometers with multiple PSDs and four with single PSD. The front-end electronics consists of high voltage units, preamplifiers [2], shaping amplifiers, ratio ADCs (RDC) [3]. The data acquisition system consists of an interface card and software. Commercially available hardware like temperature controller or stepper motor controller connected over GPIB or RS232 are also integrated in the data acquisition system. The data acquisition is automated so that it can continue unattended for control parameter like temperature, thus enabling optimum utilization of available beam time. The instrumentation is scalable and can be easily configured for various instrumental requirements. The front-end electronics and the data acquisition system are described here.

Upgrade of Dhruva fuel channel flow instrumentation

International Nuclear Information System (INIS)

Gadgil, Kaustubh; Awale, P.K.; Sengupta, C.; Sumanth, P.; Roy, Kallol

2014-01-01

Dhruva, a 100 MW Heavy Water moderated and cooled, vertical tank-type Research Reactor, using metallic natural Uranium fuel has flow instrumentation for all the 144 fuel channels, consisting of venturi and triplicate DP gauges for each fuel channel. These gauges provide contacts for generation of reactor trip on low flow through fuel channel. These DP gauges were facing numerous generic and ageing related failures over the years and was also difficult to maintain owing to obsolescence. While considering an upgrade for these DP gauges, it was also planned to replace the existing Coolant Low Flow Trip (CLFT) system with a computer based Reactor Trip Logic System (RTLS). Being a retrofit job, the existing panels for mounting the gauges, cable layout, impulse tubing layout, etc. were retained, thereby simplifying the site execution, reducing reactor down time and also reducing person-milli-Sievert consumption. A customized Electronic DP Indicating Switch (EDPIS) was conceptualized for achieving these objectives. Such a design, utilizing a standard DP transmitter with customized electronic circuitry, was developed, evaluated and finalized after a series of factory trials, field trials and prototyping. The instrument design included contact input for existing CLFT system and also provision for 4-20 mA current output for the proposed computer based RTLS. The display and form factor of the instrument remained identical to older one and ensures familiarity of O and M personnel. Since EDPIS is classified as Safety Class IA, stringent type tests, hardware FMEA and V and V of the micro-controller software were carried out as per the requirements laid down by relevant standards for qualification of these instruments. Being a customized instrument, the manufacturing process was closely monitored and was followed by stringent QA plan and acceptance tests. A total of 396 gauges were replaced in a phased manner during scheduled fuelling outages and thereby did not affect reactor

Operating and maintenance experience of Dhruva secondary shutdown system

International Nuclear Information System (INIS)

Sharma, U.L.; Bharathan, R.

1997-01-01

Nine numbers of cadmium shut-off rods are used as primary fast acting shutdown devices while moderator dumping is used as secondary shutdown system. The secondary shutdown system in Dhruva reactor comprises of 3 dump valves and 3 control valves. Under normal operations, the control valves are used to control the moderator level and thereby the reactor power. Under Trip conditions the dump valves as well as the control valves open fully, dumping the moderator to the dump tank, thereby acting as secondary shutdown devices. While the failure of any of these valves to close fully is an incident, the failure of any of these valves to open on a demand is a safety related unusual occurrence and needs to be viewed seriously. During the last 11 years of operation of these valves, there was one incidence of a valve not closing fully and there were two instances of a valve not opening fully on demand. The possible causes, the corrective action taken to rehabilitate these valves and the elaborate system preparations undertaken to enable maintenance jobs are described. (author)

Experiences with on line fault detection system for protection system logic and decay heat removal system logic in Dhruva

International Nuclear Information System (INIS)

Ramkumar, N.; Dutta, P.K.; Darbhe, M.D.; Bharadwaj, G.

2001-01-01

Dhruva is a 100 MW (Thermal) natural uranium fuelled, vertical core, tank type multi purpose research reactor with heavy water acting as moderator, coolant and reflector. Helium is used as cover gas for heavy water system. Reactor Protection System and Decay Heat Removal System (DHRS) have triplicated instrumented channels. The logic for these systems are hybrid in nature with a mixture of relay logic and solid state logic. Fine Impulse Technique(FIT) is employed for On-line fault detection in the solid state logics of these systems. The FIT systems were designed in the early eighties. Operating experiences over the past 15 years has revealed certain deficiencies. In view of this, a microcomputer based state of the art FIT systems for logics of Reactor Protection System and DHRS are being implemented with improved functionalities built into them. This paper describes the operating experience of old FIT systems and improved features of the proposed new FIT systems. (author)

Process development, design and operation of off-line purification system for oil-contaminated impure heavy water

International Nuclear Information System (INIS)

Bose, H.; Rakesh Kumar; Gandhi, H.C.; Unny, V.K.P.; Ghosh, S.K.; Mishra, Vivek; Shukla, D.K.; Duraisamy, S.; Agarwal, S.K.

2004-01-01

A large volume of degraded, tritiated heavy water contaminated with mineral oil and ionic impurities have accumulated at Dhruva in the past years of reactor operation as a result of routine operation and maintenance activities. The need was felt for a simple and efficient process that could be set up and operated locally at site using readily available materials, to purify the accumulated impure heavy waters at Dhruva so as to make them acceptable at the up gradation facilities. After a detailed laboratory study, a three stage clean-up process was developed which could purify a highly turbid oil-water emulsion to yield clear, oil-free and de-mineralized heavy water at reasonable rates of volume through-put. Based on the laboratory data, a suitably scaled up purification unit has been designed and commissioned which in the past few months has processed a sizeable volume of oil-contaminated heavy water waste from Dhruva, with most satisfactory results

Quantification of chlorine in zirconium oxide and biological samples by instrumental NAA utilizing PCF of Dhruva reactor

International Nuclear Information System (INIS)

Shinde, Amol D.; Reddy, A.V.R.; Acharya, R.; Balaji Rao, Y.

2012-01-01

Recently studies on chlorine contents in various samples are being pursued due to its corrosive nature. Chlorine present at trace level in various finished products as well as powder is used as a raw material for production of different types of zircaloys used as structural materials in nuclear technology. As a part of quality assurance program, it is necessary to quantify chlorine accurately with suitable and simple technique. In the present work we have applied instrumental neutron activation analysis (INAA) utilizing its short-lived activation product ( 38 Cl, 37 min, 1642 and 2168 keV) for its estimation. Pneumatic Carrier Facility (PCF) of Dhruva reactor, BARC was used sample irradiation of zirconium oxide dry powder, synthetic wax and IAEA RMs 1515 (Apple leaves) and Lichen 336. (author)

The pneumatic carrier facility in Dhruva reactor: commissioning, characterization and utilization

International Nuclear Information System (INIS)

Reddy, A.V.R.; Newton Nathaniel, T.; Nair, A.G.C.; Acharya, R.; Lahiri, D.K.; Kulkarni, U.S.; Sengupta, C.; Duraisamy, S.; Shukla, D.K.; Chakrabarty, K.; Ghosh, R.; Mondal, S.K.; Gujar, H.G.

2007-11-01

The 100 MWt power Dhruva research reactor, BARC is provided with pneumatic carrier facility (PCF) to carry out R and D work using short-lived (seconds to minutes) radioisotopes in the fields like neutron activation analysis (NAA) and nuclear fission. The samples are kept inside a high density polypropylene capsule (rabbit), which is pneumatically sent to the irradiation position in the core and retrieved after a preset time of irradiation. After the irradiation, radioactivity assay is carried out using high resolution gamma ray spectrometry with HPGe detector coupled to PC based MCA. The availability of high neutron flux (∼ 5 x 10 13 cm -2 s -1 at 50 MWt power) and shorter retrieval time (∼5 seconds) make it possible to measure short-lived isotopes with enhanced sensitivity. This report describes the salient features of this facility, characterization of the neutron spectrum at this irradiation position and its utilization. The PCF is being extensively utilized for analytical applications using NAA as well as nuclear fission studies. A brief description of analysis of some samples of geological, environmental and biological origin, nuclear materials as well as reference materials is included in this report. Protocol and check list for carrying out PCF irradiations and gamma spectrometric assay are also given at the end of the report. (author)

Design and applications of Computed Industrial Tomographic Imaging System (CITIS)

Energy Technology Data Exchange (ETDEWEB)

Ramakrishna, G S; Kumar, Umesh; Datta, S S [Bhabha Atomic Research Centre, Bombay (India). Isotope Div.

1994-12-31

This paper highlights the design and development of a prototype Computed Tomographic (CT) imaging system and its software for image reconstruction, simulation and display. It also describes results obtained with several test specimens including Dhruva reactor uranium fuel assembly and possibility of using neutrons as well as high energy x-rays in computed tomography. 5 refs., 4 figs.

14 CFR 23.753 - Main float design.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Main float design. 23.753 Section 23.753... STANDARDS: NORMAL, UTILITY, ACROBATIC, AND COMMUTER CATEGORY AIRPLANES Design and Construction Floats and Hulls § 23.753 Main float design. Each seaplane main float must meet the requirements of § 23.521. [Doc...

14 CFR 27.753 - Main float design.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Main float design. 27.753 Section 27.753... STANDARDS: NORMAL CATEGORY ROTORCRAFT Design and Construction Floats and Hulls § 27.753 Main float design. (a) Bag floats. Each bag float must be designed to withstand— (1) The maximum pressure differential...

14 CFR 29.753 - Main float design.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Main float design. 29.753 Section 29.753... STANDARDS: TRANSPORT CATEGORY ROTORCRAFT Design and Construction Floats and Hulls § 29.753 Main float design. (a) Bag floats. Each bag float must be designed to withstand— (1) The maximum pressure differential...

14 CFR 25.753 - Main float design.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Main float design. 25.753 Section 25.753 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION AIRCRAFT AIRWORTHINESS STANDARDS: TRANSPORT CATEGORY AIRPLANES Design and Construction Floats and Hulls § 25.753 Main float design...

Main designations and attributions

International Nuclear Information System (INIS)

2010-01-01

The chapter presents the main designations and attributions of the LNMRI - Brazilian National Laboratory of Metrology of Ionizing Radiation, the Cooperative Center in Radiation Protection and Medical Preparations for Accidents with Radiation; the Treaty for fully banning of nuclear tests and the Regional Center for Training of IAEA

The Fermilab Main Injector Technical Design Handbook

Energy Technology Data Exchange (ETDEWEB)

None, None

1994-08-01

This report contains a description of the design, cost estimate, and construction schedule of the Fermilab Main Injector (FMI) Project. The technical, cost, and schedule baselines for the FMI Project have already been established and may be found in the Fermilab Main Injector Title I Design Report, issued in August 1992. This report updates and expands upon the design and schedule for construction of all subsystem components and associated civil construction described in the Title I Design Report. The facilities described have been designed in conformance with DOE 6430.1A, "United States Department of Energy General Design Criteria."

Engineering Design of KSTAR tokamak main structure

International Nuclear Information System (INIS)

Im, K.H.; Cho, S.; Her, N.I.

2001-01-01

The main components of the KSTAR (Korea Superconducting Tokamak Advanced Research) tokamak including vacuum vessel, plasma facing components, cryostat, thermal shield and magnet supporting structure are in the final stage of engineering design. Hundai Heavy Industries (HHI) has been involved in the engineering design of these components. The current configuration and the final engineering design results for the KSTAR main structure are presented. (author)

Challenges in design of zirconium alloy reactor components

International Nuclear Information System (INIS)

Kakodkar, Anil; Sinha, R.K.

1992-01-01

Zirconium alloy components used in core-internal assemblies of heavy water reactors have to be designed under constraints imposed by need to have minimum mass, limitations of fabrication, welding and joining techniques with this material, and unique mechanisms for degradation of the operating performance of these components. These constraints manifest as challenges for design and development when the size, shape and dimensions of the components and assemblies are unconventional or untried, or when one is aiming for maximization of service life of these components under severe operating conditions. A number of such challenges were successfully met during the development of core-internal components and assemblies of Dhruva reactor. Some of the then untried ideas which were developed and successfully implemented include use of electron beam welding, cold forming of hemispherical ends of reentrant cans, and a large variety of rolled joints of innovative designs. This experience provided the foundation for taking up and successfully completing several tasks relating to coolant channels, liquid poison channels and sparger channels for PHWRs and test sections for the in-pile loops of Dhruva reactor. For life prediction and safety assessment of coolant channels of PHWRs some analytical tools, notably, a computer code for prediction of creep limited life of coolant channels has been developed. Some of the future challenges include the development of easily replaceable coolant channels and also large diameter coolant channels for Advanced Heavy Water Reactor, and development of solutions to overcome deterioration of service life of coolant channels due to hydriding. (author). 5 refs., 13 figs., 1 tab

Development of a purification system at Dhruva to treat oil contaminated and chemically impure heavy water

International Nuclear Information System (INIS)

Suttraway, S.K.; Mishra, V.; Bitla, S.V.; Ghosh, S.K.

2006-01-01

Dhruva, a 100 MW (thermal) Research reactor uses Heavy Water as moderator, reflector and coolant. Normally during plant operation, the Heavy water from the system gets removed during operational and maintenance activities and this collected heavy water gets degraded and contaminated in the process. The degraded heavy water meeting the chemical specification requirement of the up gradation plant is sent for up gradation. Part of the Heavy water collected is contaminated with various organic and inorganic impurities and therefore cannot be sent for IP up gradation as it does not meet the chemical specification of the up gradation plant. This contaminated Heavy water was being stored in SS drums. Over the years of Reactor operation reasonable amount of contaminated Heavy water got collected in the plant. This Heavy water collected from leakages, during routine maintenance, operational activities and fuelling operation had tritium activity and variety of contamination including oil, chlorides, turbidity due to which the specific conductivity was very high. It was decided to purify this Heavy water in house to bring it up to up gradation plant chemical specification requirement. There were number of challenges in formulating a scheme to purify this Heavy water. The scheme needed to be simple and compact in design which could be set up in the plant itself. It should not pose radiological hazards due to radioactive Heavy water during its purification and handling. The contaminated Heavy water collected in drums had varying chemistry and IP. The purification plant should be able to do batch processing so that the different IP and chemical quality of Heavy water stored in different drums are not mixed during purification. It should be capable of removing the oil, chlorides, turbidity and decrease the conductivity to acceptable limits of the Up gradation plant. A purification plant was developed and commissioned after detail laboratory studies and trials. This paper explains

JWST-MIRI spectrometer main optics design and main results

Science.gov (United States)

Navarro, Ramón; Schoenmaker, Ton; Kroes, Gabby; Oudenhuysen, Ad; Jager, Rieks; Venema, Lars

2017-11-01

MIRI ('Mid InfraRed Instrument') is the combined imager and integral field spectrometer for the 5-29 micron wavelength range under development for the James Webb Space Telescope JWST. The flight acceptance tests of the Spectrometer Main Optics flight models (SMO), part of the MIRI spectrometer, are completed in the summer of 2008 and the system is delivered to the MIRI-JWST consortium. The two SMO arms contain 14 mirrors and form the MIRI optical system together with 12 selectable gratings on grating wheels. The entire system operates at a temperature of 7 Kelvin and is designed on the basis of a 'no adjustments' philosophy. This means that the optical alignment precision depends strongly on the design, tolerance analysis and detailed knowledge of the manufacturing process. Because in principle no corrections are needed after assembly, continuous tracking of the alignment performance during the design and manufacturing phases is important. The flight hardware is inspected with respect to performance parameters like alignment and image quality. The stability of these parameters is investigated after exposure to various vibration levels and successive cryogenic cool downs. This paper describes the philosophy behind the acceptance tests, the chosen test strategy and reports the results of these tests. In addition the paper covers the design of the optical test setup, focusing on the simulation of the optical interfaces of the SMO. Also the relation to the SMO qualification and verification program is addressed.

Experience in the application of the IAEA QA code and guides to the manufacture of nuclear reactor components

International Nuclear Information System (INIS)

Dutta, N.G.; Mankame, M.A.; Kulkarni, P.G.; Vijayaraghavan, R.; Balaramamoorthy, K.

1985-01-01

India has made considerable progress in the indigenous manufacture of 'Quality' nuclear reactor components. All activities associated with the development of atomic energy from mining of strategic minerals to the design, construction, and operation of nuclear power plants including supporting research and development efforts are mainly carried out by the Department of Atomic Energy (DAE). Through the sustained efforts of DAE, the major industries, both in public and private sectors supplying nuclear components have now adopted the practice of systematic quality assurance (QA). The stringent QA steps are mandatory for achieving the desired quality in the manufactured nuclear components. Control blades for BWRs are now indigenously manufactured by the Atomic Fuels Division (AFD) of Bhabha Atomic Research Centre (BARC), a constituent unit of DAE. For the Project Dhruva, a 100 MW(th) nuclear reactor, constructed at BARC, Trombay, Bombay, an independent cell was formed to carry out quality audit on the manufactured components. The components were designed, fabricated, inspected and tested to the desired quality level. The QA activities were enforced from the procurement of raw materials to the audit of the completed component for monitoring the manufacturer's continued compliance with the design. The major components of Dhruva, viz. calandria, end-shield, coolant channels, heat exchangers, etc., were covered under these quality audit activities. The paper highlights the QA programme implemented in the manufacture of control blades for BWRs, illustrated with a typical example, the end-shield for Dhruva. The authors consider that the recommendations and guidelines provided in the documents 50-SG-QA3, 50-SG-QA8, 50-SG-QA10, etc., were useful in providing a formal and systematic framework, under which various quality assurance functions have been carried out

Design of SMART alarm system using main memory database

International Nuclear Information System (INIS)

Jang, Kue Sook; Seo, Yong Seok; Park, Keun Oak; Lee, Jong Bok; Kim, Dong Hoon

2001-01-01

To achieve design goal of SMART alarm system, first of all we have to decide on how to handle and manage alarm information and how to use database. So this paper analyses concepts and deficiencies of main memory database applied in real time system. And this paper sets up structure and processing principles of main memory database using nonvolatile memory such as flash memory and develops recovery strategy and process board structures using these. Therefore this paper shows design of SMART alarm system is suited functions and requirements

Heat exchangers in heavy water reactor systems

International Nuclear Information System (INIS)

Mehta, S.K.

1988-01-01

Important features of some major heat exchange components of pressurized heavy water reactors and DHRUVA research reactor are presented. Design considerations and nuclear service classifications are discussed

Aboveground roofed design for the disposal of low-level radioactive waste in Maine

Energy Technology Data Exchange (ETDEWEB)

Alexander, J.A. [Univ. of Maine, Orono, ME (United States)

1993-03-01

The conceptual designs proposed in this report resulted from a study for the Maine Low-level Radioactive Waste Authority to develop conceptual designs for a safe and reliable disposal facility for Maine`s low-level radioactive waste (LLW). Freezing temperatures, heavy rainfall, high groundwater tables, and very complex and shallow glaciated soils found in Maine place severe constraints on the design. The fundamental idea behind the study was to consider Maine`s climatic and geological conditions at the beginning of conceptual design rather than starting with a design for another location and adapting it for Maine`s conditions. The conceptual designs recommended are entirely above ground and consist of an inner vault designed to provide shielding and protection against inadvertent intrusion and an outer building to protect the inner vault from water. The air dry conditions within the outer building should lead to almost indefinite service life for the concrete inner vault and the waste containers. This concept differs sharply from the usual aboveground vault in its reliance on at least two independent, but more or less conventional, roofing systems for primary and secondary protection against leakage of radioisotopes from the facility. Features include disposal of waste in air dry environment, waste loading and visual inspection by remote-controlled overhead cranes, and reliance on engineered soils for tertiary protection against release of radioactive materials.

Fusion reactor blanket-main design aspects

International Nuclear Information System (INIS)

Strebkov, Yu.; Sidorov, A.; Danilov, I.

1994-01-01

The main function of the fusion reactor blanket is ensuring tritium breeding and radiation shield. The blanket version depends on the reactor type (experimental, DEMO, commercial) and its parameters. Blanket operation conditions are defined with the heat flux, neutron load/fluence, cyclic operation, dynamic heating/force loading, MHD effects etc. DEMO/commercial blanket design is distinguished e.g. by rather high heat load and neutron fluence - up to 100 W/cm 2 and 7 MWa/m 2 accordingly. This conditions impose specific requirements for the materials, structure, maintenance of the blanket and its most loaded components - FW and limiter. The liquid Li-Pb eutectic is one of the possible breeder for different kinds of blanket in view of its advantages one of which is the blanket convertibility that allow to have shielding blanket (borated water) or breeding one (Li-Pb eutectic). Using Li-Pb eutectic for both ITER and DEMO blankets have been considered. In the conceptual ITER design the solid eutectic blanket was carried out. The liquid eutectic breeder/coolant is suggested also for the advanced (high parameter) blanket

Switchyard in the Main Injector era conceptual design report

International Nuclear Information System (INIS)

Brown, C.; Kobilarcik, T.; Lucas, P.; Malensek, A.; Murphy, C.T.; Yang, M.-J.

1997-08-01

This report presents elements of a design of the Switchyard and of the present fixed target beamlines in the era of the Main Injector (MI). It presumes that 800 GeV Tevatron beam will be transported to this area in the MI era, and permits it to share cycles with 120 GeV Main Injector beam if this option is desired. Geographically, the region discussed extends from the vicinity of AO to downstream points beyond which beam properties will be determined by the requirements of specific experiments. New neutrino lines not utilizing the present Switchyard (NuMI, BooNE) are not addressed. Similarly Main Injector beams upstream of AO are described fully in MI documentation and are unaffected by what is presented here. The timing both of the preparation of this report and of its recommendations for proceeding with construction relate to a desire to do required work in Transfer Hall and Enclosure B during the Main Injector construction shutdown (September 1997 - September 1998). As these areas are off-limits during any Tevatron operation, it is necessary for the fixed target program that work be completed here during this extended down period. The design presented here enables the operation of all beamlines in the manner specified in the current Laboratory plans for future fixed- target physics

Benchmark of physics design of a proposed 30 MW Multi Purpose Research Reactor using a Monte Carlo code MCNP

International Nuclear Information System (INIS)

Singh, Tej; Kumar, Jainendra; Sharma, Archana; Singh, Kanchhi; Raina, V.K.; Srinivasan, P.

2009-01-01

At present Dhruva and Cirus reactors provide majority of research reactor based experimental/irradiation facilities to cater to various needs of the vast pool of researchers in the field of sciences research and development work for nuclear power plants and production of radioisotopes. With a view to further consolidate and expand the scope of research and development in nuclear and allied sciences, a new 30 MWt Multi Purpose Research Reactor is proposed to be constructed. This paper describes some of the physics design features of this reactor using MCNP code to validate the deterministic methods. The criticality calculations for 100 material testing reactor (JHR) of France and 610 MW SAVANNAH thermal reactor were performed using MCNP computer codes to boost the confidence level in designing the physics design of reactor core. (author)

Research on design method of main control room intake air radioactive monitoring

International Nuclear Information System (INIS)

Li Lei; Sun Yu; Wang Jiaoya; Liu Hongtao

2014-01-01

According to the design of the main control room intake gamma radiation dose rate monitoring channels in CPR1000 project and the study of relevant regulations and standards, a design method of main control room air inlet radioactive monitoring was presented. The measured object, equipment layout and chain operation were described. The threshold setting was explored using a calculation model established by MCNP software. The advantages, disadvantages and improvement ideas of this design were presented on the basis of calculation results. (authors)

Study on the main control room design for Hamaoka Unit No.5

International Nuclear Information System (INIS)

Tsuruta, Tadakazu; Sakamoto, Minoru; Maruyama, Tohru; Saito, Tadashi

2000-01-01

The main control room of nuclear power station is important to operate the power station and to promote public acceptance of nuclear power station. To enhance them, there is an idea of high ceiling control room with a gallery room located in backside middle upper floor. The control room is expected to enhance habitability and to offer visitors the fine view of the control room. In this study, psychological and physiological influence of such a high ceiling control room design on operators was investigated first. And then some human engineering requirements for desirable main control room were identified. A control room (ceiling height: about 5 meters) adequate to the requirements was designed, and finally the validity of the design was verified by means of full mockup model room tests. The results of this study are applied to the main control room design of Hamaoka Nuclear Power Station Unit No.5 (Chubu Electric Power Co., Inc.) (author)

Evaluation of human factors in interface design in main control rooms

International Nuclear Information System (INIS)

Hwang, S.-L.; Liang, S.-F.M.; Liu, T.-Y.Y.; Yang, Y.-J.; Chen, P.-Y.; Chuang, C.-F.

2009-01-01

An evaluation of human factors in a new nuclear power plant was conducted prior to the beginning of any business operations. After the task analysis and observation of training, two stages of interviews were carried out with the operators in the Fourth Nuclear Power Plant (NPP4). The main concerns identified were problems resulting from the operating interface of the display and controls in the main control room, usability of procedures, and the layout of the main control room. The latent human errors and suggestions were listed, and the top three problems were analyzed. The operators indicated that the alarm design issues and the critical problem of the operating mode with the VDU were worth further study in order to provide suggestions for a new interface design for future power plants.

The design and manufacture of the Fermilab Main Injector Dipole Magnet

International Nuclear Information System (INIS)

Brown, B.C.; Chester, N.S.; Harding, D.J.; Martin, P.S.

1992-03-01

Fermilab's new Main Injector Ring (MIR) will replace the currently operating Main Ring to provide 150 GeV Proton and Antiproton beams for Tevetron injection, and rapid cycling, high intensity, 120 GeV Proton beams for Antiproton production. To produce and maintain the required high beam quality, high intensity, and high repetition rate, conventional dipole magnets with laminated iron core and water cooled copper conductor were chosen as the bending magnet. A new magnet design having low inductance, large copper cross section, and field uniformity sufficient for high intensity injection and efficient slow resonant extraction, is required to obtain the needed geometric aperture, dynamic aperture, and operational reliability. The current Main Injector Ring lattice design requires the use of 344 of these magnets. 216 of these magnets are to be 6 m long, and 128 are to be 4 m long

Spatial filter lens design for the main laser of the National Ignition Facility

International Nuclear Information System (INIS)

Korniski, R.J.

1998-01-01

The National Ignition Facility (NIF), being designed and constructed at Lawrence Livermore National Laboratory (LLNL), comprises 192 laser beams The lasing medium is neodymium in phosphate glass with a fundamental frequency (1ω) of 1 053microm Sum frequency generation in a pair of conversion crystals (KDP/KD*P) will produce 1 8 megajoules of the third harmonic light (3ω or λ=351microm) at the target The purpose of this paper is to provide the lens design community with the current lens design details of the large optics in the Main Laser This paper describes the lens design configuration and design considerations of the Main Laser The Main Laser is 123 meters long and includes two spatial filters one 13 5 meters and one 60 meters These spatial filters perform crucial beam filtering and relaying functions We shall describe the significant lens design aspects of these spatial filter lenses which allow them to successfully deliver the appropriate beam characteristic onto the target For an overview of NIF please see ''Optical system design of the National Ignition Facility,'' by R Edward English. et al also found in this volume

Design technology development of the main coolant pump for an integral reactor

International Nuclear Information System (INIS)

Park, J. S.; Lee, J. S.; Kim, M. H.; Kim, D. W.; Kim, J. I.

2004-01-01

All of the reactor coolant pump currently used in commercial nuclear power plant were imported from foreign country. Now, the developing program of design technology for the reactor coolant pump will be started in a few future by domestic researchers. At this stage, the design technology of the main coolant pump for an integral reactor is developed based on the regulation of domestic nuclear power plant facilities. The main coolant pump is a canned motor axial pump, which accommodates all constraints required from the integral reactor system. The main coolant pump does not have mechanical seal device because the rotor of motor and the shaft of impeller are the same one. There is no flywheel on the rotating shaft of main coolant pump so that the coastdown duration time is short when the electricity supply is cut off

A high resolution powder diffractometer using focusing optics

Indian Academy of Sciences (India)

E-mail: siruguri@csr.ernet.in. Abstract. In this paper, we describe the design, construction and performance of a new high resolution neutron powder diffractometer that has been installed at the Dhruva reactor, Trombay, India. The instrument employs novel design concepts like the use of bent, perfect crystal monochromator ...

Concept of Advanced Back-up Control Panel Design of Digital Main Control Room

International Nuclear Information System (INIS)

Jiang, Guo Jin; Sun, Yong Bin; Tan, Ke; Zhang, Li Ming; Shi, Ji; Zhang, Xue Gang; Huang, Wei Jun; Mao, Ting; Liu Yanzi

2011-01-01

Back-up control panel (BCP) of digital main control room (DMCR) is the backup means for main computerized control means (MCM). This paper focus on technical issues for advanced design of Backup Panel (BCP) for CPR1000 using qualified computer-based video display unit to display plant process indication and alarms. HFE issues also have been considered in the BCP design. Then, mean to fulfill safety target of NPP, best ergonomic effect has been described. At last conclusion on advanced BCP design is provided

Concept of Advanced Back-up Control Panel Design of Digital Main Control Room

Energy Technology Data Exchange (ETDEWEB)

Jiang, Guo Jin; Sun, Yong Bin; Tan, Ke; Zhang, Li Ming; Shi, Ji; Zhang, Xue Gang; Huang, Wei Jun; Mao, Ting; Liu Yanzi [China Nuclear Power Engineering Company, Shenzen (China)

2011-08-15

Back-up control panel (BCP) of digital main control room (DMCR) is the backup means for main computerized control means (MCM). This paper focus on technical issues for advanced design of Backup Panel (BCP) for CPR1000 using qualified computer-based video display unit to display plant process indication and alarms. HFE issues also have been considered in the BCP design. Then, mean to fulfill safety target of NPP, best ergonomic effect has been described. At last conclusion on advanced BCP design is provided.

Integrated design of superconducting accelerator magnets. A case study of the main quadrupole

International Nuclear Information System (INIS)

Russenschuck, S.; Calmon, F.; Lewin, M.; Paul, C.; Ramberger, S.; Rodriguez-Mateos, F.; Tortschanoff, T.; Verweij, A.; Wolf, R.

1998-01-01

This paper describes the software tool which has been developed for the design of the superconducting magnets for the large hadron collider (LHC) at CERN. Applied methods include numerical field calculation with a reduced vector-potential formulation, the application of vector-optimization methods, and the use of genetic as well as deterministic minimization algorithms. Together with the applied concept of features, the software tool is used as an approach towards integrated design of superconducting magnets. The main quadrupole magnet for the LHC, which was designed at CEA Saclay (France) using a different approach, was chosen as an example for the integrated design process. The paper focuses on the design issues and is not a project report on the main quadrupoles under construction. (orig.)

Two-Level Designs to Estimate All Main Effects and Two-Factor Interactions

NARCIS (Netherlands)

Eendebak, P.T.; Schoen, E.D.

2017-01-01

We study the design of two-level experiments with N runs and n factors large enough to estimate the interaction model, which contains all the main effects and all the two-factor interactions. Yet, an effect hierarchy assumption suggests that main effect estimation should be given more prominence

Pattern-based framework for data acquisition systems

International Nuclear Information System (INIS)

Padmini, S.; Diwakar, M.P.; Nair, Preetha; Mathew, R.

2004-01-01

The data acquisition framework implements a reusable abstract architectural design for use in the development of data acquisition systems. The framework is being used to build Flux Mapping system (FMs) for TAPS III-IV and RRS Data Acquisition System for Dhruva reactor

The design of trachea-main bronchial covered embranchment stent and the primary clinical application

International Nuclear Information System (INIS)

Han Xinwei; Wu Gang; Gao Xuemei; Li Yongdong; Wang Yanli; Ma Nan

2004-01-01

Objective: To design the trachea-main bronchus covered embranchment stent and study the primary treatment for thoracostomach main bronchial fistula and main bronchial stenosis. Methods: The stent was designed on the bases of the peculiar anatomic structure and the pathological changes of thoracostomach-main bronchial fistula and main bronchial stenosis. Under the fluoroscopic guidance, implantations were carried out in thoracostomach-carina fistula 1 case thoracostomach-left main bronchial fistula 1, thoracostomach-right main bronchial fistula and left main bronchial stenosis 1 case, altogether with 5 stents. Results: Stents were placed successfully, not only improving the breathing and living quality but also completing the closure of the ora of the thoracostomach-airway fistula with further vanishing of the choke after drinking and eating together with the inhalation pneumonia. The bronchus became normal in a main bronchial stenosis after the stent was taken out. Conclusions: Trachea-main bronchial covered embranchment stent could be used to close thoracostomach-airway fistula and to treat main bronchial benign/malignant stenosis. The procedure is simple and safe. (authors)

Conceptual Design of the Linac4 Main Dump

CERN Document Server

Leitao, I V; Maglioni, C

2012-01-01

Linac4 is the new CERN linear accelerator intended to replace the ageing Linac2 as the injector to the Proton Synchrotron Booster (PSB) for increasing the luminosity of the Large Hadron Collider (LHC). By delivering a 160MeV H- beam, Linac4 will provide the necessary conditions to double the brightness and intensity of the beam extracted from the PSB. This paper describes the conceptual design of the Linac4 Main Dump, where two different concepts relying respectively on water and air cooling were compared and evaluated. Based on the application of analytical models for the energy deposited by the beam, heat conduction and cooling concepts, a parametric study was performed. This approach allowed the identification of the “optimal” configuration for these two conceptual geometries and their relative comparison. Besides giving the theoretical guidelines for the design of the new dump, this work also contributes to the development of analytical tools to allow a better understanding of the influence of the se...

Case studies in ultrasonic testing

International Nuclear Information System (INIS)

Prasad, V.; Satheesh, C.; Varde, P.V.

2015-01-01

Ultrasonic testing is widely used Non Destructive Testing (NDT) method and forms the essential part of In-service inspection programme of nuclear reactors. Main application of ultrasonic testing is for volumetric scanning of weld joints followed by thickness gauging of pipelines and pressure vessels. Research reactor Dhruva has completed the first In Service Inspection programme in which about 325 weld joints have been volumetrically scanned, in addition to thickness gauging of 300 meters of pipe lines of various sizes and about 24 nos of pressure vessels. Ultrasonic testing is also used for level measurements, distance measurements and cleaning and decontamination of tools. Two case studies are brought out in this paper in which ultrasonic testing is used successfully for identification of butterfly valve opening status and extent of choking in pipe lines in Dhruva reactor systems

The E-ELT project: the telescope main structure detailed design study

Science.gov (United States)

Marchiori, Gianpietro; Busatta, Andrea; Ghedin, Leonardo; De Lorenzi, Simone

2012-09-01

The European Extremely Large Telescope (E-ELT) is the biggest telescope in the world. Within the Detailed Design activities, ESO has awarded EIE GROUP (European Industrial Engineering) a contract for the Design of the Main Structure to the point where the concept of the telescope has been consolidated, from a construction point of view. All the Design activities have been developed in order to create an integrated system in terms of functionality and performance, while the engineering activities have been performed with the aim of obtaining a telescope that can be built, transported, integrated, with a reduced maintainability.

Preliminary structural design of composite main rotor blades for minimum weight

Science.gov (United States)

Nixon, Mark W.

1987-01-01

A methodology is developed to perform minimum weight structural design for composite or metallic main rotor blades subject to aerodynamic performance, material strength, autorotation, and frequency constraints. The constraints and load cases are developed such that the final preliminary rotor design will satisfy U.S. Army military specifications, as well as take advantage of the versatility of composite materials. A minimum weight design is first developed subject to satisfying the aerodynamic performance, strength, and autorotation constraints for all static load cases. The minimum weight design is then dynamically tuned to avoid resonant frequencies occurring at the design rotor speed. With this methodology, three rotor blade designs were developed based on the geometry of the UH-60A Black Hawk titanium-spar rotor blade. The first design is of a single titanium-spar cross section, which is compared with the UH-60A Black Hawk rotor blade. The second and third designs use single and multiple graphite/epoxy-spar cross sections. These are compared with the titanium-spar design to demonstrate weight savings from use of this design methodology in conjunction with advanced composite materials.

ITER cryostat main chamber and vacuum vessel pressure suppression system design

International Nuclear Information System (INIS)

Ito, Akira; Nakahira, Masataka; Takahashi, Hiroyuki; Tada, Eisuke; Nakashima, Yoshitane; Ueno, Osamu

1999-03-01

Design of Cryostat Main Chamber and Vacuum Vessel Pressure Suppression System (VVPS) of International Thermonuclear Experimental Reactor (ITER) has been conducted. The cryostat is a cylindrical vessel that includes in-vessel component such as vacuum vessel, superconducting toroidal coils and poloidal coils. This cryostat provides the adiabatic vacuum about 10 -4 Pa for the superconducting coils operating at 4 K and forms the second confinement barrier to tritium. The adiabatic vacuum is to reduce thermal loads applied to the superconducting coils and their supports so as to keep their temperature 4 K. The VVPS consists of a suppression tank located under the lower bio-shield and 4 relief pipes to connect the vacuum vessel and the suppression tank. The VVPS is to keep the maximum pressure rise of the vacuum vessel below the design value of 0.5 MPa in case of the in-vessel LOCA (water spillage from in-vessel component). The spilled water and steam are lead to the suppression tank through the relief pipes when the internal pressure of vacuum vessel is over 0.2 MPa, and then the internal pressure is kept below 0.5 MPa. This report summarizes the structural design of the cryostat main chamber and pressure suppression system, together with their fabrication and installation. (author)

ITER cryostat main chamber and vacuum vessel pressure suppression system design

Energy Technology Data Exchange (ETDEWEB)

Ito, Akira; Nakahira, Masataka; Takahashi, Hiroyuki; Tada, Eisuke [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Nakashima, Yoshitane; Ueno, Osamu

1999-03-01

Design of Cryostat Main Chamber and Vacuum Vessel Pressure Suppression System (VVPS) of International Thermonuclear Experimental Reactor (ITER) has been conducted. The cryostat is a cylindrical vessel that includes in-vessel component such as vacuum vessel, superconducting toroidal coils and poloidal coils. This cryostat provides the adiabatic vacuum about 10{sup -4} Pa for the superconducting coils operating at 4 K and forms the second confinement barrier to tritium. The adiabatic vacuum is to reduce thermal loads applied to the superconducting coils and their supports so as to keep their temperature 4 K. The VVPS consists of a suppression tank located under the lower bio-shield and 4 relief pipes to connect the vacuum vessel and the suppression tank. The VVPS is to keep the maximum pressure rise of the vacuum vessel below the design value of 0.5 MPa in case of the in-vessel LOCA (water spillage from in-vessel component). The spilled water and steam are lead to the suppression tank through the relief pipes when the internal pressure of vacuum vessel is over 0.2 MPa, and then the internal pressure is kept below 0.5 MPa. This report summarizes the structural design of the cryostat main chamber and pressure suppression system, together with their fabrication and installation. (author)

State highways as main streets : a study of community design and visioning.

Science.gov (United States)

2009-10-01

The objectives for this project were to explore community transportation design policy to improve collaboration when state highways serve as local main streets, determine successful approaches to meet the federal requirements for visioning set forth ...

Use of probabilistic design methods for NASA applications. [to be used in design phase of Space Transportation Main Engine

Science.gov (United States)

Safie, Fayssal M.

1992-01-01

This paper presents a reliability evaluation process designed to improve the reliability of advanced launch systems. The work performed includes the development of a reliability prediction methodology to be used in the design phase of the Space Transportation Main Engine (STME). This includes prediction techniques which use historical data bases as well as deterministic and probabilistic engineering models for predicting design reliability. In summary, this paper describes a probabilistic design approach for the next-generation liquid rocket engine, the STME.

Research on PCPV for BWR - physical model as design tool - main results

International Nuclear Information System (INIS)

Fumagalli, E.; Verdelli, G.

1975-01-01

ISMES (Experimental Institute for Models and Structures) is now carrying out a series of tests on physical models as a part of a research programme sponsored by DSR (Studies and Research Direction) of ENEL (Italian State Electricity Board) on behalf of CPN (Nuclear Design and Construction Centre) of ENEL with the aim to experience a 'Thin'-walled PCPV for 'BWR'. The physical model, together with the mathematical model and the rheological model of the materials, is intended as a meaningful design tool. The mathematical model covers the overall structural design phase, (geometries) and the linear behaviour, whereas the physical model, besides of a global information to be compared with the results of the mathematical model, supplies a number of data as the non-linear behaviour up to failure and local conditions (penetration area etc.) are concerned. The aim of the first phase of this research programme is to make a comparison between the calculation and experiment tests as the thicknesses of the wall and the bottom slab are concerned, whereas the second phase of the research deals with the behaviour of the removable lid and its connection with the main structure. To do this, a model in scale 1:10 has been designed which symmetrically reproduces with respect to the equator, the bottom part of the structure. In the bottom slab the penetrations of the prototype design are reproduced, whereas the upper slab is plain. This paper describes the model, and illustrates the main results, underlining the different behaviour of the upper and bottom slabs up to collapse

Choke-mode damped structure design for the Compact Linear Collider main linac

CERN Document Server

Zha, Hao; Grudiev, Alexej; Huang, Wenhui; Shi, Jiaru; Tang, Chuanxiang; Wuensch, Walter

2012-01-01

Choke-mode damped structures are being studied as an alternative design to waveguide damped structures for the main linac of the Compact Linear Collider (CLIC). Choke-mode structures have the potential for lower pulsed temperature rise and simpler and less expensive fabrication. An equivalent circuit model based on transmission line theory for higher-order-mode damping is presented. Using this model, a new choke geometry is proposed and the wakefield performance is verified using GDFIDL. This structure has a comparable wakefield damping effect to the baseline design which uses waveguide damping. A prototype structure with the same iris dimensions and accelerating gradient as the nominal CLIC design, but with the new choke geometry, has been designed for high-power tests. DOI: 10.1103/PhysRevSTAB.15.122003

Optical design of the National Ignition Facility main laser and switchyard/target area beam transport systems

Science.gov (United States)

Miller, John L.; English, R. Edward, Jr.; Korniski, Ronald J.; Rodgers, J. Michael

1999-07-01

The optical design of the main laser and transport mirror sections of the National Ignition Facility are described. For the main laser the configuration, layout constraints, multiple beam arrangement, pinhole layout and beam paths, clear aperture budget, ray trace models, alignment constraints, lens designs, wavefront performance, and pupil aberrations are discussed. For the transport mirror system the layout, alignment controls and clear aperture budget are described.

Design of the 1.8 Tesla wiggler for the DAΦNE Main Rings

International Nuclear Information System (INIS)

Sanelli, C.; Hsieh, H.

1992-01-01

The electromagnetic and mechanical design of the eight wiggler magnets for DAΦNE Main Rings is described. The wigglers have a large 1.8 Tesla flat top magnetic field, 64 cm period and 4 cm gap. The magnetic 3-D calculations, the electromagnetic design and the adopted mechanical solutions, with particular attention to the vacuum chamber problems are described. A full scale prototype (5 full poles and two half pole) will be constructed in order to verify the accuracy of magnetic calculations, the end pole design and the multipole content. (author) 4 figs.; 1 tab

Optimal design of a main driving mechanism for servo punch press based on performance atlases

Science.gov (United States)

Zhou, Yanhua; Xie, Fugui; Liu, Xinjun

2013-09-01

The servomotor drive turret punch press is attracting more attentions and being developed more intensively due to the advantages of high speed, high accuracy, high flexibility, high productivity, low noise, cleaning and energy saving. To effectively improve the performance and lower the cost, it is necessary to develop new mechanisms and establish corresponding optimal design method with uniform performance indices. A new patented main driving mechanism and a new optimal design method are proposed. In the optimal design, the performance indices, i.e., the local motion/force transmission indices ITI, OTI, good transmission workspace good transmission workspace(GTW) and the global transmission indices GTIs are defined. The non-dimensional normalization method is used to get all feasible solutions in dimensional synthesis. Thereafter, the performance atlases, which can present all possible design solutions, are depicted. As a result, the feasible solution of the mechanism with good motion/force transmission performance is obtained. And the solution can be flexibly adjusted by designer according to the practical design requirements. The proposed mechanism is original, and the presented design method provides a feasible solution to the optimal design of the main driving mechanism for servo punch press.

Finite impulse testing (FIT) system for Emergency Cooling System (ECS) in Dhruva

International Nuclear Information System (INIS)

Punekar, Parag; Ramkumar, N.; Kulkarni, U.S.; Darbhea, M.D.; Bharadhwaj, G; Jangra, L.R.; Geetha, Patil; Das, Shantanu; Sonnis, S.T.; Trevedi, P.; Patil, M.B.; Biswas, B.B.

2006-01-01

Finite Impulse Testing (FIT) system for Emergency Cooling System (ECS) is used to check healthiness of ECS logic circuits in an online mode. The ECS is an important safety system that ensures the cooling of reactor core during shutdown state of Main Coolant Pumps (MCPs), and hence FIT-ECS that monitors the health of ECS logic circuits in an online (real time) mode is an important part of it. Based on a Safety Related Unusual Occurrence in ECS system due to the malfunction of its earlier single channel FIT system, the new FIT-ECS system has been designed with new features and is commissioned. The FIT-ECS system feeds the simulated input signals (fine impulses of nominal width 575 μS) to the ECS logic circuits and read the outputs. These output (predicted) signals from ECS logic circuit are processed in the FIT-ECS system and in event of any discrepancy, the FIT-ECS system displays fault signature on local panel, detailed information of the fault on Operator Console (OC), and generates an alarm 'ECS logic Fail' in the control room. FIT-ECS also monitors the inputs and outputs of ECS logic circuit. All the information required is stored as a database that can be subsequently displayed in various formats. ECS system is designated as Category I-A system and is a hardwired system and FIT-ECS monitors the healthiness of the logics of the ECS System is a computerized system. As per IEC 1226, FIT-ECS is categorized as Category I-B system. This paper provides technical information on FIT-ECS system design, its important features, the testing carried on the FIT-ECS system, interconnections of FIT-ECS and ECS and the commissioning experience of FIT-ECS system. (author)

Literature survey, numerical examples, and recommended design studies for main-coolant pumps. Final report

International Nuclear Information System (INIS)

Allaire, P.E.; Barrett, L.E.

1982-06-01

This report presents an up-to-date literature survey, examples of calculations of seal forces or other pump properties, and recommendations for future work pertaining to primary coolant pumps and primary recirculating pumps in the nuclear power industry. Five main areas are covered: pump impeller forces, fluid annuli, bearings, seals, and rotor calculations. The main conclusion is that forces in pump impellers is perhaps the least well understood area, seals have had some good design work done on them recently, fluid annuli effects are being discussed in the literature, bearing designs are fairly well known, and rotor calculations have been discussed widely in the literature. It should be noted, however, that usually the literature in a given area is not applied to pumps in nuclear power stations. The most immediate need for a combined theoretical and experimental design capability exists in mechanical face seals

Optimization design of the main switch in 12 MeV linear induction accelerator

International Nuclear Information System (INIS)

Li Xin; Wang Jinsheng; Ding Hensong; Ye Yi

2004-01-01

A method for optimization design of the main switch (using in 12 MeV linear induction accelerator) was introduced. The switch's inductance was decreased from 63.7 nH to 35 nH by optimizing the configuration of the main switch and the size of the electric poles so that the accelerating cavity can get a better rising time of 27 ns. The accelerator's performance can be effectively improved through this method, the feasibility of the method is also proved by testing

Quality assurance in the manufacture of metallic uranium fuel for research reactors

International Nuclear Information System (INIS)

Shah, B.K.; Kumar, Arbind; Nanekar, P.P.; Vaidya, P.R.

