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Sample records for materials project barc

  1. BARC safety framework

    International Nuclear Information System (INIS)

    Jayarajan, K.; Taly, Y.K.

    2017-01-01

    BARC has a large number facilities and a large number of employees. It has a variety of activities, carried out in different parts of India. All activities related nuclear fuel cycle are carried out in BARC. In addition, BARC has many non-nuclear facilities and projects. Therefore, regulation of BARC facilities is a challenging task. BSC was constituted in the year 2000 to address the challenges of regulating safety of the projects, plants and facilities of BARC. It has a comprehensive regulatory framework, which makes use of the expertise of more than one thousand experts of BARC for safety and regulatory activities. BSC has completed hundred meetings and issued regulatory consents to many projects, facilities and activities. During the last 17 years, BSC has constituted 44 committees in three tiers, which had conducted more than 2000 meetings to support safety and regulatory activities of BSC

  2. BARC highlights '88

    International Nuclear Information System (INIS)

    1989-01-01

    Highlights of research and development activities of the Bhabha Atomic Research Centre (BARC), Bombay during 1988 are presented in chapters entitled: Physical Sciences, Chemical Sciences, Materials and Materials Sciences, Radioisotopes, Reactors, Fuel Cycle, Radiological Safety and Protection, Electronics and Instrumentation, Engineering Services, and Life Sciences. Main thrust of the R and D activities of BARC is on nuclear power reactor technology and all stages of nuclear fuel cycle. Some activities are also in the frontier areas such as high temperature superconductivity and inertial confinement fusion. (M.G.B.). figs., tabs., coloured ills

  3. Electron beam accelerator at BARC-BRIT complex - electron beam processing of materials and industrial utilization

    International Nuclear Information System (INIS)

    Khader, S.A.; Patkari, R.K.; Sharma, K.S.S.

    2013-01-01

    During the last decade, the 2MeV/20kW electron beam (EB) accelerator located at BARC-BRIT complex, Vashi has been successfully utilised for non-thermal applications to develop speciality products useful for the industry. Polymer materials are exposed to high energy electrons to induce crosslinking and degradation reactions in a number of industrial products without the use of external chemicals and additives. Various EB crosslinked products viz. PE O-rings, automotive components, automobile tyres, electrical insulations, etc have been found to be much superior in quality compared to those produced conventionally. A process has been developed to enhance colours in the polished diamonds and gem stones using EB irradiation at the facility which has attracted much attention in the Indian diamond industry as a value-addition process. Recycling of polymer waste processed under EB to produce microfine PTFE powder, to reuse in automobile industry etc. has shown good potential for the industrial use. The process feasibility both in terms of economics and technology have been amply demonstrated on a technological scale by installing special conveyors at our facility for irradiating various industrial products. Around 100 km cable insulations, 1.5 million PE O-rings and more than 40000 carats of polished diamonds have been processed in our facility over a period of time on commercial scale. Encouraged with the results, Indian private entrepreneurs have set up dedicated EB machines in some of the most significant industries producing wire and cables, electrical gadgets based on polymer composites, automobile tyres and diamonds. The products are unique in properties and are in some cases, became import substitutes. The industry is now fully geared up to adapt the technology by realising the advantages viz ease in adaptability, convenient, safe and environmental-friendly nature. Encouraged by the process demonstrations, while five EB accelerators were setup and are in operation

  4. BARC highlights 86

    International Nuclear Information System (INIS)

    1987-01-01

    The Bhabha Atomic Research Centre (BARC), Bombay, is the premier multidisciplinary research establishment of the Department of Atomic Energy (India). It provides Research and Development (R and D) support to the nuclear programmes of the country. Some of its important R and D activities and achievements during 1986 are described in brief in the chapters entitled: Physical Sciences, Chemical Sciences, Materials and Materials Sciences, Life Sciences, Reactors, Fuel Cycle, and Electronics and Instrumentation. The entire text is illustrated with a number of diagrams and photographs. (M.G.B.)

  5. Detection of radioactive material in public places: BARC's handheld tele radionuclide detector

    International Nuclear Information System (INIS)

    Bharade, S.K.; Sinha, Vineet; Vinod, M.; Ananthakrishnan, T.S.; Jindal, G.D.; Srivastava, Shikha; Sarade, Bhagyashree; Kamble, Ashok D.; Pithawa, C.K.; Subramanian, Venkat

    2011-01-01

    Electronics Division, BARC has developed a compact and portable system for detection of radioactive nuclides like 60 Co, 137 Cs etc. with high levels of radioactivity. These radioactive sources, because of their long life and relative ease of availability, have the potential of being used in radiological dispersion devices (dirty bombs) for panic creation in public places. The unit comprises of a compact CsI detector, photo diode and front-end electronics, micro-controller, a GPS module and Blue-tooth connectivity. The application software running on the mobile phone provides the interface as well as transmission of data to remote server. This is highly suitable for covert operations. The person, who carries this instrument, suitably camouflaged, also has a mobile phone in his pocket, which is connected to the system via blue tooth. On detection of activity above set limit, the system sends an alarm to the mobile phone. The mobile phone can be kept in vibration mode in order to avoid any undue attention. The graphical display on screen of mobile phone provides an indication of activity and the isotope identification. Simultaneously, the mobile phone sends information about the activity detected and source identification automatically along with the location of the instrument (longitude and latitude), provided by the GPS module in the instrument, to a remote server. The remote server provides radiation information on a map with position-coordinates. Based on this, necessary action can be initiated by the security personnel. (author)

  6. Understanding deviations in lithographic patterns near interfaces: Characterization of bottom anti-reflective coatings (BARC) and the BARC resist interface

    Science.gov (United States)

    Lenhart, Joseph L.; Fischer, Daniel; Sambasivan, Sharadha; Lin, Eric K.; Wu, Wen-Li; Guerrero, Douglas J.; Wang, Yubao; Puligadda, Rama

    2007-02-01

    Interactions between a bottom anti-reflective coating (BARC) and a photoresist can critically impact lithographic patterns. For example, a lithographic pattern can shrink or spread near a BARC interface, a process called undercutting or footing respectively, due to incompatibility between the two materials. Experiments were conducted on two industrial BARC coatings in an effort to determine the impact of BARC surface chemistry on the footing and undercutting phenomena. The BARC coatings were characterized by near edge X-ray absorption fine structure (NEXAFS), contact angle measurements, and neutron and X-ray reflectivity. Contact angle measurement using a variety of fluids showed that the fluid contact angles were independent of the type of BARC coating or the BARC processing temperature. NEXAFS measurements showed that the surface chemistry of each BARC was also independent of the processing temperature. These results suggest that acid-base interactions at the BARC-resist interface are not the cause of the footing-undercutting phenomena encountered in lithographic patterns.

  7. Development of membrane technology in BARC

    International Nuclear Information System (INIS)

    Misra, B.M.

    2003-01-01

    BARC has been engaged in research and development work on pressure-driven membrane technology from laboratory to pilot plant scale and its commercial scale deployment, for sea and brackish water desalination into potable water, effluent water treatment and water reuse and in various industrial separations including decontamination of radioactive liquid effluents for their safe disposal into the environment. This paper gives a brief description of pressure-driven membrane processes, reverse osmosis, nano filtration, ultrafiltration and micro filtration. Selection of polymeric candidate materials, preparation of semi-permeable membranes and their characterization has been discussed. Various applications of these processes conducted on pilot plant scale have been presented. Large scale deployment of membrane processes for sea water desalination has been indicated. Research and development at BARC has thus resulted in the indigenous development of membrane processes for commercial scale operation. (author)

  8. Molecular laser isotope separation programme at BARC

    International Nuclear Information System (INIS)

    Sarkar, Sisir K.; Parthasarathy, Venkatachari

    2007-09-01

    Little over thirty years ago, BARC ventured into a new frontier of scientific research: Molecular Laser Isotope Separation (MLIS) programme based on the interaction of lasers with molecules. The initial project was a scheme to produce enriched uranium. The idea was to use the intense, monochromatic light of lasers to break the chemical bonds of only those molecules containing the fissionable isotope uranium-235. At present the programme is evolving around separation of low and middle mass isotopes, namely sulphur 34/33/32, oxygen 17/18, carbon 13/12, hydrogen T/D/H to be followed by an advanced engineering programme designed to lead to a demonstration plant. The latest results have come very close to the design parameters specified for a full-scale separation of carbon isotopes. All these expertise provide an infra structure for future front line R and D activities in the general area of Laser Photochemical Technology which would include i) LIS of other useful elements ii) Material processing and iii) Fuel reprocessing/ waste management (author)

  9. BARC-TIFR Pelletron Linac facility

    International Nuclear Information System (INIS)

    Gore, J.A.; Gupta, A.K.; Saxena, A.

    2017-01-01

    The Pelletron Accelerator, set up as a collaborative project between the Bhabha Atomic Research Centre and the Tata Institute of Fundamental Research, has been serving as the workhorse for the heavy ion accelerator based research in India since its commissioning in December 30, 1988. The facility was augmented with an indigenously developed superconducting Linac booster to enhance the energy of the Pelletron accelerated beams and was fully commissioned on November 28, 2007. The augmented facility is renamed as Pelletron Linac facility (PLF). While the PLF is predominantly utilized by the experimental users from BARC and TIFR, the users include researchers from other research institutions and universities within India and abroad

  10. Preparation of safety and regulatory document for BARC Facilities

    International Nuclear Information System (INIS)

    Prasad, S.S.; Jayarajan, K.

    2017-01-01

    In India, the necessary codes and safety guidelines for achieving the safety objectives are provided by the Atomic Energy Regulatory Board (AERB), which are in conformity with the principles of radiation protection as formulated by the International Council of Radiation Protection (ICRP) and International Atomic Energy Agency (IAEA). The same is followed by BARC Safety Council (BSC), which is the regulatory body for the BARC facilities. In addition to all types of fuel cycle facilities, BSC regulates safety of many types of conventional facilities. Many such types of facilities and projects are not under the regulatory purview of AERB. Therefore, the Council has also initiated a programme for development and publication of safety documents for installations in BARC in the fields/ topics yet not addressed by IAEA or AERB. This makes the task pioneering, as some of the areas taken up for defining the regulatory requirements are new, where standard regulatory documents are not available

  11. BARC solution for burn injuries

    CERN Multimedia

    2003-01-01

    The Bhabha Atomic Research Centre (BARC), has developed Hydrogel which is expected to be mass marketed soon in India. Dr Anil Kakodkar, Chairman of Atomic Energy Commission, said the product not only heals the wound, but also eliminates scars (1/2 page).

  12. Dose apportionment for BARC facilities

    International Nuclear Information System (INIS)

    Preetha, J.; Sundar, D.; Munshi, S.K.; Pradeepkumar, K.S.

    2017-01-01

    One of the important responsibilities of BARC Safety Council (BSC) is to ensure that appropriate measures are in place to protect the members of the public and the environment from the undue effects of radioactive releases from the facilities regulated by BSC. It is with this aim in mind that a Standing Committee for Dose Apportionment (DAC) was constituted by BSC in 2005, to ensure that the limits are set by the regulatory body for release of low-level gaseous and liquid effluents into the environment from BARC facilities. There are three Committees for dose apportionment constituted by the Chairman, BSC, viz, DAC-TK for Tarapur and Kalpakkam facilities, DAC-TV for Trombay and DACSF for specific faculties

  13. BARC highlights 1991

    International Nuclear Information System (INIS)

    1992-01-01

    Some of the important research and development (R and D) activities carried out at the Centre during the last two or three years are described in brief. The descriptions are arranged under the headings : Physical Sciences, Chemical Sciences, Material and Materials Science, Radioisotopes, Reactors, Fuel Cycle, Radiological Safety and Protection, Electronics and Instrumentation, Engineering Services, and Life Sciences. The text is illustrated with a number of photographs - some of them coloured. (M.G.B.)

  14. Bio-organic chemistry at BARC

    International Nuclear Information System (INIS)

    Sharma, A.; Ghosh, S.K.; Chattopadhyay, S.

    2009-01-01

    Bioorganic chemistry plays a pivotal role of co-ordination amongst the research and developmental activities of physical, biological, material and nuclear sciences. Understandably, the domain of bioorganic chemistry encompasses overlapping scientific fields, and often involves multi-disciplinary subjects. The research activities of bioorganic research at BARC are, therefore directed with reference to deliverables, relevant to various nuclear and non-nuclear programmes of the department. Also, the activities of the division are fine tuned to address the contemporary needs. It is now well recognized that organic compounds are essential in various programmes of nuclear technology. These include solvents and membranes for the back-end process, carrier molecules for radiopharmaceuticals, optoelectrical materials and sensors for high tech applications etc. Coupled with this, bioorganics also form integral part of the departmental mission-oriented societal programmes in the areas of health and agriculture

  15. Investigation of UFO defect on DUV CAR and BARC process

    Science.gov (United States)

    Yet, Siew Ing; Ko, Bong Sang; Lee, Soo Man; May, Mike

    2004-05-01

    Photo process defect reduction is one of the most important factors to improve the process stability and yield in sub-0.18um DUV process. In this paper, a new approach to minimize the Deep-UV (DUV) Chemically Amplified Resist (CAR) and Bottom Anti-Reflective Coating (BARC) induced defect known as UFO (UnidentiFied Object) defect will be introduced. These defects have mild surface topography difference on BARC; it only exists on the wide exposed area where there is no photoresist pattern. In this test, Nikon KrF Stepper & Scanner and TEL Clean track were used. Investigation was carried out on the defect formulation on both Acetal and ESCAP type of photoresist while elemental analysis was done by Atomic Force Microscope (AFM) & Auger Electron Spectroscopy (AES). Result indicated that both BARC and photoresist induce this UFO defect; total defect quantity is related with Post Exposure Bake (PEB) condition. Based on the elemental analysis and process-split test, we can conclude that this defect is caused by lack of acid amount and low diffusivity which is related to PAG (Photo Acid Generator) and TAG (Thermal Acid Generator) in KrF photoresist and BARC material. By optimizing photoresist bake condition, this UFO defect as well as other related defect such as Satellite defect could be eliminated.

  16. BARC annual report 1987

    International Nuclear Information System (INIS)

    1988-11-01

    The report summarises the Research and Development (R and D) activities of the Bhabha Atomic Research Centre, Bombay, during 1987. These R and D activities are described in the chapters entitled: Physical Sciences, Chemical S ciences, Materials and Materials Sciences, Radioisotopes, Reactors, Fuel Cycle, Radiological Safety and Protection, Electronics and Instrumentation, Engineering Services, and Life Sciences. Activities in the fields of remote handling and robotics, technology transfer, and auxiliary activities like technical information, human resources and development etc. are dealt in the chapter entitled General. At the end of each chapter, a list of publications by the scientists in the corresp onding subject field is given. Some of the major highlights of the work during 1987 are: (1) DHRUVA reactor became fully operational at its rated capacity making neutrons available for isotope production and studies in neutron scattering and condensed matter, (2) R and D activities were extended to study h igh temperature superconductivity in both fundamental and applied aspects and (3) a laboratory for production of 32 P-biomolecules was set up at the Centre for Cellular and Molecular Biology at Hyderabad. (M.G.B.)

  17. Proceedings of the theme meeting on the journey of BARC Safety Council for strengthening safety culture in BARC facilities: 2000-2017

    International Nuclear Information System (INIS)

    Jayarajan, K.; Jolly, V.M.

    2017-07-01

    The book has about one hundred articles, written by the regulators and the authorities of the facilities and projects of BARC. The articles are organised into four parts. Part-I gives an overview of the history of safety regulation in BARC and the details of BARC Safety Framework. Part-II of the book has articles about the facilities and projects of BARC, for which BSC had issued of regulatory consents. The facility-specific articles, written by the concerned project/facility authorities, emphasis safety aspects of the facilities and the regulatory processes they had undergone. This part is divided into seven sections, based on the broad category of facility. Experts in the concerned areas have written general articles on each category of facility. The Part-III consists of the work carried out by the specialised committees, which are under the purview of BSC. Some of the other regulatory activities of BSC are summarised in Part-IV of this book. In addition to safety and regulatory activities of BSC, the book contains the details of the major facilities and upcoming projects of BARC. Papers relevant to INIS are indexed separately

  18. Theory and verification manual for BARC-R6 software

    International Nuclear Information System (INIS)

    Rastogi, Rohit; Bhasin, Vivek; Vaze, K.K.; Kushwaha, H.S.

    2001-01-01

    This report presents the technical description of the BARC-R6 computer code that has been developed in Reactor Safety Division, BARC. The program has been designed to run on Windows95 based PCs. The R6 method is a tool, which can perform analysis considering fracture and plastic instability together as failure criteria. The R6 method for analyzing flawed components requires construction of number of graphs. The results of study are arrived at by analyzing these graphs. BARC- R6 is designed with a highly intuitive graphical user interface for input as well as output. This report presents the implementation details of the program. The current version has provision for any flaw orientation and type in pipes and elbows. This program will be highly useful for fracture assessment and Leak Before Break (LBB) qualification for Nuclear Power Plant (NPP) piping. The complete PHT piping of any typical NPP can be assessed with in a very short time. It is capable of handling Option-1 and Option-2 Failure Assessment Line (FAL) for both Category-1 and Category-3 type analysis. It has provision for exhaustive sensitivity analyses for judging the significance of margins with respect to variation in material properties, crack sizes etc. The report is divided into 6 sections. The first section introduces the document. The details offer method are presented in the second section. This is followed by the technical description of the program. The fourth section lists many benchmark problems solved to highlight its usage and validation. These benchmark problems cover the wide range of cases encountered in the practical situations. The user manual is provided in the fifth section. The sixth section contains the references used in this report. This is followed by an appendix containing the co-relations for stress intensity factor and limit loads, used in the BARC-R6 code. (author)

  19. Regulatory role and approach of BARC Safety Council in safety and occupational health in BARC facilities

    International Nuclear Information System (INIS)

    Rajdeep; Jayarajan, K.; Taly, Y.K.

    2016-01-01

    Bhabha Atomic Research Centre is involved in multidisciplinary research and developmental activities, related to peaceful use of nuclear energy and its societal benefits. In order to achieve high level of performance of these facilities, the best efforts are made to maintain good health of the plant personnel and good working conditions. BARC Safety Council (BSC), which is the regulatory body for BARC facilities, regulates radiation safety, industrial safety and surveillance of occupational health, by implementing various rules and guidelines in BARC facilities. BARC Safety framework consists of various committees in a 3-tier system. The first tier is BSC, which is the apex body authorized for issuing directives, permissions, consents and authorizations. It is having responsibility of ensuring protection and safety of public, environment, personnel and facilities of BARC through enforcement of radiation protection and industrial safety programmes. Besides the 18 committees in 2"n"d tier, there are 6 other expert committees which assist in functioning of BSC. (author)

  20. Management of chemical disposal in BARC

    International Nuclear Information System (INIS)

    Shenoy, K.T.; Deolekar, Shailesh

    2017-01-01

    Most of the activities in BARC are of radiological in nature and are regulated as per Atomic Energy Act 1962. The radioactive waste generated is managed safely as per Atomic Energy (Safe Disposal of Radioactive Waste) Rules, 1987. However, many developmental activities related to nuclear fuel cycle and laboratories, which support the quality control aspects, generate inactive chemical waste. In addition, being multidisciplinary in nature, BARC carries out research in frontiers of chemical science for societal benefit and academic interest. All these scientific activities over the decades have resulted in accumulation of many partially used/surplus laboratory chemicals. These chemicals are in large varieties though small in terms of quantity. Although these chemicals do not have any further utility and commercial value, can add to potential hazards and hence require safe disposal. Considering this, BARC Safety Council(BSC) has re-constituted the 'Advisory Committee for Chemical Disposal (ACCD)' on March 18, 2016

  1. Regulatory measures for occupational health monitoring in BARC facilities

    International Nuclear Information System (INIS)

    Rajdeep; Chattopadhyay, S.

    2017-01-01

    Bhabha Atomic Research Centre (BARC) is the premier organization actively engaged in the research and developmental activities related to nuclear science and technology for the benefit of society and the nation. BARC has various facilities like nuclear fuel fabrication facilities, research reactors, spent fuel storage facilities, nuclear fuel re-cycling facilities, radioactive waste management facilities, machining workshops and various Physics, Chemistry and Biological laboratories. In BARC, aspects related to Occupational Safety and Health (OSH) are given paramount importance. The issues related OSH are subjected to multi-tier review process. BARC Safety Council (BSC) is the apex committee in the three-tier safety and security review framework of BARC. BSC functions as regulatory body for BARC facilities. BSC is responsible for occupational safety and health of employees in BARC facilities

  2. BARC technologies for benefit of farming community

    International Nuclear Information System (INIS)

    Mehetre, S.T.; Venugopalan, V.P.

    2017-01-01

    BARC has developed several technologies for the benefit of farming community, many of which have become very popular amongst farmers in India. Nisargaruna biogas plant has been developed at BARC for processing different types of biodegradable wastes, including agriculture waste generated in farmers' fields. This technology has been widely adopted across various sectors of society. Recently, it has been adapted for the slaughterhouse waste also. Soil organic carbon is an indicator of soil health. A field test kit called Soil Organic Carbon Detection Kit has been developed at BARC. This is a very quick, accurate and easy to perform test, using which a farmer can know the organic carbon levels of his soil within a short time. This technology has been transferred to six companies and products based on the technology are available in the market. Demonstration of this kit can be arranged, where soil samples from farmers' field can be analysed and measures suggested for soil improvement. Biological control of insect and disease has gained significance during recent times, particularly due to ill effects of pesticide chemicals. Different technologies developed at BARC in this area include Trichoderma mass multiplication medium, Trichoderma virens mutant strain for better disease control and neem based microfine formulation for enhanced insect control. All these technologies have tremendous application in agriculture. Products based on these technologies are available in the market and display of these products can be arranged at the venue. Using radiation induced mutations, BARC has developed 42 crop varieties; these have been notified and released for commercial cultivation in different agro-climatic zones in the country. The improved characters include higher yield, earliness, large seed size, resistance to biotic and abiotic stresses

  3. Bhabha Atomic Research Centre (BARC) annual report 1985-86

    International Nuclear Information System (INIS)

    1987-01-01

    The research and development (R and D) activities and accomplishments during the financial year 1985-86 of the Bhabha Atomic Research Centre, Bombay are reported. The BARC is a multidisciplinary laboratory engaged in R and D activities in the field of nuclear energy. The main thrust of the R and D activities of the Centre is aimed at: (1) achieving targets of India's nuclear power programme, (2) indigenisation of the various steps in the nuclear fuel cycle, (3) developing and propagating peaceful applications of nuclear science and technology in the country in fields such as agriculture, medicine and industry, (4) providing scientific support to regulatory functions associated with nuclear facilities and radiation protection activities in the country. The salient features of these R and D activities are described in the chapters entitled: (1) physical sciences, (2) chemical sciences, (3) materials and materials sciences, (4) life sciences, (5) radioisotopes, (6) reactors, (7) fuel cycle, (8) health and safety, (9) electronics and instrumentation, and (10) technical services. A list of publications by the staff-members during the report period is given at the end of each chapter. The R and D activities of the outstation units of BARC, namely, Nuclear Research Laboratory at Srinagar, High Altitude Research Laboratory at Gulmarg, Variable Energy Cyclotron Centre at Calcutta and Gauribidanur Seismic Array near Bangalore are also covered in the report. Other activities of the Centre include technology transfer and manpower training which are also described briefly. (M.G.B.)

  4. Folded tandem ion accelerator facility at BARC

    International Nuclear Information System (INIS)

    Agarwal, Arun; Padmakumar, Sapna; Subrahmanyam, N.B.V.; Singh, V.P.; Bhatt, J.P.; Ware, Shailaja V.; Pol, S.S; Basu, A.; Singh, S.K.; Krishnagopal, S.; Bhagwat, P.V.

    2017-01-01

    The 5.5 MV single stage Van de Graaff (VDG) accelerator was in continuous operation at Nuclear Physics Division (NPD), Bhabha Atomic Research Centre (BARC) since its inception in 1962. During 1993-96, VDG accelerator was converted to a Folded Tandem Ion Accelerator (FOTIA). The scientists and engineers of NPD, IADD (then a part of NPD) along with several other divisions of BARC joined hands together in designing, fabrication, installation and commissioning of the FOTIA for the maximum terminal voltage of 6 MV. After experiencing the first accelerated ion beam on the target from FOTIA during April 2000, different ion species were accelerated and tested. Now this accelerator FOTIA is in continuous use for different kind of experiments

  5. Regulatory measures of BARC Safety Council to control radiation exposure in BARC Facilities

    International Nuclear Information System (INIS)

    Rajdeep; Jolly, V.M.; Jayarajan, K.

    2018-01-01

    Bhabha Atomic Research Centre is involved in multidisciplinary research and developmental activities, related to peaceful use of nuclear energy including societal benefits. BARC facilities at different parts of India include nuclear fuel fabrication facilities, research reactors, nuclear recycle facilities and various Physics, Chemistry and Biological laboratories. BARC Safety Council (BSC) is the regulatory body for BARC facilities and takes regulatory measures for radiation protection. BSC has many safety committees for radiation protection including Operating Plants Safety Review Committee (OPSRC), Committee to Review Applications for Authorization of Safe Disposal of Radioactive Wastes (CRAASDRW) and Design Safety Review Committees (DSRC) in 2 nd tier and Unit Level Safety Committees (ULSCs) in 3 rd tier under OPSRC

  6. Nordic project food contact materials

    DEFF Research Database (Denmark)

    Li, Ågot; Tesdal Håland, Julie; Petersen, Jens Højslev

    Denmark, Finland, Faroe Islands, Iceland, Norway and Sweden have in 2013––2015 conducted a Nordic project on food contact materials. Food contact materials are used in all stages of food production and can be a general source of contamination. The food safety authorities in most of the Nordic...... countries have had a limited focus on the FCM area with the exception of Denmark and Finland. The aim of the project was therefore to control establishments producing, importing or using plastic food contact materials as well as to increase the knowledge of the inspectors performing these controls....... The focus of the inspections was to control the declaration of compliance (DoC) for plastic food contact materials. The requirement for a Doc is mandatory in order to ensure that the FCM complies with the legislation. In addition some products were analyzed for phthalates....

  7. Regulatory inspection of BARC facilities

    International Nuclear Information System (INIS)

    Rajdeep; Jayarajan, K.

    2017-01-01

    Nuclear and radiation facilities are sited, constructed, commissioned, operated and decommissioned, in conformity with the current safety standards and codes. Regulatory bodies follow different means to ensure compliance of the standards for the safety of the personnel, the public and the environment. Regulatory Inspection (RI) is one of the important measures employed by regulatory bodies to obtain the safety status of a facility or project and to verify the fulfilment of the conditions stipulated in the consent

  8. Radioactive materials in construction projects

    International Nuclear Information System (INIS)

    Herrmann, Ralf; Ohlendorf, Frank; Kaltz, Andrea Christine

    2014-01-01

    Till 1990 residues often of the former uranium mining were partly used as building material for road construction, terrain compensation and house construction in Saxony. These recommendations for action are addressed to applicants, planners and building constructors in the engineering and construction sector. It provides information for planning, preliminary investigations, applications, construction supervision related to radiation protection measures and documentation of construction projects where radioactive materials are expected.

  9. Via fill properties of organic BARCs in dual-damascene application

    Science.gov (United States)

    Huang, Runhui

    2004-05-01

    With the introduction of copper as the interconnect metal, the Dual Damascene (DD) process has been integrated into integrated circuit (IC) device fabrication. The DD process utilizes organic bottom anti-reflective coatings (BARCs) not only to eliminate the thin film interference effects but also to act as via fill materials. However, three serious processing problems are encountered with organic BARCs. One is the formation of voids, which are trapped gas bubbles (evaporating solvent, byproduct of the curing reaction and air) inside the vias. Another problem is non-uniform BARC layer thickness in different via pitch areas. The third problem is the formation of fences during plasma etch. Fences are formed from materials that are removed by plasma and subsequently deposited on the sidewall surrounding the via openings during the etching process. Voids can cause variations in BARC top thickness, optical properties, via fill percentage, and plasma etch rate. This study focuses on the factors that influence the formation of voids and addresses the ways to eliminate them by optimizing the compositions of formulations and the processing conditions. Effects of molecular weight of the polymer, nature of the crosslinker, additives, and bake temperature were examined. The molecular weight of the polymer is one of the important factors that needs to be controlled carefully. Polymers with high molecular weights tend to trap voids inside the vias. Low molecular weight polymers have low Tg and low viscosity, which enables good thermal flow so that the BARC can fill vias easily without voids. Several kinds of crosslinkers were investigated in this study. When used with the same polymer system, formulations with different crosslinkers show varying results that affect planar fill, sidewall coverage, and, in some cases, voids. Additives also can change via fill behavior dramatically, and choosing the right additive will improve the via fill property. Processing conditions such as

  10. Setting up of a PIXE facility at FOTIA at BARC

    International Nuclear Information System (INIS)

    Joseph, Daisy; Saxena, A.

    2005-01-01

    PIXE-(Proton Induced X-ray Emission) -an ideal technique for material characterization has been set up at the Folded Tandem Ion Accelerator (FOTIA) at BARC, Trombay. A separate beam line at 45 deg port in which a dedicated PIXE chamber has been installed is being used for PIXE studies. PIXE studies on gold standards were carried out using protons of energy 3.3 MeV. Caritage values of gold standards were obtained which agree well with the certified values. Single element standard solutions (100 μg/ml) for low-Z elements such as Cr, Mn, Fe, Co, Cu and Zn were analyzed by PIXE. Well resolved α and β components of the x-rays were seen with detection limits in the range of 0.8-4 μg/g. (author)

  11. 6 MV Folded Tandem Ion Accelerator facility at BARC

    International Nuclear Information System (INIS)

    Gupta, S.K.

    2010-01-01

    The 6 MV Folded Tandem Ion Accelerator (FOTIA) facility is operational round the clock and accelerated beams of both light and heavy ions are being used extensively by various divisions of BARC, Universities, lIT Bombay and other R and D labs across the country. The FOTIA is an upgraded version of the old 5.5 MV single stage Van-de-Graaff accelerator (1962-1992). Since its commissioning in the year 2000, the poor beam transmission through the 180 deg folding magnet was a matter of concern. A systematic study for beam transmission through the accelerator was carried out and progressive modifications in folding magnet chamber, foil stripper holder and improvement in average vacuum level through the accelerator have resulted in large improvement of beam transmission leading to up to 2.0 micro-amp analyzed proton beams on target. Now the utilization of the beams from the accelerator has increased many folds for basic and applied research in the fields of atomic and nuclear physics, material science and radiation biology etc. Few new beam lines after the indigenously developed 5-port switching magnet are added and the experimental setup for PIXE, PIGE, External PIXE, 4 neutron detector, Proton Induced Positron Annihilation Spectroscopy (PIPAS) setup and the general purpose scattering chamber etc have been commissioned in the beam hall. The same team has developed a Low Energy Accelerator Facility (LEAF) which delivers negative ions of light and heavy ions for application in implantation, irradiation damage studies in semiconductor devices and testing of new beam line components being developed for Low Energy High Intensity Proton Accelerator (LEHIPA) programme at BARC. The LEAF has been developed as stand alone facility and can deliver beam quickly with minimum intervention of the operator. Few more features are being planned to deliver uniform scanned beams on large targets. (author)

  12. Control system for BARC-TIFR Pelletron

    International Nuclear Information System (INIS)

    Singh, S.; Singh, P.; Gore, J.; Kulkarni, S.

    2012-01-01

    BARC-TIFR Pelletron is a 14 MV tandem accelerator in operation from more than 20 years. It was having a DOS based control system software which was running on a 486 PC and it was not possible to port it on new PCs. It was based on serial highway and Uport adapter based CAMAC crate controller which are now not available and all spares were used. Hence we have changed CAMAC controller with in house developed Ethernet based CAMAC controller and new software has been developed. New Control system software is based on LINUX operating system with graphical user interface developed using Trolltech's QT API, but can be easily ported on MS windows. (author)

  13. Beam transport calculations for BARC-TIFR 14UD pelletron

    International Nuclear Information System (INIS)

    Prasad, K.G.

    1993-01-01

    The 14UD pelletron tandem accelerator installed at Tata Institute of Fundamental Research (TIFR) as a joint BARC-TIFR project, is supplied by National Electrostatic Corporation (NEC), U.S.A. To optimise the parameters of various elements along the beam path, it is essential to work out the beam optics of the entire system. There are various computer codes in use for such calculations. All these codes, except the detailed ray tracing programs, use matrix formulation. Thus each ion optical element is characterised in terms of a transport matrix, whose elements are assumed to be independent of particle trajectory. We have performed only the first order calculations, meaning thereby that no aberrations are included. Further, all calculations are carried out assuming ideal conditions like axial beam injection, perfectly aligned beam line elements, etc. The main code that has been employed in our calculations is based on the one at the Australian National University, Canberra, suitably modified for use with CYBER 170/730 computer at TIFR. However, codes at NEC and Stony Brook were also used for the checking the results. The results of calculations are given and discussed. (author). 2 figs

  14. Popularization of groundnut varieties through BARC-UASD collaboration

    International Nuclear Information System (INIS)

    Madhusudan, K.; Nadaf, H.L.; Hanchinal, R.R.; Krishna Naik, L.; Motagi, B.N.; Biradar Patil, N.K.; Hunje, Ravi; D'Souza, S.F.; Badigannavar, A.M.

    2009-01-01

    To boost the productivity of groundnut, farmers need to have an access to improved seeds of the right variety, at the right time, at the right place, at an affordable price. The awareness and benefits of the improved varieties and quality seeds of groundnut was carried out by carefully planned co-ordinated educational systems such as field trials, demonstrations, field days, training farmers, interface meetings through the well established network of the University and mass media promotional tools. The BARC-UASD collaboration led to the popularization of BARC groundnut varieties like TAG-24, TG-26, TPG-41 and TDG-39 among the farming community of north Karnataka. (author)

  15. Fundamental Hyperelastic Material Study Project

    Data.gov (United States)

    National Aeronautics and Space Administration — This research is part of an innovative effort to use hyperelastic materials to produce flexible and seamless aircraft structures that reduce drag and...

  16. Status report on the folded tandem ion accelerator at BARC

    Indian Academy of Sciences (India)

    Folded tandem ion accelerator; charged particle beams; voltage stability; Rutherford backscattering; ion optics; beam lines. Abstract. The folded tandem ion accelerator (FOTIA) facility set up at BARC has become operational. At present, it is used for elemental analysis studies using the Rutherford backscattering technique.

  17. Project Management Plan for Material Stabilization

    International Nuclear Information System (INIS)

    SPEER, D.R.

    1999-01-01

    This plan presents the overall objectives, description, justification and planning for the plutonium Finishing Plant (PFP) Materials Stabilization project. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617/Rev. 0. This is the top-level definitive project management document that specifies the technical (work scope), schedule, and cost baselines to manager the execution of this project. It describes the organizational approach and roles/responsibilities to be implemented to execute the project. This plan is under configuration management and any deviations must be authorized by appropriate change control action. Materials stabilization is designated the responsibility to open and stabilize containers of plutonium metal, oxides, alloys, compounds, and sources. Each of these items is at least 30 weight percent plutonium/uranium. The output of this project will be containers of materials in a safe and stable form suitable for storage pending final packaging and/or transportation offsite. The corrosion products along with oxides and compounds will be stabilized via muffle furnaces to reduce the materials to high fired oxides

  18. Research projects on life management: materials ageing

    International Nuclear Information System (INIS)

    Gomez Briceno, D.

    1997-01-01

    Materials ageing is a time-dependent process, that involves the loss of availability of nuclear plants. Radiation embrittlement, stress corrosion cracking, irradiation assisted stress corrosion cracking, and thermal ageing are the most relevant time-dependent material degradation mechanisms that can be identified in the materials ageing process. The Materials Programme of Nuclear Energy Institute at CIEMAT carries out research projects and metallurgical examinations of failed components to gain some insight into the mechanisms of materials degradation with a direct impact on the life management of nuclear plants. (Author)

  19. Project network-oriented materials management policy for complex projects

    DEFF Research Database (Denmark)

    Dixit, Vijaya; Srivastava, Rajiv K; Chaudhuri, Atanu

    2015-01-01

    This work devises a materials management policy integrated with project network characteristics of complex projects. It proposes a relative quantitative measure, overall criticality (OC), for prioritisation of items based on penalty incurred due to their non-availability. In complex projects...... managerial tacit knowledge which provides them enough flexibility to provide information in real form. Computed OC values can be used for items prioritisation and as shortage cost coefficient in inventory models. The revised materials management policy was applied to a shipbuilding project. OC values were......, practicing managers find it difficult to measure OC of items because of the subjective factors and intractable nature of penalties involved. However, using their experience, they can linguistically identify the antecedents and relate them to consequent OC. This work adopts Fuzzy Set Theory to capture...

  20. Evolution of nuclear safety regulation for BARC Facilities

    International Nuclear Information System (INIS)

    Jayarajan, K.; Taly, Y.K.

    2017-01-01

    Safety programmes in BARC stared during the formative years and grown its stature, as the years passed by. Seventeen years of BSC, with one hundred meetings, have been quite eventful with several achievements. BSC could bring all facilities of BARC under its safety umbrella and could streamline many safety and regulatory activities. BSC aims at incident free operation of all facilities and protection of the workers, the public, the environment from radiation and other hazards. Although, incidents could not be entirely prevented, BSC have taken every event as a lesson and used the experience for improving safety. Safety enhancement is an endless journey, which has to be performed by joining hands of the managers, designers, manufacturers, inspectors and operators, in addition to the regulators

  1. Research on refractory, reactive and rare metals in BARC

    International Nuclear Information System (INIS)

    Banerjee, Srikumar

    2016-01-01

    Material processing activities were given a due thrust in Atomic Energy Programme right from the beginning. Initially research was primarily focused on metals such as uranium, thorium and zirconium which are of direct relevance to the nuclear programme. Having attained the success in processing these metals from the indigenous resources, the scope and range of material processing activities were enhanced and broadened considerably in the subsequent years. Having mastered the Kroll process for zirconium extraction, the same process was adopted in laboratory and in pilot scales for the extraction of titanium. With the experience gained in processing and handling reactive metals, flow sheet development of group V-A and VI-A metals was taken up. This presentation will summarise how different unit operations for the processing of Mo, V, Ta, W and Nb were developed and optimized. These elements have the same crystal structure (bcc), high melting points, similar chemical interactions with other elements, generally exhibiting high ductile to brittle transition temperatures and have similar alloying behavior. The general approach of processing and purification of these metals for improving the strength and ductability are discussed. The principles for the development of protective coatings on these reactive metals are also covered. The manufacturing process for the multi-filamentary superconducting cable made out of Niobium is described to illustrate the success story of the development of entire chain of operations leading to the final deployable product meeting the exacting specifications. The challenges faced in the development of beryllium, another reactive and toxic metal is briefly discussed. In order to exploit the sizeable resources of rare earth elements in India, research on processing of rare earths was initiated quite early. In the recent past there have been efforts on separation of individual rare earth elements and in preparing rare earth compounds and inter

  2. Research and development work on NAA at RCD, BARC

    International Nuclear Information System (INIS)

    Acharya, R.; Nair, A.G.C.; Burte, P.P.; Sudarshan, K.; Pandey, A.K.; Scindia, Y.M.; Goswami, A.; Reddy, A.V.R.; Manohar, S.B.

    2006-01-01

    Radiochemistry Division is engaged in R and D using NAA. They have standardized single comparator method of NAA called k 0 -based NAA using different irradiation sites of reactors at BARC Trombay. In addition, methodologies for large sample analysis, internal mono standard NAA and chemical NAA namely radiochemical, derivative and speciation NAA have been developed and are being used in different R and D works. The work on k 0 NAA and chemical NAA carried out till date are described in brief

  3. Modal data for the BARC challenge problem Test Report

    Energy Technology Data Exchange (ETDEWEB)

    Rohe, Daniel Peter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2018-01-22

    Modal testing was performed on the uncut BARC structure as a whole and broken into its two sub-assemblies. The structure was placed on soft foam during the test. Excitation was provided with a small modal hammer attached to an actuator. Responses were measured using a 3D Scanning Laser Doppler Vibrometer. Data, shapes, and geometry from this test can be downloaded in Universal File Format from the Sandia Connect SharePoint site.

  4. Prediction and Analysis of students Behavior using BARC Algorithm

    OpenAIRE

    M.Sindhuja; Dr.S.Rajalakshmi; S.M.Nandagopal

    2013-01-01

    Educational Data mining is a recent trends where data mining methods are experimented for the improvement of student performance in academics. The work describes the mining of higher education students’ related attributes such as behavior, attitude and relationship. The data were collected from a higher education institution in terms of the mentioned attributes. The proposed work explored Behavior Attitude Relationship Clustering (BARC) Algorithm, which showed the improvement in students’ per...

  5. Advancement adopted for physical protection system at BARC facilities Tarapur

    International Nuclear Information System (INIS)

    Jaroli, Manish; Ameta, Rohit; Patil, V.H.; Dubey, K.

    2015-01-01

    Considering the prevailing security situation and threat perception to the nuclear installations in particular, it has become essential to strengthen security system at BARC Tarapur in an effective manner to avert any attempt of sabotage and to ensure smooth functioning of security and safety of the nuclear installations. International Atomic Energy Agency (IAEA) and Atomic Energy Regulatory Board (AERB) have provided various security guides for the physical protection system (PPS) for nuclear installations and there has been advancement in physical and personnel protection system due to evolution of new technologies. In line with this, latest technologies have been adopted in PPS for BARC facilities, Tarapur recently. This includes state of art RFID card based access control, visitor and contractor management system, electronic key management system. Digital signature based biometric visitor and contractor management system; Digital signature based leave management system; Distress alarm system (DAS); Guard tour monitoring system (GTMS); Secure network access system (SNAS) as well as multilayered access control system at plant level. This will strengthen the surveillance and monitoring of personnel and visitors at BARC facilities. (author)

  6. Development of optically stimulated luminescence reader systems in BARC

    International Nuclear Information System (INIS)

    Kulkarni, M.S.

    2008-01-01

    BARC has very vast experience in the development of thermoluminescence (TL) reader systems both for routine personnel monitoring and research application. However, optically stimulated luminescence (OSL) related instrumentation is a recent development in BARC. The increasing popularity of OSL technique in the radiation dosimetry applications in the recent past has driven investigation and developmental programme in the OSL measurement facilities at BARC. As the consequence of the efforts directed towards the indigenous development of OSL reader system, OSL readers with various readout modes like continuous wave (CW) OSL mode, linear intensity modulated OSL (LM-OSL), pulsed OSL (POSL) have been developed. In addition to these conventional modes of operation a novel non-linear OSL mode (NL-OSL) has also been developed for the OSL measurements. This paper reviews the details of the development of OSL reader system including experience with high intensity blue/green LED stimulation light source and detection system. Also discussed are recently developed versatile integrated TL/OSL reader systems for TL and OSL measurements. (author)

  7. Legacy material work-off project

    International Nuclear Information System (INIS)

    Sloan, T.J.; Baker, D.H. IV

    1999-01-01

    Los Alamos National Laboratory (LANL) and its subcontractors recently completed a nine-month legacy material clean-up effort. Legacy materials were defined as chemicals, hazardous, non-hazardous, and both hazardous and radioactive (mixed), that no longer served a programmatic use and had no identified individual owner within the Laboratory. Once personnel identified the legacy materials, the items were transferred to Solid Waste Operation's (EM-SWO) control. Upon completing this process, the responsible division-level manager was required to certify that all non-radioactive hazardous and non-hazardous materials and acceptable mixed legacy materials had been identified and transferred to EM-SWO for proper handling or disposal. The major expense in this project was the cost of actual chemical and radiological analysis. This expense was the result of items not having an identified individual owner. The major benefit of this project is that LANL is now in an excellent position to implement its Integrated Safety Management (ISM) Plan, which requires the implementation of safe work practices, including requirements for removing unused items when vacating workspaces. Effective implementation of ISM will go a long way toward ensuring that legacy materials are no longer an issue at the Laboratory

  8. Materials Modification Under Ion Irradiation: JANNUS Project

    International Nuclear Information System (INIS)

    Serruys, Y.; Trocellier, P.; Ruault, M.-O.; Henry, S.; Kaietasov, O.; Trouslard, Ph.

    2004-01-01

    JANNUS (Joint Accelerators for Nano-Science and Nuclear Simulation) is a project designed to study the modification of materials using multiple ion beams and in-situ TEM observation. It will be a unique facility in Europe for the study of irradiation effects, the simulation of material damage due to irradiation and in particular of combined effects. The project is also intended to bring together experimental and modelling teams for a mutual fertilisation of their activities. It will also contribute to the teaching of particle-matter interactions and their applications. JANNUS will be composed of three accelerators with a common experimental chamber and of two accelerators coupled to a 200 kV TEM

  9. 7-MeV electron LINAC based pulse radiolysis facility at RPCD, BARC

    International Nuclear Information System (INIS)

    Naik, C.B.; Nadkarni, S.A.; Toley, M.A.; Shinde, S.J.; Naik, P.D.

    2017-01-01

    7-MeV electron LINAC based pulse radiolysis facility is operational in Chemistry Group of BARC since 1986. The Accelerator is housed in B-132 room in basement of Modular Labs. BARC Accelerator was procured from Radiation Dynamics Inc. UK and its detection system was indigenously developed

  10. Commentary: The Materials Project: A materials genome approach to accelerating materials innovation

    Directory of Open Access Journals (Sweden)

    Anubhav Jain

    2013-07-01

    Full Text Available Accelerating the discovery of advanced materials is essential for human welfare and sustainable, clean energy. In this paper, we introduce the Materials Project (www.materialsproject.org, a core program of the Materials Genome Initiative that uses high-throughput computing to uncover the properties of all known inorganic materials. This open dataset can be accessed through multiple channels for both interactive exploration and data mining. The Materials Project also seeks to create open-source platforms for developing robust, sophisticated materials analyses. Future efforts will enable users to perform ‘‘rapid-prototyping’’ of new materials in silico, and provide researchers with new avenues for cost-effective, data-driven materials design.

  11. R and D in vibration engineering at BARC

    International Nuclear Information System (INIS)

    Bhattacharjee, B.

    2002-01-01

    A comprehensive capability for design, experimental verifications to validate the computational codes involved in the vibration analysis of highly complex structures, equipment and piping belonging to all seismic categories have been firmly established at BARC. All the major pending issues in seismic design, viz ground motion, damping of piping system, design rules for piping and requalification and retrofitting of existing nuclear facilities are being rigorously pursued for enhancing the current level of knowledge base for seismic analysis through experimental verification of the theoretical models of the seismic behaviours of various structures, equipment and piping system. This has not only enabled requalification and retrofitting in the existing nuclear facilities for their usage over extended life span without compromising the safety but also led to development of various special devices for seismic response control design

  12. Role of ESLs in reaching BARC technologies to rural India - experience at Kaiga

    International Nuclear Information System (INIS)

    Nayak, P.D.; Ujjappa, K.M.; Ravi, P.M.; Hegde, A.G.