2009-01-01

Two Research Reactors viz. CIRUS and DHRUVA are operating at Trombay since 1960 and 1985 respectively. Cirus is a 40 MWth reactor using heavy water as moderator and light water as coolant. Dhruva is a 100 MWth reactor using heavy water as moderator and coolant. The maximum neutron flux of these reactors are 6.7 x 10 13 n/cm 2 /s (Cirus) and 1.8 x 10 14 n/cm 2 /s (Dhruva). Both these reactors are used for basic research, R and D in reactor technology, isotope production and operator training. Fuel material for these reactors is natural uranium metallic rods claded in finned aluminium (99.5%) tubes. This presentation will discuss various issues related to fabrication quality assurance and reactor behavior of metallic uranium fuel used in research reactors

Main design and safety features of a 200MW nuclear heating reactor

International Nuclear Information System (INIS)

Zheng, Wenxiang; Gao, Zuying; Wang, Dazhong

1992-01-01

Inept has been in charge of the development of a nuclear heating reactor since 1980s, which is one of the national key R and D Programs in China. A 5MWt experimental NCR was completed at Inept in 1989 and has operated successfully for space heating since then. In order to realize the commercialization of the NCR, it has been decided to construct a 200MW demonstration NCR in 1993. A number of advanced features, including natural circulation, integrated arrangement, self-pressurized performance, dual vessel structure, hydraulic control rod drive and passive safety systems, have been incorporated into the NCR-200 to achieve its safety goal and economic viability. This makes the NCR safe, simple, reliable, easy-constructed and maintained. At present, the design work of the NCR-200 have shown that its safety characteristics are excellent. The NCR could play an important role in resolving future energy and environmental problems in China. The paper will mainly cover the key design considerations, main technical features and safety analysis results of the NCR-200

Main physics features driving design concept and physics design constraints

International Nuclear Information System (INIS)

Fujisawa, Noboru; Sugihara, Masayoshi; Yamamoto, Shin

1987-07-01

Major physics design philosophies are described, which are essential bases for a plasma design and may have significant impacts on a reactor design concept. Those design philosophies are classified into two groups, physics design drivers and physics design constraints. The design drivers are featured by the fact that a designer is free to choose and the choice may be guided by his opinion, such as ignition, a pulse length, an operation scenario, etc.. The design constraints may follow a physical law, such as plasma confinement, β-limit, density limit, and so on. (author)

Main engineering features driving design concept and engineering design constraints

International Nuclear Information System (INIS)

Saito, Ryusei; Kobayashi, Takeshi; Yamada, Masao

1987-09-01

Major engineering design philosophies are described, which are essential bases for an engineering design and may have significant impacts on a reactor design concept. Those design philosophies are classified into two groups, engineering design drivers and engineering design constraints. The design drivers are featured by the fact that a designer is free to choose and the choice may be guided by his opinion, such as coil system, a mechanical configuration, a tritium breeding scenario, etc.. The design constraints may follow a natural law or engineering limit, such as material strength, coil current density, and so on. (author)

Large screen mimic display design research for advanced main control room in nuclear power plant

International Nuclear Information System (INIS)

Zheng Mingguang; Yang Yanhua; Xu Jijun; Zhang Qinshun; Ning Zhonghe

2002-01-01

Firstly the evolution of mimic diagrams or displays used in the main control room of nuclear power plant was introduced. The active functions of mimic diagrams were analyzed on the release of operator psychological burden and pressure, the assistance of operator for the information searching, status understanding, manual actuation, correct decision making as well as the safe and reliable operation of the nuclear power plant. The importance and necessity to use the (large screen) mimic diagrams in advanced main control room of nuclear power plant, the design principle, design details and verification measures of large screen mimic display are also described

DESIGN, INNOVATION AND PERSONALIZATION – THE MAIN ASSET COMPANY “SIMPO”, VRANJE

Directory of Open Access Journals (Sweden)

Ljiljana Stošić Mihajlović

2013-07-01

Full Text Available The company "Simpo" – Vranje, is the largest exporter of Serbian furniture and more than four decades has been present on the international market, in almost every continent. And today in about 30 countries worldwide exports 65% of production. Its main advantages are a business emphasis on modern design, the constant innovation of products and materials, and personalization.

A conceptual design of main components sizing for UMT PHEV powertrain

Science.gov (United States)

Haezah, M. N.; Norbakyah, J. S.; Atiq, W. H.; Salisa, A. R.

2015-12-01

This paper presents a conceptual design of main components sizing for Universiti Malaysia Terengganu plug-in hybrid electric vehicle (UMT PHEV) powertrain. In the design of hybrid vehicles, it is important to identify a proper component sizes. Component sizing significantly affects vehicle performance, fuel economy and emissions. The proposed UMT PHEV has only one electric machine (EM) which functions as either a motor or generator at a time and using batteries and ultracapacitors as an energy storage system (ESS). In this work, firstly, energy and power requirements based on parameters, specifications and performance requirements of vehicle are calculated. Then, the parameters for internal combustion engine, EM and ESS are selected based on the developed Kuala Terengganu drive cycle. The results obtained from this analysis are within reasonable range and satisfactory.

Design, construction, qualification and reliability of main components, from the safety aspect

International Nuclear Information System (INIS)

Crette, J.P.

1982-01-01

In FRANCE, the design and construction of reliable components, which condition the safe operation and availability of breeder plants, is based on the experience acquired during the operation of RAPSODIE, PHENIX and the various test facilities. The technical progress achieved on all main components is illustrated by examples taken from the CREYS-MALVILLE plant. In parallel with the development of these components, an extensive program covering research, development and the definition of design, construction and inspection rules, together with scheduling and quality assurance methods, prepares the industrialization of this reactor system, in compliance with the rules and recommendations issued by the pertinent safety authorities

Overview of the main challenges for the engineering design of the test facilities system of IFMIF

International Nuclear Information System (INIS)

Molla, J.; Nakamura, K.

2009-01-01

High intense radiation fields were demanded to IFMIF to address the lack of information on effects in materials due to radiation fields with fusion reactor features. Such intense radiation fields will also produce a number of unwanted effects in exposed materials and components. The main difficulties to achieve a reliable engineering design of the Test Facilities System during the Engineering Validation and the Engineering Design phase of IFMIF now under development are reviewed in this paper. The most challenging activities will be the design of the high flux test module, the creep fatigue test module, the test cell and the remote handling system. The intense radiation fields in the irradiation area and the high availability required for IFMIF (70%) are the main reasons for these difficulties.

Engineering design on main mechanism of a high throughput vol-oxidizer for decladding and vol-oxidation of rod-cuts

International Nuclear Information System (INIS)

Kim, Y. H.; Park, B. S.; Jung, J. H.; Yoon, J. S.; Kim, H. D.; Hwang, J. S.; Yoon, K. H.

2008-01-01

In this paper, we designed the main mechanisms for a high throughput device for the rod-cuts of a spent fuel. To design the main mechanisms, we evaluated the current mechanical (slitting, ball mill, roller straightening) and chemical methods (muffle furnace, rotary kiln). As a result, the methods for a ball drop and a rotary drum as concepts were selected at the analysis step. For an enhancement of the oxidation rate, we devised blades for the reactor as a mesh type. Also, for an enhancement of the decladding rate, we designed the ball size and the rotation of the reactor as a mesh type and devised a vacuum system for the fission products. We also designed the main mechanisms devices and tested the capacity of these devices. Mechanisms for the oxidation and recovery can simultaneously handle the rod-cuts of a spent fuel and provide an independent recovery. The results of the mechanisms designs can be used for a scale-up of a high throughput device

The Examination of The Main Transportation Arteries of Konya In Terms of Landscape Architecture Design Criteria

Directory of Open Access Journals (Sweden)

Sertaç Güngör

2017-04-01

Full Text Available Ensuring comfort of use and security of pedestrians, which are the main users of urban green spaces, and the determination of their needs are important since local authorities are guiding for new pedestrian zone studies in the Konya city. Because of the problems caused by the upper structure, the necessary care is not given in terms of transportation comfort, pedestrian safety, vehicle security, plant design and ergonomic / antropemetric standards. The pedestrian way and refuge landscape designs have an important position and amount among open green areas on the scale of Konya. However, it was identified that the applications conducted were inadequate in terms of aesthetic and functional characteristics and were not suitable for the urban landscape design principles, in general, and the standards of urban afforestation of the streets. In this study, the current situation of 3 main streets of Konya used most intensely was examined in terms of landscape design criteria and some suggestions were made by attempting to identify the improvement works that should be performed by the public authorities.

The Fermilab Main Injector dipole and quadrupole cooling design and bus connections

International Nuclear Information System (INIS)

Satti, J.A.

1995-06-01

The proposed system for connecting the low conductivity water (LCW) and the electrical power to the magnets is explained. This system requires minimum maintenance. Stainless steel headers supply LCW to local, secondary manifolds which regulate the flow to the dipole and to the copper bus which conduct both power and cooling water to the quadrupole. A combination of ceramic feedthroughs and thermoplastic hoses insulate the piping electrically from the copper bus system. The utilities for the Main Injector are grouped together at the outside wall of the tunnel leaving most of the enclosure space for servicing. Space above the headers is available for future accelerator expansion. The new dipoles have bolted electrical connections with flexible copper jumpers. Separate compression fittings are used for the water connections. Each dipole magnet has two water circuits in parallel designed to minimize thermal stresses and the number of insulators. Two electrical insulators are used in series because this design has been shown to minimize electrolyses problems and copper ion deposits inside the insulators. The design value of the temperature gradient of the LCW is 8 degrees C

Main components of business cards design

Directory of Open Access Journals (Sweden)

Ю. В. Романенкова

2003-03-01

Full Text Available The essay is dedicated to the urgent problem of necessity of creation of professional design of business cards, that are important part of the image of modem businessman. There are classification of cards by functional principle, the functions of cards of each type were analyzed. All components of business card, variants of its composition schemes, color characteristics, principles of use of trade marks and other design elements have been allocated

Simplified Models for Analysis and Design of the Control System Main Loops of CAREM Reactor

International Nuclear Information System (INIS)

Etchepareborda, Andres; Flury, Celso

2000-01-01

The target of this work is to show a few models developed for control analysis and design of the reactor CAREM's main control loops within a broad range of power (between 40 % and 100%).By one side, it is shown the main features of a analytic model programed in MATLAB.This model is based on fitting steady state points at different power levels of the CAREM's RETRAN model.By the other side, it is shown linear models of black-box type denoting the perturbed behavior of the system for each level power point.These models are identified from temporal responses of CAREM's RETRAN model to perturbed input signals over the different steady power level points.Then the dynamics of these models are verified contrasting the temporal responses of the RETRAN model versus the responses of the MATLAB model and the identified models, in each steady power level point.Also are contrasting the frequency response of the linearization of MATLAB model versus the frequency response of the identified models, in each steady power level point.Either the MATLAB model as the identified models are good enough for the control analysis and design of the three main control loops.The MATLAB model has a few differences against the RETRAN model in the primary pressure output variable, that it must be taken into account in the design of this control loop if this model is used.The aim of these models is to represent in a satisfactory way the dynamics of the plant for a later control analysis and design of the control loops in a frequency range between 0.01 rad/seg and 0.3 rad/seg, and a power range between 40 % and 100 %

Design and fabrication of 4π Clover Detector Array Assembly for gamma-spectroscopy studies using thermal neutrons

International Nuclear Information System (INIS)

Kumar, Manish; Kamble, S.R.; Chaudhari, A.T.; Sabharwal, T.P.; Pathak, Kavindra; Prasad, N.K.; Kinage, L.A.; Biswas, D.C.; Bhagwat, P.V.

2017-01-01

Nuclear spectroscopy has been studied earlier from the measurement of prompt gamma rays produced in reactions with thermal neutrons from CIRUS reactor. For studying the prompt γ-spectroscopy using thermal neutrons from Dhruva Reactor, BARC, the development of a dedicated beam line (R-3001) is in progress. In this beam line a detector assembly consisting of Clover Ge detectors will be used. This experimental setup will be utilized to investigate nuclear structure using prompt (n,γ) reactions and also to study the spectroscopy of neutron-rich fission-fragment nuclei

Design for Fermilab main injector magnet ramps which account for hysteresis

International Nuclear Information System (INIS)

Brown, B.C.; Bhat, C.M.; Harding, D.J.; Martin, P.S.; Wu, G.

1997-05-01

Although the dominant fields in accelerator electromagnets are proportional to the excitation current, precise control of accelerator parameters requires a detailed understanding of the fields in Main Injector magnets including contribution from eddy currents, magnet saturation, and hysteresis. Operation for decelerating beam makes such considerations particularly significant. Analysis of magnet measurements and design of control system software is presented. Field saturation and its effects on low field hysteresis are accounted for in specifying the field ramps for dipole, quadrupole and sextupole magnets. Some simplifying assumptions are made which are accepted as limitations on the required ramp sequences. Specifications are provided for relating desired field ramps to required current ramps for the momentum, tune, and chromaticity control

Main flexible pavement and mix design methods in Europe and challenges for the development of an European method

Directory of Open Access Journals (Sweden)

Paulo Pereira

2017-08-01

Full Text Available Pavement and mix design represent one of the key components within the life cycle of a road infrastructure, with links to political, economic, technical, societal and environmental issues. Recent researches related to the characteristics of materials and associated behavior models both for materials and pavement, made it appropriate to consider updating current pavement design methods, and especially in the USA this has already been in process while in Europe uses of the methods developed in the early 1970s. Thus, this paper firstly presents a brief historical overview of pavement design methods, highlighting early limitations of old empirical methods. Afterwards, French, UK and Shell methods currently in use in Europe will be presented, underlining their main components in terms of methodology, traffic, climatic conditions and subgrade. The asphalt mix design and modeling in Europe are presented with their inclusion in the pavement design methods. Finally, the main challenges for the development of a European pavement design method are presented as well as the recent research developments that can be used for that method.

Condition monitoring of pumps with co-relating field observations

International Nuclear Information System (INIS)

Mishra, S.K.; Prasad, V.; Sharma, R.B.

1994-01-01

The maintenance of 40 MWth research reactor, Cirus has been carried out for over 30 years following the time based maintenance schedule. With the commissioning of indigenously built 100 MWth nuclear research reactor Dhruva in the year 1985, a systematic work on condition monitoring has been commissioned. Apart from process parameters, which are recorded on hourly basis, vibration, noise, temperature, kurtosis etc. are measured for assessment of condition of pumps. The bearings of flywheel assembly of main pumps, Dhruva broke down almost abruptly during the initial years after first commissioning. The regular measurements of vibration level and kurtosis have greatly helped in avoiding breakdown. In a recent case one newly procured herringbone gear box (300 hp, 1475/1760 rpm) for the primary coolant pump was showing high vibration. In further checking using Fast Fourier Transform (FFT) analyser in a time domain plot the gear teeth damage was indicated. The pump was shut down for inspection and when the gear box was dismantled teeth were found broken. An attempt has been made in this paper to discuss a few interesting field experiences with condition monitoring and correlating field observations on pumps. (author). 3 figs

Finite Element Analysis and Lightweight Optimization Design on Main Frame Structure of Large Electrostatic Precipitator

Directory of Open Access Journals (Sweden)

Xuewen Wang

2018-01-01

Full Text Available The geometric modeling and finite element modeling of the whole structure of an electrostatic precipitator and its main components consisting of top beam, column, bottom beam, and bracket were finished. The strength calculation was completed. As a result, the design of the whole structure of the electrostatic precipitator and the main components were reasonable, the structure was in a balance state, its working condition was safe and reliable, its stress variation was even, and the stress distribution was regular. The maximum von Mises stress of the whole structure is 20.14 MPa. The safety factor was large, resulting in a waste of material. An optimization mathematical model is established. Using the ANSYS first-order method, the dimension parameters of the main frame structure of the electrostatic precipitator were optimized. After optimization, more reasonable structural design parameters were obtained. The model weight is 72,344.11 kg, the optimal weight is 49,239.35 kg, and the revised weight is 53,645.68 kg. Compared with the model weight, the optimal weight decreased by 23,104.76 kg and the objective function decreased by 31.94%, while the revised weight decreased by 18,698.43 kg and the objective function decreased by 25.84%.

LECOTELO - conceptual design, testings and realisation of the main vessel

International Nuclear Information System (INIS)

Ioan, M.; Hororoi, M.

2013-01-01

Lead Corrosion Testing Loop (LECOTELO) facility was conceived to assure all conditions requested by corrosion/erosion tests in pure hot lead for different materials. The main vessel will receive at least 36 different material samples; each of them must be swept on both sides by a lead flow at a very well known speed. Taking into account that the inner system of this vessel is rather complex, it is very important to know the behavior of the vessel at different speeds of the lead flow around the samples. After many simulations of different configurations of the inner components, it was obtained the best inner geometry of the flow which provides the minimum pressure loss between inlet and outlet vessel. Consequently, the design of vessel components was changed in accordance with these new results of simulations and in this moment they are in the manufacturing process. (authors)

FERMILAB: Main Injector

International Nuclear Information System (INIS)

Anon.

1993-01-01

The Fermilab Main Injector (FMI) project is the centerpiece of the Laboratory's Fermilab III programme for the 1990s. Designed to support a luminosity of at least 5x10 31 cm -2 s -1 in the Tevatron collider, it will also provide new capabilities for rare neutral kaon decay and neutrino oscillation studies. The Fermilab Main Injector 8-150 GeV synchrotron is designed to replace the existing Main Ring which seriously limits beam intensities for the Tevatron and the antiproton production target. The project has passed several significant milestones and is now proceeding rapidly towards construction. The project received a $11.65M appropriation in 1992 and has been given $15M for the current fiscal year. Through the Energy Systems Acquisition Advisory Board (ESAAB) process, the US Department of Energy (DoE) has authorized funds for construction of the underground enclosure and service building where the Main Injector will touch the Tevatron, and to the preparation of bids for remaining project construction

Multi purpose research reactor

International Nuclear Information System (INIS)

Raina, V.K.; Sasidharan, K.; Sengupta, Samiran; Singh, Tej

2006-01-01

At present Dhruva and Cirus reactors provide the majority of research reactor based facilities to cater to the various needs of a vast pool of researchers in the field of material sciences, physics, chemistry, bio sciences, research and development work for nuclear power plants and production of radio isotopes. With a view to further consolidate and expand the scope of research and development in nuclear and allied sciences, a new 20 MWt multi purpose research reactor is being designed. This paper describes some of the design features and safety aspects of this reactor

Ergonomic Investigation On The Layout And Design Of The Main Control Room Of (MCR)Reactor Thermalhydraulic Testing Loop

International Nuclear Information System (INIS)

DARLlS; WIDAGDO, SUHARYO

2000-01-01

Ergonomics investigation on the layout and design of the reactor thermalhydraulic testing loop main control room has been done. This reason is needed to be done as the primary step for evaluating of operator workload. The operator work load be influence on the operator performance, and finally would influencing the installation operation safety. Generally, the factors that is influencing on operator performance are the layout and design of MCR and its supporting physical environments factors for instance lighting, noising and climatic condition respectively. From investigation had been done, cod be identified that ergonomics point of view not implemented yet on the main control console design, especially on the alarm panel, and also found a little bit brightness problem. Otherwise the temperature and noise room are still in the tolerance boundary

FERMILAB: Main Injector

Energy Technology Data Exchange (ETDEWEB)

Anon.

1993-06-15

The Fermilab Main Injector (FMI) project is the centerpiece of the Laboratory's Fermilab III programme for the 1990s. Designed to support a luminosity of at least 5x10{sup 31} cm{sup -2} s{sup -1} in the Tevatron collider, it will also provide new capabilities for rare neutral kaon decay and neutrino oscillation studies. The Fermilab Main Injector 8-150 GeV synchrotron is designed to replace the existing Main Ring which seriously limits beam intensities for the Tevatron and the antiproton production target. The project has passed several significant milestones and is now proceeding rapidly towards construction. The project received a $11.65M appropriation in 1992 and has been given $15M for the current fiscal year. Through the Energy Systems Acquisition Advisory Board (ESAAB) process, the US Department of Energy (DoE) has authorized funds for construction of the underground enclosure and service building where the Main Injector will touch the Tevatron, and to the preparation of bids for remaining project construction.

Telemetry system for monitoring the ECG for patients with high cardiovascular risk. Main design requirements and technical solutions

International Nuclear Information System (INIS)

Rodriguez, J; Meissimilly, G; Berovides, JD

2005-01-01

In this paper the main design requirements concerning the setting up of a telemetry ECG monitoring system are presented. The design's most important technical solutions as well as some details are also discussed. This system is intended to provide skilled medical assistance during the cardiac rehabilitation of both asymptomatic and high risk coronary patients

Universal method for opnimal design main structural assemblies of steel structures stationary conveyor with hanging ribbon

Directory of Open Access Journals (Sweden)

Boslovyak P.V.

2015-10-01

Full Text Available The technique and the detailed algorithm for optimal design of steel structures hospitaltion of the conveyor with hang-ing ribbon. Developed a universal objective function together with the system-limited-subject to limits of main components of steel structures of stationary conveyor with hanging ribbon.

Turbine main engines

CERN Document Server

Main, John B; Herbert, C W; Bennett, A J S

1965-01-01

Turbine Main Engines deals with the principle of operation of turbine main engines. Topics covered include practical considerations that affect turbine design and efficiency; steam turbine rotors, blades, nozzles, and diaphragms; lubricating oil systems; and gas turbines for use with nuclear reactors. Gas turbines for naval boost propulsion, merchant ship propulsion, and naval main propulsion are also considered. This book is divided into three parts and begins with an overview of the basic mode of operation of the steam turbine engine and how it converts the pressure energy of the ingoing ste

MINU Main Injector Neutrino Upgrade: Conceptual Design Report

Energy Technology Data Exchange (ETDEWEB)

Bogert, Dixon [Fermilab; Alber, Russ [Fermilab

2007-02-01

This Conceptual Design Report (CDR) is intended to be a selfconsistent basis for a project baseline cost estimate. It is not a Title 1 report and has not answered every technical design question. The current level of contingency is believed to be consistent with the degree of technical confidence in the design at this stage. It is recognized that some basic construction concerns will be reviewed and optimized during the remaining stages of the project.

Plutonium Plant, Trombay

International Nuclear Information System (INIS)

Yadav, J.S.; Agarwal, K.

2017-01-01

The journey of Indian nuclear fuel reprocessing started with the commissioning of Plutonium Plant (PP) at Trombay on 22"n"d January, 1965 with an aim to reprocess the spent fuel from research reactor CIRUS. The basic process chosen for the plant was Plutonium Uranium Reduction EXtraction (PUREX) process. In seventies, the plant was subjected to major design modifications and replacement of hardware, which later met the additional demand from research reactor DHRUVA. The augmented plutonium plant has been operating since 1983. Experience gained from this plant was very much helpful to design future reprocessing plant in the country

Maine's Employability Skills Program

Science.gov (United States)

McMahon, John M.; Wolffe, Karen E.; Wolfe, Judy; Brooker, Carrie

2013-01-01

This Practice Report describes the development and implementation of the "Maine Employability Skills Program," a model employment program developed by the Maine Division for the Blind and Visually Impaired (DBVI). The program was designed to support the efforts of the chronically unemployed or underemployed. These consumers were either…

14 CFR 27.547 - Main rotor structure.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Main rotor structure. 27.547 Section 27.547... structure. (a) Each main rotor assembly (including rotor hubs and blades) must be designed as prescribed in this section. (b) [Reserved] (c) The main rotor structure must be designed to withstand the following...

Activities of the Main Studies and Designing Bureau for Mines in export of technical experience and international cooperation

Energy Technology Data Exchange (ETDEWEB)

Danielak, Z

1985-07-01

The Main Studies and Designing Bureau for Mines in Poland consists of 3 units: the Mine Design Bureau in Katowice (leading unit) and Mine Design Bureaus in Cracow and Katowice. There are 2200 employees (75% specialists) in 3 units. The Bureau is the leading agency for coal mine design and mine modernization in Poland. In 35 years the Bureau has developed the design of 25 coal mines in Poland, the design of more than 100 mining levels, and modernization projects for more than 50 coal mines. The Bureau specializes in programs for coal district development, mine design and mine modernization. It has developed the design of coal mines and coal preparation plants in the following countries: Albania, China, Mongolia, Vietnam, Argentina, Colombia, Canada, Colombia, India, Mexico, Peru and Venezuela. Prospects for increasing exports by the Bureau are discussed.

Performance Data from a Wind-Tunnel Test of Two Main-rotor Blade Designs for a Utility-Class Helicopter

Science.gov (United States)

Singleton, Jeffrey D.; Yeager, William T., Jr.; Wilbur, Matthew L.

1990-01-01

An investigation was conducted in the NASA Langley Transonic Dynamics Tunnel to evaluate an advanced main rotor designed for use on a utility class helicopter, specifically the U.S. Army UH-60A Blackhawk. This rotor design incorporated advanced twist, airfoil cross sections, and geometric planform. For evaluation purposes, the current UH-60A main rotor was also tested and is referred to as the baseline blade set. A total of four blade sets were tested. One set of both the baseline and the advanced rotors were dynamically scaled to represent a full scale helicopter rotor blade design. The remaining advanced and baseline blade sets were not dynamically scaled so as to isolate the effects of structural elasticity. The investigation was conducted in hover and at rotor advance ratios ranging from 0.15 to 0.4 at a range of nominal test medium densities from 0.00238 to 0.009 slugs/cu ft. This range of densities, coupled with varying rotor lift and propulsive force, allowed for the simulation of several vehicle gross weight and density altitude combinations. Performance data are presented for all blade sets without analysis; however, cross referencing of data with flight condition may be useful to the analyst for validating aeroelastic theories and design methodologies as well as for evaluating advanced design parameters.

State-of-the-art of wind turbine design codes: main features overview for cost-effective generation

Energy Technology Data Exchange (ETDEWEB)

Molenaar, D-P.; Dijkstra, S. [Delft University of Technology (Netherlands). Mechanical Engineering Systems and Control Group

1999-07-01

For successful large-scale application of wind energy, the price of electricity generated by wind turbines should decrease. Model-based control can be important since it has the potential to reduce fatigue loads, while simultaneously maintaining a desired amount of energy production. The controller synthesis, however, requires a mathematical model describing the most important dynamics of the complete wind turbine. In the wind energy community there is a wide variety in codes used to model a wind turbine's dynamic behaviour or to carry out design calculations. In this paper, the main features of the state-of-the-art wind turbine design codes have been investigated in order to judge the appropriateness of using one of these for the modeling, identification and control of flexible, variable speed wind turbines. It can be concluded that, although the sophistication of the design codes has increased enormously over the last two decades, they are, in general, not suitable for the design, and easy implementation of optimal operating strategies.

Prediction of the Main Engine Power of a New Container Ship at the Preliminary Design Stage

Science.gov (United States)

Cepowski, Tomasz

2017-06-01

The paper presents mathematical relationships that allow us to forecast the estimated main engine power of new container ships, based on data concerning vessels built in 2005-2015. The presented approximations allow us to estimate the engine power based on the length between perpendiculars and the number of containers the ship will carry. The approximations were developed using simple linear regression and multivariate linear regression analysis. The presented relations have practical application for estimation of container ship engine power needed in preliminary parametric design of the ship. It follows from the above that the use of multiple linear regression to predict the main engine power of a container ship brings more accurate solutions than simple linear regression.

Procedures for the design of the main mechanical components of a wind system; Dimensionamento dos componentes mecanicos principais de aerogeradores

Energy Technology Data Exchange (ETDEWEB)

Hirata, M.H.; Marco Filho, F. de [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia

1990-12-31

Procedures for the design of the main mechanical components of a wind system were developed. One of the main concerns was related to the possibility of its use in small micro-computers. This goal was reached and an APPLE II computer was used. The resulting algorithm permits a friendly interaction between man and machine. 5 refs., 12 figs

Conceptual design of the DEMO neutral beam injectors: main developments and R&D achievements

Science.gov (United States)

Sonato, P.; Agostinetti, P.; Bolzonella, T.; Cismondi, F.; Fantz, U.; Fassina, A.; Franke, T.; Furno, I.; Hopf, C.; Jenkins, I.; Sartori, E.; Tran, M. Q.; Varje, J.; Vincenzi, P.; Zanotto, L.

2017-05-01

The objectives of the nuclear fusion power plant DEMO, to be built after the ITER experimental reactor, are usually understood to lie somewhere between those of ITER and a ‘first of a kind’ commercial plant. Hence, in DEMO the issues related to efficiency and RAMI (reliability, availability, maintainability and inspectability) are among the most important drivers for the design, as the cost of the electricity produced by this power plant will strongly depend on these aspects. In the framework of the EUROfusion Work Package Heating and Current Drive within the Power Plant Physics and Development activities, a conceptual design of the neutral beam injector (NBI) for the DEMO fusion reactor has been developed by Consorzio RFX in collaboration with other European research institutes. In order to improve efficiency and RAMI aspects, several innovative solutions have been introduced in comparison to the ITER NBI, mainly regarding the beam source, neutralizer and vacuum pumping systems.

Design and performance of General Electric boiling water reactor main steam line isolation valves

International Nuclear Information System (INIS)

Rockwell, D.A.; van Zylstra, E.H.

1976-08-01

An extensive test program has been completed by the General Electric Company in cooperation with the Commonwealth Edison Company on the basic design type of large main steam line isolation valves used on General Electric Boiling Water Reactors. Based on a total of 40 tests under simulated accident conditions covering a wide range of mass flows, mixture qualities, and closing times, it was concluded that the commercially available valves of this basic type will close completely and reliably as required. Analytical methods to predict transient effects in the steam line and valve after postulated breaks were refined and confirmed by the test program

The investigation of the superconducting NMR-imaging main magnets

International Nuclear Information System (INIS)

Zhang, Y.; Han, S.; Feng, Z.X.

1989-01-01

The design principles of MRI main magnets and the problems in the design process have been analyzed. A computer program in which the critical characteristics of superconductor, the uniformity of the magnetic field, the economization of magnet and the selection of magnet constructions are considered has been established. The program can also be used to design high uniformity superconducting magnet in some other uses. In designing MRI superconducting main magnet, five different magnet constructions have been analyzed. Using this computer program the authors made a series of designs of MRI superconducting main magnets with different construction, different central magnetic field, and different bore diameters. By analyzing the computing results some conclusions useful for the practical design of the MRI superconducting main magnets are obtained

Heat transfer and fluid flow research relevant to India's nuclear power program

International Nuclear Information System (INIS)

Mehta, S.K.; Venkatraj, V.

1988-01-01

The Indian Nuclear Power Programme envisages three important stages viz., installation of thermal reactors, fast reactors and utilization of Thorium. By the year 2000 AD, it is proposed to have an installed total capacity of nuclear power of about 10,000 MWe. Starting from the present installed capacity of 1330 MWe, the additional contribution will be mainly made by thermal power reactors of the Pressurized Heavy Water type (PHWR). Apart from the reactors presently under construction about 12 numbers of 235 MWe units are planned to be constructed, which will be based on the standardized design of the reactors at Narora Atomic Power Project (NAPP). In addition, 10 units of 500 MWe capacity each, the design for which is currently under progress, will also be installed. The design, construction and operating agency is the Nuclear Power Board (NPB), while the Bhabha Atomic Research Centre (BARC) is responsible for the research and development work required. In addition to the programme on thermal power reactors, a thermal research reactor (DHRUVA) of 100 MWth capacity has been designed, constructed and has been commissioned. Some of the important heat transfer and fluid flow research problems relevant to the Indian nuclear power and research reactors are discussed in this paper

Design and main characteristics of HTGR fuel elements

International Nuclear Information System (INIS)

Chernikov, A.S.; Kolesov, V.S.; Permyakov, L.N.; Koshelev, Yu.V.; Mikhajlichenko, L.I.

1983-01-01

Two types of spherical fuel elements and coated particles were investigated under the operating conditions of the high temperature reactors in the Soviet Union (VGR-50 and VG-400). This paper gives the main characteristics of spherical fuel elements (thermal conductivity, static and dynamic strength, wear resistance, release of gaseous fission products, etc.) as determined in test facilities. (author)

The optimum support design selection by using AHP method for the main haulage road in WLC Tuncbilek colliery

Energy Technology Data Exchange (ETDEWEB)

Yavuz, M.; Iphar, M.; Once, G.

2008-03-15

The engineers can frequently encounter with the situation to select the optimum option among the alternatives related with mining operations. The optimum choice can be selected by the experienced engineers taking into consideration their judgement and intuition. However, decision-making methods can offer to the engineers to support their optimum selection for a particular application in the scientific way. The Analytical Hierarchy Process (AHP) is one of the multi attribute decision-making (MADM) methods utilizing structured pair-wise comparisons. This paper presents an application of the AHP method to the selection of the optimum support design for the main transport road, which has been planned for deep coal seam panels of Western Lignite Corporation (WLC) Tuncbilek in Turkeiy. The methodology considers eight main objectives, namely: four different displacement values for determined history locations, factor of safety (FOS), cost, labour and applicability factor for the selection of support design. The displacements and stress values were obtained by using the finite difference program FLAC(3D) as the numerical studies have been widely used by the engineers examining the response of any opening in underground, in advance. After carrying out several numerical models for different support design, the AHP method was incorporated to evaluate these support designs according to the pre-determined criteria. The result of this study shows that such AHP application can assist the engineers to effectively evaluate the support system alternatives for an underground mine.

Collins' bypass for the main ring

International Nuclear Information System (INIS)

Ohnuma, S.

1982-01-01

Design of the bypass for the main ring at Fermilab is discussed. Specific design features discussed include space, path length, geometric closure, matching of betatron functions, and external dispersion. Bypass parameters are given

Safety evaluation of small samples for isotope production

International Nuclear Information System (INIS)

Sharma, Archana; Singh, Tej; Varde, P.V.

2015-09-01

Radioactive isotopes are widely used in basic and applied science and engineering, most notably as environmental and industrial tracers, and for medical imaging procedures. Production of radioisotope constitutes important activity of Indian nuclear program. Since its initial criticality DHRUVA reactor has been facilitating the regular supply of most of the radioisotopes required in the country for application in the fields of medicine, industry and agriculture. In-pile irradiation of the samples requires a prior estimation of the sample reactivity load, heating rate, activity developed and shielding thickness required for post irradiation handling. This report is an attempt to highlight the contributions of DHRUVA reactor, as well as to explain in detail the methodologies used in safety evaluation of the in pile irradiation samples. (author)

Conceptual design of main coolant pump for integral reactor SMART

Energy Technology Data Exchange (ETDEWEB)

Park, Jin Seok; Kim, Jong In; Kim, Min Hwan [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-12-01

The conceptual design for MCP to be installed in the integral reactor SMART was carried out. Canned motor pump was adopted in the conceptual design of MCP. Three-dimensional modeling was performed to visualize the conceptual design of the MCP and to check interferences between the parts. The theoretical design procedure for the impeller was developed. The procedures for the flow field and structural analysis of impeller was also developed to assess the design validity and to verify its structural integrity. A computer program to analyze the dynamic characteristics of the rotor shaft of MCP was developed. The rotational speed sensor was designed and its performance test was conducted to verify the possibility of operation. A prototypes of the canned motor was manufactured and tested to confirm the validity of the design concept. The MCP design concept was also investigated for fabricability by establishing the manufacturing procedures. 41 refs., 96 figs., 10 tabs. (Author)

Main building complex WWER 440/213 upper range design response spectra for soft soil site conditions (Paks)

International Nuclear Information System (INIS)

Krutzik, N.

1996-01-01

Within the Benchmark studies parallel investigation were prepared for the main building complex of the WWER-440/213 Paks NPP by several participating institutions. The investigations were based on various mathematical models and procedures but all had the same seismological data as input. The calculation methods as well as software tools were different. This report covers the enveloped response results which were the basis for the benchmark studies and which should be used for upgrading of mechanical and electrical components and systems which will follow. These response spectra which consider a certain conservatism namely neglecting the frequency independence of the stiffness and the cut-off of damping values are named 'Upper Range design Benchmark Response Spectra' for the main building of Paks NPP

Main building complex WWER 440/213 upper range design response spectra for soft soil site conditions (Paks)

Energy Technology Data Exchange (ETDEWEB)

Krutzik, N [Siemens AG, Power Generation Group (KWU) NDA2, Offenbach (Germany)

1996-07-01

Within the Benchmark studies parallel investigation were prepared for the main building complex of the WWER-440/213 Paks NPP by several participating institutions. The investigations were based on various mathematical models and procedures but all had the same seismological data as input. The calculation methods as well as software tools were different. This report covers the enveloped response results which were the basis for the benchmark studies and which should be used for upgrading of mechanical and electrical components and systems which will follow. These response spectra which consider a certain conservatism namely neglecting the frequency independence of the stiffness and the cut-off of damping values are named 'Upper Range design Benchmark Response Spectra' for the main building of Paks NPP.

Design and construction of the main linac module for the superconducting energy recovery linac project at Cornell

Energy Technology Data Exchange (ETDEWEB)

Eichhorn, R.; Bullock, B.; He, Y.; Hoffstaetter, G.; Liepe, M.; O' Connell, T.; Quigley, P.; Sabol, D.; Sears, J.; Smith, E.; Veshcherevich, V. [Cornell Laboratory for Accelerator-based Science and Education (CLASSE), Cornell University, 161 Synchrotron Drive, Ithaca, NY 14853 (United States)

2014-01-29

Cornell University has been designing and building superconducting accelerators for various applications for more than 50 years. Currently, an energy-recovery linac (ERL) based synchrotron-light facility is proposed making use of the existing CESR facility. As part of the phase 1 R and D program funded by the NSF, critical challenges in the design were addressed, one of them being a full linac cryo-module. It houses 6 superconducting cavities- operated at 1.8 K in continuous wave (CW) mode - with individual HOM absorbers and one magnet/ BPM section. Pushing the limits, a high quality factor of the cavities (2⋅10{sup 10}) and high beam currents (100 mA accelerated plus 100 mA decelerated) are targeted. We will present the design of the main linac cryo-module (MLC) being finalized recently, its cryogenic features and report on the status of the fabrication which started in late 2012.

Structures of Two Coronavirus Main Proteases: Implications for Substrate Binding and Antiviral Drug Design

Energy Technology Data Exchange (ETDEWEB)

Xue, Xiaoyu; Yu, Hongwei; Yang, Haitao; Xue, Fei; Wu, Zhixin; Shen, Wei; Li, Jun; Zhou, Zhe; Ding, Yi; Zhao, Qi; Zhang, Xuejun C.; Liao, Ming; Bartlam, Mark; Rao, Zihe (SCAU); (Tsinghua); (Chinese Aca. Sci.)

2008-07-21

Coronaviruses (CoVs) can infect humans and multiple species of animals, causing a wide spectrum of diseases. The coronavirus main protease (M{sup pro}), which plays a pivotal role in viral gene expression and replication through the proteolytic processing of replicase polyproteins, is an attractive target for anti-CoV drug design. In this study, the crystal structures of infectious bronchitis virus (IBV) MP{sup pro} and a severe acute respiratory syndrome CoV (SARS-CoV) M{sup pro} mutant (H41A), in complex with an N-terminal autocleavage substrate, were individually determined to elucidate the structural flexibility and substrate binding of M{sup pro}. A monomeric form of IBV M{sup pro} was identified for the first time in CoV M{sup pro} structures. A comparison of these two structures to other available M{sup pro} structures provides new insights for the design of substrate-based inhibitors targeting CoV M{sup pro}s. Furthermore, a Michael acceptor inhibitor (named N3) was cocrystallized with IBV M{sup pro} and was found to demonstrate in vitro inactivation of IBV M{sup pro} and potent antiviral activity against IBV in chicken embryos. This provides a feasible animal model for designing wide-spectrum inhibitors against CoV-associated diseases. The structure-based optimization of N3 has yielded two more efficacious lead compounds, N27 and H16, with potent inhibition against SARS-CoV M{sup pro}.

Design and analysis of the tooling upgrade for the production of the superconductive main dipole magnet prototypes of LHC

CERN Document Server

AUTHOR|(CDS)2093638

Design and analysis of the tooling upgrade for the production of the superconductive main dipole magnet prototypes of LHC Master of Science Thesis, 110 pages, 12 Appendix pages September 2013 Major: Design of machines and systems Examiner: Professor Reijo Kouhia Keywords: CERN, LHC, High Luminosity LHC project, superconductive dipole magnet, welding press, Nb$_{3}$Sn, pre-stress, Ar-inert gas furnace This thesis work has been carried out as a contribution to the development program of superconductive magnets within the LHC High Luminosity study. The thesis provides an insight to the steps that need to be taken in order to produce a superconductive magnet mainly focusing on mechanical assembly. Tooling upgrade is necessary for the production of the superconductive dipole magnet prototypes in near future. Major attention is given by the introduction of the welding assembly in chapter three. The structural compression is given by the so called shell stress defined by the thermal shrinkage of the weld. The associ...

The influence on the contact condition and initial fixation stability of the main design parameters of a self-expansion type anterior cruciate ligament fixation device

International Nuclear Information System (INIS)

Kim, Jong Dae; Oh, Chae Youn; Kim, Cheol Sang

2008-01-01

This paper proposes a self-expansion type anterior cruciate ligament fixation device. The proposed fixation device provides graft fixation force by maintaining contact with the bone tunnel. Since the device maintains contact with the bone tunnel by the force that expands by the self-driven elastic force of the device, the main design parameters that determine the performance of this device are the ring thickness and expansion angle. This paper develops the three-dimensional finite element models of the fixation device and bone. By simulation with the developed finite element model, this paper studies the influence of the main design parameters of the device on the maximum stress around the ring when grasping the fixation device. Through the analysis of the stress on the bone tunnel wall when the fixation device comes in contact with the bone tunnel, this paper shows the influence of the main design parameters of the fixation device on the contact condition. In addition, through the analysis of the migration that occur upon application of the pull-out force, this paper studies the influence of the main design parameters on the initial fixation stability of the fixation device

The influence on the contact condition and initial fixation stability of the main design parameters of a self-expansion type anterior cruciate ligament fixation device

Energy Technology Data Exchange (ETDEWEB)

Kim, Jong Dae [Jeonju University, Jeonju (Korea, Republic of); Oh, Chae Youn; Kim, Cheol Sang [Chonbuk National University, Jeonju (Korea, Republic of)

2008-12-15

This paper proposes a self-expansion type anterior cruciate ligament fixation device. The proposed fixation device provides graft fixation force by maintaining contact with the bone tunnel. Since the device maintains contact with the bone tunnel by the force that expands by the self-driven elastic force of the device, the main design parameters that determine the performance of this device are the ring thickness and expansion angle. This paper develops the three-dimensional finite element models of the fixation device and bone. By simulation with the developed finite element model, this paper studies the influence of the main design parameters of the device on the maximum stress around the ring when grasping the fixation device. Through the analysis of the stress on the bone tunnel wall when the fixation device comes in contact with the bone tunnel, this paper shows the influence of the main design parameters of the fixation device on the contact condition. In addition, through the analysis of the migration that occur upon application of the pull-out force, this paper studies the influence of the main design parameters on the initial fixation stability of the fixation device

Dynamic imperfections and optimized feedback design in the Compact Linear Collider main linac

Directory of Open Access Journals (Sweden)

Peder Eliasson

2008-05-01

Full Text Available The Compact Linear Collider (CLIC main linac is sensitive to dynamic imperfections such as element jitter, injected beam jitter, and ground motion. These effects cause emittance growth that, in case of ground motion, has to be counteracted by a trajectory feedback system. The feedback system itself will, due to jitter effects and imperfect beam position monitors (BPMs, indirectly cause emittance growth. Fast and accurate simulations of both the direct and indirect effects are desirable, but due to the many elements of the CLIC main linac, simulations may become very time consuming. In this paper, an efficient way of simulating linear (or nearly linear dynamic effects is described. The method is also shown to facilitate the analytic determination of emittance growth caused by the different dynamic imperfections while using a trajectory feedback system. Emittance growth expressions are derived for quadrupole, accelerating structure, and beam jitter, for ground motion, and for noise in the feedback BPMs. Finally, it is shown how the method can be used to design a feedback system that is optimized for the optics of the machine and the ground motion spectrum of the particular site. This feedback system gives an emittance growth rate that is approximately 10 times lower than that of traditional trajectory feedbacks. The robustness of the optimized feedback system is studied for a number of additional imperfections, e.g., dipole corrector imperfections and faulty knowledge about the machine optics, with promising results.

Dynamic imperfections and optimized feedback design in the Compact Linear Collider main linac

Science.gov (United States)

Eliasson, Peder

2008-05-01

The Compact Linear Collider (CLIC) main linac is sensitive to dynamic imperfections such as element jitter, injected beam jitter, and ground motion. These effects cause emittance growth that, in case of ground motion, has to be counteracted by a trajectory feedback system. The feedback system itself will, due to jitter effects and imperfect beam position monitors (BPMs), indirectly cause emittance growth. Fast and accurate simulations of both the direct and indirect effects are desirable, but due to the many elements of the CLIC main linac, simulations may become very time consuming. In this paper, an efficient way of simulating linear (or nearly linear) dynamic effects is described. The method is also shown to facilitate the analytic determination of emittance growth caused by the different dynamic imperfections while using a trajectory feedback system. Emittance growth expressions are derived for quadrupole, accelerating structure, and beam jitter, for ground motion, and for noise in the feedback BPMs. Finally, it is shown how the method can be used to design a feedback system that is optimized for the optics of the machine and the ground motion spectrum of the particular site. This feedback system gives an emittance growth rate that is approximately 10 times lower than that of traditional trajectory feedbacks. The robustness of the optimized feedback system is studied for a number of additional imperfections, e.g., dipole corrector imperfections and faulty knowledge about the machine optics, with promising results.

Drive mechanism for shut down system-1 of TAPP-3 and 4

International Nuclear Information System (INIS)

Singh, Manjit; Badodkar, D.N.

2002-01-01

Full text: Shut down system-l (SDS-l) being the most important safety system of the nuclear power plant, it calls for a very high reliability of operation as well as effectiveness, which are mainly governed by its ability to operate within a very short interval and the magnitude of the negative reactivity worth it can impart to the reactor. Design, development and qualification work for drive mechanism of SDS-l for Tarapur Atomic Power Project-3 and 4 (TAPP-3 and 4) was taken up at Division of Remote Handling and Robotics (DRHR), Bhabha Atomic Research Centre (BARC). An electromechanical, cable winch type drive mechanism with advance features has been developed for this purpose. The design and life cycle testing of the prototype drive mechanism on full-scale test station has been completed. Based on satisfactory test performance, the clearance for production of drive mechanism for TAPP-3 and 4 has been given to Nuclear Power Corporation of India Ltd. (NPCIL). The design drawings have been issued to NPCIL for production of mechanisms for reactor use. Design of this mechanism is significantly different from the mechanisms used in Dhruva, Kamini and 220 MWe pressurized heavy water reactors (PHWR). The paper describes the salient design features and the results of testing of shut-off rod drive mechanism carried out on full-scale test station at DRHR, BARC

Main propulsion system design recommendations for an advanced Orbit Transfer Vehicle

Science.gov (United States)

Redd, L.

1985-01-01

Various main propulsion system configurations of an advanced OTV are evaluated with respect to the probability of nonindependent failures, i.e., engine failures that disable the entire main propulsion system. Analysis of the life-cycle cost (LCC) indicates that LCC is sensitive to the main propulsion system reliability, vehicle dry weight, and propellant cost; it is relatively insensitive to the number of missions/overhaul, failures per mission, and EVA and IVA cost. In conclusion, two or three engines are recommended in view of their highest reliability, minimum life-cycle cost, and fail operational/fail safe capability.

Use of diffusion bonded SS-Al composite material in the development of neutron detectors

International Nuclear Information System (INIS)

Alex, Mary; Prasad, K.R.; Pappachan, A.L.; Grover, A.K.; Krishnan, J.; Derose, D.J.; Bhanumurthy, K.; Kale, G.B.

2005-01-01

The present paper describes the development of a SS-Al composite plate in-house at BARC by diffusion bonding technique. Details of the several tests carried out on the composite material and the use of the plate in the development of a boron lined neutron chamber for Dhruva reactor control instrumentation has been described. The bonded sample has withstood tensile strength test, leak test and thermal cycling test and the leak rate was observed to be less than 3 x 10 -10 stdcc/sec. The chamber with the composite material has been installed in Dhruva Basket C location and connected to the log rate safety channel. It has been working successfully for the past two years. The use of SS-Al composite material has improved the reliability and long-term performance of the detector. (author)

46 CFR 108.419 - Fire main capacity.

Science.gov (United States)

2010-10-01

... COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) A-MOBILE OFFSHORE DRILLING UNITS DESIGN AND EQUIPMENT Fire Extinguishing Systems Fire Main System § 108.419 Fire main capacity. The diameter of the fire... pumps operating simultaneously. ...

Function analysis and function assignment of NPP advanced main control room

International Nuclear Information System (INIS)

Zheng Mingguang; Xu Jijun

2001-01-01

The author addresses the requirements of function analysis and function assignment, which should be carried out in the design of main control room in nuclear power plant according to the design research of advanced main control room, then states its contents, functions, importance and necessity as well as how to implement these requirements and how to do design verification and validation in the design of advanced main control room of nuclear power plant

Design and su pply of main control rooms for nuclear progra mme in China Tecnatom has played a significant

International Nuclear Information System (INIS)

Rejas, L.; Martinez, V.

2016-01-01

Tecnatom has played a significant role in the challenging energy development programme in China, which expects to increase the production of nuclear energy in 150 GWe in 2030. Tecnatom scope of work consisted of the design and supply of 10 main control rooms for Fuqing 1-4, Fangjiashan 1-2, Hainan 1-2 and Yangjiang 5-6 nuclear power plants. These projects have reinforced Tecnatom capabilities on human factors engineering, operation environments design, equipment qualification, fabrication, testing and installation among others, in an international and complex environment, with very tight schedules, achieving very successful results. (Author)

Design and su pply of main control rooms for nuclear progra mme in China Tecnatom has played a significant

Energy Technology Data Exchange (ETDEWEB)

Rejas, L.; Martinez, V.

2016-07-01

Tecnatom has played a significant role in the challenging energy development programme in China, which expects to increase the production of nuclear energy in 150 GWe in 2030. Tecnatom scope of work consisted of the design and supply of 10 main control rooms for Fuqing 1-4, Fangjiashan 1-2, Hainan 1-2 and Yangjiang 5-6 nuclear power plants. These projects have reinforced Tecnatom capabilities on human factors engineering, operation environments design, equipment qualification, fabrication, testing and installation among others, in an international and complex environment, with very tight schedules, achieving very successful results. (Author)

Nitrogen chronology of massive main sequence stars

NARCIS (Netherlands)

Köhler, K.; Borzyszkowski, M.; Brott, I.; Langer, N.; de Koter, A.

2012-01-01

Context. Rotational mixing in massive main sequence stars is predicted to monotonically increase their surface nitrogen abundance with time. Aims. We use this effect to design a method for constraining the age and the inclination angle of massive main sequence stars, given their observed luminosity,

Design features and operation experience of the main circulating pumps for the ''Loviisa'' NPP with the WWER-440 reactor

International Nuclear Information System (INIS)

Iofs, D.; Kujyala, I.; Timperi, I.; Shlejfer, G.; Vistbakka, V.; Prudovskij, A.M.; Turetskij, L.I.; Vorona, P.N.

1980-01-01

Technical characteristics and the operation of main circulating pumps (MCP) designed and mounted at the ''Loviisa'' NPP by Finnish firms ''Alstrem'' and ''Stremberg'' are described. The above MCP have specific advantages over similar pumps mounted at other NPP with pressurized water cooled reactors. This is a possibility of substitution of potentially most damaged units (bearing and pump shaft sealing) for several hours, without MCP disassembly as a whole as well as using rolling bearings together with the original electromagnetic unloading system from the axial force instead of usually employed in similar MCP radial thrust slip bearings. The two year operation experience has confirmed the efficiency and reliability of ''Loviisa'' NPP main circulating pumps

ANS main control complex three-dimensional computer model development

International Nuclear Information System (INIS)

Cleaves, J.E.; Fletcher, W.M.

1993-01-01

A three-dimensional (3-D) computer model of the Advanced Neutron Source (ANS) main control complex is being developed. The main control complex includes the main control room, the technical support center, the materials irradiation control room, computer equipment rooms, communications equipment rooms, cable-spreading rooms, and some support offices and breakroom facilities. The model will be used to provide facility designers and operations personnel with capabilities for fit-up/interference analysis, visual ''walk-throughs'' for optimizing maintain-ability, and human factors and operability analyses. It will be used to determine performance design characteristics, to generate construction drawings, and to integrate control room layout, equipment mounting, grounding equipment, electrical cabling, and utility services into ANS building designs. This paper describes the development of the initial phase of the 3-D computer model for the ANS main control complex and plans for its development and use

Magnetic structure of molecular magnet Fe[Fe(CN)6]·4H2O

Indian Academy of Sciences (India)

perature disordered (paramagnetic) to an ordered magnetic phase transition at 22.6 K. ... three-dimensional network of straight Fe3+–C≡N–Fe3+ chains along the edges of the ... powder diffractometer (λ = 1.249 Å) at Dhruva reactor, Trombay.

Validated design of the ITER main vacuum pumping systems

International Nuclear Information System (INIS)

Day, Chr.; Antipenkov, A.; Dremel, M.; Haas, H.; Hauer, V.; Mack, A.; Boissin, J.-C.; Class, G.; Murdoch, D.K.; Wykes, M.

2005-01-01

Forschungszentrum Karlsruhe is developing the ITER high vacuum cryogenic pumping systems (torus, cryostat, NBI) as well as the corresponding mechanical roughing pump trains. All force-cooled big cryopumps incorporate similar design of charcoal coated cryopanels cooled to 5 K with supercritical helium. A model of the torus exhaust cryopump was comprehensively characterised in the TIMO testbed at Forschungszentrum. This paper discusses the vacuum performance results of the model pump and outlines how these data were incorporated in a sound design of the whole ITER torus exhaust pumping system. To do this, the dedicated software package ITERVAC was developed which is able to describe gas flow in viscous, transitional and molecular flow regimes as needed for the gas coming through the divertor slots and along the pump ducts into the cryopumps. The entrance section between the divertor cassettes and each pumping duct was identified to be the bottleneck of the gas flow. The interrelation of achievable throughputs as a function of the divertor pressure and the cryopump pumping speed is discussed. The system design is completed by assessment of the NBI cryopump system and integrating performance curves for the roughing pump trains needed during the regeneration phases of the cryopumps. (author)

Welded joints engineering design of the primary circuit, surge line and main steam piping of the Angra 2 reactor

International Nuclear Information System (INIS)

Volta, Angelo Roberto; Couto, Jose Gonzalo Villaverde

1995-01-01

The erection of nuclear systems of a Nuclear Power Station is under international requests, that results in a detailed elaboration of documents for the performance of welds. NUCLEN as an engineering design company, responsible for the erection of Angra 2, developed a suitable software program for the elaboration of welding procedure qualifications, tests and examination sequence plans and heat treatment plans applied to primary circuit, surgeline and main steam piping. The paper shows the employed methodology for the elaboration of these documents, as well as the requested engineering design of welding technology and testability in order to assure the stipulated quality level, according to requirements of the specifications, codes and norms. (author). 6 refs

Molecular dynamics using quasielastic neutron scattering

CERN Document Server

Mitra, S

2003-01-01

Quasielastic neutron scattering (QENS) technique is well suited to study the molecular motions (rotations and translations) in solids or liquids. It offers a unique possibility of analysing spatial dimensions of atomic or molecular processes in their development over time. We describe here some of the systems studied using the QENS spectrometer, designed, developed and commissioned at Dhruva reactor in Trombay. We have studied a variety of systems to investigate the molecular motion, for example, simple molecular solids, molecules adsorbed in confined medium like porous systems or zeolites, monolayer-protected nano-sized metal clusters, water in Portland cement as it cures with time, etc. (author)

Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Maine Yankee nuclear power plant

International Nuclear Information System (INIS)

Latorre, V.R.; Mayn, B.G.

1979-08-01

This report documents the technical evaluation of the electrical, instrumentation, and control design aspects for the low temperature overpressure protection system of the Maine Yankee nuclear power plant. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria

Challenges of the ILC Main Linac

International Nuclear Information System (INIS)

Ross, Marc

2007-01-01

With the completion of the ILC Reference Design Report (RDR), we begin the next phase of the project - development of the Engineering Design. Our strategy and priorities come from the identification, contained in the RDR, of scientific and engineering challenges of the ILC. First among these is the cost of the main linac which, including the associated earthworks and cooling/power systems, amounts to 60% of the ILC total cost. Next is the challenge to reach the highest practical gradient since this R and D has the largest cost leverage of any of the ongoing programs. Finally, we have to understand the beam dynamics and beam tuning processes in the main linac, as we will not have the opportunity to do full (or even large) scale tests of these before the linac is constructed.

Reliability assessment of shut-off rod drive mechanism for TAPP - 3 and 4 and critical facility through life cycle testing

International Nuclear Information System (INIS)

Singh, Manjit; Badodkar, D.N.; Singh, N.K.; Dalal, N.S.; Mishra, M.K.; Veda Vyas, G.; Kothari, C.B.; Rao, V.V.S.S.; Saraf, R.K.

2006-01-01

Shut-off rod drive mechanism forms a safety critical system of a nuclear reactor. It is the space constraints for the given reactor layout, which makes design of shut-off rod drive mechanism (SRDM) a custom built design. Design of SRDM adopts fail-safe, replaceability and the simplicity criterion ensuring very high reliability of its operation. Shut-off rod drive mechanism for TAPP-3 and 4 and 'Critical Facility' have been recently designed and developed at Division of Remote Handling and Robotics (DRHR), BARC. These are designed with a number of advanced features and these are significantly different than those used in Dhruva and 220 MWe PHWRs. Design of SRDM is qualified through proto typing and life cycle testing on a full-scale test set-up. This paper gives details of qualification and life cycle test data for prototype SRDM for TAPP-3 and 4 and 'Critical Facility' and reliability assessment. (author)

Structural mechanics research and development for main components of chinese 300 MWe PWR NPPs: from design to life management

International Nuclear Information System (INIS)

Yao Weida; Dou Yikang; Xie Yongcheng; He Yinbiao; Zhang Ming; Liang Xingyun

2005-01-01

Qinshan Nuclear Power Plant (Unit I), is a 300 MWe prototype PWR independently developed by Chinese own efforts, from design, manufacture, construction, installation, commissioning, to operation, inspection, maintenance, ageing management and lifetime assessment. Shanghai Nuclear Engineering Research and Design Institute (SNERDI) has taken up with and involved in deeply the R and D to tackle problems of this type of reactor since very beginning in early 1970s. Structural mechanics is one of the important aspects to ensure the safety and reliability for NPP components. This paper makes a summary on role of structural mechanics for component safety and reliability assessment in different stages of design, commissioning, operation, as well as lifetime assessment on this type PWR NPPs, including Qinshan-I and Chashma-I, a sister plant in Pakistan designed by SNERDI. The main contents of the paper cover design by analysis for key components of NSSS; mechanical problems relating to safety analysis; special problems relating to pressure retaining components, such as fracture mechanics, sealing analysis and its test verifications, etc.; experimental research on flow-induced vibration; seismic qualification for components; component failure diagnosis and root cause analysis; vibration qualification and diagnosis technique; component online monitoring technique; development of defect assessment; methodology of aging management and lifetime assessment for key components of NPPs, etc. (authors)

New Main Ring control system

International Nuclear Information System (INIS)

Seino, K.; Anderson, L.; Ducar, R.; Franck, A.; Gomilar, J.; Hendricks, B.; Smedinghoff, J.

1990-03-01

The Fermilab Main Ring control system has been operational for over sixteen years. Aging and obsolescence of the equipment make the maintenance difficult. Since the advent of the Tevatron, considerable upgrades have been made to the controls of all the Fermilab accelerators except the Main Ring. Modernization of the equipment and standardization of the hardware and software have thus become inevitable. The Tevatron CAMAC serial system has been chosen as a basic foundation in order to make the Main Ring control system compatible with the rest of the accelerator complex. New hardware pieces including intelligent CAMAC modules have been designed to satisfy unique requirements. Fiber optic cable and repeaters have been installed in order to accommodate new channel requirements onto the already saturated communication medium system. 8 refs., 2 figs

Development of triple axis neutron spectrometer (Paper No. 24)

International Nuclear Information System (INIS)

Pal, B.C.; Wadhwa, N.R.; Goveas, S.H.

1987-02-01

The triple axis neutron spectrometers are the basic instruments intended for use with neutron beams from reactors. Various types of spectrometers, each devoted to different kinds of measurement can be designed and manufactured, once a prototype having all the attributes of a versatile instrument is designed and developed. With the view to achieving self reliance in this field, Central Workshops of Bhabha Atomic Research Centre (BARC), Bombay designed and developed a prototype of triple axis spectrometer meeting the specifications prepared by Nuclear Physics Division of BARC . This spectrometer, with a moving wedge system was successfully manufactured and installed at 'DHRUVA'. Another version of this spectrometer, called the 'Polarised Neutron Spectrometer' was also built and exported to South Korea and installed at Korea Advanced Energy Research Institute, Seoul. This paper deals with basic concept, development of design, engineering of mechanical assemblies, the manufacturing approach and problems encountered during manufacture. (author). 3 figs

Design optimization of single-main-amplifier KrF laser-fusion systems

International Nuclear Information System (INIS)

Harris, D.B.; Pendergrass, J.H.

1985-01-01

KrF lasers appear to be a very promising laser fusion driver for commercial applications. The Large Amplifier Module for the Aurora Laser System at Los Alamos is the largest KrF laser in the world and is currently operating at 5 kJ with 10 to 15 kJ eventually expected. The next generation system is anticipated to be a single-main-amplifier system that generates approximately 100 kJ. This paper examines the cost and efficiency tradeoffs for a complete single-main-amplifier KrF laser fusion experimental facility. It has been found that a 7% efficient $310/joule complete laser-fusion system is possible by using large amplifier modules and high optical fluences

Development and application of intelligent CAE system for cyclotron main magnet

International Nuclear Information System (INIS)

Zhang Tianjue; Chen Yong; Fan Mingwu

1993-01-01

The main magnet that represents the feature of the cyclotron is the most important part in a cyclotron construction. Though there are many codes devoted to solve magnetic field computation problems, the results from them are depended on user's skill and experience very much. To help cyclotron magnet designer get acceptable result an intelligent CAE system for cyclotron main magnet design and machining has been developed. A reasonable good results in design could be get even the designer is a beginner with the help from an expert knowledge library installed in the program. The codes include following functions: 1. Intelligent CAD; 2. 2D and 3D magnetic field computation; 3. Beam dynamics analysis; 4. CAM for main magnet

Fermilab Main Injector plan

Energy Technology Data Exchange (ETDEWEB)

Anon.

1990-07-15

The Fermilab Main Injector is the centrepiece of the 'Fermilab III' scheme to significantly upgrade the Laboratory's existing accelerator complex. The new accelerator is designed to provide increased particle beam levels to boost the collision rate in the Tevatron proton-antiproton collider (luminosity in excess of 5 x 10{sup 31} per sq cm per s) and, if approved, would provide increased flexibility in all areas of high energy physics research.

Description of the Main Features of the Series Production of the LHC Main Dipole Magnets

CERN Document Server

Savary, F; Chevret, P; de Rijk, G; Fessia, P; Liénard, P; Miles, J; Modena, M; Rossi, L; Tommasini, D; Vlogaert, J; Bresson, D; Grunblatt, G; Decoene, JF; Bressani, F; Drago, G; Gagliardi, P; Eysselein, F; Gärtner, W; Lublow, P

2008-01-01

The series production of the LHC main dipole magnets was completed in November 2006. This paper presents the organization implemented at CERN and the milestones fixed to fullfil the technical requirements and to respect the master schedule of the machine installation. The CERN organization for the production follow-up, the quality assurance and the magnet testing, as well as the organization of the three main contractors will be described. A description of the design work and procurement of most of the specific heavy tooling and key components will be given with emphasis on the advantages and drawbacks.

Space transportation main engine reliability and safety

Science.gov (United States)

Monk, Jan C.

1991-01-01

Viewgraphs are used to illustrate the reliability engineering and aerospace safety of the Space Transportation Main Engine (STME). A technology developed is called Total Quality Management (TQM). The goal is to develop a robust design. Reducing process variability produces a product with improved reliability and safety. Some engine system design characteristics are identified which improves reliability.

In-service inspection robot for PFBR main vessel- concept

Energy Technology Data Exchange (ETDEWEB)

Rajendran, S; Ramakumar, M S [Bhabha Atomic Research Centre, Mumbai (India). Div. of Remote Handling and Robotics

1994-12-31

In-service inspection (ISI) of critical components in a nuclear reactor is one of the foremost and important tasks which reveals the state of health of the system, thereby ensuring the safety of the plant, personnel and environment. Prototype Fast Breeder Reactor (PFBR) is designed as a pool type reactor. A safety vessel is provided in the design which envelopes the main reactor vessel. The ISI of the main vessel is mandatory and will be carried out by a robot which will operate on this annular gap. The design of the robot is such that it can crawl around the vessel and into the gap at the bottom of the vessel relying on friction grip. The mobile robot will carry a CCTV camera and the inspection technique packages into the interspace, position and orient these to carry out the ISI of the main vessel. The paper discusses about the design features of the robot including the gripping mechanism and the crawling sequence to perform ISI of the reactor vessel. 3 figs.

In-service inspection robot for PFBR main vessel- concept

International Nuclear Information System (INIS)

Rajendran, S.; Ramakumar, M.S.

1994-01-01

In-service inspection (ISI) of critical components in a nuclear reactor is one of the foremost and important tasks which reveals the state of health of the system, thereby ensuring the safety of the plant, personnel and environment. Prototype Fast Breeder Reactor (PFBR) is designed as a pool type reactor. A safety vessel is provided in the design which envelopes the main reactor vessel. The ISI of the main vessel is mandatory and will be carried out by a robot which will operate on this annular gap. The design of the robot is such that it can crawl around the vessel and into the gap at the bottom of the vessel relying on friction grip. The mobile robot will carry a CCTV camera and the inspection technique packages into the interspace, position and orient these to carry out the ISI of the main vessel. The paper discusses about the design features of the robot including the gripping mechanism and the crawling sequence to perform ISI of the reactor vessel. 3 figs

The main chemical safety problems in main process of nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Song Fengli; Zhao Shangui; Liu Xinhua; Zhang Chunlong; Lu Dan; Liu Yuntao; Yang Xiaowei; Wang Shijun

2014-01-01

There are many chemical reactions in the aqueous process of nuclear fuel reprocessing. The reaction conditions and the products are different so that the chemical safety problems are different. In the paper the chemical reactions in the aqueous process of nuclear fuel reprocessing are described and the main chemical safety problems are analyzed. The reference is offered to the design and accident analysis of the nuclear fuel reprocessing plant. (authors)

Conceptual design main progress of EAST Articulated Maintenance Arm (EAMA) system

Energy Technology Data Exchange (ETDEWEB)

Shi, Shanshuang, E-mail: shiss@ipp.ac.cn [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031 (China); Laboratory of Intelligent Machines, Lappeenranta University of Technology (Finland); Song, Yuntao; Cheng, Yong [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031 (China); Villedieu, Eric; Bruno, Vincent [CEA-IRFM, F-13108 Saint-Paul-Lez-Durance (France); Feng, Hansheng [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031 (China); Wu, Huapeng [Laboratory of Intelligent Machines, Lappeenranta University of Technology (Finland); Wang, Peng [State Key Laboratory of Solid Lubrication, Lanzhou Institute of Chemical Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Hao, Zhiwei; Li, Yang; Wang, Kun; Pan, Hongtao [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031 (China)

2016-03-15

Highlights: • EAST Articulated Maintenance Arm (EAMA) system is being collaboratively developed by ASIPP and CEA-IRFM. • Conceptual design for a 3-DOF wrist end effector with gripper has been finished. • Kinematic design can reach 90% of the workspace inside EAST tokamak vessel. • A prototype of EAMA arm segment has been built to validate the design. - Abstract: EAST articulated maintenance arm (EAMA) system is being collaboratively developed by ASIPP and CEA-IRFM for the purpose of remote inspection and simple maintenance operations in EAST vacuum vessel during physical experiments without breaking the ultra-high vacuum condition. The EAMA system design is based on a similar articulated inspection arm robot successfully demonstrated in Tore Supra in 2008. In order to better meet EAST configurations and maintenance requirements, optimized mechanisms and dimensions are considered for EAMA robot as upgrades. Besides, the segmented arm is equipped with a 3-DOF wrist end effector and gripper for gripping operation as well as inspection. Some calculations and simulations on statics, kinematics and workspace of EAMA have been presented to validate the feasibility. This paper introduces the overall design of the EAMA robot and presents implementation progress.

Conceptual design main progress of EAST Articulated Maintenance Arm (EAMA) system

International Nuclear Information System (INIS)

Shi, Shanshuang; Song, Yuntao; Cheng, Yong; Villedieu, Eric; Bruno, Vincent; Feng, Hansheng; Wu, Huapeng; Wang, Peng; Hao, Zhiwei; Li, Yang; Wang, Kun; Pan, Hongtao

2016-01-01

Highlights: • EAST Articulated Maintenance Arm (EAMA) system is being collaboratively developed by ASIPP and CEA-IRFM. • Conceptual design for a 3-DOF wrist end effector with gripper has been finished. • Kinematic design can reach 90% of the workspace inside EAST tokamak vessel. • A prototype of EAMA arm segment has been built to validate the design. - Abstract: EAST articulated maintenance arm (EAMA) system is being collaboratively developed by ASIPP and CEA-IRFM for the purpose of remote inspection and simple maintenance operations in EAST vacuum vessel during physical experiments without breaking the ultra-high vacuum condition. The EAMA system design is based on a similar articulated inspection arm robot successfully demonstrated in Tore Supra in 2008. In order to better meet EAST configurations and maintenance requirements, optimized mechanisms and dimensions are considered for EAMA robot as upgrades. Besides, the segmented arm is equipped with a 3-DOF wrist end effector and gripper for gripping operation as well as inspection. Some calculations and simulations on statics, kinematics and workspace of EAMA have been presented to validate the feasibility. This paper introduces the overall design of the EAMA robot and presents implementation progress.

Fermilab Main Injector plan

International Nuclear Information System (INIS)

Anon.

1990-01-01

The Fermilab Main Injector is the centrepiece of the 'Fermilab III' scheme to significantly upgrade the Laboratory's existing accelerator complex. The new accelerator is designed to provide increased particle beam levels to boost the collision rate in the Tevatron proton-antiproton collider (luminosity in excess of 5 x 10 31 per sq cm per s) and, if approved, would provide increased flexibility in all areas of high energy physics research

Cost-efficient and storm surge-sensitive bridge design for coastal Maine.

Science.gov (United States)

2013-08-01

Climatic variation felt through changing weather patterns is having increasingly acute effects on Maines : transportation infrastructure. Acute risk occurs as a result of events, such as storms and flooding, while chronic risk : surrounds longer r...

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

Design and construction of electrostatic separators for TRISTAN Main Ring

International Nuclear Information System (INIS)

Shintake, Tsumoru; Suetsugu, Yusuke; Mori, Kenji; Sato, Masayuki; Higo, Toshiyasu.

1989-03-01

Sixteen electrostatic separators have been installed in TRISTAN Main Ring for separating the electron and positron beams. The maximum designed voltage is 240 kV across a gap of 8 cm between 4.6 or 3.2 m long titanium electrodes. Special care was taken to secure the passage of the wall current produced by the passing bunched beam and also to reduce irradiation of the synchrotron radiation onto the ceramic parts, so that no H.V. breakdown will occur. Even if one of them breaks down, it will result in total beam loss. In order to make the H.V. sparking rate as low as possible, the chemical cleaning process was studied carefully. The process was focused on removing the contamination such as machining oil, sander emery on the metal surfaces. The field distributions were studied by the computer simulation code DENKAI, and the shapes of the electrodes and ceramics were optimized, taking into account the limit of Kilpatrick Criterion. Every one of the H.V.-bushings and ceramic supports were tested by applying H.V. up to 150 kV, and assembled into the chamber in a clean room. The power of the parasitic mode was pulled out through the H.V.-bushing and damped by ferrite microwave absorbers inside the shield box. It was estimated that the maximum power of the electrode heating is less than 25 W and temperature rise is less than 50degC. With this much temperature rise, no significant deterioration of vacuum pressure is expected. The direct electrode cooling became unnecessary, and the structure of the separator became very simple. The separators showed excellent H.V. properties, i.e., no H.V. spark was observed over two days for 16 separators at 240 kV without the beams circulating the ring. With the beams of 9 mA, neither beam loss nor sparks were observed at the separation voltage of 200 kV. The vacuum pressure rose by only twice as high as the base pressure. The rise was not much different from that of the neighborhood, and enough for the beam operation. (author)

New schools design: Acoustics as main target

Science.gov (United States)

Maffei, Luigi; Lembo, Paola

2005-04-01

The effects of poor intelligibility and high background noise levels on the cognitive development of school children and on the dissatisfaction of teachers has been largely investigated. National standards have been implemented and attempts to harmonize these standards in international guidelines are ongoing. All these activities have led to the awareness that design of new schools must be centered on the achievement of a good acoustic environment. At this point a strong research effort to study and implement best solutions must be conducted, in collaboration, by architects, acousticians, pedagogues, psychologists, builders and acoustic materials producers. Recently an international competition for the planning of new primary schools in Rome, Italy has been announced. The aim of the competition is to study new architectural and running features of primary schools to obtain, among other parameters such as lighting, low cost energy solutions and air quality, the control of reverberation time, sound insulation and mechanical equipments noise. In these school buildings, as innovative requirement, children must be also able to elaborate interpretative hypothesis of physical phenomena such as sound emission and perception and be aware of their influence on these phenomena. Different possible solutions are presented.

Study on Manufacturing Process of Hollow Main Shaft by Open Die Forging

International Nuclear Information System (INIS)

Kwon, Yong Chul; Kang, Jong Hun; Kim, Sang Sik

2016-01-01

The main shaft is one of the key components connecting the rotor hub and gear box of a wind power generator. Typically, main shafts are manufactured by open die forging method. However, the main shaft for large MW class wind generators is designed to be hollow in order to reduce the weight. Additionally, the main shafts are manufactured by a casting process. This study aims to develop a manufacturing process for hollow main shafts by the open die forging method. The design of a forging process for a solid main shaft and hollow shaft was prepared by an open die forging process design scheme. Finite element analyses were performed to obtain the flow stress by a hot compression test at different temperature and strain rates. The control parameters of each forging process, such as temperature and effective strain, were obtained and compared to predict the suitability of the hollow main shaft forging process. Finally, high productivity reflecting material utilization ratio, internal quality, shape, and dimension was verified by the prototypes manufactured by the proposed forging process for hollow main shafts

Study on Manufacturing Process of Hollow Main Shaft by Open Die Forging

Energy Technology Data Exchange (ETDEWEB)

Kwon, Yong Chul [Gyeongnam Technopark, Changwon (Korea, Republic of); Kang, Jong Hun [Jungwon Univ., Goisan (Korea, Republic of); Kim, Sang Sik [Gyeongsang Natiional Univ., Jinju (Korea, Republic of)

2016-02-15

The main shaft is one of the key components connecting the rotor hub and gear box of a wind power generator. Typically, main shafts are manufactured by open die forging method. However, the main shaft for large MW class wind generators is designed to be hollow in order to reduce the weight. Additionally, the main shafts are manufactured by a casting process. This study aims to develop a manufacturing process for hollow main shafts by the open die forging method. The design of a forging process for a solid main shaft and hollow shaft was prepared by an open die forging process design scheme. Finite element analyses were performed to obtain the flow stress by a hot compression test at different temperature and strain rates. The control parameters of each forging process, such as temperature and effective strain, were obtained and compared to predict the suitability of the hollow main shaft forging process. Finally, high productivity reflecting material utilization ratio, internal quality, shape, and dimension was verified by the prototypes manufactured by the proposed forging process for hollow main shafts.

Guide to the Main Ring DO overpass

International Nuclear Information System (INIS)

Turkot, F.

1985-01-01

The DO overpass is a modification of the beam orbit in Main Ring in order to better accommodate a Tevatron collider detector at DO. The orbit is moved up approx. 51 inches over most of the long straight section at DO, thus making the Main Ring the world's first non-planar proton synchrotron. A similar overpass, but with four times the displacement, is planned for the CDF detector at the BO straight section. The nominal separation between the beam orbit in the Main Ring and the orbit in the Tevatron is 25.5 inches. Early in the design study of a detector that would utilize the Tevatron is a anti pp collider, it was apparent that a larger separation at the detector was highly desirable. In 1981, Tom Collins proposed a specific lattice geometry in the Main Ring for achieving larger separation, called ''the screw beam''. His proposal has served as the basis for the design of both the BO and DO overpasses. The main purpose of this report is to describe in some detail the implementation of the DO overpass. Topics to be covered include: (a) geometry of the overpass orbit, (b) the new hardware in the tunnel, (c) the power supply system, (d) the control facility, (e) accelerator beam dynamics ramifications, and (f) commissioning experience. A secondary purpose is to provide a fairly complete ''bibliography'' to the sources of information on the overpass. 17 refs., 17 figs

Rotational dynamics of propylene inside Na-Y zeolite cages

Indian Academy of Sciences (India)

We report here the quasielastic neutron scattering (QENS) studies on the dynamics of propylene inside Na-Y zeolite using triple axis spectrometer (TAS) at Dhruva reactor, Trombay. Molecular dynamics (MD) simulations performed on the system had shown that the rotational motion involves energy larger than that involved ...

Load Asymmetry Observed During Orion Main Parachute Inflation

Science.gov (United States)

Morris, Aaron L.; Taylor, Thomas; Olson, Leah

2011-01-01

The Crew Exploration Vehicle Parachute Assembly System (CPAS) has flight tested the first two generations of the Orion parachute program. Three of the second generation tests instrumented the dispersion bridles of the Main parachute with a Tension Measuring System. The goal of this load measurement was to better understand load asymmetry during the inflation process of a cluster of Main parachutes. The CPAS Main parachutes exhibit inflations that are much less symmetric than current parachute literature and design guides would indicate. This paper will examine loads data gathered on three cluster tests, quantify the degree of asymmetry observed, and contrast the results with published design guides. Additionally, the measured loads data will be correlated with videos of the parachute inflation to make inferences about the shape of the parachute and the relative load asymmetry. The goal of this inquiry and test program is to open a dialogue regarding asymmetrical parachute inflation load factors.

Alarm system for ABWR main control panels

Energy Technology Data Exchange (ETDEWEB)

Kobayashi, Yuji; Saito, Koji [Toshiba Corp., Yokohoma (Japan)

1997-09-01

TOSHIBA has developed integrated digital control and instrumentation system for ABWR, which is the third-generation man machine interface system for main control room that we call A-PODIA (Advanced PODIA). A-Podia has been introduced the first actual ABWR plant in Japan. in A-PODIA, TOSHIBA has realized improvement of alarm system that all operator crews in the control room can recognize plant anomalies easily. The alarm system can recognize essential alarms for plant safety easily and understand annunciators with each integrated annunciators and their prioritized color easily by classifying alarms into plant-level essential annunciators, system-level integrated annunciators and equipment level individual annunciators with hierarchical structure. This paper describes conventional alarm system and the design philosophy, alarm system design and operation of ``Alarm System for ABWR Main Control Panels``. (author). 5 refs, 8 figs, 1 tab.

Alarm system for ABWR main control panels

International Nuclear Information System (INIS)

Kobayashi, Yuji; Saito, Koji

1997-01-01

TOSHIBA has developed integrated digital control and instrumentation system for ABWR, which is the third-generation man machine interface system for main control room that we call A-PODIA (Advanced PODIA). A-Podia has been introduced the first actual ABWR plant in Japan. in A-PODIA, TOSHIBA has realized improvement of alarm system that all operator crews in the control room can recognize plant anomalies easily. The alarm system can recognize essential alarms for plant safety easily and understand annunciators with each integrated annunciators and their prioritized color easily by classifying alarms into plant-level essential annunciators, system-level integrated annunciators and equipment level individual annunciators with hierarchical structure. This paper describes conventional alarm system and the design philosophy, alarm system design and operation of ''Alarm System for ABWR Main Control Panels''. (author). 5 refs, 8 figs, 1 tab

A transitionless lattice for the Fermilab Main Injector

International Nuclear Information System (INIS)

Ng, K.Y.; Trbojevic, D.; Lee, S.Y.

1991-05-01

Medium energy (1 to 30 GeV) accelerators are often confronted with transition crossing during acceleration. A lattice without transition is presented, which is a design for the Fermilab Main Injector. The main properties of this lattice are that the γ t is an imaginary number, the maxima of the dispersion function are small, and two long-straight section with zero dispersion. 7 refs., 5 figs

Approach to the E-ELT dome and main structure challenges

Science.gov (United States)

Bilbao, Armando; Murga, Gaizka; Gómez, Celia; Llarena, Javier

2014-07-01

The E-ELT as a whole could be classified as an extremely challenging project. More precisely, it should be defined as an array of many different sub-challenges, which comprise technical, logistical and managerial matters. This paper reviews some of these critical challenges, in particular those related to the Dome and the Main Structure, suggesting ways to face them in the most pragmatic way possible. Technical challenges for the Dome and the Main Structure are mainly related to the need to upscale current design standards to an order of magnitude larger design. Trying a direct design escalation is not feasible; it would not work. A design effort is needed to cross hybridize current design standards with technologies coming from other different applications. Innovative design is therefore not a wish but a must. And innovative design comes along with design risk. Design risk needs to be tackled from two angles: on the one hand through thorough design validation analysis and on the other hand through extensive pre-assembly and testing. And, once again, full scale integrated pre-assembly and testing of extremely large subsystems is not always possible. Therefore, defining a comprehensive test plan for critical components, critical subsystems and critical subassemblies becomes essential. Logistical challenges are linked to the erection site. Cerro Armazones is a remote site and this needs to be considered when evaluating transport and erection requirements. But it is not only the remoteness of the site that needs to be considered. The size of both Dome and Main Structure require large construction cranes and a well defined erection plan taking into account pre-assembly strategies, limited plan area utilization, erection sequence, erection stability during intermediate stages and, very specifically, efficient coordination between the Dome and the Main Structure erection processes. Managerial issues pose another set of challenges in this project. Both the size of the

National facility for neutron beam research

Indian Academy of Sciences (India)

In this talk, the growth of neutron beam research (NBR) in India over the past five decades is traced beginning with research at Apsara. A range of problems in condensed matter physics could be studied at CIRUS, followed by sophisticated indegenous instrumentation and research at Dhruva. The talk ends with an overview ...

TRIGA reactor main systems

International Nuclear Information System (INIS)

Boeck, H.; Villa, M.

2007-01-01

This module describes the main systems of low power (<2 MW) and higher power (≥2 MW) TRIGA reactors. The most significant difference between the two is that forced reactor cooling and an emergency core cooling system are generally required for the higher power TRIGA reactors. However, those TRIGA reactors that are designed to be operated above 3 MW also use a TRIGA fuel that is specifically designed for those higher power outputs (3 to 14 MW). Typical values are given for the respective systems although each TRIGA facility will have unique characteristics that may only be determined by the experienced facility operators. Due to the inherent wide scope of these research reactor facilities construction and missions, this training module covers those systems found at most operating TRIGA reactor facilities but may also discuss non-standard equipment that was found to be operationally useful although not necessarily required. (author)

ONKALO - Main drawings in 2007

International Nuclear Information System (INIS)

2008-05-01

The first overall site characterisation programme for a Finnish repository of spent nuclear fuel was introduced in 1982. This programme already suggested that the site confirmation for a detailed repository design and safety assessment should include characterisation performed in an underground rock characterisation facility (URCF). This idea was confirmed during the detailed site characterisation. International views have also emphasised the importance of underground characterisation before the final decision to construct the repository is taken. The underground rock characterisation facility (ONKALO) is excavated at Olkiluoto in the municipality of Eurajoki. ONKALO should be constructed to allow characterisation work for site confirmation without jeopardising long-term safety of the repository site. It should also be possible to link ONKALO later to the repository as to a part of it. The construction of ONKALO was started in 2004 and will be completed in 2014. The characterisation work has started in ONKALO and will focus on the disposal depth. In the main drawings stage, ONKALO was described at the level of detail needed for a construction permit in 2003. This meant description of the location, final structures and final systems. This summary report describes the development of design to updated main drawings in 2007 at the same level of detail (no temporary arrangements are described). The main changes are the added exhaust air shaft and advancing the controlled area's inlet air shaft to the ONKALO phase. Also the layout and the depth of the characterisation levels have been updated according to the current bedrock information. Some buildings on the surface will house sets of equipment directly connected with underground facility and this equipment is described in this report. No buildings or other equipment are described in this report, because they are not directly connected with the underground facility. The main element of ONKALO is a system of

The advanced main control console for next japanese PWR plants

International Nuclear Information System (INIS)

Tsuchiya, A.; Ito, K.; Yokoyama, M.

2001-01-01

The purpose of the improvement of main control room designing in a nuclear power plant is to reduce operators' workload and potential human errors by offering a better working environment where operators can maximize their abilities. In order to satisfy such requirements, the design of main control board applied to Japanese Pressurized Water Reactor (PWR) type nuclear power plant has been continuously modified and improved. the Japanese Pressurized Water Reactor (PWR) Utilities (Electric Power Companies) and Mitsubishi Group have developed an advanced main control board (console) reflecting on the study of human factors, as well as using a state of the art electronics technology. In this report, we would like to introduce the configuration and features of the Advanced Main Control Console for the practical application to the next generation PWR type nuclear power plants including TOMARI No.3 Unit of Hokkaido Electric Power Co., Inc. (author)

30 CFR 75.310 - Installation of main mine fans.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Installation of main mine fans. 75.310 Section... mine fans. (a) Each main mine fan shall be— (1) Installed on the surface in an incombustible housing... that gives a signal at the mine when the fan either slows or stops. A responsible person designated by...

Further improvement of human-machine interface for ABWR main control room

International Nuclear Information System (INIS)

Makino, S.

2001-01-01

Tokyo Electric Power Company (TEPCO) has developed main control room panels based on progress in C and I technology. ABWR type main control room panels (ABWR MCR PNLs) are categorized as third generation type domestic BWR MCR, that is, they are were developed step by step based on operating experience with the first and the second generation BWR. ABWR type main control room panels were applied to Kashiwazaki-Kariwa Nuclear Power Station Units Number 6 and 7 (K-6/7) for the first time. K-6/7 are the first advanced BWR (ABWR), which started commercial operation in November 1996 and July 1997, respectively. The concept of ABWR MCR design was verified through wooden mock-up panels, start-up tests and commercial operation. Though the K-6/7 design has borne fruit, we are planning to refine and standardize the design based on the following concepts: to maintain the plant operation and monitoring style of ABWR MCR PNLs; to introduce brand-new HMI technology and devices; to incorporate operators' advice in the design. This paper outlines the features and improvements of the K6/7 MCR PNLs design. (author)

Designing a reverse osmosis desalination plant, main parameters and compounds; Diseno de una planta desilinizadora de osmosis inversa, parametros y componentes principales

Energy Technology Data Exchange (ETDEWEB)

Arango Mesa, H. [Universidad del Valle. Cali. Colombia (Colombia); Gomez Gotor, A. [Universidad de las Palmas de Gran Canaria (Spain)

1998-12-31

This paper comments on some of the design features which should be taken into account in planning a reverse osmosis sea water desalination plant. It also examine the components of some of the plant`s main units, such as the high pressure pumping unit and energy recovering system and the types of membrane modules and their use. Finally, it compares that most common commercially available products. (Author) 6 refs.

Small-angle neutron scattering studies of nonionic surfactant: Effect ...

Indian Academy of Sciences (India)

celle above a concentration called critical micelle concentration (CMC) where their properties are different from those of the ... It is well-known that SANS is an ideal technique to study the micellar structure of surfactants [8,9] and this has also ... ment at the Dhruva reactor, Mumbai [11]. The mean wavelength of the incident.

Journal of Earth System Science | Indian Academy of Sciences

Indian Academy of Sciences (India)

Home; Journals; Journal of Earth System Science; Volume 125; Issue 1. Prediction and error growth in the daily forecast of precipitation from the NCEP CFSv2 over the subdivisions of Indian subcontinent. Dhruva Kumar Pandey Shailendra Rai A K Sahai S Abhilash N K Shahi. Volume 125 Issue 1 February 2016 pp 29-45 ...

The BTeV main spectrometer

International Nuclear Information System (INIS)

Sheldon, P.D.

2001-01-01

BTeV is a second generation B-factory experiment that will use a double-arm, forward spectrometer in the C0 experimental hall at the Fermilab Tevatron. I will describe the motivation and design of the 'main spectrometer', consisting of a ring-imaging Cherenkov system for charged particle identification, an electromagnetic calorimeter of lead-tungstate crystals, a proportional tube muon system with magnetized filtering steel, and a straw-tube and silicon strip charged particle tracking system

Main gas circulator for VG-400 reactor plant

International Nuclear Information System (INIS)

Mitenkov, F.M.; Kostin, V.I.; Novinskij, E.G.; Kuropatov, A.I.; Protsenko, A.N.; Smirnov, V.P.; Stolyarevskij, A.Ya.

1988-01-01

Principle parameters and operating conditions of the main gas circulator (MGC) in VG-400 reactor plant are presented. Brief MGC design description and experimental work scope are given. (author). 4 refs, 4 figs, 1 tab

Space Shuttle main engine product improvement

Science.gov (United States)

Lucci, A. D.; Klatt, F. P.

1985-01-01

The current design of the Space Shuttle Main Engine has passed 11 certification cycles, amassed approximately a quarter million seconds of engine test time in 1200 tests and successfully launched the Space Shuttle 17 times of 51 engine launches through May 1985. Building on this extensive background, two development programs are underway at Rocketdyne to improve the flow of hot gas through the powerhead and evaluate the changes to increase the performance margins in the engine. These two programs, called Phase II+ and Technology Test Bed Precursor program are described. Phase II+ develops a two-tube hot-gas manifold that improves the component environment. The Precursor program will evaluate a larger throat main combustion chamber, conduct combustion stability testing of a baffleless main injector, fabricate an experimental weld-free heat exchanger tube, fabricate and test a high pressure oxidizer turbopump with an improved inlet, and develop and test methods for reducing temperature transients at start and shutdown.

Main aspects of the design of a support structure of a LMFBR with particular reference to the explosive accident consequences

International Nuclear Information System (INIS)

Giuliano, V.; Lazzeri, L.

1977-01-01

The aim of this paper is a review of the main aspects of the design of a support structure of a LMFBR tank, with particular reference to the analysis of the non-linear dynamic behaviour of the structure in the plastic range under the effect of an explosive accident within the tank. The structure is composed by a L-shaped flange, which supports the tank, connected by means of nine square beams to a rigid box-type ring, fixed to the concrete. The plug of the tank is connected to the L-shaped figure by means of a group of SS bars. The non-linear dynamic analysis of the explosive accident has been carried out on a lumped mass model, with elastic-plastic elements which simulate main components of the support structure and tank. The impulsive load connected to the explosive accident has been modelled (on the basis of extensive comparative studies carried out) as two triangular pressure impulses acting on the plug and on the botton of the tank. A large amount of results, which describe displacements, velocities and accelerations of the plug, of the tank, and of the support structure, together with the forces and stresses acting on the main structural components are presented and discussed, with particular reference to the influence of the various parameters involved in the analysis. (Auth.)

Pelamis WEC - main body structural design and materials selection

Energy Technology Data Exchange (ETDEWEB)

Anderson, C.

2003-07-01

This report summarises the results of a study evaluating the potential use of rolled steel, glass reinforced plastic, wood-epoxy laminate, and different forms of concrete as primary structural materials for the Pelamis Wave Energy Converter (WEC) as part of a strategy to refine the design by highlighting cost savings for long-term manufacture. Details are given of the drawing up of a load spectrum in order to assess the candidate structures, the choice of glass reinforced plastic, concrete, and steel for further evaluation based on preliminary screening, the assessment of the material requirements for each candidate structure, and cost estimates. The advantages of the use of concrete are discussed and recommendations are presented.

Temperature effects on the structure of liquid D-methanol through ...

Indian Academy of Sciences (India)

Here, the liquid consists of deuterated methanol and neutron data was collected on the high- diffractometer at Dhruva, BARC. The corrected data at elevated temperatures (BP (boiling point) and double the BP) show that there is a large change in the H-bonded structure of this liquid. The pre-peak or hump, known to be ...

Air and gas pockets in sewerage pressure mains.

Science.gov (United States)

Lubbers, C L; Clemens, F

2005-01-01

In The Netherlands, wastewater is collected in municipal areas and transported to large centralised WWTPs by means of an extensive system of pressure mains. Over the past decades these pressure mains did not receive much attention in terms of monitoring of performance or maintenance. For that reason, in practice their state of functioning is often not known. Failure of operation is only noticed when the capacity of the system proves to be insufficient to fulfil the minimum design capacity demand. A recent inventory showed that half of the pressure mains show an increased pressure loss for no directly obvious reason. Many causes may account for the reduction of the system's nominal capacity like an increased wall roughness, scaling or occurrence of free gas in the pipeline. The occurrence of free gas may be caused by degassing of dissolved (bio) gas or by air entrained at the pumps' inlet or at air valves. A research study is started that will focus on three main issues: The description of the gas-water phenomena in wastewater pressure mains with respect to transportation and dynamic hydraulic behaviour, A method to diagnose gas problems, and To overcome future problems by either applying remedial measures or improving the design of wastewater pressure systems. For this study, two experimental facilities are constructed, a small circuit for the study of multi-phase flow and a second, larger one for the research into diagnostic methods. This paper describes the preliminary results of the experiments in the multi-phase circuit.

Design study for superconducting main field coils for the Oak Ridge Isochronous Cyclotron

International Nuclear Information System (INIS)

Schwenterly, S.W.; Litherland, P.S.; Ballou, J.K.

1981-01-01

The design study described here demonstrated the feasibility of replacing the existing ORIC coils with superconducting magnets. The design is quite conservative, requires no unusual technology, and should result in a coil system with good reliability and durability. The operating regime of ORIC will be considerably extended, and running costs should be reduced. A proposal to continue with detailed design and coil fabrication is currently under review and has been submitted to the Nuclear Science Advisory Committee

Evaluation of the Main Steam Line Break Accident for the APR+ Standard Design using MARS-KS

Energy Technology Data Exchange (ETDEWEB)

Park, M. H.; Kim, Y. S.; Hwang, Min Jeong; Sim, S. K. [Environment Energy Technology, Daejeon (Korea, Republic of); Bang, Young Seok [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-05-15

As a part of licensing evaluation of the APR+ (Advanced Power Reactor +) standard design, Korea Institute of Nuclear Safety(KINS) performed safety evaluation of the APR+ Standard Safety Analysis Report(SSAR). The results of the safety evaluation of the APR+ Main Steam Line Break(MSLB) accident is presented for the most limiting post-trip return-to-power case with the single failure assumption of the Loss Of Offsite Power(LOOP). MARS-KS regulatory safety analysis code has been used to evaluate safety as well as the system behavior during MSLB accident. The MARS-KS analysis results are compared with the results of the MSLB safety analysis presented in the SSAR of the APR+. Independent safety evaluation has been performed using MARS-KS regulatory safety analysis code for the APR+ MSLB accident inside containment for the limiting case of the full power post-trip return-to-power. The results of MARS-KS analysis were compared with the results of the MSLB safety analysis presented in the APR+ SSAR. Due to higher cooldown of the MARS-KS analysis, the MARS-KS analysis results in a higher positive reactivity insertion into the core by the negative moderator and fuel temperature reactivity coefficients than the APR+ SSAR analysis. Both results show no return-to-power during the limiting case of the MSLB inside containment. However, APR+ SSAR moderator temperature reactivity insertion should be evaluated against the MARS-KS moderator density reactivity insertion for is conservatism. This study also clearly shows asymmetric thermal hydraulic behavior during the MSLB accident at intact and affected sides of the downcomer and the core. These asymmetric phenomena should be further investigated for the effects on the system design.

Study on the task categorization of main control room in NPP

International Nuclear Information System (INIS)

Fang Zhou; Ma Zhicai; Ma Xusheng; Zheng Mingguang

2005-01-01

The paper states the importance and trendy requirements of Main Control Room (MCR) in nuclear power plant and introduces how to implement the human factor engineering principle in the design of advanced main control room. It mainly focuses on the purpose and functions, strategy and methodology, scope and contents of the MCR task categorization. The preliminary MCR task categorization is performed according to these principles. (authors)

Progress on a prototype main ring rf cavity

International Nuclear Information System (INIS)

Swain, G.; Kandarian, R.; Thiessen, H.A.; Poirier, R.; Smythe, W.R.