    2009-01-01

    Considering the various site selection requirements, most of the nuclear power plants in India under Nuclear Power Corporation of India Limited (NPCIL), are located in very remote locations. The Environmental Survey Laboratories (ESLs) under Health Physics Division, BARC are located at all Nuclear Power Stations. This paper presents the experience gained at ESL, KGS, Kaiga in acting as an interface between BARC, the technology developer and the rural public, the end user of the technology. (author)

  13. High-Si content BARC for dual-BARC systems such as trilayer patterning

    Science.gov (United States)

    Kennedy, Joseph; Xie, Song-Yuan; Wu, Ze-Yu; Katsanes, Ron; Flanigan, Kyle; Lee, Kevin; Slezak, Mark; Liu, Zhi; Lin, Shang-Ho

    2009-03-01

    This work discusses the requirements and performance of Honeywell's middle layer material, UVAS, for tri-layer patterning. UVAS is a high Si content polymer synthesized directly from Si containing starting monomer components. The monomers are selected to produce a film that meets the requirements as a middle layer for tri-layer patterning (TLP) and gives us a level of flexibility to adjust the properties of the film to meet the customer's specific photoresist and patterning requirements. Results of simulations of the substrate reflectance versus numerical aperture, UVAS thickness, and under layer film are presented. ArF photoresist line profiles and process latitude versus UVAS bake at temperatures as low as 150ºC are presented and discussed. Immersion lithographic patterning of ArF photoresist line space and contact hole features will be presented. A sequence of SEM images detailing the plasma etch transfer of line space photoresist features through the middle and under layer films comprising the TLP film stack will be presented. Excellent etch selectivity between the UVAS and the organic under layer film exists as no edge erosion or faceting is observed as a result of the etch process. A detailed study of the impact of a PGMEA solvent photoresist rework process on the lithographic process window of a TLP film stack was performed with the results indicating that no degradation to the UVAS film occurs.

  14. Fenceline water quality monitoring of effluents from BARC establishment

    International Nuclear Information System (INIS)

    Prathibha, P.; Kothai, P.; Saradhi, I.V.; Pandit, G.G.; Puranik, V.D.

    2007-01-01

    Wastewater generated from various sources (industrial, residential, rain water runoff etc.,) is either discharged into water bodies or reused/recycled for various purposes. Continuous monitoring of the wastewater is necessary to check whether these effluents are meeting the stringent limits proposed for discharge into water bodies or recycled/reused. Monitoring of these effluents also helps in designing the wastewater treatment system required to meet the standards. In this paper, water quality monitoring carried out during each quarter of the year 2005 for the effluents discharged from different utilities of BARC into Trombay bay is presented. The results indicate that the Bio-chemical oxygen demand (BOD) and chemical oxygen demand (COD) are in the range of 7.9 to 38.9 mg/l and 29.4 to 78.9 mg/l respectively. The nitrates and sulphates are in the range of 0.5 to 7.2 mg/l and 7.8 to 52.3 mg/l respectively. The water quality data of the parameters analyzed are well within the limits stipulated by Central Pollution Control Board. (author)

  15. Kinder Lernen Deutsch. Materials Project Part I. Revised.

    Science.gov (United States)

    American Association of Teachers of German.

    The Kinder Lernen Deutsch (LKD) materials evaluation project identifies materials appropriate for the elementary school German classrooms in grades K-8. This guide consists of an annotated bibliography, with ratings, of these materials. The guiding principles by which the materials were assessed were: use of the communicative approach; integration…

  16. QUECHUA LANGUAGE MATERIALS PROJECT, GUIDE TO THE MATERIALS.

    Science.gov (United States)

    SOLA, DONALD F.

    THIS GUIDEBOOK DESCRIBES THE NATURE AND USE OF THE MATERIALS PREPARED FOR TEACHING THREE OF THE MAIN DIALECTS OF QUECHUA TO SPEAKERS OF ENGLISH INTERESTED IN WORKING OR DOING RESEARCH IN THE ANDEAN REGION. DESCRIPTIVE AND PEDAGOGICAL MATERIALS HAVE BEEN PREPARED FOR EACH OF THREE IMPORTANT DIALECTS--CUZCO AND AYACUCHO IN PERU, AND COCHABAMBA IN…

  17. Innovations in Advanced Materials and Metals Manufacturing Project (IAM2)

    Energy Technology Data Exchange (ETDEWEB)

    Scott, Elizabeth [Columbia River Economic Development Council, Vancouver, WA (United States)

    2017-01-06

    This project, under the Jobs and Innovation Accelerator Challenge, Innovations in Advanced Materials and Metals Manufacturing Project, contracted with Cascade Energy to provide a shared energy project manager engineer to work with five different companies throughout the Portland metro grant region to implement ten energy efficiency projects and develop a case study to analyze the project model. As a part of the project, the energy project manager also looked into specific new technologies and methodologies that could change the way energy is consumed by manufacturers—from game-changing equipment and technology to monitor energy use to methodologies that change the way companies interact and use their machines to reduce energy consumption.

  18. Automation and remote handling activities in BARC: an overview

    International Nuclear Information System (INIS)

    Badodkar, D.N.

    2016-01-01

    Division of Remote Handling and Robotics, BARC has been working on design and development of various application specific remote handling and automation systems for nuclear front-end and back-end fuel cycle technologies. Division is also engaged in preservice and in-service inspection of coolant channels for Pressurized Heavy Water Reactors in India. Design and development of Reactor Control Mechanisms for Nuclear Research and Power Reactors (PHWRs and Compact LWRs) is another important activity carried out in this division. Robotic systems for Indoor and Outdoor surveillance in and around nuclear installations have also been developed. A line scan camera based system has been developed for measuring individual PHWR fuel pellet lengths as well as stack length. An industrial robot is used for autonomous exchange of pellets to achieve desired stack length. The system can be extended for active fuel pellets also. An automation system has been conceptualized for remote handling and transfer of spent fuel bundles from storage pool directly to the chopper unit of reprocessing plant. In case of Advanced Heavy Water Reactor which uses mixed oxides of (Th-Pu) and (Th-"2"3"3U ) as fuel, automation system for front-end fuel cycle has been designed, which includes Powder processing and pressing; Pellet handling and inspection; Pin handling and inspection; and Cluster assembly and dis-assembly in shielded facilities. System demonstration through fullscale mock-up facility is nearing completion. Above talk is presented on behalf of all the officers and staff of DRHR. The talk is mainly focused on development of an automated fuel fabrication facility for mixed oxides of (Th- Pu)/(Th-"2"3"3U ) fuel pins. An overview of divisional ongoing activities in the field of remote handling and automation are also covered. (author)

  19. Project Plan For Remove Special Nuclear Material (SNM) from Plutonium Finishing Plant (PFP) Project

    International Nuclear Information System (INIS)

    BARTLETT, W.D.

    1999-01-01

    This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove SNM Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617. This project plan is the top-level definitive project management document for the PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baseline to manage the execution of the Remove SNM Materials project. Any deviation to the document must be authorized through the appropriate change control process. The Remove SNM Materials project provides the necessary support and controls required for DOE-HQ, DOE-RL, BWHC, and other DOE Complex Contractors the path forward to negotiate shipped/receiver agreements, schedule shipments, and transfer material out of PFP to enable final deactivation

  20. Influential Factors Affecting Materials Management in Construction Projects

    Directory of Open Access Journals (Sweden)

    Jusoh Zairra Mat

    2017-12-01

    Full Text Available Construction projects are more often than not plagued by poor performances such as delays, cost overrun, low productivity, construction wastes and compromised quality. Amongst the critical contributory factors of poor project performances, is the ineffectiveness of materials management occurring in the construction sites. Indeed, materials management is a very important component for construction projects. However, there are only limited numbers of research available regarding this topic. Thus, this research focuses its study on materials management, specifically in identifying the influential factors that affect materials management in the construction project activities. Literatures from books, journal articles and conference papers related to poor project performances and materials management have been reviewed. Consequently, this study sorted the salient influential factors and categorized them based on their specific group. Out of 47 factors identified, they are classified into 8 groups. They are (1 site condition; (2 planning and handling on site; (3 management; (4 materials; (5 supplier and manufacturer default; (6 transportation; (7 contractual; and (8 governmental interferences. In conclusion, this study contends that by identifying the influential factors affecting materials management, it will help construction players to avoid the occurrence of those factors and will minimize the negative impacts on the overall performance of construction projects. Hence, the handling-over of project will be according to schedule and not delayed by materials mismanagement.

  1. Intelligent Materials Tracking System for Construction Projects Management

    Directory of Open Access Journals (Sweden)

    Narimah Kasim

    2015-05-01

    Full Text Available An essential factor adversely affecting the performance of construction projects is the improper handling of materials during site activities. In addition, paper-based reports are mostly used to record and exchange information related to the material components within the supply chain, which is problematic and inefficient. Generally, technologies (such as wireless systems and RFID are not being adequately used to overcome human errors and are not well integrated with project management systems to make tracking and management of materials easier and faster. Findings from a literature review and surveys showed that there is a lack of positive examples of such tools having been used effectively. Therefore, this research focused on the development of a materials tracking system that integrates RFID-based materials management with resources modelling to improve on-site materials tracking. Rapid prototyping was used to develop the system and testing of the system was carried out to examine the functionality and working appropriately. The proposed system is intended to promote the employment of RFID for automatic materials tracking with integration of resource modelling (Microsoft (R Office Project in the project management system in order to establish which of the tagged components are required resources for certain project tasks. In conclusion, the system provides an automatic and easy tracking method for managing materials during materials delivery and inventory management processes in construction projects.

  2. Witness: The Movie. A Material Development Project.

    Science.gov (United States)

    Conlon, Susan Henderson

    A teaching guide and series of exercises for high-intermediate or advanced English-as-a-Second-Language (ESL) instruction based on the movie "Witness" are presented. The materials are designed primarily to develop English listening and speaking skills and enhance awareness of American culture and the criminal justice system. The teaching…

  3. Development and performance evaluation of high speed cryogenic turboexpanders at BARC, India

    Science.gov (United States)

    Chakravarty, A.; Menon, R. S.; Goyal, M.; Ahmed, N.; Jadhav, M.; Rane, T.; Nair, S. R.; Kumar, J.; Kumar, N.; Bharti, S. K.; Jain, A.; Joemon, V.

    2017-12-01

    Turboexpanders are a key focus area for Bhabha Atomic Research Centre (BARC), Mumbai, India in the program for development of helium refrigerators and liquefiers for intra departmental requirements. To start with, a turbine impeller with major diameter 16 mm and design speed of 264,000 RPM, suited for use in the 1st stage of a modified Claude cycle/reverse Brayton cycle based standard helium liquefier/refrigerator, is developed. Later on, a second series of turboexpander with the same major diameter (16 mm) and design speed of 260,000 RPM is developed with “splitter” blades at the major diameter end. Yet another turboexpander series, size 16.5 mm and design speed 168,000 RPM, is also developed suited for use in the 2nd stage of a standard helium liquefier/refrigerator. The present article describes these turboexpander development efforts at BARC, including results obtained during field trials with the BARC helium refrigerator and liquefier.

  4. MATERIALS PERFORMANCE TARGETED THRUST FY 2004 PROJECTS

    International Nuclear Information System (INIS)

    DOE

    2005-01-01

    The Yucca Mountain site was recommended by the President to be a geological repository for commercial spent nuclear fuel and high-level radioactive waste. The multi-barrier approach was adopted for assessing and predicting system behavior, including both natural barriers and engineered barriers. A major component of the long-term strategy for safe disposal of nuclear waste is first to completely isolate the radionuclides in waste packages for long times and then to greatly retard the egress and transport of radionuclides from penetrated packages. The goal of the Materials Performance Targeted Thrust program is to further enhance the understanding of the role of engineered barriers in waste isolation. In addition, the Thrust will explore technical enhancements and seek to offer improvements in materials costs and reliability

  5. Regulations of safe transport of radioactive material

    International Nuclear Information System (INIS)

    Patel, R.J.; Sumathi, E.

    2017-01-01

    BARC is a multi-disciplinary nuclear research organisation with facilities located at various parts of the country. The nuclear and radiological facilities in BARC include fuel fabrication facilities, nuclear research reactors, radiological laboratories, nuclear recycle facilities, waste management facilities and other associated facilities. RAdioactive Material (RAM) such as fresh nuclear fuel, irradiated fuel, radioactive sources, vitrified high level wastes, special nuclear material etc., are transported between these facilities either within the controlled premises or in public domain. In BARC the regulatory approval for the packages used for transport of RAM is issued by BARC Safety Council (BSC). Competent Authority for issuing the design approval for the BARC packages in public domain is Director, BARC. In this aspect BSC is assisted by Safety Review Committee-Transport of Radioactive Material (SRC-TRM) constituted by BSC entrusted with the mandate to ensure the packages are designed, manufactured and transported in accordance with the current regulations. This article summarizes the regulatory requirements for transport of RAM and experience in BARC facilities

  6. Project plan remove special nuclear material from PFP project plutonium finishing plant; TOPICAL

    International Nuclear Information System (INIS)

    BARTLETT, W.D.

    1999-01-01

    This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove Special Nuclear Material (SNM) Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617,Rev. 0. This project plan is the top-level definitive project management document for PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Remove SNM Materials project. Any deviations to the document must be authorized through the appropriate change control process

  7. Project plan remove special nuclear material from PFP project plutonium finishing plant

    International Nuclear Information System (INIS)

    BARTLETT, W.D.

    1999-01-01

    This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove Special Nuclear Material (SNM) Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617, Rev. 0. This project plan is the top-level definitive project management document for PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Remove SNM Materials project. Any deviations to the document must be authorized through the appropriate change control process

  8. Regulatory process for material handling equipment

    International Nuclear Information System (INIS)

    Rajendran, S.; Agarwal, Kailash

    2017-01-01

    Atomic Energy (Factories) Rules (AEFR) 1996, Rule 35 states, 'Thorough inspection and load testing of a Crane shall be done by a Competent Person at least once every 12 months'. To adhere to this rule, BARC Safety Council constituted 'Material Handling Equipment Committee (MHEC)' under the aegis of Conventional Fire and Safety Review Committee (CFSRC) to carry out periodical inspection and certification of Material Handling Equipment (MHE), tools and tackles used in BARC Facilities at Trombay, Tarapur and Kalpakkam

  9. Inflammable materials stores

    International Nuclear Information System (INIS)

    Nandagopan, V.

    2017-01-01

    A new Inflammable Materials Stores has been constructed by A and SED, BARC near Gamma Field for storage of inflammable materials falling into Petroleum Class ‘A’ ‘B’ and “C” mainly comprising of oils and lubricants, Chemicals like Acetone, Petroleum Ether etc. which are regularly procured by Central Stores Unit (CSU) for issue to the various divisions of BARC. The design of the shed done by A and SED, BARC was duly got approved from Petroleum and Explosive Safety Organization (PESO) which is a mandatory requirement before commencement of the construction. The design had taken into account various safety factors which is ideally required for an inflammable materials stores

  10. IAEA safeguards for the Fissile Materials Disposition Project

    International Nuclear Information System (INIS)

    Close, D.A.

    1995-06-01

    This document is an overview of International Atomic Energy Agency (IAEA) safeguards and the basic requirements or elements of an IAEA safeguards regime. The primary objective of IAEA safeguards is the timely detection of the diversion of a significant quantity of material and the timely detection of undeclared activities. The two important components of IAEA safeguards to accomplish their primary objective are nuclear material accountancy and containment and surveillance. This overview provides guidance to the Fissile Materials Disposition Project for IAEA inspection requirements. IAEA requirements, DOE Orders, and Nuclear Regulatory Commission regulations will be used as the basis for designing a safeguards and security system for the facilities recommended by the Fissile Materials Disposition Project

  11. NORDTEST Project on Moisture Buffer Value of Materials

    DEFF Research Database (Denmark)

    Rode, Carsten; Peuhkuri, Ruut Hannele; Hansen, Kurt Kielsgaard

    2005-01-01

    Building materials and furnishing used in contact with indoor air have some effect to moderate the variations of indoor humidity in occupied buildings. Very low humidity can be alleviated in winter, as well as can high indoor humidity in summer and during high occupancy loads. Thus, materials can...... have been carried out on various typical building materials. The paper gives an account on the definition of the Moisture Buffer Value, it outlines the content of the test protocol, and it gives some examples of results from the Round Robin Tests....... being completed, to develop a definition, and to declare it in the form of a NORDTEST method. Apart from the definition of the term Moisture Buffer Value, the project also declares a test protocol which expresses how materials should be tested. Finally as a part of the project, some Round Robin Tests...

  12. NAA in characterization of matrices at ACD, BARC

    International Nuclear Information System (INIS)

    Rajan A, Nicy; Swain, Kallola K.; Kayasth, Satish

    2006-01-01

    The use of characterization in material science means an approach that indicates those features of materials related to its composition and structure. In simple terms, characterization of a material means what atoms are present and where they are. In general characterization deals with the complete and accurate information of composition of the material (major, minor, trace elements) for specific application. Neutron activation analysis (NAA) is identified as one of the most powerful analytical technique useful for performing both qualitative and quantitative multi-element analysis of major, minor, and trace elements in almost every conceivable field of scientific/technical interest and is extensively used for wide variety of materials

  13. Project accent: graphite irradiated creep in a materials test reactor

    International Nuclear Information System (INIS)

    Brooking, M.

    2014-01-01

    Atkins manages a pioneering programme of irradiation experiments for EDF Energy. One of these projects is Project ACCENT, designed to obtain evidence of a beneficial physical property of the graphite, which may extend the life of the Advanced Gas-cooled Reactors (AGRs). The project team combines the in-house experience of EDF Energy with two supplier organisations (providing the material test reactors and testing facilities) and supporting consultancies (Atkins and an independent technical expert). This paper describes: - Brief summary of the Project; - Discussion of the challenges faced by the Project; and - Conclusion elaborating on the aims of the Project. These challenging experiments use bespoke technology and both un-irradiated (virgin) and irradiated AGR graphite. The results will help to better understand graphite irradiation-induced creep (or stress modified dimensional change) properties and therefore more accurately determine lifetime and safe operating envelopes of the AGRs. The first round of irradiation has been completed, with a second round about to commence. This is a key step to realising the full lifetime ambition for AGRs, demonstrating the relaxation of stresses within the graphite bricks. (authors)

  14. Repair-welding technology of irradiated materials - WIM project

    International Nuclear Information System (INIS)

    Nakata, K.; Oishi, M.

    1998-01-01

    A new project on the development of repair-welding technology for core internals and reactor (pressure) vessel, consigned by the Ministry of International Trade and Industry (MITI), has been started from October 1997. The objective of the project is classified into three points as follows: (1) to develop repair-welding techniques for neutron irradiated materials, (2) to prove the availability of the techniques for core internals and reactor (pressure) vessel, and (3) to recommend the updated repair-welding for the Technical Rules and Standards. Total planning, neutron irradiation, preparation of welding equipment are now in progress. The materials are austenitic stainless steels and a low alloy steel. Neutron irradiation is performed using test reactors. In order to suppress the helium aggregation along grain boundaries, low heat input welding techniques, such as laser, low heat input TIG and friction weldings, will be applied. (author)

  15. Project plan, Hazardous Materials Management and Emergency Response Training Center: Project 95L-EWT-100

    International Nuclear Information System (INIS)

    Borgeson, M.E.

    1994-01-01

    The Hazardous Materials Management and Emergency Response (HAMMER) Training Center will provide for classroom lectures and hands-on practical training in realistic situations for workers and emergency responders who are tasked with handling and cleanup of toxic substances. The primary objective of the HAMMER project is to provide hands-on training and classroom facilities for hazardous material workers and emergency responders. This project will also contribute towards complying with the planning and training provisions of recent legislation. In March 1989 Title 29 Code of Federal Regulations Occupational Safety and Health Administration 1910 Rules and National Fire Protection Association Standard 472 defined professional requirements for responders to hazardous materials incidents. Two general types of training are addressed for hazardous materials: training for hazardous waste site workers and managers, and training for emergency response organizations

  16. Materials Development Program: Ceramic Technology Project bibliography, 1984--1992

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    The Ceramic Technology [for Advanced Heat Engines] Project was begun in 1983 to meet the ceramic materials needs of the companion DOE automotive engine program, the Advanced Gas Turbine (AGT) project, and the Heavy Duty Transport (low-heat-rejection, heavy-duty diesel) project. Goal is to develop an industry technology base for reliable and cost effective ceramics for applications in advanced automotive gas turbine and diesel engines. Research areas were identified following extensive input from industry and academia. Majority of research is done by industry (60%); work is also done at colleges and universities, in-house, and at other national laboratories and government agencies. In the beginning, reliability of ceramic components was the key issue. The reliability issues have largely been met and, at the present time, cost is the driving issue, especially in light of the highly cost-sensitive automotive market. Emphasis of the program has now been shifted toward developing cost-effective ceramic components for high-performance engines in the near-term. This bibliography is a compilation of publications done in conjunction with the Ceramic Technology Project since its beginning. Citations were obtained from reports done by participants in the project. We have tried to limit citations to those published and easily located. The end date of 1992 was selected.

  17. Gas-gun facility for shock wave research at BARC

    International Nuclear Information System (INIS)

    Gupta, S.C.; Jyoti, G.; Suresh, N.; Sikka, S.K.; Chidambaram, R.; Agarwal, R.G.; Roy, S.; Kakodkar, A.

    1995-01-01

    For carrying out shock-wave experiments on materials, we have built a 63 mm diameter gas-gun facility at our laboratory. It is capable of accelerating projectiles (about half kg in weight) to velocities up to 1 km/s using N 2 and He gases. These on impacting a target generate shock pressures up to 40 GPa, depending upon the impedance of the impactor and the target. The barrel of the gun is slotted so that a keyed projectile can be fired for combined compression- shear studies. Large samples can be shocked (about 60 mm diameter and 5-10 mm thick), with pressures lasting for a few microseconds. The gun is similar in design to the one at Washington State University. A number of diagnostic techniques have also been developed. These include measurement of projectile velocity, tilt between the impactor and the target, shock velocity in the target, and time resolved in-material stress wave histories in the shock loaded samples. Recovery capsules have also been made to retrieve shocked samples on unloading, which are then analysed using microscopic techniques like x-ray diffraction, Raman and electron microscopy. The gun has been performing well and has already been used for a few phase transition studies. (author). 73 refs., 42 figs

  18. Remote material handling in the Plutonium Immobilization Project. Revision 1

    International Nuclear Information System (INIS)

    Brault, J.R.

    2000-01-01

    With the downsizing of the US and Russian nuclear stockpiles, large quantities of weapons-usable plutonium in the US are being declared excess and will be disposed of by the Department of Energy Fissile Materials Disposition Program. To implement this program, DOE has selected the Savannah River Site (SRS) for the construction and operation of three new facilities: pit disassembly and conversion; mixed oxide fuel fabrication; and plutonium immobilization. The Plutonium Immobilization Project (PIP) will immobilize a portion of the excess plutonium in a hybrid ceramic and glass form containing high level waste for eventual disposal in a geologic repository. The PIP is divided into three distinct operating areas: Plutonium Conversion, First Stage Immobilization, and Second Stage Immobilization. Processing technology for the PIP is being developed jointly by the Lawrence Livermore National Laboratory and Westinghouse Savannah River Company. This paper will discuss development of the automated unpacking and sorting operations in the conversion area, and the automated puck and tray handling operations in the first stage immobilization area. Due to the high radiation levels and toxicity of the materials to be disposed of, the PIP will utilize automated equipment in a contained (glovebox) facility. Most operations involving plutonium-bearing materials will be performed remotely, separating personnel from the radiation source. Source term materials will be removed from the operations during maintenance. Maintenance will then be performed hands on within the containment using glove ports

  19. An overview of BARC-TIFR pelletron linac facility

    International Nuclear Information System (INIS)

    Gupta, A.K.

    2014-01-01

    The 14UD Pelletron Accelerator at Mumbai has recently completed twenty five years of successful operation. The accelerator is primarily used for basic research in the fields of nuclear, atomic, condensed matter and material science. The superconducting Linac booster provides additional acceleration to the ions from Pelletron injector up to A∼60 region with E∼5 MeV/A. Further, an alternate injector system to the Superconducting LINAC booster is planned as an augmentation programme, comprising of a superconducting ECR ion source, room temperature RFQ and superconducting low-beta cavity resonators. This talk will provide an overview of the recent developmental activities carried out at the Pelletron Accelerator Facility, resulting in enhanced overall performance and uptime of the accelerator. The application oriented programs initiated at Pelletron Accelerator and the current status of the alternate injector system at the Pelletron-Linac facility will also be discussed. (author)

  20. An overview of BARC-TIFR Pelletron-Linac Facility

    International Nuclear Information System (INIS)

    Gupta, A. K.

    2015-01-01

    The 14UD Pelletron Accelerator at Mumbai has recently completed twenty five years of successful operation. The accelerator is primarily used for basic research in the fields of nuclear, atomic, condensed matter and material science. The superconducting Linac booster provides additional acceleration to the ions from Pelletron injector up to A~60 region with E~5 MeV/A. Further, an alternate injector system to the Superconducting LINAC booster is planned as an augmentation programme, comprising of a superconducting ECR ion source, room temperature RFQ and superconducting low-beta cavity resonators. This talk will provide an overview of the recent developmental activities carried out at the Pelletron Accelerator Facility, resulting in enhanced overall performance and uptime of the accelerator. The application oriented programs initiated at Pelletron Accelerator and the current status of the alternate injector system at the Pelletron-Linac facility will also be discussed. (author)

  1. Installation and commissioning of Scandiflash-450 flash X-ray generator at BARC, Visakhapatnam

    International Nuclear Information System (INIS)

    Banerjee, P.; Verma, R.; Shukla, R.; Sharma, S.K.; Das, B.; Prabaharan, T.; Deb, P.; Das, R.; Adhikary, B.; Meena, M.; Sagar, K.; Shyam, A.

    2014-08-01

    Energetics and Electromagnetics Division, BARC, Visakhapatnam has possessed a Flash X-ray radiography (FXR) system, make: Scandiflash, Sweden. This installation and commissioning of the system has been done by ourselves. Few problems have been detected during installation and commissioning. The troubleshooting of the system has been done. Somewhere we needed to replace the original components by indigenously made one. The complete installation and commissioning has been reportedly as far as detailed possible. Presently the system is working with satisfaction. The installed facility is being used as one of the primary means of diagnostics in many of the ongoing experiments. (author)

  2. Medium energy heavy ion accelerator 14 UD Pelletron- a BARC-TIFR facility: a 5 year progress report 1989-1994

    International Nuclear Information System (INIS)

    Chatterjee, A.; Tandon, P.N.

    1995-01-01

    The medium energy heavy ion accelerator (MEHIA) facility based on 14 UD Pelletron set up under the collaborative project of Bhabha Atomic Research Centre (BARC) and Tata Institute of Fundamental Research (TIFR) at the TIFR campus at Bombay has been serving as a joint BARC-TIFR facility for heavy-ion accelerator based research. As this accelerator has just completed five years of its successful operations, it has been thought to be an appropriate time to bring out a report of the research work carried out with the accelerator facility over these last five years. To put the research work in proper perspective, the present report is formatted to provide a short write-up highlighting the work carried out in each area of activity along with a list of the publications which have resulted from these investigations. Some theoretical work related to the experimental activities with the pelletron accelerator has also been included in the list of publications. The research work in the area of nuclear physics, which forms the main thrust of the research activities with the accelerator, covers areas of high spin states, high energy photons, resonances in heavy ion reactions, heavy ion elastic and transfer reactions, heavy ion fusion-fission reactions and radiochemical studies in heavy ion reactions. The interdisciplinary areas of research include condensed matter physics and accelerator based atomic physics. In addition to the above topics the present report also describes the work related to the pelletron accelerator and associated experimental facilities, gas detector development work, data acquisition systems and spectrometer for heavy recoil ions under development. The present status of the superconducting Linac booster project is also briefly described. (author). refs., tabs

  3. Flat-plate solar array project. Volume 2: Silicon material

    Science.gov (United States)

    Lutwack, R.

    1986-10-01

    The goal of the Silicon Material Task, a part of the Flat Plate Solar Array (FSA) Project, was to develop and demonstate the technology for the low cost production of silicon of suitable purity to be used as the basic material for the manufacture of terrestrial photovoltaic solar cells. Summarized are 11 different processes for the production of silicon that were investigated and developed to varying extent by industrial, university, and Government researchers. The silane production section of the Union Carbide Corp. (UCC) silane process was developed completely in this program. Coupled with Siemens-type chemical vapor deposition reactors, the process was carried through the pilot stage. The overall UCC process involves the conversion of metallurgical-grade silicon to silane followed by decomposition of the silane to purified silicon. The other process developments are described to varying extents. Studies are reported on the effects of impurities in silicon on both silicon-material properties and on solar cell performance. These studies on the effects of impurities yielded extensive information and models for relating specific elemental concentrations to levels of deleterious effects.

  4. Flat-plate solar array project. Volume 2: Silicon material

    Science.gov (United States)

    Lutwack, R.

    1986-01-01

    The goal of the Silicon Material Task, a part of the Flat Plate Solar Array (FSA) Project, was to develop and demonstate the technology for the low cost production of silicon of suitable purity to be used as the basic material for the manufacture of terrestrial photovoltaic solar cells. Summarized are 11 different processes for the production of silicon that were investigated and developed to varying extent by industrial, university, and Government researchers. The silane production section of the Union Carbide Corp. (UCC) silane process was developed completely in this program. Coupled with Siemens-type chemical vapor deposition reactors, the process was carried through the pilot stage. The overall UCC process involves the conversion of metallurgical-grade silicon to silane followed by decomposition of the silane to purified silicon. The other process developments are described to varying extents. Studies are reported on the effects of impurities in silicon on both silicon-material properties and on solar cell performance. These studies on the effects of impurities yielded extensive information and models for relating specific elemental concentrations to levels of deleterious effects.

  5. Indigenous development and performance evaluation of BARC aerodynamic size separator (BASS)

    CERN Document Server

    Singh, S; Khan, A; Mayya, Y S; Narayanan, K P; Purwar, R C; Sapra, B K; Sunny, F

    2002-01-01

    Commercially available cascade impactors, commonly used for aerodynamic size separation of aerosol particles, are based on the principle of inertial impaction. As of now, these instruments are imported at a cost of several lakhs of rupees; hence an effort has been made to develop an aerodynamic particle sizer indigenously in BARC. This unit, referred to as BARC Aerodynamic Size Separator (BASS), separates aerosols into seven size classes ranging from 0.53 mu m to 10 mu m and operates at a flow rate of 45 Ipm. Intercomparison studies between the standard Andersen Mark-II (Grasbey Andersen Inc.) impactor and BASS using nebulizer generated aerosols have consistently shown excellent performance by BASS in all respects. In particular, BASS yielded the parameters of polydisperse aerosols quite accurately. Experiments to evaluate the individual stage cut-off diameters show that these are within 8% of their designed value for all stages except the higher two stages which indicate about 30% lower values than the desig...

  6. Proceedings of the national symposium on BARC technologies for development of rural India

    International Nuclear Information System (INIS)

    Mishra, R.K.; Wadawale, Amey; Bhadauria, Y.S.; Joseph, Daisy; Kumar, Manoj; Girija, K.G.; Gautam, S; Rawat, A.S.; Misra, S.K.

    2009-01-01

    For empowering Indian villages, science and technology (S and T) based eco-friendly work plan have to be evolved. Sustainable techno-economic growth of rural sector in a country of vast size such as India requires technology innovations and their ingenious adaptation. This can be achieved to a great extent by adopting such technologies for varied local conditions so that it can be applied quickly to enhance the quality of life of larger population. Considering the wealth of technology and innovative capability generated in BARC, as an off-shoot of R and D in nuclear energy and its applications in power and non-power areas, Department of Atomic Energy (DAE), India has launched - Societal Initiative for utilization of Non-Power Applications (NPAs) and Spin off technologies (Spin-offs) in the area of water, land, agriculture, food processing and urban-rural waste management. Within this framework of societal initiative, structured programme called 'AKRUTI - KRUTIK - FORCE' has been formulated and is being implemented by BARC for techno-economic growth of the rural sector, as one of the many schemes for large-scale deployment of NPAs and spin-offs. This symposium consisting of invited lectures and poster presentations covered the topics like food and agriculture, health and environment, energy and conservation. Papers relevant to INIS are indexed separately

  7. Track Etch Membranes (TEMS) for separation sciences from BARC-TIFR Pelletron accelerator

    International Nuclear Information System (INIS)

    Nair, J.P.; Surendran, P.; Sparrow, Hillary; Gupta, A.K.; Kailas, S.; Bhagwat, P.V.

    2014-01-01

    TEMs are very much in need for the separation of desirable/undesirable metals from industrial effluents and radioactive wastes as well as in the field of biology and gas separation. It is necessary to optimize pore size and pore density for a specific application. TEMs available in market are imported and are used for laboratory scale activity. To carry the success of these activities on industrial scale large scale production of TEMs is needed. The availability of heavy ion accelerator made possible the production of TEMs in wide range of sizes. Many countries have set up facilities for continuous production of TEMs. BARC-TIFR Pelletron Accelerator at Mumbai delivers MeV energies of heavy ions for research in basic as well as applied sciences. Heavy ions of various species and energies from BARC-TIFR Pelletron Accelerator were used to make TEMs using polyethylene terephthalate (PET/Mylar) films of 25 micron thickness. The films used were procured from reputed manufactures in India

  8. Controlling Beryllium Contaminated Material And Equipment For The Building 9201-5 Legacy Material Disposition Project

    International Nuclear Information System (INIS)

    Reynolds, T.D.; Easterling, S.D.

    2010-01-01

    This position paper addresses the management of beryllium contamination on legacy waste. The goal of the beryllium management program is to protect human health and the environment by preventing the release of beryllium through controlling surface contamination. Studies have shown by controlling beryllium surface contamination, potential airborne contamination is reduced or eliminated. Although there are areas in Building 9201-5 that are contaminated with radioactive materials and mercury, only beryllium contamination is addressed in this management plan. The overall goal of this initiative is the compliant packaging and disposal of beryllium waste from the 9201-5 Legacy Material Removal (LMR) Project to ensure that beryllium surface contamination and any potential airborne release of beryllium is controlled to levels as low as practicable in accordance with 10 CFR 850.25.

  9. Axisymmetric global structural analysis of BARC prestressed concrete containment model for beyond design pressure

    International Nuclear Information System (INIS)

    Singh, Tarvinder; Singh, R.K.; Ghosh, A.K.

    2008-10-01

    In order to check the adequacy of the Indian Pressurized Heavy Water Reactor (PHWR) containment structure to withstand severe accident induced internal pressure load, the ultimate load capacity assessment is required. Reactor Safety Division (RSD) of Bhabha Atomic Research Centre (BARC) has initiated an experimental program at BARC Tarapur Containment Test Facility to evaluate the ultimate load capacity of Indian PHWR containment. For this study, BARC Containment Model (BARCOM), which is 1:4 scale representation of Tarapur Atomic Power Station (TAPS) unit-3 and 4 540 MWe PHWR Inner Containment of Pre-stressed Concrete has been constructed. The model includes all the important major design features of the prototype containment and simulates Main Air Lock (MAL), Steam Generator (SG), Emergency Air Lock (EAL) and Fueling Machine Air Lock (FMAL) openings. The design pressure (Pd) of BARCOM is 1.44kg/cm 2 (g), which is same as the prototype. The pretest analysis of BARCOM has been performed with finite element axi-symmetric modeling. The objective of this simulation was to understand the behavior of containment model under internal pressure and find out the various failure modes and critical locations important for instrumentation during the experiment. The structural response of the containment model is assessed in terms of wall and dome displacement; cracking of concrete, longitudinal and hoop strains and stresses. Another objective of the analysis was to predict the various failure modes of BARCOM with regard to the concrete cracking, reinforcement yielding and tendon inelastic behavior along with the estimation of the ultimate load capacity of the containment model. It is noted that the BARCOM has an ultimate load capacity factor of 3.54 Pd. However, further analysis is needed to quantify the factor of safety with detail 3D model, which should account for the local structural behavior due to various openings. Meanwhile, this preliminary simplified analysis helps to

  10. Production of Working Reference Materials for the Capability Evaluation Project

    Energy Technology Data Exchange (ETDEWEB)

    Phillip D. Noll, Jr.; Robert S. Marshall

    1999-03-01

    Nondestructive waste assay (NDA) methods are employed to determine the mass and activity of waste-entrained radionuclides as part of the National TRU (Trans-Uranic) Waste Characterization Program. In support of this program the Idaho National Engineering and Environmental Laboratory Mixed Waste Focus Area developed a plan to acquire capability/performance data on systems proposed for NDA purposes. The Capability Evaluation Project (CEP) was designed to evaluate the NDA systems of commercial contractors by subjecting all participants to identical tests involving 55 gallon drum surrogates containing known quantities and distributions of radioactive materials in the form of sealed-source standards, referred to as working reference materials (WRMs). Although numerous Pu WRMs already exist, the CEP WRM set allows for the evaluation of the capability and performance of systems with respect to waste types/configurations which contain increased amounts of {sup 241}Am relative to weapons grade Pu, waste that is dominantly {sup 241}Am, as well as wastes containing various proportions of depleted uranium. The CEP WRMs consist of a special mixture of PuO{sub 2}/AmO{sub 2} (IAP) and diatomaceous earth (DE) or depleted uranium (DU) oxide and DE and were fabricated at Los Alamos National Laboratory. The IAP WRMS are contained inside a pair of welded inner and outer stainless steel containers. The DU WRMs are singly contained within a stainless steel container equivalent to the outer container of the IAP standards. This report gives a general overview and discussion relating to the production and certification of the CEP WRMs.

  11. Hot target assembly at 14 UD Pelletron Accelerator Facility, BARC- TIFR, Mumbai

    International Nuclear Information System (INIS)

    Sharma, S.C.; Ramjilal; Ninawe, N.G.; Bhagwat, P.V.; Ahmeabadhai, P.; Kain, V.

    2005-01-01

    BARC-TIFR 14 UD Pelletron Accelerator Facility at Mumbai is operational since 1989 with progressively increased efficiency. The accelerator has been serving as major facility for heavy ion based research in India. There is an increased demand for high current proton beam, especially on heated targets for reactor physics based experiments. A proton beam setup is commissioned in the tower area of the existing facility itself, which provide proton beam of energy 2 MeV to 26 MeV with maximum 3 μA current. This setup is being used to produce radioisotopes and tracer packets. Proton beam of few MeV in μA current range is also needed to study radiation effects on metals at higher temperature, for use in reactors. For this purpose a hot target assembly has been designed and is being currently used at the Pelletron Accelerator

  12. Indigenous development and performance evaluation of BARC aerodynamic size separator (BASS)

    International Nuclear Information System (INIS)

    Singh, Sanjay; Purwar, R.C.; Das, Tanmoy; Narayanan, K.P.; Sapra, B.K.; Sunny, Faby; Khan, Arshad; Mayya, Y.S.

    2002-06-01

    Commercially available cascade impactors, commonly used for aerodynamic size separation of aerosol particles, are based on the principle of inertial impaction. As of now, these instruments are imported at a cost of several lakhs of rupees; hence an effort has been made to develop an aerodynamic particle sizer indigenously in BARC. This unit, referred to as BARC Aerodynamic Size Separator (BASS), separates aerosols into seven size classes ranging from 0.53 μm to 10 μm and operates at a flow rate of 45 Ipm. Intercomparison studies between the standard Andersen Mark-II (Grasbey Andersen Inc.) impactor and BASS using nebulizer generated aerosols have consistently shown excellent performance by BASS in all respects. In particular, BASS yielded the parameters of polydisperse aerosols quite accurately. Experiments to evaluate the individual stage cut-off diameters show that these are within 8% of their designed value for all stages except the higher two stages which indicate about 30% lower values than the designed ones. The replotting of all the mass distribution data using the experimental cut-off diameters showed perfect lognormal fits, thereby indicating that these diameters are closer to the true stage cut-off diameters for BASS. The studies show that BASS will be suitable for determining the particle size distributions in the context of the radiological safety programmes of DAE. Being indigenous in design, it may be fabricated on a commercial scale at a cost far less than that of the imported units. Such a venture will greatly help several national programmes on atmospheric pollution being carried out by many laboratories and institutions across the country. (author)

  13. Proceedings of the national symposium on BARC technologies for development of rural India

    International Nuclear Information System (INIS)

    2013-01-01

    Empowering villages with Science and Technology (S and T) based on eco-friendly work plan for sustainable Techno-Economic growth of rural sector in a country of vast size, technology innovations and adaptations have to be evolved. This can be achieved to a great measure particularly since such technology will fit with varied local conditions and can be applied quickly to enhance the quality of life of larger population. Considering the wealth of technology and innovative capability generated in BARC, as an off-shoot of R and D in Nuclear Energy and its applications in power and non-power areas, Department of Atomic Energy (DAE) has launched - Societal Initiative for utilization of Non-Power Applications (NPAs) and Spinoff technologies (Spinoffs) in the area of water, land, agriculture, food processing and urban-rural waste management. Within this framework of societal initiative, structured programme called 'AKRUTI - KRUTIK - FORCE' has been formulated and is being implemented by BARC for techno-economic growth of the rural sector, as one of the many schemes for large-scale deployment of NPAs and spinoffs. Bhabha Atomic Research Centre Officer's Association (BARCOA) is making a maiden attempt to hold a symposium where the scientists, technologists, agriculturists and the consumers will come on a common platform to discuss these issues. This symposium is organized to enable to take the fruits of technology to grass-root level to every villager in the remote corner and provide inclusive growth to the rural sector and tap the hidden innovative capability of large rural India. This symposium describes the various technologies developed indigenously by Bhabha Atomic Research Centre for the development of rural India. Papers relevant to INIS are indexed separately

  14. Bulk material management mode of general contractors in nuclear power project

    International Nuclear Information System (INIS)

    Zhang Jinyong; Zhao Xiaobo

    2011-01-01

    The paper introduces the characteristics of bulk material management mode in construction project, and the advantages and disadvantages of bulk material management mode of general contractors in nuclear power project. In combination with the bulk material management mode of China Nuclear Power Engineering Co., Ltd, some improvement measures have been put forward as well. (authors)

  15. Regulatory inspection practices for industrial safety (electrical, mechanical, material handling and conventional aspects)

    International Nuclear Information System (INIS)

    Agarwal, K.

    2017-01-01

    Regulatory Inspection (RI) of BARC facilities and projects are carried out under the guidance of BARC Safety Council (BSC) Secretariat. Basically facilities and projects have been divided into two board categories viz. radiological facilities and non-radiological facilities. The Rls of radiological facilities should be carried out under OPSRC and of non-radiological facilities under CFSRC. Periodicity of inspection shall be at least once in a year. The RI of projects is carried out under concerned DSRC. RI practices with industrial safety which includes electrical, mechanical, material handling and conventional aspect for these facilities starts with check lists. The inspection areas are prepared in the form of checklists which includes availability of approved documents, compliance status of previous RIT and various safety committee's recommendations, radiological status of facilities, prompt reporting of safety related unusual occurrences, major incident, site visit for verification of actual status of system/plant. The practices for inspection in the area of electrical safety shall include checking of maintenance procedure for all critical class IV system equipment's such as HT panel, LT panel, transformer and motors. Load testing of Class III system such as D.G. set etc. shall be carried out as technical specification surveillance schedule. Status of aviation lights, number of qualified staff, availability of qualified staff etc. shall be form of inspection

  16. Kinder Lernen Deutsch Materials Evaluation Project: Grades K-8.

    Science.gov (United States)

    American Association of Teachers of German.

    The Kinder Lernen Deutsch (Children Learn German) project, begun in 1987, is designed to promote German as a second language in grades K-8. The project is premised on the idea that the German program will contribute to the total development of the child and the child's personality. Included in this guide are a selection of recommended core…

  17. Radio frequency identification (RFID) tagging for material tracking and future asset management : research project capsule.

    Science.gov (United States)

    2016-07-01

    Current Louisiana Department of Transportation and Development (DOTD) : practice allows multiple mixtures or materials to be submitted and subsequently : used during a highway construction project. Such materials include mechanically : stabilized ear...

  18. Development of hybrid micro circuit based multi-channel programmable HV supply for BARC-pelletron experimental facility

    International Nuclear Information System (INIS)

    Manna, A.; Thombare, S.; Moitra, S.; Kuswarkar, M.; Punna, M.; Nair, P.M.; Diwakar, M.P.; Pithawa, C.K.

    2013-01-01

    Electronics Division, BARC has developed a Multi channel programmable HV bias supply system for charge particle detector array for use in BARC-TIFR Pelletron-LINAC facility. The HV supplies are compact in size due to use of hybrid micro-circuits developed indigenously and are modular in construction to achieve versatility, scalability and serviceability. All programming operations and monitoring are performed remotely through PC over Ethernet. Each supply has a built-in over voltage, over current and thermal overload protections for safe operation and employs a Zero Voltage Switching (ZVS) technique to reduce thermal stress on the inverter switches. This article describes salient design aspects and performance of the HV supply system. (author)

  19. Characterisation of dust material emitted during harbour operations (HADA Project)

    Energy Technology Data Exchange (ETDEWEB)

    Moreno, N.; Alastuey, A.; Querol, X.; Artinano, B.; Guerra, A.; Luaces, J.A.; Lorente, A.; Basora, J. [CSIC, Institute of Earth Science ' Jaume Almera' , Barcelona (Spain)

    2007-09-15

    The aim of this work is to compile an inventory of the main characteristics (chemical, morphological, mineralogical and grain size parameters) of the bulk cargo materials and of the material emitted during different port operations for possible use as tracers of the fugitive PM emission sources. For all cases, the tracer characteristics determined for each bulk material were also identified in the corresponding PM material emitted. This inventory could assist the harbour authorities to identify the origin of high PM events recorded by air quality monitoring networks in harbour areas, and could also help modellers to predict the impact of harbour activities on ambient PM levels. The harbour of Tarragona (north-east Spain) was selected for this study given the high volume of solids in bulk handled. To this end, 12 handling operations of selected materials (clinker, phosphate, pyrite ash, Mn mineral, fine Si-Mn, coke (coal), bituminous coal, tapioca, soybean, alfalfa, corn, andalusite) were selected for the characterisation of suspended and deposited PM. In spite of the coarse grain size distribution of these bulk cargo materials, with a very low % in the fraction {lt}10 {mu}m, manipulation of these materials during harbour operations may result in high emissions of PM 10 with relatively high levels of potential toxic elements. Furthermore, ambient PM 10 in the area with the highest traffic density of the harbour was also sampled and characterised.

  20. The Feed Materials Program of the Manhattan Project: A Foundational Component of the Nuclear Weapons Complex

    Science.gov (United States)

    Reed, B. Cameron

    2014-12-01

    The feed materials program of the Manhattan Project was responsible for procuring uranium-bearing ores and materials and processing them into forms suitable for use as source materials for the Project's uranium-enrichment factories and plutonium-producing reactors. This aspect of the Manhattan Project has tended to be overlooked in comparison with the Project's more dramatic accomplishments, but was absolutely vital to the success of those endeavors: without appropriate raw materials and the means to process them, nuclear weapons and much of the subsequent cold war would never have come to pass. Drawing from information available in Manhattan Engineer District Documents, this paper examines the sources and processing of uranium-bearing materials used in making the first nuclear weapons and how the feed materials program became a central foundational component of the postwar nuclear weapons complex.

  1. Transport of nuclear materials as an international project

    International Nuclear Information System (INIS)

    Bartejsova, Eva

    2010-01-01

    The following companies are involved in this project: CEZ a.s., ALTA a.s., ALTA 32 s.r.o., DMS s.r.o., TVEL (RF), and NUKLON (RF). Transport containers are TK-S5 (for Temelin) and TK-S55 (for Dukovany) types. Details of fuel supplies for the 2 Czech NPPs are described and the fresh fuel element transport procedure is highlighted. (P.A.)

  2. Solar Energy Educational Material, Activities and Science Projects

    Science.gov (United States)

    dropdown arrow Site Map A-Z Index Menu Synopsis Solar Energy Educational Materials Solar with glasses " ;The sun has produced energy for billions of years. Solar energy is the solar radiation that reaches the earth. Solar energy can be converted directly or indirectly into other forms of energy, such as

  3. Advanced Research Projects Agency on Materials Preparation and Characterization Research

    Science.gov (United States)

    Briefly summarized is research concerned with such topics as: Preparation of silica glass from amorphous silica; Glass structure by Raman ...ferroelectrics; Silver iodide crystals; Vapor phase growth; Refractory optical host materials; Hydroxyapatite ; Calcite; Characterization of single crystals with a double crystal spectrometer; Characterization of residual strain.

  4. Results from the European Integrated Project '' New Materials for Extreme Environments (ExtreMat) ''

    International Nuclear Information System (INIS)

    Bolt, H.; Linsmeier, Ch.; Baluc, N.; Garcia-Rosales, G.; Gualco, G. C.; Simancik, F.

    2006-01-01

    The goal of the European Integrated Project '' ExtreMat '' is to provide and to industrialize new materials and their compounds for applications in extreme environments that are beyond reach with incremental materials development only. The R(and)D activities in this project aim to provide a) self-passivating protection materials for sensitive structures operated in physico-chemically aggressive environments at high temperatures; b) new heat sink materials with the capability of very efficient heat removal, often at very high temperature level; c) radiation resistant materials for very high operation temperatures; d) new processing routes for complex heterogeneous compounds that can be operated in extreme environments. Key applications for these new materials are in the sectors of fusion, advanced fission, space, and electronic applications. Further use of these materials is expected in spin-off fields, such as brake applications and energy conversion. The project started in December 2004 for a duration of five years and is supported by the European Community. The 37 project participants are from 13 EU member states and include 6 universities, 7 research institutes, 10 research centres and 14 industrial companies. Research results regarding the development of materials for application in nuclear fusion, especially on protection, heat sink, and radiation resistant materials will be presented. A view to other applications of these materials in the fields of fission, space and electronics will be given in the presentation. ExtreMat Project Partners: see http://www.extremat.org/. (author)

  5. Projectables

    DEFF Research Database (Denmark)

    Rasmussen, Troels A.; Merritt, Timothy R.

    2017-01-01

    CNC cutting machines have become essential tools for designers and architects enabling rapid prototyping, model-building and production of high quality components. Designers often cut from new materials, discarding the irregularly shaped remains. We introduce ProjecTables, a visual augmented...... reality system for interactive packing of model parts onto sheet materials. ProjecTables enables designers to (re)use scrap materials for CNC cutting that would have been previously thrown away, at the same time supporting aesthetic choices related to wood grain, avoiding surface blemishes, and other...... relevant material properties. We conducted evaluations of ProjecTables with design students from Aarhus School of Architecture, demonstrating that participants could quickly and easily place and orient model parts reducing material waste. Contextual interviews and ideation sessions led to a deeper...

  6. The effect of desiccation on UMTRA Project radon barrier materials

    International Nuclear Information System (INIS)

    1990-11-01

    The proposed US Environmental Protection Agency (EPA) groundwater standards (40 CFR 192) require that Uranium Mill Tailings Remedial Action (UMTRA) Project remedial action designs meet low numerical limits for contaminants contained in water or vapors exiting the disposal cell embankments. To meet the standards, a cover of compacted, fine-grained soil is placed over UMTRA Project embankments. One of the functions of this cover is to limit infiltration into the disposal cell . The hydraulic conductivity of this infiltration barrier must be low in order to reduce the resultant seepage from the base of the cell to the extent necessary to comply with the proposed EPA groundwater standards. Another function of this cover is to limit the emission of radon gas. The air permeability of the cover must be low in order to reduce radon emissions to comply with EPA standards. Fine-grained soils exposed to evaporation will dry. Continued exposure will cause shrinking that, if allowed to continue, will eventually result in the development of cracks. The results of the cracking could be an increase in the hydraulic conductivity and an increase in the air permeability. This could then allow additional infiltration and increased radon emissions. Cracking of the radon barrier has been noted at one UMTRA Project location. The potential for cracking of the radon barrier during construction has been addressed by requiring moistening of previously compacted surfaces prior to placing additional lifts. The efficacy of these treatments has not been verified. The potential for cracking after construction of the cover is completed has also not been examined. The purpose of this study is to evaluate the potential for cracking of the radon barrier both during construction and after completion of the cover. The effect of shrinkage cracking on the performance of the radon barrier will also be examined

  7. Fluor Hanford Nuclear Material Stabilization Project Welding Manual

    International Nuclear Information System (INIS)

    BERKEY, J.R.

    2000-01-01

    The purpose of this section of the welding manual is to: (1) Provide a general description of the major responsibilities of the organizations involved with welding. (2) Provide general guidance concerning the application of codes related to welding. This manual contains requirements for welding for all Fluor Hanford (FH) welding operators working on the W460 Project, in the Plutonium Finishing Plant (PFP) at the U. S. Department of Energy (DOE) Hanford facilities. These procedures and any additional requirements for these joining processes can be used by all FH welding operators that are qualified. The Welding Procedure Specifications (WPS) found in this document were established from Procedure Qualification Records (PQR) qualified by FH specifically for the W460 Project. PQRs are permanent records of the initial testing and qualification program and are used to backup, and support, the WPS. The identification numbers of the supporting PQR(s) are recorded on each WPS. All PQRs are permanently stored under the supervision of the Fluor Hanford Welding Engineer (FHWE). New PQRs and WPSs will continue to be developed as necessary. The qualification of welders, welding operators and welding procedures will be performed for FH under supervision and concurrent of the FHWE. All new welding procedures to be entered in this manual or welder personnel to be added to the welder qualification database, shall be approved by the FHWE

  8. MIDDLE MIOCENE DEPOSITIONAL MODEL IN THE DRAVA DEPRESSION DESCRIBED BY GEOSTATISTICAL POROSITY AND THICKNESS MAPS (CASE STUDY: STARI GRADAC-BARCS NYUGAT FIELD

    Directory of Open Access Journals (Sweden)

    Tomislav Malvić

    2006-12-01

    Full Text Available Neogene depositional environments in the Drava depression can be classified in two groups. One group is of local alluvial fans, which were active during the period of Middle Miocene (Badenian extension through the entire Pannonian Basin. The second group is represented by continuous Pannonian and Pontian sedimentation starting with lacustrine environment of partly deep water and partly prodelta (turbidity fans and terminating at the delta plain sedimentation. The coarse-grained sediments of alluvial fans have the great hydrocarbon potential, because they often comprise reservoir rocks. Reservoir deposits are mostly overlain (as result of fan migration by pelitic seal deposits and sometimes including organic rich source facies. That Badenian sequences are often characterised by complete petroleum systems, what is confirmed by large number of oil and gas discoveries in such sediments in the Drava and other Croatian depressions. Alluvial environments are characterised by frequent changes of petrophysical properties, due to local character of depositional mechanism and material sources. In the presented paper, Stari Gradac-Barcs Nyugat field is selected as a case study for demonstrating the above mentioned heterogenic features of the Badenian sequences. Structural solutions are compared by maps of parameters related to depositional environment, i.e. porosity and thickness maps. Geostatistics were used for spatial extension of input dataset. The spatial variability of porosity values, i.e. reservoir quality, is interpreted by transition among different sub-environments (facies in the alluvial fan system.

  9. Hexapartite safeguards project team 3: material accounting and control questionnaire

    International Nuclear Information System (INIS)

    Swindle, D.W. Jr.

    1981-01-01

    Information provided in this report reflects the current design and operating procedures for the GCEP. However, since the installation is currently under construction, facility design and operating procedures discussed in this report are subject to change. Where applicable, the responses are based on material control and accounting practices of the Portsmouth Gaseous Diffusion Plant's (GDP) operating contractor (Goodyear Atomic Corporation). These practices meet US Department of Energy (DOE) standards and are assumed to be the reference practices for the GCEP. This report covers data collection and record keeping actions of the operator

  10. Comparison of aerosol inhalation lung images using BARC and other nebulizers

    International Nuclear Information System (INIS)

    Isawa, Toyoharu; Teshima, Takeo; Anazawa, Yoshiki; Miki, Makoto

    1994-01-01

    Various factors determine the site of inhaled aerosol deposition in the lungs. They are the size of aerosol the composition of carrier gas of the aerosol, the airflow rate, physico-chemical properties of the carrier gas or the aerosol, the shape and structure of the airways, and the body position during inhalation. Aerosol inhalation lung images were obtained in the same subjects using 99m Tc-human serum albumin aerosol generated by 3 different aerosol generators each producing different-sized aerosol and 2 or 3 days apart from each study. The size of aerosol produced by an ultrasonic nebulizer (Mistogen) was 1.93 Micron in activity median aerodynamic diameter (AMAD) with its geometric standard deviation (σg) of 1.73, that by a jet nebulizer (Ultra Vent) was 1.04 micron in AMAD with its σg of 1.71, and that by our BARC nebulizer, a type of a jet nebulizer, was 0.84 micron in AMAD with its σg of 1.73. In addition Technegas was also applied to selected patients. The latter produced aerosol of less than 0.2 micron in size at the largest and the majority, say, 95% or more of the generated aerosol was less than 0.1 micron in size by electron Microscopy. Each subject inhaled aerosol in resting tidal breathing through a mouth-piece with a one way double J valve with the nose clipped in the sitting position. After inhaling approximately 2-3 mCi (74 to 111 MBq) in the thorax, four view lung images were taken: anterior, posterior, and right and left laterals. 300 K counts per view were collected. They were not only pictured on polaroid films as analogue data but also recorded and stored in a computer as digital data. In case of Technegas breathing it for the RV (residual volume) to the TLC (total lung capacity) level followed by breath-holding for 5 to 10 sec in duration was repeated 2 to 3 times as a breathing maneuver instead of tidal breathing. Otherwise deposition efficiency of Technegas is very little because of the small size of the Technegas. Representative 10

  11. Development and deployment of BARC Vessel Inspection System (BARVIS) for TAPS-1 and 2

    International Nuclear Information System (INIS)

    Singh, Jit Pal; Ranjon, R.; Kulkarni, M.P.; Soni, N.L.; Patel, R.J.

    2016-01-01

    As per regulatory requirements, inspection of welds in Reactor Pressure Vessel (RPV) is necessary for further continuing operation of TAPS - 1 and 2. Upper shell longitudinal welds of RPV which were seen as inaccessible up till now have been inspected first time since operation of the reactors by deploying Weld Inspection Manipulator (WIM) in Unit-1 in August 2012. Subsequently Unit-2 and again Unit-1 upper shell welds were inspected with upgraded versions of WIM in Feb 2013 and March 2015 respectively. Inspection of upper shell welds paves the way for more challenging inspection of beltline region welds. These welds are accessible only from Inside Diameter (JD) surface through a narrow annular gap of 25 mm between RPV wall and thermal shield by managing obstructions due to core internals. BARC Vessel Inspection System (BARVIS) for inspection of beltline region welds from inner side of the RPV was designed, manufactured, tested and qualified for sending scanning probes in to the annular gap of 25mm as per RPV engineering drawings and also based on actual gap measured in Unit-2. Annular gap measurement was done in Units-1 before deployment of BARVIS during 25 th Refuelling Outage (RFO) in Unit-1. Contrary to the expectation, the annular gap was found less and inspection of beltline region with BARVIS in Unit-1 could not be done. Finally during RFO in January 2016 of Unit-2, BARVIS has been successfully deployed for beltline region welds inspection. BARVIS mainly consists of manipulator, its operating system and data acquisition system. Data acquisition system and data analysis are not covered in this report. (author)

  12. Safety margin evaluation of pre-stressed concrete nuclear containment vessel model with BARC code ULCA

    International Nuclear Information System (INIS)

    Basha, S.M.; Patnaik, R.; Ramanujam, S.; Singh, R.K.; Kushwaha, H.S.; Venkat Raj, V.

    2002-01-01

    Full text: Ultimate load capacity assessment of nuclear containments has been a thrust research area for Indian pressurised heavy water reactor (PHWR) power programme. For containment safety assessment of Indian PHWRs a finite element code ULCA was developed at BARC, Trombay. This code has been extensively benchmarked with experimental results and for prediction of safety margins of Indian PHWRs. The present paper highlights the analysis results for prestressed concrete containment vessel (PCCV) tested at Sandia National Labs, USA in a round robin analysis activity co-sponsored by Nuclear Power Engineering Corporation (NUPEC), Japan and the U.S Nuclear Regulatory Commission (NRC). Three levels of failure pressure predictions namely the upper bound, the most probable and the lower bound (all with 90% confidence) were made as per the requirements of the round robin analysis activity. The most likely failure pressure is predicted to be in the range of 2.95 Pd to 3.15 Pd (Pd = design pressure of 0.39 MPa for the PCCV model) depending on the type of liners used in the construction of the PCCV model. The lower bound value of the ultimate pressure of 2.80 Pd and the upper bound of the ultimate pressure of 3.45 Pd are also predicted from the analysis. These limiting values depend on the assumptions of the analysis for simulating the concrete tendon interaction and the strain hardening characteristics of the steel members. The experimental test has been recently concluded at Sandia Laboratory and the peak pressure reached during the test is 3.3 Pd that is enveloped by our upper bound prediction of 3.45 Pd and is close to the predicted most likely pressure of 3.15 Pd

  13. Materials and Structures Research for Gas Turbine Applications Within the NASA Subsonic Fixed Wing Project

    Science.gov (United States)

    Hurst, Janet

    2011-01-01

    A brief overview is presented of the current materials and structures research geared toward propulsion applications for NASA s Subsonic Fixed Wing Project one of four projects within the Fundamental Aeronautics Program of the NASA Aeronautics Research Mission Directorate. The Subsonic Fixed Wing (SFW) Project has selected challenging goals which anticipate an increasing emphasis on aviation s impact upon the global issue of environmental responsibility. These goals are greatly reduced noise, reduced emissions and reduced fuel consumption and address 25 to 30 years of technology development. Successful implementation of these demanding goals will require development of new materials and structural approaches within gas turbine propulsion technology. The Materials and Structures discipline, within the SFW project, comprise cross-cutting technologies ranging from basic investigations to component validation in laboratory environments. Material advances are teamed with innovative designs in a multidisciplinary approach with the resulting technology advances directed to promote the goals of reduced noise and emissions along with improved performance.

  14. Z-Plant material information tracking system (ZMITS) software development and integration project management plan

    International Nuclear Information System (INIS)

    IBSEN, T.G.

    1999-01-01

    This document plans for software and interface development governing the implementation of ZMITS and other supporting systems necessary to manage information for material stabilization needs of the Project Hanford Management Contract (PHMC)

  15. Green technology foresight of products and materials - some reflections and results from an ongoing Danish project

    DEFF Research Database (Denmark)

    Jørgensen, Michael Søgaard; Pedersen, Thomas Thoning; Falch, Morten

    2005-01-01

    The article presents some methodological and theoretical reflections and some preliminary results from a Danish Green Technology Foresight project about environmental friendly products and materials, where the environmental potentials and risks from three technology areas are analysed: nano- bio...

  16. Using an Undergraduate Materials Research Project to Foster Multidisciplinary Teaming Skills

    Science.gov (United States)

    Newell, James A.; Cleary, Doug D.

    2004-01-01

    This paper describes the use of undergraduate materials multidisciplinary research projects as a means of addressing the growing industrial demand for graduates experienced in working in multidisciplinary teams. It includes a detailed description of a project in which a multidisciplinary team of chemical engineering and civil engineering students…

  17. A post-contract project analysis of material waste and cost overrun ...

    African Journals Online (AJOL)

    Material waste and cost overrun have been identified as common problems in the construction industry. These problems occur at both pre- and post-contract stages of a construction project. As a result of a dearth of empirical research and low level of awareness, the majority of managers of construction projects in Nigeria ...

  18. Evaluation of the Benefits Attributable to Automotive Lightweight Materials Program Research and Development Projects; TOPICAL

    International Nuclear Information System (INIS)

    Das, S

    2001-01-01

    The purpose of this project is to identify and test methods appropriate for estimating the benefits attributable to research and development (R and D) projects funded by the Automotive Lightweight Materials (ALM) Program of the Office of Advanced Automotive Technologies (OAAT) of the U.S. Department of Energy (DOE). Funded projects range from basic materials science research to applied research in production environments. Collaborators on these projects include national laboratories, universities, and private sector firms, such as leading automobile manufacturers and their suppliers. Three ALM R and D projects were chosen for this pilot evaluation: Low-Cost, Continuous Cast Aluminum Sheet; Advanced Forming Technologies for Aluminum; and Manufacturing of Composite Automotive Structures. These projects were chosen because they represent a range of benefits evaluation situations. The first project resulted in an improved process that may be commercialized. The second project is on going and has two distinct components. The third project has yielded an improved technology that has been commercialized. This completed project also benefited from numerous complementary projects

  19. Construction projects using alternative materials: a framework to assess their sustainability.

    OpenAIRE

    Fevre-Gautier , Anne-Lise; Beylot , Antoine; Vaxelaire , Stéphane; Michel , Pascale; Brullot , Sabrina; Lannou , Grégory; Stoos , Marion

    2012-01-01

    The increasing use of alternative materials and local solutions for construction projects raises questions about success conditions and criteria for the economic feasibility and global sustainability of such projects. Among others, how can design conditions - especially regarding the decision process - determine their success? We will present the results of a two-years project conducted from February 2010 to March 2012 in collaboration with ADEME (French agency of environment and energy contr...

  20. Comparative study on TSPM levels, anions and trace metal concentrations at BARC during the years 2000-2002

    International Nuclear Information System (INIS)

    Saradhi, I.V.; Prathibha, P.; Kothai, G.; Mahadevan, T.N.; Venkat Raj, V.; Kumar, Shaji C.

    2003-01-01

    Both total and respirable suspended particulate matter in the ambient air of Mumbai have been identified as the single largest pollutant associated with the health impacts in the community. This study deals with the extensive monitoring work carried out at BARC, Trombay during the period 2000-2002. The paper also deals with the comparative status of the TSPM levels and select trace metal and anion concentrations. While Pb levels have stabilized over the years following the introduction of unleaded gasoline, sulphate as a major contributor in the fine fraction of SPM assumes importance. The possible source profiles are presented and discussed. (author)

  1. Modification in existing SF6 gas handling system at 14UD BARC-TIFR Pelletron Accelerator, Mumbai

    International Nuclear Information System (INIS)

    Ninawe, N.G.; Gupta, S.K.; Ramjilal; Sparrow, Hillary; Sharma, S.C.; Bhagwat, P.V.; Salvi, S.B.

    2003-01-01

    BARC-TIFR 14 UD Pelletron Accelerator facility at TIFR, Mumbai is operational since inception 1989. The accelerator is housed inside a pressure vessel of 6 metre diameter, 25 metre long and 525m 3 volume. The accelerator tank is pressurized with SF 6 at 80 to 100 psig in order to achieve 14MV. The inventory of SF 6 gas is about 18,000 Kg (approximately) at 80 psig. SF 6 gas can be transported from Accelerator tank to storage tank using gas handling system, which consists of oil free compressor, vacuum pump, dust filters, oil filters, dryers etc

  2. FUNCTIONAL MODEL OF THE MATERIAL RESOURCES MANAGEMENT FOR PROJECTS OF THE CREATION OF NEW TECHNIQUES

    Directory of Open Access Journals (Sweden)

    S. Yu. Danshyna

    2016-01-01

    Full Text Available The article is devoted to problem of material management arising in the implementation of projects for the development and creation (modernization of the new techniques. The uniqueness of the projects, their limit on the cost and time does not allow the use of traditional approaches to resource management. Such projects are often implemented in the development of companies; where it is not possible to abandon the traditional operating methods of management. The aim of the article is a formalization of the process of material management of projects, a description of its information flows for integrate into the project management practices and for improve the efficiency of material management. For the systematization of information arising from the material resources management, invited the set-theoretic representation of the management process. According with the requirements of project management standards were described the sets and defined rules of their transformation. Specification of the set-theoretic representation helped to establish the area and limits of the modelling process. Further decomposition process became the basis of the functional model, constructed in accordance with the methodology IDEF 0. A graphical representation of the model allows you to visualize the process at different levels of detail. For specification of issues related to the organization and promotion of material flow, were developed functional models of sub-processes and were described the identified data-flows. For the harmonization of process and project approaches formulated conditions for evaluating the efficiency of material management. The developed models can be the basis for designing the structure of companies, for regulation of their project activities, as well as for establishing an information system of management resources of projects.

  3. Law project on the radioactive materials and wastes management 2006 recommendations presented by Anne Duthilleul

    International Nuclear Information System (INIS)

    2006-01-01

    This document provides recommendations on the law project concerning the radioactive material and wastes management. It precises the law objectives, the french particularities concerning the radioactive wastes and materials management, the public debate in France, the evaluation of the researches, the recommendations of the economic and social council. (A.L.B.)

  4. Towards A Framework For ICT-Enabled Materials Management In Complex Projects

    Directory of Open Access Journals (Sweden)

    N. B. Kasim

    2011-10-01

    Full Text Available This paper describes a research project, aimed at developing a system to integrate RFID-based materials management with resources modelling in project management to improve on-site materials tracking and inventory management processes. In order to develop the system, a comprehensive literature review and exploratory case studies were conducted to investigate current practices, problems, implementation of ICT and potential use of emerging technologies (such as RFID and wireless technologies in overcoming the logistical difficulties associated with materials management. An initial assessment revealed that there is a potential to improve the tracking and management of materials using modern ICT, thus will enhance the operational efficiency of the project delivery process. Moreover, sophisticated technologies such as wireless systems and tagging are not generally used to overcome human error in materials identification and the space constraints inherent in many projects. This paper concludes the finding from case studies for developing a real-time materials tracking framework to support construction professional in handling materials more effectively.

  5. Project GRETE: evaluation of non destructive testing techniques for monitoring of material degradation

    International Nuclear Information System (INIS)

    Coste, J.F.

    2001-01-01

    The material aging of major critical components of nuclear installations due to in-service conditions may lead to a degradation of their mechanical characteristics. The early detection of material changes and their monitoring using innovative non destructive testing techniques would allow to plan actions in order to prevent the apparition of macroscopic damage (e.g. cracks). One major difficulty in using these particular techniques is to correlate the changes in the measured NDT signals to the microstructural changes in the material due to aging. This problem may be solved through careful microstructural examinations of the material damage. The objective of the project GRETE is to illustrate the potential use of NDT techniques for the monitoring of material degradation through two examples: neutron irradiation of reactor pressure vessel steel and thermal fatigue of piping. The purpose of this paper is to present the project and its programme of work. (author)

  6. The development of thematic materials using project based learning for elementary school

    Science.gov (United States)

    Yuliana, M.; Wiryawan, S. A.; Riyadi

    2018-05-01

    Teaching materials is one of the important factors in supporting on learning process. This paper discussed about developing thematic materials using project based learning. Thematic materials are designed to make students to be active, creative, cooperative, easy in thinking to solve the problem. The purpose of the research was to develop thematic material using project based learning which used valid variables. The method of research which used in this research was four stages of research and development proposed by Thiagarajan consisting of 4 stages, namely: (1) definition stage, (2) design stage, (3) development stage, and (4) stage of dissemination. The first stage was research and information collection, it was in form of need analysis with questionnaire, observation, interview, and document analysis. Design stage was based on the competencies and indicator. The third was development stage, this stage was used to product validation from expert. The validity of research development involved media validator, material validator, and linguistic validator. The result from the validation of thematic material by expert showed that the overall result had a very good rating which ranged from 1 to 5 likert scale, media validation showed a mean score 4,83, the material validation showed mean score 4,68, and the mean of linguistic validation was e 4,74. It showed that the thematic material using project based learning was valid and feasible to be implemented in the context thematic learning.

  7. Preliminary selection criteria for the Yucca Mountain Project waste package container material

    International Nuclear Information System (INIS)

    Halsey, W.G.

    1991-01-01

    The Department of Energy's Yucca Mountain Project (YMP) is evaluating a site at Yucca Mountain in Nevada for construction of a geologic repository for the storage of high-level nuclear waste. Lawrence Livermore National Laboratory's (LLNL) Nuclear Waste Management Project (NWMP) has the responsibility for design, testing, and performance analysis of the waste packages. The design is performed in an iterative manner in three sequential phases (conceptual design, advanced conceptual design, and license application design). An important input to the start of the advanced conceptual design is the selection of the material for the waste containers. The container material is referred to as the 'metal barrier' portion of the waste package, and is the responsibility of the Metal Barrier Selection and Testing task at LLNL. The selection will consist of several steps. First, preliminary, material-independent selection criteria will be established based on the performance goals for the container. Second, a variety of engineering materials will be evaluated against these criteria in a screening process to identify candidate materials. Third, information will be obtained on the performance of the candidate materials, and final selection criteria and quantitative weighting factors will be established based on the waste package design requirements. Finally, the candidate materials will be ranked against these criteria to determine whether they meet the mandated performance requirements, and to provide a comparative score to choose the material for advanced conceptual design activities. This document sets forth the preliminary container material selection criteria to be used in screening candidate materials. 5 refs

  8. Waste-efficient materials procurement for construction projects: A structural equation modelling of critical success factors.

    Science.gov (United States)

    Ajayi, Saheed O; Oyedele, Lukumon O

    2018-05-01

    Albeit the understanding that construction waste is caused by activities ranging from all stages of project delivery process, research efforts have been concentrated on design and construction stages, while the possibility of reducing waste through materials procurement process is widely neglected. This study aims at exploring and confirming strategies for achieving waste-efficient materials procurement in construction activities. The study employs sequential exploratory mixed method approach as its methodological framework, using focus group discussion, statistical analysis and structural equation modelling. The study suggests that for materials procurement to enhance waste minimisation in construction projects, the procurement process would be characterised by four features. These include suppliers' commitment to low waste measures, low waste purchase management, effective materials delivery management and waste-efficient Bill of Quantity, all of which have significant impacts on waste minimisation. This implies that commitment of materials suppliers to such measures as take back scheme and flexibility in supplying small materials quantity, among others, are expected of materials procurement. While low waste purchase management stipulates the need for such measures as reduced packaging and consideration of pre-assembled/pre-cut materials, efficient delivery management entails effective delivery and storage system as well as adequate protection of materials during the delivery process, among others. Waste-efficient specification and bill of quantity, on the other hand, requires accurate materials take-off and ordering of materials based on accurately prepared design documents and bill of quantity. Findings of this study could assist in understanding a set of measures that should be taken during materials procurement process, thereby corroborating waste management practices at other stages of project delivery process. Copyright © 2018. Published by Elsevier Ltd.

  9. Sensing and collecting radioactive materials as a project to teach engineering design

    International Nuclear Information System (INIS)

    Drake, D.; Majdi, T.; Strack, J.

    2015-01-01

    The remote detection and isolation of radioactive materials is both a challenging engineering design project and a relevant issue given modern nuclear circumstances. This project is used in the undergraduate capstone class of the Engineering Physics Department at McMaster University to teach students engineering design. This paper discusses the course outline and learning outcomes of the students who took the course over the 2014-2015 academic year. (author)

  10. Sensing and collecting radioactive materials as a project to teach engineering design

    Energy Technology Data Exchange (ETDEWEB)

    Drake, D.; Majdi, T.; Strack, J., E-mail: draked2@mcmaster.ca [McMaster University, Hamiltion, ON (Canada); and others

    2015-07-01

    The remote detection and isolation of radioactive materials is both a challenging engineering design project and a relevant issue given modern nuclear circumstances. This project is used in the undergraduate capstone class of the Engineering Physics Department at McMaster University to teach students engineering design. This paper discusses the course outline and learning outcomes of the students who took the course over the 2014-2015 academic year. (author)

  11. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    International Nuclear Information System (INIS)

    1995-01-01

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system

  12. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

  13. GCD TechPort Data Sheets Thermal Protection System Materials (TPSM) Project

    Science.gov (United States)

    Chinnapongse, Ronald L.

    2014-01-01

    The Thermal Protection System Materials (TPSM) Project consists of three distinct project elements: the 3-Dimensional Multifunctional Ablative Thermal Protection System (3D MAT) project element; the Conformal Ablative Thermal Protection System (CA-TPS) project element; and the Heatshield for Extreme Entry Environment Technology (HEEET) project element. 3D MAT seeks to design, develop and deliver a game changing material solution based on 3-dimensional weaving and resin infusion approach for manufacturing a material that can function as a robust structure as well as a thermal protection system. CA-TPS seeks to develop and deliver a conformal ablative material designed to be efficient and capable of withstanding peak heat flux up to 500 W/ sq cm, peak pressure up to 0.4 atm, and shear up to 500 Pa. HEEET is developing a new ablative TPS that takes advantage of state-of-the-art 3D weaving technologies and traditional manufacturing processes to infuse woven preforms with a resin, machine them to shape, and assemble them as a tiled solution on the entry vehicle substructure or heatshield.

  14. IAEA TC Project 'Strengthening safety and reliability of fuel and materials in nuclear power plants'

    International Nuclear Information System (INIS)

    Makihara, Y.

    2008-01-01

    The Regional TC Project in Europe RER9076 'Strengthening Safety and Reliability of Fuel and Materials in Nuclear Power Plants' was launched in 2003 as a four-year project and was subsequently extended in 2006 to run through 2008. The purpose of the Project is to support the Central and Eastern European countries with the necessary tools to fulfill their own fuel and material licensing needs. The main objective will be to provide quality data on fuel and materials irradiated in power reactors and in dedicated experiments carried out in material test reactors (MTRs). Within the framework of the Project, ten tasks were implemented. These included experiments performed at the test facilities in the region, training courses and workshops related to fuel safety. While several tasks are expected to be completed by the end of RER9076, some remain. It would be desirable to initiate a new RER Project from the next TC cycle (2009-2011) in order to take over RER9076 and to implement new tasks required for enhancing fuel safety in the region. (author)

  15. An overview of the fuels and materials testing programme at the OECD Halden Reactor Project

    Energy Technology Data Exchange (ETDEWEB)

    Wiesenack, W [Institutt for Energiteknikk, Halden (Norway). OECD Halden Reaktor Projekt

    1997-08-01

    The fuels and materials testing programme of the OECD Halden Reactor Project is aimed at investigations of fuel and cladding properties at high burnup, water chemistry effects and in-core materials ageing problems. For the execution of this programme, different types of irradiation rigs and experimental facilities providing typical power reactors conditions are available. Data are obtained from in-core sensors developed at the Halden Project; these are shortly described. An overview of the current test programme and the scope of the following years are briefly presented. (author). 5 refs, 3 figs.

  16. Evaluation of copper, aluminum bronze, and copper-nickel for YMP [Yucca Mountain Project] container material

    International Nuclear Information System (INIS)

    Kass, J.N.

    1989-05-01

    In this presentation, I will discuss our evaluation of the materials copper, 7% aluminum bronze, and 70/30 copper-nickel. These are three of the six materials currently under consideration as potential waste-packaging materials. I should mention that we are also considering alternatives to these six materials. This work is part of the Yucca Mountain Project (YMP), formerly known as the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. The expected-case environment in our proposed vault is quite different from that encountered at the WIPP site or that expected in a Canadian vault. Our proposed site is under a desert mountain, Yucca Mountain, in southern Nevada. The repository itself will be located approximately 700 feet above the water table and 300 to 1200 feet below the surface of the mountain. The variations in these numbers are due to the variations in mountain topography

  17. ARCHER Project: Progress on Material and component activities for the Advanced High Temperature Reactor

    International Nuclear Information System (INIS)

    Buckthorpe, D.E.

    2014-01-01

    The ARCHER (Advanced High-Temperature Reactors for Cogeneration of Heat and Electricity R&D) integrated project is a four year project which was started in 2011 as part of the European Commission 7th Framework Programme (FP7) to perform High Temperature Reactor technology R&D in support of reactor demonstration. The project consortium encompasses conventional and Nuclear Industry, Utilities, Technical Support Organizations, Research & Development Organizations and Academia. The activities involved contribute to the Generation IV (GIF) International Forum and collaborate with related projects in the US, China, Japan, and the Republic of Korea in cooperation with IAEA and ISTC. This paper addresses the progress of the work on ARCHER materials and component activities since the start of the project and underlines some of the main conclusions reached. (author)

  18. Materials Information for Science and Technology (MIST): Project overview: Phase 1 and 2 and general considerations

    Energy Technology Data Exchange (ETDEWEB)

    Grattidge, W.; Westbrook, J.; McCarthy, J.; Northrup, C. Jr.; Rumble, J. Jr.

    1986-11-01

    The National Bureau of Standards and the Department of Energy have embarked on a program to build a demonstration computerized materials data system called Materials Information for Science and Technology (MIST). This report documents the first two phases of the project. The emphasis of the first phase was on determining what information was needed and how it could impact user productivity. The second phase data from the Aerospace Metal Handbook on a set of alloys was digitized and incorporated in the system.

  19. 76 FR 41308 - Strata Energy, Inc., Ross In Situ Recovery Uranium Project, Crook County, WY; Notice of Materials...

    Science.gov (United States)

    2011-07-13

    ..., Inc., Ross In Situ Recovery Uranium Project, Crook County, WY; Notice of Materials License Application...-4737, or by e-mail to [email protected] . The Ross In Situ Recovery Uranium Project License... source and byproduct materials license at its Ross In Situ Recovery Uranium Project site located in Crook...

  20. A computer based approach for Material, Manpower and Equipment managementin the Construction Projects

    Science.gov (United States)

    Sasidhar, Jaladanki; Muthu, D.; Venkatasubramanian, C.; Ramakrishnan, K.

    2017-07-01

    The success of any construction project will depend on efficient management of resources in a perfect manner to complete the project with a reasonable budget and time and the quality cannot be compromised. The efficient and timely procurement of material, deployment of adequate labor at correct time and mobilization of machinery lacking in time, all of them causes delay, lack of quality and finally affect the project cost. It is known factor that Project cost can be controlled by taking corrective actions on mobilization of resources at a right time. This research focuses on integration of management systems with the computer to generate the model which uses OOM data structure which decides to include automatic commodity code generation, automatic takeoff execution, intelligent purchase order generation, and components of design and schedule integration to overcome the problems of stock out. To overcome the problem in equipment management system inventory management module is suggested and the data set of equipment registration number, equipment number, description, date of purchase, manufacturer, equipment price, market value, life of equipment, production data of the equipment which includes equipment number, date, name of the job, hourly rate, insurance, depreciation cost of the equipment, taxes, storage cost, interest, oil, grease, and fuel consumption, etc. is analyzed and the decision support systems to overcome the problem arising out improper management is generated. The problem on labor is managed using scheduling, Strategic management of human resources. From the generated support systems tool, the resources are mobilized at a right time and help the project manager to finish project in time and thereby save the abnormal project cost and also provides the percentage that can be improved and also research focuses on determining the percentage of delays that are caused by lack of management of materials, manpower and machinery in different types of projects

  1. Project for a beam line consecrated to soft condensed matter, common heterogeneous materials and non-crystalline materials on soleil

    International Nuclear Information System (INIS)

    Ne, F.; Zemb, T.

    1998-01-01

    This project is a part of the 'SOLEIL' synchrotron project. The camera proposed is optimized for small angle x-ray scattering in the domain of soft condensed matter, common heterogeneous materials such as wood, cements, glass, and more generally non-crystalline materials. The beam line is designed to allow a quick succession of different users without time consuming adjustments. Therefore, optical settings are minimized, taking into account the pluri-disciplinary nature of the analysis possibilities. To this end, the technical requirements are as follows. First and essentially, the wave-length has to be fixed and set around 12 keV. Focusing mirrors, optics to sample and sample to detector distances, and the size of the detector allow for a wide range of wave vector to be used. Rejection rate will be lower, and angular dynamical range will be larger than any of the current synchrotron lines. We want this line to be, and to stay, complementary to more specific systems, such as reflectivity experiments or grazing angle scattering experiments. However, we are thinking of an adaptation to ultra small angle scattering mode, based on the Bonse and Hart camera. Such equipment, actually a kind of 'Instamatic' of the reciprocal space, will fulfill to the need of chemical engineers, biophysicists or material scientists interested in hard as well as soft condensed matter. It will allow a large amount of experiments per time unit. (author)

  2. The projected relative index of consequence equivalence of transport of radioactive materials

    International Nuclear Information System (INIS)

    Nandakumar, A.N.

    1999-01-01

    The need exists for defining a unit risk factor to enable analysis to make a proper decision when faced with many options relating to the transport of radioactive materials between sites. A method is discussed for deriving such a factor with reference to the collective dose receivable due to the transport of radioactive material incidental to the production of one GWe.a of nuclear power. This quantity would enable the analyst to determine the projected relative index of consequence equivalence (PRICE) for the transport of various types of radioactive materials. (author)

  3. Evaluation of the Benefits Attributable to Automotive Lighweight Materials Program Research and Development Projects

    Energy Technology Data Exchange (ETDEWEB)

    Das, S.

    2002-01-11

    The purpose of this project is to identify and test methods appropriate for estimating the benefits attributable to research and development (R and D) projects funded by the Automotive Lightweight Materials (ALM) Program of the Office of Advanced Automotive Technologies (OAAT) of the U.S. Department of Energy (DOE). The program focuses on the development and validation of advanced lightweight materials technologies to significantly reduce automotive vehicle body and chassis weight without compromising other attributes such as safety, performance, recyclability, and cost. The work supports the goals of the Partnership for a New Generation of Vehicles (PNGV). Up to thirty percent of the improvement required to meet the PNGV goal of tripling vehicle fuel economy and much of its cost, safety, and recyclability goal depend on the lightweight materials. Funded projects range from basic materials science research to applied research in production environments. Collaborators on these projects include national laboratories, universities, and private sector firms, such as leading automobile manufacturers and their suppliers.

  4. 76 FR 71082 - Strata Energy, Inc., Ross Uranium Recovery Project; New Source Material License Application...

    Science.gov (United States)

    2011-11-16

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 40-9091; NRC-2011-0148] Strata Energy, Inc., Ross Uranium Recovery Project; New Source Material License Application; Notice of Intent To Prepare a... intent to prepare a supplemental environmental impact statement. SUMMARY: Strata Energy, Inc. (Strata...

  5. Fast three-material modeling with triple arch projection for electronic cleansing in CTC.

    Science.gov (United States)

    Lee, Hyunna; Lee, Jeongjin; Kim, Bohyoung; Kim, Se Hyung; Shin, Yeong-Gil

    2014-07-01

    In this paper, we propose a fast three-material modeling for electronic cleansing (EC) in computed tomographic colonography. Using a triple arch projection, our three-material modeling provides a very quick estimate of the three-material fractions to remove ridge-shaped artifacts at the T-junctions where air, soft-tissue (ST), and tagged residues (TRs) meet simultaneously. In our approach, colonic components including air, TR, the layer between air and TR, the layer between ST and TR (L(ST/TR)), and the T-junction are first segmented. Subsequently, the material fraction of ST for each voxel in L(ST/TR) and the T-junction is determined. Two-material fractions of the voxels in L(ST/TR) are derived based on a two-material transition model. On the other hand, three-material fractions of the voxels in the T-junction are estimated based on our fast three-material modeling with triple arch projection. Finally, the CT density value of each voxel is updated based on our fold-preserving reconstruction model. Experimental results using ten clinical datasets demonstrate that the proposed three-material modeling successfully removed the T-junction artifacts and clearly reconstructed the whole colon surface while preserving the submerged folds well. Furthermore, compared with the previous three-material transition model, the proposed three-material modeling resulted in about a five-fold increase in speed with the better preservation of submerged folds and the similar level of cleansing quality in T-junction regions.

  6. Aspects of investment protection in the case of raw material projects; Aspekte des Investitionsschutzes bei Rohstoffprojekten

    Energy Technology Data Exchange (ETDEWEB)

    Wolkewitz, Mathias [Wintershall Holding GmbH, Kassel (Germany). Bereich Recht, Steuern und Versicherungen; TU Clausthal (Germany). Inst. fuer Energierecht

    2011-04-15

    Addressing the question of investment protection currently is of particular importance under the tree aspects: (a) Due to the financial crisis and economic crisis, foreign investment in the years 2008 and 2009 have been drastically reduced; (b) There is a growing critique at the system of international investment protection; (c) For the first time, the Articles 206 and 207 of the Treaty of Lisbon of the European Union show a competence for foreign direct investment. These three aspects seem partly contradictory, but have a considerable changing potential in the area of investment protection. The author of the contribution under consideration describes the tools of investment protection as those are used for raw material projects. Subsequently the author picks out investment protection agreements and deals with some aspects that are important for practical applications in business companies. Raw material projects are projects for the exploration and production of oil and gas in foreign states.

  7. Simultaneous planning of the project scheduling and material procurement problem under the presence of multiple suppliers

    Science.gov (United States)

    Tabrizi, Babak H.; Ghaderi, Seyed Farid

    2016-09-01

    Simultaneous planning of project scheduling and material procurement can improve the project execution costs. Hence, the issue has been addressed here by a mixed-integer programming model. The proposed model facilitates the procurement decisions by accounting for a number of suppliers offering a distinctive discount formula from which to purchase the required materials. It is aimed at developing schedules with the best net present value regarding the obtained benefit and costs of the project execution. A genetic algorithm is applied to deal with the problem, in addition to a modified version equipped with a variable neighbourhood search. The underlying factors of the solution methods are calibrated by the Taguchi method to obtain robust solutions. The performance of the aforementioned methods is compared for different problem sizes, in which the utilized local search proved efficient. Finally, a sensitivity analysis is carried out to check the effect of inflation on the objective function value.

  8. Development of a compact 25-channel preamplifier module for Si-pad detectors of the BARC-CPDA

    International Nuclear Information System (INIS)

    Inkar, A.; John, Bency; Vind, R.P.; Kinage, L.; Jangale, R.V.; Biswas, D.C.; Nayak, B.K.

    2011-01-01

    The BARC Charged Particle Detector Array modules use indigenously developed Si pad detectors as their first element. Total number of charge sensitive pre-amplifiers required for the Si-pad detectors is 250. One of the main ideas here is a layout of five pre-amplifiers connected with one Si-pad detector (called a bank of preamplifiers). In the present work, a 25-channel pre-amplifier module that can cater to 5 independent Si-pad detectors, or a five-bank module, has been developed. This module uses pre-amp hybrid chips A1422H from CAEN S.p.A. and is housed in a double width NIM standard box. The module has been tested for performance using proton and ''7Li beams from FOTIA facility, Trombay

  9. Search for the Pentaquark via the Decay $P^0_{\\bar{c}s} \\to \\phi \\pi \\rho$

    Energy Technology Data Exchange (ETDEWEB)

    Beck, S.Maytal [Tel Aviv U.

    1998-01-01

    This work reports results of the first search for the pentaquark, which is predicted to be a doublet of states: $P^0_{\\bar{c}s} = \\mid \\bar{c}suud$ > and $P^-_{\\bar{c}s}$ = $\\mid \\bar{c}sddu>$. The color hyperfine interaction between their constituent quarks results in a maximal binding potential of 150 MeV. Calculations done using other models predict that the pentaquark is either bound or is a near-threshold resonance. A bound pentaquark would have a mass below 2.907 GeV /$c^2$ and its lifetime would be like that of other charm particles, of the order of $10^{-13}$ s. Crude estimates of the pentaquark production cross section predict values of the order of 1 % of that of the $D_s$. Observation of the pentaquark is interesting for its unusual structure and would contribute to the understanding of QCD and the concept of confinement....

  10. Evolution of Safeguards over Time: Past, Present, and Projected Facilities, Material, and Budget

    International Nuclear Information System (INIS)

    Kollar, Lenka; Mathews, Caroline E.

    2009-01-01

    This study examines the past trends and evolution of safeguards over time and projects growth through 2030. The report documents the amount of nuclear material and facilities under safeguards from 1970 until present, along with the corresponding budget. Estimates for the future amount of facilities and material under safeguards are made according to non-nuclear-weapons states (NNWS) plans to build more nuclear capacity and sustain current nuclear infrastructure. Since nuclear energy is seen as a clean and economic option for base load electric power, many countries are seeking to either expand their current nuclear infrastructure, or introduce nuclear power. In order to feed new nuclear power plants and sustain existing ones, more nuclear facilities will need to be built, and thus more nuclear material will be introduced into the safeguards system. The projections in this study conclude that a zero real growth scenario for the IAEA safeguards budget will result in large resource gaps in the near future.

  11. Evolution of Safeguards over Time: Past, Present, and Projected Facilities, Material, and Budget

    Energy Technology Data Exchange (ETDEWEB)

    Kollar, Lenka; Mathews, Caroline E.

    2009-07-01

    This study examines the past trends and evolution of safeguards over time and projects growth through 2030. The report documents the amount of nuclear material and facilities under safeguards from 1970 until present, along with the corresponding budget. Estimates for the future amount of facilities and material under safeguards are made according to non-nuclear-weapons states’ (NNWS) plans to build more nuclear capacity and sustain current nuclear infrastructure. Since nuclear energy is seen as a clean and economic option for base load electric power, many countries are seeking to either expand their current nuclear infrastructure, or introduce nuclear power. In order to feed new nuclear power plants and sustain existing ones, more nuclear facilities will need to be built, and thus more nuclear material will be introduced into the safeguards system. The projections in this study conclude that a zero real growth scenario for the IAEA safeguards budget will result in large resource gaps in the near future.

  12. Proliferation Resistance and Material Type considerations within the Collaborative Project for a European Sodium Fast Reactor

    International Nuclear Information System (INIS)

    Renda, Guido; Alim, Fatih; Cojazzi, Giacomo GM.

    2015-01-01

    The collaborative project for a European Sodium Fast Reactor (CP‑ESFR) is an international project where 25 European partners developed Research & Development solutions and concepts for a European sodium fast reactor. The project was funded by the 7. European Union Framework Programme and covered topics such as the reactor architectures and components, the fuel, the fuel element and the fuel cycle, and the safety concepts. Within sub‑project 3, dedicated to safety, a task addressed proliferation resistance considerations. The Generation IV International Forum (GIF) Proliferation Resistance and Physical Protection (PR and PP) Evaluation Methodology has been selected as the general framework for this work, complemented by punctual aspects of the IAEA‑INPRO Proliferation Resistance methodology and other literature studies - in particular for material type characterization. The activity has been carried out taking the GIF PR and PP Evaluation Methodology and its Addendum as the general guideline for identifying potential nuclear material diversion targets. The targets proliferation attractiveness has been analyzed in terms of the suitability of the targets’ nuclear material as the basis for its use in nuclear explosives. To this aim the PR and PP Fissile Material Type measure was supplemented by other literature studies, whose related metrics have been applied to the nuclear material items present in the considered core alternatives. This paper will firstly summarize the main ESFR design aspects relevant for PR following the structure of the GIF PR and PP White Paper template. An analysis on proliferation targets is then discussed, with emphasis on their characterization from a nuclear material point of view. Finally, a high‑level ESFR PR analysis according to the four main proliferation strategies identified by the GIF PR and PP Evaluation Methodology (concealed diversion, concealed misuse, breakout, clandestine production in clandestine facilities) is

  13. Material decomposition in an arbitrary number of dimensions using noise compensating projection

    Science.gov (United States)

    O'Donnell, Thomas; Halaweish, Ahmed; Cormode, David; Cheheltani, Rabee; Fayad, Zahi A.; Mani, Venkatesh

    2017-03-01

    Purpose: Multi-energy CT (e.g., dual energy or photon counting) facilitates the identification of certain compounds via data decomposition. However, the standard approach to decomposition (i.e., solving a system of linear equations) fails if - due to noise - a pixel's vector of HU values falls outside the boundary of values describing possible pure or mixed basis materials. Typically, this is addressed by either throwing away those pixels or projecting them onto the closest point on this boundary. However, when acquiring four (or more) energy volumes, the space bounded by three (or more) materials that may be found in the human body (either naturally or through injection) can be quite small. Noise may significantly limit the number of those pixels to be included within. Therefore, projection onto the boundary becomes an important option. But, projection in higher than 3 dimensional space is not possible with standard vector algebra: the cross-product is not defined. Methods: We describe a technique which employs Clifford Algebra to perform projection in an arbitrary number of dimensions. Clifford Algebra describes a manipulation of vectors that incorporates the concepts of addition, subtraction, multiplication, and division. Thereby, vectors may be operated on like scalars forming a true algebra. Results: We tested our approach on a phantom containing inserts of calcium, gadolinium, iodine, gold nanoparticles and mixtures of pairs thereof. Images were acquired on a prototype photon counting CT scanner under a range of threshold combinations. Comparison of the accuracy of different threshold combinations versus ground truth are presented. Conclusions: Material decomposition is possible with three or more materials and four or more energy thresholds using Clifford Algebra projection to mitigate noise.