1989-01-01

A prototype rf cavity and rf drive system for a hadron facility main ring has been designed and will be tested in the Proton Storage Ring (PSR) at Los Alamos as a part of a collaborative effort between LANL and TRIUMF. The cavity uses an orthogonally biased ferrite tuner. The design provides for accelerating gap voltages up to 200 kV for the 49.3 to 50.8 MHz range. Progress on the cavity construction and testing is described. 13 refs., 5 figs

The Design Lab: Re-thinking What to Design and How to Design

DEFF Research Database (Denmark)

Brandt, Eva; Johansson, Martin; Messeter, Jörn

2005-01-01

. In our view there seems to be a growing divide between mainly North American contributions to IT design emphasing new information technology concepts such as ubiquitous computing, tangible interaction and augmented reality, and mainly European contributions emphasizing the role of particular information......Over the last decades there has been a dramatic change in the design agenda within the field of IT design. With the increase of mobile and wireless devices and the massive expansion of Internet availability the classical object of design - the dedicated information system targeted towards a well...... technology applications in the light of in-depth studies of the potential contexts of use....

Designing high energy accelerators under DOE's 'New Culture' for environment and safety: An example, the Fermilab 150 GeV Main Injector proton synchrotron

International Nuclear Information System (INIS)

Fowler, W.B.

1991-01-01

Fermilab has initiated a design for a new Main Injector (150 GeV proton synchrotron) to take the place of the current Main Ring accelerator. 'New Culture' environmental and safety questions are having to be addressed. The paper details the necessary steps that have to be taken in order to obtain the permits which control the start of construction. Obviously these depend on site-specific circumstances, however some steps are universally applicable. In the example, floodplains and wetlands are affected and therefore the National Environmental Policy Act (NEPA) compliance is a significant issue. The important feature is to reduce the relevant regulations to a concise set of easily understandable requirements. The effort required and the associated time line are presented so that other new accelerator proposals can benefit from the experience gained from this example

Design of production process main shaft process with lean manufacturing to improve productivity

Science.gov (United States)

Siregar, I.; Nasution, A. A.; Andayani, U.; Anizar; Syahputri, K.

2018-02-01

This object research is one of manufacturing companies that produce oil palm machinery parts. In the production process there is delay in the completion of the Main shaft order. Delays in the completion of the order indicate the low productivity of the company in terms of resource utilization. This study aimed to obtain a draft improvement of production processes that can improve productivity by identifying and eliminating activities that do not add value (non-value added activity). One approach that can be used to reduce and eliminate non-value added activity is Lean Manufacturing. This study focuses on the identification of non-value added activity with value stream mapping analysis tools, while the elimination of non-value added activity is done with tools 5 whys and implementation of pull demand system. Based on the research known that non-value added activity on the production process of the main shaft is 9,509.51 minutes of total lead time 10,804.59 minutes. This shows the level of efficiency (Process Cycle Efficiency) in the production process of the main shaft is still very low by 11.89%. Estimation results of improvement showed a decrease in total lead time became 4,355.08 minutes and greater process cycle efficiency that is equal to 29.73%, which indicates that the process was nearing the concept of lean production.

Integration of test modules in the main blanket and vacuum vessel design

International Nuclear Information System (INIS)

Nakahira, Masataka; Kurasawa, Toshimasa; Sato, Satoshi; Furuya, Kazuyuki; Togami, Ikuhide; Hashimoto, Toshiyuki; Takatsu, Hideyuki; Kuroda, Toshimasa.

1995-07-01

Typical test modules for water-cooled and helium-cooled ceramic breeder blankets have been designed, and their major design parameters are summarized. Among various candidates studied in Japan at present, BOT (Breeder Out of Tube) type of blanket is exemplified here. The integration scheme of the test module into ITER basic machine is also shown. Even with other type of blanket, the integration scheme won't be affected. The composition and space requirement of cooling and tritium recovery systems for the test module have also been studied. (author)

Validation study on reliability analysis of main safety system in Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Cho, Nam Jin; Cho, Chang Keun; Kim, Yong Hui; Kim, Tae Hyeong; Hong, Seo Kee; Park, Keon Woo; Park, Chang Jea [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Cheong, Woo Sik [Institute for Advanced Engineering, Yongin (Korea, Republic of); Park, Moon Kyu [KEPRI, Taejon (Korea, Republic of)

1993-12-15

The scope and contents of this validation study are to review the design changes of the four main safety systems in Wolsong 2/3/4 Nuclear Power Plants, to review the consideration of the above design changes in the AECL reports, the structure of fault trees, and the data base used in the quantification of the fault trees, to quantify the unavailabilities of main safety systems and check them if they meet the requirements, and to recommend desirable design changes in the emergency core cooling system to reduce the unavailability.

Development of Pneumatic Transport System (PTS) for safe handling of uranium oxide powder in UMP/UED

International Nuclear Information System (INIS)

Manna, S.; Satpati, S.K.; Roy, S.B.

2009-01-01

Tonnage quantity radioactive uranium oxide powder of particle size sub micron to 100 micron is handled in Uranium Metal Plant (UMP), UED/BARC for production of nuclear grade uranium metal, required for fuelling research reactors - Dhruva and Cirus. A Pneumatic Transfer System (PTS) using vacuum has been introduced and is being used for handling radioactive powder to improve radiation protection

Main principles of development stationary training facilities

International Nuclear Information System (INIS)

Tsiptsyura, R.D.

1986-01-01

The designation of stationary training facilities is shown and the main requirements for them are formulated. When considering the above-mentioned requirements, special attention was paid to obligatory correspondence between training experience and practical skill of an operator. It is shown, that the switchboard block is the major unit of the training facility, which should develop skills and habits of an operator

Dark current and radiation shielding studies for the ILC main linac

Energy Technology Data Exchange (ETDEWEB)

Mokhov, Nikolai V. [Fermilab; Rakhno, I. L. [Fermilab; Solyak, N. A. [Fermilab; Sukhanov, A. [Fermilab; Tropin, I. S. [Fermilab

2016-12-05

Electrons of dark current (DC), generated in high-gradient superconducting RF cavities (SRF) due to field emission, can be accelerated up to very high energies—19 GeV in the case of the International Linear Collider (ILC) main linac—before they are removed by focusing and steering magnets. Electromagnetic and hadron showers generated by such electrons can represent a significant radiation threat to the linac equipment and personnel. In our study, an operational scenario is analysed which is believed can be considered as the worst case scenario for the main linac regarding the DC contribution to the radiation environment in the main linac tunnel. A detailed modelling is performed for the DC electrons which are emitted from the surface of the SRF cavities and can be repeatedly accelerated in the high-gradient fields in many SRF cavities. Results of MARS15 Monte Carlo calculations, performed for the current main linac tunnel design, reveal that the prompt dose design level of 25 μSv/hr in the service tunnel can be provided by a 2.3-m thick concrete wall between the main and service ls.

PRISMA database machine: A distributed, main-memory approach

NARCIS (Netherlands)

Schmidt, J.W.; Apers, Peter M.G.; Ceri, S.; Kersten, Martin L.; Oerlemans, Hans C.M.; Missikoff, M.

1988-01-01

The PRISMA project is a large-scale research effort in the design and implementation of a highly parallel machine for data and knowledge processing. The PRISMA database machine is a distributed, main-memory database management system implemented in an object-oriented language that runs on top of a

Main aspects of the design of a support structure of a LMFBR with particular reference to the explosive accident consequences

International Nuclear Information System (INIS)

Giuliano, V.; Lazzeri, L.

1977-01-01

The aim of this paper is a review of the main aspects of the design of a support structure of a LMFBR tank, with particular reference to the analysis of the non-linear dynamic behavior of the structure in the plastic range under the effect of an explosive accident within the tank. The structure is composed by a L-shaped flange, which supports the tank, connected by means of nine square beams to a rigid box-type ring, fixed to the concrete. The plug of the tank is connected to the L-shaped flange by means of a group of SS bars. The non-linear dynamic analysis of the explosive accident has been carried out on a lumped mass model, with elastic-plastic elements which simulate main components of the support structure and tank. The impulsive load connected to the explosive accident has been modelled (on the basis of extensive comparative studies carried out) as two triangular pressure impulses has been the object of a parametric evaluation. The dynamic transient on the support structure during and after the explosive accident for each couple of pressure impulses has been analyzed by means of modified version of the NON SAP code running on a CDC 7600 computer. A large amount of results, which describe displacements, velocities and accelerations of the plug, of the tank, and of the support structure, together with the forces and stresses acting on the main structural components are presented and discussed, with particular reference to the influence of the various parameters involved in the analysis

Design of an inspection robot for small diameter gas distribution mains

NARCIS (Netherlands)

Dertien, Edwin Christian

2014-01-01

The gas distribution network in the Netherlands has a length of roughly 100.000 km in urban areas. This network needs to be monitored constantly and segments need to be replaced when the risks of leaks increase. Since no information can be obtained from inse the network, in this thesis the design of

Designing high energy accelerators under DOE's ''New Culture'' for environment and safety: An example, the Fermilab 150 GeV Main Injector proton synchrotron

International Nuclear Information System (INIS)

Fowler, W.B.

1991-05-01

Fermilab has initiated a design for a new Main Injector (150 GeV proton synchrotron) to take the place of the current Main Ring accelerator. ''New Culture'' environmental and safety questions are having to be addressed. The paper will detail the necessary steps that have to be taken in order to obtain the permits which control the start of construction. Obviously these depend on site-specific circumstances, however some steps are universally applicable. In the example, floodplains and wetlands are affected and therefore the National Environmental Policy Act (NEPA) compliance is a significant issue. The important feature is to reduce the relevant regulations to a concise set of easily understandable requirements. The effort required and the associated time line will be presented so that other new accelerator proposals can benefit from the experience gained from this example

Main-chain supramolecular block copolymers.

Science.gov (United States)

Yang, Si Kyung; Ambade, Ashootosh V; Weck, Marcus

2011-01-01

Block copolymers are key building blocks for a variety of applications ranging from electronic devices to drug delivery. The material properties of block copolymers can be tuned and potentially improved by introducing noncovalent interactions in place of covalent linkages between polymeric blocks resulting in the formation of supramolecular block copolymers. Such materials combine the microphase separation behavior inherent to block copolymers with the responsiveness of supramolecular materials thereby affording dynamic and reversible materials. This tutorial review covers recent advances in main-chain supramolecular block copolymers and describes the design principles, synthetic approaches, advantages, and potential applications.

Update on reactors and reactor instruments in Asia

Science.gov (United States)

Rao, K. R.

1991-10-01

The 1980s have seen the commissioning of several medium flux (∼10 14 neutrons/cm 2s) research reactors in Asia. The reactors are based on indigenous design and development in India and China. At Dhruva reactor (India), a variety of neutron spectrometers have been established that have provided useful data related to the structure of high- Tc materials, phonon density of states, magnetic moment distributions and micellar aggregation during the last couple of years. Polarised neutron analysis, neutron interferometry and neutron spin echo methods are some of the new techniques under development. The spectrometers and associated automaton, detectors and neutron guides have all been indigenously developed. This paper summarises the developments and on-going activities in Bangladesh, China, India, Indonesia, Korea, Malaysia, the Philippines and Thailand.

Update on reactors and reactor instruments in Asia

International Nuclear Information System (INIS)

Rao, K.R.

1991-01-01

The 1980s have seen the commissioning of several medium flux (∝10 14 neutrons/cm 2 s) research reactors in Asia. The reactors are based on indigenous design and development in India and China. At Dhruva reactor (India), a variety of neutron spectrometers have been established that have provided useful data related to the structure of high-Tc materials, phonon density of states, magnetic moment distributions and micellar aggregation during the last couple of years. Polarised neutron analysis, neutron interferometry and neutron spin echo methods are some of the new techniques under development. The spectrometers and associated automaton, detectors and neutron guides have all been indigenously developed. This paper summarises the developments and on-going activities in Bangladesh, China, India, Indonesia, Korea, Malaysia, the Philippines and Thailand. (orig.)

ANALYSIS AND SIMULATION OF MAIN MAGNET TRANSMISSION LINE EFFECT

Energy Technology Data Exchange (ETDEWEB)

ZHANG,W.; MARNERIS, I.; SANDBERG, J.

2007-06-25

A main magnet chain forms a pair of transmission lines. Pulse-reflection-caused voltage and current differentiation throughout the magnet chain can have adverse effect on main magnet field quality. This effect is associated with magnet system configuration, coupling efficiency, and parasitic parameters. A better understanding of this phenomenon will help us in new design and existing system upgrade. In this paper, we exam the transmission line effect due to different input functions as well as configuration, coupling, and other parameters.

Money and Design

Directory of Open Access Journals (Sweden)

Artur Borcuch

2015-01-01

Full Text Available The purpose of this article is to analyze the influence of the money design on willingness to make purchases. In this paper, we focus on three aspects that structure the relation between money and design: the link between design and finance (in general, determinants of design and perspective of currency design. The main research problem explored in this paper is: Does the money design have influence on the willingness to make purchases by employees/employers at design studios, design students and students of economics/management? The main hypothesis is as follows – the more experience in design practice, the more important is money design.

Radioisotope applications in industry and environment: Indian scenario

International Nuclear Information System (INIS)

Pant, H.J.

2016-01-01

Applications of radioisotopes and radiation technology in industry, medicine and agriculture form an important part of India's programme of using nuclear technology for societal benefits. Radioisotope production in India started on a modest scale soon after 1 MW APSARA reactor at Trombay, Mumbai became critical in 1956. The scope of activities expanded thereafter. With the commissioning of 40 MW CIRUS reactor in 1960, the setting up of modern radioisotope processing laboratories in late sixties and the production of cobalt-60 in power reactors in megacurie quantities in late seventies made India self-sufficient in radioisotope production. The radioisotope production received a major boost in 1985 with the commissioning of high flux 100 MW DHRUVA reactor, which provided opportunity to extend the range of radioisotopes available in the country both in quantity as well in specific activity. The CIRUS reactor has been shutdown in year 2010 and 1 MW APSARA reactor is presently being upgraded to 5 MW. Today, The DHRUVA reactor operating at its full capacity is being used for production of 100 different radioisotopes those are used in industry, agriculture and medicine. (author)

Emittance and trajectory control in the main linacs of the NLC

International Nuclear Information System (INIS)

Assmann, R.; Adolphsen, C.; Bane, K.; Raubenheimer, T.O.; Thompson, K.

1996-09-01

The main linacs of the next generation of linear colliders need to accelerate the particle beams to energies of up to 750 GeV while maintaining very small emittances. This paper describes the main mechanisms of static emittance growth in the main linacs of the Next Linear Collider (NLC). The authors present detailed simulations of the trajectory and emittance control algorithms that are foreseen for the NLC. They show that the emittance growth in the main linacs can be corrected down to about 110%. That number is significantly better than required for the NLC design luminosity

Dynamic imperfections and optimized feedback design in the Compact Linear Collider main linac

CERN Document Server

Eliasson, Peder

2008-01-01

The Compact Linear Collider (CLIC) main linac is sensitive to dynamic imperfections such as element jitter, injected beam jitter, and ground motion. These effects cause emittance growth that, in case of ground motion, has to be counteracted by a trajectory feedback system. The feedback system itself will, due to jitter effects and imperfect beam position monitors (BPMs), indirectly cause emittance growth. Fast and accurate simulations of both the direct and indirect effects are desirable, but due to the many elements of the CLIC main linac, simulations may become very time consuming. In this paper, an efficient way of simulating linear (or nearly linear) dynamic effects is described. The method is also shown to facilitate the analytic determination of emittance growth caused by the different dynamic imperfections while using a trajectory feedback system. Emittance growth expressions are derived for quadrupole, accelerating structure, and beam jitter, for ground motion, and for noise in the feedback BPMs. Fina...

Association of Cytokine Candidate Genes with Severity of Pain and Co-Occurring Symptoms in Breast Cancer Patients Receiving Chemotherapy

Science.gov (United States)

2014-12-01

chemotherapy administration (i.e., acute symptoms). 3 Keywords Pain, fatigue, sleep disturbance, depressive symptoms, symptom cluster, breast cancer, gene ...across a greater number of cytokine genes were evaluated than initially proposed (See Table 2 below for genes evaluated). 5 DNA samples were...Cooper, B. A., Dhruva, A., et al. (2012). Evidence of associations between cytokine genes and subjective reports of sleep disturbance in oncology

Instrumentation for PSD-based neutron diffractometers at Dhruva ...

Indian Academy of Sciences (India)

These include three diffractometers with multiple PSDs and four with single ... causes ionization in the gas, the charge is collected at both ends of the wire and .... terface required for data acquisition, control, presentation and system setup. The.

Improvement of main control room

International Nuclear Information System (INIS)

Chae, Sung Ki; Ham, Chang Sik; Kwon, Ki Chun

1991-07-01

Information display system, advanced alarm system and fiber optical communication system were developed to improve the main control room in nuclear power plant. Establishing the new hierachical information structure of plant operation data, plant overview status board(POSB) and digital indicator(DI) were designed and manufactured. The prototype advanced alarm system which employed the new alarm logics and algorithm compared with the conventional alarm system were developed and its effectiveness was proved. Optical communication system which has multi-drop feature and capability of upgrading to large-scale system by using BITBUS communication protocol which is proven technology, were developed. Reliability of that system was enhanced by using distributed control. (Author)

Main Ring bunch spreaders: Past, 1987/1988 fixed target run, and proposed future

International Nuclear Information System (INIS)

Jackson, G.P.

1989-01-01

During the last 1987--1988 fixed target running period beam intensity was limited many times by coherent instabilities in both the Main Ring and in the Tevatron. The intensity thresholds for instabilities are generally inversely proportional to the proton bunch length. Since fixed target operations are insensitive to the longitudinal phase space emittance of the beam, bunch spreaders are employed to increase this emittance, and hence the bunch length. As a result, more beam intensity can be delivered to the fixed target experiments. This paper starts with a short history behind the old Main Ring bunch spreader. After discussing the physics of stimulated emittance growth, the design and performance of the 1987--1988 fixed target run Main Ring bunch spreader is discussed. Finally, designs of improved Main Ring and Tevatron bunch spreaders for the next fixed target run are proposed. 23 figs

Operation Aspect of the Main Control Room of NPP

International Nuclear Information System (INIS)

Sahala M Lumbanraja

2009-01-01

The main control room of Nuclear Power Plant (NPP) is operational centre to control all of the operation activity of NPP. NPP must be operated carefully and safely. Many aspect that contributed to operation of NPP, such as man power whose operated, technology type used, ergonomic of main control room, operational management, etc. The disturbances of communication in control room must be anticipated so the high availability of NPP can be achieved. The ergonomic of the NPP control room that will be used in Indonesia must be designed suitable to anthropometric of Indonesia society. (author)

Additively Manufactured Main Fuel Valve Housing

Science.gov (United States)

Eddleman, David; Richard, Jim

2015-01-01

Selective Laser Melting (SLM) was utilized to fabricate a liquid hydrogen valve housing typical of those found in rocket engines and main propulsion systems. The SLM process allowed for a valve geometry that would be difficult, if not impossible to fabricate by traditional means. Several valve bodies were built by different SLM suppliers and assembled with valve internals. The assemblies were then tested with liquid nitrogen and operated as desired. One unit was also burst tested and sectioned for materials analysis. The design, test results, and planned testing are presented herein.

Studies on the seismic buckling design guideline of FBR main vessels. 9. Buckling evaluation under elastic-plastic seismic response

International Nuclear Information System (INIS)

Hagiwara, Yutaka; Yamamoto, Kohsuke; Kawamoto, Yoji; Nakagawa, Masaki; Akiyama, Hiroshi

1998-01-01

Plastic shear-bending buckling under seismic loadings is one of the major problems in the structural design of FBR main vessels. Pseudo-dynamic and dynamic buckling tests of cylinders were performed in order to study the effects of nonlinear seismic response on buckling strength, ductility, and plastic response reduction. The buckling strength formulae and the rule for ductility factors both derived from static tests were confirmed to be valid for the tests under dynamic loads. The displacement-constant rule for response reduction effect was modified by acceleration amplification factor in order to maintain applicability for various spectral profiles of seismic excitations. The response reduction estimated by the proposed rule was reasonably conservative for all cases of the pseudo-dynamic and the dynamic tests. Finally, a seismic safety assessment rule was proposed for plastic shear-bending buckling of cylinders, which include the proposed response reduction rule. (author)

Siberian snakes for the Fermilab Main Injector

International Nuclear Information System (INIS)

Anferov, V.A.; Baiod, R.; Courant, E.D.

1993-01-01

Appropriate Siberian snakes were designed to maintain the proton beam polarization during acceleration in the Fermilab Main Injector from 8 to 150 GeV. Various snake designs were investigated to find one fitting into the 14 m straight section spaces with the required spin rotation axis and the minimum orbit excursion. The authors studied both cold and warm discrete magnet snakes as well as warm snakes with helical magnets. For the warm discrete magnet snake, obtaining small orbit excursions required a nearly longitudinal snake axis, while axes near ±45 degrees are needed when using two snakes in a ring. The authors found acceptable snakes either by using superconducting magnets or by using warm magnets with a helical dipole field

CBA main magnet power supply ripple reduction

International Nuclear Information System (INIS)

Bagley, G.; Edwards, R.J.

1983-01-01

The preliminary results of a development program to minimize beam perturbation resulting from ripple current generated by the CBA Main Magnet Power Supply are presented. The assessment of the magnitude and causes of the ripple generated led to a modification of the SCR Gate Driver and the addition of a bandpass amplifier correction loop which gave significant improvement. A description of the changes made and the results obtained are included. A second design approach was developed in which the timing of the SCR gate pulses is directly determined by a VCO. The results reported with this VCO Loop indicate superior performance particularly at frequencies below 60 Hz. A shunt transistor regulator design is proposed to minimize higher SCR switching frequency harmonics

FOSTERING SUSTAINABILITY: DESIGNING A GREEN SCIENCE BUILDING AT A SMALL MAINE COLLEGE

Science.gov (United States)

The overarching goal of the project ‘as to develop a feasibility study of building design and construction that takes into account the various local conditions, optimizes energy savings. use of building materials, and long term sustainability of the structur...

Design Methodology - Design Synthesis

DEFF Research Database (Denmark)

Andreasen, Mogens Myrup

2003-01-01

Design Methodology is part of our practice and our knowledge about designing, and it has been strongly supported by the establishing and work of a design research community. The aim of this article is to broaden the reader¿s view of designing and Design Methodology. This is done by sketching...... the development of Design Methodology through time and sketching some important approaches and methods. The development is mainly forced by changing industrial condition, by the growth of IT support for designing, but also by the growth of insight into designing created by design researchers.......ABSTRACT Design Methodology shall be seen as our understanding of how to design; it is an early (emerging late 60ies) and original articulation of teachable and learnable methodics. The insight is based upon two sources: the nature of the designed artefacts and the nature of human designing. Today...

Design professional activity analysis in design management

Directory of Open Access Journals (Sweden)

Claudia de Souza Libanio

2013-08-01

Full Text Available Design use perception, as an essential element for achieving competitive advantage, also suggests the need to manage the design activities in companies. However, a few is discussed about the activity of these design professionals who participate in this process, their roles, functions and competencies, including  their connections to a company and other involved sectors. This article aims to analyze, during the design management processes, the work relations of design professionals connected to organizations both internal and externally, in order to comprehend the structure and intervenient factors on the activity of these professionals, as well as the interactions with their main coworkers. The methodology was exploratory and qualitative, using in-depth interviews with three design professionals. Subsequently, the responses were analyzed allowing the comparison of these obtained data to the theoretical bases researched. Through this case study, it was possible to realize the aspects and the structure of the design professional activity, connected intern and externally to organizations, as well as its relations with the main coworkers.

Optimization of the main control room habitability system in nuclear power plant

International Nuclear Information System (INIS)

Zheng Guanghui; Zhao Xinyan

2013-01-01

This article describes the optimization of main control room habitability system in nuclear power plant. It also describes the design shortage in terms of habitability in the main control room. Through modification and optimization, habitable conditions are met for personnel staying in the emergency area of the main control room for a period of time, with an aim to take accident intervention measures smoothly and reduce the accident loss and radioactive contamination as low as possible. (authors)

Main circulator design features for HTR 100, HTR 500 and space heating plants

International Nuclear Information System (INIS)

Engel, J.; Glass, D.

1988-01-01

All design alternatives for modern high-temperature reactors have a common circulator concept: It is based on a vertical shaft design with a flying impeller. The circulators are equipped with active magnetic bearings and are driven by induction motors connected to variable-speed static converters. Due to their multiple functions during normal reactor operation and under accident conditions, extremely high requirements are made to safety-relevant circulators, since with the reactor pressurized as well as under depressurized conditions specified delivery heads and flow rates have to be ensured. The use of active magnetic bearings permits to obtain maintenance-free operation and functional safety to an extent which had not been achieved before. Magnetic bearings are therefore provided for the total range including primary gas circulators of a drive power of several MW as well as circulators for helium loops of reactor auxiliary systems. The essential feature for using active magnetic bearings is the retainer bearing technology, preventing contact between rotor and static circulator parts upon unintended deenergisation of the magnets. Results of current experiments are reported. Another aspect to be considered for reliable long-term operation for several decades is the effect of rotor dynamics. The various natural frequencies resulting from torsion and bending modes in view of a drive by a frequency-controlled induction motor have to be considered as well as the specific characteristics of the active magnetic bearings. Special attention has to be directed to the internal cooling loop so as to ensure that reactor temperature excursions in the event of deviation from normal operation can be overcome without damage. For circulator components exposed to temperature fields the design characteristics are determined by combining experimental and analytical methods. The coordination of all component parts is currently being optimized on a prototype circulator whose detailed

Croatian repository construction project - present status and main obstacles

International Nuclear Information System (INIS)

Kucar Dragicevic, S.; Subasic, D.; Schaller, A.; Lokner, V.; Cerskov Klika, M.

1999-01-01

Croatia has been preparing backgrounds for the construction of the repository for low and intermediate radioactive waste on its territory, almost for a decade, now. In the name of Hrvtaska elektroprivreda, the co-owner of the NE Krsko, APO has been co-ordinating and organising numerous activities and projects during that time period. Siting process, safety assessment, disposal technology and repository design and public acceptance issues are the main fields of activities. The overall status of the project at the moment, including the overview of the present status of the main four aspects of activities, will be presented. Relatively, big and important progress made on the project work out during the last two years, as well as the main obstacles we were faced with during that time period, will be discussed.(author)

Designing Human Technologies

DEFF Research Database (Denmark)

Simonsen, Jesper

and the design process, in ethical and society-related concerns, and in evaluating how designs fulfill needs and solve problems. Designing Human Technologies subscribes to a broad technology concept including information and communication, mobile, environmental/sustainable and energy technologies......Design is increasingly becoming a part of the university curriculum and research agenda. The keynote present and discuss Designing Human Technologies – an initiative aiming at establishing a design oriented main subject area alongside traditional main subject areas such as Natural Science......, the Humanities, and Social Science. The initiative broadens the perspective of IS and recognize reflections on aesthetics, ethics, values, connections to politics, and strategies for enabling a better future as legitimate parts of the research agenda. Designing Human Technologies is a design-oriented Strategic...

Design and performance of the main amplifier system for the National Ignition Facility

International Nuclear Information System (INIS)

Beullier, J; Erlandson, A; Grebot, E; Guenet, J; Guenet, M; Horvath, J; Jancaitis, K; Larson, D; Lawson, J; LeTouze, G; Maille, X; Manes, K; Marshall, C; Mengue, T; Moor, E; Payne, S; Pedrotti, L; Rotter, M; Seznec, S; Sutton, S; Zapata, L.

1999-01-01

This paper describes the design and performance of flashlamp-pumped, Nd:glass. Brewster-angle slab amplifiers intended to be deployed in the National Ignition Facility (NIF). To verify performance, we tested a full-size, three-slab-long, NIF prototype amplifier, which we believe to be the largest flashlamp-pumped Nd:glass amplifier ever assembled. Like the NIF amplifier design, this prototype amplifier had eight 40-cm-square apertures combined in a four-aperture-high by two-aperture-wide matrix. Specially-shaped reflectors, anti-reflective coatings on the blastshields, and preionized flashlamps were used to increase storage efficiency. Cooling gas was flowed over the flashlamps to remove waste pump heat and to accelerate thermal wavefront recovery. The prototype gain results are consistent with model predictions and provide high confidence in the final engineering design of the NIF amplifiers. Although the dimensions, internal positions, and shapes of the components in the NIF amplifiers will be slightly different from the prototype, these differences are small and should produce only slight differences in amplifier performance

A damped and detuned accelerating structure for the main linacs of the compact linear collider

CERN Document Server

Khan, V

2011-01-01

Linear colliders are an option for lepton collision at several TeV. The Compact Linear Collider (CLIC) aims at electron and positron collisions at a centre of mass energy of 3 TeV. In CLIC, the main accelerating structures are designed to operate at an X-band frequency of 12 GHz with an accelerating gradient of 100 MV/m. Two significant issues in linear accelerators that can prevent high gradient being achieved are electrical breakdown and wakefields. The baseline design for the CLIC main linacs relies on a small aperture size to reduce the breakdown probability and a strong damping scheme to suppress the wakefields. The strong damping scheme may have a higher possibility of electrical breakdown. In this thesis an alternative design for the main accelerating structures of CLIC is studied and various aspects of this design are discussed. This design is known as a Damped and Detuned Structure (DDS) which relies on moderate damping and strong detuning of the higher order modes (HOMs). The broad idea of DDS is ba...

The collection of the main issues for wind farm optimisation in complex terrain

DEFF Research Database (Denmark)

Xu, Chang; Chen, Dandan; Han, Xingxing

2016-01-01

The paper aims at establishing the collection of the main issues for wind farm optimisation in complex terrain. To make wind farm cost effective, this paper briefly analyses the main factors influencing wind farm design in complex terrain and sets up a series of mathematical model that includes...... micro-siting, collector circuits, access roads design for optimization problems. The paper relies on the existing one year wind data in the wind farm area and uses genetic algorithm to optimize the micro-siting problem. After optimization of the turbine layout, single-source shortest path algorithm...

Separation and purification of 99Mo from uranium and fission products using Cintichem process, our experience

International Nuclear Information System (INIS)

Manolkar, R.B.; Mathakar, A.R.; Kumar, Yogendra; Kumar, Manoj; Dash, A.; Venkatesh, Meera; Pillai, K.T.; Singh, Sarbjit; Venugopal, V.

2009-01-01

A pilot study was carried out to assess the feasibility of producing 99 Mo by fission of Unat following the Cintichem method. U-Mo alloy was irradiated for one week at Dhruva reactor and processed for the separation of 99 Mo from fission products. The irradiated targets were chemically processed to separate and purify the 99 Mo. Recovery of ∼70% and the purity of 99 Mo was > 99%. (author)

Technology development for indigenous water lubricated bearings

International Nuclear Information System (INIS)

Limaye, P.K.; Soni, N.L.; Agrawal, R.G.

2010-01-01

Water Lubricated Bearings (WLB) are used in various mechanisms of fuel handling systems of PHWRs and AHWR. Availability and random failures of these bearings was a major factor in refuelling operations. Indigenous development of these bearings was taken up and 7 types of antifriction bearings in various sizes (totaling 37 variants) for PHWR, AHWR and Dhruva applications were successfully developed. This paper deals with various aspects of WLB development. (author)

75 FR 27863 - Savings Bank of Maine, MHC and Savings Bank of Maine, Gardiner, Maine; Approval of Conversion...

Science.gov (United States)

2010-05-18

... DEPARTMENT OF THE TREASURY Office of Thrift Supervision [AC-38: OTS Nos. 06947 and H 4709] Savings Bank of Maine, MHC and Savings Bank of Maine, Gardiner, Maine; Approval of Conversion Application Notice is hereby given that on May 7, 2010, the Office of Thrift Supervision approved the application of...

Theoretical study and design of a low-grade heat-driven pilot ejector refrigeration machine operating with butane and isobutane and intended for cooling of gas transported in a gas-main pipeline

KAUST Repository

Petrenko, V.O.

2011-11-01

This paper describes the construction and performance of a novel combined system intended for natural gas transportation and power production, and for cooling of gas transported in a gas-main pipeline. The proposed system includes a gas turbine compressor, a combined electrogenerating plant and an ejector refrigeration unit operating with a hydrocarbon refrigerant. The combined electrogenerating plant consists of a high-temperature steam-power cycle and a low-temperature hydrocarbon vapor power cycle, which together comprise a binary vapor system. The combined system is designed for the highest possible effectiveness of power generation and could find wide application in gas-transmission systems of gas-main pipelines. Application of the proposed system would enable year-round power generation and provide cooling of natural gas during periods of high ambient temperature operation. This paper presents the main results of a theoretical study and design performance specifications of a low-grade heat-driven pilot ejector refrigeration machine operating with butane and isobutane. © 2010 Elsevier Ltd and IIR. All rights reserved.

MK-III function tests in JOYO. Primary main cooling pump

International Nuclear Information System (INIS)

Isozaki, Kazunori; Saito, Takakazu; Sumino, Kouzo; Karube, Kouji; Terano, Toshihiro; Sakaba, Hideo; Nakai, Satoru

2004-06-01

MK-III function test (SKS-1) that was carried out from October 17, 2001 through October 23, 2001 using MK-III transition core configuration and MK-III function tests (SKS-2) was carried out from January 27, 2003 through February 13, 2003 using MK-III core configuration. The major function tests results of primary cooling system were shown as follows; (1) The stability of the primary main pump flow control system was confirmed on both CAS (cascade) mode and Man (manual) mode. Also no divergence of flow and revolution of the pump were observed at step flow change disturbance. (2) The main motor was shifted to run-back flow control operation in about 54 seconds after scram. The flow rate and pump revolution at run-back operation of A and B cooling system were 167 m 3 /h and 117 rpm, 185m 3 /h and 118 rpm respectively. The pump revolution was within the design target revolution 122 rpm ± 8 rpm and the flow was over the 10% of the rated flow. (3) The pony motor was engaged in operation in about 39 seconds after the primary main pump trip. The flow rate and pump revolution at the pony motor operation of A and B cooling system were 180 m 3 /h and 124 rpm, 190 m 3 /h and 123 rpm respectively. These values were satisfied the design low limit of 93 rpm and 10% of the rated flow. (4) Free flow coast down time constant was longer than 10 seconds that was design shortest time at both the primary pump trip and run-back operation. (5) Pump over flow column sodium levels of both A and B cooling system at rated operating condition were NL-1550 mm and, NL-1468 mm respectively and were lower than NL-1581 mm of the design value. This result shows the new IHX pressure loss estimation was conservative. (6) It was confirmed that the primary main pump could operate with out scram for up to 0.6 seconds of external power supply loss. (author)

Design, installation, and commissioning of the D0 overpass at the Fermilab main ring

International Nuclear Information System (INIS)

Gerig, R.; May, M.; Moore, C.; Ohnuma, S.; Pruss, S.; Turkot, F.

1985-06-01

In order to accommodate large detectors for anti pp studies at the Tevatron, the Main Ring has been modified to be non-planar. A 700 foot-long portion of the ring has been reworked to create an overpass which displaces the beam orbit upwards by 51 inches at the D0 long straight section. The overpass region follows the ''screw'' geometry proposed by T. Collins. A set of four vertically bending dipoles were inserted into the Main Ring lattice; they are powered on a separate bus and operate at twice the current and field level of a standard bend. To make space for these vertical bends, at each vertical bend point two of the four standard dipoles in a half-cell are removed and the other two are powered at twice the current and field level of the rest of the ring. The vertical bends also have a set of trim coils powered by a separate supply so that any difference in the horizontal and vertical bending strengths can be compensated. The D0 overpass was commissioned with beam in November-December 1984. The principal effect on beam dynamics - predicted and observed - is the introduction of momentum dispersion in the vertical dimension of peak value 1.9m. To preserve closed orbit quality during acceleration, the vertical bends must track the rest of the ring with a precision of better than 0.1%. The Main Ring-Tevatron complex has now been running the fixed-target program for four months; the impact of the D0 overpass on accelerator performance has been minimal

Main injector synchronous timing system

International Nuclear Information System (INIS)

Blokland, W.; Steimel, J.

1998-01-01

The Synchronous Timing System is designed to provide sub-nanosecond timing to instrumentation during the acceleration of particles in the Main Injector. Increased energy of the beam particles leads to a small but significant increase in speed, reducing the time it takes to complete a full turn of the ring by 61 nanoseconds (or more than 3 rf buckets). In contrast, the reference signal, used to trigger instrumentation and transmitted over a cable, has a constant group delay. This difference leads to a phase slip during the ramp and prevents instrumentation such as dampers from properly operating without additional measures. The Synchronous Timing System corrects for this phase slip as well as signal propagation time changes due to temperature variations. A module at the LLRF system uses a 1.2 Gbit/s G-Link chip to transmit the rf clock and digital data (e.g. the current frequency) over a single mode fiber around the ring. Fiber optic couplers at service buildings split off part of this signal for a local module which reconstructs a synchronous beam reference signal. This paper describes the background, design and expected performance of the Synchronous Timing System. copyright 1998 American Institute of Physics

Main injector synchronous timing system

International Nuclear Information System (INIS)

Blokland, Willem; Steimel, James

1998-01-01

The Synchronous Timing System is designed to provide sub-nanosecond timing to instrumentation during the acceleration of particles in the Main Injector. Increased energy of the beam particles leads to a small but significant increase in speed, reducing the time it takes to complete a full turn of the ring by 61 nanoseconds (or more than 3 rf buckets). In contrast, the reference signal, used to trigger instrumentation and transmitted over a cable, has a constant group delay. This difference leads to a phase slip during the ramp and prevents instrumentation such as dampers from properly operating without additional measures. The Synchronous Timing System corrects for this phase slip as well as signal propagation time changes due to temperature variations. A module at the LLRF system uses a 1.2 Gbit/s G-Link chip to transmit the rf clock and digital data (e.g. the current frequency) over a single mode fiber around the ring. Fiber optic couplers at service buildings split off part of this signal for a local module which reconstructs a synchronous beam reference signal. This paper describes the background, design and expected performance of the Synchronous Timing System

Main results of BN-600 reactor stress-strain state investigations

International Nuclear Information System (INIS)

Panov, V.A.

1983-01-01

The development of BN-600 fast reactor plant needed the solution of a series of complex engineering problems including ones for confirming integrity of the most vital structural components. The particular attention was given to the main vessel since reactor availability end safe operation of the plant as a whole depend on vessel strength end integrity. The present report deals with the main results of theoretical and experimental investigations of the stress-strain state of BN-600 reactor vessel carried out during design, start-up and initial bringing the reactor to power

Main unit electrical protection at Sizewell 'B' power station

International Nuclear Information System (INIS)

Fischer, A.; Keates, T.

1992-01-01

For any power station, reliable electrical protection of the main generating units (generators plus generator transformers) has important commercial implications. Spurious trips cause loss of generation and consequent loss of revenue, while failure to rapidly isolate a fault leads to unnecessary damage and again, loss of generation and revenue. While these conditions apply equally to Sizewell B there are additional factors to be taken into consideration. A spurious trip of a main generating unit may lead to a trip of the reactor with an associated challenge to the shutdown and core cooling plant. The generator transformers, besides exporting power from the generators to the 400 kV National Grid, also import power from the Grid to the 11 kV Main Electrical System, which in turn is the preferred source of supply to the Essential Electrical System. The Main Unit Protection is designed to clear generator faults leaving this off-site power route intact. Hence failure to operate correctly could affect the integrity of the Essential Electrical Supplies. (Author)

Genetic algorithm to optimize the design of main combustor and gas generator in liquid rocket engines

Science.gov (United States)

Son, Min; Ko, Sangho; Koo, Jaye

2014-06-01

A genetic algorithm was used to develop optimal design methods for the regenerative cooled combustor and fuel-rich gas generator of a liquid rocket engine. For the combustor design, a chemical equilibrium analysis was applied, and the profile was calculated using Rao's method. One-dimensional heat transfer was assumed along the profile, and cooling channels were designed. For the gas-generator design, non-equilibrium properties were derived from a counterflow analysis, and a vaporization model for the fuel droplet was adopted to calculate residence time. Finally, a genetic algorithm was adopted to optimize the designs. The combustor and gas generator were optimally designed for 30-tonf, 75-tonf, and 150-tonf engines. The optimized combustors demonstrated superior design characteristics when compared with previous non-optimized results. Wall temperatures at the nozzle throat were optimized to satisfy the requirement of 800 K, and specific impulses were maximized. In addition, the target turbine power and a burned-gas temperature of 1000 K were obtained from the optimized gas-generator design.

A Study on Large Display Panel Design for the Countermeasures against Team Errors within the Main Control Room of APR-1400

Energy Technology Data Exchange (ETDEWEB)

Kim, Sa Kil; Lee, Yong Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

The personal aspect of human errors has been mainly overcome by virtue of the education and training. However, in the system aspect, the education and training system needs to be reconsidered for more effective reduction of human errors affected from various systems hazards. Traditionally the education and training systems are mainly not focused on team skills such as communication, situational awareness, and coordination, etc. but individual knowledge, skill, and attitude. However, the team factor is one of the crucial issues to reduce the human errors in most industries. In this study, we identify the emerging types of team errors, especially, in digitalized control room of nuclear power plants such as the APR-1400 main control room. Most works in nuclear industry are to be performed by a team of more than two persons. Even though the individual errors can be detected and recovered by the qualified others and/or the well trained team, it is rather seldom that the errors by team could be easily detected and properly recovered by the team itself. Note that the team is defined as two or more people who are appropriately interacting with each other, and the team is a dependent aggregate, which accomplishes a valuable goal. Team error is one of the typical organizational errors that may occur during performing operations in nuclear power plants. The large display panel is a representative feature of digitalized control room. As a group-view display, the large display panel provides plant overview to the operators. However, in terms of team performance and team errors, the large display panel is on a discussion board still because the large display panel was designed just a concept of passive display. In this study, we will propose revised large display panel which is integrated with several alternative interfaces against feasible team errors.

A Study on Large Display Panel Design for the Countermeasures against Team Errors within the Main Control Room of APR-1400

International Nuclear Information System (INIS)

Kim, Sa Kil; Lee, Yong Hee

2015-01-01

The personal aspect of human errors has been mainly overcome by virtue of the education and training. However, in the system aspect, the education and training system needs to be reconsidered for more effective reduction of human errors affected from various systems hazards. Traditionally the education and training systems are mainly not focused on team skills such as communication, situational awareness, and coordination, etc. but individual knowledge, skill, and attitude. However, the team factor is one of the crucial issues to reduce the human errors in most industries. In this study, we identify the emerging types of team errors, especially, in digitalized control room of nuclear power plants such as the APR-1400 main control room. Most works in nuclear industry are to be performed by a team of more than two persons. Even though the individual errors can be detected and recovered by the qualified others and/or the well trained team, it is rather seldom that the errors by team could be easily detected and properly recovered by the team itself. Note that the team is defined as two or more people who are appropriately interacting with each other, and the team is a dependent aggregate, which accomplishes a valuable goal. Team error is one of the typical organizational errors that may occur during performing operations in nuclear power plants. The large display panel is a representative feature of digitalized control room. As a group-view display, the large display panel provides plant overview to the operators. However, in terms of team performance and team errors, the large display panel is on a discussion board still because the large display panel was designed just a concept of passive display. In this study, we will propose revised large display panel which is integrated with several alternative interfaces against feasible team errors

Crack widths in concrete with fibers and main reinforcement

DEFF Research Database (Denmark)

Christensen, Frede; Ulfkjær, Jens Peder; Brincker, Rune

2015-01-01

The main object of the research work presented in this paper is to establish design tools for concrete structures where main reinforcement is combined with addition of short discrete steel fibers. The work is concerned with calculating and measuring crack widths in structural elements subjected...... to bending load. Thus, the aim of the work is to enable engineers to calculate crack widths for flexural concrete members and analyze how different combinations of amounts of fibers and amounts of main reinforcement can meet a given maximum crack width requirement. A mathematical model including...... the ductility of the fiber reinforced concrete (FRC) is set up and experimental work is conducted in order to verify the crack width model. The ductility of the FRC is taken into account by using the stress crack width relation. The constitutive model for the FRC is based on the idea that the initial part...

Design Research as Conceptual Designing

DEFF Research Database (Denmark)

Ylirisku, Salu; Jacucci, Giulio; Sellen, Abigail

2015-01-01

define conceptual designing as a constructive framing and re-framing activity, which is mediated by and targeted at the creation of new design concepts. Conceptual designing as an approach is valuable for addressing the fuzziness and ambiguity typical of research that explores novel areas with new...... partners, methods and resources. It is by no means a new phenomenon, and the main contribution of the article is the clarification of conceptual designing as a particular approach to designing and researching. The approach embraces openness, resource-construction and collaboration. We conclude...... that conceptual designing can be especially useful in research and design projects that bring different kinds of people, organizations, technologies and domains together into the forming of new well-founded proposals for development. The presentation of conceptual designing in this paper is written...

Sense of place along a scenic byway in Maine

Science.gov (United States)

Marilynne Mann; Jessica Leahy

2008-01-01

Sense of place defines the value and meaning of location. The Rangeley Lakes area of Maine, an unusual natural environment with cultural and historic significance, was nationally recognized in 2000 by the designation of the Rangeley Lakes National Scenic Byway. A survey during the summer of 2006 sought to identify sense of place in the midst of tourism-related growth...

Study of an electromagnetic pump in a sodium cooled reactor. Design study of secondary sodium main pumps (Joint research)

International Nuclear Information System (INIS)

Chikazawa, Yoshitaka; Kisohara, Naoyuki; Hishida, Masahiko; Fujii, Tadashi; Konomura, Mamoru; Ara, Kuniaki; Hori, Toru; Uchida, Akihito; Nishiguchi, Youhei; Nibe, Nobuaki

2006-07-01

In the feasibility study on commercialized fast breeder cycle system, a medium scale sodium cooled reactor with 750 MW electricity has been designed. In this study, EMPs are applied to the secondary sodium main pump. The EMPs type is selected to be an annular linear induction pump (ALIP) type with double stators which is used in the 160 m 3 /min EMP demonstration test. The inner structure and electromagnetic features are decided reviewing the 160 m 3 /min EMP. Two dimensional electromagnetic fluid analyses by EAGLE code show that Rms (magnetic Reynolds number times slip) is evaluated to be 1.08 which is less than the stability limit 1.4 confirmed by the 160 m 3 /min EMP test, and the instability of the pump head is evaluated to be 3% of the normal operating pump head. Since the EMP stators are cooled by contacting coolant sodium duct, reliability of the inner structures are confirmed by temperature distribution and stator-duct contact pressure analyses. Besides, a power supply system, maintenance and repair feature and R and D plan of EMP are reported. (author)

Intelligent CAE system of CYCLONE type cyclotron main magnet and its applications

International Nuclear Information System (INIS)

Zhang Tianjue; Chen Yong; Fan Mingwu

1992-07-01

The main magnet that represents the feature of the cyclotron is the most important part in a cyclotron construction. Though there are many codes devoted to solve magnetic field computation problems, the results from them depend on the user's skill and experience very much. To help cyclotron magnet designer to get acceptable results, an intelligent CAE (computer aided engineering) system for CYCLONE type cyclotron magnet design and machining has been developed. A reasonable good results in the design could be got even if the designer is a beginner, because of the help from an expert knowledge library installed in the program

Fabrication and testing of main sodium pumps of Superphenix 1

International Nuclear Information System (INIS)

Noel, H.; Pasqualini, G.

1985-01-01

The complexity of the loads involved and the extremely fine analysis required necessitates extensive design calculations for the Superphenix 1 primary and secondary pumps and associated expansion tanks, aiming toward detailed design validation, after slight adjustments, mainly to the secondary pumps and expansion tanks. The component parts to be built were far larger than those for the previous pumps (Rapsodie, Phenix), with very low manufacturing tolerances, which led to precision machining and welding operations, together with numerous dimensional inspections and materials characterization tests to achieve the required quality standards

The main challenges for manufacturing companies in implementing and utilizing configurators

DEFF Research Database (Denmark)

Kristjansdottir, Katrin; Shafiee, Sara; Hvam, Lars

2018-01-01

Companies providing customized products increasingly apply configurators in supporting sales and design activities, thus improving lead-times, quality, cost, benefits perceived by customers, and customer satisfaction. While configurator advantages have been substantially investigated....... Finally, it is investigated whether the importance of the main categories of challenges varies according to a number of potential context variables. The results of the survey, which studies manufacturing companies that use configurators in providing customized products, offer new insights......, the challenges of implementing and utilizing configurators have less often been considered. By reviewing relevant literature, the present study first categorizes the main challenges faced by manufacturing companies when implementing and utilizing configurators. Six main categories of challenges are identified...