  14. Search for hidden high-Z materials inside containers with the Muon Portal Project

    International Nuclear Information System (INIS)

    Rocca, P La; Bandieramonte, M; Blancato, A A; Bonanno, D; Indelicato, V; Presti, D Lo; Petta, C; Antonuccio, V; Becciani, U; Belluso, M; Billotta, S; Bonanno, G; Costa, A; Garozzo, S; Massimino, P; Belluomo, F; Fallica, G; Leonora, E; Longhitano, F; Longo, S

    2014-01-01

    The Muon Portal is a recently born project that plans to build a large area muon detector for a noninvasive inspection of shipping containers in the ports, searching for the presence of potential fissile (U, Pu) threats. The technique employed by the project is the well-known muon tomography, based on cosmic muon scattering from high-Z materials. The design and operational parameters of the muon portal under construction will be described in this paper, together with preliminary simulation and test results

  15. Search for hidden high-Z materials inside containers with the Muon Portal Project

    Science.gov (United States)

    La Rocca, P.; Antonuccio, V.; Bandieramonte, M.; Becciani, U.; Belluomo, F.; Belluso, M.; Billotta, S.; Blancato, A. A.; Bonanno, D.; Bonanno, G.; Costa, A.; Fallica, G.; Garozzo, S.; Indelicato, V.; Leonora, E.; Longhitano, F.; Longo, S.; Lo Presti, D.; Massimino, P.; Petta, C.; Pistagna, C.; Pugliatti, C.; Puglisi, M.; Randazzo, N.; Riggi, F.; Riggi, S.; Romeo, G.; Russo, G. V.; Santagati, G.; Valvo, G.; Vitello, F.; Zaia, A.; Zappalà, G.

    2014-01-01

    The Muon Portal is a recently born project that plans to build a large area muon detector for a noninvasive inspection of shipping containers in the ports, searching for the presence of potential fissile (U, Pu) threats. The technique employed by the project is the well-known muon tomography, based on cosmic muon scattering from high-Z materials. The design and operational parameters of the muon portal under construction will be described in this paper, together with preliminary simulation and test results.

  16. Project T100 -- Hazardous Materials Management and Emergency Response Training Center (HAMMER)

    International Nuclear Information System (INIS)

    Norton, C.E.

    1994-01-01

    The scope of this Quality Assurance Program Plan (QAPP) is to provide a system of Quality Assurance reviews and verifications on the design and construction of the Hazardous Materials Management and Emergency Response (HAMMER) Training Center, project 95L-EWT-100 at Hanford. The reviews and verifications will be on activities associated with design, procurement, and construction of the HAMMER project which includes, but is not limited to earthwork, placement of concrete, laying of rail, drilling of wells, water and sewer line fabrication and installation, communications systems, fire protection/detection systems, line tie-ins, building and mock-up (prop) construction, electrical, instrumentation, pump and valves and special coatings

  17. Integrated Water Basin Management Including a Large Pit Lake and a Water Supply Reservoir: The Mero-Barcés Basin

    Science.gov (United States)

    Delgado, Jordi; Juncosa-Rivera, Ricardo; Hernández-Anguiano, Horacio; Muñoz-Ibáñez, Andrea

    2016-04-01

    use of lake water is acceptable from different points of view (water quality, legal constrains, etc.). Our results indicate that the joint use of the lake/reservoir system is feasible. Based on this and other complementary study, the basin water authorities has developed a project by which a 2.1 km uptake tunnel will be excavated in the next years to drain water from the lake towards the Barcés river and complement the water supply necessities of the Abegondo-Cecebre reservoir in case of hydric emergencies.

  18. Project management plan, Hazardous Materials Management and Emergency Response Training Center

    International Nuclear Information System (INIS)

    Borgeson, M.E.

    1994-01-01

    For the next 30 years, the main activities at the Hanford Site will involve the handling and cleanup of toxic substances. Thousands of workers involved in these new activities will need systematic training appropriate to their tasks and associated risks. This project is an important part of the Hanford Site mission and will enable the US Department of Energy (DOE) to meet high standards for safety. The Hazardous Materials Management and Emergency Response Training Center (HAMMER) project will construct a centralized regional training center dedicated to training hazardous materials workers and emergency responders in classrooms and with hands-on, realistic training aids representing actual field conditions. The HAMMER Training Center will provide a cost-effective, high-quality way to meet the Hanford Site training needs. The training center creates a partnership among DOE; government contractors; labor; local, state, and tribal governments; and selected institutions of higher education

  19. Supporting PECO countries in combating illicit trafficking of nuclear materials - Status of ongoing projects

    International Nuclear Information System (INIS)

    Janssens, W.; Daures, P.; Cromboom, O.; Mayer, K.; Koch, L.

    2001-01-01

    Full text: In order to support the development of an efficient and validated response to counteract illicit trafficking of nuclear materials in the EU, the candidate countries and some CIS countries, ITU is currently executing a series of dedicated projects with the Candidate Countries to the European Union, based upon the experience gained in previous Phare and Tacis projects. Following the recommendations of the International Technical Working Group (ITWG), the objectives of the projects are: assessment of the national situation during a fact-finding mission in the country; technical upgrade and/or training related to the categorisation of nuclear material on the spot and assistance for the identification of seized nuclear material, through joint analysis at ITU; implementation of the recommended Model Action Plan in the form of a national handbook called RITNUM (Response to Illicit Trafficking of NUclear Material); validation of the national Model Action Plan by the organisation of a demonstration exercise in the country involving all the identified services in the field. After a kick-off meeting held in Karlsruhe in November 2000 and attended by two participants of each country, 5 fact-finding missions have been already performed (Romania, Slovenia and the three Baltic States). A general meeting with all the involved parties (Customs, Police, Intelligence services. Health Physics, Nuclear reference laboratory...) was organised to describe the procedure of the integrated response and the national needs were assessed. The corresponding training sessions are planed in January 2002 at ITU for three participants for each country (Customs and Police officer and high level scientist dealing with nuclear measurements). This training session will be organised and supported by IAEA which have a common interest through its Regional Program on Combating Illicit Trafficking (RER60). This joint action will be extended to other eastern countries (ex. Belarus) on IAEA request

  20. Feasibility study on consolidation of Fernald Environmental Management Project depleted uranium materials

    International Nuclear Information System (INIS)

    1995-01-01

    In 1991, the DOE made a decision to close the FMPC located in Fernald, Ohio, and end its production mission. The site was renamed FEMP to reflect Fernald's mission change from uranium production to environmental restoration. As a result of this change, the inventory of strategic uranium materials maintained at Fernald by DOE DP will need to be relocated to other DOE sites. Although considered a liability to the Fernald Plant due to its current D and D mission, the FEMP DU represents a potentially valuable DOE resource. Recognizing its value, it may be important for the DOE to consolidate the material at one site and place it in a safe long-term storage condition until a future DOE programmatic requirement materializes. In August 1995, the DOE Office of Nuclear Weapons Management requested, Lockheed Martin Energy Systems (LMES) to assess the feasibility of consolidating the FEMP DU materials at the Oak Ridge Reservation (ORR). This feasibility study examines various phases associated with the consolidation of the FEMP DU at the ORR. If useful short-term applications for the DU fail to materialize, then long-term storage (up to 50 years) would need to be provided. Phases examined in this report include DU material value; potential uses; sampling; packaging and transportation; material control and accountability; environmental, health and safety issues; storage; project management; noneconomic factors; schedule; and cost

  1. Advanced Industrial Materials (AIM) Program: Compilation of project summaries and significant accomplishments, FY 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    In many ways, the Advanced Industrial Materials (AIM) Program underwent a major transformation in Fiscal Year 1995 and these changes have continued to the present. When the Program was established in 1990 as the Advanced Industrial Concepts (AIC) Materials Program, the mission was to conduct applied research and development to bring materials and processing technologies from the knowledge derived from basic research to the maturity required for the end use sectors for commercialization. In 1995, the Office of Industrial Technologies (OIT) made radical changes in structure and procedures. All technology development was directed toward the seven ``Vision Industries`` that use about 80% of industrial energy and generated about 90% of industrial wastes. The mission of AIM has, therefore, changed to ``Support development and commercialization of new or improved materials to improve productivity, product quality, and energy efficiency in the major process industries.`` Though AIM remains essentially a National Laboratory Program, it is essential that each project have industrial partners, including suppliers to, and customers of, the seven industries. Now, well into FY 1996, the transition is nearly complete and the AIM Program remains reasonably healthy and productive, thanks to the superb investigators and Laboratory Program Managers. This report contains the technical details of some very remarkable work by the best materials scientists and engineers in the world. Subject areas covered are: advanced metals and composites; advanced ceramics and composites; polymers and biobased materials; and new materials and processes.

  2. Profile of Students' Creative Thinking Skills on Quantitative Project-Based Protein Testing using Local Materials

    Directory of Open Access Journals (Sweden)

    D. K. Sari

    2017-04-01

    Full Text Available The purpose of this study is to obtain a profile of students’ creative thinking skills on quantitative project-based protein testing using local materials. Implementation of the research is using quasi-experimental method pre-test post-test control group design with 40 students involved in Biochemistry lab. The research instrument is pre-test and post-test using creative thinking skills in the form of description and students’ questionnaire. The analysis was performed with SPSS 22.0 program to see the significance normality, U Mann-Whitney test for nonparametric statistics, N-Gain score, and the percentage of student responses to the practicum performed. The research result shows that the pretest rate in the experimental group is 8.25 while in the control group is 6.90. After attending a project-based practicum with local materials, the experimental group obtained the mean of posttest is 37.55 while in control class is 11.18. The students’ improvement on creative thinking skills can be seen from the average of N-Gain in the experimental class with 0.32 (medium category and in the control category with 0.05 (low category. The experimental and control class have different creative thinking skills significantly different fluency, flexibility, novelty, and detail. It can be concluded that quantitative project-based protein testing using local materials can improve students’ creative thinking skills. 71% of total students feel that quantitative project-based protein testing using local materials make them more creative in doing a practicum in the laboratory.

  3. Active Learning through Materials Development: A Project for the Advanced L2 Classroom

    Directory of Open Access Journals (Sweden)

    Katrina Daly Thompson

    2008-01-01

    Full Text Available Building on the notion of active learning, the assumption that students learn more when given opportunities to practice using their skills and to receive feedback on their performance, this article de-scribes a project undertaken in an Advanced (third-year Swahili course in which students were given the opportunity to develop L2 materials for computer-mediated peer instruction. The article exam-ines the goals, design and results of the project in light of the litera-ture on active learning and learner autonomy, and suggests how the project might be improved in order to serve as a model for other Ad-vanced L2 courses.

  4. Teaching Reform of Civil Engineering Materials Course Based on Project-Driven Pedagogy

    Science.gov (United States)

    Yidong, Xu; Wei, Chen; WeiguoJian, You; Jiansheng, Shen

    2018-05-01

    In view of the scattered experimental projects in practical courses of civil engineering materials, the poor practical ability of students and the disconnection between practical teaching and theoretical teaching, this paper proposes a practical teaching procedure. Firstly, the single experiment should be offered which emphasizes on improving the students’ basic experimental operating ability. Secondly, the compressive experiment is offered and the overall quality of students can be examined in the form of project team. In order to investigate the effect of teaching reform, the comparative analysis of the students of three grades (2014, 2015 and 2016) majored in civil engineering was conducted. The result shows that the students’ ability of experimental operation is obviously improved by using the project driven method-based teaching reform. Besides, the students’ ability to analyse and solve problems has also been improved.

  5. Bibliography of documents and related materials collected for the Hawaii Geothermal Project Environmental Impact Statement

    Energy Technology Data Exchange (ETDEWEB)

    Glenn, F.M.; Boston, C.R.; Burns, J.C.; Hagan, C.W. Jr.; Saulsbury, J.W.; Wolfe, A.K.

    1995-03-01

    This report has been prepared to make available and archive information developed during preparation of the Environmental Impact Statement for Phases 3 and 4 of the Hawaii Geothermal Project as defined by the state of Hawaii in its April 1989 proposal to Congress. On May 17, 1994, the USDOE published a notice in the Federal Register withdrawing its Notice of Intent of February 14, 1992, to prepare the HGP EIS. Since the state of Hawaii is no longer pursuing or planning to pursue the HGP, DOE considers the project to be terminated. This report provides a bibliography of documents, published papers, and other reference materials that were obtained or used. The report provides citations for approximately 642 documents, published papers, and other reference materials that were gathered to describe the potentially affected environment on the islands of Hawaii, Maui, and Oahu. The listing also does not include all the reference materials developed by support subcontractors and cooperating agencies who participated in the project. This listing does not include correspondence or other types of personal communications. The documents listed in this report can be obtained from original sources or libraries.

  6. Generation IV and transmutation materials (GETMAT) project: First assessment of selected results

    International Nuclear Information System (INIS)

    Fazio, Concetta; Serrano, Marta; Gessi, Alessandro; Henry, Jean; Malerba, Lorenzo

    2015-01-01

    The Generation IV and Transmutation Material (GETMAT) project has been initiated within the 7. EURATOM framework programme with the objective to support the development of innovative reactor designs. Emphasis has been put on the investigation, both in the theoretical and experimental domains, of selected material properties that are cross-cutting among the various Generation IV and Transmutation systems. The selection of the properties to be investigated has been performed by identifying relevant conditions of key components as cores and primary systems. Moreover, taking into account the envisaged conditions of these components it turned out that innovative materials might be a better choice with respect to conventional nuclear grade steels. Therefore, ODS alloys and 9-12 Cr Ferritic/Martensitic (F/M) steels have been selected as reference for the GETMAT project. The R and D activities have been focused on basic characterisation of ODS alloys produced ad hoc for the project and on an extensive PIE programme of F/M steels irradiated in previous programmes. Finally, first principle modelling studies to explain irradiation hardening and embrittlement of F/M alloys were an additional important task. The objective of this manuscript is to make a first assessment of the results obtained within GETMAT. (authors)

  7. Materials information for science and technology (MIST): Project overview: Phases I and II and general considerations

    Energy Technology Data Exchange (ETDEWEB)

    Grattidge, W.; Westbrook, J.; McCarthy, J.; Northrup, C. Jr.; Rumble, J. Jr.

    1986-01-01

    This report documents the initial phases of the Materials Information for Science and Technology (MIST) project jointly supported by the Department of Energy and the National Bureau of Standards. The purpose of MIST is to demonstrate the power and utility of computer access to materials property data. The initial goals include: to exercise the concept of a computer network of materials databases and to build a demonstration of such a system suitable for use as the core of operational systems in the future. Phases I and II are described in detail herein. In addition, a discussion is given of the expected usage of the system. The primary MIST prototype project is running on an IBM 3084 under STS at the Stanford University's Information Technology Services (ITS). Users can access the Stanford system via ARPANET, TELENET, and TYMNET, as well as via commercial telephone lines. For fastest response time and use of the full screen PRISM interface, direct connection using a 2400 baud modem with the MNP error-correcting protocol over standard telephone lines gives the best results - though slower speed connections and a line-oriented interface are also available. This report gives detailed plans regarding the properties to be enterend and the materials to be entered into the system.

  8. Preliminary sensitivity analyses of corrosion models for BWIP [Basalt Waste Isolation Project] container materials

    International Nuclear Information System (INIS)

    Anantatmula, R.P.

    1984-01-01

    A preliminary sensitivity analysis was performed for the corrosion models developed for Basalt Waste Isolation Project container materials. The models describe corrosion behavior of the candidate container materials (low carbon steel and Fe9Cr1Mo), in various environments that are expected in the vicinity of the waste package, by separate equations. The present sensitivity analysis yields an uncertainty in total uniform corrosion on the basis of assumed uncertainties in the parameters comprising the corrosion equations. Based on the sample scenario and the preliminary corrosion models, the uncertainty in total uniform corrosion of low carbon steel and Fe9Cr1Mo for the 1000 yr containment period are 20% and 15%, respectively. For containment periods ≥ 1000 yr, the uncertainty in corrosion during the post-closure aqueous periods controls the uncertainty in total uniform corrosion for both low carbon steel and Fe9Cr1Mo. The key parameters controlling the corrosion behavior of candidate container materials are temperature, radiation, groundwater species, etc. Tests are planned in the Basalt Waste Isolation Project containment materials test program to determine in detail the sensitivity of corrosion to these parameters. We also plan to expand the sensitivity analysis to include sensitivity coefficients and other parameters in future studies. 6 refs., 3 figs., 9 tabs

  9. Production of NDA Working Reference Materials for the Capability Evaluation Project

    International Nuclear Information System (INIS)

    Noll, P.D. Jr.; Marshall, R.S.

    1998-01-01

    The production of Non Destructive Assay (NDA) Working Reference Materials (WRMs) that are traceable to nationally recognized standards was undertaken to support implementation of the Idaho National Engineering and Environmental Laboratory (INEEL) Nondestructive Waste Assay Capability Evaluation Project (CEP). The WRMs produced for the CEP project consist of Increased Am/Pu mass ration (IAP) and depleted Uranium (DU) WRMs. The CEP IAP/DU WRM set provides radioactive material standards for use in combination with 55 gallon drum waste matrix surrogates for the assessment of waste NDA assay system performance. The Production of WRMs is a meticulous process that is not without certain trials and tribulations. Problems may arise at any of the various stages of WRM production which include, but are not limited to; material characterization (physical, chemical, and isotopic), material blend parameters, personnel radiation exposure, gas generation phenomenon, traceability to national standards, encapsulation, statistical evaluation of the data, and others. Presented here is an overall description of the process by which the CEP WRMs were produced and certified as well as discussions pertaining to some of the problems encountered and how they were solved

  10. Discriminative illumination: per-pixel classification of raw materials based on optimal projections of spectral BRDF.

    Science.gov (United States)

    Liu, Chao; Gu, Jinwei

    2014-01-01

    Classifying raw, unpainted materials--metal, plastic, ceramic, fabric, and so on--is an important yet challenging task for computer vision. Previous works measure subsets of surface spectral reflectance as features for classification. However, acquiring the full spectral reflectance is time consuming and error-prone. In this paper, we propose to use coded illumination to directly measure discriminative features for material classification. Optimal illumination patterns--which we call "discriminative illumination"--are learned from training samples, after projecting to which the spectral reflectance of different materials are maximally separated. This projection is automatically realized by the integration of incident light for surface reflection. While a single discriminative illumination is capable of linear, two-class classification, we show that multiple discriminative illuminations can be used for nonlinear and multiclass classification. We also show theoretically that the proposed method has higher signal-to-noise ratio than previous methods due to light multiplexing. Finally, we construct an LED-based multispectral dome and use the discriminative illumination method for classifying a variety of raw materials, including metal (aluminum, alloy, steel, stainless steel, brass, and copper), plastic, ceramic, fabric, and wood. Experimental results demonstrate its effectiveness.

  11. Sealing properties of cement-based grout materials used in the rock sealing project

    International Nuclear Information System (INIS)

    Onofrei, M.; Gray, M.N.; Pusch, R.; Boergesson, L.; Karnland, O.; Shenton, B.; Walker, B.

    1993-12-01

    The Task Force on Sealing Materials and Techniques of the Stripa Project recommended that work be undertaken to study the sealing properties of cement-based grout materials. A new class of cement-based grouts (high-performance grouts) with the ability to penetrate and seal fine fractures in granite was investigated. The materials were selected for their small mean particle size and the ability to be made fluid by a superplasticizer at low water/cementitious-materials ratios. The fundamental physical and chemical properties (such as the particle size and chemical composition) of the materials were evaluated. The rheological properties of freshly mixed grouts, which control the workability of the grouts, were determined together with the properties of hardened materials, which largely control the long-term performance (longevity) of the materials in repository settings. The materials selected were shown to remain gel-like during the setting period, and so the grouts may be expected to remain largely homogenous during and after injection into the rock without separating into solid and liquid phases. The hydraulic conductivity and strength of hardened grouts were determined. The microstructure of the bulk grouts was characterized by a high degree of homogeneity with extremely fine porosity. The low hydraulic conductivity and good mechanical properties are consistent with the extremely fine porosity. The ability of the fractured grouts to self-seal was also observed in tests in which the hydraulic conductivity of recompacted granulated grouts was determined. The laboratory tests were carried out in parallel with investigations of the in situ performance of the materials and with the development of geochemical and theoretical models for cement-based grout longevity. (author). 56 refs., 15 tabs., 98 figs

  12. Sealing properties of cement-based grout materials used in the rock sealing project

    Energy Technology Data Exchange (ETDEWEB)

    Onofrei, M; Gray, M N; Pusch, R; Boergesson, L; Karnland, O; Shenton, B; Walker, B

    1993-12-01

    The Task Force on Sealing Materials and Techniques of the Stripa Project recommended that work be undertaken to study the sealing properties of cement-based grout materials. A new class of cement-based grouts (high-performance grouts) with the ability to penetrate and seal fine fractures in granite was investigated. The materials were selected for their small mean particle size and the ability to be made fluid by a superplasticizer at low water/cementitious-materials ratios. The fundamental physical and chemical properties (such as the particle size and chemical composition) of the materials were evaluated. The rheological properties of freshly mixed grouts, which control the workability of the grouts, were determined together with the properties of hardened materials, which largely control the long-term performance (longevity) of the materials in repository settings. The materials selected were shown to remain gel-like during the setting period, and so the grouts may be expected to remain largely homogenous during and after injection into the rock without separating into solid and liquid phases. The hydraulic conductivity and strength of hardened grouts were determined. The microstructure of the bulk grouts was characterized by a high degree of homogeneity with extremely fine porosity. The low hydraulic conductivity and good mechanical properties are consistent with the extremely fine porosity. The ability of the fractured grouts to self-seal was also observed in tests in which the hydraulic conductivity of recompacted granulated grouts was determined. The laboratory tests were carried out in parallel with investigations of the in situ performance of the materials and with the development of geochemical and theoretical models for cement-based grout longevity. (author). 56 refs., 15 tabs., 98 figs.

  13. Analysis of explosion-induced releases of toxic materials at an environmental restoration project

    International Nuclear Information System (INIS)

    Bloom, S.G.; Moon, W.H. Jr.

    1993-01-01

    Prior to 1988, a variety of materials were buried on the US DOE Oak Ridge Reservation. Records of the disposal operations are incomplete and toxic materials may have been placed adjacent to potential explosives. One of the safety concerns in conducting an environmental restoration project at the burial sites, is the possibility of an explosion which could release toxic materials to the atmosphere. A safety analysis examined the consequences of such releases by first postulating an upper bound for the strength of an explosive. A correlation, developed by Steindler and Seefeldt of Argonne National Laboratory, was then used to estimate the amount and particle-size distribution of the material that could become airborne from the explosion. The estimated amount of airborne material was the source term in an atmospheric dispersion model which was used to calculate infinite-time, concentration-time integrals and 5-minute, time- weighted average concentrations at locations down-wind from the explosion. The dispersion model includes particle deposition as a function of particle-size distribution class. The concentration-time integrals and average concentrations were compared to published guidelines to assess the consequences of an accidental explosion

  14. The 2016-2018 National Plan of Management of Radioactive Materials and Wastes - Project

    International Nuclear Information System (INIS)

    Gazzo, Alexis; Robert, Jean-Gabriel; Abraham, Christophe; Benaze, Manon de

    2015-01-01

    A first document contains the project of the National Plan of Management of Radioactive Materials and Wastes (PNGMDR) for the period 2016-2018: principles and objectives (presentation of radioactive materials and wastes, principles to be taken into account to define pathways of management of radioactive wastes, legal and institutional framework, information transparency), the management of radioactive materials (context and challenges, management pathways, works on fast breeder reactors of fourth generation), assessment and perspectives of existing pathways of management of radioactive wastes (management of historical situations, management of residues of mining and sterile processing, management of waste with a high natural radioactivity, management of very short life waste, of very low activity wastes, and low and medium activity wastes), needs and perspectives regarding management processes to be implemented for the different types of radioactive wastes. Appendices to this document contain a recall of the content of previous PNGMDR since 2007, a synthesis of realisations and researches performed abroad, research orientations for the concerned period, and international agreement on spent fuel and radioactive waste management. A second document, released by the ASN, proposes an environmental and strategic assessment of the plan. A third one and a fourth one contain the opinion of the Environmental Authority, respectively on the plan preliminary focus, and on the plan itself. An answer to this last one is then proposed, followed by a synthesis of the plan project and the text of the corresponding decree

  15. Thermal properties variations in unconsolidated material for very shallow geothermal application (ITER project)

    Science.gov (United States)

    Sipio, Eloisa Di; Bertermann, David

    2018-04-01

    In engineering, agricultural and meteorological project design, sediment thermal properties are highly important parameters, and thermal conductivity plays a fundamental role when dimensioning ground heat exchangers, especially in very shallow geothermal systems. Herein, the first 2 m of depth from surface is of critical importance. However, the heat transfer determination in unconsolidated material is difficult to estimate, as it depends on several factors, including particle size, bulk density, water content, mineralogy composition and ground temperature. The performance of a very shallow geothermal system, as a horizontal collector or heat basket, is strongly correlated to the type of sediment at disposal and rapidly decreases in the case of dry-unsaturated conditions. The available experimental data are often scattered, incomplete and do not fully support thermo-active ground structure modeling. The ITER project, funded by the European Union, contributes to a better knowledge of the relationship between thermal conductivity and water content, required for understanding the very shallow geothermal systems behaviour in saturated and unsaturated conditions. So as to enhance the performance of horizontal geothermal heat exchangers, thermally enhanced backfilling material were tested in the laboratory, and an overview of physical-thermal properties variations under several moisture and load conditions for different mixtures of natural material was here presented.

  16. A Seven-Year Major and Trace Element Study of Rain Water in the Barcés River Watershed, A Coruña, NW Spain

    Science.gov (United States)

    Delgado, Jordi; Cereijo-Arango, José Luis; Juncosa-Rivera, Ricardo

    2016-04-01

    Precipitation constitutes an important source of soluble materials to surface waters and, in areas where they are diluted precipitation (either dry or wet) it can be the most relevant solute source. Certain trace elements may have a limited natural availability in soils and rocks although they can be important with respect the operation of different biogeochemical cycles, for the computation of local/regional atmospheric pollutant loads or from the global mass budget. In the present study we report the results obtained in a long-lasting (December 2008-December 2015) monitoring survey of the chemical composition of bulk precipitation as monthly-integrated samples taken at the headwaters of the Barcés river watershed (A Coruña, Spain). This location was selected based on the necessity of quantification of the chemical composition and elemental loads associated with the different water types (stream water, ground water and precipitation) contributing to the flooding of the Meirama lake. Available data includes information on meteorological parameters (air temperature, relative humidity, atmospheric pressure, wind speed and direction, total and PAR radiation and precipitation) as well as a wide bundle of physico-chemical (pH, redox, electrical conductivity, alkalinity, Li, Na, K, Mg, Ca, Sr, Mn, Fe, NH4, Cs, Rb, Ba, Zn, Cu, Sb, Ni, Co, Cr, V, Cd, Ag, Pb, Se, Hg, Ti, Sn, U, Mo, F, Cl, Br, SO4, NO3, NO2, Al, As, PO4, SIO2, B, O2, DIC, DOC) and isotopic (18Ov-smow and 2Hv-smow) constituents. The average pH of local precipitation is 5.6 (n=65) which is consistent with the expected value for natural, unpolluted rain water. Most of the studied elements (eg. Na, Ca, K, Mg, SiO2, etc.) shows significant increases in their concentration in the dry period of the year. That points towards a more significant contribution of dry deposition in these periods compared with the wet ones. The average electrical conductivity is about 67 S/cm while the average chloride

  17. The REEME project: a cooperative model for sharing international medical education materials.

    Science.gov (United States)

    Iserson, Kenneth V

    2008-07-01

    Although the Internet has become an excellent source of medical education materials, in many specialties, including Emergency Medicine (EM), most of the information is in English. Few international EM practitioners can attend costly specialty conferences, importing foreign experts to teach at these conferences is costly and, even then, these experts are available for a limited time to relatively few people. Countries with minimal health care or medical education budgets find providing even basic materials for professional medical education difficult. An exciting international project now freely distributes Spanish language educational programs to health care professionals on topics relating to EM. The Recursos Educacionales en Español para Medicina de Emergencia (REEME; Educational Resources in Spanish for EM) Project (www.reeme.arizona.edu) was developed to overcome some of these problems by providing language-specific specialty information and widespread international availability, and by promoting international cooperation among professional health care educators. It also provides a ready source of Spanish medical vocabulary for those trying to learn the language. With computer support from the University of Arizona's Learning and Technology Center, REEME first went "live" on November 1, 2004. Three years later, as of November 1, 2007, the site had 575 programs from 411 donors representing 19 countries and the United Nations. There are currently about 645 downloads per month to users in 73 countries. The REEME Project demonstrates the power of the Internet as a means to achieve international cooperation in medical education, and can serve as a model for similar projects in other specialties and languages.

  18. Development of AUC-based process at BARC for production of free-flowing and sinterable UO2 powder

    International Nuclear Information System (INIS)

    Keni, V.S.; Ghosh, S.K.; Ganguly, C.; Majumdar, S.

    1994-01-01

    Ammonium uranium carbonate (AUC) process has been developed and industrially used in Germany for preparation of free-flowing and sinterable UO 2 powder for fabrication of UO 2 fuel pellets for light water reactors (LWR). Efforts are underway at Bhabha Atomic Research Centre (BARC) for developing AUC-based process which would yield free-flowing UO 2 powder suitable for direct pelletisation and sintering to very high density (> 96% T.D.) UO 2 fuel pellets for pressurised heavy water reactors (PHWRs) in India. The first phase of this work has been completed jointly by Chemical Engineering Division (ChED) and Radiometallurgy Division (RMD) in batches of 1.5 kg. It was possible to fabricate UO 2 pellets of density 93-95% T.D. on a reproducible basis. At ChED, process parameters have been optimised for fabrication of AUC with suitable physical properties in batches of 1.5 kg (U), starting with nuclear pure uranyl nitrate solution. At RMD calcination parameters of AUC was optimised in batches of 500 g for obtaining free-flowing UO 2 powder, suitable for direct pelletisation and sintering. The pelletisation and sintering have been carried out at Radiometallurgy Division in batches of 1-1.5 kg. The maximum achievable density of UO 2 pellets has been in the range of 95.5-96% T.D. (author). 11 refs

  19. Management and Beneficial Reuse of Overburden Material - Linde Formerly Utilized Sites Remedial Action Program (FUSRAP) Remediation Project

    International Nuclear Information System (INIS)

    Boyle, J.D.; Schwippert, M.; Lorenz, W.D.

    2009-01-01

    This paper outlines three separate and distinct situations where the proper management of overburden material allows for the beneficial reuse of overburden material. Beneficial reuse of overburden material at the Linde Project was made possible by a simultaneous combination of physical conditions at the site in conjunction with collaborative planning and cooperation between U.S. Army Corps of Engineers - Buffalo District, New York State Department of Energy and Conservation, the Owner and Shaw Environmental and Infrastructure. Efforts by the project team focused on maintaining compliance with project plan requirements, communicating the plan to all parties, executing the plan safely and efficiently, and emphasizing fiscal responsibility to ensure maximum cost savings. (authors)

  20. Preliminary corrosion models for BWIP [Basalt Waste Isolation Project] canister materials

    International Nuclear Information System (INIS)

    Fish, R.L.; Anantatmula, R.P.

    1983-01-01

    Waste package development for the Basalt Waste Isolation Project (BWIP) requires the generation of materials degradation data under repository relevant conditions. These data are used to develop predictive models for the behavior of each component of waste package. The component models are exercised in performance analyses to optimize the waste package design. This document presents all repository relevant canister materials corrosion data that the BWIP and others have developed to date, describes the methodology used to develop preliminary corrosion models and provides the mathematical description of the models for both low carbon steel and Fe9Cr1Mo steel. Example environment/temperature history and model application calculations are presented to aid in understanding the models. The models are preliminary in nature and will be updated as additional corrosion data become available. 6 refs., 5 tabs

  1. PENGEMBANGAN LKS BERBASIS PROJECT BASED LEARNING UNTUK PEMBELAJARAN MATERI SEGITIGA DI KELAS VII

    Directory of Open Access Journals (Sweden)

    Dian Novita

    2016-06-01

    Full Text Available Penelitian ini merupakan penelitian pengembangan yang bertujuan untuk (1mengetahui karakteristik LKS berbasis Project Based Learning (PjBL yang valid dan praktis dalam pembelajaran materi segitiga di kelas VII; (2mengetahui efek potensial penggunaan LKS berbasis PjBL terhadap hasil belajar siswa dalam pembelajaran materi segitiga di kelas VII. Metode penelitian pengembangan yang digunakan adalah model  ADDIE (Analysis, Design, Development, Implementation, and Evaluation. Teknik pengumpulan data yang digunakan adalah walkthrough, tes hasil belajar dan angket. Dari tes hasil belajar, diperoleh bahwa sebesar 82,5% siswa telah mencapai kategori tuntas dan 17,5% belum tuntas dengan KKM 75. Hasil angket respon siswa menunjukkan bahwa untuk pelaksanaan pembelajaran menggunakan LKS berbasis PjBL telah mencapai kriteria kepraktisan. Kemudian untuk LKS berbasis PjBL yang telah didesain, divalidasi oleh beberapa pakar, kemudian direvisi berdasarkan saran dari para pakar tersebut. LKS yang telah direvisi tersebut dianggap telah memenuhi kriteria kevalidan dan kepraktisan sehingga dapat digunakan dalam pembelajaran materi segitiga di kelas VII. Kesimpulan dari penelitian ini adalah (1 LKS bebasis PjBL yang dikembangkan valid, tergambar dari konten (sesuai dengan kurikulum untuk materi segitiga, konstruk (sesuai dengan prinsip PjBL, dan bahasa (sesuai dengan ejaan yang disempurnakan (EYD. Kepraktisan tergambar dari proses kerja siswa dalam melaksanakan LKS dan hasil angket respon siswa terhadap pembelajaran menggunakan LKS berbasis PjBL; (2 dari hasil latihan yang dikerjakan oleh siswa, LKS berbasis PjBL memiliki efek potensial terhadap hasil belajar, yakni sebanyak 33 siswa termasuk kategori tuntas (82,5% dan 7 orang belum tuntas (17,5%, dengan KKM 75. Kata Kunci : LKS, Project Based Learning DOI: http://dx.doi.org/10.22342/jpm.10.2.3626.1-12

  2. Improvement in performance and operational experience of 14 UD Pelletron accelerator facility, BARC-TIFR

    International Nuclear Information System (INIS)

    Bhagwat, P.V.

    2002-01-01

    14 UD Pelletron accelerator facility at Mumbai has been operational since 1989. The project MEHIA (Medium Energy Heavy Ion Accelerator) started in 1982 and was formally inaugurated on 30th December 1988. Since then the accelerator has been working round the clock. Improvement in accelerator performance and operational experience are described. (author)

  3. Evaluation of dredged material proposed for ocean disposal from Westchester Creek project area, New York

    Energy Technology Data Exchange (ETDEWEB)

    Pinza, M.R.; Gardiner, W.W.; Barrows, E.S.; Borde, A.B.

    1996-11-01

    The objective of the Westchester Creek project was to evaluate proposed dredged material from this area to determine its suitability for unconfined ocean disposal at the Mud Dump Site. Westchester Creek was one of five waterways that the US Army Corps of Engineers- New York District (USACE-NYD) requested the Battelle/Marine Sciences Laboratory (MSL) to sample and evaluate for dredging and disposal in May 1995. The evaluation of proposed dredged material from the Westchester Creek project area consisted of bulk sediment chemical analyses, chemical analyses of dredging site water and elutriate, benthic acute and water-column toxicity tests, and bioaccumulation studies. Thirteen individual sediment core samples were collected from this area and analyzed for grain size, moisture content, and total organic carbon (TOC). One composite sediment sample representing the Westchester Creek area to be dredged, was analyzed for bulk density, specific gravity, metals, chlorinated pesticides, polychlorinated biphenyl (PCB) congeners, polynuclear aromatic hydrocarbons (PAHs), and 1,4-dichlorobenzene. Dredging site water and elutriate water, which is prepared from the suspended- particulate phase (SPP) of the Westchester Creek sediment composite, was analyzed for metals, pesticides, and PCBS.

  4. QUANTUM ESPRESSO: a modular and open-source software project for quantum simulations of materials.

    Science.gov (United States)

    Giannozzi, Paolo; Baroni, Stefano; Bonini, Nicola; Calandra, Matteo; Car, Roberto; Cavazzoni, Carlo; Ceresoli, Davide; Chiarotti, Guido L; Cococcioni, Matteo; Dabo, Ismaila; Dal Corso, Andrea; de Gironcoli, Stefano; Fabris, Stefano; Fratesi, Guido; Gebauer, Ralph; Gerstmann, Uwe; Gougoussis, Christos; Kokalj, Anton; Lazzeri, Michele; Martin-Samos, Layla; Marzari, Nicola; Mauri, Francesco; Mazzarello, Riccardo; Paolini, Stefano; Pasquarello, Alfredo; Paulatto, Lorenzo; Sbraccia, Carlo; Scandolo, Sandro; Sclauzero, Gabriele; Seitsonen, Ari P; Smogunov, Alexander; Umari, Paolo; Wentzcovitch, Renata M

    2009-09-30

    QUANTUM ESPRESSO is an integrated suite of computer codes for electronic-structure calculations and materials modeling, based on density-functional theory, plane waves, and pseudopotentials (norm-conserving, ultrasoft, and projector-augmented wave). The acronym ESPRESSO stands for opEn Source Package for Research in Electronic Structure, Simulation, and Optimization. It is freely available to researchers around the world under the terms of the GNU General Public License. QUANTUM ESPRESSO builds upon newly-restructured electronic-structure codes that have been developed and tested by some of the original authors of novel electronic-structure algorithms and applied in the last twenty years by some of the leading materials modeling groups worldwide. Innovation and efficiency are still its main focus, with special attention paid to massively parallel architectures, and a great effort being devoted to user friendliness. QUANTUM ESPRESSO is evolving towards a distribution of independent and interoperable codes in the spirit of an open-source project, where researchers active in the field of electronic-structure calculations are encouraged to participate in the project by contributing their own codes or by implementing their own ideas into existing codes.

  5. Cementitious materials for radioactive waste management within IAEA coordinated research project - 59021

    International Nuclear Information System (INIS)

    Drace, Zoran; Ojovan, Michael I.

    2012-01-01

    The IAEA Coordinated Research Project (CRP) on cementitious materials for radioactive waste management was launched in 2007 [1, 2]. The objective of CRP was to investigate the behaviour and performance of cementitious materials used in radioactive waste management system with various purposes and included waste packages, waste-forms and backfills as well as investigation of interactions and interdependencies of these individual elements during long term storage and disposal. The specific research topics considered were: (i) cementitious materials for radioactive waste packaging: including radioactive waste immobilization into a solid waste form, (ii) waste backfilling and containers; (iii) emerging and alternative cementitious systems; (iv) physical-chemical processes occurring during the hydration and ageing of cement matrices and their influence on the cement matrix quality; (v) methods of production of cementitious materials for: immobilization into wasteform, backfills and containers; (vi) conditions envisaged in the disposal environment for packages (physical and chemical conditions, temperature variations, groundwater, radiation fields); (vii) testing and non-destructive monitoring techniques for quality assurance of cementitious materials; (viii) waste acceptance criteria for waste packages, waste forms and backfills; transport, long term storage and disposal requirements;and finally (ix) modelling or simulation of long term behaviours of cementations materials used for packaging, waste immobilization and backfilling, especially in the post-closure phase. The CRP has gathered overall 26 research organizations from 22 Member States aiming to share their research and practices on the use of cementitious materials [2]. The main research outcomes of the CRP were summarized in a summary report currently under preparation to be published by IAEA. The generic topical sections covered by report are: a) conventional cementitious systems; b) novel cementitious

  6. Analysis of Construction Material Procurement Retardation on Sepaku-Petung Rigid Pavement Improvement Project in East Kalimantan Province

    Directory of Open Access Journals (Sweden)

    Rama Nugraha

    2017-11-01

    Full Text Available his study aims to know the factors influencing the retardation in procurement of construction materials on Sepaku-Petung pavement improvement project in East Kalimantan Province;to know the most dominant factor affecting the retardation in procurement of construction materials on Sepaku-Petung pavement improvement project in East Kalimantan Province; to determine what strategies that minimize the waiting time of materials in the improvement of Sepaku-Petung pavement project in East Kalimantan Province. This study used quantitative research method. The data was collected through interview, questionnaire distribution, and discussion forum. Based on the results of research and data analysis conducted, it can be concluded thatsuppliers, contractors, field conditions, and unpredictable conditionswere affecting the retardation in procurement of materials in the pavement improvement project in East Kalimantan. Field condition was the most dominant factors in the realization of Sepaku-Petung pavement improvement project in East Kalimantan province. Type B (Retarding Admixtures could be added to retard the time-binding of the concrete (setting time, therefore minimizing material procurement waiting time. The contractor should also build his own supplier close to the project site to reduce the distance between the concrete supplier location and the project site.

  7. Electricity from photovoltaic solar cells: Flat-Plate Solar Array Project final Report. Volume II: Silicon material

    OpenAIRE

    Lutwack, R.

    1986-01-01

    The Flat-Plate Solar Array (FSA) Project, funded by the U.S. Government and managed by the Jet Propulsion Laboratory, was formed in 1975 to develop the module/array technology needed to attain widespread terrestrial use of photovoltaics by 1985. To accomplish this, the FSA Project established and managed an Industry, University, and Federal Government Team to perform the needed research and development. The goal of the Silicon Material Task, a part of the FSA Project, was to develop and ...

  8. Innovative materials for GEN IV systems and transmutation facilities (cross-cutting research project GETMAT)

    International Nuclear Information System (INIS)

    Fazio, Concetta; Rieth, Michael; Gomez Briceno, Dolores; Gessi, Alessandro; Henry, Jean; Malerba, Lorenzo

    2010-01-01

    The objectives of the 'Generation IV and Transmutation Materials' (GETMAT) project is to contribute to the development, qualification and ranking of different types of ODS steels and to qualify Ferritic/Martensitic steels in a wide irradiation condition range. The experimental approach is complemented by the development of physical models with the aim to understand and improve the predictability of the materials performance. The GETMAT consortium is composed of fourteen Research centres, nine Universities and one Utility, from eleven European countries. The R and D tasks address (i) the materials availability, fabricability, weldability and their fundamental mechanical properties, (ii) their compatibility with aggressive coolants and development of corrosion protection methods; (iii) their performance under neutron irradiation, and (iv) starting from model alloys relevant for the two classes of alloys, the development and validation of physical models. The exploitation of results to potential end-users will occur through the 'GETMAT User Group', where exchange of information with the nuclear and steel industries, international (outside Europe) Research Organisations and engineers involved in the design of the new reactors, will occur. The exploitation of results to potential end-users will occur through the G ETMAT User Group , where exchange of information with the nuclear and steel industries, international (outside Europe) Research Organisations and engineers involved in the design of the new reactors, will occur

  9. Micro-controller based fiber optic data telemetry system for the ion source of low energy accelerator facility at BARC

    International Nuclear Information System (INIS)

    Padmakumar, Sapna; Ware, Shailaja V.; Subrahmanyam, N.B.V.; Bhatt, J.P.; Singh, S.K.; Gupta, S.K.; Singh, P.; Choudhury, R.K.

    2009-01-01

    The Low Energy Accelerator Facility (LEAF) is a 50 keV, high intensity, negative ion accelerator facility that has been set up indigenously at Nuclear Physics Division, BARC. This facility is capable of delivering a wide range of negative ion beams of both light and heavy ions across the periodic table using a SNICS II (Source of Negative Ion by Caesium Sputtering) source. A micro-controller based control and monitoring system has been developed exclusively for the ion source parameters of LEAF. The data control and monitoring system mainly targets acquiring the data from the field in the terms of parameters such as voltages and currents. There are processes which need to be monitored continuously in order to keep certain parameters under check. The microcontroller based fiber optic data telemetry system allows us to perform the aforesaid task. The voltages can be controlled and monitored by providing the inputs and receiving the feedback through a user friendly graphic user interface. With this system one can control the status as well as analog value of the high voltage power supplies like extractor, cathode, filament, focus line heater and oven. This system consists of Fiber optic transceiver, which is connected on serial port (RS 232C) of microcontroller as well as RS232 port of PC. The whole control system is reliable even in noisy environments including RF and worse EMI conditions. This compact modular design is implemented using low cost devices and allows easy and fast maintainability. In the paper, the details of the system are presented. (author)

  10. Assessment of Ultimate Load Capacity for Pre-Stressed Concrete Containment Vessel Model of PWR Design With BARC Code ULCA

    International Nuclear Information System (INIS)

    Basha, S.M.; Singh, R.K.; Patnaik, R.; Ramanujam, S.; Kushwaha, H.S.; Venkat Raj, V.

    2002-01-01

    Ultimate load capacity assessment of nuclear containments has been a thrust research area for Indian Pressurised Heavy Water Reactor (PHWR) power programme. For containment safety assessment of Indian PHWRs a finite element code ULCA was developed at BARC, Trombay. This code has been extensively benchmarked with experimental results. The present paper highlights the analysis results for Prestressed Concrete Containment Vessel (PCCV) tested at Sandia National Labs, USA in a Round Robin analysis activity co-sponsored by Nuclear Power Engineering Corporation (NUPEC), Japan and the U.S Nuclear Regulatory Commission (NRC). Three levels of failure pressure predictions namely the upper bound, the most probable and the lower bound (all with 90% confidence) were made as per the requirements of the round robin analysis activity. The most likely failure pressure is predicted to be in the range of 2.95 Pd to 3.15 Pd (Pd= design pressure of 0.39 MPa for the PCCV model) depending on the type of liners used in the construction of the PCCV model. The lower bound value of the ultimate pressure of 2.80 Pd and the upper bound of the ultimate pressure of 3.45 Pd are also predicted from the analysis. These limiting values depend on the assumptions of the analysis for simulating the concrete-tendon interaction and the strain hardening characteristics of the steel members. The experimental test has been recently concluded at Sandia Laboratory and the peak pressure reached during the test is 3.3 Pd that is enveloped by our upper bound prediction of 3.45 Pd and is close to the predicted most likely pressure of 3.15 Pd. (authors)

  11. Materials and process engineering projects for the Sandia National Laboratories/Newly Independent States Industrial Partnering Program. Volume 2

    International Nuclear Information System (INIS)

    Zanner, F.J.; Moffatt, W.C.