Selling Your Design: Oral Communication Pedagogy in Design Education

Science.gov (United States)

Morton, Janne; O'Brien, David

2005-01-01

Good design skills are the main focus of assessment practices in design education and are evaluated primarily by drawings and models. In some settings, design studio pedagogy tends to reflect only these content-oriented assessment priorities, with minimal attention paid to the development of oral communication skills. Yet, in many professional…

Intelligent CAE system of CYCLONE type cyclotron main magnet and its applications

International Nuclear Information System (INIS)

Zhang Tianjue; Chen Yong; Fan Mingwu

1993-01-01

The main magnet that features the cyclotron is the most important part in a cyclotron construction. Though there are many codes devoted to solving magnetic field computation problems, the results depend on the user's skill and experience very much. To help a cyclotron magnet designer get acceptable results, an intelligent CAE system for CYCLONE type cyclotron magnet design and machining has been developed. Reasonable good results could be got even the designer with the help from an expert knowledge library installed in the program

Main Memory DBMS

NARCIS (Netherlands)

P.A. Boncz (Peter); L. Liu (Lei); M. Tamer Özsu

2008-01-01

htmlabstractA main memory database system is a DBMS that primarily relies on main memory for computer data storage. In contrast, normal database management systems employ hard disk based persisntent storage.

A PREDICTABLE MULTI-THREADED MAIN-MEMORY STORAGE MANAGER

Institute of Scientific and Technical Information of China (English)

无

2001-01-01

This paper introduces the design and implementation of a predictable multi-threaded main-memo- ry storage manager (CS20), and emphasizes the database service mediator(DSM), an operation prediction model using exponential averaging. The memory manager, indexing, as well as lock manager in CS20 are also presented briefly. CS20 has been embedded in a mobile telecommunication service system. Practice showed, DSM effectively controls system load and hence improves the real-time characteristics of data accessing.

EPR compared to international requirements (Mainly EUR)

International Nuclear Information System (INIS)

Broecker, B.

1996-01-01

A number of European Utilities have entered an agreement to write common requirements dedicated to future light water nuclear power plants to be built in Europe. The activities are known under the sign EUR (European Utilities Requirements). EPR, the future European Pressurized water Reactor, is the first installation of this type which will be operational from the year 2000 onwards, must fulfill the European requirements. EPR will serve as a test whether these requirements are realistic and well balanced. At the basic design stage of EPR, this paper concentrates on four main topics: the requirements which are new compared with existing reactors and which put a major challenge to the designer; the requirements today still open and the way they can be met by the EPR or not; the points for which already today the EPR special requirements exceed the EUR; the examples where the design of the EPR has given feedback which has led to a change of the EUR. EPR and EUR are different approaches to the reactor of the future. EUR is a set of requirements which leaves a flexibility to the designer while EPR is a real project which defines the technical solutions. EPR will fulfill the EUR and will at the same time serve as a test whether these requirements are realistic. EPR will also fulfill international requirements with minor changes. (J.S.). 7 figs

Conceptual thermal design

NARCIS (Netherlands)

Strijk, R.

2008-01-01

Present thermal design tools and methods insufficiently support the development of structural concepts engaged by typical practicing designers. Research described in this thesis identifies the main thermal design problems in practice. In addition, models and methods are developed that support an

Modern wind energy technology for Russian applications. Main report

Energy Technology Data Exchange (ETDEWEB)

Hauge Madsen, P.; Winther-Jensen, M., Bindner, H.W. [and others

1999-05-01

The general objective of the project is to establish a technical foundation for an intensified application of wind energy in Russia with medium to large wind turbines and transfer/adaptation of Danish and European wind turbine technology as a basis for future joint ventures and technology exports. More specifically, the objective is to develop and establish the basic knowledge and design criteria for adaptation and development of Danish wind turbine technology for application under Russian conditions. The research programme is envisaged to be carried out in three phases, the first phase being the project reported herein. The main purpose of phase 1 is to assess the needs for modifications and adaptations of established standard (in casu Danish) wind turbine designs for decentralised energy systems with a limited number of medium sized wind turbines and for grid connected wind turbines in cold climate and in-land sites of Russia. As part of this work it is necessary to clarify the types of operational conditions and requirements that are to be met by wind turbines operating in such conditions, and to outline suitable test procedures and test set-up is for verifications of such adapted and modified wind turbines. The reporting of this project is made in one main report and four topical reports, all of them issued as Risoe reports. This is the Main Report, (Risoe-R-1069), summing up the activities and findings of phase 1 and outlining a strategy for Russian-Danish cooperation in wind energy as agreed upon between the Russian and the Danish parties. (au)

General scheme of research reactor mainly for production of fission 99Mo

International Nuclear Information System (INIS)

Shen Feng; Liu Xingmin; Wu Xiaochun; Sun Zheng; Guo Chunqiu; Yi Dayong

2012-01-01

On the basis of the analysis for current circumstance and development tendency of research reactor mainly for 99 Mo production in the world, the design idea of this sort of research reactor was proposed. By the optimization and basic design, the general design parameters of the reactor were analyzed and testified. The evaluation of output activities of 99 Mo and the analysis of economics were conducted on the basically assumption. It is argued that the economics of this reactor is improved dramatically while the safety is ensured by the analysis. (authors)

The role of Main Institutions

DEFF Research Database (Denmark)

Persson, H Thomas R; Chabanet, Didier; Rakar, Fredrik

2017-01-01

), in many countries the need emerged to understand the best methods to promote their establishment and continued success. In order to understand these issues, to contribute to the academic debate on SEs and to give useful policy advice on a truly enabling ecosystem, in November 2013 a consortium of 11...... Entrepreneurship”; to identify the “New Generation” of Social Entrepreneurs; to build an “Evolutionary Theory of Social Entrepreneurship”; to provide effective policy advices to stakeholders. In order to pursue and achieve these research objectives, the consortium implemented a complex research design...... in the social economy; - In the fifth chapter the authors address the role of the main institutions in developing (or hindering) social enterprises; - In the sixth chapter, stakeholder network maps are used to identify four ‘ecosystem types’ across the 10 partner countries; - The seventh chapter gives...

Ethical Design Fiction

DEFF Research Database (Denmark)

Jensen, Thessa; Vistisen, Peter

2017-01-01

In this paper we examine how ethical challenges can be approached in and through design fiction. To do so, we develop a new framework for analysis as well as creation of design fictions. Our main focus will be on design fiction within a strategical setting, connecting the notion of design fiction...

Lubrication analysis of the journal bearing in the main coolant pump of SMART

International Nuclear Information System (INIS)

Lee, J. S.; Park, J. S.; Kim, J. H.; Kim, J. I.; Jang, M. H.

2000-01-01

Special type journal bearings are installed in the main coolant pump for SMART to support the rotating shaft with proper lubrication. The canned motor type main coolant pumps are arranged vertically on the reactor vessel. The MCP bearings are lubricated with water without external lubricating oil supply. Long bearing with vertical grooves is designed with relatively large bearing clearance to accommodate the long shaft. Lubricational analysis method for journal bearing with vertical grooves in the main coolant pump of SMART is proposed, and lubricational characteristics of the bearings are examined in this paper

Nuclear fuel for NPPs: current status and main trends of development

International Nuclear Information System (INIS)

Molchanov, V.

2013-01-01

The customer’s main requirements to nuclear fuel at the present day are: to provide high performance of operational reliability of fuel; to uprate NPP’s capacity to the level of more than 100% from the designed one; to increase fuel cycle length; to increase the burnup of the fuel; to introduce load-follow mode at NPPs. To achieve this requirements the following TVEL activities are presented: New FA designs; Modern designing methods; New automated technologies of nuclear fuel fabrication; Driving to Zero Failure; Increase in safety and reliability of operation; Increase in economical efficiency of fuel utilization; Decrease in amount of spent fuel

The MainSTREAM Component Platform: A Holistic Approach to Microfluidic System Design

DEFF Research Database (Denmark)

Sabourin, David; Skafte-Pedersen, Peder; Søe, Martin Jensen

2013-01-01

A microfluidic component library for building systems driving parallel or serial microfluidic-based assays is presented. The components are a miniaturized eight-channel peristaltic pump, an eight-channel valve, sample-to-waste liquid management, and interconnections. The library of components...... of reaction chips; (2) highly parallel pumping and routing/valving capability; (3) methods to interface pumps and chip-to-liquid management systems; (4) means to construct a portable system; (5) reconfigurability/flexibility in system design; (6) means to interface to microscopes; and (7) compatibility...

Technical basis for the ITER-FEAT outline design. Progress in resolving open design issues from the outline design report

International Nuclear Information System (INIS)

2000-01-01

In this publication the technical basis for the ITER-FEAT outline design is presented. It comprises the Plant Design Specifications, the Safety Principles and Environmental Criteria, the Site Requirements and Site Design Assumptions. The outline of the key features of the ITER-FEAT design includes main physical parameters and assessment, design overview and preliminary safety assessment, cost and schedule

76 FR 59151 - Announcement of Funding Awards; HOPE VI Main Street Grant Program, Fiscal Year (FY) 2009

Science.gov (United States)

2011-09-23

... central business district or ``Main Street'' area by replacing unused commercial space in buildings with... historic or traditional architecture or design features in Main Street areas; (3) enhance economic...

Main Quality Attributes of Monoclonal Antibodies and Effect of Cell Culture Components

Science.gov (United States)

Torkashvand, Fatemeh; Vaziri, Behrouz

2017-05-01

The culture media optimization is an inevitable part of upstream process development in therapeutic monoclonal antibodies (mAbs) production. The quality by design (QbD) approach defines the assured quality of the final product through the development stage. An important step in QbD is determination of the main quality attributes. During the media optimization, some of the main quality attributes such as glycosylation pattern, charge variants, aggregates, and low-molecular-weight species, could be significantly altered. Here, we provide an overview of how cell culture medium components affects the main quality attributes of the mAbs. Knowing the relationship between the culture media components and the main quality attributes could be successfully utilized for a rational optimization of mammalian cell culture media for industrial mAbs production.

Main-coolant-pump shaft-seal guidelines. Volume 3. Specification guidelines. Final report

International Nuclear Information System (INIS)

Fair, C.E.; Greer, A.O.

1983-03-01

This report presents a set of guidelines and criteria to aid in the generation of procurement specifications for Main Coolant Pump Shaft Seals. The noted guidelines are developed from EPRI sponsored nuclear power plant seal operating experience studies, a review of pump and shaft seal literature and discussions with pump and seal designers. This report is preliminary in nature and could be expanded and finalized subsequent to completion of further design, test and evaluation efforts

The Fermilab main injector dipole construction techniques and prototype magnet measurements

International Nuclear Information System (INIS)

Bleadon, M.; Brown, B.; Chester, N.; Desavouret, E.; Garvey, J.; Glass, H.; Harding, D.; Harfoush, F.; Holmes, S.; Humbert, J.; Kerby, J.; Knauf, A.; Kobliska, G.; Lipski, A.; Martin, P.; Mazur, P.; Orris, D.; Ostiguy, J.; Peggs, S.; Pachnik, J.; Pewitt, E.; Satti, J.; Schmidt, E.; Sim, J.; Snowdon, S.; Walbridge, D.

1991-09-01

The Fermilab Main Injector Project will provide 120--150 GeV Proton and Antiproton Beams for Fermilab Fixed Target Physics and Colliding Beams Physics use. A dipole magnet has been designed and prototypes constructed for the principal bending magnets of this new accelerator. The design considerations and fabrication techniques are described. Measurement results on prototypes are reported, emphasizing the field uniformity achieved in both body field and end field at excitation levels from injection at 0.1 T to full field of 1.7 T. 6 refs., 5 figs., 3 tabs

Optimization of a space spectrograph main frame and frequency response analysis of the frame

Science.gov (United States)

Zhang, Xin-yu; Chen, Zhi-yuan; Yang, Shi-mo

2009-07-01

A space spectrograph main structure is optimized and examined in order to satisfy the space operational needs. The space spectrograph will be transported into its operational orbit by the launch vehicle and it will undergo dynamic environment in the spacecraft injection period. The unexpected shocks may cause declination of observation accuracy and even equipment damages. The main frame is one of the most important parts because its mechanical performance has great influence on the operational life of the spectrograph, accuracy of observation, etc. For the reason of cost reduction and stability confirming, lower weight and higher structure stiffness of the frame are simultaneously required. Structure optimization was conducted considering the initial design modal analysis results. The base modal frequency raised 10.34% while the whole weight lowered 8.63% compared to the initial design. The purpose of this study is to analyze the new design of main frame mechanical properties and verify whether it can satisfy strict optical demands under the dynamic impact during spacecraft injection. For realizing and forecasting the frequency response characteristics of the main structure in mechanical environment experiment, dynamic analysis of the structure should be performed simulating impulse loads from the bottom base. Therefore, frequency response analysis (FRA) of the frame was then performed using the FEA software MSC.PATRAN/NASTRAN. Results of shock response spectrum (SRS) responses from the base excitations were given. Stress and acceleration dynamic responses of essential positions in the spacecraft injection course were also calculated and spectrometer structure design was examined considering stiffness / strength demands. In this simulation, maximum stresses of Cesic material in two acceleration application cases are 45.1 and 74.1 MPa, respectively. They are all less than yield strengths. As is demonstrated from the simulation, strength reservation of the frame is

Breakwater design

OpenAIRE

Verhagen, H.J.; van den Bos, J.P.

2017-01-01

For this book we have deliberately chosen that the text should follow a more or less logical design procedure for breakwaters. It follows the required design steps from the system level down to the individual crosssection level, and in time from conceptual design to construction. This systematic approach starts at the functional description of breakwaters, system analysis including side-effects and derivation of boundary conditions and continues to the actual design, first of the main armour ...

System 80+trademark Standard Design: CESSAR design certification. Volume 16

International Nuclear Information System (INIS)

1997-01-01

This report has been prepared in support of the industry effort to standardize nuclear plant designs. This document describes the Combustion Engineering, Inc. System 80+trademark Standard Design. This volume contain Chapter 18 -- Human Factors Engineering. Topics covered include: design team organization and responsibilities; design goals and design bases; design process and application to human factors engineering; functional task analysis; control room configuration; information presentation and panel layout evaluation; control and monitoring outside the main control room; and verification and validation

Improving Design Understandings and Skills through Enhanced Metacognition: Reflective Design Journals

Science.gov (United States)

Kurt, Mustafa; Kurt, Sevinc

2017-01-01

The main aim of this study was to investigate and discover whether going through the process of reflection by keeping reflective design journals (RDJ) enhances architecture students' metacognition and whether this enhanced metacognition improves their design understandings and skills. The study was a mixed-methods design and utilised content…

Reliability-Based Robust Design Optimization of Structures Considering Uncertainty in Design Variables

Directory of Open Access Journals (Sweden)

Shujuan Wang

2015-01-01

Full Text Available This paper investigates the structural design optimization to cover both the reliability and robustness under uncertainty in design variables. The main objective is to improve the efficiency of the optimization process. To address this problem, a hybrid reliability-based robust design optimization (RRDO method is proposed. Prior to the design optimization, the Sobol sensitivity analysis is used for selecting key design variables and providing response variance as well, resulting in significantly reduced computational complexity. The single-loop algorithm is employed to guarantee the structural reliability, allowing fast optimization process. In the case of robust design, the weighting factor balances the response performance and variance with respect to the uncertainty in design variables. The main contribution of this paper is that the proposed method applies the RRDO strategy with the usage of global approximation and the Sobol sensitivity analysis, leading to the reduced computational cost. A structural example is given to illustrate the performance of the proposed method.

The 8-GeV transfer line injection into main ring

International Nuclear Information System (INIS)

Yang, M.J.

1995-06-01

Included in this report are a brief review of the design lattice of the 8-GeV beam transfer line and the Main Ring, the recent measurements on the 8-GeV line lattice function as well as that of the Main Ring at 8-GeV. The injection matching is a very important part of the MR operation. Mismatches such as energy, timing, or position are easily corrected because they cause oscillations which are visible on the Turn-By-Turn (TBT) TV monitor display. Mis-matches due to beta and dispersion functions are detected only by using the Flying Wire or by doing measurements during beam study. A new method which makes use of the available data from TBT hardware was used to obtain the beam phase space ellipse. Data taken from Main Ring at injection gives the beta function needed for transfer matching from 8-GeV line. The result of this measurement is also presented here

Research on reliability measures of the main transformer and GIS equipment manufacturing process

International Nuclear Information System (INIS)

Wu Honglong

2014-01-01

Based on the accidents of the main transformer GIS equipment and the accidents of the high voltage switch equipment, combined with the main transformer switch equipment maintenance experience and electrical theory, the reliability measures of the main transformer GIS equipment during manufacturing stage are studied and improved. Six successful reliability measures are identified: 1) design properly and check the ability of transformer for anti short circuit; 2) choose mature and reliable main transformer HV bushing; 3) choose GIS switch operation mechanism of high quality and reliability; 4) ensure that the insulation margin through tests piece by piece on withstand voltage and partial discharge of the GIS equipment insulation; 5) take test measures such as GIS conductor, shell polishing witness process and full form lightning impulse, to find out and eliminate the defects of abnormal electric field distribution; 6) Anti VFTO design for the main transformer connected with GIS with the voltage of 500 kV should be considered, and its anti VFTO ability to meet the safe operation under VFTO requirements should be checked. This paper proposed 2 new measures: 1) the main transformer insulation material quality standard is determined not only by its high dielectric strength, but more importantly by the homogeneous dielectric electric strength. Insulating Materials with a high and also uniform dielectric strength should be chosen. 2) During the silver-coating stage of the GIS equipment conductor, QC group activities should be organized to ensure that the plating layer quality, and the current lap surface DC resistance measurements should be supervised and witnessed to ensure the quality of the conductor contact surface. These measures are verified in Fuqing project of GIS main transformer equipment manufacturing process, and their effectiveness is proven. (author)

Building Process and Architectural Planning Characteristics of Daehan Hospital Main Building

Directory of Open Access Journals (Sweden)

Geauchul LEE

2016-04-01

Full Text Available This paper explores the introduction process of Daehan Hospital from Japan as the modern medical facility in Korea, and the architectural planning characteristics as a medical facility through the detailed building process of Daehan Hospital main building. The most noticeable characteristic of Daehan Hospital is that it was designed and constructed not by Korean engineers but by Japanese engineers. Therefore, Daehan Hospital was influenced by Japanese early modern medical facility, and Japanese engineers modeled Daehan Hospital main building on Tokyo Medical School main building which was constructed in 1876 as the first national medical school and hospital. The architectural type of Tokyo Medical School main building was a typical school architecture in early Japanese modern period which had a middle corridor and a pseudo Western-style tower, but Tokyo Medical School main building became the model of a medical facility as the symbol of the medical department in Tokyo Imperial University. This was the introduction and transplantation process of Japanese modern ‘model’ like as other modern systems and technologies during the Korean modern transition period. However, unlike Tokyo Medical School main building, Daehan Hospital main building was constructed not as a wooden building but as a masonry building. Comparing with the function of Daehan Hospital main building, its architectural form and construction costs was excessive scale, which was because Japanese Resident-General of Korea had the intention of ostentation that Japanese modernity was superior to Korean Empire.

[Building Process and Architectural Planning Characteristics of Daehan Hospital Main Building].

Science.gov (United States)

Lee, Geauchul

2016-04-01

This paper explores the introduction process of Daehan Hospital from Japan as the modern medical facility in Korea, and the architectural planning characteristics as a medical facility through the detailed building process of Daehan Hospital main building. The most noticeable characteristic of Daehan Hospital is that it was designed and constructed not by Korean engineers but by Japanese engineers. Therefore, Daehan Hospital was influenced by Japanese early modern medical facility, and Japanese engineers modeled Daehan Hospital main building on Tokyo Medical School main building which was constructed in 1876 as the first national medical school and hospital. The architectural type of Tokyo Medical School main building was a typical school architecture in early Japanese modern period which had a middle corridor and a pseudo Western-style tower, but Tokyo Medical School main building became the model of a medical facility as the symbol of the medical department in Tokyo Imperial University. This was the introduction and transplantation process of Japanese modern 'model' like as other modern systems and technologies during the Korean modern transition period. However, unlike Tokyo Medical School main building, Daehan Hospital main building was constructed not as a wooden building but as a masonry building. Comparing with the function of Daehan Hospital main building, its architectural form and construction costs was excessive scale, which was because Japanese Resident-General of Korea had the intention of ostentation that Japanese modernity was superior to Korean Empire.

Research pressure instrumentation for NASA Space Shuttle main engine, modification no. 5

Science.gov (United States)

Anderson, P. J.; Nussbaum, P.; Gustafson, G.

1984-01-01

Research concerning the development of pressure instrumentation for the space shuttle main engine is reported. The following specific topics were addressed: (1) transducer design and materials, (2) silicon piezoresistor characterization at cryogenic temperatures, (3) chip mounting characterization, and (4) frequency response optimization.

High resolution main-ion charge exchange spectroscopy in the DIII-D H-mode pedestal.

Science.gov (United States)

Grierson, B A; Burrell, K H; Chrystal, C; Groebner, R J; Haskey, S R; Kaplan, D H

2016-11-01

A new high spatial resolution main-ion (deuterium) charge-exchange spectroscopy system covering the tokamak boundary region has been installed on the DIII-D tokamak. Sixteen new edge main-ion charge-exchange recombination sightlines have been combined with nineteen impurity sightlines in a tangentially viewing geometry on the DIII-D midplane with an interleaving design that achieves 8 mm inter-channel radial resolution for detailed profiles of main-ion temperature, velocity, charge-exchange emission, and neutral beam emission. At the plasma boundary, we find a strong enhancement of the main-ion toroidal velocity that exceeds the impurity velocity by a factor of two. The unique combination of experimentally measured main-ion and impurity profiles provides a powerful quasi-neutrality constraint for reconstruction of tokamak H-mode pedestals.

Kinematics at the Main Mechanism of a Railbound Forging Manipulator

Directory of Open Access Journals (Sweden)

Florian Ion Tiberiu Petrescu

2015-09-01

Full Text Available Normal 0 false false false EN-US X-NONE X-NONE MicrosoftInternetExplorer4 Heavy payload forging manipulators are mainly characterized by large load output and large capacitive load input. The relationship between outputs and inputs will greatly influence the control and the reliability. Forging manipulators have become more prevalent in the industry today. They are used to manipulate objects to be forged. The most common forging manipulators are moving on a railway to have a greater precision and stability. They have been called the railbound forging manipulators. In this paper we analyze the general kinematics of the main mechanism from a such manipulator. Kinematic scheme shows a typical forging manipulator, with the basic motions in operation process: walking, motion of the tong and buffering. The lifting mechanism consists of several parts including linkages, hydraulic drives and motion pairs. The principle of type design from the viewpoints of the relationship between output characteristics and actuator inputs is discussed. An idea of establishing the incidence relationship between output characteristics and actuator inputs is proposed. These novel forging manipulators which satisfy certain functional requirements provide an effective help for the design of forging manipulators.

Recovery of 233U from irradiated J rods - operating experience

International Nuclear Information System (INIS)

Lakshmanan, K.; Natarajan, D.; Muthukumar, M.; Halder, Surajit; Jayakrishnan, G.; Selvarasan, M.; Kuppusamy, V.; Ganesan, V.; Vijayakumar, V.

2000-01-01

The first campaign of reprocessing was completed in 1988 and 233 U was delivered for fabrication of fuel for KAMINI. After revamping the facility, the second campaign was started in Dec 1998 and has processed some of the high density thoria rods from CIRUS successfully. Currently the campaign is in progress and it is planned to process the irradiated thorium rods from Dhruva. Interim 23 process selective to 233 U is adopted for separation of uranium from thorium and fission products

Removal of aluminum turbidity from heavy water reactors by precipitation ion exchange using magnesium hydroxide

International Nuclear Information System (INIS)

Venkateswarlu, K.S.; Shanker, R.; Velmurugan, S.; Venkateswaran, G.; Rao, M.R.

1988-01-01

A special magnesium hydroxide MG(OH)/sub 2/ sorber, loaded onto an ion-exchange matrix has been developed to remove hydrated alumina turbidity in heavy water. This sorber was applied to the coolant/moderator system in the research reactor Dhruva. The sorber not only removed turbidity but also suspended uranium at parts per billion levels and associated β, γ activity. The sorption is based on the attraction between the positively charged Mg(OH)/sub 2/ surface and the negatively charged hydrated alumina particles

Budget Period 1 Summary Report: Hywind Maine Project

Energy Technology Data Exchange (ETDEWEB)

Keiser, Meagan [Statoil, Stavanger (Norway)

2014-02-28

In accordance with the Statement of Project Objectives (SOPO) agreed to between the Department of Energy (“DOE”) and Statoil for the Hywind Maine project, Statoil hereby submits a Budget Period 1 Summary Report which includes accomplishments for the project. The report includes summaries of the other submitted reports (see Section 1.2-2) and progress regarding innovations leading to potential reductions in the Cost of Energy (see Section 3). The Hywind Demo project, the world’s first full-scale 2.3 megawatts (MW) floating wind turbine, installed at a water depth of 200 meter (m), 10 kilometer (km) off the coast of Norway, has proven that the Hywind floating substructure is a suitable platform for conventional multi- MW turbines. A principal goal of the Hywind Maine Project was to leverage that experience, both to demonstrate the commercial feasibility of the technology and to further develop and optimize the technology all in order to bring the costs down in a larger scale development. With the Hywind Maine Project, Statoil planned to deploy four turbines of 3 MW in approximately 140 meters water depth. Although the project in Maine will not move forward, much value was gained through the BP1 work package. Advanced modeling related to the design basis, which will have applicability beyond the Maine project, was completed. In addition, initial supply chain analyses were conducted, which will help assist with development of updated cost of energy models. Geophysical and various environmental surveys were also conducted, the results of which Statoil has committed to share publicly, and which will help build a database of information that future developers may be able to access. Finally, Statoil gained a greater understanding of the US offshore wind industry and related markets, which will assist the company as it looks for full-scale, commercial opportunities.

76 FR 38408 - Notice of Funding Availability (NOFA) for HUD's Fiscal Year 2011 HOPE VI Main Street Grants

Science.gov (United States)

2011-06-30

... traditional central business district or ``Main Street'' area by replacing unused commercial space in... areas; 2. Preserve historic or traditional architecture or design features in Main Street areas; 3...

a basic approach to designing e calculator and c oach to designing

African Journals Online (AJOL)

eobe

machine may have three main functions ree main functions ... most control systems using digital logic w implemented using individual ... OACH TO DESIGNING EMBEDDED SYSTEMS USING A SI. OACH TO .... Jumper Wires. No Units. 1 yard.

Maine's forests 2008

Science.gov (United States)

George L. McCaskill; William H. McWilliams; Charles J. Barnett; Brett J. Butler; Mark A. Hatfield; Cassandra M. Kurtz; Randall S. Morin; W. Keith Moser; Charles H. Perry; Christopher W. Woodall

2011-01-01

The second annual inventory of Maine's forests was completed in 2008 after more than 3,160 forested plots were measured. Forest land occupies almost 17.7 million acres, which represents 82 percent of the total land area of Maine. The dominant forest-type groups are maple/beech/yellow birch, spruce/fir, white/red/jack pine, and aspen/white birch. Statewide volume...

Positive design : An introduction to design for subjective well-being

NARCIS (Netherlands)

Desmet, P.M.A.; Pohlmeyer, A.E.

2013-01-01

This paper addresses the question of how design can contribute to the happiness of individuals–to their subjective well-being. A framework for positive design is introduced that includes three main components of subjective well-being: pleasure, personal significance and virtue. Each component

Measurement of the transfer function of the main SPS Quadrupoles

CERN Document Server

Dinius, A; Semanaz, P; CERN. Geneva. SPS and LEP Division

1998-01-01

During two short MD's we have measured the transfer function (amplitude and phase) of the main quadrupole string QD. By the word string we mean the global effect of power supplies, magnets and the eddy current effects of the vacuum chamber. This paper presents the measurement procedure and the results, which are needed for the design of a real-time feedback system for the betatron tunes ( Qloop).

Main results of substantiation of the ecological safety of the Novovoronezh NPP-2 design

International Nuclear Information System (INIS)

Kopytov, I.I.; Kocher'yan, V.M.; Leonov, S.V.; Chionov, V.G.; Ehrnestova, L.S.

2005-01-01

Paper presents the results of the efforts to determine both the actual (hydrochemical, hydrobiological, geobotanical, soil, radiological) and the predicted parameters of the region ecology derived when substantiating the ecological safety of the Novovoronezh NPP-2 design [ru

Fermilab 500 GeV main accelerator rf cavity 128 MHz mode damper

International Nuclear Information System (INIS)

Kerns, Q.A.; Miller, H.W.

1977-01-01

The Fermilab 500-GeV main accelerating system has been operating for a year now with the aid of 128-MHz mode dampers. Such dampers proved to be necessary to achieve stable operation and a reasonably smooth slow spill at intensities of approximately 2 x 10 13 protons per pulse, and furthermore are low-cost and reliable. The approach used to identify troublesome modes, the observed beam blow-up without dampers, and the steps taken to design and install suitable dampers on eighteen main ring cavities are discussed. Spectrum analyzer pictures help illustrate the performance

Research pressure instrumentation for NASA Space Shuttle main engine, modification no. 6

Science.gov (United States)

Anderson, P. J.; Johnson, R. L.

1984-01-01

Research concerning the utilization of silicon piezoresistive strain sensing technology for space shuttle main engine applications is reported. The following specific topics were addressed: (1) transducer design and materials, (2) silicon piezoresistor characterization at cryogenic temperatures, (3) chip mounting characterization, and (4) frequency response optimization.

Designing Online Education Courses.

Science.gov (United States)

Trentin, Guglielmo

2001-01-01

Focuses on the main elements that characterize online course design. Topics include design constraints; analysis of learning needs; defining objectives; course prerequisites; content structuring; course flexibility; learning strategies; evaluation criteria; course activities; course structure; communication architecture; and design evaluation.…

Use of the Human Centered Design concept when designing ergonomic NPP control rooms

International Nuclear Information System (INIS)

Skrehot, Petr A.; Houser, Frantisek; Riha, Radek; Tuma, Zdenek

2015-01-01

Human-Centered Design is a concept aimed at reconciling human needs on the one hand and limitations posed by the design disposition of the room being designed on the other hand. This paper describes the main aspects of application of the Human-Centered Design concept to the design of nuclear power plant control rooms. (orig.)

Development of LBB Piping Evaluation Diagram for APR 1000 Main Steam Line Piping

International Nuclear Information System (INIS)

Yang, J. S.; Jeong, I. L.; Park, C. Y.; Bai, S. Y.

2010-01-01

This paper presents the piping evaluation diagram (PED) to assess the applicability of Leak-Before- Break(LBB) for APR 1000 main steam line piping. LBB-PED of APR 1000 main steam line piping is independent of its piping geometry and has a function of the loads applied in piping system. Also, in order to evaluate LBB applicability during construction process with only the comparative evaluation of material properties between actually used and expected, the expected changes of material properties are considered in the LBB-PED. The LBB-PED, therefore, can be used for quick LBB evaluation of APR 1000 main steam line piping of both design and construction

CONCEPTUAL PRODUCT DESIGN IN VIRTUAL PROTOTYPING

Directory of Open Access Journals (Sweden)

Debeleac Carmen

2009-07-01

Full Text Available A conceptual model of the industrial design process for isolation against vibrations is proposed and described. This model can be used to design products subject to functional, manufacturing, ergonomic, aesthetic constraints. In this paper, the main stages of the model, such as component organization, conception shape, product detailing and graphical design are discussed. The work has confirmed the validity of proposed model for rapid generation of aesthetic preliminary product designs using the virtual prototyping technique, by one of its main component that is conceptual product design.

Maine Forests 2013

Science.gov (United States)

George L. McCaskill; Thomas Albright; Charles J. Barnett; Brett J. Butler; Susan J. Crocker; Cassandra M. Kurtz; William H. McWilliams; Patrick D. Miles; Randall S. Morin; Mark D. Nelson; Richard H. Widmann; Christopher W. Woodall

2016-01-01

The third 5-year annualized inventory of Maine's forests was completed in 2013 after more than 3170 forested plots were measured. Maine contains more than 17.6 million acres of forest land, an area that has been quite stable since 1960, covering more than 82 percent of the total land area. The number of live trees greater than 1 inch in diameter are approaching 24...

User-centered design

International Nuclear Information System (INIS)

Baik, Joo Hyun; Kim, Hyeong Heon

2008-01-01

The simplification philosophy, as an example, that both of EPRI-URD and EUR emphasize is treated mostly for the cost reduction of the nuclear power plants, but not for the simplification of the structure of user's tasks, which is one of the principles of user-centered design. A user-centered design is a philosophy based on the needs and interests of the user, with an emphasis on making products usable and understandable. However, the nuclear power plants offered these days by which the predominant reactor vendors are hardly user-centered but still designer-centered or technology-centered in viewpoint of fulfilling user requirements. The main goal of user-centered design is that user requirements are elicited correctly, reflected properly into the system requirements, and verified thoroughly by the tests. Starting from the user requirements throughout to the final test, each requirement should be traceable. That's why requirement traceability is a key to the user-centered design, and main theme of a requirement management program, which is suggested to be added into EPRI-URD and EUR in the section of Design Process. (author)

Enhancing field GP engagement in hospital-based studies. Rationale, design, main results and participation in the diagest 3-GP motivation study

Directory of Open Access Journals (Sweden)

Berkhout Christophe

2012-06-01

Full Text Available Abstract Background Diagest 3 was a study aimed at lowering the risk of developing type 2 diabetes within 3 years after childbirth. Women with gestational diabetes were enrolled in the study. After childbirth, the subjects showed little interest in the structured education programme and did not attend workshops. Their general practitioners (GPs were approached to help motivate the subjects to participate in Diagest 3, but the GPs were reluctant. The present study aimed to understand field GPs’ attitudes towards hospital-based studies, and to develop strategies to enhance their involvement and reduce subject drop-out rates. Methods We used a three-step process: step one used a phenomenological approach exploring the beliefs, attitudes, motivations and environmental factors contributing to the GPs’ level of interest in the study. Data were collected in face-to-face interviews and coded by hand and with hermeneutic software to develop distinct GP profiles. Step two was a cross-sectional survey by questionnaire to determine the distribution of the profiles in the GP study population and whether completion of an attached case report form (CRF was associated with a particular GP profile. In step three, we assessed the impact of the motivation study on participation rates in the main study. Results Fifteen interviews were conducted to achieve data saturation. Theorisation led to the definition of 4 distinct GP profiles. The response rate to the questionnaire was 73%, but dropped to 52% when a CRF was attached. The link between GP profiles and the rate of CRF completion remains to be verified. The GPs provided data on the CRF that was of comparable quality to those collected in the main trial. Our analysis showed that the motivation study increased overall participation in the main study by 23%, accounting for 16% (24/152 of all final visits for 536 patients who were initially enrolled in the Diagest 3 study. Conclusions When a hospital-led study

Enhancing field GP engagement in hospital-based studies. Rationale, design, main results and participation in the Diagest 3-GP motivation study.

Science.gov (United States)

Berkhout, Christophe; Vandaele-Bétancourt, Marie; Robert, Stéphane; Lespinasse, Solène; Mitha, Gamil; Bradier, Quentin; Vambergue, Anne; Fontaine, Pierre

2012-06-21

Diagest 3 was a study aimed at lowering the risk of developing type 2 diabetes within 3 years after childbirth. Women with gestational diabetes were enrolled in the study. After childbirth, the subjects showed little interest in the structured education programme and did not attend workshops. Their general practitioners (GPs) were approached to help motivate the subjects to participate in Diagest 3, but the GPs were reluctant. The present study aimed to understand field GPs' attitudes towards hospital-based studies, and to develop strategies to enhance their involvement and reduce subject drop-out rates. We used a three-step process: step one used a phenomenological approach exploring the beliefs, attitudes, motivations and environmental factors contributing to the GPs' level of interest in the study. Data were collected in face-to-face interviews and coded by hand and with hermeneutic software to develop distinct GP profiles. Step two was a cross-sectional survey by questionnaire to determine the distribution of the profiles in the GP study population and whether completion of an attached case report form (CRF) was associated with a particular GP profile. In step three, we assessed the impact of the motivation study on participation rates in the main study. Fifteen interviews were conducted to achieve data saturation. Theorisation led to the definition of 4 distinct GP profiles. The response rate to the questionnaire was 73%, but dropped to 52% when a CRF was attached. The link between GP profiles and the rate of CRF completion remains to be verified. The GPs provided data on the CRF that was of comparable quality to those collected in the main trial. Our analysis showed that the motivation study increased overall participation in the main study by 23%, accounting for 16% (24/152) of all final visits for 536 patients who were initially enrolled in the Diagest 3 study. When a hospital-led study explores issues in primary care, its design must anticipate GP

Cryostat Design

Energy Technology Data Exchange (ETDEWEB)

Parma, V [European Organization for Nuclear Research, Geneva (Switzerland)

2014-07-01

This paper aims to give non-expert engineers and scientists working in the domain of accelerators a general introduction to the main disciplines and technologies involved in the design and construction of accelerator cryostats. Far from being an exhaustive coverage of these topics, an attempt is made to provide simple design and calculation rules for a preliminary design of cryostats. Recurrent reference is made to the Large Hadron Collider magnet cryostats, as most of the material presented is taken from their design and construction at CERN.

The characteristics of the Westinghouse accident procedures and the main differences with SOP

International Nuclear Information System (INIS)

Hu Yan; Gan Peijiang; Sun Chen

2014-01-01

In this note, the Westinghouse operation file system is summarized. The structures of procedures, design methods, implementation logics of the Westinghouse accident procedures are discussed. And compared with the SOP principles, the main differences are clarified. (authors)

The effects of improvement of the main shaft on the operating conditions of the Agnew turbine

Energy Technology Data Exchange (ETDEWEB)

Yassi, Y. [Iranian Research Organization for Science and Technology (IROST), Tehran (Iran)

2009-10-15

Agnew turbine is a 45 axial flow Kaplan type micro hydro. The turbine was designed by an ex-lecturer of the Univ. of Glasgow, to operate without guide vanes. Later due to a joint research program between the Iranian Research Organization for Science and Technology (IROST) and the Univ. of Glasgow it was developed to operate under low head and limited flow potentials in Iran. The original design of the main shaft of the turbine was supported by a bearing housing consisting of three bearings outside the main casing, leaving the rest of the shaft, hub and the runner without any supports inside the turbine.Later a suitable support near the runner and inside the casing was designed and installed. Standard turbine tests showed considerable improvements in operating characteristics of the turbine due to these design modifications. This paper presents details of these improvements and the related outcomes. (author)

The effects of improvement of the main shaft on the operating conditions of the Agnew turbine

International Nuclear Information System (INIS)

Yassi, Y.

2009-01-01

Agnew turbine is a 45 deg. axial flow Kaplan type micro hydro. The turbine was designed by an ex-lecturer of the University of Glasgow, to operate without guide vanes. Later due to a joint research program between the Iranian Research Organization for Science and Technology (IROST) and the University of Glasgow it was developed to operate under low head and limited flow potentials in Iran. The original design of the main shaft of the turbine was supported by a bearing housing consisting of three bearings outside the main casing, leaving the rest of the shaft, hub and the runner without any supports inside the turbine .Later a suitable support near the runner and inside the casing was designed and installed. Standard turbine tests showed considerable improvements in operating characteristics of the turbine due to these design modifications. This paper presents details of these improvements and the related outcomes.

The New Control and Interlock System for the SPS Main Power Converters

CERN Document Server

Denis, B; Mugnier, C; Varas, J

1999-01-01

The Control and Interlock System (CIS) of the SPS main power converters was designed in the mid-70s and became increasingly difficult to maintain. A new system based on Programmable Logic Controllers has been developed by an external contractor in close collaboration with CERN. The system is now operational and fully integrated in the SPS/LEP control infrastructure. The CIS is the first major contracted industrial solution used to control accelerator equipment directly involved in the production of particle beams at CERN. This paper gives an overview of the SPS main power converter installation and describes both the contractual and technical solution adopted for the CIS. It first explains how the system was specified and how the contractual relationship was defined to respect CERN’s purchasing rules and the operational requirements of the SPS accelerator. The architectural design of the new system is presented with special emphasis on how the conflict between safety and availability has been addressed.

Qualification test of a main coolant pump for SMART pilot

International Nuclear Information System (INIS)

Park, Sang Jin; Yoon, Eui Soo; Oh, Hyong Woo

2006-01-01

SMART Pilot is a multipurpose small capacity integral type reactor. Main Coolant Pump (MCP) of SMART Pilot is a canned-motor-type axial pump to circulate the primary coolant between nuclear fuel and steam generator in the primary system. The reactor is designed to operate under condition of 310 .deg. C and 14.7 MPa. Thus MCP has to be tested under same operating condition as reactor design condition to verify its performance and safety. In present work, a test apparatus to simulate real operating situations of the reactor has been designed and constructed to test MCP. And then functional tests, performance tests, and endurance tests have been carried out upon a prototype MCP. Canned motor characteristics, homologous head/torque curves, coast-down curves, NPSH curves and life-time performance variations were obtained from the qualification test as well as hydraulic performance characteristics of MCP

The AGS Booster main ring power supply system

International Nuclear Information System (INIS)

Soukas, A.; Hughes, K.; Sandberg, J.; Toldo, F.; Zhang, S.Y.

1989-01-01

The AGS Booster is being designed as a very versatile particle accelerator. Its primary function is to be a high quality injector to the currently operating Alternating Gradient Synchrotron (AGS). The Booster/AGS combination will produce proton intensities greater than 5 x 10 13 protons per pulse (ppp), and accelerate heavy ions, with mass up to 200, to a maximum energy of 15 GeV per atomic mass unit (GeV/amu). The power supply for the Booster Main Ring (BMRPS) has to accommodate a wide range of cycles and a wide range of operating parameters. The cycles range from storage for several seconds to rapid cycling at 7.5 Hz. The peak output power is 18 MW. This paper will describe the AGS Booster machine powering requirements, the choice of power supply, the a.c. circuit tie-in and its associated problems and some of the details of the design of the BMRPS. 9 refs., 2 figs

The Communication Between Designer and Design Receiver

DEFF Research Database (Denmark)

Dai, Zheng; Dai, Yan

2009-01-01

When people think about a product,the first impression always mainly influences the result.Product is the medium of communication between designer and designer receiver.Because both of them have varied different experience and background,the information would be biased during the transferring...... process.The common symbols which can be recognized by both of designer and receiver are the key tools for communication.In some case,the same symbol in one product would be leads to different receiver impression.Generally,impression includes 3 aspects:aesthetics,function, and emotion.Designer needs...... to create an attractive and accurate impression in product from these 3 aspects.For facing the dilemma of communication,some experimental approaches can help designer deal with unique and diversity situations.Solving the detail problem in each step could keep the original meaning of designer....

Indigenous development of TBq levels of "1"7"7Lu radioisotope production at RPhD for nuclear medicine applications - a successful venture

International Nuclear Information System (INIS)

Chakraborty, Sudipta; Vimalnath, K.V.; Dash, Ashutosh

2017-01-01

Lutetium-177 ("1"7"7Lu) has emerged as a potential radionuclide during last decade for the development of radionuclide therapy owing to its favorable nuclear decay characteristics (T_1_/_2=6.65 d, E_β_(_m_a_x) = 0.497 MeV, E_γ = 113 keV (6.4%) and 208 keV (11%)). The long half-life of this promising radioisotope offering distinct logistical advantage and feasibility of its large-scale production in medium flux Dhruva research reactor contributed to its success story

High-resolution protein design with backbone freedom.

Science.gov (United States)

Harbury, P B; Plecs, J J; Tidor, B; Alber, T; Kim, P S

1998-11-20

Recent advances in computational techniques have allowed the design of precise side-chain packing in proteins with predetermined, naturally occurring backbone structures. Because these methods do not model protein main-chain flexibility, they lack the breadth to explore novel backbone conformations. Here the de novo design of a family of alpha-helical bundle proteins with a right-handed superhelical twist is described. In the design, the overall protein fold was specified by hydrophobic-polar residue patterning, whereas the bundle oligomerization state, detailed main-chain conformation, and interior side-chain rotamers were engineered by computational enumerations of packing in alternate backbone structures. Main-chain flexibility was incorporated through an algebraic parameterization of the backbone. The designed peptides form alpha-helical dimers, trimers, and tetramers in accord with the design goals. The crystal structure of the tetramer matches the designed structure in atomic detail.

Thin film heat flux sensor for Space Shuttle Main Engine turbine environment

Science.gov (United States)

Will, Herbert

1991-01-01

The Space Shuttle Main Engine (SSME) turbine environment stresses engine components to their design limits and beyond. The extremely high temperatures and rapid temperature cycling can easily cause parts to fail if they are not properly designed. Thin film heat flux sensors can provide heat loading information with almost no disturbance of gas flows or of the blade. These sensors can provide steady state and transient heat flux information. A thin film heat flux sensor is described which makes it easier to measure small temperature differences across very thin insulating layers.

Development of design technology for system - integrated modular advanced react or (SMART) /technology support of NSSS design for SMART

Energy Technology Data Exchange (ETDEWEB)

Joon, Hah Yung; Kim, Kee Eun [KOPEC, Taejeon (Korea)

2002-03-01

SMART design concept is very different from that of the commercial PWRs, as the main components such as the steam generator, pressurizer, and the main coolant pumps are incorporate the related sub-part systems into the reactor vessel. In this report the design for SMART is the basic design stage and is the new design technology development task for the first trial in Korea. KOPEC NED has participated with Korea Atomic Energy Research Institute for the task of 'Development of Design Technology for SMART' as supporting sub-task of it. The system design (ECCS, Makeup and Purification System), mechanical design (Seismic Analysis, BLPB Analysis, Structural Analysis, Design Load Calculation, Stress Fatigue Evaluation, Fracture Mechanical and Structural Integrity Evaluation), MMIS design (Alarm and Indication System, Information Processing System, Large Display Panel, Human System Interface Guideline) have been performed as a basic design for SMART during 31 months (1999. 9.1{approx}2002.3.31). This report is the final one for the support of the main task of Korea Atomic Energy Research Institute. 124 refs., 154 figs., 97 tabs. (Author)

Effect of main stem pruning and fruit thinning on the postharvest conservation of melon

Directory of Open Access Journals (Sweden)

Rafaella M. de A. Ferreira

Full Text Available ABSTRACT Main stem pruning and fruit thinning are cultivation practices that can influence the yield and quality of the fruit. This study aimed to evaluate the effects of main stem pruning and fruit thinning on the postharvest conservation of Charentais Banzai melons. In the field, the plants were subjected to main stem pruning and fruit thinning, with harvesting done 74 days after sowing (DAS. The fruits were transported to the laboratory where they were cleaned, characterized, and stored in a cold chamber (5 °C and 90 ± 2% RH. In the field, the experiment was designed as a split-plot using a 2 × 4 + 1 factorial design, with two levels of main stem pruning (pruned and unpruned, four levels of thinning times (42, 45, 48, and 51 DAS, and a control (unpruned and unthinned. The sub-plot consisted of storage times (0, 7, 14, 21, and 28 days, with four blocks. The preharvest treatments did not significantly influence the production characteristics of the Banzai hybrid. The treatment without pruning increased the titratable acidity of fruit, and the thinning at 51 days after sowing (DAS reduced soluble sugars. There was a decline in pulp firmness, titratable acidity, reducing sugars, and an increase in soluble solids, total soluble sugar, and non-reducing sugars during storage. Pruning the main melon stem reduced the weight loss of the fruit after 28 days of storage.

Determination of trace concentrations of aluminium in rice samples by INAA and PIGE methods

International Nuclear Information System (INIS)

Nanda, B.B.; Biswal, R.R.; Acharya, R.; Pujari, P.K.

2015-01-01

Aluminium is one of the toxic elements entering human body mainly through food and food products. Though its bioavailability is very less, it is necessary to evaluate its total concentrations in food and food products entering to the body through. In order to evaluate total aluminium contents in various food items for daily dietary intake of aluminum, authors have systematically planned to carry out experiments in various food items including rice. Rice is the main food in many parts of India as well as in Odisha. Rice samples under study belong to three categories; (i) various rice samples from local market, (ii) various rice samples grown in similar irrigation (soil and water) conditions and (iii) same variety of rice with different irrigation conditions. Solid samples (pre-cleaned) were powdered, homogenized and taken for analysis by two nuclear analytical techniques (NATs) namely instrumental neutron activation analysis (INAA) using reactor neutrons at BARC and particle induced gamma ray emission (PIGE) using 4 MeV proton beam (20 nA current) from 3 MV Tandetron at IOP, Bhubaneswar in conjunction with high resolution gamma-ray spectrometry. Samples of 10-50 mg for INAA and 250 mg (pelletized in cellulose) for PIGE were used for experiments. For INAA, samples were irradiated at PCF, Dhruva reactor for 1 minute

Severe accidents and ESFR design issues

International Nuclear Information System (INIS)

Rineiski, A.

2013-01-01

Current SFR studies in Germany: ⇒ In support of European SFR studies, mainly on safety and safety-related (design optimization) issues; ⇒ ADS and SFR as main options for spent fuel management in studies on the possibility of P&T; ⇒ ESFR-type designs studied recently; ⇒ ASTRID-type designs to be studied in the future; ⇒ Particular area: modeling of severe accidents with SAS4A/SAS-SFR and SIMMER codes

Report of the Solid State Physics Division (1991-1992)

International Nuclear Information System (INIS)

1995-01-01

This report summarizes the activities carried out in the Solid State Physics Division at Bhabha Atomic Research Centre (BARC) covering the period from 1991-1992. The activities are reported in the form of individual summaries arranged under headings: Research Activities, Instrumentation and Software Development. The main research activity of the Division is centered around the utilisation of the neutron beams at the Dhruva and Cirus reactors. A number of research proposals from the universities, funded by the Inter University Consortium come under the category of powder diffraction studies. Another area of research where there is a good demand from universities is in the field of small angle neutron scattering. In addition to the neutron beam research, a number of other investigations pertaining to Raman scattering, liquid crystals, model membranes, magnetism, protein crystallography etc. have contributed significantly to the research programme. The fully indigenous guide laboratory is expected to become operational soon. A list of published papers, internal reports and submitted theses is given at the end. (author). refs., figs., tabs

Energy Recovery for the Main and Auxiliary Sources of Electric Vehicles

Directory of Open Access Journals (Sweden)

Binggang Cao

2010-10-01

Full Text Available Based on the traditional regenerative braking electrical circuit, a novel energy recovery system for the main and auxiliary sources of electric vehicles (EVs has been developed to improve their energy efficiency. The electrical circuit topology is presented in detail. During regenerative braking, the recovered mechanical energy is stored in both the main source and the auxiliary source at the same time. The mathematical model of the proposed system is derived step by step. Combining the merits and defects of H2 optimal control and H∞ robust control, a H2/H∞ controller is designed to guarantee both the system performance and robust stability. The perfect match between the simulated and experimental results validates the notion that the proposed novel energy recovery system is both feasible and effective, as more energy is recovered than that with the traditional energy recovery systems, in which recovered energy is stored only in the main source.

High-ratio voltage conversion in CMOS for efficient mains-connected standby

CERN Document Server

Meyvaert, Hans

2016-01-01

This book describes synergetic innovation opportunities offered by combining the field of power conversion with the field of integrated circuit (IC) design. The authors demonstrate how integrating circuits enables increased operation frequency, which can be exploited in power converters to reduce drastically the size of the discrete passive components. The authors introduce multiple power converter circuits, which are very compact as result of their high level of integration. First, the limits of high-power-density low-voltage monolithic switched-capacitor DC-DC conversion are investigated to enable on-chip power granularization. AC-DC conversion from the mains to a low voltage DC is discussed, enabling an efficient and compact, lower-power auxiliary power supply to take over the power delivery during the standby mode of mains-connected appliances, allowing the main power converter of these devices to be shut down fully. Discusses high-power-density monolithic switched-capacitor DC-DC conversion in bulk CMOS,...

Energy Recovery for the Main and Auxiliary Sources of Electric Vehicles

Energy Technology Data Exchange (ETDEWEB)

Min Ye [Key Laboratory for Highway Construction Technology and Equipment of Ministry of Education, Chang’an University, Xi’an (China); Sengjie Jiao [Key Laboratory for Highway Construction Technology and Equipment of Ministry of Education, Chang’an University, Xi’an (China); Binggang Cao [School of Mechanical Engineering, Xi’an Jiaotong University, Xi’an (China)

2010-09-15

Based on the traditional regenerative braking electrical circuit, a novel energy recovery system for the main and auxiliary sources of electric vehicles (EVs) has been developed to improve their energy efficiency. The electrical circuit topology is presented in detail. During regenerative braking, the recovered mechanical energy is stored in both the main source and the auxiliary source at the same time. The mathematical model of the proposed system is derived step by step. Combining the merits and defects of H2 optimal control and H-infinity robust control, a H2/H-infinity controller is designed to guarantee both the system performance and robust stability. The perfect match between the simulated and experimental results validates the notion that the proposed novel energy recovery system is both feasible and effective, as more energy is recovered than that with the traditional energy recovery systems, in which recovered energy is stored only in the main source.

Energy Recovery for the Main and Auxiliary Sources of Electric Vehicles

Energy Technology Data Exchange (ETDEWEB)

Ye, M.; Jiao, S. [Key Laboratory for Highway Construction Technology and Equipment of Ministry of Education, Chang' an University, Xi' an 710064 (China); Cao, B. [School of Mechanical Engineering, Xi' an Jiaotong University, Xi' an 710049 (China)

2010-10-15

Based on the traditional regenerative braking electrical circuit, a novel energy recovery system for the main and auxiliary sources of electric vehicles (EVs) has been developed to improve their energy efficiency. The electrical circuit topology is presented in detail. During regenerative braking, the recovered mechanical energy is stored in both the main source and the auxiliary source at the same time. The mathematical model of the proposed system is derived step by step. Combining the merits and defects of H{sub 2} optimal control and H{sub {infinity}} robust control, a H{sub 2}/H{sub {infinity}} controller is designed to guarantee both the system performance and robust stability. The perfect match between the simulated and experimental results validates the notion that the proposed novel energy recovery system is both feasible and effective, as more energy is recovered than that with the traditional energy recovery systems, in which recovered energy is stored only in the main source. (authors)

Analysis of containment parameters during the main steam line break with the failure of the feedwater control valves

International Nuclear Information System (INIS)

Fabjan, L.; Petelin, S.; Mavko, B.; Gortnar, O.; Tiselj, I.

1992-01-01

U.S. Nuclear Regulatory Commission (NRC) information notice 91-69: 'Errors in Main Steam Line Break Analyses for Determining Containment Parameters' shows the possibility of an accident which could lead to beyond design containment pressure and temperature. Such accident would be caused by the continuation of feedwater flow following a main stream line break (MSLB) inside the containment. Krsko power plant already experienced problems with main feedwater control valves. For that reason, analysis of MSLB has been performed taking into account continuous feedwater addition scenario and different containment safety systems capabilities availability. Steam and water released into the containment during MSLB was calculated using RELAP5/MOD2 computer code. The containment response to MSLB was calculated using CONTEMPT-LT/028 computer code. The results indicated that the continuous feedwater flow following a MSLB could lead to beyond design containment pressure. The peak pressure and temperature depend on isolation time for main- and auxiliary-feedwater supply. In the case of low boron concentration injection, the core recriticality is characteristic for this type of accidents. It was concluded that the presented analysis of MSLB with continuous feedwater addition scenario is the worst case for containment design

CERN's new Career Structure Main Changes in a Nutshell

CERN Multimedia

2001-01-01

All Staff Members will have received an official notification of their position in the new career path structure, with effect from 1 September 2001. A Weekly Bulletin announcement two weeks ago (Bulletin 33/2001) referred to documents and contacts for individual or general information, notably via the HR Division Web site (see below). The present article summarises the main changes between the MOAS and the MAPS (Merit Advancement and Promotion Scheme). The aim of MAPS is to make the career structure more dynamic, while retaining positive elements of the MOAS scheme, notably an annual interview and performance assessment process. The main changes are: - Career reviews including salary band promotion at several stages in a person's career replace the previous automatic grade-to-grade progression within a career path. - Speeds of advancement can be modulated to a greater extent. - The exceptional advancement zone is re-designed. - Premiums or allowances linked to performance, responsibility, and specific labou...

Quality control of three main materials for civil construction of nuclear power plant

International Nuclear Information System (INIS)

Wang Feng

2011-01-01

The construction and operation of nuclear power plant is a systematic engineering. To ensure quality and safety of nuclear power plants, each work from design to operation can have certain impact on the quality and safety of the project. The quality of each related work shall be controlled. Starting from the quality control over raw materials for the civil construction of nuclear power plant, this article mainly analyzes how to control the quality and manage the three main materials of steel, concrete and modular parts in the civil construction. (author)

New generation main control room of enhanced safety NPP with MKER reactor

International Nuclear Information System (INIS)

Golovanev, V.E.; Gorelov, A.I.; Proshin, V.A.

1994-01-01

Russia is planning to begin the gradual substitution RMBK NPP units, whose resources were worked out itself, to NPP units with a 800 MW multiloop boiling water power reactor (MKER-800) enhanced safety at next ten-year period. Main drawbacks of RBMK Reactor were completely removed in design of MKER-800 reactor. Moreover some special decisions were made to give MKER-800 self-safety properties. The proposed design of the MKER-800 enhanced safety reactor is not only fully free from the drawbacks of the RBMK reactors, but also show a number of advantages of channel-type reactors. This Paper presents some preliminary proposals of MCR Design, that developed Research and Development Institute of Power Energy (RDIPE). 6 refs, 2 figs

Design of a Construction Safety Training System using Contextual Design Methodology

OpenAIRE

Baldev, Darshan H.

2006-01-01

In the U.S., the majority of construction companies are small companies with 10 or fewer employees (BLS, 2004). The fatality rate in the construction industry is high, indicating a need for implementing safety training to a greater extent. This research addresses two main goals: to make recommendations and design a safety training system for small construction companies, and to use Contextual Design to design the training system. Contextual Design was developed by Holtzblatt (Beyer and Holtzb...

Management of radioactive effluents from research Reactors and PHWRs

International Nuclear Information System (INIS)

Bodke, S.B.; Surender Kumar; Sinha, P.K.; Budhwar, R.K.; Raj, Kanwar

2006-01-01

Indian nuclear power programme is mainly based on pressurized heavy water reactors (PHWRs). In addition we have research reactors namely Apsara, CIRUS, Dhruva at Trombay. The operation and maintenance activities of these reactors generate radioactive liquid waste. These wastes require effective management so that the release of radioactivity to the environment is well within the authorized limits. India is self reliant in the design, erection, commissioning and operation of effluent management system for nuclear reactors. Segregation at source based on nature of effluents and radioactivity content is the first and foremost step in the over all management of liquid effluents. The effluents from the power reactors contain mainly activation products like 3 H. It also contains fission products like 137 Cs. Containment of these radionuclide along with 60 Co, 90 Sr, 131 I plays an important part in liquid waste management. Treatment processes for decontamination of these radionuclide include chemical treatment, ion exchange, evaporation etc. Effluents after treatment are monitored and discharged to the nearby water body after filtration and dilution. The concentrates from the processes are conditioned in cement matrix and disposed in Near Surface Disposal Facilities (NSDFs) co-located at each site. Some times large quantity of effluents with higher radioactivity concentration may get generated from the abnormal operation such as failure of heat exchangers. These effluents are handled on a campaign basis for which adequate storage capacity is provided. The treatment is given taking into consideration the required decontamination factor (DF), capacities of available treatment process, discharge limits and the availability of the dilution water. Similarly large quantities of effluents may get generated during fuel clad failure incident in reactors. In such situation, as in CIRUS large volume of effluent containing higher radioactivity are generated and are managed by delay

The main ring polarimeter at KEK 12 GeV PS

International Nuclear Information System (INIS)

Sato, Hikaru; Hiramatsu, Shigenori; Toyama, Takeshi; Arakawa, Dai; Sakamoto, Hiroshi; Imai, Ken-ichi; Tamura, Norio.

1984-03-01

An internal polarimeter was constructed to detect the beam polarization from T sub(P) = 500 MeV to 12 GeV. The polarimeter was installed in the main ring of KEK proton synchrotron and successfully used for the measurement of the beam polarization at 500 MeV in order to study depolarizing resonances during acceleration in the booster synchrotron. We report the design and the performance of the polarimeter and the results of the first measurement. (author)

Main issues of the licensing of the Creys-Malville's LMFBR

International Nuclear Information System (INIS)

Natta, M.; Dufresne, J.; Jaffres, R.; Meyer-Heine, A.; Orzoni, G.

1986-06-01

This report presents the main features of general interest concerning the licensing procedures, procedures which are still in progress. The design studies and the construction of the Creys-Malville power plant were submitted to several assessments which allowed to verify the correct realisation of the plant and to intervene in due time on important issues. All related aspects of the start-up tests are followed by the safety authorities in satisfactory conditions without increasing significantly the applicant own duties

Main Memory

NARCIS (Netherlands)

P.A. Boncz (Peter); L. Liu (Lei); M. Tamer Özsu

2008-01-01

htmlabstractPrimary storage, presently known as main memory, is the largest memory directly accessible to the CPU in the prevalent Von Neumann model and stores both data and instructions (program code). The CPU continuously reads instructions stored there and executes them. It is also called Random

A 2 MW, 170 GHz coaxial cavity gyrotron - experimental verification of the design of main components

Energy Technology Data Exchange (ETDEWEB)

Piosczyk, B [Forschungszentrum Karlsruhe, Association EURATOM-FZK, Institut fuer Hochleistungsimpuls- und Mikrowellentechnik (IHM), Postfach 3640, D-76021 Karlsruhe (Germany); Dammertz, G [Forschungszentrum Karlsruhe, Association EURATOM-FZK, Institut fuer Hochleistungsimpuls- und Mikrowellentechnik (IHM), Postfach 3640, D-76021 Karlsruhe (Germany); Dumbrajs, O [Department of Engineering Physics and Mathematics, Helsinki University of Technology, Association EURATOM-TEKES, FIN-02150 Espoo (Finland)] (and others)

2005-01-01

A 2 MW, CW, 170 GHz coaxial cavity gyrotron is under development in cooperation between European Research Institutions (FZK Karlsruhe, CRPP Lausanne, HUT Helsinki) and the European tube industry (TED, Velizy, France). The design of critical components has recently been examined experimentally at FZK Karlsruhe with a short pulse ({approx} few ms) coaxial cavity gyrotron. This gyrotron uses the same cavity and the same quasioptical (q.o.) RF-output system as designed for the industrial prototype and a very similar electron gun.

Main Propulsion Test Article (MPTA)

Science.gov (United States)

Snoddy, Cynthia

2010-01-01

Scope: The Main Propulsion Test Article integrated the main propulsion subsystem with the clustered Space Shuttle Main Engines, the External Tank and associated GSE. The test program consisted of cryogenic tanking tests and short- and long duration static firings including gimbaling and throttling. The test program was conducted on the S1-C test stand (Position B-2) at the National Space Technology Laboratories (NSTL)/Stennis Space Center. 3 tanking tests and 20 hot fire tests conducted between December 21 1 1977 and December 17, 1980 Configuration: The main propulsion test article consisted of the three space shuttle main engines, flightweight external tank, flightweight aft fuselage, interface section and a boilerplate mid/fwd fuselage truss structure.

The booster linac of the Sparkle Company 18 MeV Cyclotron: main design elements

International Nuclear Information System (INIS)

Picardi, L.; Ronsivalle, C.

2009-01-01

The Sparkle Company (Casarano, Le) that is setting up a centre for production and research on radioisotopes for medical use, has requested to the ENEA Accelerator Laboratory a specific design of a linear accelerator for boosting the energy of its commercial cyclotron from 18 to 24 MeV, with the aim of implementing a small proton irradiation facility for radiobiology studies. This is the first case of coupling a cyclotron beam to a linac, that, if successful, can give rise to a new class of accelerators for proton therapy. The linac can accelerate only a very small portion of the cyclotron beam, due to the intrinsic mismatching of the two kind of accelerators both in the vertical and in the longitudinal phase planes. A beam transport line has been studied that besides matching at best the beam to the linac in the transverse plane, is equipped with a chopping system to lower drastically the primary beam power in order to protect the linac structure. The linac is SCDTL type, and operates at 3 GHz. In the following the results of the design are presented. [it

Parametric Design Strategies for Collaborative Urban Design

DEFF Research Database (Denmark)

Steinø, Nicolai; Yıldırım, Miray Baş; Özkar, Mine

2013-01-01

to the collaboration between professionals, participation by different non-professional stakeholders, such as residents, local authorities, non-governmental organizations and investors, is another important component of collaborative urban design processes. The involvement of community in decision making process...... implications of planning and design decisions, unless they are presented with relatively detailed architectural models, whether physical or virtual. This however, typically presents steep demands in terms of time and resources. As a foundation for our work with parametric urban design lies the hypothesis...... to solve different scripting challenges. The paper is organized into an introduction, three main sections and closing section with conclusions and perspectives. The first section of the paper gives a theoretical discussion of the notion of collaborative design and the challenges of collaborative urban...

Safety criteria for the future LMFBR's in France and main safety issues for the rapide 1500 project

International Nuclear Information System (INIS)

Justin, F.; Natta, M.; Orzoni, G.

1985-04-01

The main safety criteria for future LMFBR in France and the related issues for the RAPIDE 1500 project are presented and discussed. The evolutions with respect to SUPERPHENIX options and requirements are emphasized, in particular for the concerns of the prevention of core melt accidents, fuel damage limits and related required performances of the protection system, since one main option is not to consider whole core melt accidents in the containment design. One shall also point out the advantages of some mitigating features which were nevertheless added in the containment design, although without any explicit consideration for core melt accidents

Long-Range Untethered Real-Time Live Gas Main Robotic Inspection System

Energy Technology Data Exchange (ETDEWEB)

Hagen Schempf; Daphne D' Zurko

2004-10-31

Under funding from the Department of Energy (DOE) and the Northeast Gas Association (NGA), Carnegie Mellon University (CMU) developed an untethered, wireless remote controlled inspection robot dubbed Explorer. The project entailed the design and prototyping of a wireless self-powered video-inspection robot capable of accessing live 6- and 8-inch diameter cast-iron and steel mains, while traversing turns and Ts and elbows under real-time control with live video feedback to an operator. The design is that of a segmented actively articulated and wheel-leg powered robot design, with fisheye imaging capability and self-powered battery storage and wireless real-time communication link. The prototype was functionally tested in an above ground pipe-network, in order to debug all mechanical, electrical and software subsystems, and develop the necessary deployment and retrieval, as well as obstacle-handling scripts. A pressurized natural gas test-section was used to certify it for operation in natural gas at up to 60 psig. Two subsequent live-main field-trials in both cast-iron and steel pipe, demonstrated its ability to be safely launched, operated and retrieved under real-world conditions. The system's ability to safely and repeatably exidrecover from angled and vertical launchers, traverse multi-thousand foot long pipe-sections, make T and varied-angle elbow-turns while wirelessly sending live video and handling command and control messages, was clearly demonstrated. Video-inspection was clearly shown to be a viable tool to understand the state of this critical buried infrastructure, irrespective of low- (cast-iron) or high-pressure (steel) conditions. This report covers the different aspects of specifications, requirements, design, prototyping, integration and testing and field-trialing of the Explorer platform.

Main Power Distribution Unit for the Jupiter Icy Moons Orbiter (JIMO)

Science.gov (United States)

Papa, Melissa R.

2004-01-01

Around the year 2011, the Jupiter Icy Moons Orbiter (JIMO) will be launched and on its way to orbit three of Jupiter s planet-sized moons. The mission goals for the JIMO project revolve heavily around gathering scientific data concerning ingredients we, as humans, consider essential: water, energy and necessary chemical elements. The JIM0 is an ambitious mission which will implore propulsion from an ION thruster powered by a nuclear fission reactor. Glenn Research Center is responsible for the development of the dynamic power conversion, power management and distribution, heat rejection and ION thrusters. The first test phase for the JIM0 program concerns the High Power AC Power Management and Distribution (PMAD) Test Bed. The goal of this testing is to support electrical performance verification of the power systems. The test bed will incorporate a 2kW Brayton Rotating Unit (BRU) to simulate the nuclear reactor as well as two ION thrusters. The first module of the PMAD Test Bed to be designed is the Main Power Distribution Unit (MPDU) which relays the power input to the various propulsion systems and scientific instruments. The MPDU involves circuitry design as well as mechanical design to determine the placement of the components. The MPDU consists of fourteen relays of four different variations used to convert the input power into the appropriate power output. The three phase system uses 400 Vo1ts(sub L-L) rms at 1000 Hertz. The power is relayed through the circuit and distributed to the scientific instruments, the ION thrusters and other controlled systems. The mechanical design requires the components to be positioned for easy electrical wiring as well as allowing adequate room for the main buss bars, individual circuit boards connected to each component and power supplies. To accomplish creating a suitable design, AutoCAD was used as a drafting tool. By showing a visual layout of the components, it is easy to see where there is extra room or where the

A main amplifier circuit and data acquisition system for charged particle detector array

International Nuclear Information System (INIS)

Hao Rui; Ge Yucheng

2011-01-01

The charged particle detector array has huge amounts of signal and needs high counting rate. To meet the requirements, a main amplifier and analog-to-digital conversion circuit based on high-speed op-amp chips and ADC chip was designed. A 51-MCU was used to control the circuit of ADC and the USB communication chip. The signals were digitized and uploaded by the MCU-ADC-USB circuit. The whole system has a compact hardware structure and a reasonable controlling software, which meet the design requirements. (authors)

High resolution ADC interface to main magnet power supply at the NSLS

International Nuclear Information System (INIS)

Bordoley, M.

1993-01-01

Previous readings of DCCT were limited to 11 bits of resolution with large offsets and drifts, providing inaccurate data. The current design overcomes this limitation by using Analog Device's AD7703 20 bit serial output ADC to digitize the main magnet DCCT at the power supply, and transmit the data serially at 2KHz over to the VME controller

Designing Inclusive Systems Designing Inclusion for Real-world Applications

CERN Document Server

Clarkson, John; Robinson, Peter; Lazar, Jonathan; Heylighen, Ann

2012-01-01

The Cambridge Workshops on Universal Access and Assistive Technology (CWUAAT) are a series of workshops held at a Cambridge University College every two years. The workshop theme: “Designing inclusion for real-world applications” refers to the emerging potential and relevance of the latest generations of inclusive design thinking, tools, techniques, and data, to mainstream project applications such as healthcare and the design of working environments. Inclusive Design Research involves developing tools and guidance enabling product designers to design for the widest possible population, for a given range of capabilities. There are five main themes: •Designing for the Real-World •Measuring Demand And Capabilities •Designing Cognitive Interaction with Emerging Technologies •Design for Inclusion •Designing Inclusive Architecture In the tradition of CWUAAT, we have solicited and accepted contributions over a wide range of topics, both within individual themes and also across the workshop’s scope. ...

A prototype cavity beam position monitor for the CLIC Main Beam

CERN Document Server

Cullinany , F; Joshi, N; Lyapin, A; Bastard, D; Calvo, E; Chritin, N; Guillot-Vignot, F; Lefevre, T; Søby, L; Wendt, M; Lunin, A; Yakovlev, V P; Smith, S

2012-01-01

The Compact Linear Collider (CLIC) places unprecedented demands on its diagnostics systems. A large number of cavity beam position monitors (BPMs) throughout the main linac and beam delivery system (BDS) must routinely perform with 50 nm spatial resolution. Multiple position measurements within a single 156 ns bunch train are also required. A prototype low-Q cavity beam position monitor has been designed and built to be tested on the CLIC Test Facility (CTF3) probe beam. This paper presents the latest measurements of the prototype cavity BPM and the design and simulation of the radio frequency (RF) signal processing electronics with regards to the final performance. Installation of the BPM in the CTF3 probe beamline is also discussed.

SSC design update

International Nuclear Information System (INIS)

Syphers, M.J.

1992-11-01

Recent developments in the design and construction of the SSC are presented. Topics include status of the 20 TeV Collider rings, including interaction regions, utility regions, and main arcs, plus some remarks on the injector accelerators. Remaining issues facing the design of the colliding beams synchrotron and its injectors are discussed

Urban Design - Architectural Workshop Nova Gorica

Directory of Open Access Journals (Sweden)

Anja Planišček

2012-01-01

Full Text Available The workshop ran through the 2008-09 academic year. The main themes were a thorough design of Magistrala, the main city street, and research of the spatial and programmatic development alongside it. The research was based on the original urban plan of Nova Gorica designed by architect Edvard Ravnikar in 1949.The workshop was divided into two phases. In the first phase, students researched the possibilities of an overall design for Magistrala (traffic arrangement, relations between built and vacant space, green spaces, public and private domain etc.. In the second phase, they proposed urban architectural interventions in the open spaces along Magistrala (university campus in the northern part of the city, student housing, residential areas, main square, law court, hotel etc..

SWR 1000: the main design features of the advanced boiling water reactor with passive safety systems

International Nuclear Information System (INIS)

Carsten, Pasler

2007-01-01

The SWR-1000 (1000 MW) is a boiling water reactor whose economic efficiency in comparison with large-capacity designs is achieved by deploying very simple passive safety equipment, simplified systems for plant operation, and a very simple plant configuration in which systems engineering is optimized and dependence on electrical and instrumentation and control systems is reduced. In addition, systems and components that require protection against natural and external man-made hazards are accommodated in such a way that as few buildings as possible have to be designed to withstand the loads from such events. The fuel assemblies have been enlarged from a 10*10 rod array to a 12*12 array. This reduces the total number of fuel assemblies in the core and thus also the number of control rods and control rod drives, as well as in-core neutron flux monitors. The design owes its competitiveness to the fact that investment costs, maintenance costs and fuel cycle costs are all lower. In addition, refueling outages are shorter, thanks to the reduced scope of outage activities. The larger fuel assemblies have been extensively and successfully tested, as have all of the other new components and systems incorporated into the plant design. As in existing plants, the forced coolant circulation method is deployed, ensuring problem-free startup, and enabling plant operators to adjust power rapidly in the high power range (70%-100%) without moving the control rods, as well as allowing spectral-shift and stretch-out operation. The plant safety concept is based on a combination of passive safety systems and a reduced number of active safety systems. All postulated accidents can be controlled using passive systems alone. Control of a postulated core melt accident is assured with considerable safety margins thanks to passive flooding of the containment for in-vessel melt retention. The SWR-1000 is compliant with international nuclear codes and standards, and is also designed to withstand

ECO DESIGN IN DESIGN PROCESS

Directory of Open Access Journals (Sweden)

PRALEA Jeni

2014-05-01

Full Text Available Eco-design is a new domain, required by the new trends and existing concerns worldwide, generated by the necessity of adopting new design principles. New design principles require the designer to provide a friendly relationship between concept created, environment and consume. This "friendly" relationship should be valid both at present and in the future, generating new opportunities for product, product components or materials from which it was made. Awareness, by the designer, the importance of this new trend, permits the establishment of concepts that have as their objective the protection of present values and ensuring the legacy of future generations. Ecodesig, by its principles, is involved in the design process, from early stage, the stage of product design. Priority objective of the designers will consist in reducing the negative effects on the environment through the entire life cycle and after it is taken out of use. The main aspects of the eco-design will consider extending product exploitation, make better use of materials, reduction of emission of waste. The design process in the "eco"domein must be started by selecting the function of the concept, materials and technological processes, causing the shape of macro and micro geometric of the product through an analysis that involves optimizing and streamlining the product. This paper presents the design process of a cross-sports footwear concept, built on the basis of the principles of ecodesign

Study on ventilation and noise reduction in the main transformer room in indoor substation

Directory of Open Access Journals (Sweden)

Hu Sheng

2016-01-01

Full Text Available The noise emission should be considered in the ventilation and cooling design for the main transformer room of indoor substation. In this study, based on Soundplan software, effects of four common ventilation and cooling schemes on the cooling and sound insulation were compared. The research showed that the region with low noise requirement, the ventilation could be set on the outer wall or on the door of the main transformer room, while the region with high noise requirement, air inlet muffler or ventilation through the cable interlayer under the main transformer room must be used. All of the four kinds of ventilation schemes, ventilation through the cable interlayer is the best in cooling and noise reduction.

Design and Manufacture of the Superconducting Bus-bars for the LHC Main Magnets

CERN Document Server

Belova, L M; Perinet-Marquet, J L; Ivanov, P; Urpin, C

2002-01-01

The main magnets of the LHC are series-connected electrically in different powering circuits by means of superconducting bus-bars, carrying a maximum current of 13 kA. These superconducting bus-bars consist of a superconducting cable thermally and electrically coupled to a copper profile all along the length. The function of the copper profile is essentially to provide an alternative path for the current in case the superconducting cable loses its superconducting state and returns to normal state because of a transient disturbance or of a normal zone propagation coming from the neighbouring magnets. When a superconducting bus-bar quenches to normal state its temperature must always stay below a safe values of about 100°C while the copper is conducting. When a resistive transition is detected, the protection systems triggers the ramping down of the current from 13000 A to 0. The ramp rate must not exceed a maximum value to avoid the transition of magnets series-connected in the circuit. This paper concerns th...

The upgraded data acquisition system for beam loss monitoring at the Fermilab Tevatron and Main Injector

International Nuclear Information System (INIS)

Baumbaugh, A.; Briegel, C.; Brown, B.C.; Capista, D.; Drennan, C.; Fellenz, B.; Knickerbocker, K.; Lewis, J.D.; Marchionni, A.; Needles, C.; Olson, M.

2011-01-01

A VME-based data acquisition system for beam-loss monitors has been developed and is in use in the Tevatron and Main Injector accelerators at the Fermilab complex. The need for enhanced beam-loss protection when the Tevatron is operating in collider-mode was the main driving force for the new design. Prior to the implementation of the present system, the beam-loss monitor system was disabled during collider operation and protection of the Tevatron magnets relied on the quench protection system. The new Beam-Loss Monitor system allows appropriate abort logic and thresholds to be set over the full set of collider operating conditions. The system also records a history of beam-loss data prior to a beam-abort event for post-abort analysis. Installation of the Main Injector system occurred in the fall of 2006 and the Tevatron system in the summer of 2007. Both systems were fully operation by the summer of 2008. In this paper we report on the overall system design, provide a description of its normal operation, and show a number of examples of its use in both the Main Injector and Tevatron.

ELECTRO-THERMAL AND MECHANICAL VALIDATION EXPERIMENT ON THE LHC MAIN BUSBAR SPLICE CONSOLIDATION

CERN Document Server

Willering, GP; Bourcey, N; Bottura, L; Charrondiere, M; Cerqueira Bastos, M; Deferne, G; Dib, G; Giloux, Chr; Grand-Clement, L; Heck, S; Hudson, G; Kudryavtsev, D; Perret, P; Pozzobon, M; Prin, H; Scheuerlein, Chr; Rijllart, A; Triquet, S; Verweij, AP

2012-01-01

To eliminate the risk of thermal runaways in LHC interconnections a consolidation by placing shunts on the main bus bar interconnections is proposed by the Task Force Splices Consolidation. To validate the design two special SSS magnet spares are placed on a test bench in SM-18 to measure the interconnection in between with conditions as close as possible to the LHC conditions. Two dipole interconnections are instrumented and prepared with worst-case-conditions to study the thermo-electric stability limits. Two quadrupole interconnections are instrumented and prepared for studying the effect of current cycling on the mechanical stability of the consolidation design. All 4 shunted interconnections showed very stable behaviour, well beyond the LHC design current cycle.

Measurements of Gun Tube Motion and Muzzle Pointing Error of Main Battle Tanks

Directory of Open Access Journals (Sweden)

Peter L. McCall

2001-01-01

Full Text Available Beginning in 1990, the US Army Aberdeen Test Center (ATC began testing a prototype cannon mounted in a non-armored turret fitted to an M1A1 Abrams tank chassis. The cannon design incorporated a longer gun tube as a means to increase projectile velocity. A significant increase in projectile impact dispersion was measured early in the test program. Through investigative efforts, the cause of the error was linked to the increased dynamic bending or flexure of the longer tube observed while the vehicle was moving. Research and investigative work was conducted through a collaborative effort with the US Army Research Laboratory, Benet Laboratory, Project Manager – Tank Main Armament Systems, US Army Research and Engineering Center, and Cadillac Gage Textron Inc. New test methods, instrumentation, data analysis procedures, and stabilization control design resulted through this series of investigations into the dynamic tube flexure error source. Through this joint research, improvements in tank fire control design have been developed to improve delivery accuracy. This paper discusses the instrumentation implemented, methods applied, and analysis procedures used to characterize the tube flexure during dynamic tests of a main battle tank and the relationship between gun pointing error and muzzle pointing error.

Development of manufacturing technology and fabrication of prototype for main coolant pump

Energy Technology Data Exchange (ETDEWEB)

Chung, Koon Seok; Han, C.K.; Chei, J.M.; Chung, K.S.; Youn, M.H.; Shin, S.A.; Choi, D.J.; Kim, H.C. [HALLA Industrial Co., Ltd., Pusan (Korea)

1999-03-01

This study presents the development of the manufacturing technology for the Main Coolant Pump of the SMART. This report contains the followings; (1) Select axial type pump for the MCP (2) MCP is drived by squirrel-cage induction motor that consisted canned motor type. (3) MCP shaft has three horizontal and one vertical support bearings. (4) Design of several part of the MCP (5) Manufacturing of the performance test motor (6) Design and manufacturing of the speed sensor (7) Procedures for three-axial and five-axial M.C.T., Tig welding and Electron Beam Welding were developed. (8) Conceptional design of the MCP test facility for the performance test under operating conditions. (9) Results of standard weld test specimens according to the ASME section IX. (author). 21 refs., 35 figs., 10 tabs.

Study of an electromagnetic pump applied to a primary main pump of a large scale sodium cooled reactor

International Nuclear Information System (INIS)

Aizawa, Kosuke; Kotake, Shoji; Chikazawa, Yoshitaka; Ara, Kuniaki; Araseki, Hideo; Aizawa, Rie; Ota, Hiroyuki

2009-01-01

This paper describes a future innovative design options with a parallel electromagnetic pump (EMP) system as the main circulating pump of the JSFR design. A conceptual design of EMPs integrated with an intermediate heat exchanger (IHX) is carried out. The major design parameters are consistent with the current JSFR design, where the main flow rate is 630 m 3 /min and the flow halving time is the same of the mechanical pump with the similar reliability. As a result of several design studies, a five parallel EMPs with IHX system has been selected from the geometry suitability for JSFR design. The EMP advantages comparing with mechanical pumps are investigated from the views of in-service inspection, maintenance and reliability. Numerical analysis with two dimensional MHD codes is conducted on a former experiment of a 160 m 3 /min flow rate EMP. The overall trend of the experimental data and the numerical results agrees with that in small-scale EMPs. However, the difference between the experimental data and the numerical results seems larger compared with the small-scale EMPs, which comes from large magnetic Reynolds number and interaction parameter of 160 m 3 /min EMP. (author)

Application of the reliability theory on the analysis of the effects of sbwr' main control console maintenance

International Nuclear Information System (INIS)

Widagdo, S.

1997-01-01

Maintenance activities on the main control console, which is a primary element of the man-machine interface system, are a source of concern. this concern has been arisen since the main control function is the central part to observe and control the reactor operation. the paper will discuss a study of the effects of main control console maintenance activity upon the operability of SBWR. the first step is learning the SBWR main control room design in order to know its monitoring and controlling capability and then makes an assumption of maintenance requirement followed by an evaluation of the effects of the maintenance activity. it is assumed that 2 years or equivalent to 17.520 hours are the reference time for one cycle operation of SBWR. the aim is to identify any adverse effects and eliminate or minimize them through design improvements. the evaluation method used here is the reability theory R(t) = e sup-λt. Based on the result of the evaluation can be concluded that there are no negative effects of maintenance activity upon the operability of the SBWR

Deliberately by design, or ?

DEFF Research Database (Denmark)

Møller, Charles; Brandt, Charlotte; Carugati, Andrea

2012-01-01

, this article sets the stage to investigate in detail the case of EA transformation at Arla Foods. The main goal with this article is to delineate a research design to uncover the transformation process from three perspectives: Design thinking, Institutional theory, and Sociomateriality....

Deliberately by Design, Or?

DEFF Research Database (Denmark)

Møller, Charles; Brandt, Charlotte J; Carugati, Andrea

2011-01-01

, this article sets the stage to investigate in detail the case of EA transformation at Arla Foods. The main goal with this article is to delineate a research design to uncover the transformation process from three perspectives: Design thinking, Institutional theory, and Sociomateriality....

46 CFR 58.05-1 - Material, design and construction.

Science.gov (United States)

2010-10-01

... 46 Shipping 2 2010-10-01 2010-10-01 false Material, design and construction. 58.05-1 Section 58.05... AUXILIARY MACHINERY AND RELATED SYSTEMS Main Propulsion Machinery § 58.05-1 Material, design and construction. (a) The material, design, construction, workmanship, and arrangement of main propulsion machinery...

Design of the control room of the N4-type PWR: main features and feedback operating experience

International Nuclear Information System (INIS)

Peyrouton, J.M.; Guillas, J.; Nougaret, Ch.

2004-01-01

This article presents the design, specificities and innovating features of the control room of the N4-type PWR. A brief description of control rooms of previous 900 MW and 1300 MW -type PWR allows us to assess the change. The design of the first control room dates back to 1972, at that time 2 considerations were taken into account: first the design has to be similar to that of control rooms for thermal plants because plant operators were satisfied with it and secondly the normal operating situation has to be privileged to the prejudice of accidental situations just as it was in a thermal plant. The turning point was the TMI accident that showed the weight of human factor in accidental situations in terms of pilot team, training, procedures and the ergonomics of the work station. The impact of TMI can be seen in the design of 1300 MW-type PWR. In the beginning of the eighties EDF decided to launch a study for a complete overhaul of the control room concept, the aim was to continue reducing the human factor risk and to provide a better quality of piloting the plant in any situation. The result is the control room of the N4-type PWR. Today the cumulated feedback experience of N4 control rooms represents more than 20 years over a wide range of situations from normal to incidental, a survey shows that the N4 design has fulfilled its aims. (A.C.)

High resolution ADC interface to main magnet power supply at the NSLS

Energy Technology Data Exchange (ETDEWEB)

Bordoley, M.

1993-07-01

Previous readings of DCCT were limited to 11 bits of resolution with large offsets and drifts, providing inaccurate data. The current design overcomes this limitation by using Analog Device`s AD7703 20 bit serial output ADC to digitize the main magnet DCCT at the power supply, and transmit the data serially at 2KHz over to the VME controller.

High resolution ADC interface to main magnet power supply at the NSLS

Energy Technology Data Exchange (ETDEWEB)

Bordoley, M.

1993-01-01

Previous readings of DCCT were limited to 11 bits of resolution with large offsets and drifts, providing inaccurate data. The current design overcomes this limitation by using Analog Device's AD7703 20 bit serial output ADC to digitize the main magnet DCCT at the power supply, and transmit the data serially at 2KHz over to the VME controller.

Experimental simulation study on hydraulic behavior of the main heat exchanger of Daqing 200 MW nuclear heating reactor

International Nuclear Information System (INIS)

Jiang Shengyao; Zhang Youjie; Jia Haijun; Bo Jinhai; Hong Liuming; Bo Hanliang; Liu Zhiyong

1997-07-01

The hydraulic behavior of the main heat exchanger of Daqing 200 MW nuclear heating reactor is studied through a 1:2.33 test model. The design and other feature of the test model is described. The experimental results show that the flow resistance coefficient of the heat exchanger becomes self-simulation when Reynolds number is greater than 5000. The value of flow resistance coefficient at self-simulation condition and the distribution of pressure drop in the heat exchanger are given through experiment. The option design to reduce flow resistance is proposed. The designed and experimental value for the flow resistance coefficient are in good agreement. The variation of system parameters during flow excursion was described. The experimental results are of great significant for the final design of the main heat exchanger of Daqing 200 MW nuclear heating reactor. (2 refs., 5 figs., 1 tab.)

Main maintenance operations for Test Blanket Systems in ITER TBM port cells

Energy Technology Data Exchange (ETDEWEB)

Pascal, R., E-mail: romain.pascal@iter.org [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Cortes, P.; Friconneau, J.-P.; Giancarli, L.M.; Gotewal, K.K.; Iseli, M.; Kim, B.Y.; Levesy, B.; Martins, J.-P.; Merola, M. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Nevière, J.-C. [Comex-Nucleaire, 13115 Saint Paul Lez Durance (France); Patisson, L. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Siarras, A. [Sogetti, Parc de la Duranne, 13857 Aix-en-Provence (France); Tesini, A. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France)

2013-10-15

Highlights: • The Test Blanket System components layout in Port Cell room is described. • The maintenance of the two Test Blanket Systems in ITER port cell is addressed. • The overall replacement/maintenance strategy is defined. • The main maintenance tasks of the systems are discussed. • The maintenance strategy and required tools are presented. -- Abstract: Each Test Blanket System in ITER is formed by an in-vessel component, the Test Blanket Module, and several associated ancillary systems (coolant and Tritium systems, instrumentation and control systems). The paper describes the overall replacement/maintenance strategy and the main maintenance tasks that have to be considered in the design of the systems. It shows that there are no critical issues.

Design considerations for a Space Shuttle Main Engine turbine blade made of single crystal material

Science.gov (United States)

Abdul-Aziz, A.; August, R.; Nagpal, V.

1993-01-01

Nonlinear finite-element structural analyses were performed on the first stage high-pressure fuel turbopump blade of the Space Shuttle Main Engine. The analyses examined the structural response and the dynamic characteristics at typical operating conditions. Single crystal material PWA-1480 was considered for the analyses. Structural response and the blade natural frequencies with respect to the crystal orientation were investigated. The analyses were conducted based on typical test stand engine cycle. Influence of combined thermal, aerodynamic, and centrifugal loadings was considered. Results obtained showed that the single crystal secondary orientation effects on the maximum principal stresses are not highly significant.

Introduction to (participatory) design games

DEFF Research Database (Denmark)

Brandt, Eva

2014-01-01

This article gives an introduction to (participatory) design games in three rounds. Firstly it argues that designing design games is a particular and very productive genre for formatting participation and design dialogues during ongoing design projects. Secondly it presents some of the main contr...... contributions to the development of design games in a historical perspective, and thirdly it introduces three recent PhD dissertations that all but in very different ways have investigated design games in more detail....

ROKCY-12 (KCCH PET-dedicated cyclotron): main features and improvements

International Nuclear Information System (INIS)

Chai, J. S.; Kim, Y. S.; Yang, Y. T.; Jung, I. S.; Hong, S. S.; Lee, M. Y.; Jang, H. S.; Kim, J. H.

2002-01-01

In this paper, we describe the development of 13 MeV cyclotron (ROKCY-12) that can be used for a Position Emission Tomography(PET) purpose. This cyclotron with a maximum beam energy of 13 MeV can produce radio isotopes especially 18 F which has a relatively short half lifetime of 110 minutes. First, we show the beam characteristics can be used to carry out the operation of ROCKY-12. Based on this, a computer program has been developed to determine main cyclotron parameters such as cyclotron magnet, RF system, ion source, vacuum system and other cyclotron operation parameters. And then we show the result of design and manufacturing feature of ROKCY-12. By using this design program, one can determines magnet yoke geometry and the average magnetic fields etc. And then the three-dimensional computer program OPERA-3D has been invoked to determine magnet pole tips. Validity of the design can be seen by investigating magnetic fields, radial and vertical focusing frequencies as a function of the beam energy. In this paper, we show the results of cyclotron beam by ROCKY-12. We designed 77.3 MHz RF system and ion source system. We tested RF resonance each coupling methods. We show the result of RF design and prototype operation. Developed ion source is PIG type. We described our design methods and implementation. We report the result of getting negative hydrogen ion. Cyclotron controller asks inputs of every sensor and output of every instrument for notifying current condition to operator. It has independent controllers, for example DC power supply, vacuum system, beam profile system, beam extraction system, RF system, ion source, cooling unit and so on. Basically, each control system uses RS-485 for communication to main control computer. Consumers reward products and services that feature quality, originality, a distinct personality and charm. The International Standardization Organization (ISO) requires, as its mission, that we achieve competitive superiority by

Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 1: Main report

International Nuclear Information System (INIS)

1994-07-01

This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR section 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE's application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design

Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 1: Main report

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design.

Design for mood : Twenty activity-based opportunities to design for mood regulation

NARCIS (Netherlands)

Desmet, P.M.A.

2015-01-01

This paper introduces a theory-based approach to design for mood regulation. The main proposition is that design can best influence mood by enabling and stimulating people to engage in a broad range of mood-regulating activities. The first part of the manuscript reviews state-of-the art mood-focused

DESIGN OPTIMIZATION OF A FOOT VALVE BY USING ANSYS®

Directory of Open Access Journals (Sweden)

Serdar KARAOĞLU

2008-02-01

Full Text Available In this study, main components of a foot valve, being produced by casting, were optimized for minimum weight. The study was focused on the minimization of casting costs by reducing the volumes of two main parts of the foot valve. ANSYS® finite elements package was used in the study. In the optimization stage, parametrical dimensions were determined according to manufacturer's design criteria and related standards. Final design of the foot valve was completed by using the calculated values of optimum dimensions of the main components. Design optimization procedure gave about 8.5% of weight reductions in the main foot valve components.

Design of a pulsed angular selective electron gun for the KATRIN main spectrometer

Energy Technology Data Exchange (ETDEWEB)

Winzen, Daniel; Hannen, Volker; Ortjohann, Hans-Werner; Zacher, Michael; Weinheimer, Christian [Institut fuer Kernphysik, Westfaelische Wilhelms-Universitaet, Muenster (Germany); Collaboration: KATRIN-Collaboration

2012-07-01

The KATRIN (KArlsruhe TRItium Neutrino mass) experiment will study the tritium {beta}-spectrum near the endpoint of 18.6 keV, aiming to measure the mass of the electron antineutrino. Using an electrostatic retarding spectrometer (MAC-E-Filter), the projected sensitivity for m{sub ve} is 200 meV/c{sup 2} at 90% C.L. In order to map out the electric and magnetic fields in the main spectrometer, an angular selective electron gun is currently being developed. The e-gun uses an UV-Laser to produce electrons via the photo-electric effect from a copper substrate which are then accelerated electrostatically. It features a small energy spread of approx. 0.1 eV, a sharp emission angle and will be able to cover the whole magnetic flux tube of KATRIN. Using a pulsed laser it is also possible to investigate the time of flight (TOF) of electrons through the spectrometer, offering enhanced sensitivity to spectrometer properties far away from the analysing plane. By comparing information from transmission function measurements and TOF data with Monte Carlo simulations of the setup, one will be able to achieve a detailed understanding of the spectrometer properties.

STORYPLY : designing for user experiences using storycraft

NARCIS (Netherlands)

Atasoy, B.; Martens, J.B.O.S.; Markopoulos, P.; Martens, J.B.; Malins, J.; Coninx, K.; Liapis, A.

2016-01-01

The role of design shifts from designing objects towards designing for experiences. The design profession has to follow this trend but the current skill-set of designers focuses mainly on objects; their form, function, manufacturing and interaction. However, contemporary methods and tools that

Design Education

DEFF Research Database (Denmark)

Brandt, Eva

2007-01-01

In resent years the two main design schools in Denmark (Danmarks Designskole and Designskolen Kolding ) undergo many changes. The overall goal for both is to obtain status as a university, and they will be evaluated in this regard in 2010. Transforming a vocational school with long handicraft...... traditions into a research based institution for higher education is demanding. Danmarks Designskole is in the middle of this process, many activities are initiated, both employees and students are involved, and from outside representatives from various design professions. The design process has many...... stakeholders with various interests and opinions. The aim it is not to design a computer system, a service or product but re-designing curriculum, work procedures, self images etc. which support educating designers of the future. This paper reports on two investigations that have been carried through as part...