    1995-07-01

    In July, 1994, a team of materials specialists from Sandia and US. Industry traveled to Russia and the Ukraine to select and fund projects in materials and process technology in support of the Newly Independent States/Industrial Partnering Program (NIS/IPP). All of the projects are collaborations with scientists and Engineers at NIS Institutes. Each project is scheduled to last one year, and the deliverables are formatted to supply US. Industry with information which will enable rational decisions to be made regarding the commercial value of these technologies. This work is an unedited interim compilation of the deliverables received to date

  12. Materials and process engineering projects for the Sandia National Laboratories/Newly Independent States Industrial Partnering Program. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Zanner, F.J.; Moffatt, W.C.

    1995-07-01

    In July, 1994, a team of materials specialists from Sandia and U S Industry traveled to Russia and the Ukraine to select and fund projects in materials and process technology in support of the Newly Independent States/Industrial Partnering Program (NIS/IPP). All of the projects are collaborations with scientists and Engineers at NIS Institutes. Each project is scheduled to last one year, and the deliverables are formatted to supply US Industry with information which will enable rational decisions to be made regarding the commercial value of these technologies. This work is an unedited interim compilation of the deliverables received to date.

  13. Materials and process engineering projects for the Sandia National Laboratories/Newly Independent States Industrial Partnering Program. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Zanner, F.J.; Moffatt, W.C.

    1995-07-01

    In July, 1994, a team of materials specialists from Sandia and US. Industry traveled to Russia and the Ukraine to select and fund projects in materials and process technology in support of the Newly Independent States/Industrial Partnering Program (NIS/IPP). All of the projects are collaborations with scientists and Engineers at NIS Institutes. Each project is scheduled to last one year, and the deliverables are formatted to supply US. Industry with information which will enable rational decisions to be made regarding the commercial value of these technologies. This work is an unedited interim compilation of the deliverables received to date.

  14. The NILE Project - Advances in the Conversion of Lignocellulosic Materials into Ethanol

    International Nuclear Information System (INIS)

    Monot, F.; Margeot, A.; Hahn-Haegerdal, B.; Lindstedt, J.; Slade, R.

    2013-01-01

    NILE ('New Improvements for Lignocellulosic Ethanol') was an integrated European project (2005-2010) devoted to the conversion of lignocellulosic raw materials to ethanol. The main objectives were to design novel enzymes suitable for the hydrolysis of cellulose to glucose and new yeast strains able to efficiently converting all the sugars present in lignocellulose into ethanol. The project also included testing these new developments in an integrated pilot plant and evaluating the environmental and socio-economic impacts of implementing lignocellulosic ethanol on a large scale. Two model raw materials - spruce and wheat straw - both preconditioned with similar pretreatments, were used. Several approaches were explored to improve the saccharification of these pretreated raw materials such as searching for new efficient enzymes and enzyme engineering. Various genetic engineering methods were applied to obtain stable xylose- and arabinose-fermenting Saccharomyces cerevisiae strains that tolerate the toxic compounds present in lignocellulosic hydrolysates. The pilot plant was able to treat 2 tons of dry matter per day, and hydrolysis and fermentation could be run successively or simultaneously. A global model integrating the supply chain was used to assess the performance of lignocellulosic ethanol from an economical and environmental perspective. It was found that directed evolution of a specific enzyme of the cellulolytic cocktail produced by the industrial fungus, Trichoderma reesei, and modification of the composition of this cocktail led to improvements of the enzymatic hydrolysis of pretreated raw material. These results, however, were difficult to reproduce at a large scale. A substantial increase in the ethanol conversion yield and in specific ethanol productivity was obtained through a combination of metabolic engineering of yeast strains and fermentation process development. Pilot trials confirmed the good behaviour of the yeast strains in industrial

  15. Control of tracers, fluids, and materials for the Yucca Mountain Site Characterization Project

    International Nuclear Information System (INIS)

    Kalia, H.N.

    1993-01-01

    This paper describes use and control of tracers, fluids, and materials (TFM) at the Yucca Mountain Site Characterization Project, Management of TFM is necessary to ensure that site characterization activity does not introduce TFM that may have impact on Yucca Mountain's ability to isolate high-level radioactive waste from the accessible environment. All participants must identify TFM used for testing and construction and have the TFM evaluated to ascertain any impact on waste isolation capabilities of the site or on adjacent tests. Two data bases are created to track TFM: a working data base managed by Los Alamos National Lab. and a permanent data base managed by EG ampersand G, which will contain information on actual TFM used

  16. Project of the JAERI superconducting AVF cyclotron for applications in biotechnology and materials science

    International Nuclear Information System (INIS)

    Miyawaki, Nobumasa; Kurashima, Satoshi; Okumura, Susumu; Chiba, Atsuya; Agematsu, Takashi; Kamiya, Tomihiro; Kaneko, Hirohisa; Nara, Takayuki; Saito, Yuichi; Ishii, Yasuyuki; Sakai, Takuro; Mizuhashi, Kiyoshi; Fukuda, Mitsuhiro; Yokota, Watalu; Arakawa, Kazuo

    2005-01-01

    A project for expanding TIARA (Takasaki Ion accelerators for Advanced Radiation Application) facilities of JAERI has been proposed to broaden application region of biotechnology and materials science. As a result of the investigation of TIARA facility user's request, energy increase up to more than 100 MeV/n for heavy ions and up to 300 MeV for proton are strongly required. The magnet of a superconducting AVF cyclotron with a K number of 900 has been designed to cope with acceleration of both 150 MeV/n heavy ions and 300 MeV protons. The lower limit of energies has been investigated to overlap the energy region covered by the JAERI AVF cyclotron, required to increase beam time for present users. We have designed a beam transport system to satisfy various requirements of the applications. (author)

  17. Evaluation of copper, aluminum bronze, and copper-nickel container material for the Yucca mountain project

    International Nuclear Information System (INIS)

    Kass, J.

    1990-01-01

    Copper, 70 percent aluminum bronze, and 70/30 copper-nickel were evaluated as potential waste-packaging materials as part of the Yucca Mountain Project. The proposed waste repository site is under a desert mountain in southern Nevada. The expected temperatures at the container surface are higher than at other sites, about 250C at the beginning of the containment period; they could fall below the boiling point of water during this period, but will be exposed to very little water, probably less than 5 l/a. Initial gamma flux will be 10 4 rad/h, and no significant hydrostatic or lithostatic pressure is expected. Packages will contain PWR or BWR fuel, or processed-glass waste. Three copper alloys are being considered for containers: oxygen-free copper (CDA 102); 7 percent aluminum bronze (CDA 613); and 70/30 copper-nickel (CDA 715). Phase separation due to prolonged thermal exposure could be a problem for the two alloys, causing embrittlement. The reduction of internal oxides present in pure copper by hydrogen could cause mechanical degradation. Corrosion and oxidation rates measured for the three materials in well water with and without gamma irradiation at flux rates about ten times higher than those expected were all quite small. The corrosion/oxidation rates for CDA715 show a marked increase under irradiation, but are still acceptable. In the presence of ammonia and other nitrogen-bearing species stress corrosion cracking (SCC) is a concern. Welded U-bend specimens of all three materials have been tested for up to 10000 h in highly irradiated environments, showing no SCC. There was some alloy segregation in the Al bronze specimens. The investigators believe that corrosion and mechanical properties will not present problems for these materials at this site. Further work is needed in the areas of weld inspection, welding techniques, embrittlement of weld metal, the effects of dropping the containers during emplacement, and stress corrosion cracking. Other materials

  18. Engineering high power induction plasma unit at BARC for mass synthesis of refractory nano-ceramics

    International Nuclear Information System (INIS)

    Ghorui, S.; Sahasrabudhe, S.N.; Dhamale, G.; Das, A.K.

    2013-01-01

    Atmospheric pressure RF thermal plasma sources are gaining increasing importance for production of high purity novel nano-materials in different high-end technological applications. Inherent electrode-less features of the discharge together with the large volume and high energy density of the produced plasma ensures contamination free process environment and mass production ability. Reported herewith is the development of an indigenous induction plasma system for mass synthesis of nanopowders of refractory ceramic materials. The system has been tested for continuous synthesis of Al 2 O 3 nano-powder at a rate of more than 600 gm per hour and checked for its viability for bulk production of nano-particles of other refractory ceramics like Yttrium oxide and Neodymium Oxide. From collected evidences, the process of formation of the nano-particles is identified as the evaporation and subsequent homogeneous nucleation. Major features observed for alumina are complete conversion into highly spherical nano-sized particles, small particle sizes, very narrow size distribution, highly crystallite nature and mixed phases depending on the zone of collection. For alumina, the particles are found to exhibit a uni-modal distribution with peak near 15 nm

  19. 15 year's summary report on blanket technology and materials of mixed fuel reactor research sponsored by national '863' projects

    International Nuclear Information System (INIS)

    Xu Zengyu; Chen Jiming; Liu Xiang

    2001-01-01

    15 year's achievements of Southwestern Institute of Physics, China, in fusion technology and materials research sponsored by National '863' Engineering Projects are summarized. Many scientific and technical achievements are obtained in the researches on tritium production and recovery, doped carbon basic materials, V-alloys, 316L SS irradiation performance, B 4 C and TiC coatings, etc. Some facilities were built and some were improved for materials research. 108 references are annexed

  20. Hazardous materials in aquatic environments of the Mississippi River Basin. Quarterly project status report, October 1, 1993--December 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    This quarterly project status report discusses research projects being conducted on hazardous materials in aquatic environments of the Mississippi River basin. We continued to seek improvement in our methods of communication and interactions to support the inter-disciplinary, inter-university collaborators within this program. In addition to the defined collaborative research teams, there is increasing interaction among investigators across projects. Planning for the second year of the project has included the development of our internal request for proposals, and refining the review process for selection of proposals for funding.

  1. Neutron measurements at BRIT/BARC medical cyclotron facility of RMC, Parel

    International Nuclear Information System (INIS)

    Sathian, Deepa; Sathian, V.; Phandnis, U.V.; Soni, P.S.; Mohite, D.Y.

    2005-01-01

    Neutron leakage and its long distance propagation in the atmosphere from the intense neutron facilities such as high energy accelerators like Cyclotron are very important for the shielding design of the facilities and resulting dose reduction to nearby population, because of strong penetrability of high energy neutrons. The neutron interaction cross sections are highly energy dependent, so different methods are adopted for measuring different energy neutrons. The method also depends on the amount of neutron fluence rate expected at the location. When the fluence rate is very high, the foil activation is the best method for the measurement of neutron fluence rate. In foil activation technique an inactive material is activated by neutrons and the activity is measured and correlated to the neutron fluence rate. In this paper, neutron fluence rate measurement using different activation foils at medical cyclotron room of Radiation Medicine Centre (RMC) is discussed. (author)

  2. Containment aerosol behaviour simulation studies in the BARC nuclear aerosol test facility

    International Nuclear Information System (INIS)

    Mayya, Y.S.; Sapra, B.K.; Khan, Arshad; Sunny, Faby; Nair, R.N.; Raghunath, Radha; Tripathi, R.M.; Markandeya, S.G.; Puranik, V.D.; Ghosh, A.K.; Kushwaha, H.S.; Shreekumar, K.P.; Padmanabhan, P.V.A.; Murthy, P.S.S.; Venlataramani, N.

    2005-02-01

    A Nuclear Aerosol Test Facility (NATF) has been built and commissioned at Bhabha Atomic Research Centre to carry out simulation studies on the behaviour of aerosols released into the reactor containment under accident conditions. This report also discusses some new experimental techniques for estimation of density of metallic aggregates. The experimental studies have shown that the dynamic densities of aerosol aggregates are far lower than their material densities as expected by the well-known fractal theory of aggregates. In the context of codes, this has significant bearing in providing a mechanistic basis for the input density parameter used in estimating the aerosol evolution characteristics. The data generated under the quiescent and turbulent conditions and the information on aggregate densities are now being subjected to the validation of the aerosol behaviour codes. (author)

  3. Design and development of collimator for 9 MeV BARC-ECIL linac

    International Nuclear Information System (INIS)

    Ghodke, S.R.; Barnwal, Rajesh; Mahendra Kumar; Nayak, Susanta; Barje, S.R.; Sinha, A.K.; Mittal, K.C.; Chakravarthy, D.P.; Gantayet, L.M.; Baiswar, Rishabh

    2011-01-01

    High Energy electron beam technology is useful for both fundamental and applied research in the sciences, and also in many technical and industrial fields. It has been estimated that there are approximately 26,000 accelerators worldwide. The collimator is designed to function with a 9 MeV LINAC Test Facility (LTF) at ECIL, Hyderabad. The accelerated electron beam hits a tantalum target and X-Rays generated though the target are fed to the collimator. Thereafter, collimated high energy X-Rays will be used for cargo scanning. The X-ray collimator will complement the existing system at LTF, ECIL to get collimated fan beam. A collaborative effort has been made to identify novel and advanced materials to achieve low coefficient of friction for various lateral and angular movements of collimator plates weighing nearly 5 tons. Complex numerical calculations simulating extreme conditions and experimental tests have been undertaken using Ansys. In parallel, an innovative modular design concept of the assembly has been developed to allow fitting in alternative materials, minimizing the load induced deformations, withstanding accidents and accepting desired radiation doses. The collimator plates are made up of mild steel blocks of IS 2062A grade ensuring high geometrical stability. The assembly structures for the collimator are made up of high stiffness I-beams ISMB 150. Each plate has been machined with high precision Electric Discharge Machining (EDM) and Surface Grinding processes. The plates are also hard chrome plated to provide corrosion resistance and increase surface hardness. A full scale collimator prototype has been manufactured to validate each feature of the new design at the LTF, ECIL, Hyderabad. (author)

  4. 50 years of uranium metal production in Uranium Metal Plant, BARC, Trombay

    International Nuclear Information System (INIS)

    2009-01-01

    The Atomic Energy Programme in India, from the very beginning, has laid emphasis on indigenous capabilities in all aspects of nuclear technology. This meant keeping pace with developments abroad and recognizing the potentials of indigenous technologies. With the development of nuclear programme in India, the importance of uranium was growing at a rapid pace. The production of reactor grade uranium in India started in January 1959 when the first ingot of nuclear pure uranium was discharged using CTR process at Trombay. The decision to set up a uranium refinery to purify the crude uranium fluoride, obtained as a by-product of the DAE's Thorium Plant at Trombay, and to produce nuclear grade pure uranium metal was taken at the end of 1956. The task was assigned to the 'Project Fire Wood Group'. The main objective of the plant was to produce pure uranium metal for use in the Canada India Reactor and Zerlina. Besides this, it was to function as a pilot plant to collect operational data and to train personnel for larger plants to be set up in future. The plant designing and erection work was entrusted to Messrs. Indian Rare Earths Ltd.

  5. Scarab/Saffron Development Project Case study: Material Selection Criteria for the Monoethylene Glycol Recovery Package

    International Nuclear Information System (INIS)

    Moussa, A.M.; Habib, S.; Shinaishin, A.

    2004-01-01

    MEG Recovery Unit for Scarab/Saffron development project is the first application in gas production. The Mono Ethylene Glycol Recovery Unit (MEG) recovers MEG from Water/MEG stream and removes salts and other contaminants. MEG Recovery Unit Equipment Design Criteria were designed for two parallel trains A and B, each train is capable to treat 500 bbl MEG, 1500 bbl water and 9 ton salt. The MEG unit is a combination of two unit operations; MEG Recovery unit is normally applicable in the oil and gas industries that is applying distillation technique, while the new technology is salt treatment and handling. The MEG Unit material selection is made to be suitable for the entire design life which is 25 years, the materials for MEG Recovery Unit have been selected among the available corrosion resistance alloys, where requested by the service and ambient conditions. Therefore all. the parts of the MEG unit that are in saline service are in either (2205 duplex, AISI 316L) and in Inconel alloy 625 related to operating temperature. This case study focused at Inconel alloy 625, which is selected for salt service and their operation problem occurred during the construction and operating conditions

  6. Treatability of flare pit material : bio-reactor project 1994-1995

    International Nuclear Information System (INIS)

    Danielson, R.M.

    1996-01-01

    The feasibility of bioremediation as a potential treatment in upstream salt and hydrocarbon contaminated soils and solid wastes was studied. Both laboratory and pilot field scale operations were conducted to study the usefulness of microbially treating heavily contaminated materials and to determine if bioremediation could answer both environmental and economic concerns. This report for 1994/1995 discussed the testing of flare pit, the third of three wastes studied in this project, the other two being crude oil contaminated topsoil and diesel invert mud residue. The material tested contained 8.5 per cent extractable hydrocarbons and was highly saline. Gas chromatographic analysis of the extractable hydrocarbons indicated that a substantial portion should be subject to biological degradation. Hydrocarbon mineralization to CO 2 was measured for periods up to 4.5 months and rates of CO 2 evolution and total CO 2 evolved were calculated. Solvent extractable hydrocarbon contents were also measured but CO 2 respiration appeared to be the most reliable measurement of treatment progress. Mineralization rates were slow after 4.5 months, indicating that large quantities of contaminating hydrocarbons would persist for years, if not decades. The major constraint to degradation of hydrocarbons appeared to be bioavailability. The conclusion was that little could be done to increase rates after the first few months of treatment. 24 refs., 16 tabs., 24 figs

  7. SPADA: a project to study the effectiveness of shielding materials in space

    International Nuclear Information System (INIS)

    Pugliese, M.; Casolino, M.; Cerciello, V.

    2008-01-01

    The SPADA (SPAce Dosimetry for Astronauts) project is a part of an extensive teamwork that aims to optimize shielding solutions against space radiation. Shielding is indeed all irreplaceable tool to reduce, exposure of crews of future Moon and Mars missions. We concentrated our studies on two flexible materials, Kevlar (R) and Nextel (R), because of their ability to protect space infrastructure from micro meteoroids measured radiation hardness of these shielding materials and compared to polyethylene, generally acknowledged as the most effective space radiation shield with practical applications in spacecraft. Both flight test (on the International Space Station and on the Russian FOTON M3 rocket), with passive dosimeters and accelerator-based experiments have been performed. Accelerator tests using high-energy Fe ions have demonstrated that Kevlar is almost as effective as polyethylene in shielding heavy ions, while Nextel is a poor shield against, high-charge and -energy particles. Preliminary results from spaceflight, however, show that for the radiation environment ill low-Earth orbit. dominated by trapped protons, thin shields of Kevlar and Nextel provide limited reduction.

  8. The function of packing materials in a high-level nuclear waste repository and some candidate materials: Salt Repository Project

    International Nuclear Information System (INIS)

    Bunnell, L.R.; Shade, J.W.

    1987-03-01

    Packing materials should be included in waste package design for a high-level nuclear waste repository in salt. A packing material barrier would increase confidence in the waste package by alleviating possible shortcomings in the present design and prolonging confinement capabilities. Packing materials have been studied for uses in other geologic repositories; appropriately chosen, they would enhance the confinement capabilities of salt repository waste packages in several ways. Benefits of packing materials include retarding or chemically modifying brines to reduce corrosion of the waste package, providing good thermal conductivity between the waste package and host rock, retarding or absorbing radionuclides, and reducing the massiveness of the waste package. These benefits are available at low percentage of total repository cost, if the packing material is properly chosen and used. Several candidate materials are being considered, including oxides, hydroxides, silicates, cement-based mixtures, and clay mixtures. 18 refs

  9. Generation of ozone and safety aspects in an accelerator facility of BARC

    International Nuclear Information System (INIS)

    Dubey, Praveen; Sawatkar, Aparna R.; Sathe, Arun P.; Soundararajan, S.; Sarma, K.S.S.

    2009-01-01

    Industrial electron beam accelerators up to 10 MeV are commonly employed for different applications. During normal operation of an accelerator, the principal hazard is the high radiation level produced. Experiments and applications in which the electron beam is used to irradiate materials outside the accelerator vacuum system are associated with problems such as radiation damage and production of considerable quantities of ozone. The possible generation of ozone during the operation of an electron beam accelerator is of special interest due to reactivity, corrosivity and the toxic characteristics of ozone. Industrial hygiene surveys were conducted to estimate the airborne concentration of ozone during operations of the electron beam accelerator (Type: ILU-6; 2 MeV; 20 KW) at varied operating parameters. The ozone concentration in the accelerator room was measured at different powers of the accelerator and the ozone decay pattern was also observed after beam shut down. Ozone in the accelerator room was measured by different methods such as colorimetry using neutral buffered potassium iodide, chemiluminescence method using ethylene and by using electrochemical sensor. An air velocity meter was used to measure the linear air velocity across the exhaust grills and the number of air changes available in the accelerator room was calculated. Necessary control measures were suggested to keep the occupational exposure of the personnel to ozone concentrations well within the Threshold Limit Values. (author)

  10. Coordinated research project on radiation sterilization and decontamination of pharmaceuticals and pharmaceutical raw materials. CRP report

    International Nuclear Information System (INIS)

    2005-01-01

    Radiation processing is a very convenient tool for imparting desirable effects in materials and it has been an area of enormous interest in the last few decades. Radiation processing of synthetic and natural polymers for improving their characteristics is largely used in laboratory and industrial scale. Radiation sterilization is a well developed and established technology for many products. It is especially useful for the treatment of pharmaceuticals due to flexibility of radiation processing to be carried out at any desired temperature, sterilizability of mixed products in kits, offering simultaneous sterilization and modification of polymer based formulations. The success of radiation technology for processing of synthetic and natural polymers and treatment of pharmaceuticals has been based, to a large extent, on empirical knowledge. But now, the applications of natural polymers are being sought in knowledge-demanding areas such as pharmacy and biotechnology. Reliable analytical methods are being developed for controlling of degradation effects of radiation on polymers. Procedures and chemical formulations are being investigated enhancing or preventing degradation effects depending on the desired application of the process. The Coordinated Research Project (CRP) on the use of radiation processing for sterilization or decontamination of pharmaceuticals and pharmaceutical raw materials has been completed in 2002. The overall objective of the CRP was to coordinate the research and development programmes carried out in different countries in use of radiation processing for sterilization or decontamination of pharmaceuticals and pharmaceutic raw materials. It has been concluded that in addition to well known advantages of radiation sterilization being a well developed and established technology requiring the control of only one parameter, dose, to achieve sterilization; it is especially useful for the treatment of pharmaceuticals due to flexibility of radiation

  11. Coordinated research project on radiation sterilization and decontamination of pharmaceuticals and pharmaceutical raw materials. CRP report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    Radiation processing is a very convenient tool for imparting desirable effects in materials and it has been an area of enormous interest in the last few decades. Radiation processing of synthetic and natural polymers for improving their characteristics is largely used in laboratory and industrial scale. Radiation sterilization is a well developed and established technology for many products. It is especially useful for the treatment of pharmaceuticals due to flexibility of radiation processing to be carried out at any desired temperature, sterilizability of mixed products in kits, offering simultaneous sterilization and modification of polymer based formulations. The success of radiation technology for processing of synthetic and natural polymers and treatment of pharmaceuticals has been based, to a large extent, on empirical knowledge. But now, the applications of natural polymers are being sought in knowledge-demanding areas such as pharmacy and biotechnology. Reliable analytical methods are being developed for controlling of degradation effects of radiation on polymers. Procedures and chemical formulations are being investigated enhancing or preventing degradation effects depending on the desired application of the process. The Coordinated Research Project (CRP) on the use of radiation processing for sterilization or decontamination of pharmaceuticals and pharmaceutical raw materials has been completed in 2002. The overall objective of the CRP was to coordinate the research and development programmes carried out in different countries in use of radiation processing for sterilization or decontamination of pharmaceuticals and pharmaceutic raw materials. It has been concluded that in addition to well known advantages of radiation sterilization being a well developed and established technology requiring the control of only one parameter, dose, to achieve sterilization; it is especially useful for the treatment of pharmaceuticals due to flexibility of radiation

  12. LOT Project long term test of buffer material at the Aespoe HRL

    International Nuclear Information System (INIS)

    Karnland, O.; Olsson, S.; Dueck, A.; Birgersson, M.; Nilsson, U.; Hernan-Haakansson, T.; Pedersen, K.; Eriksson, S.; Eriksen, T.; Eriksson, S.; Rosborg, B.; Muurinen, A.; Rousset, D.; Mosser-Ruck, R.; Cathelineau, M.; Villieras, F.; Pelletier, M.; Kaufold, S.; Dohrmann, R.; Fernandez, R.; Maeder, U.; Koroleva, M.

    2010-01-01

    Document available in extended abstract form only. Bentonite clay has been proposed as buffer material in several concepts for HLW repositories. The decaying spent fuel in the HLW canisters will increase temperature of the bentonite buffer. A number of laboratory test series, made by different research groups, have resulted in various bentonite alteration models. According to these models no significant alteration of the buffer is expected to take place at the prevailing physico-chemical conditions in the proposed Swedish KBS-3 repository, neither during, nor after water saturation. The ongoing LOT test series is focused on quantifying the mineralogical alteration in the buffer in a repository like environment at the Aespoe HRL. Further, buffer related processes concerning bacterial survival/activity, cation transport, and copper corrosion are studied. In total, the LOT test series includes seven test parcels, of which three are exposed to standard KBS-3 conditions and four test parcels are exposed to adverse conditions. Each test parcel contains a central Cu-tube surrounded by bentonite cylinder rings with a diameter of 30 cm, additional test material (Cu coupons, 60 Co tracers, bacteria etc) and instruments. Electrical heaters were place within the copper tube in order to simulate effect of decaying power from the spent fuel. The entire test parcels were released from the rock after the field exposure by overlapping boring and the bentonite material was analyzed with respect to: - physical properties (water content, density, swelling pressure, hydraulic conductivity, rheology); - mineralogical alteration in the bentonite; - distribution of added substances (e.g diffusional transport of 60 Co); - copper corrosion; - bacterial survival/activity. Two one year tests were started in 1996 and terminated in 1998. The results from tests and analyses are presented in SKB TR-00-22. The remaining four test parcels were installed during the fall 1999 plus one additional one

  13. Overview of Japan Proton Accelerator Research Complex (J-PARC) project and Materials and Life Science Experimental Facility (MLF)

    International Nuclear Information System (INIS)

    Ikeda, Yujiro

    2008-01-01

    The J-PARC project has been conducted jointly by JAERI and KEK since 2001. This paper reports an overview and current status of the project. The high intensity proton accelerator consists of a 400 MeV Linac, a 3 GeV synchrotron and 50 GeV synchrotron to deliver MW level pulsed proton beam to experimental facilities. The MW proton power will provide an advanced scientific experimental research complex aiming at making breakthroughs in materials and life science with neutron and muon, nuclear and elementary physics, etc. Regarding the project being close to its completion in 2008, this paper describes the overview of J-PARC project with emphasis of the Materials and Life Science Experimental Facility, in which the MW pulsed neutron and muon sources, are placed to provide high quality neutron and muon beams to the world wide users. (author)

  14. Program Evaluation - Automotive Lightweighting Materials Program Research and Development Projects Assessment of Benefits - Case Studies No. 2

    Energy Technology Data Exchange (ETDEWEB)

    Das, S.

    2003-01-23

    This report is the second of a series of studies to evaluate research and development (R&D) projects funded by the Automotive Lightweighting Materials (ALM) Program of the Office of Advanced Automotive Technologies (OAAT) of the U.S. Department of Energy (DOE). The objectives of the program evaluation are to assess short-run outputs and long-run outcomes that may be attributable to the ALM R&D projects. The ALM program focuses on the development and validation of advanced technologies that significantly reduce automotive vehicle body and chassis weight without compromising other attributes such as safety, performance, recyclability, and cost. Funded projects range from fundamental materials science research to applied research in production environments. Collaborators on these projects include national laboratories, universities, and private sector firms, such as leading automobile manufacturers and their suppliers. Three ALM R&D projects were chosen for this evaluation: Design and Product Optimization for Cast Light Metals, Durability of Lightweight Composite Structures, and Rapid Tooling for Functional Prototyping of Metal Mold Processes. These projects were chosen because they have already been completed. The first project resulted in development of a comprehensive cast light metal property database, an automotive application design guide, computerized predictive models, process monitoring sensors, and quality assurance methods. The second project, the durability of lightweight composite structures, produced durability-based design criteria documents, predictive models for creep deformation, and minimum test requirements and suggested test methods for establishing durability properties and characteristics of random glass-fiber composites for automotive structural composites. The durability project supported Focal Project II, a validation activity that demonstrates ALM program goals and reduces the lead time for bringing new technology into the marketplace. Focal

  15. BARC golden jubilee and DAE-BRNS life sciences symposium 2006 on trends in research and technologies in agriculture and food sciences: abstracts

    International Nuclear Information System (INIS)

    2006-01-01

    Better methods of agricultural production, availability of hybrid and mutant varieties of crop plants, irrigation, fertilizers and pesticides have all helped boost up agricultural production, and famines and droughts remain restricted to a few pockets in the world. Innovative approach to step up agricultural production, especially of food crops symbolize synergy and synthesis of conventional and mutation breeding aided by modern biotechnological tools like DNA markers and gene manipulation in tune with the policy of environmental and soil conservation. It has increased the production of oil seeds in India during the last decade with a shift from groundnut and mustard to soybean and sunflower. Bhabha Atomic Research Centre (BARC), Mumbai which has strongly pursued the important societal programmes using nuclear technology in agriculture and health, has made a very significant impact on the country's agriculture by developing 27 new crop varieties mostly of oil seeds and pulses. Further, radiation processing of food, pioneered in India by BARC, is now gaining global acceptance and has opened new vistas for agriculture exports. The present symposium is dedicated to trends in research of technologies in agriculture and food sciences. The papers relevant to INIS are indexed separately

  16. HB-Line Special Nuclear Material Campaigns: Model-Based Project Management

    International Nuclear Information System (INIS)

    CHANG, ROBERT

    2004-01-01

    This study is to show how a model was used to enable management to better estimate production capabilities to ensure contract milestones/commitments are met, to cope with fast changing project baselines and project missions, to ensure the project will meet the negotiated throughput, and to eliminate unnecessary but costly design changes

  17. BARC progress report - 1998

    Energy Technology Data Exchange (ETDEWEB)

    Kalyane, V L [comp.; Library and Information Services Div., Bhabha Atomic Research Centre, Mumbai (India)

    1999-04-01

    This report is a compilation of the progress in various major activities and Research and Development programmes of the different Divisions of the Bhabha Atomic Research Centre, Mumbai. The list of publications and papers presented at the various conferences, symposia, workshops and papers published in journal by the staff members of the Divisions are also given. (author) figs., tabs.

  18. BARC progress report - 1998

    International Nuclear Information System (INIS)

    Kalyane, V.L.

    1999-04-01

    This report is a compilation of the progress in various major activities and Research and Development programmes of the different Divisions of the Bhabha Atomic Research Centre, Mumbai. The list of publications and papers presented at the various conferences, symposia, workshops and papers published in journal by the staff members of the Divisions are also given. (author)

  19. BARC progress report - 1997

    Energy Technology Data Exchange (ETDEWEB)

    Kalyane, V L [comp.; Library and Information Services Div., Bhabha Atomic Research Centre, Mumbai (India)

    1998-07-01

    This report is a compilation of the progress in various major activities and Research and Development programmes of the different Divisions of the Bhabha Atomic Research Centre, Mumbai. The list of publications and papers presented at the various conferences, symposia, workshops and papers published in journal by the staff members of the Divisions are also given. (author) figs., tabs.

  20. BARC progress report - 1997

    International Nuclear Information System (INIS)

    Kalyane, V.L.

    1998-07-01

    This report is a compilation of the progress in various major activities and Research and Development programmes of the different Divisions of the Bhabha Atomic Research Centre, Mumbai. The list of publications and papers presented at the various conferences, symposia, workshops and papers published in journal by the staff members of the Divisions are also given. (author)

  1. BARC progress report - 1996

    International Nuclear Information System (INIS)

    1997-01-01

    This report summarises the various activities and research and development programmes of the different Divisions of the Bhabha Atomic Research Centre, Mumbai. The list of publications and paper presented at various conferences, symposia, workshops etc and papers published in various journals by the staff members of the different Divisions are also given. (author)

  2. BARC progress report - 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    This report summarises the various activities and research and development programmes of the different Divisions of the Bhabha Atomic Research Centre, Mumbai. The list of publications and paper presented at various conferences, symposia, workshops etc and papers published in various journals by the staff members of the different Divisions are also given. (author)

  3. The Texts of the Instruments connected with the Agency's Assistance to Turkey in furthering Projects by the Supply of Materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1966-07-20

    The texts of the Master Agreement between the Agency and the Government of Turkey and of Supplementary Agreement No. 1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials are reproduced in this document for the information of all Members. Both Agreements entered into force on 8 February 1966.

  4. Individualization and Modularization of Vocational Education Instructional Materials. An Annotated Bibliography of Publications and Projects. Bibliography Series No. 32.

    Science.gov (United States)

    Magisos, Joel H., Comp.; Stakelon, Anne E., Comp.

    This annotated bibliography is designed to assist applicants for research grants under part C (section 131a) of the amendments to the Vocational Education Act of 1963 by providing access to documents, journal articles, and current projects related to the individualization and modularization of vocational education instructional materials. The…

  5. The Texts of the Instruments connected with the Agency's Assistance to Turkey in furthering Projects by the Supply of Materials

    International Nuclear Information System (INIS)

    1966-01-01

    The texts of the Master Agreement between the Agency and the Government of Turkey and of Supplementary Agreement No. 1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials are reproduced in this document for the information of all Members. Both Agreements entered into force on 8 February 1966

  6. The Text of the Agreement connected with the Agency's Assistance to Bulgaria in furthering Projects by the Supply of Materials

    International Nuclear Information System (INIS)

    1971-01-01

    The text of the Master Agreement between the Agency and the Government of Bulgaria for assistance by the Agency in furthering projects by the supply of materials is reproduced herein for the information of all Members. This Agreement entered into force on 15 July 1970.

  7. The Texts of the Instruments connected with the Agency's Assistance to Greece in furthering Projects by the Supply of Materials

    International Nuclear Information System (INIS)

    1971-01-01

    The texts of the Master Agreement between the Agency and the Government of Greece, and of Supplementary Agreement No. 1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials are reproduced herein for the information of all Members. These Agreements entered into force on 2 June 1970 and 20 July 1970 respectively.

  8. The Texts of the Instruments connected with the Agency's Assistance to India in furthering Projects by the Supply of Materials

    International Nuclear Information System (INIS)

    1967-01-01

    The texts of the Master Agreement between the Agency and the Government of India, and of Supplementary Agreement No. 1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials, are reproduced in this document for the information of all Members. Both Agreements entered into force on 9 December 1966

  9. The Text of the Agreement connected with the Agency's assistance to Pakistan in furthering Projects by the Supply of Materials

    International Nuclear Information System (INIS)

    1971-01-01

    The text of the Master Agreement between the Agency and the Government of Pakistan for assistance by the Agency in furthering projects by the supply of materials is reproduced herein for the information of all Members. This Agreement entered into force on 27 February 1970.

  10. The Texts of the Instruments connected with the Agency's Assistance to Iraq in Furthering Projects by the Supply of Materials

    International Nuclear Information System (INIS)

    1973-01-01

    The texts of the Master Agreement between the Agency and the Government of Iraq, and of Supplementary Agreement No. 1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials, are reproduced herein for the information of all Members

  11. The Texts of the Instruments connected with the Agency's Assistance to Brazil in Furthering Projects by the Supply of Material

    International Nuclear Information System (INIS)

    1971-01-01

    The texts of the Master Agreement between the Agency and the Government of Brazil, and of Supplementary Agreement No.1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials, are reproduced herein for the information of all Members. These Agreements entered into force on 20 November 1970 and 12 January 1971 respectively.

  12. The Text of the Agreement connected with the Agency's Assistance to Bulgaria in furthering Projects by the Supply of Materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1971-05-20

    The text of the Master Agreement between the Agency and the Government of Bulgaria for assistance by the Agency in furthering projects by the supply of materials is reproduced herein for the information of all Members. This Agreement entered into force on 15 July 1970.

  13. The Texts of the Instruments connected with the Agency's Assistance to Mexico in Furthering Projects by the Supply of Materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1973-11-28

    The texts of the Master Agreement between the Agency and the Government of Mexico, and of Supplementary Agreement No. 1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials, are reproduced herein for the information of all Members.

  14. The Texts of the Instruments connected with the Agency's Assistance to Greece in furthering Projects by the Supply of Materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1971-05-27

    The texts of the Master Agreement between the Agency and the Government of Greece, and of Supplementary Agreement No. 1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials are reproduced herein for the information of all Members. These Agreements entered into force on 2 June 1970 and 20 July 1970 respectively.

  15. The Texts of the Instruments connected with the Agency's Assistance to India in furthering Projects by the Supply of Materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1967-06-09

    The texts of the Master Agreement between the Agency and the Government of India, and of Supplementary Agreement No. 1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials, are reproduced in this document for the information of all Members. Both Agreements entered into force on 9 December 1966.

  16. The Texts of the Instruments connected with the Agency's Assistance to Brazil in Furthering Projects by the Supply of Material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1971-05-20

    The texts of the Master Agreement between the Agency and the Government of Brazil, and of Supplementary Agreement No.1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials, are reproduced herein for the information of all Members. These Agreements entered into force on 20 November 1970 and 12 January 1971 respectively.

  17. The Texts of the Instruments connected with the Agency's Assistance to Iraq in Furthering Projects by the Supply of Materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1973-11-28

    The texts of the Master Agreement between the Agency and the Government of Iraq, and of Supplementary Agreement No. 1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials, are reproduced herein for the information of all Members.

  18. The Text of the Agreement connected with the Agency's assistance to Pakistan in furthering Projects by the Supply of Materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1971-05-20

    The text of the Master Agreement between the Agency and the Government of Pakistan for assistance by the Agency in furthering projects by the supply of materials is reproduced herein for the information of all Members. This Agreement entered into force on 27 February 1970.

  19. Simulating The Impact Of The Material Flow In The Jordanian Construction Supply Chain And Its Impact On Project Performance

    Directory of Open Access Journals (Sweden)

    Dr. Ghaith Al-Werikat

    2017-03-01

    Full Text Available With the new developments and challenges within the construction industry improving the construction supply chain is becoming a major concern to both governments and industries. Improving the construction supply chain helps in improving the quality of construction projects reducing cost wastes delays and other disruptions. This paper discusses the analysis of material flow in the construction supply chain. The methodology consisted of preliminary investigations survey and simulation development to analyse the extent of impact that material flow has on construction projects in Jordan. Both the main survey and the investigations revealed that material flow delays are caused mainly by 3 types of delays late delivery wrong specification and material damaged on site. The highest impact regarding late deliveries was scaffolding with a 16 probability of occurrence a 2-day delay on the activitys duration. Concrete ranked highest regarding wrong specification with a 19 probability of occurrence an 8-day delay the activitys duration. Regarding materials damaged on site bricks ranked highest with a 9 probability of occurrence a 3-day delay on the duration. The simulation results exhibited a delay of 50 on the projects duration and a probability of a delay occurring is 9.2.

  20. Hazardous materials in Aquatic environments of the Mississippi River basin. Quarterly project status report, 1 January 1994--30 March 1994

    Energy Technology Data Exchange (ETDEWEB)

    Abdelghani, A.

    1994-06-01

    Projects associated with this grant for studying hazardous materials in aquatic environments of the Mississippi River Basin are reviewed and goals, progress and research results are discussed. New, one-year initiation projects are described briefly.

  1. Engineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 3: Corrosion and data modeling

    International Nuclear Information System (INIS)

    Van Konynenburg, R.A.; McCright, R.D.; Roy, A.K.; Jones, D.A.

    1995-08-01

    This three-volume report serves several purposes. The first volume provides an introduction to the engineered materials effort for the Yucca Mountain Site Characterization Project. It defines terms and outlines the history of selection and characterization of these materials. A summary of the recent engineered barrier materials characterization workshop is presented, and the current candidate materials are listed. The second volume tabulates design data for engineered materials, and the third volume is devoted to corrosion data, radiation effects on corrosion, and corrosion modeling. The second and third volumes are intended to be evolving documents, to which new data will be added as they become available from additional studies. The initial version of Volume 3 is devoted to information currently available for environments most similar to those expected in the potential Yucca Mountain repository. This is volume three

  2. Analysis of the application of an interdisciplinar project in education of future engineers: assembly of thermal machines with recycled materials

    Directory of Open Access Journals (Sweden)

    Elaine Cristina Marques

    2015-12-01

    Full Text Available Teaching through the four areas of learning development is increasing in educational systems. The methods used for this purpose are: analysis and solving of problems, and development of integrative or interdisciplinary projects. Both use active learning methodologies, making it possible to circumvent the low capacity for concentration and retention of information from today’s students, so globalized and dependent on computers. In this sense, the development of this project aims for the students to manufacture a steam machine with reused/recycled materials, and to present it during a trial lesson. This project was developed in the Fundamentals of Thermodynamics and Engineering and Materials Science courses, taken in the first semester of 2014, and involved 130 students enrolled in the fifth semester of the Production Engineering course at Centro Universitário Padre Anchieta. A total of 28 steam machines were presented and, after prior modification, the majority succeeded in their functioning. Most of the groups used industrial materials and/or industrial tools in order to accomplish their projects. Due to this experience, they could apply their knowledge in both student and professional routines. Based on that, it is believed that the projects may play a role of meaningful learning for students. At the end of the activity, most students signaled their satisfaction with the project and their desire to repeat such activities, which interconnect disciplines. It is possible to conclude that teaching through interdisciplinary projects is an important tool in the teaching of engineering, thus, understanding of knowledge is more articulate and less fragmented. It contributes to the use of science as an element of interpretation and intervention of reality

  3. Law project of program relative to the management of radioactive materials and wastes

    International Nuclear Information System (INIS)

    Villepin, D. de; Breton, T.

    2006-03-01

    The law of the 30 December 1991 defined three axis of researches and fixed a the legal aspects of the researches programs management. Based on these researches results a law project has been defined. The first part of the document presents the objectives of the law project and discusses the different articles. The second part is devoted to the text of the law project. (A.L.B.)

  4. Developing improved opportunities for the recycling and reuse of materials in road, bridge, and construction projects.

    Science.gov (United States)

    2014-12-01

    The use of recycled and reused materials in transportation construction reduces consumption of non-renewable : resources. The objective of this research was to develop opportunities for improving the recycling and reuse of : materials in road and bri...

  5. Beneficial use of dredged materials in Great Lakes commercial ports for transportation projects.

    Science.gov (United States)

    2014-05-01

    This report describes an effort to facilitate beneficial use of dredged materials (DM) from Great Lakes ports and harbors as an alternative construction : material in transportation-related earthwork applications. The overall objective is to link tog...

  6. Beneficial Uses of Dredged Material Fact Sheet: Project Partners and Decision Makers

    Science.gov (United States)

    Disposal of dredged material is managed and conducted by federal, state, and local governments; private entities; and semi-private entities. Cooperation among these groups strengthens the possibility that suitable materials will be used beneficially.

  7. Mutation induction, evaluation and utilization for development of high yielding varieties in Indian mustard and sunflower: an overview of BARC work

    International Nuclear Information System (INIS)

    Jambhulkar, S.J.; Shitre, A.S.

    2009-01-01

    Mutation breeding programme in Indian mustard and sunflower at BARC has resulted into the development of wide spectrum of mutations for seed coat colour, chlorophyll, plant height, maturity, flower morphology, seed weight and oil content. In Indian mustard, TM1 and TM50 are high yielding yellow seed coat mutants, which were exploited in hybridisation to develop bold, yellow seed coat and high yielding genotypes. Light green leaf and variegated leaf are novel mutation in mustard. Putative mutants for drought tolerance have been isolated. Variability for zero erucic acid and zero glucosinolates genotypes have been developed in B. napus and B. juncea. In sunflower, high yielding black seed coat mutant were isolated. Extreme dwarf measuring only 11 cm is novel. Three high yielding varieties namely TM2, TM4, and TPM1 in mustard and one i.e.TAS82 in sunflower have been released for cultivation in collaboration with state agricultural universities. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  9. Potential food applications of biobased materials. An EU- concerted action project

    DEFF Research Database (Denmark)

    Haugaard, V.K.; Udsen, A.M.; Mortensen, G.

    2001-01-01

    and coatings to food but novel commercial applications of these are scarce. Based on information currently available on the properties of biobased packaging materials the study identified products in the fresh meat, dairy, ready meal, beverage, fruit and vegetable, snack, frozen food and dry food categories......The objective of the study was to ascertain the state of the art with regard to the applicability of biobased packaging materials to foods and to identify potential food applications for biobased materials. The study revealed relatively few examples of biobased materials used as primary, secondary...... or tertiary packaging materials for foods. This is due to the fact that published investigations on the use of biobased materials are still scarce, and results obtained remain unpublished because of commercial pressures. The scientific literature contains numerous reports on applications of edible films...

  10. Pollution Prevention, Waste Minimization and Material Recycling Successes Realized during Savannah River Site's K Area Materials Storage (KAMS) Project, W226

    International Nuclear Information System (INIS)

    Ellis, M.S.

    2001-01-01

    As DOE continues to forge ahead and re-evaluate post cold war missions, facilities that were constructed and operated for DOE/DOD over the past 50+ years are coming to the end of their useful life span. These various facilities throughout the country had served a very useful purpose in our nations history; however, their time of Cold War materials production has come to an end. With this looming finalization comes a decision as to how to remedy their existence: D and R the facilities and return to ''Greenfield''; or, retrofit the existing facilities to accommodate the newer missions of the DOE Complex. The 105-K Reactor Building located at the Savannah River Site in Aiken, South Carolina was retrofit on an accelerated project schedule for a new mission called K-Area Materials Storage (KAMS). Modifications to the former defense reactor's building and equipment will allow storage of Plutonium from the Rocky Flats Site in Colorado and other materials deemed necessary by the Department of Energy. Proper project planning and activity sequencing allowed the DOE and the Westinghouse Savannah River Company to realize savings from: the recycling and/or reuse of modified facility components; reduction and reclassification of waste; reduction in radiological area footprint (rollbacks)

  11. Technological project of serpentine raw material milling from Dobšiná heaps

    Directory of Open Access Journals (Sweden)

    Alena Pietriková

    2005-11-01

    Full Text Available Serpentine heaps in the surrounding of Dobšiná are an old ecological problem of the city and at the same time a suitable material for the production of MgCl2 and SiO2. The technology of the production is based on the chemical processing of the raw material, which is preceded by the raw material preparation comprising of the mechanical and hydraulic sorting, milling and the magnetic separation operations.

  12. The project of the Spanish Nuclear Industry Forum to develop an interactive educational material on Radiological Protection

    International Nuclear Information System (INIS)

    Real, A.; Cruz, T. de la; Girona, L.; Montesinos, L.; Sanchez, P.

    2012-01-01

    The Training Department of the Spanish Nuclear Industry Forum has undertaken a new project to develop an interactive educational material on Radiological Protection. The objective was to develop an attractive, comprehensive and interactive material, to facilitate students and teachers of Elementary, Middle and High schools, to become familiar with ionising radiations. The novelly of the project, is that based on the European framework of key competencies for file long learning, which are defined as a set of knowledge, skills and altitudes that all individuals need for personal fulfilment and employment. The material presented in this paper, is based in an integrated structure of tasks, activities and exercises, which will facilitate the acquisition of as may key competencies as possible. Besides, the material also includes reference texts, links to pertinent web sites and videos. Students, through the development of a specific task (and related activities and exercises), will learn the differences between ionizing and non ionising radiation, the origin, characteristics and types of types of ionising radiation, how to detect and measure them, the potential detrimental health effects, the principles of radiation protection and the beneficial applications can have for man. The material is freely available in www.rinconeducativo.org. (Author) 4 refs.

  13. Investigations of Materials under High Repetition and Intense Fusion Pulses. Report of a Coordinated Research Project 2011-2016

    International Nuclear Information System (INIS)

    2017-12-01

    This publication presents experimental simulations of plasma-surface interaction phenomena at extreme conditions as expected in a fusion reactor, using dedicated test bed devices such as dense plasma focus, particle accelerators, plasma accelerators and plasma guns. It includes the investigation of the mechanism of material damage during transient heat loads on materials and addresses, in particular, the performance and adequacy of tungsten as plasma facing material for the next step fusion devices, such as ITER and fusion demonstration power plants. The publication is a compilation of the main results and findings of an IAEA coordinated research project on investigations on materials under high repetition and intense fusion pulses, conducted in the period 2011-2016 and provides a practical knowledge base for scientists and engineers carrying out activities in the plasma-material surface interaction area. Through its coordinated research activities, the IAEA has made it possible for States that are not yet members of the ITER project to contribute to ITER relevant scientific investigations, which have led to increased capabilities of diagnostics for plasma surface interaction.

  14. Bill project authorizing the approval of the amendment to the convention on physical protection of nuclear material - Nr 11

    International Nuclear Information System (INIS)

    Ayrault, Jean-Marc; Fabius, Laurent

    2012-01-01

    This document contains the brief text of the bill project and the text of the amendment to the Convention on physical protection of nuclear material which has been adopted in Vienna in August 2005 to amend the Convention adopted in October 1979. This amendment introduces the following measures: extension of the scope of application of the Convention to nuclear materials used for peaceful purposes, definition of the objectives of the Convention, articulation of the Convention with other international instruments, definition of the main principles of physical protection, strengthened international cooperation, legal issues concerning extradition and legal cooperation

  15. Testing a Novel Geopolymer Binder as a Refractory Material for Rocket Plume Environments at SSC Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The project involved the development and testing of a new alumina-silicate based multi-purpose, cost-effective, ‘green’ cementitious binder (geopolymer)...

  16. A post-contract project analysis of material waste and cost overrun ...

    African Journals Online (AJOL)

    In Malaysia, 28.34% of the total waste sent to landfills originates from ..... by comparing the opinions of the first two interviewees. The process continued .... the causes of delay and cost overrun in Uganda's public sector construction projects.

  17. The Texts of the Instruments connected with the Agency's Assistance to Yugoslavia in Furthering Projects by the Supply of Materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1971-05-27

    The texts of the Master Agreement between the Agency and the Government of Yugoslavia, and of Supplementary Agreements No. 1 and No. 2 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials, are reproduced herein for the information of all Members. These Agreements entered into force on 29 May 1970, 8 September 1970 and 2 February 1971 respectively.

  18. The Texts of the Instruments Connected with the Agency's Assistance to Chile in Furthering Projects by the Supply of Materials

    International Nuclear Information System (INIS)

    1973-01-01

    The texts of the Master Agreement between the Agency and the Government of Chile, and of Supplementary Agreement No. 1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials, are reproduced herein for the information of all Members. The Master Agreement entered into force on 16 March 1973, pursuant to its Article XIV, and the Supplementary Agreement on 14 June 1973, pursuant to its Article IV.

  19. The Texts of the Instruments connected with the Agency's Assistance to Romania in Furthering Projects by the Supply of Materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1967-06-09

    The texts of the Master Agreement between the Agency and the Government of Romania, and of Supplementary Agreement No. 1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials, are reproduced in this document for the information of all Members. The former Agreement entered into force on 22 April 1966, and the latter on 1 August 1966.

  20. The Texts of the Instruments Connected with the Agency's Assistance to Chile in Furthering Projects by the Supply of Materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1973-11-29

    The texts of the Master Agreement between the Agency and the Government of Chile, and of Supplementary Agreement No. 1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials, are reproduced herein for the information of all Members. The Master Agreement entered into force on 16 March 1973, pursuant to its Article XIV, and the Supplementary Agreement on 14 June 1973, pursuant to its Article IV.

  1. The Texts of the Instruments connected with the Agency's Assistance to Yugoslavia in Furthering Projects by the Supply of Materials

    International Nuclear Information System (INIS)

    1971-01-01

    The texts of the Master Agreement between the Agency and the Government of Yugoslavia, and of Supplementary Agreements No. 1 and No. 2 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials, are reproduced herein for the information of all Members. These Agreements entered into force on 29 May 1970, 8 September 1970 and 2 February 1971 respectively.

  2. Law project modified by the Senate, of the program relative to the sustainable management of radioactive materials and wastes

    International Nuclear Information System (INIS)

    2006-05-01

    In the framework of a sustainable development and of the nuclear energy development, the France decided by the law of the 30 December 1991, to study three axis or researches: the radioactive wastes transmutation, their deep underground disposal and their storage during ten years. Today, after evaluation of the researches results a law project on the sustainable management of the radioactive materials and wastes, has been prepared. This document presents the different articles of the law. (A.L.B.)

  3. The Texts of the Instruments connected with the Agency's Assistance to Romania in Furthering Projects by the Supply of Materials

    International Nuclear Information System (INIS)

    1967-01-01

    The texts of the Master Agreement between the Agency and the Government of Romania, and of Supplementary Agreement No. 1 thereto, in connection with the Agency's assistance to that Government in furthering projects by the supply of materials, are reproduced in this document for the information of all Members. The former Agreement entered into force on 22 April 1966, and the latter on 1 August 1966

  4. Recovery Act, EFRC Project: Solar Energy Conversion in Complex Materials (SECCM)

    Energy Technology Data Exchange (ETDEWEB)

    Green, Peter F. [Univ. of Michigan, Ann Arbor, MI (United States)

    2015-06-25

    The goal of the Center was to design and to synthesize new materials for high efficiency photovoltaic (PV) and thermoelectric (TE) devices, predicated on new fundamental insights into equilibrium and non-equilibrium processes, including quantum phenomena, that occur in materials over various spatial and temporal scales.

  5. Yucca Mountain project canister material corrosion studies as applied to the electrometallurgical treatment metallic waste form

    International Nuclear Information System (INIS)

    Keiser, D.D.

    1996-11-01

    Yucca Mountain, Nevada is currently being evaluated as a potential site for a geologic repository. As part of the repository assessment activities, candidate materials are being tested for possible use as construction materials for waste package containers. A large portion of this testing effort is focused on determining the long range corrosion properties, in a Yucca Mountain environment, for those materials being considered. Along similar lines, Argonne National Laboratory is testing a metallic alloy waste form that also is scheduled for disposal in a geologic repository, like Yucca Mountain. Due to the fact that Argonne's waste form will require performance testing for an environment similar to what Yucca Mountain canister materials will require, this report was constructed to focus on the types of tests that have been conducted on candidate Yucca Mountain canister materials along with some of the results from these tests. Additionally, this report will discuss testing of Argonne's metal waste form in light of the Yucca Mountain activities

  6. Scoping corrosion tests on candidate waste package basket materials for the Yucca Mountain project

    International Nuclear Information System (INIS)

    Konynenburg, R.A. van; Curtis, P.G.; Summers, T.S.E.

    1998-03-01

    A scoping corrosion test was performed on candidate waste package basket materials. The corrosion medium was a pH-buffered solution of chemical species expected to be produced by radiolysis. The test was conducted at 90 C for 96 hours. Samples included aluminum-, copper-, stainless steel- and zirconium-based metallic materials and several ceramics, incorporating neutron-absorbing elements. Sample weight losses and solution chemical changes were measured. Both corrosion of the host materials and dissolution of the neutron-absorbing elements were studied. The ceramics and the zirconium-based materials underwent only minor corrosion. The stainless steel-based materials performed well except for a welded sample. The aluminum- and copper-based materials exhibited the highest corrosion rates. Boron dissolution depends on its chemical form. Boron oxide and many metal borides dissolve readily in acidic solutions while high-chromium borides and boron carbide, though thermodynamically unstable, exhibit little dissolution in short times. The results of solution chemical analyses were consistent with this. Gadolinium did not dissolve significantly from monazite, and hafnium showed little dissolution from a variety of host materials, in keeping with its low solubility

  7. Final Project Report for ER15351 ''A Study of New Actinide Zintl Ions Materials''

    International Nuclear Information System (INIS)

    Peter K. Dorhout

    2007-01-01

    The structural chemistry of actinide main-group metal materials provides the fundamental basis for the understanding of structural coordination chemistry and the formation of materials with desired or predicted structural features. The main-group metal building blocks, comprising sulfur-group, phosphorus-group, or silicon-group elements, have shown versatility in oxidation state, coordination, and bonding preferences. These building blocks have allowed us to elucidate a series of structures that are unique to the actinide elements, although we can find structural relationships to transition metal and 4f-element materials. In the past year, we investigated controlled metathesis and self-propagating reactions between actinide metal halides and alkali metal salts of main-group metal chalcogenides such as K-P-S salts. Ternary plutonium thiophosphates have resulted from these reactions at low temperature in sealed ampules. we have also focused efforts to examine reactions of Th, U, and Pu halide salts with other alkali metal salts such as Na-Ge-S and Na-Si-Se and copper chloride to identify if self-propagating reactions may be used as a viable reaction to prepare new actinide materials and we prepared a series of U and Th copper chalcogenide materials. Magnetic measurements continued to be a focus of actinide materials prepared in our laboratory. We also contributed to the XANES work at Los Alamos by preparing materials for study and for comparison with environmental samples

  8. Validation of Material Models For Automotive Carbon Fiber Composite Structures Via Physical And Crash Testing (VMM Composites Project)

    Energy Technology Data Exchange (ETDEWEB)

    Coppola, Anthony [General Motors Company, Flint, MI (United States); Faruque, Omar [Ford Motor Company, Dearborn, MI (United States); Truskin, James F [FCA US LLC, Auburn Hills, MI (United States); Board, Derek [Ford Motor Company, Dearborn, MI (United States); Jones, Martin [Ford Motor Company, Dearborn, MI (United States); Tao, Jian [FCA US LLC, Auburn Hills, MI (United States); Chen, Yijung [Ford Motor Company, Dearborn, MI (United States); Mehta, Manish [M-Tech International LLC, Dubai (United Arab Emirates)

    2017-09-27

    As automotive fuel economy requirements increase, the push for reducing overall vehicle weight will likely include the consideration of materials that have not previously been part of mainstream vehicle design and manufacturing, including carbon fiber composites. Vehicle manufacturers currently rely on computer-aided engineering (CAE) methods as part of the design and development process, so going forward, the ability to accurately and predictably model carbon fiber composites will be necessary. If composites are to be used for structural components, this need applies to both, crash and quasi-static modeling. This final report covers the results of a five-year, $6.89M, 50% cost-shared research project between Department of Energy (DOE) and the US Advanced Materials Partnership (USAMP) under Cooperative Agreement DE-EE-0005661 known as “Validation of Material Models for Automotive Carbon Fiber Composite Structures Via Physical and Crash Testing (VMM).” The objective of the VMM Composites Project was to validate and assess the ability of physics-based material models to predict crash performance of automotive primary load-carrying carbon fiber composite structures. Simulation material models that were evaluated included micro-mechanics based meso-scale models developed by the University of Michigan (UM) and micro-plane models by Northwestern University (NWU) under previous collaborations with the DOE and Automotive Composites Consortium/USAMP, as well as five commercial crash codes: LS-DYNA, RADIOSS, VPS/PAM-CRASH, Abaqus, and GENOA-MCQ. CAE predictions obtained from seven organizations were compared with experimental results from quasi-static testing and dynamic crash testing of a thermoset carbon fiber composite front-bumper and crush-can (FBCC) system gathered under multiple loading conditions. This FBCC design was developed to demonstrate progressive crush, virtual simulation, tooling, fabrication, assembly, non-destructive evaluation and crash testing

  9. Brownfields Recover Your Resources - Reduce, Reuse, and Recycle Construction and Demolition Materials at Land Revitalization Projects

    Science.gov (United States)

    This document provides background information on how the sustainable reuse of brownfield properties includes efforts to reduce the environmental impact by reusing and recycling materials generated during building construction, demolition, or renovation.

  10. 0-6717 : investigation of alternative supplementary cementing materials (SCMs) : [project summary].

    Science.gov (United States)

    2014-08-01

    In Texas, Class F fly ash is extensively used as a : supplementary cementing material (SCM) : because of its ability to control thermal cracking : in mass concrete and to mitigate deleterious : expansions in concrete from alkali-silica reaction : (AS...

  11. Future semiconductor material requirements and innovations as projected in the ITRS 2005 roadmap

    International Nuclear Information System (INIS)

    Arden, Wolfgang

    2006-01-01

    The international technology roadmap for semiconductors (ITRS) is a joint global effort of the semiconductor industry, the manufacturing equipment and material industry and the research community and consortia to define the future requirements and development of the semiconductor technology for the next 15 years. The ITRS started in 1992 as a US-national roadmap and became an international effort in 1998 with all major five industrial global regions (US, Japan, Taiwan, Korea and Europe) participating in its definition. The outlook in semiconductor manufacturing expects the continuous application of silicon technology for the next 15 years where complementary metal oxide semiconductor (CMOS) based devices will carry the development of the industry at least for one more decade. New device architectures and concepts based on silicon wafer material are being developed to support the development of the IC industry for another one or two decade. The major section of the ITRS contains technical information about frontend processing and interconnects, device structures and memory concepts, lithography and metrology as well as factory integration and environmental issues. This paper will review the material requirements and the expected material innovations for the industry as outlined in the ITRS Version 2005. Materials to be discussed are, for example, high permittivity gate dielectrics, insulating layers with low dielectric constants for interconnects, and capacitor dielectrics for dynamic memories. In addition, the paper will address, for example, new transistor gate materials, new solutions for interconnect systems beyond copper as well as new starting materials for wafer sizes beyond 300 mm. This publication was presented as an invited paper in the Symposium V of the 2006 spring meeting of the European Materials Research Society (E-MRS) in Nice, May 29th

  12. Experiments on container materials for Swiss high-level waste disposal projects. Part 2

    International Nuclear Information System (INIS)

    Simpson, J.P.

    1984-12-01

    The present concept for final disposal of high-level waste in Switzerland consists of a repository at a depth of 1000 to 1500 m in the crystalline bedrock of northern Switzerland. The waste will be placed in a container which is required to function as a high integrity barrier for at least 1000 years. This report is the second of a set of two dealing with the evaluation of potential materials for such containers. Four materials were identified for further evaluation in the first of these reports; they were cast steel, nodular cast iron, copper and Ti-Code 12. It was concluded that some testing was needed, in particular with respect to corrosion, in order to confirm these materials as candidate container materials. The experimental programme included: 1) corrosion tests on copper under gamma radiation; 2) immersion corrosion tests on the four candidate materials including welded specimens; 3) corrosion testing of the four materials in saturated bentonite; 4) constant strain rate testing of Ti-Code 12 and copper at 80 degrees C; 5) the behaviour of copper, Ti-Code 12 and Zircaloy-2 when immersed in liquid lead; 6) corrosion potential and galvanic current measurements on several material pairs. The standard test medium was natural mineral water from the Bad Saeckingen source. This water has a total dissolved solids content of approx. 3200 mg/l, about 1600 mg/l as chloride. The oxygen level was defined as 0.1 μg/g. In certain cases this medium was modified in order to test under more severe conditions. The results of the corrosion tests confirm in general the evaluation in the first part of the report. All of the materials are suitable for high-level waste containers: cast steel, nodular cast iron and copper as single layer containers, and Ti-Code 12 as an outer corrosion resistant layer. Copper could also be used under an outer steel layer, where it could arrest local penetration

  13. Repository seal materials performance for a SALT Repository Project 5-year code/model development plan: Draft

    International Nuclear Information System (INIS)

    1987-06-01

    This document describes an integrated laboratory testing and model development effort for the seal system for a high-level nuclear waste repository in salt. The testing and modeling efforts are designed to determine seal material response in the repository environment, to provide models of seal system components for performance assessment, and to assist in the development of seal system designs. A code/model development and performance analysis program will be performed to predict the short- and long-term response of seal materials and seal components. The results from these analyses will be used to support the material testing activities on this contract and to support performance assessment activities that are conducted in other parts of the Salt Repository Project (SRP). 48 refs., 15 figs., 4 tabs

  14. How to Start Your Own Business. Women Entrepreneurs Project. Instructional Materials.

    Science.gov (United States)

    McCaslin, Barbara S.; McNamara, Patricia P.

    This text consisting of eight learning activities packages (LAP's) was developed during the California Women Entrepreneurs Project for use in a course designed to help women entrepreneurs learn how to start their own small business. The LAP's included here are self-paced, student-centered modules which take the learner step by step through the…

  15. The Project for the High Energy Materials Science Beamline at Petra III

    International Nuclear Information System (INIS)

    Martins, R. V.; Lippmann, T.; Beckmann, F.; Schreyer, A.

    2007-01-01

    The high energy materials science beamline will be among the first fourteen beamlines planned to be operational in 2009 at the new third generation synchrotron light source Petra III at DESY, Germany. The operation and funding of this beamline is assured by GKSS. 70% of the beamline will be dedicated to materials science. The remaining 30% are reserved for physics and are covered by DESY. The materials science activities will be concentrating on three intersecting topics which are industrial, applied, and fundamental research. The beamline will combine three main features: Firstly, the high flux, fast data acquisition systems, and the beamline infrastructure will allow carrying out complex and highly dynamic in-situ experiments. Secondly, a high flexibility in beam shaping will be available, fully exploiting the high brilliance of the source. Thirdly, the beamline will provide the possibility to merge in one experiment different analytical techniques such as diffraction and tomography

  16. History and practice of material research on the examples of Material Testing and Materialpruefungsanstalt (MPA) Stuttgart, liquid crystals and screen technology as well as superconductivity. An interdisciplinary teaching project of the University of Stuttgart

    International Nuclear Information System (INIS)

    Hentschel, Klaus; Webel, Josef

    2016-01-01

    The knowledge of material research and its history is not very common among scientists and engineers alike. Within the scope of an interdisciplinary teaching project carried out for the first time in the summer semester 2014 and ever since then every summer semester at the University of Stuttgart, an attempt is made to approach material research both from a scientific, technical and historical perspective. The Material Testing and Materials Testing Institute in Stuttgart (MPA), the liquid crystals and the screen technology as well as the superconductivity were selected as topics, which have a long tradition in research and teaching in Stuttgart. In this anthology the materials of the teaching project are summarized. [de

  17. ELABORATION PROCESS OF REFRACTORY MATERIALS BY REACTIVE PROJECTION OF OXIDE, PEROXIDE AND METALS

    OpenAIRE

    Pilatti , M.; Cransveld , J.; Raymond , G.; Plumat , E.; Duvigneaud , P.

    1986-01-01

    A device has been set up for spraying with accuracy a compound having a controlled grain size of refractory oxide, peroxide and metals. The refractory material is obtained by melting and recristallisation on a preheated substrate. Composition in the CaO.Al2O3 system and in the CaO-Al2O3-ZrO2 system have been synthesized. They have been analysed by X-ray diffraction and SEM. Dense and well cristallized materials have been deposited. This process can be successfully applied for the repair of a ...

  18. Evaluation of dredged material proposed for ocean disposal from Red Hook/Bay Ridge project areas, New York

    Energy Technology Data Exchange (ETDEWEB)

    Pinza, M.R.; Barrows, E.S.; Borde, A.B. [Battelle/Marine Sciences Lab., Sequim, WA (United States)

    1996-09-01

    The objective of the Red HookIBay Ridge project was to evaluate proposed dredged material from these two areas to determine its suitability for unconfined ocean disposal at the Mud Dump Site. Sediment samples were collected from the Red Hook/Bay Ridge project areas. Tests and analyses were conducted. The evaluation of proposed dredged material from the Red Hook/Bay Ridge project areas consisted of bulk sediment chemical analyses, chemical analyses of dredging site water and elutriate, water-column and benthic acute toxicity tests. Twenty-four individual sediment core samples were collected from these two areas and analyzed for grain size, moisture content, and total organic carbon (TOC). Three composite sediment samples, representing Red Hook Channel and the two Bay Ridge Reaches to be dredged, were analyzed for bulk density, specific gravity, metals, chlorinated pesticides, polychlorinated biphenyl (PCB) congeners, polynuclear aromatic hydrocarbons (PAH), and 1,4-dichlorobenzene. Dredging site water and elutriate water, which is prepared from the suspended-particulate phase (SPP) of the three Red Hook Bay Ridge sediment composites, were analyzed for metals, pesticides, and PCBS. Benthic acute toxicity tests were performed. Water-column or SPP toxicity tests were performed. Bioaccumulation tests were also conducted.

  19. The development of mini project interactive media on junior statistical materials (developmental research in junior high school)

    Science.gov (United States)

    Fauziah, D.; Mardiyana; Saputro, D. R. S.

    2018-05-01

    Assessment is an integral part in the learning process. The process and the result should be in line, regarding to measure the ability of learners. Authentic assessment refers to a form of assessment that measures the competence of attitudes, knowledge, and skills. In fact, many teachers including mathematics teachers who have implemented curriculum based teaching 2013 feel confuse and difficult in mastering the use of authentic assessment instruments. Therefore, it is necessary to design an authentic assessment instrument with an interactive mini media project where teacher can adopt it in the assessment. The type of this research is developmental research. The developmental research refers to the 4D models development, which consist of four stages: define, design, develop and disseminate. The research purpose is to create a valid mini project interactive media on statistical materials in junior high school. The retrieved valid instrument based on expert judgment are 3,1 for eligibility constructions aspect, and 3,2 for eligibility presentation aspect, 3,25 for eligibility contents aspect, and 2,9 for eligibility didactic aspect. The research results obtained interactive mini media projects on statistical materials using Adobe Flash so it can help teachers and students in achieving learning objectives.

  20. Materialism.

    Science.gov (United States)

    Melnyk, Andrew

    2012-05-01

    Materialism is nearly universally assumed by cognitive scientists. Intuitively, materialism says that a person's mental states are nothing over and above his or her material states, while dualism denies this. Philosophers have introduced concepts (e.g., realization and supervenience) to assist in formulating the theses of materialism and dualism with more precision, and distinguished among importantly different versions of each view (e.g., eliminative materialism, substance dualism, and emergentism). They have also clarified the logic of arguments that use empirical findings to support materialism. Finally, they have devised various objections to materialism, objections that therefore serve also as arguments for dualism. These objections typically center around two features of mental states that materialism has had trouble in accommodating. The first feature is intentionality, the property of representing, or being about, objects, properties, and states of affairs external to the mental states. The second feature is phenomenal consciousness, the property possessed by many mental states of there being something it is like for the subject of the mental state to be in that mental state. WIREs Cogn Sci 2012, 3:281-292. doi: 10.1002/wcs.1174 For further resources related to this article, please visit the WIREs website. Copyright © 2012 John Wiley & Sons, Ltd.

  1. Engineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 1, Introduction, history, and current candidates

    International Nuclear Information System (INIS)

    Van Konynenburg, R.A.; McCright, R.D.; Roy, A.K.; Jones, D.A.

    1995-08-01

    The purpose of the Yucca Mountain Site Characterization Project is to evaluate Yucca Mountain for its suitability as a potential site for the nation's first high-level nuclear waste repository. As part of this effort, Lawrence Livermore National Laboratory (LLNL) has been occupied for a number of years with developing and evaluating the performance of waste packages for the potential repository. In recent years this work has been carried out under the guidance of and in collaboration with the Management and Operating contractor for the Civilian Radioactive Waste Management System, TRW Environmental Safety Systems, Inc., which in turn reports to the Office of Civilian Radioactive Waste Management of the US Department of Energy. This report summarizes the history of the selection and characterization of materials to be used in the engineered barrier system for the potential repository at Yucca Mountain, describes the current candidate materials, presents a compilation of their properties, and summarizes available corrosion data and modeling. The term ''engineered materials'' is intended to distinguish those materials that are used as part of the engineered barrier system from the natural, geologic materials of the site

  2. The new EC FP7 MatISSE project: materials' innovations for a safe and sustainable nuclear in Europe

    International Nuclear Information System (INIS)

    Cabet, C.; Michaux, A.; Fazio, C.; Malerba, L.; Maday, M.F.; Serrano, M.; Nilsson, K.F.; )

    2015-01-01

    The European Energy Research Alliance (EERA), set-up under the European SET-Plan, has launched an initiative for a Joint Programme on Nuclear Materials (JPNM). The JNMP aims to establish key priorities in the area of advanced nuclear materials, identify funding opportunities and harmonise this scientific and technical domain at the European level by maximising complementarities and synergies with the major actors of the field. The JPNM partners submitted the MatISSE proposal which was accepted by the European Commission. The MatISSE project has the ambition to prepare the building of a European integrated research programme on materials innovation for a safe and sustainable nuclear. Emphasis is on advanced nuclear systems in particular sodium-cooled fast reactor (SFR), lead-cooled fast reactor (LFR) and gas-cooled fast reactor (GFR). The aim of the selected scientific and technical work is to make progress in the fields of conventional materials, advanced materials and predictive capabilities for fuel elements and structural components. (authors)

  3. PENGARUH STRATEGI PROJECT BASED LEARNING (PJBL TERHADAP KEMAMPUAN BERPIKIR KRITIS SISWA KELAS XI IPA PADA MATERI KOLOID

    Directory of Open Access Journals (Sweden)

    Nur Hikmah

    2016-11-01

    Full Text Available The 21st century education aims to develop the ability of intelligence of students in order to resolve the problems faced in real life. Project-Based Learning is one instructional strategies to develop the skills required in the 21st century. Through a given project, students are not only required to achieve the learning objectives that have been set, but students will be trained to face the world of work that requires their ability to access, mesintesis, communicating information, and work together to solve complex problems so as to improve the ability of students critical thinking. This research is a quasi-experimental research (quasy experiment with posttest only control group design. This research aims to determine the influence of Project Based Learning Strategy (PjBL to the critical thinking skills of students of class XI IPA at SMAN 1 Malua on colloidal material. The research population includes students of class XI IPA at SMAN 1 Malua, with random cluster sampling technique sampling. Data were analyzed using independent sample t-test in SPSS 20 for windows at the 0.05 level of significance. The result showed that the significance level of critical thinking skills of 0.001 which indicates that there are differences between students' critical thinking skills that learned using a strategy of Project Based Learning (PjBL with students that learned using conventional methods. Pendidikan abad 21 bertujuan untuk membangun kemampuan intelegensi siswa dalam pembelajaran agar mampu menyelesaikan permasalahan yang dihadapi. salah satu strategi pembelaj aran di abad 21 yang mengembangkan keterampilan siswa ialah Project Based Learning. Melalui proyek yang diberikan, siswa tidak hanya dituntut untuk mencapai tujuan pembelajaran yang telah ditetapkan, tetapi siswa akan lebih terlatih menghadapi dunia kerja yang membutuhkan kemampuan mereka dalam mengakses, mesintesis, mengomunikasikan infomasi, dan bekerja sama memecahkan masalah yang kompleks

  4. Corn Production. A Unit for Teachers of Vocational Agriculture. Production Agriculture Curriculum Materials Project.

    Science.gov (United States)

    Grace, Clyde, Jr.

    Designed to provide instructional materials for use by vocational agriculture teachers, this unit contains nine lessons based upon competencies needed to maximize profits in corn production. The lessons cover opportunities for growing corn; seed selection; seedbed preparation; planting methods and practices; fertilizer rates and application;…

  5. Bilingual Instructional Materials Dissemination Project. Report I: A Follow-Up Survey of SEDL Product Adopters.

    Science.gov (United States)

    Butler, Jacqueline; McGinty, John

    The Southwest Evaluation and Research Division conducted a survey of 165 purchasers of bilingual instructional materials produced by SEDL to determine which information channels predominate in the curriculum adoption-decision process. The findings of this survey may be useful in the selection of the most efficient ways to communicate information…

  6. Structural model for the first wall W-based material in ITER project

    Institute of Scientific and Technical Information of China (English)

    Dehua Xu; Xinkui He; Shuiquan Deng; Yong Zhao

    2014-01-01

    The preparation, characterization, and test of the first wall materials designed to be used in the fusion reactor have remained challenging problems in the material science. This work uses the first-principles method as implemented in the CASTEP package to study the influ-ences of the doped titanium carbide on the structural sta-bility of the W–TiC material. The calculated total energy and enthalpy have been used as criteria to judge the structural models built with consideration of symmetry. Our simulation indicates that the doped TiC tends to form its own domain up to the investigated nano-scale, which implies a possible phase separation. This result reveals the intrinsic reason for the composite nature of the W–TiC material and provides an explanation for the experimen-tally observed phase separation at the nano-scale. Our approach also sheds a light on explaining the enhancing effects of doped components on the durability, reliability, corrosion resistance, etc., in many special steels.

  7. Characterization of a backfill candidate material, IBECO-RWC-BF Baclo Project - Phase 3 Laboratory tests

    International Nuclear Information System (INIS)

    Johannesson, Lars-Erik; Sanden, Torbjoern; Dueck, Ann; Ohlsson, Lars

    2010-01-01

    A backfill candidate material, IBECO-RWC-BF, which origin from Milos, Greece, has been investigated. The material was delivered both as granules and as pellets. The investigation described in this report aimed to characterize the material and evaluate if it can be used in a future repository. The following investigations have been done and are presented in this report: 1. Standard laboratory tests. Water content, liquid limit and swelling potential are examples on standard tests that have been performed. 2. Block manufacturing. The block compaction properties of the material have been determined. A first test was performed in laboratory but also tests in large scale have been performed. After finishing the test phase, 60 tons of blocks were manufactured at Hoeganaes Bjuf AB. The blocks will be used in large scale laboratory tests at Aespoe HRL. 3. Mechanical parameters. The compressibility of the material was investigated with oedometer tests (four tests) where the load was applied in steps after saturation. The evaluated oedometer modulus varied between 34.50 MPa. Tests were made to evaluate the elastic parameters of the material (E, ν). Altogether three tests were made on specimens with dry densities of about 1,710 kg/m 3 . The evaluated E-modulus and Poisson's ratio varied between 231-263 MPa and 0.16-0.19 respectively. The strength of the material, both the compressive strength and the tensile strength were measured on specimens compacted to different dry densities. The test results yielded a relation between density and the two types of strength. Furthermore, tests have been made in order to determine the compressibility of the unsaturated filling of pellets. Two tests were made where the pellets were loosely filled in a Proctor cylinder and then compressed at a constant rate of strain during continuously measurement of the applied load. 4. Swelling pressure and hydraulic conductivity. There is, as expected, a very clear influence of the dry density on the

  8. Development and characterization of semiconductor materials by ion beams. Final report of a co-ordinated research project

    International Nuclear Information System (INIS)

    2002-06-01

    This CRP was recommended by the Consultants meeting on Ion Beam Techniques Applied to Semiconductor and Related Advanced Materials, held in April 1997 in Vienna. The consultants proposed to have a CRP in the field of application of MeV ion beams for the development and characterization of semiconductor materials. The CRP was approved and a first RCM was held in Vienna between 2-5 June 1998, in order to stimulate ideas and to promote collaborations among CRP participants. The goals and practical outcomes of the CRP were defined and several specific topics were identified including: optoelectronic characterization of semiconductor materials and devices by ion microbeams, characterization of thin films, defect transformations in semiconductors, light element analysis. One important recommendation was that sample exchanges among different laboratories be strongly encouraged. The participants presented individual activities on their projects, all subjects of research were identified and linked with approved individual projects. Collaboration among the participants was discussed and established. Some modifications to work plans were adopted. As proposed during the first RCM, the final RCM was held at the Ruder Boskovic Institute, Zagreb, Croatia, between 25 and 29 September 2000, with the purpose of reviewing/discussing the results achieved during the course of the CRP and to prepare a draft of the final report and associated publication. This document contains summary of the CRP and ten individual reports presented by participants. Each of the reports has been indexed separately

  9. International projects of the Chair for waste and material flow management in the period 2010-2014

    International Nuclear Information System (INIS)

    Nelles, Michael

    2015-01-01

    The waste and material flow management must align progressively to the requirements of sustainable resource and climate protection targets. She has become a recycling economy. One of the key global challenges of the future is to ensure a sustainable, i.e. economically, environmentally and socially sustainable supply of raw materials and energy. In both areas, the recycling economy make an important contribution. For Germany, despite of the ambitious targets, a positive balance can be drawn. In particular, the positive environmental effects of prevention, recovery and disposal of waste are supported by numerous scientific studies. While the recycling economy has performed well in Germany, many countries in the world are still in the beginning of a sustainable waste management development. Our Chair for Waste and Material Flow Management at the Faculty of Agricultural and Environmental Sciences of the University of Rostock has been involved for over 15 years in international technology and knowledge transfer. The regional focus are the Arab and Asian region (esp. China) and for some years, the Baltic countries, Eastern Europe and South America. Often in the projects stand in the foreground, to inform key decision-makers on the state of technology and to work out possible administrative solutions and customized technical solutions together and implement. In addition, classic R and D projects in these regions have been processed. In the framework of student works, studies in other countries, amongst other things in Vietnam and Chile, are carried out. [de

  10. Experiments on container materials for Swiss high-level waste disposal projects. Part IV

    International Nuclear Information System (INIS)

    Simpson, J.P.

    1989-12-01

    One concept for final disposal of high-level waste in switzerland consists of a repository at a depth of 1000 to 1500 m in the crystalline bedrock of Northern Switzerland. The waste will be placed in a container which will be required to function as a high integrity barrier for at least 100 years. This report is the fourth and last in the current series dealing with the evaluation of potential materials for such containers. Four materials were identified for further evaluation in the first of these reports: cast steel, nodular cast iron, copper and Ti-Code 12. This report deals with the problem of demonstrating that cast steel containers will not fail by stress corrosion cracking and with the problem of hydrogen produced by the reduction of water. The experimental results on pre-cracked specimens revealed no susceptibility of cast steel to stress corrosion cracking under model repository conditions. No crack growth was detected on compact DCB specimens exposed in aerobic and anaerobic groundwaters at 80 and 140 o C for 16-24 months. Cast steel remains a candidate material for high-level waste containers. As expected from thermodynamic considerations no hydrogen could be detected from copper immersed in model groundwaters at 50 o C. Hydrogen is evolved from corroding steel under anaerobic conditions. Hydrogen evolution due to corrosion of iron or steel in waste repositories has to be considered in any safety analysis; the amounts produced can be significant. Evidence todate suggests that both cast steel and copper are suitable container materials. Because the corrosion behaviour of both materials is sensitive to service conditions, in particular length of the aerobic phase, groundwater chemistry and temperature, further testing should be undertaken when a specific site has been identified. (author) 9 tabs., 11 figs., 25 refs

  11. Demonstration Project for a Multi-Material Lightweight Prototype Vehicle as Part of the Clean Energy Dialogue with Canada

    Energy Technology Data Exchange (ETDEWEB)

    Skszek, Tim [Vehma International Of America, Inc., Troy, MI (United States)

    2015-12-29

    The intent of the Multi-Material Lightweight Vehicle (“MMLV”) was to assess the feasibility of achieving a significant level of vehicle mass reduction, enabling engine downsizing resulting in a tangible fuel reduction and environmental benefit. The MMLV project included the development of two (2) lightweight vehicle designs, referred to as Mach-I and Mach-II MMLV variants, based on a 2013 Ford production C/D segment production vehicle (Fusion). Weight comparison, life cycle assessment and limited full vehicle testing are included in the project scope. The Mach-I vehicle variant was comprised of materials and processes that are commercially available or previously demonstrated. The 363 kg mass reduction associated with the Mach-I design enabled use of a one-liter, three-cylinder, gasoline turbocharged direct injection engine, maintaining the performance and utility of the baseline vehicle. The full MMLV project produced seven (7) MMLV Mach-I “concept vehicles” which were used for testing and evaluation. The full vehicle tests confirmed that MMLV Mach-I concept vehicle performed approximately equivalent to the baseline 2013 Ford Fusion vehicle thereby validating the design of the multi material lightweight vehicle design. The results of the Life Cycle Assessment, conducted by third party consultant, indicated that if the MMLV Mach-I design was built and operated in North America for 250,000 km (155,343 miles) it would produce significant environmental and fuel economy benefits including a 16% reduction in Global Warming Potential (GWP) and 16% reduction in Total Primary Energy (TPE). The LCA calculations estimated the combined fuel economy of 34 mpg (6.9 l/100 km) associated with the MMLV Mach-I Design compared to 28 mpg (8.4 l/100 km) for the 2013 Ford Fusion.

  12. Characterization of a backfill candidate material, IBECO-RWC-BF Baclo Project - Phase 3 Laboratory tests

    Energy Technology Data Exchange (ETDEWEB)

    Johannesson, Lars-Erik; Sanden, Torbjoern; Dueck, Ann; Ohlsson, Lars (Clay Technology AB, Lund (Sweden))

    2010-01-15

    A backfill candidate material, IBECO-RWC-BF, which origin from Milos, Greece, has been investigated. The material was delivered both as granules and as pellets. The investigation described in this report aimed to characterize the material and evaluate if it can be used in a future repository. The following investigations have been done and are presented in this report: 1. Standard laboratory tests. Water content, liquid limit and swelling potential are examples on standard tests that have been performed. 2. Block manufacturing. The block compaction properties of the material have been determined. A first test was performed in laboratory but also tests in large scale have been performed. After finishing the test phase, 60 tons of blocks were manufactured at Hoeganaes Bjuf AB. The blocks will be used in large scale laboratory tests at Aespoe HRL. 3. Mechanical parameters. The compressibility of the material was investigated with oedometer tests (four tests) where the load was applied in steps after saturation. The evaluated oedometer modulus varied between 34.50 MPa. Tests were made to evaluate the elastic parameters of the material (E, nu). Altogether three tests were made on specimens with dry densities of about 1,710 kg/m3. The evaluated E-modulus and Poisson's ratio varied between 231-263 MPa and 0.16-0.19 respectively. The strength of the material, both the compressive strength and the tensile strength were measured on specimens compacted to different dry densities. The test results yielded a relation between density and the two types of strength. Furthermore, tests have been made in order to determine the compressibility of the unsaturated filling of pellets. Two tests were made where the pellets were loosely filled in a Proctor cylinder and then compressed at a constant rate of strain during continuously measurement of the applied load. 4. Swelling pressure and hydraulic conductivity. There is, as expected, a very clear influence of the dry density on the

  13. Engineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 2, Design data

    International Nuclear Information System (INIS)

    Konynenburg, R.A.; McCright, R.D.; Roy, A.K.; Jones, D.A.

    1995-08-01

    This is Volume 2 of the Engineered Materials Characterization Report which presents the design data for candidate materials needed in fabricating different components for both large and medium multi-purpose canister (MPC) disposal containers, waste packages for containing uncanistered spent fuel (UCF), and defense high-level waste (HLW) glass disposal containers. The UCF waste package consists of a disposal container with a basket therein. It is assumed that the waste packages will incorporate all-metallic multibarrier disposal containers to accommodate medium and large MPCs, ULCF, and HLW glass canisters. Unless otherwise specified, the disposal container designs incorporate an outer corrosion-allowance metal barrier over an inner corrosion-resistant metal barrier. The corrosion-allowance barrier, which will be thicker than the inner corrosion-resistant barrier, is designed to undergo corrosion-induced degradation at a very low rate, thus providing the inner barrier protection from the near-field environment for a prolonged service period

  14. Launch vehicle flight control augmentation using smart materials and advanced composites (CDDF Project 93-05)

    Science.gov (United States)

    Barret, C.

    1995-01-01

    The Marshall Space Flight Center has a rich heritage of launch vehicles that have used aerodynamic surfaces for flight stability such as the Saturn vehicles and flight control such as on the Redstone. Recently, due to aft center-of-gravity locations on launch vehicles currently being studied, the need has arisen for the vehicle control augmentation that is provided by these flight controls. Aerodynamic flight control can also reduce engine gimbaling requirements, provide actuator failure protection, enhance crew safety, and increase vehicle reliability, and payload capability. In the Saturn era, NASA went to the Moon with 300 sq ft of aerodynamic surfaces on the Saturn V. Since those days, the wealth of smart materials and advanced composites that have been developed allow for the design of very lightweight, strong, and innovative launch vehicle flight control surfaces. This paper presents an overview of the advanced composites and smart materials that are directly applicable to launch vehicle control surfaces.

  15. Inventory and characteristics of current and projected low-level radioactive materials and waste in the United States

    International Nuclear Information System (INIS)

    Bisaria, A.; Bugos, R.G.; Pope, R.B.; Salmon, R.; Storch, S.N.; Lester, P.B.

    1994-01-01

    The Integrated Data Base (IDB), under US Department of Energy (DOE) funding and guidance, provides an annual update of compiled data on current and projected inventories and characteristics of DOE and commercially owned radioactive wastes. The data base addresses also the inventories of DOE and commercial spent fuel. These data are derived from reliable information from government sources, open literature, technical reports, and direct contacts. The radioactive materials considered are spent nuclear fuel, high-level waste (HLW), transuranic (TRU) waste, low-level waste (LLW), commercial uranium mill tailings, environmental restoration wastes, and mixed-LLW. This paper primarily focuses on LLW inventory and characterization

  16. Bill project authorizing the approval of the amendment to the Convention on the physical protection of nuclear materials

    International Nuclear Information System (INIS)

    Juppe, Alain; Fillon, Francois

    2011-01-01

    This document deals with the amendment to the Convention on the Physical Protection of Nuclear Materials which has been adopted in July 2005. This amendment notably extended the Convention's scope, objectives, relation with other international instruments and content (regarding cooperation, sanctions, and so on). After the text of this amendment, this document contains the bill project which reports an impact study (estimated economic, financial, environmental, and legal consequences of the amendment implementation), comments the penal and criminal cooperation defined in the Convention. A table indicates the impact of the amendment's articles on the French law

  17. Groundwater and vadose Zone Integration Project Nuclear Material Mass Flow and Accountability on the Hanford Site

    International Nuclear Information System (INIS)

    GRASHER, A.A.

    2001-01-01

    The purpose of this report is to provide a discussion of the accountable inventory of Hanford Site nuclear material (NM) over the operating period. This report does not provide judgments on impacts to the Hanford Site environs by the reported waste streams or inventory. The focus of this report is on the processes, facilities, and process streams that constituted the flow primarily of plutonium and uranium through the Hanford Site. The material balance reports (MBRS) are the basis of the NM accountable inventory maintained by each of the various contractors used by the U.S. Department of Energy (DOE) and its predecessors to operate the Hanford Site. The inventory was tracked in terms of a starting inventory, receipts, transfers, and ending inventory. The various components of the inventory are discussed as well as the uncertainty in the measurement values used to establish plant inventory and material transfers. The accountable NM inventory does not report all the NM on the Hanford Site and this difference is discussed relative to some representative nuclides. The composition and location of the current accountable inventory are provided, as well as the latest approved set (2000) of flow diagrams of the proposed disposition of the excess accountable NM inventory listed on the Idaho National Engineering and Environmental Laboratory (INEEL) web page

  18. Silicon materials task of the Low Cost Solar Array Project: Effect of impurities and processing on silicon solar cells

    Science.gov (United States)

    Hopkins, R. H.; Davis, J. R.; Rohatgi, A.; Hanes, M. H.; Rai-Choudhury, P.; Mollenkopf, H. C.

    1982-01-01

    The effects of impurities and processing on the characteristics of silicon and terrestrial silicon solar cells were defined in order to develop cost benefit relationships for the use of cheaper, less pure solar grades of silicon. The amount of concentrations of commonly encountered impurities that can be tolerated in typical p or n base solar cells was established, then a preliminary analytical model from which the cell performance could be projected depending on the kinds and amounts of contaminants in the silicon base material was developed. The impurity data base was expanded to include construction materials, and the impurity performace model was refined to account for additional effects such as base resistivity, grain boundary interactions, thermal processing, synergic behavior, and nonuniform impurity distributions. A preliminary assessment of long term (aging) behavior of impurities was also undertaken.

  19. Some Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository Study (The Yucca Mountain Project)

    Energy Technology Data Exchange (ETDEWEB)

    F. Hua; P. Pasupathi; N. Brown; K. Mon

    2005-09-19

    The safe disposal of radioactive waste requires that the waste be isolated from the environment until radioactive decay has reduced its toxicity to innocuous levels for plants, animals, and humans. All of the countries currently studying the options for disposing of high-level nuclear waste (HLW) have selected deep geologic formations to be the primary barrier for accomplishing this isolation. In U.S.A., the Nuclear Waste Policy Act of 1982 (as amended in 1987) designated Yucca Mountain in Nevada as the potential site to be characterized for high-level nuclear waste (HLW) disposal. Long-term containment of waste and subsequent slow release of radionuclides into the geosphere will rely on a system of natural and engineered barriers including a robust waste containment design. The waste package design consists of a highly corrosion resistant Ni-based Alloy 22 cylindrical barrier surrounding a Type 316 stainless steel inner structural vessel. The waste package is covered by a mailbox-shaped drip shield composed primarily of Ti Grade 7 with Ti Grade 24 structural support members. The U.S. Yucca Mountain Project has been studying and modeling the degradation issues of the relevant materials for some 20 years. This paper reviews the state-of-the-art understanding of the degradation processes based on the past 20 years studies on Yucca Mountain Project (YMP) materials degradation issues with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the 10,000 years regulatory period. This paper provides an overview of the current understanding of the likely degradation behavior of the waste package and drip shield in the repository after the permanent closure of the facility. The degradation scenario discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking and hydrogen induced

  20. Engineering feasibility for the fabrication and emplacement of cementitious repository materials: results from the EC-ESDRED project

    International Nuclear Information System (INIS)

    Alonso, Maria Cruz; Garcia-Sineriz, Jose Luis

    2012-01-01

    Maria Cruz Alonso of the Spanish National Research Council gave a presentation that summarised relevant findings on cementitious materials from the EC ESDRED (Engineering Studies and Demonstration of Repository Designs) Project. Concrete will be used for different purposes during the construction of geologic repositories for radioactive waste. These purposes include grouting, tunnel and drift lining, and tunnel plugging and sealing. Although some of the concrete may be removed before repository closure, a significant amount of concrete will remain in the repository. An important concern regarding the use of cementitious materials in geologic repositories for HLW and spent fuel is their interaction with the bentonite buffer, backfill material, and the host rock close to the repository near-field. For this reason, the ESDRED project has developed a low-pH concrete formulation as an alternative to standard ordinary Portland cement (OPC) concrete formulations with the aim of reducing the interaction of the cementitious materials with the near-field components. The main functional requirement required in the development of the low-pH material was a pore fluid pH < 11, which is considered acceptable for preventing or reducing the alteration of the bentonite EBS. Other functional requirements considered in the development of the low-pH concrete were: - Hydraulic conductivity. - Mechanical properties. - Durability. - Workability and pumpability. - Slumping. - Peak hydration temperature. - Thermal conductivity. - Use of organic components. - Use of other products. The development of the low-pH concrete involved laboratory work, as well as field testing at the Aespoe underground research laboratory (URL) in Sweden, and in the Grimsel URL and at the Hagerbach site in Switzerland. The ESDRED project demonstrated that low-pH cements can be formulated and used for production of concrete plugs and rock support. OPC can be used as the cement included in low-pH blends, but at least

  1. Some Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository Study (The Yucca Mountain Project)

    International Nuclear Information System (INIS)

    Hua, F.; Pasupathi, P.; Brown, N.; Mon, K.