PHARAO laser source flight model: Design and performances

Energy Technology Data Exchange (ETDEWEB)

Lévèque, T., E-mail: thomas.leveque@cnes.fr; Faure, B.; Esnault, F. X.; Delaroche, C.; Massonnet, D.; Grosjean, O.; Buffe, F.; Torresi, P. [Centre National d’Etudes Spatiales, 18 avenue Edouard Belin, 31400 Toulouse (France); Bomer, T.; Pichon, A.; Béraud, P.; Lelay, J. P.; Thomin, S. [Sodern, 20 Avenue Descartes, 94451 Limeil-Brévannes (France); Laurent, Ph. [LNE-SYRTE, CNRS, UPMC, Observatoire de Paris, 61 avenue de l’Observatoire, 75014 Paris (France)

2015-03-15

In this paper, we describe the design and the main performances of the PHARAO laser source flight model. PHARAO is a laser cooled cesium clock specially designed for operation in space and the laser source is one of the main sub-systems. The flight model presented in this work is the first remote-controlled laser system designed for spaceborne cold atom manipulation. The main challenges arise from mechanical compatibility with space constraints, which impose a high level of compactness, a low electric power consumption, a wide range of operating temperature, and a vacuum environment. We describe the main functions of the laser source and give an overview of the main technologies developed for this instrument. We present some results of the qualification process. The characteristics of the laser source flight model, and their impact on the clock performances, have been verified in operational conditions.

Development of motors and drives for main coolant pump and CEDM

Energy Technology Data Exchange (ETDEWEB)

Kang, Do Hyun; Ha, Hoi Doo; Park, Jung Woo; Koo, Dae Hyun; Chang, Ki Chan; Kim, Jong Moo; Kim, Won Ho; Rim, Geun Hie; Baek, Ju Won; Park, Doh Young; Hwang, Don Ha; Jeon, Jeong Woo [Korea Electrotechnology Research Institute, Changwon (Korea)

1999-03-01

A canned type 170kW induction motor for the main coolant pump (MCP) of the integral reactor SMART was designed to minimize the eddy current loss in the can and the volume of motor. In order to verify the design and analysis methodology, a canned type 30kW induction motor and an inverter were developed and tested. The motor was designed to have two poles with squirrel cage solid rotor and open slot stator. The motor driver was designed as VVVF inverter to operate both at 900(r.p.m) and at 3600(r.p.m). The calculated design values showed a good agreement with the experimental results. The measured efficiencies of the canned motor and the inverter were 70(%) and 96(%), respectively. A variable reluctance type linear pulse motor (LPM) with double air-gaps for the Control Element Drive Mechanism (CEDM) to lift 100kg was designed, analyzed, manufactured and tested. A converter and a test facility were manufactured to verity the dynamic performance of the LPM. The mover of the LPM was welded with magnetic material(SUS430) and non-magnetic material(SUS304) to get flux path between inner stator and outer stator. The measured thrust force was about 20(%) less than the designed thrust force. As for the rotary stepping motors for CEDM-II, which have transverse flux pattern, three design options were proposed with thrust force density of 8kN/m{sup 2}, 14kN/m{sup 2} and 52kN/m{sup 2} respectively. (author). 31 refs., 219 figs., 60 tabs.

Energy efficient design

International Nuclear Information System (INIS)

1991-01-01

Solar Applications and Energy Efficiency in Building Design and Town Planning (RER/87/006) is a United Nations Development Programme (UNDP) project of the Governments of Albania, Bulgaria, Cyprus, The Czech and Slovak Federal Republic, France, Hungary, Malta, Poland, Turkey, United Kingdom and Yugoslavia. The project began in 1988 and comes to a conclusion at the end of 1991. It is to enhance the professional skills of practicing architects, engineers and town planners in European countries to design energy efficient buildings which reduce energy consumption and make greater use of passive solar heating and natural cooling techniques. The United Nations Economic Commission for Europe (ECE) is the Executing Agency of the project which is implemented under the auspices of the Committee on Energy, General Energy Programme of Work for 1990-1994, sub-programme 5 Energy Conservation and Efficiency (ECE/ENERGY/15). The project has five main outputs or results: an international network of institutions for low energy building design; a state-of-the-art survey of energy use in the built environment of European IPF countries; a simple computer program for energy efficient building design; a design guide and computer program operators' manual; and a series of international training courses in participating European IPF countries. Energy Efficient Design is the fourth output of the project. It comprises the design guide for practicing architects and engineers, for use mainly in mid-career training courses, and the operators' manual for the project's computer program

Maine Field Station

Data.gov (United States)

Federal Laboratory Consortium — In 2000 NOAA's National Marine Fisheries Service established the Maine Field Station in Orono, ME to have more direct involvement in the conservation of the living...

An overview of the main design and performance of PBFA Z machine

International Nuclear Information System (INIS)

Song Shengyi

2002-01-01

PBFA Z is a new 60 TW/5 MJ electrical driver located at Sandia National Laboratories (SNL). It has been used to drive Z-pinches. The pulsed power design of PBFA Z is based on conventional single-pulse Marx generator with water-line pulse-forming technology used on the earlier Saturn and PBFA II accelerators. PBFA Z stores 11.4 MJ in its 36 Marx generators, couples 5 MJ in a 60 TW/105 ns pulse to the output water transmission lines, and delivers 3.0 MJ and 50 TW of electrical energy to the Z-pinch load. Depending on the initial load inductance and the implosion time, PBFA Z has attained peak currents of 16-20 MA with a rise time of 105 ns. Current is fed to the Z-pinch load through self-magnetically insulated transmission lines (MITLs). Peak electrical fields in the MITLs exceed 2 MV/cm. The current from the four independent conical-disk MITLs is combined together in a double post-hole vacuum convolute with an efficiency greater than 95%. SNL has achieved X-ray powers of 200TW and X-ray energies of 1.9 MJ from tungsten wire-array Z-pinch loads

An overview of the main design and performance of PBFA Z machine

CERN Document Server

Song Sheng Yi

2002-01-01

PBFA Z is a new 60 TW/5 MJ electrical driver located at Sandia National Laboratories (SNL). It has been used to drive Z-pinches. The pulsed power design of PBFA Z is based on conventional single-pulse Marx generator with water-line pulse-forming technology used on the earlier Saturn and PBFA II accelerators. PBFA Z stores 11.4 MJ in its 36 Marx generators, couples 5 MJ in a 60 TW/105 ns pulse to the output water transmission lines, and delivers 3.0 MJ and 50 TW of electrical energy to the Z-pinch load. Depending on the initial load inductance and the implosion time, PBFA Z has attained peak currents of 16-20 MA with a rise time of 105 ns. Current is fed to the Z-pinch load through self-magnetically insulated transmission lines (MITLs). Peak electrical fields in the MITLs exceed 2 MV/cm. The current from the four independent conical-disk MITLs is combined together in a double post-hole vacuum convolute with an efficiency greater than 95%. SNL has achieved X-ray powers of 200TW and X-ray energies of 1.9 MJ from...

Sequence of decommissioning of the main equipment in a central type VVER 440 V-230

International Nuclear Information System (INIS)

Andres, E.; Garcia Ruiz, R.

2014-01-01

IBERDROLA Ingenieria y Construccion S.A.U., leader of consortium with Empresarios Agrupados and INDRA, has developed the Basic Engineering for the decommissioning of contaminated systems and building of a VVER 440 V-230 Nuclear Power Plant, establishing the sequence and methodology for the main equipment fragmentation. For that, it has been designed dry and wet cutting zones to be set up in the area where steam generators, main cooling pumps and pressurizer are located; these components will be dismantled previously. (Author)

Grading efficiency in Design

NARCIS (Netherlands)

Eggink, Wouter; van der Bijl-Brouwer, Mieke; Buck, L.; . Frateur, G.; Ion, B.; McMahon, C.; Baelus, C.; de Grande, G.; Vervulgen, S.

2012-01-01

The academic world is constantly under pressure to deliver maximum output for a minimum of (public) costs. For Design education this is important, because doing Design cannot be learned from a book. As teaching costs are mainly driven by the costs of supervisors, the amount of time invested in

America Saves! Energizing Main Street's Small Businesses

Energy Technology Data Exchange (ETDEWEB)

Lindberg, James [National Trust for Historic Preservation, Washington, DC (United States)

2016-09-30

The America Saves! Energizing Main Street Small Businesses project engaged the 1,200-member National Main Street Center (NMSC) network of downtown organizations and other local, regional, and national partners to test a methodology for sharing customized energy efficiency information with owners of commercial buildings smaller than 50,000 square feet. Led by the National Trust for Historic Preservation’s Preservation Green Lab, the project marshalled local staff and volunteers to gather voluntarily-disclosed energy use information from participating businesses. This information was analyzed using a remote auditing tool (validated by the National Renewable Energy Lab) to assess energy savings opportunities and design retrofit strategies targeting seven building types (food service and sales, attached mixed-use, strip mall, retail, office, lodging, and schools). The original project design contemplated extensive leveraging of the Green Button protocol for sharing annualized utility data at a district scale. Due the lack of adoption of Green Button, the project partners developed customized approaches to data collection in each of twelve pilot communities. The project team encountered considerable challenges in gathering standardized annual utility data from local partners. After overcoming these issues, the data was uploaded to a data storehouse. Over 450 properties were benchmarked and the remote auditing tool was tested using full building profiles and utility records for more than 100 commercial properties in three of the pilot communities. The audit tool demonstrated potential for quickly capturing, analyzing, and communicating energy efficiency opportunities in small commercial buildings. However, the project team found that the unique physical characteristics and use patterns (partial vacancy, periodic intensive uses) of small commercial buildings required more trouble-shooting and data correction than was anticipated. In addition, the project revealed that

Design requirements for the SWIFT instrument

International Nuclear Information System (INIS)

Rahnama, P; McDade, I; Shepherd, G; Gault, W

2013-01-01

The Stratospheric Wind Interferometer for Transport studies (SWIFT) instrument is a proposed limb-viewing satellite instrument that employs the method of Doppler Michelson interferometry to measure stratospheric wind velocities and ozone densities in the altitude range of 15–45 km. The values of the main instrument parameters including filter system parameters and Michelson interferometer parameters are derived using simulations and analyses. The system design requirements for the instrument and spacecraft are presented and discussed. Some of the retrieval-imposed design requirements are also discussed. Critical design issues are identified. The design optimization process is described. The sensitivity of wind measurements to instrument characteristics is investigated including the impact on critical design issues. Using sensitivity analyses, the instrument parameters were iteratively optimized in order to meet the science objectives. It is shown that wind measurements are sensitive to the thermal sensitivity of the instrument components, especially the narrow filter and the Michelson interferometer. The optimized values of the main system parameters including Michelson interferometer optical path difference, instrument visibility, instrument responsivity and knowledge of spacecraft velocity are reported. This work also shows that the filter thermal drift and the Michelson thermal drift are two main technical risks. (paper)

Development of the Main Wing Structure of a High Altitude Long Endurance UAV

Science.gov (United States)

Park, Sang Wook; Shin, Jeong Woo; Kim, Tae-Uk

2018-04-01

To enhance the flight endurance of a HALE UAV, the main wing of the UAV should have a high aspect ratio and low structural weight. Since a main wing constructed with the thin walled and slender components needed for low structural weight can suffer catastrophic failure during flight, it is important to develop a light-weight airframe without sacrificing structural integrity. In this paper, the design of the main wing of the HALE UAV was conducted using spars which were composed of a carbon-epoxy cylindrical tube and bulkheads to achieve both the weight reduction and structural integrity. The spars were sized using numerical analysis considering non-linear deformation under bending moment. Static strength testing of the wing was conducted under the most critical load condition. Then, the experimental results obtained for the wing were compared to the analytical result from the non-linear finite-element analysis. It was found that the developed main wing reduced its structural weight without any failure under the ultimate load condition of the static strength testing.

Beam-induced quench test of LHC main quadrupole

CERN Document Server

Priebe, A; Dehning, B; Effinger, E; Emery, J; Holzer, E B; Kurfuerst, C; Nebot Del Busto, E; Nordt, A; Sapinski, M; Steckert, J; Verweij, A; Zamantzas, C

2011-01-01

Unexpected beam loss might lead to a transition of the accelerator superconducting magnet to a normal conducting state. The LHC beam loss monitoring (BLM) system is designed to abort the beam before the energy deposited in the magnet coils reach a quench-provoking level. In order to verify the threshold settings generated by simulation, a series of beam-induced quench tests at various beam energies has been performed. The beam losses are generated by means of an orbital bump peaked in one of main quadrupole magnets (MQ). The analysis includes not only BLM data but also the quench protection system (QPS) and cryogenics data. The measurements are compared to Geant4 simulations of energy deposition inside the coils and corresponding BLM signal outside the cryostat.

Substantiation of vibration strength of nuclear reactor and steam generator internals. Main problems

International Nuclear Information System (INIS)

Fyodorov, V.G.; Sinyavasky, V.F.

1977-01-01

The report details the scope and priority of studies necessary for substantiation of vibration strength of steam generator tube bundles and reactor fuel assemblies, and design modifications helping to reduce flow-induced vibration of the internals specified. Steam generator tube bundles are studied on the basis of a standard establishing vibration requirements at various stages of design, manufacture and operation of a steam generator at a nuclear power station. The main vibration characteristics of tubes obtained through model and full-scale tests are compared with calculation results. Results are provided concerning test-stand vibration tests of fuel elements and fuel assemblies. (author)

A kaon physics program at the Fermilab Main Injector

International Nuclear Information System (INIS)

Cooper, Peter

1997-11-01

In this paper we describe a triad of kaon experiments which will form the foundation of a kaon physics program at Fermilab in the Main Injector era. These three experiments; KAMI, CKM and CPT, span the range of experiment types discussed above. KAMI will use the existing neutral kaon beam and the KTeV detector as the basis of a search for the Standard Model ultra rare decay K L → π 0 ν anti ν decay mode is by far the theoretically cleanest measurement of the Standard Model parameter responsible for CP violation. CKM will measure the analogous charged kaon decay mode. Together these two experiments will determine the Standard Model contribution to CP violation independent of the B meson sector. The Standard Model parameters controlling CP violation must be observed to be the same in the K and B meson sectors in order to confirm the Standard Model as the sole source of CP violation in nature. CPT is a hybrid beam experiment using a high purity K + beam to produce a pure K 0 beam in order to search for violation of CPT symmetry at a mass scale up to the Planck mass. CPT also will measure new CP violation parameters to test the Standard Model and search for rare K S decays. The Fermilab infrastructure for such a physics program largely already exists. The Main Injector will be an existing accelerator by late 1998 with beam properties comparable to any of the previous ''kaon factory'' proposals. The KTeV detector and neutral kaon beamline are unsurpassed in the world and were originally designed to also operate with the 120 GeV Main Injector beam as KAMI. The Fermilab Meson laboratory was originally designed as an area for fixed target experiments using 200 GeV proton beams. The charged kaon beam experiments will naturally find a home there. Both charged kaon experiments, CKM and CPT, will share a new high purity RF separated charged kaon beam based on superconducting RF technology which will provide the highest intensity and purity charged kaon beam in the world

Design and competitive edge: A model for design management excellence in European SME's

OpenAIRE

Borja de Mozota, B

2002-01-01

This article suggests to use the conceptual model of Michael Porter Value Chain in order to integrate all the variables that explain the mechanism of value creation through design. The results of the study of 33 European SMES participating in the European Design Prize explain the role of design in the management of innovation, identify the variables that characterize design management and classify them according to the value chain concept. The main result of this research was the ...

Initial design process of the repository

International Nuclear Information System (INIS)

Osmanlioglu, A.E.

2001-01-01

The concept of the final disposal of high level wastes is to isolate the waste from the biosphere for extremely long periods of time by emplacement of wastes into deep stable geological formations. Several geological formations have been considered as candidate host environments for high level waste disposal and several techniques have been developed for repository design. In this study, interrelationships of main parameters of a general repository design have been defined and effective parameters are shown at each step. Initial design process is based on the long term stability of underground openings as disposal galleries. For this reason, this design process includes two main analyses: mechanical analysis and thermal analysis. Each of the analysis systems is directly related to each other by technical precautions. As a result of this design process, general information about the acceptable depth of the repository, layout and emplacement pattern can be taken. Final design study can be established on the result of initial design process. (author)

Robust Backstepping Control for Cold Rolling Main Drive System with Nonlinear Uncertainties

Directory of Open Access Journals (Sweden)

Xu Yang

2013-01-01

Full Text Available The nonlinear model of main drive system in cold rolling process, which considers the influence with parameter uncertainties such as clearance and variable friction coefficient, as well as external disturbance by roll eccentricity and variation of strip material quality, is built. By transformation, the lower triangular structure form of main drive system is obtained. The backstepping algorithm based on signal compensation is proposed to design a linear time-invariant (LTI robust controller, including a nominal controller and a robust compensator. A comparison with PI controller shows that the controller has better disturbance attenuation performance and tracking behaviors. Meanwhile, according to its LTI characteristic, the robust controller can be realized easily; therefore it is also appropriated to high speed dynamic rolling process.

Quits and Job Changes among Home Care Workers in Maine: The Role of Wages, Hours, and Benefits

Science.gov (United States)

Morris, Lisa

2009-01-01

Purpose: Figuring out how to make home care jobs more attractive has become a top policy priority. This study investigates the impact of wages, hours, and benefits on the retention of home care workers. Design and Methods: Using a 2-wave survey design and a sample of home care workers from Maine, the factors associated with turnover intentions,…

33 CFR 334.20 - Gulf of Maine off Cape Small, Maine; naval aircraft practice mining range area.

Science.gov (United States)

2010-07-01

... REGULATIONS § 334.20 Gulf of Maine off Cape Small, Maine; naval aircraft practice mining range area. (a) The... 33 Navigation and Navigable Waters 3 2010-07-01 2010-07-01 false Gulf of Maine off Cape Small, Maine; naval aircraft practice mining range area. 334.20 Section 334.20 Navigation and Navigable Waters...

Designing Learning Opportunities in Interaction Design: Interactionaries as a means to study and teach student design processes

Directory of Open Access Journals (Sweden)

Robert Ramberg

2013-12-01

Full Text Available Learning by practice, apprenticeship and paradigmatic examples have been prime paths for learning within interaction design. These have been criticized for being time-consuming and costly, of not being implementable in academic contexts. In this article we suggest and evaluate a pedagogical model to address these problems in design teaching and learning. Results from a time-constrained collaborative design exercise, a so-called “interactionary”, are presented. Student design work is analyzed using the framework of learning design sequences and analysis of the primary transformation unit shows that interactionaries reveal patterns in student design work. Materials are used mainly to document design ideas rather than as a design material to further investigate design ideas and aspects of interaction. In the critiquing sessions, regarded as the secondary transformation unit, many issues hardly addressed during the design work were brought up. Thus, the designers continued to develop their design proposal primed by critique presented by the reviewers. Based on the results, possible teacher interventions to coach student design work are suggested.

Design evaluation on sodium piping system and comparison of the design codes

International Nuclear Information System (INIS)

Lee, Dong Won; Jeong, Ji Young; Lee, Yong Bum; Lee, Hyeong Yeon

2015-01-01

A large-scale sodium test loop of STELLA-1 (Sodium integral effect test loop for safety simulation and assessment) with two main piping systems has been installed at KAERI. In this study, design evaluations on the main sodium piping systems in STELLA-1 have been conducted according to the DBR (design by rule) codes of the ASME B31.1 and RCC-MRx RB-3600. In addition, design evaluations according to the DBA (design by analysis) code of the ASME Section III Subsection NB-3200 have been conducted. The evaluation results for the present piping systems showed that results from the DBR codes were more conservative than those from the DBA code, and among the DBR codes, the non-nuclear code of the ASME B31.1 was more conservative than the French nuclear DBR code of the RCC-MRx RB-3600. The conservatism on the DBR codes of the ASME B31.1 and RCC-MRx RB-3600 was quantified based on the present sodium piping analyses.

Design evaluation on sodium piping system and comparison of the design codes

Energy Technology Data Exchange (ETDEWEB)

Lee, Dong Won; Jeong, Ji Young; Lee, Yong Bum; Lee, Hyeong Yeon [KAERI, Daejeon (Korea, Republic of)

2015-03-15

A large-scale sodium test loop of STELLA-1 (Sodium integral effect test loop for safety simulation and assessment) with two main piping systems has been installed at KAERI. In this study, design evaluations on the main sodium piping systems in STELLA-1 have been conducted according to the DBR (design by rule) codes of the ASME B31.1 and RCC-MRx RB-3600. In addition, design evaluations according to the DBA (design by analysis) code of the ASME Section III Subsection NB-3200 have been conducted. The evaluation results for the present piping systems showed that results from the DBR codes were more conservative than those from the DBA code, and among the DBR codes, the non-nuclear code of the ASME B31.1 was more conservative than the French nuclear DBR code of the RCC-MRx RB-3600. The conservatism on the DBR codes of the ASME B31.1 and RCC-MRx RB-3600 was quantified based on the present sodium piping analyses.

PWR core design calculations

International Nuclear Information System (INIS)

Trkov, A.; Ravnik, M.; Zeleznik, N.

1992-01-01

Functional description of the programme package Cord-2 for PWR core design calculations is presented. Programme package is briefly described. Use of the package and calculational procedures for typical core design problems are treated. Comparison of main results with experimental values is presented as part of the verification process. (author) [sl

Tinkering at the main-ring lattice

Energy Technology Data Exchange (ETDEWEB)

Ohnuma, S.

1982-08-23

To improve production of usable antiprotons using the proton beam from the main ring and the lossless injection of cooled antiprotons into the main ring, modifications of the main ring lattice are recommended.

The main signs of ageing in people with intellectual disability.

Science.gov (United States)

Wark, Stuart; Hussain, Rafat; Edwards, Helen

2016-12-01

Investigations around ageing with an intellectual disability have increased substantially in the past three decades. A research gap continued to exist regarding the detection of ageing issues in this cohort of people, particularly in rural areas where access to specialist support continued to be limited. The purpose of this study was to identify the main signs of ageing in rural people with intellectual disabilities. A multi-round Delphi design was used to examine what signs of ageing were observed by disability support staff, who assisted people with intellectual disability. The project was conducted across nine of the ten rural regions (as defined by the government funding body) in New South Wales (NSW). There were 31 participants representing 14 non-government organisations. The group was composed of 26 women and 5 men, with a mean age of 47 years, who averaged 10-year experience with people with intellectual disabilities. The objective was to gain the direct input of rurally based disability workers to identify the main signs of ageing in people with intellectual disabilities. Thirty-two specific signs of ageing, including emerging mental health issues, grief, loss of identity and aggression, were identified. A thematic analysis indicated two main categories: mental/emotional functioning and physical functioning. When carers have the information and skills needed to identify the main signs of ageing, they can more accurately recognise and address potential problems in a timely manner. Such understandings have the potential to reduce premature admissions to residential aged-care. © 2016 National Rural Health Alliance Inc.

Dynamic buckling and nonlinear response of FBR main vessels under earthquake loading

International Nuclear Information System (INIS)

Hagiwara, Yutaka; Kawamoto, Yoji; Nakagawa, Masaki; Akiyama, Hiroshi.

1991-01-01

Pseudo-dynamic tests of cylindrical shells under high temperature were performed in order to study elasto-plastic shear-bending buckling and the nonlinear response of FBR main vessels under earthquake loading. The test results showed a response reduction effect due to pre-buckling plasticity, and a large seismic margin due to post-buckling energy absorption of the cylinders. A simple expression of the response reduction effect was proposed, as a contribution to the safe and effective seismic design of FBRs. Two methods for seismic margin evaluation were also proposed, and it was shown that appropriate seismic margins can be ensured, when the response reduction effect is incorporated into the seismic design. (author)

Main sequence mass loss

International Nuclear Information System (INIS)

Brunish, W.M.; Guzik, J.A.; Willson, L.A.; Bowen, G.

1987-01-01

It has been hypothesized that variable stars may experience mass loss, driven, at least in part, by oscillations. The class of stars we are discussing here are the δ Scuti variables. These are variable stars with masses between about 1.2 and 2.25 M/sub θ/, lying on or very near the main sequence. According to this theory, high rotation rates enhance the rate of mass loss, so main sequence stars born in this mass range would have a range of mass loss rates, depending on their initial rotation velocity and the amplitude of the oscillations. The stars would evolve rapidly down the main sequence until (at about 1.25 M/sub θ/) a surface convection zone began to form. The presence of this convective region would slow the rotation, perhaps allowing magnetic braking to occur, and thus sharply reduce the mass loss rate. 7 refs

Thermodynamic analysis of combined cycle under design/off-design conditions for its efficient design and operation

International Nuclear Information System (INIS)

Zhang, Guoqiang; Zheng, Jiongzhi; Xie, Angjun; Yang, Yongping; Liu, Wenyi

2016-01-01

Highlights: • Based on the PG9351FA gas turbine, two gas-steam combined cycles are redesigned. • Analysis of detailed off-design characteristics of the combined cycle main parts. • Suggestions for improving design and operation performance of the combined cycle. • Higher design efficiency has higher off-design efficiency in general PR range. • High pressure ratio combined cycles possess good off-design performance. - Abstract: To achieve a highly efficient design and operation of combined cycles, this study analyzed in detail the off-design characteristics of the main components of three combined cycles with different compressor pressure ratios (PRs) based on real units. The off-design model of combined cycle was built consisting of a compressor, a combustor, a gas turbine, and a heat recovery steam generator (HRSG). The PG9351FA unit is selected as the benchmark unit, on the basis of which the compressor is redesigned with two different PRs. Then, the design/off-design characteristics of the three units with different design PRs and the interactive relations between topping and bottoming cycles are analyzed with the same turbine inlet temperature (TIT). The results show that the off-design characteristics of the topping cycle affect dramatically the combined cycle performance. The variation range of the exergy efficiency of the topping cycle for the three units is between 11.9% and 12.4% under the design/off-design conditions. This range is larger than that of the bottoming cycle (between 9.2% and 9.5%). The HRSG can effectively recycle the heat/heat exergy of the gas turbine exhaust. Comparison among the three units shows that for a traditional gas-steam combined cycle, a high design efficiency results in a high off-design efficiency in the usual PR range. The combined cycle design efficiency of higher pressure ratio is almost equal to that of the PG9351FA, but its off-design efficiency is higher (maximum 0.42%) and the specific power decreases. As for

MOOC Design Workshop

DEFF Research Database (Denmark)

Nørgård, Rikke Toft; Mor, Yishay; Warburton, Steven

2016-01-01

For the last two years we have been running a series of successful MOOC design workshops. These workshops build on previous work in learning design and MOOC design patterns. The aim of these workshops is to aid practitioners in defining and conceptualising educational innovations (predominantly......, but not exclusively MOOCs) which are based on an empathic user-centered view of the target learners and teachers. In this paper, we share the main principles, patterns and resources of our workshops and present some initial results for their effectiveness...

Condom use with "casual" and "main" partners: what's in a name?

Science.gov (United States)

Lescano, Celia M; Vazquez, Elizabeth A; Brown, Larry K; Litvin, Erika B; Pugatch, David

2006-09-01

This study examined adolescents' attitudes about and behaviors toward condom use with "casual" vs. "main" sexual partners. Participants were sexually active adolescents aged 15-21 years (n = 1316) recruited from primary care clinics and through outreach activities in three major cities in the United States. Assessment of condom use within the past 90 days, relevant attitudes, substance use, and demographic data were obtained via audio computer-assisted self-interview (ACASI). Participants were divided into two groups: the 65% who reported main partners only (MP group) and the 35% who had at least one casual partner (CP group). Adolescents in the MP group were more likely to be female, whereas males were significantly more likely to report casual partners. Race/ethnicity, age, education level, household income, and sexually transmitted infection (STI) history were unrelated to group status (i.e., sexual partner type). Greater substance use and riskier attitudes were reported by teens in the CP group. The number of unprotected sex acts in the past 90 days was substantial and equivalent between the main and casual partner groups (19.2 vs. 21.5, respectively). Regression analyses revealed that perceptions of main partner attitudes toward condom use and condom use expectations were significantly related to condom use with MPs, but that attitudes were not related to condom use with CPs. Adolescents with either casual or main partners may be at continued risk for contracting human immunodeficiency virus (HIV) and STIs, given high rates of unprotected sex. Interventions that do not target attitudes and practices related to casual partners as compared with main partners may miss an opportunity to change risk behaviors. This study demonstrates the importance of understanding an adolescent's perception of partner types in order to design effective interventions.

Participatory Design of Websites with Web Design Workshops

Directory of Open Access Journals (Sweden)

Alison Bersani

2008-03-01

Full Text Available At the University of Rochester's River Campus Libraries we have included users in technology development with great success. "Participatory design" entails collaboration among designers, developers, and users from the earliest stages of conception through to implementation of websites and other technology. Using participatory methods, a project to redesign the library website began with workshops to identify user needs and preferences. The results of these workshops led to the identification of key tasks for the main page. They also generated a hierarchy of tasks for sub-pages and rich information about how students and faculty members use current websites in their work. In our article, we explain our reasons for running participatory design workshops, describe our methods, review participants and recruitment, and summarize key findings. We also include information about our local implementation and general conclusions about the value of design workshops for website design and development.

Study of 1 MW neutron source synchrotron dual frequency power circuit for the main ring magnets

International Nuclear Information System (INIS)

McGhee, D.G.

1993-01-01

This paper describes the proposed design of the resonant power circuits for the 1-MW neutron source synchrotron's main ring magnets. The synchrotron is to have a duty cycle of 30 Hz with a maximum upper limit of operation corresponding to 2.0 GeV and a maximum design value of 2.2 GeV. A stability of 30 ppM is the design goal for the main bending and focusing magnets (dipoles and quadruples), in order to achieve an overall stabffity of 100 ppm when random field and position errors of the magnets are included. The power circuits of this design are similar to those used in Argonne's Intense Pulsed Neutron Source (IPNS) where the energy losses during each cycle are supplied by continuous excitation from modulated multiphase DC power supplies. Since only 50% of the 30-Hz sinewave is used for acceleration, a dual-frequency resonant magnet circuit is used in this design. The 30-Hz repetition rate is maintained with a 20-Hz magnet guide field during acceleration and a 60-Hz reset field when no beam is present. This lengthens the guide-field rise time and shortens the fall time, improving the duty factor for acceleration. The maximum B dot is reduced by 33% during acceleration and hence, the maximum rf voltage/turn is reduced by 56%

Main trends of upgrading the 1000 MW steam turbine

International Nuclear Information System (INIS)

Drahy, J.

1990-01-01

Parameters are compared for the 1000 MW steam turbine manufactured by the Skoda Works, Czechoslovakia, and turbines in the same power range by other manufacturers, viz. ABB, Siemens/KWU, GEC and LMZ. The Skoda turbine compares well with the other turbines with respect to all design parameters, and moreover, enables the most extensive heat extraction for district heating purposes. The main trends in upgrading this turbine are outlined; in particular, they include an additional increase in the heat extraction, which is made possible by a new design of the low-pressure section or by using a ''satellite'' turbine. The studies performed also indicate that the output of the full-speed saturated steam turbine can be increased to 1300 MW. An experimental turbine representing one flow of the high-pressure part of the 1000 MW turbine is being built on the 1:1 scale. It will serve to verify the methods of calculation of the wet steam flow and to experimentally test the high-pressure part over a wide span of the parameters. (Z.M.). 1 tab., 3 figs., 7 refs

Lungmen ABWR containment analyses during short-term main steam line break LOCA using GOTHIC

International Nuclear Information System (INIS)

Chen, Yen-Shu; Yuann, Yng-Ruey; Dai, Liang-Che

2012-01-01

Highlights: ► The Lungmen ABWR containment responses due to the main steam line break are analyzed. ► In the Lungmen FSAR, the peak drywell temperature is greater than the designed value. ► GOTHIC is used to calculate the containment responses in this study. ► With more realistic conditions, the drywell temperature can be reasonably suppressed. - Abstract: Lungmen Nuclear Power Plant in Taiwan is a GE-designed twin-unit Advanced Boiling Water Reactor (ABWR) plant with rated thermal power of 3926 MWt. Both units are currently under construction. In the Lungmen Final Safety Analysis Report (FSAR) section 6.2, the calculated peak drywell temperature during the short-term Main Steam Line Break (MSLB) event is 176.3 °C, which is greater than the designed temperature of 171.1 °C. It resulted in a controversial issue in the FSAR review process conducted by the Atomic Energy Council in Taiwan. The purpose of this study is to independently investigate the Lungmen ABWR containment pressure and temperature responses to the MSLB using the GOTHIC program. Blowdown conditions are either calculated by using a simplified reactor vessel volume in GOTHIC model, or provided by the RELAP5 transient analysis. The blowdown flow rate from the steam header side is calculated with a more reasonable pressure loss coefficient of the open main steam isolation valves, and the peak drywell temperature is then reduced. By using the RELAP5 blowdown data, the peak drywell temperature can be further reduced because of the initial liquid entrainment in the blowdown flow. The drywell space is either treated as a single volume, or separated into a upper drywell and a lower drywell to reflect the real configuration of the Lungmen containment. It is also found that a single drywell volume may not present the overheating of the upper drywell. With more realistic approaches and assumptions, the drywell temperature can be reasonably below the design value and the Lungmen containment integrity

Left main percutaneous coronary intervention.

Science.gov (United States)

Teirstein, Paul S; Price, Matthew J

2012-10-23

The introduction of drug-eluting stents and advances in catheter techniques have led to increasing acceptance of percutaneous coronary intervention (PCI) as a viable alternative to coronary artery bypass graft (CABG) for unprotected left main disease. Current guidelines state that it is reasonable to consider unprotected left main PCI in patients with low to intermediate anatomic complexity who are at increased surgical risk. Data from randomized trials involving patients who are candidates for either treatment strategy provide novel insight into the relative safety and efficacy of PCI for this lesion subset. Herein, we review the current data comparing PCI with CABG for left main disease, summarize recent guideline recommendations, and provide an update on technical considerations that may optimize clinical outcomes in left main PCI. Copyright © 2012 American College of Cardiology Foundation. Published by Elsevier Inc. All rights reserved.

Simulation research on operation scheme of dissymmetrical main engine of CODOG propulsion system

Directory of Open Access Journals (Sweden)

HUANG Bin

2018-02-01

Full Text Available [Objectives] How to maintain propulsion capability in a CODOG propulsion system damage situation has important significance. [Methods] A ‘Hull-Engine-CPP-Rudder’ simulation model of a CODOG marine power plant is established on Simulink using the modularized method, and a dissymmetrical main engine urgent working mode is proposed and simulated. [Results] The results show that in the dissymmetrical working mode, two different engines cannot work simultaneously at designed capacity. However, by adjusting the pitch of the CPP, one engine can work at designed capacity and the other can work at partial load capacity; under this working mode, if high speed is demanded, the gas turbine should work at designed capacity. The CPP pitch driven by diesel should be maintained at a high value near the maximum. The maximum speed of this working mode is 84.4% of the designed speed, which is higher than the speed of the single shaft working mode driven by a gas turbine. [Conclusions] The research results of this paper can provide useful references for the design of ship propulsion systems.

Improving STEM Undergraduate Education with Efficient Learning Design

DEFF Research Database (Denmark)

Godsk, Mikkel

2018-01-01

The project investigates the potential of Learning Design for efficiently improving STEM undergraduate education with technology. In order to investigate this potential, the project consists of two main studies at Aarhus University: a study of the perspectives of the main stakeholders on Learning...... Design uptake. The project concludes that it is possible to improve STEM undergraduate education with Learning Design for technology-enhanced learning efficiently and that Efficient Learning Design provides a useful concept for qualifying educational decisions....... provided by technology-enhanced learning based on Learning Design, and in particular students’ learning was of a high common interest. However, only the educators were directly interested in Learning Design and its support for design, reuse in their practice and to inform pedagogy. A holistic concept...

Optimal covariate designs theory and applications

CERN Document Server

Das, Premadhis; Mandal, Nripes Kumar; Sinha, Bikas Kumar

2015-01-01

This book primarily addresses the optimality aspects of covariate designs. A covariate model is a combination of ANOVA and regression models. Optimal estimation of the parameters of the model using a suitable choice of designs is of great importance; as such choices allow experimenters to extract maximum information for the unknown model parameters. The main emphasis of this monograph is to start with an assumed covariate model in combination with some standard ANOVA set-ups such as CRD, RBD, BIBD, GDD, BTIBD, BPEBD, cross-over, multi-factor, split-plot and strip-plot designs, treatment control designs, etc. and discuss the nature and availability of optimal covariate designs. In some situations, optimal estimations of both ANOVA and the regression parameters are provided. Global optimality and D-optimality criteria are mainly used in selecting the design. The standard optimality results of both discrete and continuous set-ups have been adapted, and several novel combinatorial techniques have been applied for...

Documentation control process of Brazilian multipurpose reactor: conceptual design and basic design

International Nuclear Information System (INIS)

Kibrit, Eduardo; Prates, Jose Eduardo; Longo, Guilherme Carneiro; Salvetti, Tereza Cristina

2015-01-01

Established in the scope of Plan of Action of the Ministry of Science, Technology and Innovation (PACTI/MCTI) in 2007, the construction of the Brazilian Multipurpose Reactor (RMB) is on the way. This type of reactor has a broad spectrum of applications in the nuclear field and related technologies such as the radioisotopes used as supplies in the production of radiopharmaceuticals, with very much benefit to the Brazilian society being, therefore, the main goal of the Project. RMB Project consists of the following stages: site selection and site evaluation; design (conceptual design, basic design, detailed design and experimental design); construction (procurement, manufacturing; civil construction; electromechanical construction and assembling); commissioning; operation and decommissioning. Each stage requires adaptation of human resources for the stage schedule execution. The implementation of a project of this magnitude requires a complex project management, which covers not only technical, but also administrative areas. Licensing, financial resources, quality and document control systems, engineering are some of the areas involved in project success. The development of the conceptual and basic designs involved the participation of three main engineering companies. INTERTECHNE Consultores S.A. was in charge of conceptual and basic designs for conventional systems of buildings and infrastructure. INVAP S.E. was responsible for preparing the basic design of the reactor core and annexes. MRS Estudos Ambientais Ltda. has prepared documents for environmental licensing. This paper describes the procedures used during conceptual and basic design stages to control design documentation and flow of this documentation, involving the analysis and incorporation of comments from experts, control and storage of a volume of approximately 15,000 documents. (author)

Documentation control process of Brazilian multipurpose reactor: conceptual design and basic design

Energy Technology Data Exchange (ETDEWEB)

Kibrit, Eduardo; Prates, Jose Eduardo; Longo, Guilherme Carneiro; Salvetti, Tereza Cristina, E-mail: ekibrit@ipen.br, E-mail: jeprates@ipen.br, E-mail: glongo@ipen.br, E-mail: salvetti@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

Established in the scope of Plan of Action of the Ministry of Science, Technology and Innovation (PACTI/MCTI) in 2007, the construction of the Brazilian Multipurpose Reactor (RMB) is on the way. This type of reactor has a broad spectrum of applications in the nuclear field and related technologies such as the radioisotopes used as supplies in the production of radiopharmaceuticals, with very much benefit to the Brazilian society being, therefore, the main goal of the Project. RMB Project consists of the following stages: site selection and site evaluation; design (conceptual design, basic design, detailed design and experimental design); construction (procurement, manufacturing; civil construction; electromechanical construction and assembling); commissioning; operation and decommissioning. Each stage requires adaptation of human resources for the stage schedule execution. The implementation of a project of this magnitude requires a complex project management, which covers not only technical, but also administrative areas. Licensing, financial resources, quality and document control systems, engineering are some of the areas involved in project success. The development of the conceptual and basic designs involved the participation of three main engineering companies. INTERTECHNE Consultores S.A. was in charge of conceptual and basic designs for conventional systems of buildings and infrastructure. INVAP S.E. was responsible for preparing the basic design of the reactor core and annexes. MRS Estudos Ambientais Ltda. has prepared documents for environmental licensing. This paper describes the procedures used during conceptual and basic design stages to control design documentation and flow of this documentation, involving the analysis and incorporation of comments from experts, control and storage of a volume of approximately 15,000 documents. (author)

Main facts 1995

International Nuclear Information System (INIS)

1996-01-01

This report presents the main facts of the studies carried out by the Direction des Etudes et Recherches (DER) of Electricite de France: new applications of electricity, classical and nuclear thermal power plants, electrical equipment, environment protection, monitoring and plants operations

Business Intelligence. A Presentation of the Current Lead Solutions and a Comparative Analysis of the Main Providers

Directory of Open Access Journals (Sweden)

Bogdan-Andrei IONESCU

2014-09-01

Full Text Available The aim of this paper is to synthesize the concepts behind Business Intelligence, by studying the solutions available on the market provided by the main players. We will present the software solutions already provided by them emphasizing the main advantages and benefits of each of them, but also as a comparative analysis, designed to reveal the area in which each provider is more remarkable than the others.

ForGATE - A Forest Sector Greenhouse Gas Assessment Tool for Maine: Calibration and Overview

Science.gov (United States)

Chris Hennigar; Luke Amos-Binks; Ryan Cameron; John Gunn; David A. MacLean; Mark Twery

2013-01-01

This report describes the background calibration, inputs, and outputs of ForGATE, a forest sector greenhouse gas (GHG) accounting tool designed primarily to communicate information relevant to the evaluation of projected net GHG exchange in the context of Maine's forests, the Northeast forest sector, and alternative national or regional carbon (C) accounting...

LHC main dipole magnet circuits: sustaining near-nominal beam energies

CERN Document Server

AUTHOR|(CDS)2085621; Auchmann, Bernhard; Knox, Andrew; O'Shea, Valentine

2016-11-04

Crossing the Franco-Swiss border, the Large Hadron Collider (LHC), designed to collide 7 TeV proton beams, is the world's largest and most powerful particle accelerator the operation of which was originally intended to commence in 2008. Unfortunately, due to an interconnect discontinuity in one of the main dipole circuit's 13 kA superconducting busbars, a catastrophic quench event occurred during initial magnet training, causing significant physical system damage. Furthermore, investigation into the cause found that such discontinuities were not only present in the circuit in question, but throughout the entire LHC. This prevented further magnet training and ultimately resulted in the maximum sustainable beam energy being limited to approximately half that of the design nominal, 3.5-4 TeV, for the first three years of operation (Run 1, 2009-2012) and a major consolidation campaign being scheduled for the first long shutdown (LS 1, 2012-2014). Throughout Run 1, a series of studies attempted to predict the amo...

Design of a nuclear fuel rod support grid using axiomatic design

International Nuclear Information System (INIS)

Song, Kee Nam; Yoon, Kyung Ho; Kang, Byung Soo; Park, Gyung Jin; Choi, Sung Kyoo

2002-01-01

Recently, much attention is imposed on the design of the fuel assemblies in the Pressurized Light Water Reactor (PWR). Spacer grid is one of the main structural components in a fuel assembly. It supports fuel rods, guides cooling water, and maintains a coolable geometry from the external impact loads. In this research, a new shape of the spacer grid is designed by the axiomatic approach. The Independence axiom is utilized for the design. For conceptual design, functional requirements (FRs) are defined and corresponding design parameters (DPs) are found to satisfy FRs in sequence. Overall configuration and shapes are determined in this process. Detail design is carried out based on the result of the axiomatic design. For the detail design, the system performances are evaluated by using linear and nonlinear finite element analysis. The dimensions are determined by optimization. Some commercial codes are utilized for the analysis and design

Initial DEMO tokamak design configuration studies

Energy Technology Data Exchange (ETDEWEB)

Bachmann, Christian, E-mail: christian.bachmann@efda.org [EFDA, Boltzmannstraße 2, 85748 Garching (Germany); Aiello, G. [CEA-Saclay, DEN, DM2S, SEMT, F-91191 Gif-Sur-Yvette (France); Albanese, R.; Ambrosino, R. [ENEA/CREATE, Universita di Napoli Federico II, Naples (Italy); Arbeiter, F. [Karlsruhe Institute of Technology (KIT), Karlsruhe (Germany); Aubert, J. [CEA-Saclay, DEN, DM2S, SEMT, F-91191 Gif-Sur-Yvette (France); Boccaccini, L.; Carloni, D. [Karlsruhe Institute of Technology (KIT), Karlsruhe (Germany); Federici, G. [EFDA, Boltzmannstraße 2, 85748 Garching (Germany); Fischer, U. [Karlsruhe Institute of Technology (KIT), Karlsruhe (Germany); Kovari, M. [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Li Puma, A. [CEA-Saclay, DEN, DM2S, SEMT, F-91191 Gif-Sur-Yvette (France); Loving, A. [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Maione, I. [Karlsruhe Institute of Technology (KIT), Karlsruhe (Germany); Mattei, M. [ENEA/CREATE, Universita di Napoli Federico II, Naples (Italy); Mazzone, G. [ENEA C.R. Frascati, via E. Fermi 45, 00044 Frascati, Roma (Italy); Meszaros, B. [EFDA, Boltzmannstraße 2, 85748 Garching (Germany); Palermo, I. [Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (CIEMAT), Madrid (Spain); Pereslavtsev, P. [Karlsruhe Institute of Technology (KIT), Karlsruhe (Germany); Riccardo, V. [CCFE, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); and others

2015-10-15

Highlights: • A definition of main DEMO requirements. • A description of the DEMO tokamak design configuration. • A description of issues yet to be solved. - Abstract: To prepare the DEMO conceptual design phase a number of physics and engineering assessments were carried out in recent years in the frame of EFDA concluding in an initial design configuration of a DEMO tokamak. This paper gives an insight into the identified engineering requirements and constraints and describes their impact on the selection of the technologies and design principles of the main tokamak components. The EU DEMO program aims at making best use of the technologies developed for ITER (e.g., magnets, vessel, cryostat, and to some degree also the divertor). However, other systems in particular the breeding blanket require design solutions and advanced technologies that will only partially be tested in ITER. The main differences from ITER include the requirement to breed, to extract, to process and to recycle the tritium needed for plasma operation, the two orders of magnitude larger lifetime neutron fluence, the consequent radiation dose levels, which limit remote maintenance options, and the requirement to use low-activation steel for in-vessel components that also must operate at high temperature for efficient energy conversion.

Regulatory aspects of control and instrumentation: role of SCCI and a case study

International Nuclear Information System (INIS)

Patil, R.K.; Suresh Babu, R.M.; Roy, D.A.; Shriwalkar, Varsha

2017-01-01

Standing Committee for Control, Instrumentation and Computer based Systems (SCCI) was constituted in the year 2001 as an expert committee under Operating Plant Safety Review Committee (OPSRC) of BARC Safety Council (BSC). The terms of reference of SCCI include: review C and I aspects of systems affecting safety of operating plants, suggest modifications/improvements, conduct periodic review/audit and advise OPSRC on C and I matters. In this paper we share our experience in the review of safety cases of computer-based systems, specifically, review of three systems that are part of Dhruva C and I upgradation

Determination of chlorine in high purity materials by charged particle activation analysis using deuteron beam from VEC accelerator

International Nuclear Information System (INIS)

Dasgupta, S.; Datta, J.; Chowdhury, D.P.; Verma, R.