    2005-01-01

    The safe disposal of radioactive waste requires that the waste be isolated from the environment until radioactive decay has reduced its toxicity to innocuous levels for plants, animals, and humans. All of the countries currently studying the options for disposing of high-level nuclear waste (HLW) have selected deep geologic formations to be the primary barrier for accomplishing this isolation. In U.S.A., the Nuclear Waste Policy Act of 1982 (as amended in 1987) designated Yucca Mountain in Nevada as the potential site to be characterized for high-level nuclear waste (HLW) disposal. Long-term containment of waste and subsequent slow release of radionuclides into the geosphere will rely on a system of natural and engineered barriers including a robust waste containment design. The waste package design consists of a highly corrosion resistant Ni-based Alloy 22 cylindrical barrier surrounding a Type 316 stainless steel inner structural vessel. The waste package is covered by a mailbox-shaped drip shield composed primarily of Ti Grade 7 with Ti Grade 24 structural support members. The U.S. Yucca Mountain Project has been studying and modeling the degradation issues of the relevant materials for some 20 years. This paper reviews the state-of-the-art understanding of the degradation processes based on the past 20 years studies on Yucca Mountain Project (YMP) materials degradation issues with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the 10,000 years regulatory period. This paper provides an overview of the current understanding of the likely degradation behavior of the waste package and drip shield in the repository after the permanent closure of the facility. The degradation scenario discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking and hydrogen induced

  2. [The highest proportion of tobacco materials in the blend analysis using PPF projection method for the near-infrared spectrum and Monte Carlo method].

    Science.gov (United States)

    Mi, Jin-Rui; Ma, Xiang; Zhang, Ya-Juan; Wang, Yi; Wen, Ya-Dong; Zhao, Long-Lian; Li, Jun-Hui; Zhang, Lu-Da

    2011-04-01

    The present paper builds a model based on Monte Carlo method in the projection of the blending tobacco. This model is made up of two parts: the projecting points of tobacco materials, whose coordinates are calculated by means of the PPF (projection based on principal component and Fisher criterion) projection method for the tobacco near-infrared spectrum; and the point of tobacco blend, which is produced by linear additive to the projecting point coordinates of tobacco materials. In order to analyze the projection points deviation from initial state levels, Monte Carlo method is introduced to simulate the differences and changes of raw material projection. The results indicate that there are two major factors affecting the relative deviation: the highest proportion of tobacco materials in the blend, which is too high to make the deviation under control; and the quantity of materials, which is so small to control the deviation. The conclusion is close to the principle of actual formulating designing, particularly, the more in the quantity while the lower in proportion of each. Finally the paper figures out the upper limit of the proportions in the different quantity of materials by theory. It also has important reference value for other agricultural products blend.

  3. Sealing properties of cement-based grout materials. Final report on the Rock sealing project

    International Nuclear Information System (INIS)

    Onofrei, M.; Gray, Malcolm; Shenton, B.; Walker, Brad; Pusch, R.; Boergesson, L.; Karnland, O.

    1992-10-01

    This report presents the results of laboratory studies of material properties. A number of different high performance grouts were investigated. The laboratory studies focused on mixtures of sulphate resistant portland cement, silica fume, superplasticizer and water. The ability of the thin films to self seal was confirmed. The surface reactions were studied in specimens of hardened grouts. The leach rates were found to vary with grout and water composition and with temperature. The short-term hydraulic and strength or properties of the hardened grout were determined. These properties were determined for the grouts both in-bulk and as thin-films. The hydraulic conductivities of the bulk, hardened material were found to be less than 10 -14 m/s. The hydraulic conductivities of thin films were found to be less than 10 -11 m/s. Broken, the hydraulic conductivity of the thin films could be increased to 10 -7 m/s. Examination of the leached grout specimens revealed a trend for the pore sizes to decrease with time. The propensity for fractured grouts to self seal was also observed in tests in which the hydraulic conductivity of recompacted mechanically disrupted, granulated grouts was determined. These tests showed that the hydraulic conductivity decreased rapidly with time. The decreases were associated with decreases in mean pore size. In view of the very low hydraulic conductivity it is likely that surface leaching at the grout/groundwater interface will be that major process by which bulk high-performance grouts may degrade. With the completion of the laboratory, in situ and modelling studies it appears that high-performance cement based grouts can be considered as viable materials for some repository sealing applications. Some of the uncertainties that remain are identified in this report. (54 refs.)

  4. Influence of projection angle in sandblasting cleaning on detrictic stone materials in Architectural Heritage

    Directory of Open Access Journals (Sweden)

    Iglesias-Campos, M. A.

    2014-05-01

    Full Text Available In this research, the influence of the angle in abrasive blasting cleaning is studied on Montjuïc sandstone with black crust. After analyzing the properties of the soiling and the material, and their possible influence on the treatment, different cleaning tests were made at four different angles, keeping the complementary parameters constant. Taking the restorer’s perspective as a starting point, and in order to fulfill the practical requirements of an intervention —time and cost reduction—, tests were evaluated with USB digital microscope, stereomicroscope with 3D visualization and measurement, and colorimeter. From the results it is established that angles close to 75° minimize surface alteration, reducing differential erosion in the binding phases of detritic materials usually caused by this treatment.En este trabajo se estudia la influencia del ángulo de la proyección de abrasivos en la limpieza de una arenisca de Montjuïc con costra negra. Tras analizar las propiedades del material, de la suciedad y su posible influencia en el tratamiento, se realizan diferentes catas de limpieza con cuatro ángulos distintos manteniendo constantes el resto de parámetros de la proyección. Partiendo de la visión del conservador-restaurador y de un carácter práctico según las necesidades reales de una intervención —reducción de tiempos y costes—, los ensayos se evalúan con microscopio digital USB, microscopio estereoscópico con visualización y medición en 3D y colorímetro. De los resultados se puede determinar que ángulos cercanos a 75° minimizan la alteración de la superficie al reducir la erosión diferencial de las fases de unión que el tratamiento normalmente provoca en los materiales detríticos.

  5. Problems studied within the state research project New Methods of Nondestructive Materials Testing Using Ionizing Radiation

    International Nuclear Information System (INIS)

    Mysak, F.; Strba, J.

    1979-01-01

    A state research project is described divided into ten subprojects, viz.: New trends of ionizing radiation detection using television technology in nondestructive testing; the application of accelerators for thick-walled product testing; the atlas of butt welds of medium thicknesses; the application of radioanalytical methods in testing the wear of gearboxes and other components of instrument parts; multielemental analyses of combustion engine wear using radionuclides; the application of radioisotope methods in research into wear of antifriction bearings of trucks and railway cars; the application of radionuclides in assessing corrosion resistance of steels and corrosion protection systems; the application of radionuclide methods in improving the quality of high-grade steel production; the selection and testing of radionuclide instruments for building production control, intermediate and acceptance checks; and radioisotope methods for building machine and equipment control. (M.S.)

  6. Materials

    CSIR Research Space (South Africa)

    Van Wyk, Llewellyn V

    2009-02-01

    Full Text Available . It is generally included as part of a structurally insulated panel (SIP) where the foam is sandwiched between external skins of steel, wood or cement. Cement composites Cement bonded composites are an important class of building materials. These products... for their stone buildings, including the Egyptians, Aztecs and Inca’s. As stone is a very dense material it requires intensive heating to become warm. Rocks were generally stacked dry but mud, and later cement, can be used as a mortar to hold the rocks...

  7. E-Area Vault Concrete Material Property And Vault Durability/Degradation Projection Recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Phifer, M. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2014-03-11

    Subsequent to the 2008 E-Area Low-Level Waste Facility (ELLWF) Performance Assessment (PA) (WSRC 2008), two additional E-Area vault concrete property testing programs have been conducted (Dixon and Phifer 2010 and SIMCO 2011a) and two additional E-Area vault concrete durability modeling projections have been made (Langton 2009 and SIMCO 2012). All the information/data from these reports has been evaluated and consolidated herein by the Savannah River National Laboratory (SRNL) at the request of Solid Waste Management (SWM) to produce E-Area vault concrete hydraulic and physical property data and vault durability/degradation projection recommendations that are adequately justified for use within associated Special Analyses (SAs) and future PA updates. The Low Activity Waste (LAW) and Intermediate Level (IL) Vaults structural degradation predictions produced by Carey 2006 and Peregoy 2006, respectively, which were used as the basis for the 2008 ELLWF PA, remain valid based upon the results of the E-Area vault concrete durability simulations reported by Langton 2009 and those reported by SIMCO 2012. Therefore revised structural degradation predictions are not required so long as the mean thickness of the closure cap overlying the vaults is no greater than that assumed within Carey 2006 and Peregoy 2006. For the LAW Vault structural degradation prediction (Carey 2006), the mean thickness of the overlying closure cap was taken as nine feet. For the IL Vault structural degradation prediction (Peregoy 2006), the mean thickness of the overlying closure cap was taken as eight feet. The mean closure cap thicknesses as described here for both E-Area Vaults will be included as a key input and assumption (I&A) in the next revision to the closure plan for the ELLWF (Phifer et al. 2009). In addition, it has been identified as new input to the PA model to be assessed in the ongoing update to the new PA Information UDQE (Flach 2013). Once the UDQE is approved, the SWM Key I

  8. E-Area Vault Concrete Material Property And Vault Durability/Degradation Projection Recommendations

    International Nuclear Information System (INIS)

    Phifer, M. A.

    2014-01-01

    Subsequent to the 2008 E-Area Low-Level Waste Facility (ELLWF) Performance Assessment (PA) (WSRC 2008), two additional E-Area vault concrete property testing programs have been conducted (Dixon and Phifer 2010 and SIMCO 2011a) and two additional E-Area vault concrete durability modeling projections have been made (Langton 2009 and SIMCO 2012). All the information/data from these reports has been evaluated and consolidated herein by the Savannah River National Laboratory (SRNL) at the request of Solid Waste Management (SWM) to produce E-Area vault concrete hydraulic and physical property data and vault durability/degradation projection recommendations that are adequately justified for use within associated Special Analyses (SAs) and future PA updates. The Low Activity Waste (LAW) and Intermediate Level (IL) Vaults structural degradation predictions produced by Carey 2006 and Peregoy 2006, respectively, which were used as the basis for the 2008 ELLWF PA, remain valid based upon the results of the E-Area vault concrete durability simulations reported by Langton 2009 and those reported by SIMCO 2012. Therefore revised structural degradation predictions are not required so long as the mean thickness of the closure cap overlying the vaults is no greater than that assumed within Carey 2006 and Peregoy 2006. For the LAW Vault structural degradation prediction (Carey 2006), the mean thickness of the overlying closure cap was taken as nine feet. For the IL Vault structural degradation prediction (Peregoy 2006), the mean thickness of the overlying closure cap was taken as eight feet. The mean closure cap thicknesses as described here for both E-Area Vaults will be included as a key input and assumption (I and A) in the next revision to the closure plan for the ELLWF (Phifer et al. 2009). In addition, it has been identified as new input to the PA model to be assessed in the ongoing update to the new PA Information UDQE (Flach 2013). Once the UDQE is approved, the SWM Key I and

  9. Overview of hydrothermal testing of waste-package barrier materials at the Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    1982-01-01

    The current Waste Package Department (WPD) hydrothermal testing program for the Basalt Waste Isolation Project (BWIP) has followed a systematic approach for the testing of waste-barrier-basalt interactions based on sequential penetration of barriers by intruding groundwaters. Present test activities in the WPD program have focused on determining radionuclide solubility limits (or steady-state conditions) of simulated waste forms and the long-term stability of waste package barriers under site-specific hydrothermal conditions. The resulting data on solution compositions and solid alteration products have been used to evaluate waste form degradation under conditions specific to a nuclear waste repository located in basalt (NWRB). Isothermal, time-invariant compositional data on sampled solutions have been coupled with realistic hydrologic flow data for near-field and far-field modeling for the calculation of meaningful radionuclide release rates. Radionuclides that are not strongly sorbed or precipitated from solution and that, therefore, may require special attention to ensure their isolation within the waste package have been identified. Taken together, these hydrothermal test data have been used to establish design requirements for waste packages located in basalt

  10. Evolution of and projections for automated composite material placement equipment in the aerospace industry

    Science.gov (United States)

    McCarville, Douglas A.

    2009-12-01

    As the commercial aircraft industry attempts to improve airplane fuel efficiency by shifting from aluminum to composites (reinforced plastics), there is a concern that composite processing equipment is not mature enough to meet increasing demand and that delivery delays and loss of high tech jobs could result. The research questions focused on the evolution of composite placement machines, improvement of machine functionality by equipment vendors, and the probability of new inventions helping to avoid production shortfalls. An extensive review of the literature found no studies that addressed these issues. Since the early twentieth century, exploratory case study of pivotal technological advances has been an accepted means of performing historic analysis and furthering understanding of rapidly changing marketplaces and industries. This qualitative case study investigated evolution of automated placement equipment by (a) codifying and mapping patent data (e.g., claims and functionality descriptions), (b) triangulating archival data (i.e., trade literature, vender Web sites, and scholarly texts), and (c) interviewing expert witnesses. An industry-level sensitivity model developed by the author showed that expanding the vendor base and increasing the number of performance enhancing inventions will most likely allow the industry to make the transition from aluminum to composites without schedule delays. This study will promote social change by (a) advancing individual and community knowledge (e.g., teaching modules for students, practitioners, and professional society members) and (b) providing an empirical model that will help in the understanding and projection of next generation composite processing equipment demand and productivity output.

  11. Ergonomic approaches to designing educational materials for immersive multi-projection system

    Science.gov (United States)

    Shibata, Takashi; Lee, JaeLin; Inoue, Tetsuri

    2014-02-01

    Rapid advances in computer and display technologies have made it possible to present high quality virtual reality (VR) environment. To use such virtual environments effectively, research should be performed into how users perceive and react to virtual environment in view of particular human factors. We created a VR simulation of sea fish for science education, and we conducted an experiment to examine how observers perceive the size and depth of an object within their reach and evaluated their visual fatigue. We chose a multi-projection system for presenting the educational VR simulation, because this system can provide actual-size objects and produce stereo images located close to the observer. The results of the experiment show that estimation of size and depth was relatively accurate when subjects used physical actions to assess them. Presenting images within the observer's reach is suggested to be useful for education in VR environment. Evaluation of visual fatigue shows that the level of symptoms from viewing stereo images with a large disparity in VR environment was low in a short time.

  12. A research project to develop and evaluate a technical education component on materials technology for orientation to space-age technology

    Science.gov (United States)

    Jacobs, J. A.

    1976-01-01

    A project was initiated to develop, implement, and evaluate a prototype component for self-pacing, individualized instruction on basic materials science. Results of this project indicate that systematically developed, self-paced instruction provides an effective means for orienting nontraditional college students and secondary students, especially minorities, to both engineering technology and basic materials science. In addition, students using such a system gain greater chances for mastering subject matter than with conventional modes of instruction.

  13. OECD MCCI project enhancing instrumentation for reactor materials experiments, Rev. 0 September 3, 2002

    International Nuclear Information System (INIS)

    Lomperski, S.; Basu, S.

    2011-01-01

    Reactor safety experiments for studying the reactions of a molten core (corium) with water and/or concrete involve materials at extremely high temperature. Such high temperature severely restricts the types of sensors that can be employed to measure characteristics of the corium itself. Yet there is great interest in improving instrumentation so that the state of the melt can be established with more precision. In particular, it would be beneficial to increase both the upper range limit and accuracy of temperature measurements. The poor durability of thermocouples at high temperature is also an important issue. For experiments involving a water-quenched melt, direct measurements of the growth rate of the crust separating the melt and water would be of great interest. This is a key element in determining the nature of heat transfer between the melt and coolant. Despite its importance, no one has been able to directly measure the crust thickness during such tests. This paper considers three specialized sensors that could be introduced to enhance melt characterization: (1) A commercially fabricated, single point infrared temperature measurement with the footprint of a thermowell. A lens assembly and fiber optic cable linked to a receiver and amplifier measures the temperature at the base of a tungsten thermowell. The upper range limit is 3000 C and accuracy is ±0.25% of the reading. (2) In-house development of an ultrasonic temperature sensor that would provide multipoint measurements at temperatures up to ∼3000 C. The sensors are constructed from tungsten rods and have a high temperature durability that is superior to that of thermocouples. (3) In-house development of an ultrasonic probe to measure the growth rate of the corium crust. This ultrasonic sensor would include a tungsten waveguide that transmits ultrasonic pulses up through the corium melt towards the crust and detects reflections from the melt/crust interface. A measurement of the echo time delay would

  14. Construction of a naturally occurring radioactive material project in the BeAAT hazardous waste facilities.

    Science.gov (United States)

    Abuahmad, H

    2015-06-01

    This paper does not necessarily reflect the views of the International Commission on Radiological Protection. Naturally occurring radioactive material (NORM) is produced during exploration and production operations of subsidiaries of the Abu Dhabi National Oil Company (ADNOC) in the United Arab Emirates, and accumulates in drilling tubulars, plant equipment, and components. These NORM hazardous wastes need to be managed in such a way that they do not damage human health and the environment. The primary radionuclides of concern in the oil and gas industries are radium-226 and radium-228. These radioisotopes are the decay products of uranium and thorium isotopes that are present in subsurface formations from which hydrocarbons are produced. While uranium and thorium are largely immobile, radium is slightly more soluble and may become mobilised in the fluid phases of the formation (International Association of Oil & Gas Producers, 2008). In order to treat and dispose of NORM waste products safely, ADNOC's subsidiary 'TAKREER' is developing a new facility, on behalf of all ADNOC subsidiaries, within the existing Central Environmental Protection Facilities (BeAAT) in Ruwais city. The NORM plant is envisaged to treat, handle, and dispose of NORM waste in the forms of scale, sludge, and contaminated equipment. The NORM treatment facility will cover activities such as decontamination, volume reduction, NORM handling, and concrete immobilisation of NORM waste into packages for designated landfilling. © The International Society for Prosthetics and Orthotics Reprints and permissions: sagepub.co.uk/journalsPermissions.nav.

  15. The raw material and waste activity balance in the projected nuclear power of Russia

    International Nuclear Information System (INIS)

    Adamov, E.O.; Ganev, I.Kh.; Lopatkin, A.V.; Muratov, V.G.; Orlov, V.V.

    1997-01-01

    Under discussion is the management of long-lived high-level wastes in the nuclear energy sector of Russia, the development of which on a large scale in the next century is motivated by the need for arresting the increasing consumption of fossil fuels. The prerequisites for the nuclear power growth consists in the design of naturally safe reactors and development of a transmutational nuclear fuel cycle (NFC) technology. The choice of operations in such a cycle and of their quantitative characteristics, is aimed at minimizing the wastes to approach the radiation balance with the natural uranium extracted and put to use. The paper discusses the way the approximation to the balance between the raw material and waste activity is influenced by introduction of the transmutational NFC (in case 2), inclusion of transmutation reactors into the energy mix (case 1), partial disposal of actinide wastes into outer space, and by recycling of protactinium (case 3). It is shown that such a balance can be sustained for a considerable time in cases 2 and 3 or throughout the operation stage of the future nuclear power (case 1). (orig.)

  16. The OSMATER project: promotion of stone materials from the Verbano-Cusio-Ossola region (Italy) and the Canton Ticino (Switzerland).

    Science.gov (United States)

    Cavallo, Alessandro; Antonella Dino, Giovanna

    2013-04-01

    The OSMATER (sub-Alpine Observatory Materials Territory Restoration) project, funded by the Piedmont Region (Italy) and the European Community, involved four Italian scientific bodies (Polytechnic of Turin, University of Turin, University of Milan-Bicocca, University of Bologna) and Switzerland (SUPSI). The aim was to investigate the present and historical quarrying and processing activities in the cross-border area between the Ossola Valley (Italy) and the Canton Ticino (Switzerland), and the use of dimension stones in local and national architecture. These materials are in many ways a "unique case", for their abundance and lithological variety. In the past, their extraction, processing and application characterized in a decisive way the architectural and constructive culture, both in terms of prestigious architecture and civil buildings, establishing a relationship between "stones and culture", "territory and its resources". In recent years, many of these traditions are losing importance and interest: this results in a loss of knowledge and historical memory, due mainly to the drastic changes in the market. The loss of this knowledge is likely to become irreversible in the short term, with the disappearance of people and social groups depositary of tradition. We can deduce that the creation of an "observatory", like OSMATER, is desirable and essential indeed, if we want to preserve the historical memory of the stone industry of an entire production area. The OSMATER project aimed the knowledge, recovery and enhancement of the architectural and cultural heritage of the cross-border area, through the census and classification of rocks, quarries (both active and historical - since Roman age), monuments and construction techniques typical of the sub-Alpine region, in order to create a documentation centre through a dedicated website. The first phase of the project was devoted to the identification of architectural works built with stone materials, with particular

  17. Projected environmental impacts of radioactive material transportation to the first US repository site

    International Nuclear Information System (INIS)

    Neuhauser, K.S.; Cashwell, J.W.; Reardon, P.C.; Ostmeyer, R.M.; McNair, G.W.

    1986-01-01

    This paper discusses the relative national environmental impacts of transporting nuclear wastes to each of the nine candidate repository sites in the United States. Several of the potential sites are closely clustered and, for the purpose of distance and routing calculations, are treated as a single location. These are: Cypress Creek Dome and Richton Dome in Mississippi (Gulf Interior Region), Deaf Smith County and Swisher County sites in Texas (Permian Basin), and Davis Canyon and Lavender Canyon site in Utah (Paradox Basin). The remaining sites are: Vacherie Dome, Louisiana; Yucca Mountain, Nevada; and Hanford Reservation, Washington. For compatibility with both the repository system authorized by the NWPA and with the MRS option, two separate scenarios were analyzed. In belief, they are (1) shipment of spent fuel and high-level wastes (HLW) directly from waste generators to a repository (Reference Case) and (2) shipment of spent fuel to a Monitored Retrievable Storage (MRS) facility and then to a repository. Between 17 and 38 truck accident fatalities, between 1.4 and 7.7 rail accident fatalities, and between 0.22 and 12 radiological health effects can be expected to occur as a result of radioactive material transportation during the 26-year operating period of the first repository. During the same period in the United States, about 65,000 total deaths from truck accidents and about 32,000 total deaths from rail accidents would occur; also an estimated 58,300 cancer fatalities are predicted to occur in the United States during a 26-year period from exposure to background radiation alone (not including medical and other manmade sources). The risks reported here are upper limits and are small by comparison with the ''natural background'' of risks of the same type. 3 refs., 6 tabs

  18. Proceedings of BARC golden jubilee year DAE-BRNS topical symposium on role of analytical chemistry in nuclear technology

    International Nuclear Information System (INIS)

    Swain, K.K.; Venkataramani, B.

    2007-01-01

    Among the various disciplines in Chemistry, Analytical Chemistry is unique, because it is an integral part of every aspect of technology- product and process development and deployment. In Nuclear Industry, the quality assurance criteria are very stringent. And truly, Analytical Chemistry has continued to play a pivotal role in the entire nuclear fuel cycle, since the beginning of the Indian Atomic Energy Programme. The conference covers invited talk, nuclear materials, reactor systems, thorium technology, alternate energy sources, biology, agriculture and environment, water technology, isotope, radiation and laser technology, development of analytical instruments, and reference materials and inter-comparison exercises. Papers relevant to INIS are indexed separately. (author)

  19. UKAEA fast reactor project research and development programme on fuel element cladding and sub-assembly wrapper materials

    International Nuclear Information System (INIS)

    Harries, D.R.

    1977-01-01

    Research and development work on fuel element component (cladding, subassembly wrappers, etc.) materials for the U.K. sodium cooled fast reactor programme has been conducted at the United Kingdom Atomic Energy Authority (UKAEA) establishments at Dounreay, Harwell, Risley, and Springfields during the past fifteen years or so. This work has formed an integral part of, and has been co-ordinated by, the UKAEA Fast Reactor Project and has involved close liaison with the Nuclear Power Company (NPC) and the Central Electricity Generating Board (CEGB). The research and development were initially related to the Prototype Fast Reactor (PFR) but the scope has now been extended to cover the first Civil Fast Reactor (CFR1), which has recently been re-designated the Civil Demonstration Fast Reactor (CDFR). The paper outlines the present status of the development of sodium cooled fast reactors in the U.K. and proceeds to summarize the principal PFR and CDFR core and fuel element parameters which have determined the planning and direction of the fuel element materials programme. The current position on the fuel element cladding and wrapper research and development programme is reviewed, and the facilities and future irradiation programme to be carried out in PFR are described

  20. Degradation mode survey candidate titanium-base alloys for Yucca Mountain project waste package materials. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Gdowski, G.E.

    1997-12-01

    The Yucca Mountain Site Characterization Project (YMP) is evaluating materials from which to fabricate high-level nuclear waste containers (hereafter called waste packages) for the potential repository at Yucca Mountain, Nevada. Because of their very good corrosion resistance in aqueous environments titanium alloys are considered for container materials. Consideration of titanium alloys is understandable since about one-third (in 1978) of all titanium produced is used in applications where corrosion resistance is of primary importance. Consequently, there is a considerable amount of data which demonstrates that titanium alloys, in general, but particularly the commercial purity and dilute {alpha} grades, are highly corrosion resistant. This report will discuss the corrosion characteristics of Ti Gr 2, 7, 12, and 16. The more highly alloyed titanium alloys which were developed by adding a small Pd content to higher strength Ti alloys in order to give them better corrosion resistance will not be considered in this report. These alloys are all two phase ({alpha} and {beta}) alloys. The palladium addition while making these alloys more corrosion resistant does not give them the corrosion resistance of the single phase {alpha} and near-{alpha} (Ti Gr 12) alloys.

  1. Comportamiento de las discapacidades en los adultos mayores. Consejo Popular Hermanos Barcón Behavior of the disabilities in the elderly. "Hermanos Barcon" Popular Council

    Directory of Open Access Journals (Sweden)

    Marvelia Díaz Calzada

    2012-02-01

    Full Text Available Se realizó una investigación descriptiva y transversal en los adultos mayores del Consejo Popular "Hermanos Barcón" durante el período de enero a junio de 2011, con el objetivo de determinar el comportamiento de las discapacidades. El universo lo constituyeron 2011 ancianos y la muestra 200. Se aplicó la encuesta de factores de riesgo de discapacidad. Los resultados se analizaron mediante el cálculo de tasas, frecuencias absolutas y porcentajes. Las discapacidades físicas están muy relacionadas con las secuelas de fracturas de cadera, mientras que las variables psicosociales que más se asocian con esta discapacidad son los niveles escolares bajos y la pérdida de rol social. Las discapacidades mentales prevalecieron en las edades avanzadas, el sexo femenino, la baja escolaridad y la desocupación.A descriptive and cross-sectional study was carried out with the elderly of "Hermanos Barcon" Popular Council, from January to June 2011 aimed at determining the behavior of their disabilities. The target group included 2011 old people and the sample 200. The survey for the disability risk factor was applied. Results were analyzed by means of rate calculation, absolute frequencies and percentages. Physical disabilities are close related to the sequelae of hip fractures, whereas low educational levels and lost of social role were the psychosocial variables most associated with this disability. Mental disabilities, female sex, low school degrees and unemployment prevailed in advanced ages.

  2. Development and applications of k0 based NAA and prompt gamma-ray NAA methods at BARC

    International Nuclear Information System (INIS)

    Acharya, R.; Nair, A.G.C.; Sudarshan, K.; Goswami, A.; Reddy, A.V.R.

    2008-01-01

    A summary of k 0 -based R and D work on neutron activation analysis (NAA), internal mono standard NAA (IM-NAA) and prompt gamma-ray NAA (PGNAA) is presented. The k 0 -based NAA was standardized by characterizing irradiation sites of research reactors, validated using reference materials and applied to samples of different origin. Recently IM-NAA method was developed, validated for small and large size samples and applied for the analysis of large size as well as non-standard geometry samples. Studies on PGNAA included characterization of neutron beam, determinations of detection efficiency and prompt k 0 -factors, and analytical applications. (author)

  3. Manpower Development to Support Indian Graduate Training School Program of BARC and its Incorporation in University System

    International Nuclear Information System (INIS)

    Dutta, B.K.

    2014-01-01

    Conclusions: • Nuclear technology is multidisciplinary, knowledge intensive, and its education and training are constrained by unusual measures demanded by the concerns about radiation and nuclear safety, physical protection of nuclear materials and facilities, and safeguards to prevent diversion of nuclear material. • This requires vast faculty resources as also extraordinary and expensive infrastructure for conducting nuclear education making the task of human resource development in nuclear science and technology a challenging one. • The human resource for the nuclear energy programme in India so far has therefore been developed in-house in the DAE. • However, large requirement of manpower to take forward the growing nuclear energy programme in the country can be met only by extending concurrently the reach of the human resource development activity in nuclear science and technology. • The DAE is therefore supporting the university system in India, and integrating the existing training program with the university system. • It may be emphasized that nuclear education, being a means of preservation and transmission of explicit knowledge, is just one component of nuclear knowledge management (NKM). • The NKM also involves creation of mechanisms to preserve and transmit implicit and tacit knowledge

  4. Ecological evaluation of proposed dredged material from Richmond Harbor Deepening Project and the intensive study of the Turning Basin

    Energy Technology Data Exchange (ETDEWEB)

    Pinza, M.R.; Mayhew, H.L.; Karle, L.M.; Kohn, N.P.; White, P.J.; Word, J.Q.; Michaels, L.L. [Battelle/Marine Sciences Lab., Sequim, WA (United States)

    1995-06-01

    Richmond Harbor is on the eastern shoreline of central San Francisco Bay and its access channels and several of the shipping berths are no longer wide or deep enough to accommodate modem deeper-draft vessels. The Water Resources Development Act of 1986 (PL99-662) authorized the US Army Corps of Engineers (USACE), San Francisco District to deepen and widen the navigation channels in Richmond Harbor. Several options for disposal of the material from this dredging project are under consideration by USACE: disposal within San Francisco Bay, at open-ocean disposal sites, or at uplands disposal sites. Purpose of this study was to conduct comprehensive evaluations, including chemical, biological, and bioaccumulation testing of sediments in selected areas of Richmond Harbor. This information was required by the Environmental Protection Agency (EPA) and USACE. Battelle/Marine Sciences Laboratory collected 20 core samples, both 4-in. and 12-in., to a project depth of -40 ft mean lower low water (MLLW) (-38 ft MLLW plus 2 ft of overdepth) using a vibratory-hammer core. These 20 field samples were combined to form five test composites plus an older bay mud (OBM) composite that were analyzed for physical/chemical parameters, biological toxicity, and tissue chemistry. Solid-phase tests were conducted with the amphipod, Rhepoxynius abronius; the clam, Macoma nasuta; and the polychaete worm, Nephtys caecoides. Suspended-particulate-phase (SPP) tests were conducted with the sanddab, Citharichthys stigmaeus; the mysid, Holmesimysis costata; and the bivalve, Mytilus galloprovincialis. Bioaccumulation of contaminants was measured in tissues of Macoma nasuta and Nereis virens. Sediments from one ocean reference sediment, and two in-bay reference sediments, were tested concurrently. Results from analysis of the five test treatments were statistically compared with the reference sediment R-OS in the first five sections of this report.

  5. Effects of polyacrylamide on soil erosion and nutrient losses from substrate material in steep rocky slope stabilization projects.

    Science.gov (United States)

    Chen, Zhang; Chen, Wenlu; Li, Chengjun; Pu, Yanpin; Sun, Haifeng

    2016-06-01

    Erosion of denuded steep rocky slopes causes increasing losses of nitrogen and phosphorus, which is a severe problem in rocky slope protection. Thus, it is important to determine the appropriate materials that can reduce the erodibility and losses of nitrogen and phosphorus of the soil. In this paper, twenty-seven simulated rainfall events were carried out in a greenhouse, in which the substrate material was artificial soil; nine types of anionic polyacrylamide (PAM) were studied, which consisted of three molecular weight (6, 12, and 18 Mg mol(-1)) and three charge density (10, 20, and 30%) formulations in a 3 by 3 factorial design. The results showed that: (1) Polyacrylamide application reduced total nitrogen losses by 35.3% to 50.0% and total phosphorus losses by 34.9% to 48.0% relative to the control group. (2) The losses of total nitrogen and total phosphorus had significant correlation with the molecular weight. Besides, the losses of total phosphorus, particulate-bound phosphorus and inorganic nitrogen (NH4-N) were significantly correlated with their molecular weight and charge density. However, the losses of dissolved organic nitrogen, inorganic nitrogen (NO3-N), dissolved organic phosphorus, inorganic phosphorus (PO4-P) were non-significantly correlated with molecular weight and charge density. (3) Particulate-bound nitrogen and phosphorus were responsible for the losses of nitrogen and phosphorus during runoff events, where particulate-bound nitrogen made up 71.7% to 73.2% of total nitrogen losses, and particulate-bound phosphorus made up 82.3% to 85.2% of total phosphorus losses. (4) Polyacrylamide treatments increased water-stable aggregates content by 32.3% to 59.1%, total porosity by 11.3% to 49.0%, final infiltrative rate by 41.3% to 72.5%, and reduced soil erosion by 18.9% to 39.8% compared with the control group. Overall, the results of this study indicated that polyacrylamide application in the steep rocky slope stabilization projects could

  6. The Behaviours of Cementitious Materials in Long Term Storage and Disposal of Radioactive Waste. Results of a Coordinated Research Project

    International Nuclear Information System (INIS)

    2013-09-01

    Radioactive waste with widely varying characteristics is generated from the operation and maintenance of nuclear power plants, nuclear fuel cycle facilities, research laboratories and medical facilities. This waste must be treated and conditioned, as necessary, to provide waste forms acceptable for safe storage and disposal. Many countries use cementitious materials (concrete, mortar, etc.) as a containment matrix for immobilization, as well as for engineered structures of disposal facilities. Radionuclide release is dependent on the physicochemical properties of the waste forms and packages, and on environmental conditions. In the use of cement, the diffusion process and metallic corrosion can induce radionuclide release. The advantage of cementitious materials is the added stability and mechanical support during storage and disposal of waste. Long interim storage is becoming an important issue in countries where it is difficult to implement low level waste and intermediate level waste disposal facilities, and in countries where cement is used in the packaging of waste that is not suitable for shallow land disposal. This coordinated research project (CRP), involving 24 research organizations from 21 Member States, investigated the behaviour and performance of cementitious materials used in an overall waste conditioning system based on the use of cement - including waste packaging (containers), waste immobilization (waste form) and waste backfilling - during long term storage and disposal. It also considered the interactions and interdependencies of these individual elements (containers, waste, form, backfill) to understand the processes that may result in degradation of their physical and chemical properties. The main research outcomes of the CRP are summarized in this report under four topical sections: (i) conventional cementitious systems; (ii) novel cementitious materials and technologies; (iii) testing and waste acceptance criteria; and (iv) modelling long

  7. The Behaviours of Cementitious Materials in Long Term Storage and Disposal of Radioactive Waste. Results of a Coordinated Research Project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-09-15

    Radioactive waste with widely varying characteristics is generated from the operation and maintenance of nuclear power plants, nuclear fuel cycle facilities, research laboratories and medical facilities. This waste must be treated and conditioned, as necessary, to provide waste forms acceptable for safe storage and disposal. Many countries use cementitious materials (concrete, mortar, etc.) as a containment matrix for immobilization, as well as for engineered structures of disposal facilities. Radionuclide release is dependent on the physicochemical properties of the waste forms and packages, and on environmental conditions. In the use of cement, the diffusion process and metallic corrosion can induce radionuclide release. The advantage of cementitious materials is the added stability and mechanical support during storage and disposal of waste. Long interim storage is becoming an important issue in countries where it is difficult to implement low level waste and intermediate level waste disposal facilities, and in countries where cement is used in the packaging of waste that is not suitable for shallow land disposal. This coordinated research project (CRP), involving 24 research organizations from 21 Member States, investigated the behaviour and performance of cementitious materials used in an overall waste conditioning system based on the use of cement - including waste packaging (containers), waste immobilization (waste form) and waste backfilling - during long term storage and disposal. It also considered the interactions and interdependencies of these individual elements (containers, waste, form, backfill) to understand the processes that may result in degradation of their physical and chemical properties. The main research outcomes of the CRP are summarized in this report under four topical sections: (i) conventional cementitious systems; (ii) novel cementitious materials and technologies; (iii) testing and waste acceptance criteria; and (iv) modelling long

  8. Recalculation of compression tests on damping materials in the frame of the research project QUEST; Nachrechnungen von Stauchversuchen an Daempfermaterialien im Forschungsvorhaben Quest

    Energy Technology Data Exchange (ETDEWEB)

    Schopphoff, E.; Vallentin, R. [Wissenschaftlich-Technische Ingenieurberatung GmbH (WTI), Juelich (Germany); Glutsch, S.; Hueggenberg, R. [GNS Gesellschaft fuer Nuklear-Service mbH, Essen (Germany)

    2011-07-01

    The mechanical design of packaging containers for radioactive material transport and storage using numerical techniques is a resilient and sufficient exact prediction of the mechanical loads due to drop accident scenarios. The correct simulation of energy dissipation of the involved shock absorbing components and materials is of main importance. The behavior of components and materials is dependent on deformation speed and environmental conditions, esp. temperature. Within the research project QUEST numerical methods based on compression test results from different damping materials are developed for the optimization of mechanical load simulation. Test results are described for polyurethane foam, wood and damping concrete. The finite element based simulation is aimed to develop and verify material models based on the experimental material reference curves.

  9. Dredging Research, Volume 3, No. 3. DNA Technology to Impact Dredged Material Projects through Faster, More Accurate Testing Methods

    National Research Council Canada - National Science Library

    McDonald, Allison

    2000-01-01

    .... Most people associate DNA with criminal cases and paternity testing, but thanks to research projects such as the Human Genome Project, which has isolated and identified thousands of genes, many...

  10. Report on materials characterization center workshop on stress corrosion cracking for the Salt Repository Project, December 16-17, 1986, Seattle, Washington: Workshop summary

    International Nuclear Information System (INIS)

    Merz, M.D.; Shannon, D.W.

    1986-09-01

    The Materials Characterization Center (MCC) at Pacific Northwest Laboratory (PNL) conducted a Workshop on Stress Corrosion Cracking for the Salt Repository Project on December 16 and 17, 1986 in Seattle, Washington. The workshop was held to formulate recommendations for addressing stress corrosion cracking (SCC) in a salt repository. It was attended by 24 representatives from major laboratories, universities, and industry. This report presents the recommendations of the workshop, along with the agenda, list of participants, questions and comments, summaries of working groups on low-strength steel and alternate materials, and materials handed out by the speakers

  11. Versailles Project on Advanced Materials and Standards Interlaboratory Study on Measuring the Thickness and Chemistry of Nanoparticle Coatings Using XPS and LEIS

    NARCIS (Netherlands)

    Belsey, N.A.; Cant, D.J.H.; Minelli, C.; Araujo, J.R.; Bock, B.; Brüner, P.; Castner, D.G.; Ceccone, C.; Counsell, J.D.P.; Dietrich, P.M.; Engelhard, M.H.; Fearn, S.; Galhardo, C.E.; Kalbe, H.; Kim, J.W.; Lartundo-Rojas, L.; Luftman, H.S.; Nunney, T.S.; Pseiner, J.; Smith, E.F.; Spampinato, V.; Sturm, Jacobus Marinus; Thomas, A.G.; Treacy, J.P.W.; Veith, L.; Wagstaffe, M.; Wang, H.; Wang, M..; Wang, Y.C.; Werner, W.; Yang, L.; Shard, A.G.

    2016-01-01

    We report the results of a Versailles Project on Advanced Materials and Standards (VAMAS) interlaboratory study on the measurement of the shell thickness and chemistry of nanoparticle coatings. Peptide-coated gold particles were supplied to laboratories in two forms: a colloidal suspension in pure

  12. The Text of the Agreement connected with the Agency's Assistance to Pakistan in furthering Projects by the Supply of Materials. Supplementary Agreement No. 1

    International Nuclear Information System (INIS)

    1972-01-01

    The text of the Supplementary Agreement No. 1 to the Master Agreement between the Agency and the Government of Pakistan for assistance by the Agency in furthering projects by the supply of materials is reproduced herein for the information of all Members. The Supplementary Agreement entered into force on 16 November 1971.

  13. Ceramics Technology Project database: September 1991 summary report. [Materials for piston ring-cylinder liner for advanced heat/diesel engines

    Energy Technology Data Exchange (ETDEWEB)

    Keyes, B.L.P.

    1992-06-01

    The piston ring-cylinder liner area of the internal combustion engine must withstand very-high-temperature gradients, highly-corrosive environments, and constant friction. Improving the efficiency in the engine requires ring and cylinder liner materials that can survive this abusive environment and lubricants that resist decomposition at elevated temperatures. Wear and friction tests have been done on many material combinations in environments similar to actual use to find the right materials for the situation. This report covers tribology information produced from 1986 through July 1991 by Battelle columbus Laboratories, Caterpillar Inc., and Cummins Engine Company, Inc. for the Ceramic Technology Project (CTP). All data in this report were taken from the project's semiannual and bimonthly progress reports and cover base materials, coatings, and lubricants. The data, including test rig descriptions and material characterizations, are stored in the CTP database and are available to all project participants on request. Objective of this report is to make available the test results from these studies, but not to draw conclusions from these data.

  14. Molten salt processes in special materials preparation

    International Nuclear Information System (INIS)

    Krishnamurthy, N.; Suri, A.K.

    2013-01-01

    As a class, molten salts are the largest collection of non aqueous inorganic solvents. On account of their stability at high temperature and compatibility to a number of process requirements, molten salts are considered indispensable to realize many of the numerous benefits of high temperature technology. They play a crucial role and form the basis for numerous elegant processes for the preparation of metals and materials. Molten salt are considered versatile heat transfer media and have led to the evolution of many interesting reactor concepts in fission and possibly in fusion. They also have been the basis of thinking for few novel processes for power generation. While focusing principally on the actual utilization of molten salts for a variety of materials preparation efforts in BARC, this lecture also covers a few of the other areas of technological applications together with the scientific basis for considering the molten salts in such situations. (author)

  15. Long term test of buffer material at the Aespoe HRL, LOT project. Final report on the A0 test parcel

    International Nuclear Information System (INIS)

    Karnland, Ola; Olsson, Siv; Sanden, Torbjoern; Faelth, Billy; Jansson, Mats; Eriksen, Trygve E.; Svaerdstroem, Kjell; Rosborg, Bo; Muurinen, Arto

    2011-02-01

    In the Swedish repository concept for nuclear waste (KBS-3 concept), the spent nuclear fuel will be stored in copper canisters surrounded by compacted bentonite. The decaying power of the fuel will increase the temperature in the repository which, in combination with the uptake of ground-water, could be expected to produce minor mineralogical changes in the bentonite. The ongoing LOT test series at the Aespoe Hard Rock Laboratory are focused on identifying and quantifying any mineralogical alterations in the bentonite exposed to typical repository-like conditions. Further, buffer-related processes concerning copper corrosion, cation transport, and bacterial survival/activity are studied. In total, the LOT project includes seven test parcels, which contain a central Cu-tube surrounded by cylindrical bentonite blocks to a total diameter of 30 cm as well as temperature, total pressure, water pressure and humidity sensors. In each test parcel, an electrical heater placed inside the copper tube is used to simulate the heat generation from the decaying spent fuel. Three test parcels (S1 to S3) have been exposed to standard KBS-3 conditions (maximum temperature below 100 deg C) and three parcels (A1 to A3) to adverse conditions (maximum temperature below ∼140 deg C). Both the standard and the adverse test series include short term tests (1 to 2 years), medium term tests (> 5 years) and long term tests (> 10 years). The present report concerns an additional short term test, thereby the designation A0, which was exposed to adverse conditions for approximately 1.5 years. Cu-coupons, 134 Cs and 57 Co tracers and specific chemical agents were placed in the bentonite at defined positions. After field exposure, the entire test parcel was released from the rock by overlapping percussion drilling and wire sawing. The parcel was lifted and divided at the test site and the bentonite material was sampled for specified analyses. The main aspects of the various tests and analyses may

  16. Long term test of buffer material at the Aespoe HRL, LOT project. Final report on the A0 test parcel

    Energy Technology Data Exchange (ETDEWEB)

    Karnland, Ola; Olsson, Siv; Sanden, Torbjoern; Faelth, Billy (Clay Technology AB, Lund (Sweden)); Jansson, Mats; Eriksen, Trygve E.; Svaerdstroem, Kjell (KTH Royal Inst. of Technology, Stockholm (Sweden)); Rosborg, Bo (Studsvik AB, Nykoeping (Sweden); Rosborg Consulting, Nykoeping (Sweden)); Muurinen, Arto (VTT, Espoo (Finland))

    2011-02-15

    In the Swedish repository concept for nuclear waste (KBS-3 concept), the spent nuclear fuel will be stored in copper canisters surrounded by compacted bentonite. The decaying power of the fuel will increase the temperature in the repository which, in combination with the uptake of ground-water, could be expected to produce minor mineralogical changes in the bentonite. The ongoing LOT test series at the Aespoe Hard Rock Laboratory are focused on identifying and quantifying any mineralogical alterations in the bentonite exposed to typical repository-like conditions. Further, buffer-related processes concerning copper corrosion, cation transport, and bacterial survival/activity are studied. In total, the LOT project includes seven test parcels, which contain a central Cu-tube surrounded by cylindrical bentonite blocks to a total diameter of 30 cm as well as temperature, total pressure, water pressure and humidity sensors. In each test parcel, an electrical heater placed inside the copper tube is used to simulate the heat generation from the decaying spent fuel. Three test parcels (S1 to S3) have been exposed to standard KBS-3 conditions (maximum temperature below 100 deg C) and three parcels (A1 to A3) to adverse conditions (maximum temperature below approx140 deg C). Both the standard and the adverse test series include short term tests (1 to 2 years), medium term tests (> 5 years) and long term tests (> 10 years). The present report concerns an additional short term test, thereby the designation A0, which was exposed to adverse conditions for approximately 1.5 years. Cu-coupons, 134Cs and 57Co tracers and specific chemical agents were placed in the bentonite at defined positions. After field exposure, the entire test parcel was released from the rock by overlapping percussion drilling and wire sawing. The parcel was lifted and divided at the test site and the bentonite material was sampled for specified analyses. The main aspects of the various tests and analyses

  17. BARC: A Novel Apoptosis Regulator

    Science.gov (United States)

    2005-06-01

    References ...................................................................................... 11 A ppendices ...that acute inhibition of Bcl-2 by the functionally interacts with inositol 1,4,5-trisphosphate (IP 3) re- green tea compound epigallocatechin gallate

  18. H N Ghosh, BARC, Mumbai

    Indian Academy of Sciences (India)

    admin

    Relentless efforts are underway allover the world to develop a low cost efficient solar cell for the solution of global energy crisis. Dye sensitized solar cell (DSSC) appeared to be one of the good discovery for the solution of energy problem. We have been involved in studying ultrafast interfacial electron transfer dynamics in.