2015-01-01

The quantitative determination of chlorine by conventional methods viz., AAS, ICP-OES is difficult and erroneous at times due to gaseous nature of elemental chlorine. It is possible to determine chlorine by NAA and charged particle activation analysis (CPAA) producing activation product 38 Cl (t 1/2 = 37.2 min, 1642 (32.8 %), 2168 keV (44 %)). Fast INAA method has been applied to determine Cl in concentration ranges 10 mgkg -1 in some suitable matrices in PCF of DHRUVA reactor with a neutron flux of 10 13 cm -2 s -1 with a detection limit of Cl of ∼1 mgkg -1

Simulating the transient regime for main condensate system at Cernavoda NPP

International Nuclear Information System (INIS)

Nita, Iulian; Gheorghiu, Mihai; Prisecaru, Ilie; Dupleac, Daniel

2005-01-01

The purpose of this project is to make a Thermal Hydraulic Analysis of Main Condensate System for getting real-time answer of installation during regimes occurring during normal and abnormal operation. To obtain the analyses the MMS code was used. The boundaries of the systems analysis are extended to Main Feedwater System in order to get a realistic response of Deaerator equipment which are situated between those two systems and have entrances from both systems. In this way we made a complex analysis with main condenser and steam generators as boundaries. We obtained a model for the entire chain of condensate and feedwater preheater with interface just turbine bleed steam. From that we could reduce the number of assumptions necessary to make the analysis. The analyses consist in hydraulics and thermal hydraulics analyses, respectively. For the first case analysed are: - the nominal operation regime with main condensate pumps; - start-up regime with total circulate of condensate to condenser; - 25% MCR (Maximum Continuous Rate) regime (this regime was used in designing the condensate regulating valves at low flow; - 40% MCR regime (with circulate of some condensate flow to condenser); - operating regime of 60% MCR with one main condensate pump operating; - operating regime with auxiliary condensate pump; - operating regime with discharging a condensate flow to condensate storage tank. The thermal hydraulic analyses deal with normal and abnormal operating regimes, respectively. In the first case analysed are the following regimes: - nominal operating regime with main condensate pump operating 100% MCR; - transient regime, 100-80% MCR; - transient regime, 100-80-60% MCR with two pumps in operation and 60 % MCR with one main condensate pump in operation; - transient regime, 100-80-60-60-40 % MCR; - shut-down regime; - start-up regime from Hot zero power to rated power regime. Finally, for the abnormal operating regimes the analyses concerned: - transient regime 100

Guided design of heating and cooling mains for lower water and energy consumption and increased efficiency

CSIR Research Space (South Africa)

Gololo, V

2011-01-01

Full Text Available Water cooling and water heating is an important source of energy consumption, accounting for more than 20% of all energy consumption in manufacturing industry. It is clear that the development of heat recycling schemes and better structural design...

Diagnosing in building main pipelines

Energy Technology Data Exchange (ETDEWEB)

Telegin, L.G.; Gorelov, A.S.; Kurepin, B.N.; Orekhov, V.I.; Vasil' yev, G.G.; Yakovlev, Ye. I.

1984-01-01

General principles are examined for technical diagnosis in building main pipelines. A technique is presented for diagnosis during construction, as well as diagnosis of the technical state of the pipeline-construction machines and mechanisms. The survey materials could be used to set up construction of main pipelines.

Main factors affecting the fixing work about nuclear engineering and its discussion

International Nuclear Information System (INIS)

Zhang Zhihua; Liu Yaoguan; Qian Dazhi; Liu Hangang; Xu Xianqi; Deng Yue

2010-01-01

Main factors to the impact of the fixing work about nuclear engineering such as project design, construction, plan program, document, preparation, order, locale management, surveillance, quality assurance system and so on were presented. These factors were analyzed and discussed in this paper. Some measures and suggestions were put forward to accelerate construction fixing plan and insure good quality. We wish provide some references and help for someone engaged with construction of nuclear engineering. (authors)

Main facts 1993

International Nuclear Information System (INIS)

1994-01-01

This report presents the main facts of the studies carried out by the Direction des Etudes et Recherches (DER) of Electricite de France: new applications of electricity, classical and nuclear thermal power plants, electrical equipment, environment protection, network analysis, information and informatic equipment

SUBSURFACE DESIGN SUPPORT LOW THERMAL LOAD REPOSITORY (25 MTU/ACRE)

International Nuclear Information System (INIS)

T.M. Lahnalampi

1999-01-01

The objective of this document is to present a comparison between the Viability Assessment Design Layout and a 25 MTU/acre conceptual repository design. The scope of this analysis is comparing the linear dimensions and the quantities of the major design elements, for example, emplacement drifts, perimeter mains, exhaust mains, performance confirmation drifts, connecting ramps and vertical development

30 CFR 57.6160 - Main facilities.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Main facilities. 57.6160 Section 57.6160...-Underground Only § 57.6160 Main facilities. (a) Main facilities used to store explosive material underground... facilities will not prevent escape from the mine, or cause detonation of the contents of another storage...

Main Memory

OpenAIRE

Boncz, Peter; Liu, Lei; Özsu, M.

2008-01-01

htmlabstractPrimary storage, presently known as main memory, is the largest memory directly accessible to the CPU in the prevalent Von Neumann model and stores both data and instructions (program code). The CPU continuously reads instructions stored there and executes them. It is also called Random Access Memory (RAM), to indicate that load/store instructions can access data at any location at the same cost, is usually implemented using DRAM chips, which are connected to the CPU and other per...

Seismic risks at Elsie Lake Main Dam

International Nuclear Information System (INIS)

McCammon, N.R.; Momenzadeh, M.; Hawson, H.H.; Nielsen, N.M.

1991-01-01

The Elsie Lake dams are located on Vancouver Island in an area of high seismic risk. A safety review in 1986 indicated potential deficiencies in the earthfill main dam with respect to modern earthquake design standards. A detailed field investigation program comprising drilling and penetration tests was carried out and the results used in an assessment of seismic stability. A 0.8 m thick less dense layer in the granular shell of the dam, possibly caused by wet construction conditions, would likely liquefy in a major earthquake but sufficient residual strength would likely remain to prevent catastrophic failure. The dam shell might undergo some distortion, and an assessment was initiated to determine the requirements for reservoir drawdown following an extreme earthquake to ensure the timely lowering of the reservoir for inspection and repair. It was suggested that an adequate evacuation capability would be 25% and 50% drawdown in not more than 30 and 50 days, respectively. 9 refs., 11 figs., 1 tab

Main heat transfer components for SNR-300

International Nuclear Information System (INIS)

De Haas Van Dorsser, A.H.

1976-01-01

Early in the joint German-Belgium-Dutch fast breeder programme it was decided that all main components should be tested, if possible at full scale, before fabrication of the actual SNR-300 components. Descriptions are given of the results of testing, and subsequent modifications, of the pumps, intermediate heat exchangers, and steam generators. A full scale model of the primary pump, free surface vertical shaft centrifugal type, was constructed and tested in the 5000 cubic metres per hour pump test facility erected at Bensberg. A 70 MW model of an intermediate heat exchanger, straight tube type with floating head, was tested in the 50 MW steam generator test station at Hengelo. Also tested in the Hengelo facility was an almost full scale straight tube 50 MW steam generator and subsequently a 50 MW helical tube evaporator. The latter tests were of more than 3000 h operation and resulted in minor changes in design and manufacturing operation. (U.K.)

Supplementary control points for reactor shutdown without access to the main control room (International Electrotechnical Commission Standard Publication 965:1989)

International Nuclear Information System (INIS)

Kubalek, J.; Hajek, B.

1993-01-01

This standard establishes the requirements for supplementary Control Points provided to enable the operating staff to shut down the reactor and maintain the plant in a safe shut-down condition when the main control room is no longer available. This standard covers the functional selection, design and organization of the man/machine interface. It also establishes requirements for procedures which systematically verify and validate the functional design of supplementary control points. The requirements reflect the application of human engineering principles as they apply to man/machine interface. This standard does not cover special emergency response centres (e.g. a Technical Support Centre). It also does not include the detailed equipment design. Unavailability of the main control room controls due to intentionally man-induced events is not considered

Preliminary crystallographic analysis of avian infectious bronchitis virus main protease

Energy Technology Data Exchange (ETDEWEB)

Li, Jun; Shen, Wei [Laboratory of Structural Biology, Tsinghua University, Beijing 100084 (China); Liao, Ming, E-mail: mliao@scau.edu.cn [Laboratory of Avian Medicine, College of Veterinary Medicine, South China Agricultural University, Guangzhou 510642 (China); Bartlam, Mark, E-mail: mliao@scau.edu.cn [Laboratory of Structural Biology, Tsinghua University, Beijing 100084 (China); National Laboratory of Biomacromolecules, Institute of Biophysics, Chinese Academy of Sciences, Beijing 100101 (China)

2007-01-01

The avian infectious bronchitis virus main protease has been crystallized; crystals diffract to 2.7 Å resolution. Infectious bronchitis virus (IBV) is the prototype of the genus Coronavirus. It causes a highly contagious disease which affects the respiratory, reproductive, neurological and renal systems of chickens, resulting great economic losses in the poultry industry worldwide. The coronavirus (CoV) main protease (M{sup pro}), which plays a pivotal role in viral gene expression and replication through a highly complex cascade involving the proteolytic processing of replicase polyproteins, is an attractive target for antiviral drug design. In this study, IBV M{sup pro} was overexpressed in Escherichia coli. Crystals suitable for X-ray crystallography have been obtained using microseeding techniques and belong to space group P6{sub 1}22. X-ray diffraction data were collected in-house to 2.7 Å resolution from a single crystal. The unit-cell parameters were a = b = 119.1, c = 270.7 Å, α = β = 90, γ = 120°. Three molecules were predicted to be present in the asymmetric unit from a calculated self-rotation function.

Issues in holistic system design

DEFF Research Database (Denmark)

Lawall, Julia L.; Probst, Christian W.; Schultz, Ulrik Pagh

2006-01-01

The coordination of layers in computer and software systems is one of the main challenges in designing such systems today. In this paper we consider Holistic System Design as a way of integrating requirements and facilities of different system layers. We also discuss some of the challenges...

TVSA-T fuel assembly for 'Temelin' NPP. Main results of design and safety analyses. Trends of development

International Nuclear Information System (INIS)

Samojlov, O.B.; Kajdalov, V.B.; Falkov, A.A.; Bolnov, V.A.; Morozkin, O.N.; Molchanov, V.L.; Ugryumov, A.V.

2010-01-01

TVSA is a fuel assembly with rigid skeleton formed by 6 angle pieces and SG is successfully operated at 17 VVER-1000 power units of Kalinin NPP, as well as at Ukrainian and Bulgarian NPPs. Based on a contract for fuel supply to the Temelin NPP, the TVSA-T fuel assembly was developed, building on proven solutions confirmed by operation of TVSA modifications during 4-6 years and by the results of post-irradiation examination. The TVSA-T design includes combined spacer grids (SG+MG) and by fuel column elongation by 150 mm. A set of analyses and experiments was performed to validate the design, including thermal hydraulic tests, validation of critical heat flux correlation for TVSA-T, integrated mechanical, vibration and lifetime tests. A licence to use the fuel has been granted by the Czech State Office for Nuclear Safety. The TVSA-T core is currently in operation at the Temelin-1 reactor unit. The presentation is concluded as follows: TVSA-T fuel assembly for Temelin has been validated. The TVSA-T design is based on approved technical decisions and meets the current requirements for lifetime, operational maneuverability and safety. The results of post-irradiation examination of TVSA-T operated at the Kalinin-1 unit for 4 years confirm the assembly operability, skeleton stiffness, geometric stability and normal fuel rod cladding condition. The properties of the TVSA fuel with MG allow the core power to be increased up to 3300 MW to match the envisaged future VVER (MIR-1200) design, providing allowable fuel rod power FΔh =1.63 (to implement effective fuel cycles). (P.A.)

Nature inspired design : Strategies towards sustainability

NARCIS (Netherlands)

De Pauw, I.C.; Kandachar, P.V.; Karana, E.; Peck, D.P.; Wever, R.

2010-01-01

Current design practices focus on eco-efficiency as the main approach in the field of sustainable product development. This approach mainly aims at improving existing products and services. Environmental product performance can be greatly improved using ecoefficiency but in many cases the

Reliability model for helicopter main gearbox lubrication system using influence diagrams

International Nuclear Information System (INIS)

Rashid, H.S.J.; Place, C.S.; Mba, D.; Keong, R.L.C.; Healey, A.; Kleine-Beek, W.; Romano, M.

2015-01-01

The loss of oil from a helicopter main gearbox (MGB) leads to increased friction between components, a rise in component surface temperatures, and subsequent mechanical failure of gearbox components. A number of significant helicopter accidents have been caused due to such loss of lubrication. This paper presents a model to assess the reliability of helicopter MGB lubricating systems. Safety risk modeling was conducted for MGB oil system related accidents in order to analyse key failure mechanisms and the contributory factors. Thus, the dominant failure modes for lubrication systems and key contributing components were identified. The Influence Diagram (ID) approach was then employed to investigate reliability issues of the MGB lubrication systems at the level of primary causal factors, thus systematically investigating a complex context of events, conditions, and influences that are direct triggers of the helicopter MGB lubrication system failures. The interrelationships between MGB lubrication system failure types were thus identified, and the influence of each of these factors on the overall MGB lubrication system reliability was assessed. This paper highlights parts of the HELMGOP project, sponsored by the European Aviation Safety Agency to improve helicopter main gearbox reliability. - Highlights: • We investigated methods to optimize helicopter MGB oil system run-dry capability. • Used Influence Diagram to assess design and maintenance factors of MGB oil system. • Factors influencing overall MGB lubrication system reliability were identified. • This globally influences current and future helicopter MGB designs

Influence of Shaft Torsional Stiffness on Dynamic Response of Four-Stage Main Transmission System

Directory of Open Access Journals (Sweden)

Yuan Chen

2018-01-01

Full Text Available Dynamic response analysis has potential for increasing fatigue life of the components in the transmission of a multistage main transmission system. The calculated data can demonstrate the influence of shaft torsional stiffness on dynamic characteristics of the system. Detecting key shafts of the system and analyzing their sensitivity are important for the design of four-stage helicopter gear box. Lumped mass method is applied for dynamic modeling and Fourier method is used to solve differential equation of the system. Results of the analysis indicate that key shafts can be designed carefully to improve the performance of the transmission system.

Beyond (eco)design : Current approaches to sustainable packaging design

NARCIS (Netherlands)

Wever, R.

2014-01-01

Packaging has always received a lot of attention within the field of design for sustainability. The classical approach has been to mainly focus on reducing the impact of the packaging. This approach stems from the ill-informed position that packaging is superfluous, or at best there only for

Main results and status of the development of LEU fuel for Russian research reactors

International Nuclear Information System (INIS)

Vatulin, A.; Morozov, A.; Suprun, V.; Dobrikova, I.

2005-01-01

VNIINM develops low enrichment uranium (LEU) fuel on base U-Mo alloys and a novel design of pin-type fuel elements. The development is carried out both for existing reactors, and for new advanced designs of reactors. The work is carried on the following main directions: - irradiate LEU U-Mo dispersion fuel (the uranium density up to 6,0 g/cm 3 ) in two Russian research reactors: MIR (RIAR, Dimitrovgrad) as pin type fuel mini-elements and in WWR-M (PINP, Gatchina) within full-scaled fuel assembly (FA) with pin type fuel elements; - finalize development of design and fabrication process of IRT type FA with pin type fuel elements; - develop methods of reducing of U-Mo fuel --Al matrix interaction under irradiation; - develop fabricating methods of fuel elements on base of monolithic U-Mo fuel. The paper generally reviews the results of calculation, design and technology investigations accomplished by now. (author)

THE ANALYSIS OF STRUCTURAL RELIABILITY OF THE MAIN ELECTRIC CONNECTION CIRCUITS OF NUCLEAR POWER PLANTS

Directory of Open Access Journals (Sweden)

M. A. Korotkevich

2017-01-01

Full Text Available The reliability of the main circuit of electrical connections at a nuclear electric power plant that has two units with a capacity of 1,200 MW each has been determined. Reliability, economical, maneuverable properties of the atomic power plant under study are largely determined by its main circuit, so the choice of the circuit for the design and its status in the process of operation occur to be critical objectives. Main electrical connection circuits in nuclear electric power plants are selected on the basis of the schematic networks of the energy system and the land attached to the plant. The circuit of the connection of a nuclear power plant to the grid in the original normal operating modes at all stages of the construction of such a plant should provide the outcome of the full added capacity of a nuclear power plant and the preservation of its stability in the power system without the influence of the emergency system automatics when any outgoing transmission line is disabled. When selecting the main circuit the individual capacity of the installed units and their number are taken into account as well as the order of development of the plant and power supply system; the voltage on which the power of a plant is delivered; a shortcircuit current for switchgear high voltage and the need for their limitation by circuit means; the most power that can be lost when damage to any switch. A model of reliability of the main circuit of electrical connections is designed to detect all types of accidents that are possible at the coincidence of failures of elements with the repair and operational modes that differs in composition and damageability of the equipment, as well as under conditions of the development of accidents due to failure of operation of devices of relay protection and automation.

A product design framework for a circular economy

NARCIS (Netherlands)

Van den Berg, M.R.; Bakker, C.A.

2015-01-01

The paper provides a circular economy framework from a product design perspective with tools to aid product designers in applying circular product design in practice. Design research for circular economy has so far mainly been limited to referring to existing fields of research such as design for

KAJIAN SUSTAINABLE DESIGN PADA SAVILL BUILDING

Directory of Open Access Journals (Sweden)

Oktavi Elok Hapsari

2015-08-01

Full Text Available Since 1980 the development of Indonesian architecture design start to leads into sustainable architectural design which as it was expected to became a solution regarding the environmental problems. The implementation of sustainable design in buildings can be applied from the buildings typologi, renewable resources on materials untill the reduction of the negative impact againts the buildings surrounding environment. As the main object for this study was 2006 The Woods Awardee, Savill Building. A literature study was conducted related to sustainable concept design and the implementation in Savill Buildings. Savill Building is a transparance walls buildings with steel and wooden as main materials on it complex curve gridshell structures. Located in a countoured site Savill Building show it assertive appearance. Due to the good landscape processing and design the Savill Building stood out and yet still shown continuity and harmony with the surrounding environment. The buildings not only has a eco-friendly public facility function, but also has the capability on attracting visitors. In the end this study is expected able expand the knowledges on sustainable design and become a design references in Indonesia architectural design.

US Mains Stacked Very High Frequency Self-oscillating Resonant Power Converter with Unified Rectifier

DEFF Research Database (Denmark)

Pedersen, Jeppe Arnsdorf; Madsen, Mickey Pierre; Mønster, Jakob Døllner

2016-01-01

This paper describes a Very High Frequency (VHF) converter made with three Class-E inverters and a single ClassDE rectifier. The converter is designed for the US mains (120 V, 60 Hz) and can deliver 9 W to a 60 V LED. The converter has a switching frequency of 37 MHz and achieves an efficiency...

14 CFR 119.47 - Maintaining a principal base of operations, main operations base, and main maintenance base...

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Maintaining a principal base of operations, main operations base, and main maintenance base; change of address. 119.47 Section 119.47 Aeronautics... Under Part 121 or Part 135 of This Chapter § 119.47 Maintaining a principal base of operations, main...

Main requirements and criteria for State nuclear material control and accounting

International Nuclear Information System (INIS)

Ryazanov, B.G.; Goryunov, V.K.; Erastov, V.V.

1999-01-01

The paper presents comments and substantiation of the main requirements and criteria for the State nuclear materials (NM) control and accounting system in the draft of the federal Main regulations of NM control and accounting. The State NM control and accounting system structure and design principles, the list of nuclear and special non-nuclear materials which are subject to the control and accounting, NM control and accounting principles are considered. Measurement system for the values for NM control and accounting and measurement assurance program, NM transfer procedures, physical inventory taking, closing a material balance and evaluation of inventory difference and balance closure of bulk form NM are shown. Accounting units in the inventory, the system accounting report documentation and preliminary notifications, the NM control and accounting arrangement, the federal and departmental control in the State NM control and accounting system, the State NM control and accounting system supervision and requirement to the personnel carrying out the NM control and accounting are discussed [ru

Leak before break evaluation for main steam piping system made of SA106 Gr.C

Energy Technology Data Exchange (ETDEWEB)

Yang, Kyoung Mo; Jee, Kye Kwang; Pyo, Chang Ryul; Ra, In Sik [Korea Power Engineering Company, Seoul (Korea, Republic of)

1997-04-01

The basis of the leak before break (LBB) concept is to demonstrate that piping will leak significantly before a double ended guillotine break (DEGB) occurs. This is demonstrated by quantifying and evaluating the leak process and prescribing safe shutdown of the plant on the basis of the monitored leak rate. The application of LBB for power plant design has reduced plant cost while improving plant integrity. Several evaluations employing LBB analysis on system piping based on DEGB design have been completed. However, the application of LBB on main steam (MS) piping, which is LBB applicable piping, has not been performed due to several uncertainties associated with occurrence of steam hammer and dynamic strain aging (DSA). The objective of this paper is to demonstrate the applicability of the LBB design concept to main steam lines manufactured with SA106 Gr.C carbon steel. Based on the material properties, including fracture toughness and tensile properties obtained from the comprehensive material tests for base and weld metals, a parametric study was performed as described in this paper. The PICEP code was used to determine leak size crack (LSC) and the FLET code was used to perform the stability assessment of MS piping. The effects of material properties obtained from tests were evaluated to determine the LBB applicability for the MS piping. It can be shown from this parametric study that the MS piping has a high possibility of design using LBB analysis.

Algebraic design theory

CERN Document Server

Launey, Warwick De

2011-01-01

Combinatorial design theory is a source of simply stated, concrete, yet difficult discrete problems, with the Hadamard conjecture being a prime example. It has become clear that many of these problems are essentially algebraic in nature. This book provides a unified vision of the algebraic themes which have developed so far in design theory. These include the applications in design theory of matrix algebra, the automorphism group and its regular subgroups, the composition of smaller designs to make larger designs, and the connection between designs with regular group actions and solutions to group ring equations. Everything is explained at an elementary level in terms of orthogonality sets and pairwise combinatorial designs--new and simple combinatorial notions which cover many of the commonly studied designs. Particular attention is paid to how the main themes apply in the important new context of cocyclic development. Indeed, this book contains a comprehensive account of cocyclic Hadamard matrices. The book...

Maine Agricultural Foods. Project SEED.

Science.gov (United States)

Beaulieu, Peter; Ossenfort, Pat

This paper describes an activity-based program that teaches students in grades 4-12 about the importance of Maine agriculture in their lives. Specifically, the goal is to increase student awareness of how the foods they eat are planted, harvested, and processed. The emphasis is on crops grown in Maine such as potatoes, broccoli, peas, blueberries,…

On justification of efficient Energy-Force parameters of Hydraulic-excavator main mechanisms

Science.gov (United States)

Komissarov, Anatoliy; Lagunova, Yuliya; Shestakov, Viktor; Lukashuk, Olga

2018-03-01

The article formulates requirements for energy-efficient designs of the operational equipment of a hydraulic excavator (its boom, stick and bucket) and defines, for a mechanism of that equipment, a new term “performance characteristic”. The drives of main rotation mechanisms of the equipment are realized by hydraulic actuators (hydraulic cylinders) and transmission (leverage) mechanisms, with the actuators (the cylinders themselves, their pistons and piston rods) also acting as links of the leverage. Those drives are characterized by the complexity of translating mechanical-energy parameters of the actuators into energy parameters of the driven links (a boom, a stick and a bucket). Relations between those parameters depend as much on the types of mechanical characteristics of the hydraulic actuators as on the types of structural schematics of the transmission mechanisms. To assess how energy-force parameters of the driven links change when a typical operation is performed, it was proposed to calculate performance characteristics of the main mechanisms as represented by a set of values of transfer functions, i.e. by functional dependences between driven links and driving links (actuators). Another term “ideal performance characteristic” of a mechanism was introduced. Based on operation-emulating models for the main mechanisms of hydraulic excavators, analytical expressions were derived to calculate kinematic and force transfer functions of the main mechanisms.

The main steps on implementation of radiation processing technology - portuguese experience

International Nuclear Information System (INIS)

Luisa Botelho, M.

2010-11-01

The development of applications of ionizing radiation for Industrial purposes in Portugal began near of 1982 with the support of IAEA under the program of Cooperation and Technical Assistance - project POR/8/002. The IAEA program of Cooperation and Technical Assistance permitted that POR/08/002 took place between 1983 up to 1988. The collaboration of the International Experts and the personnel of National Laboratory of Industrial Engineering and Technology, nowadays Nuclear and Technologic Institute (ITN), allowed the construction of a Co-60 irradiation plant, designed by Tecnabexport (Russia). This facility is located in the ITN campus in Sacavem, Portugal. The main parameters studied prior to the implementation (sitting, design, construction, commissioning, operation, maintenance and foreseen decommission) were planned and executed according with the Portuguese legislation which is based on the International rules (IAEA Safety series) and Directive EURATOM 836/80, nowadays EURATOM 1493/93. A study of the geological stability of the site for future placement of the irradiation facility was done preceding the construction. The facility was constructed under Portuguese responsibility but designed and loaded with Co-60 by the Russian business rganization: Technabexport between 1987 and 1988. The whole process was supervised and approved by the ITN's Nuclear Protection and Safety Department. The Cobalt-60 irradiation facility was initially named GammaPi and later on Radiation Technologies Unit (UTR) and its management was under ITN's authority until 2003. Once established a quality system for the gamma facility, the following phase is to develop, validate and control the sterilization/disinfection process. In this step, a multidisciplinary approach and a continuous dialog with product managers and personnel must be taken into consideration in the experimental design for the correct and effective establishment of irradiation process. The knowledge of product's elements

ESD analog circuits and design

CERN Document Server

Voldman, Steven H

2014-01-01

A comprehensive and in-depth review of analog circuit layout, schematic architecture, device, power network and ESD design This book will provide a balanced overview of analog circuit design layout, analog circuit schematic development, architecture of chips, and ESD design.  It will start at an introductory level and will bring the reader right up to the state-of-the-art. Two critical design aspects for analog and power integrated circuits are combined. The first design aspect covers analog circuit design techniques to achieve the desired circuit performance. The second and main aspect pres

Designing to target cost: one approach to design/construction integration

DEFF Research Database (Denmark)

Jørgensen, Bo

2005-01-01

One approach to a more integrated construction delivery process is the concept of ‘designing to target cost’ of which the first examples of application within a lean construction framework have recently been seen. This paper introduces the main principles of the design to target cost method...... and discusses the applicability of this approach to construction. The low degree of organizational and technical continuity from one construction project to the next limits the applicability of the design for target cost approach when compared to its origin in product development of mass manufactured artefacts....... It can be argued that design to target cost may also provide a frame for developing the supply chain towards better coordination and collaboration. Thus methods of design to target cost may serve to facilitate the development of a more integrated supply chain....

Mixed-Reality Prototypes to Support Early Creative Design

Science.gov (United States)

Safin, Stéphane; Delfosse, Vincent; Leclercq, Pierre

The domain we address is creative design, mainly architecture. Rooted in a multidisciplinary approach as well as a deep understanding of architecture and design, our method aims at proposing adapted mixed-reality solutions to support two crucial activities: sketch-based preliminary design and distant synchronous collaboration in design. This chapter provides a summary of our work on a mixed-reality device, based on a drawing table (the Virtual Desktop), designed specifically to address real-life/business-focused issues. We explain our methodology, describe the two supported activities and the related users’ needs, detail the technological solution we have developed, and present the main results of multiple evaluation sessions. We conclude with a discussion of the usefulness of a profession-centered methodology and the relevance of mixed reality to support creative design activities.

Needs Analysis and Course Design; A Framework for Designing Exam Courses

Directory of Open Access Journals (Sweden)

Reza Eshtehardi

2017-09-01

Full Text Available This paper introduces a framework for designing exam courses and highlights the importance of needs analysis in designing exam courses. The main objectives of this paper are to highlight the key role of needs analysis in designing exam courses, to offer a framework for designing exam courses, to show the language needs of different students for IELTS (International English Language Testing System exam, to offer an analysis of those needs and to explain how they will be taken into account for the design of the course. First, I will concentrate on some distinguishing features in exam classes, which make them different from general English classes. Secondly, I will introduce a framework for needs analysis and diagnostic testing and highlight the importance of needs analysis for the design of syllabus and language courses. Thirdly, I will describe significant features of syllabus design, course assessment, and evaluation procedures.

Designing end-user interfaces

CERN Document Server

Heaton, N

1988-01-01

Designing End-User Interfaces: State of the Art Report focuses on the field of human/computer interaction (HCI) that reviews the design of end-user interfaces.This compilation is divided into two parts. Part I examines specific aspects of the problem in HCI that range from basic definitions of the problem, evaluation of how to look at the problem domain, and fundamental work aimed at introducing human factors into all aspects of the design cycle. Part II consists of six main topics-definition of the problem, psychological and social factors, principles of interface design, computer intelligenc

Appropriate teaching and learning strategies for the architectural design process in pedagogic design studios

Directory of Open Access Journals (Sweden)

Ashraf M. Soliman

2017-06-01

Full Text Available The national qualification framework of a country requires a certain level of knowledge and complexity of skills for an academic degree to be recognized. For architectural programs, student workload is heavy on design courses. Therefore, each course must be carefully developed to ensure that students are not overloaded. Teaching and learning strategies have different implications for courses, which occasionally result in overloading the students. This research aims to study the three main pillars of teaching and learning strategies for each design phase in pedagogic design studios. The most appropriate model for each teaching and learning strategy, including a set of the three main pillars, is then identified for each design phase. A practical strategy for managing design studios is also determined. The aforementioned three pillars are as follows: teaching and learning methods, assigned tasks or study aspects, and design communication techniques. Two research methods, namely, a literature review and a survey among design educators, are adopted. The literature review examines aspects that contribute to the design process and its phases, teaching methods, design skills, communication methods, and studio management strategies. On the basis of the literature review, the background of developments and practices in the design education process are used as constructive tools to develop the survey for design educators. Through the survey, the pillars of teaching and learning strategies that are frequently practiced in design studios are evaluated. Results of this study are classified into three ranks using the nature break classification method for numerical values. Subsequently, three priority models that correspond to teaching and learning strategies, as well as to the required skills and capabilities, are established. A group-based strategy with an interdisciplinary approach is also determined to be the most suitable technique for managing the

Overview of collective effects in the NLC main damping rings

International Nuclear Information System (INIS)

Wolski, A.; Santis, S. de

2002-01-01

The present design for the NLC Main Damping Rings (MDRs) meets the specifications for acceptance and extracted emittance, in the limit of zero current. However, the relatively large bunch charge and moderate energy mean that a variety of collective effects can impact the beam dynamics, leading to loss of stability or increase of equilibrium emittance. These effects include intrabeam scattering, impedance from numerous sources, fast ion instability, and (in the positron ring) electron cloud. In this note, we survey the expected impact on damping ring performance from each of a number of collective effects, and discuss the priorities for future studies in this area

Methodology on ageing management review for main components of a PWR NPP

International Nuclear Information System (INIS)

Dou Yikang; He Yinbiao; Xu Xuelian; Zhang Ming; Liang Xingyun

2005-01-01

According to the requirements of NNSA, for Chinese operational NPPs periodical safety review (PSR) should be carried out every 10 years. Ageing management is one of the important safety factors to be reviewed. Entrusted by Qinshan Nuclear Power Plant (QNPP), Shanghai Nuclear Engineering Research and Design Institute (SNERDI) carried out the ageing management review (AMR), as a part of the first PSR of QNPP, from 2001 to 2003. This paper summarizes the methodology of the AMR process, including screening of critical components and structures, identification of main ageing mechanisms and their indicators and the tabulated review process, etc. 15 components and structures, hereafter referred as equipment, were selected as review objects based on their significance of safety, replaceability and cost-benefit considerations. To these objects, the main ageing mechanisms and relevant ageing indicators were identified according to specific working and environmental condition, design and manufacture information, operation and maintenance history, etc. The review can be divided into two parallel parts, the review for specific equipment and the review for overall management procedures and their implementation. To typical components, such as RPV and SG, fatigue analysis based on operational transient accounting was carried out to observe the actual safety margins. Through the review, the weaknesses in ageing management and potential threats to structural integrity were identified and thus continued improvement can be made in the next period of 10 years. (authors)

Stress analysis of advanced attack helicopter composite main rotor blade root end lug

Science.gov (United States)

Baker, D. J.

1982-01-01

Stress analysis of the Advanced Attack Helicopter (AAH) composite main rotor blade root end lug is described. The stress concentration factor determined from a finite element analysis is compared to an empirical value used in the lug design. The analysis and test data indicate that the stress concentration is primarily a function of configuration and independent of the range of material properties typical of Kevlar-49/epoxy and glass epoxy.

Optimum Design of Plasma Focus

International Nuclear Information System (INIS)

Ramos, Ruben; Gonzalez, Jose; Clausse, Alejandro

2000-01-01

The optimum design of Plasma Focus devices is presented based in a lumped parameter model of the MHD equations.Maps in the design parameters space are obtained, which determine the length and deuterium pressure required to produce a given neutron yield.Sensitivity analyses of the main effective numbers (sweeping efficiencies) was performed, and lately the optimum values were determined in order to set a basis for the conceptual design

Deformation Analysis of the Main Components in a Single Screw Compressor

Science.gov (United States)

Liu, Feilong; Liao, Xueli; Feng, Quanke; Van Den Broek, Martijn; De Paepe, Michel

2015-08-01

The single screw compressor is used in many fields such as air compression, chemical industry and refrigeration. During operation, different gas pressures and temperatures applied on the components can cause different degrees of deformation, which leads to a difference between the thermally induced clearance and the designed clearance. However, limited research about clearance design is reported. In this paper, a temperature measurement instrument and a convective heat transfer model were described and used to establish the temperature of a single screw air compressor's casing, screw rotor and star wheel. 3-D models of these three main components were built. The gas force deformation, thermal- structure deformation and thermal-force coupling deformation were carried out by using a finite element simulation method. Results show that the clearance between the bottom of the groove and the top of star wheel is reduced by 0.066 mm, the clearance between the side of groove and the star wheel is reduced by 0.015 mm, and the clearance between the cylinder and the rotor is reduced by 0.01 mm. It is suggested that these deformations should be taken into account during the design of these clearances.

Main building fire drill safely concluded

CERN Document Server

CERN Bulletin

2015-01-01

Last week, a simulated fire in the stairwell of the Main Building put CERN’s emergency response procedures to the test.   Firefighters descend the stairwell in the Main Building as the simulated fire rises.   At 2 p.m. on 22 September, alarms sounded around CERN’s Main Building as an evacuation exercise got underway. A simulated fire in the  stairwell, complete with very realistic smoke, led to the evacuation of one of the busiest places at CERN. The Main Building complex includes the Carlson Wagonlit travel agency, the post office, UBS, Uniqa, the Users Office, the Staff Association and the Novae restaurant as well as the Main Auditorium, the Council Chamber and the Charpak meeting room. It was impressive to see how quickly the smoke propagated in the staircase as well as into the corridors, and equally impressive to see how smoothly, quickly and efficiently the evacuation proceeded. The...

Key issues in european reactor seismic design

International Nuclear Information System (INIS)

Cicognani, G.; Martelli, A.

1984-01-01

The paper focuses on the main problems which have arisen in FBR design in Europe due to seismic conditions. Its first part, derived from the final report of a CEC-Belgonucleaire study contract, clarifies how ''real'' is the seismic problem for each site. Then, the second and main part deals with the studies carried out in the european countries on the relevant subjects, typical of FBRs or related to specific needs of single FBRs: these studies, for which contributions were provided by ENEA, CEA, NNC and INTERATOM, concern mainly the numerical and experimental analysis of the core, the reactor vessel, the shut-down system and the reactor building of FBRs under construction or in advanced design phase. Attention is also paid to the studies started for future purposes, the feed-backs on the design due to seismic conditions, and the instructions for future reactors

Seismic design of reactors in NUCEF

Energy Technology Data Exchange (ETDEWEB)

Kurosaki, Akira [Mitsui Shipbuilding and Engineering Co. Ltd., Tokyo (Japan); Kuchiya, Masao; Yasuda, Naomitsu; Kitanaka, Tsutomu; Ogawa, Kazuhiko; Sakuraba, Koichi; Izawa, Naoki; Takeshita, Isao

1997-03-01

Basic concept and calculation method for the seismic design of the main equipment of the reactors in NUCEF (Nuclear Fuel Cycle Safety Engineering Research Facility) are described with actual calculation examples. The present paper is published to help the seismic design of the equipment and application of the authorization for the design and constructing of facilities. (author)

The design status of the liquid lithium target facility of IFMIF at the end of the engineering design activities

Energy Technology Data Exchange (ETDEWEB)

Nitti, F.S., E-mail: francesco.nitti@enea.it [IFMIF/EVEDA Project Team, Rokkasho Japan (Japan); Ibarra, A. [CIEMAT, Madrid (Spain); Ida, M. [IHI Corporation, Tokyo (Japan); Favuzza, P. [ENEA Research Center Firenze (Italy); Furukawa, T. [JAEA Research Center, Tokai-mura, Ibaraki (Japan); Groeschel, F. [KIT Research Center, Karlsruhe (Germany); Heidinger, R. [F4E Research Center, Garching (Germany); Kanemura, T. [JAEA Research Center, Tokai-mura, Ibaraki (Japan); Knaster, J. [IFMIF/EVEDA Project Team, Rokkasho Japan (Japan); Kondo, H. [JAEA Research Center, Tokai-mura, Ibaraki (Japan); Micchiche, G. [ENEA Research Center, Brasimone (Italy); Sugimoto, M. [JAEA Research Center, Rokkasho Japan (Japan); Wakai, E. [JAEA Research Center, Tokai-mura, Ibaraki (Japan)

2015-11-15

Highlights: • Results of validation and design activity for the Li loop facility of IFMIF. • Demonstration of Li target stability, with surface disturbance <1 mm. • Demonstration of start-up and shut down procedures of Li loop. • Complete design of the heat removal system and C and O purification system. • Conceptual design of N and H isotopes purification systems. - Abstract: The International Fusion Material Irradiation Facility (IFMIF) is an experimental facility conceived for qualifying and characterizing structural materials for nuclear fusion applications. The Engineering Validation and Engineering Design Activity (EVEDA) is a fundamental step towards the final design. It presented two mandates: the Engineering Validation Activities (EVA), still on-going, and the Engineering Design Activities (EDA) accomplished on schedule in June 2013. Five main facilities are identified in IFMIF, among which the Lithium Target Facility constituted a technological challenge overcome thanks to the success of the main validation challenges impacting the design. The design of the liquid Lithium Target Facility at the end of the EDA phase is here detailed.

The design status of the liquid lithium target facility of IFMIF at the end of the engineering design activities

International Nuclear Information System (INIS)

Nitti, F.S.; Ibarra, A.; Ida, M.; Favuzza, P.; Furukawa, T.; Groeschel, F.; Heidinger, R.; Kanemura, T.; Knaster, J.; Kondo, H.; Micchiche, G.; Sugimoto, M.; Wakai, E.

2015-01-01

Highlights: • Results of validation and design activity for the Li loop facility of IFMIF. • Demonstration of Li target stability, with surface disturbance <1 mm. • Demonstration of start-up and shut down procedures of Li loop. • Complete design of the heat removal system and C and O purification system. • Conceptual design of N and H isotopes purification systems. - Abstract: The International Fusion Material Irradiation Facility (IFMIF) is an experimental facility conceived for qualifying and characterizing structural materials for nuclear fusion applications. The Engineering Validation and Engineering Design Activity (EVEDA) is a fundamental step towards the final design. It presented two mandates: the Engineering Validation Activities (EVA), still on-going, and the Engineering Design Activities (EDA) accomplished on schedule in June 2013. Five main facilities are identified in IFMIF, among which the Lithium Target Facility constituted a technological challenge overcome thanks to the success of the main validation challenges impacting the design. The design of the liquid Lithium Target Facility at the end of the EDA phase is here detailed.

30 CFR 75.302 - Main mine fans.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Main mine fans. 75.302 Section 75.302 Mineral... SAFETY STANDARDS-UNDERGROUND COAL MINES Ventilation § 75.302 Main mine fans. Each coal mine shall be ventilated by one or more main mine fans. Booster fans shall not be installed underground to assist main mine...

ITER plasma facing components, design and development

International Nuclear Information System (INIS)

Vieider, G.; Cardella, A.; Akiba, M.; Matera, R.; Watson, R.

1991-01-01

The paper summarizes the collaborative effort of the ITER Conceptual Design Activity (CDA) on Plasma Facing Components (PFC) which focused on the following main tasks: (a) The definition of basic design concepts for the First Wall (FW) and Divertor Plates (DP), (b) the analysis of the performance and likely lifetime of these PFC designs including the identification of major critical issues, (c) the start of R and D work giving already first results, and the definition of the required further R and D program to support the contemplated ITER Engineering Design Activity (EDA). From the ITER CDA effort on PFC it is mainly concluded that: (a) The expected PFC operating conditions lead to design solutions at the limit of present technology in particular for the divertor, which may constrain the overall machine performance, (b) the development of convincing PFC designs requires an intensified R and D effort both on PFC technology and plasma physics. (orig.)

Reactor System Design

International Nuclear Information System (INIS)

Chi, S. K.; Kim, G. K.; Yeo, J. W.

2006-08-01

SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

Design and analysis of sustainable computer mouse using design for disassembly methodology

Science.gov (United States)

Roni Sahroni, Taufik; Fitri Sukarman, Ahmad; Agung Mahardini, Karunia

2017-12-01

This paper presents the design and analysis of computer mouse using Design for Disassembly methodology. Basically, the existing computer mouse model consist a number of unnecessary part that cause the assembly and disassembly time in production. The objective of this project is to design a new computer mouse based on Design for Disassembly (DFD) methodology. The main methodology of this paper was proposed from sketch generation, concept selection, and concept scoring. Based on the design screening, design concept B was selected for further analysis. New design of computer mouse is proposed using fastening system. Furthermore, three materials of ABS, Polycarbonate, and PE high density were prepared to determine the environmental impact category. Sustainable analysis was conducted using software SolidWorks. As a result, PE High Density gives the lowers amount in the environmental category with great maximum stress value.

The DAG project, a 4m class telescope: the telescope main structure performances

Science.gov (United States)

Marchiori, G.; Busatta, A.; Ghedin, L.; Marcuzzi, E.; Manfrin, C.; Battistel, C.; Pirnay, O.; Flebus, Carlo; Yeşilyaprak, C.; Keskin, O.; Yerli, S.

2016-07-01

Dogu Anatolu Gözlemevi (DAG-Eastern Anatolia Observatory) Project is a 4m class optical, near-infrared Telescope and suitable enclosure which will be located at an altitude of 3.170m in Erzurum, Turkey. The DAG telescope is a project fully funded by Turkish Ministry of Development and the Atatürk University of Astrophysics Research Telescope - ATASAM. The Project is being developed by the Belgian company AMOS (project leader), which is also the optics supplier and EIE GROUP, the Telescope Main Structure supplier and responsible for the final site integration. The design of the Telescope Main Structure fits in the EIE TBO Program which aims at developing a Dome/Telescope systemic optimization process for both performances and competitive costs based on previous project commitments like NTT, VLT, VST and ASTRI. The optical Configuration of the DAG Telescope is a Ritchey-Chretien with two Nasmyth foci and a 4m primary thin mirror controlled in shape and position by an Active Optic System. The main characteristics of the Telescope Main Structure are an Altitude-Azimuth light and rigid structure system with Direct Drive Systems for both axis, AZ Hydrostatic Bearing System and Altitude standard bearing system; both axes are equipped with Tape Encoder System. An innovative Control System characterizes the telescope performance.

Sustainable Chemical Processes and Products. New Design Methodology and Design Tools

OpenAIRE

Korevaar, G.

2004-01-01

The current chemical industry is not sustainable, which leads to the fact that innovation of chemical processes and products is too often hazardous for society in general and the environment in particular. It really is a challenge to implement sustainability considerations in the design activities of chemical engineers. Therefore, the main question of this thesis is: how can a trained chemical engineer develop a conceptual design of a chemical process or a chemical product in such a way that ...

Design of Usui bridge (PC cable stayed bridge). Usuihashi (PC shachokyo) no sekkei ni tsuite

Energy Technology Data Exchange (ETDEWEB)

Kido, M.; Iizuka, Y. (Japan Highway Public Corp., Tokyo (Japan)); Tanaka, S.; Otsuka, K. (P.S. Concrete Co. Ltd. Kajima Corp. Joint Venture, Tokyo (Japan)); Kitakuni, S. (Kajima Corp., Tokyo (Japan))

1991-11-30

Structure and design of single suspension PC cable bridge, which is first kind of high way bridge in Japan and aiming to start for general use by March, 1993, are reported. As a construction outline, main construction quantity and general layout of the whole bridge together with the selective detail and characteristics of the diagonal member, tower, main girder and tower support member, are cited. Design conditions( load, materials, allowable stress and others ), basic plan of the design, and structure analysis( surface stress framed structure analysis, stereoscopic framework analysis and FEM analysis of local stress ) are explained. Design of structure member like main girder is based on diagonal member tension, wave shearing force, level of diagonal strain stress, bending stress when diagonal member anchors the deformed main tower caused by living load during earth quake, principal stress of main tower junction and local stress etc. Main tower support member design is based on the results of corbel shearing force at varied cross section and main stress, and diagonal member design is decided by allowable stress. Diagonal member anchorage traverse beam design depends on bending moment of traverse beam and shearing force. 3 refs., 15 figs., 1 tab.

Propagation engineering in radio links design

CERN Document Server

Ghasemi, Abdollah; Ghasemi, Farshid

2013-01-01

Propagation Engineering in Radio Link Design covers the basic principles of radiowaves propagation in a practical manner.  This fundamental understanding enables the readers to design radio links efficiently. This book elaborates on new achievements as well as recently developed propagation models.  This is in addition to a comprehensive overview of fundamentals of propagation in various scenarios. It examines theoretical calculations, approaches and applied procedures needed for radio links design. The authors study and analysis of the main propagation phenomena and its mechanisms based on the recommendations of International Telecommunications Union, (ITU). The book has been organized in 9 chapters and examines the role of antennas and passive reflectors in radio services, propagation mechanisms related to radar, satellite, short distance, broadcasting and trans-horizon radio links, with two chapters devoted to radio noise and main  parameters of radio link design. The book presents some 278 illustration...

PROPOSAL OF A MODEL MANAGEMENT TO SMALL DESIGN COMPANIES

Directory of Open Access Journals (Sweden)

Otávio José de OLIVEIRA

2008-11-01

Full Text Available The main purpose of this paper is the proposition of a management model specifically developed for small building design firms, aligned with their needs and particularities. The field research was conducted with a qualitative approach through the analysis of four case studies in small building design firms acting mainly in São Paulo City. The data collection was accomplished through semi-structured interviews, direct observation and analysis of documents. The proposed model includes guidance to the management of the core processes and activities of small building design firms, such as: organizational structure; strategic planning; planning and control of design process; costs management; sales management; information systems; human resources management; services added to the design; and performance evaluation. Key-words: design firms; design process; building construction.

Main group adducts of carbon dioxide and related chemistry (LDRD 149938).

Energy Technology Data Exchange (ETDEWEB)

Barry, Brian M. (University of New Mexico, Albuquerque, NM); Kemp, Richard Alan; Stewart, Constantine A.; Dickie, Diane A. (University of New Mexico, Albuquerque, NM)

2010-11-01

This late-start LDRD was broadly focused on the synthetic attempts to prepare novel ligands as complexing agents for main group metals for the sequestration of CO{sub 2}. In prior work we have shown that certain main group (p block elements) metals such as tin and zinc, when ligated to phosphinoamido- ligands, can bind CO{sub 2} in a novel fashion. Rather than simple insertion into the metal-nitrogen bonds to form carbamates, we have seen the highly unusual complexation of CO{sub 2} in a mode that is more similar to a chemical 'adduct' rather than complexation schemes that have been observed previously. The overarching goal in this work is to prepare more of these complexes that can (a) sequester (or bind) CO{sub 2} easily in this adduct form, and (b) be stable to chemical or electrochemical reduction designed to convert the CO{sub 2} to useful fuels or fuel precursors. The currently used phosphinoamido- ligands appear at this point to be less-stable than desired under electrochemical reduction conditions. This instability is believed due to the more delicate, reactive nature of the ligand framework system. In order to successfully capture and convert CO{sub 2} to useful organics, this instability must be addressed and solved. Work described in the late-start LDRD was designed to screen a variety of ligand/metal complexes that a priori are believed to be more stable to polar solvents and possible mild hydrolytic conditions than are the phosphinoamido-ligands. Results from ligand syntheses and metal complexation studies are reported.