  19. The prognostic value of bleeding academic research consortium (BARC)-defined bleeding complications in ST-segment elevation myocardial infarction: a comparison with the TIMI (Thrombolysis In Myocardial Infarction), GUSTO (Global Utilization of Streptokinase and Tissue Plasminogen Activator for Occluded Coronary Arteries), and ISTH (International Society on Thrombosis and Haemostasis) bleeding classifications

    NARCIS (Netherlands)

    Kikkert, Wouter J.; van Geloven, Nan; van der Laan, Mariet H.; Vis, Marije M.; Baan, Jan; Koch, Karel T.; Peters, Ron J.; de Winter, Robbert J.; Piek, Jan J.; Tijssen, Jan G. P.; Henriques, José P. S.

    2014-01-01

    The aim of the present analysis was to compare 1-year mortality prediction of Bleeding Academic Research Consortium (BARC)-defined bleeding complications with existing bleeding definitions in patients with ST-segment elevation myocardial infarction (STEMI) and to investigate the prognostic value of

  20. 75 FR 3261 - Powertech (USA) Inc.; Dewey-Burdock Project; New Source Material License Application; Notice of...

    Science.gov (United States)

    2010-01-20

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 40-9075; NRC-2009-0575] Powertech (USA) Inc.; Dewey... review process related to the Dewey- Burdock Uranium Project application, please contact the NRC... documents associated with the Dewey-Burdock Uranium Project, including the license application, are...

  1. A Service Learning Project on Aluminum Recycling--Developing Soft Skills in a Material and Energy Balances Course

    Science.gov (United States)

    West, Christy Wheeler

    2017-01-01

    This paper describes a project carried out in a sophomore chemical engineering course, in which students studied the energetic differences between refining and recycling aluminum. They worked in teams to prepare a presentation about the importance of aluminum recycling to a lay audience. The project reinforced classroom learning and provided an…

  2. IAEA coordinated research project on improvement of technical measures to detect and respond to illicit trafficking of nuclear and other radioactive materials

    International Nuclear Information System (INIS)

    Abedin-Zadeh, R.; Abou-Zahra, A.; Weiss, B.

    2002-01-01

    Full text: Monitoring to detect the illicit trafficking of nuclear and other radioactive materials includes screening vehicles, cargo and individuals at borders to 1) detect smuggling of these materials; 2) locate, measure and characterize the source of radiation; and 3) fully characterize any confiscated material. Currently available instruments used for the field measurements are not optimized for this purpose and may not detect shielded plutonium and highly enriched uranium. Confiscated radioactive materials need to be characterized with macro- and microanalysis techniques to fully understand the significance of the material and to provide credible evidence in the event of prosecution of the traffickers. Although most States have national laboratories capable to determine the basic characteristics of such material, only a few member States have the sophisticated analytical capability necessary to perform proper forensics analysis. The coordinated research project on 'Improvement of Technical Measures to Detect and Respond to Illicit Trafficking of Nuclear and other Radioactive Materials' has been established to: Improve the detection capability and performance of hand-held and portable isotope measurement devices, including the technical and functional specifications for such devices; standardize procedures to examine suspicious packages and to assess the hazard of confiscated material; and develop recommendations and guidelines for establishing a system to provide nuclear forensics support to member States for the characterization of seized nuclear material. Related to the nuclear forensics support, it should be noted that with the inception of the Agency's nuclear security programme in 1995, the IAEA has offered the services of its laboratories in Seibersdorf and associated laboratories to assist States in analysing confiscated nuclear materials. Since 1993 the IAEA has received reports of over 300 cases of smuggling of nuclear and other radioactive materials

  3. The project of the Spanish Nuclear Industry Forum to develop an interactive educational material on Radiological Protection; El Proyecto de Foro de la Industria Nuclear espanola para elaborar un material didactico interactivo sobre Proteccion Radiologica

    Energy Technology Data Exchange (ETDEWEB)

    Real, A.; Cruz, T. de la; Girona, L.; Montesinos, L.; Sanchez, P.

    2012-07-01

    The Training Department of the Spanish Nuclear Industry Forum has undertaken a new project to develop an interactive educational material on Radiological Protection. The objective was to develop an attractive, comprehensive and interactive material, to facilitate students and teachers of Elementary, Middle and High schools, to become familiar with ionising radiations. The novelly of the project, is that based on the European framework of key competencies for file long learning, which are defined as a set of knowledge, skills and altitudes that all individuals need for personal fulfilment and employment. The material presented in this paper, is based in an integrated structure of tasks, activities and exercises, which will facilitate the acquisition of as may key competencies as possible. Besides, the material also includes reference texts, links to pertinent web sites and videos. Students, through the development of a specific task (and related activities and exercises), will learn the differences between ionizing and non ionising radiation, the origin, characteristics and types of types of ionising radiation, how to detect and measure them, the potential detrimental health effects, the principles of radiation protection and the beneficial applications can have for man. The material is freely available in www.rinconeducativo.org. (Author) 4 refs.

  4. Proceedings No. 41. Audition of M. Francois Loos, Delegate Minister of Industry, about the law project relative to the management of radioactive materials and wastes

    International Nuclear Information System (INIS)

    2006-03-01

    The project of law about the management of radioactive materials and wastes is the logical continuation of the law no 91-1381 from December 30, 1991 relative to the researches on radioactive waste management. At the occasion of the presentation of this law project at the board of ministers, F. Loos, the French minister of industry, presented this project the same day also at the house of commons. This document is the proceedings of the audition of F. Loos. It comprises a brief recall of the researches carried out so far and a presentation of the 3 main points of the project of law: reprocessing of spent fuels and recycling in reactors, interim surface storage of non-recyclable wastes, and underground reversible disposal of ultimate wastes. One aspect of the project concerns the scheduling of future research works according to the 3 ways defined in the 1991 law: storage, disposal and transmutation. This presentation is followed by questions from the deputies about some particular points of the project like the safety aspects, the selection of storage sites, the acceptance and information of the public, the financial aspects etc. (J.S.)

  5. Apollo-Soyuz test project. Volume 1: Astronomy, earth atmosphere and gravity field, life sciences, and materials processing

    Science.gov (United States)

    1977-01-01

    The joint U.S.-USSR experiments and the U.S. conducted unilateral experiments performed during the Apollo Soyuz Test Project are described. Scientific concepts and experiment design and operation are discussed along with scientific results of postflight analysis.

  6. Law project modified by the Senate of the program relative to the sustainable management of radioactive materials and wastes

    International Nuclear Information System (INIS)

    2006-06-01

    The document presents the different articles of the law project dealing with the terminology, the radioactive wastes storage and disposal, the safety and the transport, the financing, the liabilities, the control and the sanctions. (A.L.B.)

  7. Guideline for financing agricultural biogas projects - Training material for biogas investors: D.3.7, WP 3

    OpenAIRE

    Hahn, H.

    2011-01-01

    There are many good reasons to implement a biogas plant ranging from environmental protection and waste reduction to renewable energy production. It can also include financial and non-financial incentives. Nevertheless, investors of biogas projects should be well informed about different legal requirements and financing possibilities. The guideline will help to analyse a potential biogas investment by describing its most important steps. The guideline starts with the project idea and a first ...

  8. The Texts of the Instruments connected with the Agency's Assistance to India in Furthering Projects by the Supply of Materials. Supplementary Agreements Nos 4, 5 and 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1972-04-14

    As a sequel to the assistance which the Agency has provided to the Government of India in furthering projects by the supply of materials, three additional Supplementary Agreements to the Master Agreement concerning the provision of that assistance have been concluded between the Agency and the Government. These Supplementary Agreements entered into force on 1 July 1971, 20 August 1971 and 1 October 1971 respectively, and the texts are reproduced herein for the information of all Members.

  9. The Texts of the Instruments connected with the Agency's Assistance to India in Furthering Projects by the Supply of Materials. Supplementary Agreements Nos 4, 5 and 6

    International Nuclear Information System (INIS)

    1972-01-01

    As a sequel to the assistance which the Agency has provided to the Government of India in furthering projects by the supply of materials, three additional Supplementary Agreements to the Master Agreement concerning the provision of that assistance have been concluded between the Agency and the Government. These Supplementary Agreements entered into force on 1 July 1971, 20 August 1971 and 1 October 1971 respectively, and the texts are reproduced herein for the information of all Members

  10. The Texts of the Instruments connected with the Agency's Assistance to India in Furthering Projects by the Supply of Materials. Second and Third Supplementary Agreements

    International Nuclear Information System (INIS)

    1971-01-01

    As a sequel to the assistance which the Agency has provided to the Government of India in furthering projects by the supply of materials, two additional Supplementary Agreements to the Master Agreement concerning the provision of that assistance have been concluded between the Agency and the Government. These Supplementary Agreements entered into force on 2 July 1970 and 16 November 1970 respectively, and the texts are reproduced herein for the information of all Members

  11. Vitrified radwaste from reprocessing. Material concerning the examination by the Swedish Nuclear Power Inspectorate of the supplementary geology report from the KBS-project

    International Nuclear Information System (INIS)

    1979-01-01

    The Swedish Nuclear Power Inspectorate was designated by the Swedish Government to examine the supplementary geologic investigations performed by the utilities' KBS-project and to judge wheather the area investigated, Sternoe in southern Sweden, could be used for constructing a safe repository for radioactive wastes or not. This report contains material that was ordered by or sent to the Nuclear Power Inspectorate as well as the report by the Inspectorate to the Government. (L.E.)

  12. The Texts of the Instruments connected with the Agency's Assistance to Romania in Furthering Projects by the Supply of Materials. Second and Third Supplementary Agreements

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1970-02-06

    As a sequel to the assistance which the Agency has provided to the Government of Romania in furthering projects by the supply of materials, two additional Supplementary Agreements to the Master Agreement concerning the provision of that assistance have been concluded between the Agency and the Government. These Agreements entered into force on 4 June 1968 and 21 August 1968 respectively, and the texts are reproduced herein for the information of all Members.

  13. The Texts of the Instruments connected with the Agency's Assistance to Romania in Furthering Projects by the Supply of Materials. Second and Third Supplementary Agreements

    International Nuclear Information System (INIS)

    1970-01-01

    As a sequel to the assistance which the Agency has provided to the Government of Romania in furthering projects by the supply of materials, two additional Supplementary Agreements to the Master Agreement concerning the provision of that assistance have been concluded between the Agency and the Government. These Agreements entered into force on 4 June 1968 and 21 August 1968 respectively, and the texts are reproduced herein for the information of all Members

  14. Studies on the chemical conditions and microstructure in the reference bentonites of alternative buffer materials project (ABM) in Aespoe

    International Nuclear Information System (INIS)

    Muurinen, A.

    2009-06-01

    The chemical and microstructural properties of some bentonites used in the ABM project in Aespoe HRL were studied in laboratory experiments. The aim was to obtain information about the materials before they were used in the field experiment and to test the research methods that will be used when the packages of the field experiment are retrieved. The bentonites of interest were MX-80, Deponit CAN, Asha 505 and Friedland Clay. The pH values in the compacted samples prepared from the clay powders and deionized water were about 8 for MX-80, 7 for Deponit and Asha, and 6.5 for Friedland clay. The Eh values in the compacted MX-80, Asha and Deponit samples varied between 100 mV and -100 mV, and in the Friedland clay from 0 mV to 200 mV. The total porosity, chloride porosity and the microstructure were studied in compacted samples prepared from MX-80, Deponit, Asha and Friedland Clay and equilibrated through filter plates with 0.1 M NaCl solution for 12.5 months in aerobic conditions. The dry densities of the samples were approximately 0.7, 1.0, 1.25 and 1.55 g/cm 3 . XRD and SAXS (Small Angle X-ray Scattering) were used to study the microstructure of the MX-80 and Deponit bentonites. It was obvious that the chloride porosity was lower than the water porosity in all the clays, which indicates the exclusion of anions caused by the negatively charged surfaces. In the XRD measurements on MX-80, Asha and Deponit, the measured basal spaces represented by the diffraction peaks were smaller than the theoretical one assuming a homogenous microstructure. This indicates that there was a substantial amount of water also in the pores, which were not seen by XRD. The SAXS data modelling which considered single discs and stacks of discs proposed that a large fraction of the clay should be considered as single platelets. The fraction of the single discs decreased with the increasing density of the sample. The number of layers in the stacks varied from 4 to 8. By combining the

  15. Working capital management in the process of financial support of investment and construction projects and of the construction material industry

    Science.gov (United States)

    Danilochkina, Nadezhda; Lukmanova, Inessa; Roshchina, Olga; Voytolovskiy, Nikolay

    2018-03-01

    The article presents the analysis of working capital in the process of financial support of high-rise construction investment projects. The factors influencing the choice of the working capital management model were analyzed, the reasons of the change in the requirement for the values of current assets in the process of construction of high-rise facilities were determined. The author has developed the scheme of interrelation between production, operational and financial activity cycles of enterprises implementing investment projects of unique buildings and structures and made a comparative description of their financing sources.

  16. Developing improved opportunities for the recycle and reuse of materials in road, bridge and construction projects : [summary].

    Science.gov (United States)

    2014-01-01

    Reducing waste and reusing materials is now : a part of the everyday fabric of life. Recycling : glass, paper, and plastic is an activity in many : households and businesses. Similarly, the : transportation sector generates huge quantities : of concr...

  17. Low cost solar array project. Cell and module formation research area. Process research of non-CZ silicon material

    Science.gov (United States)

    1983-01-01

    Liquid diffusion masks and liquid dopants to replace the more expensive CVD SiO2 mask and gaseous diffusion processes were investigated. Silicon pellets were prepared in the silicon shot tower; and solar cells were fabricated using web grown where the pellets were used as a replenishment material. Verification runs were made using the boron dopant and liquid diffusion mask materials. The average of cells produced in these runs was 13%. The relationship of sheet resistivity, temperature, gas flows, and gas composition for the diffusion of the P-8 liquid phosphorus solution was investigated. Solar cells processed from web grown from Si shot material were evaluated, and results qualified the use of the material produced in the shot tower for web furnace feed stock.

  18. Final environmental assessment for the U.S. Department of Energy, Oak Ridge Operations receipt and storage of uranium materials from the Fernald Environmental Management Project site

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    Through a series of material transfers and sales agreements over the past 6 to 8 years, the Fernald Environmental Management Project (FEMP) has reduced its nuclear material inventory from 14,500 to approximately 6,800 metric tons of uranium (MTU). This effort is part of the US Department of energy`s (DOE`s) decision to change the mission of the FEMP site; it is currently shut down and the site is being remediated. This EA focuses on the receipt and storage of uranium materials at various DOE-ORO sites. The packaging and transportation of FEMP uranium material has been evaluated in previous NEPA and other environmental evaluations. A summary of these evaluation efforts is included as Appendix A. The material would be packaged in US Department of Transportation-approved shipping containers and removed from the FEMP site and transported to another site for storage. The Ohio Field Office will assume responsibility for environmental analyses and documentation for packaging and transport of the material as part of the remediation of the site, and ORO is preparing this EA for receipt and storage at one or more sites.

  19. Final environmental assessment for the U.S. Department of Energy, Oak Ridge Operations receipt and storage of uranium materials from the Fernald Environmental Management Project site

    International Nuclear Information System (INIS)

    1999-01-01

    Through a series of material transfers and sales agreements over the past 6 to 8 years, the Fernald Environmental Management Project (FEMP) has reduced its nuclear material inventory from 14,500 to approximately 6,800 metric tons of uranium (MTU). This effort is part of the US Department of energy's (DOE's) decision to change the mission of the FEMP site; it is currently shut down and the site is being remediated. This EA focuses on the receipt and storage of uranium materials at various DOE-ORO sites. The packaging and transportation of FEMP uranium material has been evaluated in previous NEPA and other environmental evaluations. A summary of these evaluation efforts is included as Appendix A. The material would be packaged in US Department of Transportation-approved shipping containers and removed from the FEMP site and transported to another site for storage. The Ohio Field Office will assume responsibility for environmental analyses and documentation for packaging and transport of the material as part of the remediation of the site, and ORO is preparing this EA for receipt and storage at one or more sites

  20. Hazardous materials in aquatic environments of the Mississippi River Basin. Quarterly project status report, 1 April--30 June 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-01

    This report contains a cluster of twenty separate project reports concerning the fate, environmental transport, and toxicity of hazardous wastes in the Mississippi River Basin. Some of topics investigated involve: biological uptake and metabolism; heavy metal immobilization; biological indicators; toxicity; and mathematical models.

  1. Proceedings of DAE-BRNS national workshop on materials chemistry: functional materials

    International Nuclear Information System (INIS)

    2011-12-01

    Design and development of materials with tailored properties assumes great significance in our everyday life and are crucial to modern technologies. Chemistry has had a tremendous Convener role in developing several need based materials by integrating multiple functionalities. The year 2011, being recognised as the International Year of Chemistry by the UNESCO, assumes further significance for material chemists. In view of the renowned interest in advanced functional materials, the Society for Materials Chemistry, India together with Chemistry Division, BARC has taken an initiative to organise this National Workshop on Materials Chemistry (NWMC-2011) under the theme 'Functional Materials (FUN-MAT)'. NWMC- 2011 aims to provide a forum for young researchers to interact with experts involved in synthesis, processing and applications of various advanced functional materials. In particular, recent developments and future prospects of magnetic, electronic and optical materials, glasses, ceramics, soft materials, materials for sensors, materials for hydrogen production and storage etc. will be addressed in this workshop. Papers relevant to INIS are indexed separately

  2. Fiscal 1991 research report. Research trend survey for next-generation industrial structure technology research and development project - Research and development of advanced materials for extreme environments; 1991 nendo jisedai sangyo kiban gijutsu kenkyu kaihatsu project ni kakawaru kenkyu doko chosa hokokusho. Chotaikankyosei senshin zairyo no kenkyu kaihatsu (sekitoku sekiyu)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-03-01

    Efforts were exerted to develop intermetallic compounds and advanced C/C (carbon/carbon) composite materials usable under extreme environments such as high temperatures. In relation with advanced composite materials, especially with projects for developing composite materials using oil as raw material, a survey was conducted of the three fields of (1) summarization of activities conducted up to fiscal 1991, (2) contents of associated aerospace projects, and (3) oil based composite material technology. In Field (1), past achievements are summarized. In Field (2), aerospace projects under way across the world are broken down by airframe and engine, and are reviewed from the viewpoint of needs for materials. In Field (3), the present and future of heat resisting thermosetting composite materials, thermoplastic composite materials, and C/C composites are discussed. Characteristics such materials are supposed to finally assume and tasks to discharge for technical development are also taken up. (NEDO)

  3. Projects for the implementation of science technology society approach in basic concept of natural science course as application of optical and electrical instruments’ material

    Science.gov (United States)

    Satria, E.

    2018-03-01

    Preservice teachers in primary education should be well equipped to meet the challenges of teaching primary science effectively in 21century. The purpose of this research was to describe the projects for the implementation of Science-Technology-Society (STS) approach in Basic Concept of Natural Science course as application of optical and electrical instruments’ material by the preservice teachers in Elementary Schools Teacher Education Program. One of the reasons is the lack of preservice teachers’ ability in making projects for application of STS approach and optical and electrical instruments’ material in Basic Concept of Natural Science course. This research applied descriptive method. The instrument of the research was the researcher himself. The data were gathered through observation and documentation. Based on the results of the research, it was figured out that preservice teachers, in groups, were creatively and successful to make the projects of optical and electrical instruments assigned such as projector and doorbell. It was suggested that the construction of the instruments should be better (fixed and strong structure) and more attractive for both instruments, and used strong light source, high quality images, and it could use speaker box for projector, power battery, and heat sink for electrical instruments.

  4. Hazardous materials in aquatic environments of the Mississippi River basin. Quarterly project status report, April 1, 1993--June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    During this quarter, the Review Panel made its final recommendations regarding which of the proposals should be funded. Included in this report is a brief status report of each of the research and education projects that are currently funded in this project. The Coordinated Instrumentation Facility (CIF) sponsored 3 seminars on Environmental Sample Preparation Techniques. These seminars were designed to educate the investigators on the use of microwave digestion systems for sample preparation and the use of Inductively Coupled Plasma and Atomic Absorption Specrtroscopy for analyses. During this period, Tulane and Xavier Universities have worked closely with Oak Ridge National Laboratories (ORNL) to develop a long term relationship that will encourage interaction and collaborations among the investigators at all of the institutions.

  5. Environmentally-assisted cracking in austenitic light water reactor structural materials. Final report of the KORA-I project

    Energy Technology Data Exchange (ETDEWEB)

    Seifert, H.-P.; Ritter, S

    2009-03-15

    The following document is the final report of the KORA-I project, which was performed at the Paul Scherrer Institute (PSI) between 2006 and 2008 and was funded by the Swiss Nuclear Safety Inspectorate (ENSI). The three sub-projects of KORA-I covered the experimental characterisation of the effect of the reactor coolant environment on fatigue initiation and crack growth in austenitic stainless steels under boiling and pressurised water reactor conditions, the experimental evaluation of the potential and limits of the electrochemical noise measurement technique for the early detection of stress corrosion cracking initiation in austenitic stainless steels under boiling water reactor/normal water chemistry conditions, as well as the characterisation of the stress corrosion crack growth behaviour in the fusion line region of an Alloy 182-low-alloy reactor pressure vessel steel dissimilar metal weld. The main scientific results and major conclusions of the three sub-projects are discussed in three independent parts of this report. (author)

  6. Environmentally-assisted cracking in austenitic light water reactor structural materials. Final report of the KORA-I project

    International Nuclear Information System (INIS)

    Seifert, H.-P.; Ritter, S.

    2009-03-01

    The following document is the final report of the KORA-I project, which was performed at the Paul Scherrer Institute (PSI) between 2006 and 2008 and was funded by the Swiss Nuclear Safety Inspectorate (ENSI). The three sub-projects of KORA-I covered the experimental characterisation of the effect of the reactor coolant environment on fatigue initiation and crack growth in austenitic stainless steels under boiling and pressurised water reactor conditions, the experimental evaluation of the potential and limits of the electrochemical noise measurement technique for the early detection of stress corrosion cracking initiation in austenitic stainless steels under boiling water reactor/normal water chemistry conditions, as well as the characterisation of the stress corrosion crack growth behaviour in the fusion line region of an Alloy 182-low-alloy reactor pressure vessel steel dissimilar metal weld. The main scientific results and major conclusions of the three sub-projects are discussed in three independent parts of this report. (author)

  7. Report of the evaluation by the project evaluation committee on research and development of FBR structural materials. Result intermediate evaluation in fiscal year 2002

    International Nuclear Information System (INIS)

    2003-03-01

    The project evaluation committee of FBR (Fast Breeder Reactor) and fuel cycle evaluated the problem under the evaluation method defined by the committee on the basis of material and supplementary data produced by JNC (Japan Nuclear Cycle Development Institute) and discussion. This report consists of summary, construction of the committee, investigation process, evaluation method, opinion of object, plan, research system, results, relation to practical use, public offering of results, development and others and total evaluation. Each opinion of the committee member are reported. Development of structural material is important problem of R and D of FBR. The estimation techniques of materials, high temperature structural and earthquake-resistant design techniques are evaluated to obtain the fruitful results. The remarkable results are development of materials of 316FR, using plate to reactor, estimation method of thermal striping, improvement of earthquake-resistant analysis technology, contribution to evaluation analysis of Monju second liner and basic information to develop quantity technique of material damage. (S.Y.)

  8. Stabilizing plutonium materials at Hanford: systems engineering for PFP transition project effort on DNFSB 94-1

    Energy Technology Data Exchange (ETDEWEB)

    Huber, T.E., Westinghouse Hanford

    1996-07-02

    This report discusses the basic objectives of the stabilization and packaging activities at the Plutonium Finishing Plant that satisfy the Defense Nuclear Facility Safety Board Recommendation 94-1 by transforming the plutonium materials at hanford into forms or conditions which are suitable for safe storage to appropriate storage criteria; or discard that meets appropriate waste acceptance criteria.

  9. N.590 National assembly. Law project of program relative to the sustainable management of radioactive materials and wastes

    International Nuclear Information System (INIS)

    2006-01-01

    This document presents the different articles of the law text n. 590 on the management of the radioactive wastes and materials. It concerns the obligations and the liabilities of producers and users of radioactive spent fuels and wastes. (A.L.B.)

  10. Hands on what? The relative effectiveness of physical versus virtual materials in an engineering design project by middle school children

    Science.gov (United States)

    Klahr, David; Triona, Lara M.; Williams, Cameron

    2007-01-01

    Hands-on activities play an important, but controversial, role in early science education. In this study we attempt to clarify some of the issues surrounding the controversy by calling attention to distinctions between: (a) type of instruction (direct or discovery); (b) type of knowledge to be acquired (domain-general or domain-specific); and (c) type of materials that are used (physical or virtual). We then describe an empirical study that investigates the relative effectiveness of the physical-virtual dimension. In the present study, seventh and eighth grade students assembled and tested mousetrap cars with the goal of designing a car that would go the farthest. Children were assigned to four different conditions, depending on whether they manipulated physical or virtual materials, and whether they had a fixed number of cars they could construct or a fixed amount of time in which to construct them. All four conditions were equally effective in producing significant gains in learners' knowledge about causal factors, in their ability to design optimal cars, and in their confidence in their knowledge. Girls' performance, knowledge, and effort were equal to boys' in all conditions, but girls' confidence remained below boys' throughout. Given the fact that, on several different measures, children were able to learn as well with virtual as with physical materials, the inherent pragmatic advantages of virtual materials in science may make them the preferred instructional medium in many hands-on contexts.

  11. Design and development of an ultrasonic pulser-receiver unit for non-destructive testing of materials

    International Nuclear Information System (INIS)

    Patankar, V.H.; Joshi, V.M.

    2002-11-01

    The pulser/receiver constitutes the most vital part of an ultrasonic flaw detector or an ultrasonic imaging system used for inspection of materials. The ultrasonic properties of the material and resolution requirements govern the choice of the frequency of ultrasound that can be optimally used. The pulser/receiver in turn decides the efficiency of excitation of the transducer and the overall signal to noise ratio of the system for best sensitivity and resolution. A variety of pulsers are used in the ultrasonic instruments employed for materials inspection. This report describes a square wave type of an ultrasonic pulser-receiver unit developed at Ultrasonic Instrumentation Section, Electronics Division, BARC. It has been primarily designed for excitation of the transducer that is used with a multi-channel ultrasonic imaging system ULTIMA 100M targeted for inspection of SS403 billets, which are in turn used as the base material for fabrication of end fittings for coolant channels of pressurized heavy water nuclear reactors (PHWRs). The design of the pulser is based upon very fast MOSFETs, configured as electronic switches. The pulser is operated with a linear bipolar H.V. supply (+/- 500V max.). The receiver provides a 60 dB gain with a -3 dB BW of 40 MHz. This pulser/receiver unit has been successfully interfaced with a 4 channel ULTIMA 100 M4 multichannel ultrasonic C-scan imaging system, also designed and developed by the authors at Ultrasonic Instrumentation Section (Electronics Division, BARC) and supplied to Centre for Design and Manufacturer - CDM, BARC. This system is being regularly used in C-scan imaging mode for volumetric inspection of SS403 billets for end fittings of 500 MWe PHWRs. (author)

  12. Results of work in the hot cells of Laboratory Testing Materials Irradiated Areva of Carina project for the expansion of the database of mechanical characteristics of fractures in materials of RPV German irradiated

    International Nuclear Information System (INIS)

    Barthelmes, J.; Schabel, H.; Hein, H.; Kein, E.; Eiselt, C.

    2013-01-01

    In the frame of the already completed research projects CARINA and its predecessor CARISMA a data base was created for pre-irradiated original RPV steels of German PWRs which allowed to examine the consequences if the Master Curve (T 0 ) approach instead of the RT N OT concept is applied to the RPV safety assessment. Furthermore in CARINA different irradiation conditions with respect to the accumulated neutron fluences and specific impact parameters were investigated. Besides a brief introduction of the CARINA project and an overview of the main results an overview on the requirements of the hot laboratory work in terms of specimen manufacturing and material testing is given and examples for realization are shown. (Author)

  13. Hazardous materials in aquatic environments of the Mississippi River Basin Project management. Technical quarterly progress report, April 1, 1996--June 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    McLachlan, J.; Ide, C.F.; O`Connor, S.

    1996-08-01

    This quarterly report summarizes accomplishments for the Project examining hazardous materials in aquatic environments of the Mississippi River Basin. Among the many research areas summarized are the following: assessment of mechanisms of metal-induced reproductive toxicity in aquatic species as a biomarker of exposure; hazardous wastes in aquatic environment;ecological sentinels of aquatic contamination in the lower Mississippi River System; remediation of selected contaminants; rapid on-site immunassay for heavy metal contamination; molecular mechanisms of developmental toxicity induced by retinoids and retinoid-like molecules; resuseable synthetic membranes for the removal of aromatic and halogenated organic pollutants from waste water; Effects of steroid receptor activation in neurendocrine cell of the mammalian hypothalamus; modeling and assessment of environmental quality of louisiana bayous and swamps; enhancement of environmental education. The report also contains a summary of publications resulting from this project and an appendix with analytical core protocals and target compounds and metals.

  14. Material Systems

    DEFF Research Database (Denmark)

    Jensen, Mads Brath; Mortensen, Henrik Rubæk; Mullins, Michael

    2009-01-01

    This paper describes and reflects upon the results of an investigative project which explores the setting up of a material system - a parametric and generative assembly consisting of and taking into consideration material properties, manufacturing constraints and geometric behavior. The project...... approaches the subject through the construction of a logic-driven system aiming to explore the possibilities of a material system that fulfills spatial, structural and performative requirements concurrently and how these are negotiated in situations where they might be conflicting....

  15. Aging material evaluation and studies by non-destructive techniques (AMES-NDT) - a European network project

    International Nuclear Information System (INIS)

    Dobmann, Gerd; Debarberis, Luigi; Coste, Jean-Francois

    2001-01-01

    This paper presents results obtained in a round-robin action organized in a concerted action of ten partners in the EURATOM program of the European Community. The objective of the research was to document the state of the art of available non-destructive testing (NDT) techniques in order to characterize material aging phenomena based on a reduction of Charpy-V energy and a shift in the fracture appearance transition temperature. Therefore, samples from the Japanese nuclear reactor pressure vessel JRQ-steel (ASMT Standard A533-B Class 1) have been thermally treated at 700 deg. C for 18 h with a subsequent water quenching. Besides micromagnetic and electromagnetic NDT, the positron annihilation technique, ultrasonic reverberation by using Laser ultrasonics and the thermo-electrical power have been applied to characterize the aged material states

  16. Hazardous materials in aquatic environments of the Mississippi River Basin. Quarterly project status report, July 1, 1994--September 30, 1994

    International Nuclear Information System (INIS)

    1994-01-01

    This document references information pertaining to the presence of hazardous materials in the Mississippi River Basin. Topics discussed include: The biological fate, transport, and ecotoxicity of toxic and hazardous wastes; biological uptake and metabolism; sentinels of aquatic contamination; bioremediation; microorganisms; biomarkers of exposure and ecotoxicity; expert geographical information systems for assessing hazardous wastes in aquatic environments; and enhancement of environmental education at Tulane and Xavier

  17. Characterization of materials for a reactive transport model validation experiment: Interim report on the caisson experiment. Yucca Mountain Site Characterization Project

    International Nuclear Information System (INIS)

    Siegel, M.D.; Cheng, W.C.; Ward, D.B.; Bryan, C.R.

    1995-08-01

    Models used in performance assessment and site characterization activities related to nuclear waste disposal rely on simplified representations of solute/rock interactions, hydrologic flow field and the material properties of the rock layers surrounding the repository. A crucial element in the design of these models is the validity of these simplifying assumptions. An intermediate-scale experiment is being carried out at the Experimental Engineered Test Facility at Los Alamos Laboratory by the Los Alamos and Sandia National Laboratories to develop a strategy to validate key geochemical and hydrological assumptions in performance assessment models used by the Yucca Mountain Site Characterization Project

  18. Surface modification of materials by ion implantations for industrial and medical applications. Final report of a co-ordinated research project

    International Nuclear Information System (INIS)

    2000-07-01

    The objectives of the Co-ordinated Research Project on Modification of Materials by Ion Treatment for Industrial Applications were to develop economically acceptable surface modification techniques leading to thick treated layers, to predict ion beam mixing and impurity atom migration during and after implantation, and to evaluate the tribological post-implantation properties and performance of treated components. This TECDOC summarises the current status and prospects in surface modification by ion implantation methodology and technology, providing new information in basic and applied research

  19. Surface modification of materials by ion implantations for industrial and medical applications. Final report of a co-ordinated research project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The objectives of the Co-ordinated Research Project on Modification of Materials by Ion Treatment for Industrial Applications were to develop economically acceptable surface modification techniques leading to thick treated layers, to predict ion beam mixing and impurity atom migration during and after implantation, and to evaluate the tribological post-implantation properties and performance of treated components. This TECDOC summarises the current status and prospects in surface modification by ion implantation methodology and technology, providing new information in basic and applied research.

  20. Characterization of materials for a reactive transport model validation experiment: Interim report on the caisson experiment. Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Siegel, M.D.; Cheng, W.C. [Sandia National Labs., Albuquerque, NM (United States); Ward, D.B.; Bryan, C.R. [Univ. of New Mexico, Albuquerque, NM (United States). Dept. of Earth and Planetary Sciences

    1995-08-01

    Models used in performance assessment and site characterization activities related to nuclear waste disposal rely on simplified representations of solute/rock interactions, hydrologic flow field and the material properties of the rock layers surrounding the repository. A crucial element in the design of these models is the validity of these simplifying assumptions. An intermediate-scale experiment is being carried out at the Experimental Engineered Test Facility at Los Alamos Laboratory by the Los Alamos and Sandia National Laboratories to develop a strategy to validate key geochemical and hydrological assumptions in performance assessment models used by the Yucca Mountain Site Characterization Project.

  1. Reference materials for microanalytical nuclear techniques. Final report of a co-ordinated research project 1994-1999

    International Nuclear Information System (INIS)

    2002-06-01

    A significant problem in the use of solid- and small-sample techniques is a general lack in suitable certified reference materials (CRM). Essentially, no CRM are certified for the small sample sizes typically used. Direct utilization of most existing CRM in solid sampling analysis procedures, typically 1 mg sample size, is often difficult or even impossible because trace components may not be sufficiently homogeneously distributed in the sample or their homogeneous distribution has not been tested. To explore the production, characterization and use of CRM for determinations with sample sizes much smaller than currently used, the Coordinated Research Program focused on selection of biological and environmental materials suitable for microanalytical techniques, definition of specifications for suitable CRM, evaluation of existing CRM for use with microanalytical techniques, evaluation of requirements for sample pre-treatment, evaluation of analytical techniques and research on development of techniques to be used in characterizing the homogeneity and chemical composition of small samples, and application of analytical techniques to the characterization of candidate reference materials for use with microanalytical techniques

  2. Pengaruh Pembelajaran Project Based Learning (PjBL pada Materi Ekosistem terhadap Sikap dan Hasil Belajar Siswa SMAN 2 Malang

    Directory of Open Access Journals (Sweden)

    Susriyati Mahanal

    2010-05-01

    Full Text Available The objective of this research was to know the effect of Project Based Learning (PjBL to the attitude and student cognitive achievement in SMAN 2 Malang. This research applied quasy experimental with non-equivalent control group design. The populations of this research is all student of class X SMAN 2 Malang on academic year 2008/2009. The samples of this research were class X7 as experimental (PjBL and class X8 as control (conventional. The instrument of this research namely cognitive achievement test and attitude scale questionnaire to river ecosystem. This research data are quantitative data consisted by score cognitive achievement and attitude scale questionnaire to river ecosystem, collected on 14 Maret until 31 May 2009. Data were analysed by bilinear covariant statistical analysis (Ancova, continued with LSD test. The result of this research indicated that there were PjBL toward the cognitive achievement and student attitude to river ecosystem. Students with PjBl having attitude higher 11,65% from conventional students. Beside, students with PjBl having cognitive achievement higher 81,05% from conventional students. Based on this research, the researcher suggest to the teacher that this strategy can be implemented in biology learning.   Kata kunci: Project Based Learning, sikap terhadap ekosistem sungai, hasil belajar

  3. Performance of engineered barrier materials in near surface disposal facilities for radioactive waste. Results of a co-ordinated research project

    International Nuclear Information System (INIS)

    2001-11-01

    The primary objectives of the CRP were to: promote the sharing of experiences of the Member States in their application of engineered barrier materials for near surface disposal facilities; help enhance their use of engineered barriers by improving techniques and methods for selecting, planning and testing performance of various types of barrier materials for near surface disposal facilities. The objective of this publication is to provide and overview of technical issues related to the engineered barrier systems and a summary of the major findings of each individual research project that was carried out within the framework of the CRP. This publication deals with a general overview of engineered barriers in near surface disposal facilities, key technical information obtained within the CRP and overall conclusions and recommendations for future research and development activities. Appendices presenting individual research accomplishments are also provided. Each of the 13 appendices was indexed separately

  4. Improvement of technical measures to detect and respond to illicit trafficking of nuclear and radioactive materials [Results of a coordinated research project 2003-2006

    International Nuclear Information System (INIS)

    2008-07-01

    This publication summarizes the research conducted during an IAEA Coordinated Research Project (CRP) undertaken to address technical and operational difficulties in the detection of and response to illicit trafficking of nuclear material. Equipment to detect illicit trafficking of nuclear and radioactive materials at borders has specific technical and operational requirements that are very different from equipment used in other radiation monitoring cases. Automated and manual measurements need to be done in the field, often outdoors, at land or sea borders, crossing points or airports. The free flow of goods and passengers must not be impacted, thus requiring that the measurement time be short. The design needs to take into account that the users of the equipment are not experts in radiation detection; thus the results of the measurements should be easy to understand

  5. Experimental studies and modelling of cation interactions with solid materials: application to the MIMICC project. (Multidimensional Instrumented Module for Investigations on chemistry-transport Coupled Codes)

    International Nuclear Information System (INIS)

    Hardin, Emmanuelle

    1999-01-01

    The study of cation interactions with solid materials is useful in order to define the chemistry interaction component of the MIMICC project (Multidimensional Instrumented Module for Investigations on chemistry-transport Coupled Codes). This project will validate the chemistry-transport coupled codes. Database have to be supplied on the cesium or ytterbium interactions with solid materials in suspension. The solid materials are: a strong cation exchange resin, a natural sand which presents small impurities, and a zirconium phosphate. The cation exchange resin is useful to check that the surface complexation theory can be applied on a pure cation exchanger. The sand is a natural material, and its isotherms will be interpreted using pure oxide-cation system data, such as pure silica-cation data. Then the study on the zirconium phosphate salt is interesting because of the increasing complexity in the processes (dissolution, sorption and co-precipitation). These data will enable to approach natural systems, constituted by several complex solids which can interfere on each other. These data can also be used for chemistry-transport coupled codes. Potentiometric titration, sorption isotherms, sorption kinetics, cation surface saturation curves are made, in order to obtain the different parameters relevant to the cation sorption at the solid surface, for each solid-electrolyte-cation system. The influence of different parameters such as ionic strength, pH, and electrolyte is estimated. All the experimental curves are fitted with FITEQL code based on the surface complexation theory using the constant capacitance model, in order to give a mechanistic interpretation of the ion retention phenomenon at the solid surface. The speciation curves of all systems are plotted, using the FITEQL code too. Systems with an increasing complexity are studied: dissolution, sorption and coprecipitation coexist in the cation-salt systems. Then the data obtained on each single solid, considered

  6. STRUCTURAL DESIGN CRITERIA FOR TARGET/BLANKET SYSTEM COMPONENT MATERIALS FOR THE ACCELERATOR PRODUCTION OF TRITIUM PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    W. JOHNSON; R. RYDER; P. RITTENHOUSE

    2001-01-01

    The design of target/blanket system components for the Accelerator Production of Tritium (APT) plant is dependent on the development of materials properties data specified by the designer. These data are needed to verify that component designs are adequate. The adequacy of the data will be related to safety, performance, and economic considerations, and to other requirements that may be deemed necessary by customers and regulatory bodies. The data required may already be in existence, as in the open technical literature, or may need to be generated, as is often the case for the design of new systems operating under relatively unique conditions. The designers' starting point for design data needs is generally some form of design criteria used in conjunction with a specified set of loading conditions and associated performance requirements. Most criteria are aimed at verifying the structural adequacy of the component, and often take the form of national or international standards such as the ASME Boiler and Pressure Vessel Code (ASME B and PV Code) or the French Nuclear Structural Requirements (RCC-MR). Whether or not there are specific design data needs associated with the use of these design criteria will largely depend on the uniqueness of the conditions of operation of the component. A component designed in accordance with the ASME B and PV Code, where no unusual environmental conditions exist, will utilize well-documented, statistically-evaluated developed in conjunction with the Code, and will not be likely to have any design data needs. On the other hand, a component to be designed to operate under unique APT conditions, is likely to have significant design data needs. Such a component is also likely to require special design criteria for verification of its structural adequacy, specifically accounting for changes in materials properties which may occur during exposure in the service environment. In such a situation it is common for the design criteria

  7. Hazardous materials in aquatic environments of the Mississippi River Basin. Quarterly project status report, July 1, 1993--September 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    This document is a brief progress report from each of the research and education projects that are currently funded through the ERWM contract. During third quarter 1993, approval was given by DOE for purchase of equipment. Equipment purchases were initiated and much of the equipment has been received and installed. The committees in charge of coordination of sampling and analyses associated with the collaborative research groups continued to meet and address these issues. Sampling has been done in the lower part of Devil`s Swamp and in the Devil`s Swamp Lake area. In addition, extensive sampling has been done in Bayou Trepagnier and in Bayou St. John. During this period, Tulane and Xavier Universities continued working closely with Oak Ridge National Laboratories (ORNL). The ORNL 1993 summer student internship program was completed. Plans were made for expanding the program to support 8 students next summer. Leonard Price, a Xavier University Chemistry professor and John Walz, a Tulane University Engineering professor each spent 5 weeks at ORNL. During this time these faculty worked with ORNL researchers exploring mutual interests and discussing possible future collaborations. In September, Drs. Carl Gehrs, Lee Shugart and Marshall Adams of ORNL, visited the Tulane and Xavier campuses. They presented two seminars and met with several of the investigators being supported by the ERWM contract. Tulane/Xavier project administrators participated in the Office of Technology Development`s ``New Technologies and Program Exhibition`` in the Rayburn House Office Building on September 23 and in the Hart Senate Office Building on September 27.

  8. Project, installation and operational tests of a pneumatic system for the IEA-R1 reactor materials

    International Nuclear Information System (INIS)

    Fernando, Alberto de Jesus; Madi Filho, Tufic

    2009-01-01

    Pneumatic Transfer Systems (PTS) are equipment broadly and world widely used for the transport, movement and transfer of diverse types of materials, objects and cargo between two or more environments, near or distant from each other [1]. Due to their flexibility and quickness, the system application is present in several areas, such as medicine (hospitals and clinic analyses laboratories); industry (automobile, metallurgy, iron-making. chemical, food production) commerce (gasoline stations, cinemas, supermarkets, banks, tolls, on-line commerce, casinos); public service (public institutions, courts). In the nuclear field, the PTS has, also, a vast application, highlighting its use in the radioisotope and radiopharmaceuticals of short half life production, such as 67 Ga, 201 Tl, 18F and 123 I-ultra pure. The development of this work is directed to the application of the Pneumatic Transfer System in transport and transfer of materials that will be irradiated in the IEA-R1 reactor, located in the Institute of Energetic and Nuclear Research, IPEN/CNEN-SP, for application of the Neutron Activation Analysis (NAA). (author)

  9. Exploring the Use of Educational Material About Shoulder Dysfunction: A Quality Improvement Project in People With Amyotrophic Lateral Sclerosis.

    Science.gov (United States)

    Burke, Katherine; Ellrodt, Amy Swartz; Levine, Jason; Adams, Taylor; Allis, Rebecca; Macmurdie, Ian; Paganoni, Sabrina

    2018-05-01

    Shoulder pain is a common secondary complication of amyotrophic lateral sclerosis (ALS) that can contribute to functional decline and decreased participation in daily activities. The purpose of this study was to assess the effectiveness of an educational brochure aimed at improving knowledge regarding shoulder pain and dysfunction in people with ALS. Participants completed a preintervention survey with questions regarding their knowledge of how ALS may affect their shoulders. After completing the presurvey, they were mailed a brochure that described shoulder health and range of motion and stretching exercises. Four weeks after receiving the brochure, participants were then asked to determine the effectiveness of the educational materials in terms of impact on shoulder-related knowledge and self-efficacy with regard to prevention of shoulder pain and dysfunction. More than 50% of participants reported pain, decreased range of motion, or weakness in at least one shoulder since being diagnosed with ALS. All participants were interested in receiving educational materials, and all agreed that the brochure was easy to interpret and understand, with most (87%) reporting that it was helpful. Educational brochures are one strategy to improve awareness about shoulder health and to educate patients with ALS about exercises that may help reduce shoulder pain and dysfunction.

  10. Project materials [Commercial High Performance Buildings Project

    Energy Technology Data Exchange (ETDEWEB)

    None

    2001-01-01

    The Consortium for High Performance Buildings (ChiPB) is an outgrowth of DOE'S Commercial Whole Buildings Roadmapping initiatives. It is a team-driven public/private partnership that seeks to enable and demonstrate the benefit of buildings that are designed, built and operated to be energy efficient, environmentally sustainable, superior quality, and cost effective.

  11. Replacement and Original Magnet Engineering Options (ROMEOs): A European Seventh Framework Project to Develop Advanced Permanent Magnets Without, or with Reduced Use of, Critical Raw Materials

    Science.gov (United States)

    Mcguiness, P.; Akdogan, O.; Asali, A.; Bance, S.; Bittner, F.; Coey, J. M. D.; Dempsey, N. M.; Fidler, J.; Givord, D.; Gutfleisch, O.; Katter, M.; Le Roy, D.; Sanvito, S.; Schrefl, T.; Schultz, L.; Schwöbl, C.; Soderžnik, M.; Šturm, S.; Tozman, P.; Üstüner, K.; Venkatesan, M.; Woodcock, T. G.; Žagar, K.; Kobe, S.

    2015-06-01

    The rare-earth crisis, which peaked in the summer of 2011 with the prices of both light and heavy rare earths soaring to unprecedented levels, brought about the widespread realization that the long-term availability and price stability of rare earths could not be guaranteed. This triggered a rapid response from manufacturers involved in rare earths, as well as governments and national and international funding agencies. In the case of rare-earth-containing permanent magnets, three possibilities were given quick and serious consideration: (I) increased recycling of devices containing rare earths; (II) the search for new, mineable, rare-earth resources beyond those in China; and (III) the development of high-energy-product permanent magnets with little or no rare-earth content used in their manufacture. The Replacement and Original Magnet Engineering Options (ROMEO) project addresses the latter challenge using a two-pronged approach. With its basis on work packages that include materials modeling and advanced characterization, the ROMEO project is an attempt to develop a new class of novel permanent magnets that are free of rare earths. Furthermore, the project aims to minimize rare-earth content, particularly heavy-rare-earth (HRE) content, as much as possible in Nd-Fe-B-type magnets. Success has been achieved on both fronts. In terms of new, rare-earth-free magnets, a Heusler alloy database of 236,945 compounds has been narrowed down to approximately 20 new compounds. Of these compounds, Co2MnTi is expected to be a ferromagnet with a high Curie temperature and a high magnetic moment. Regarding the reduction in the amount of rare earths, and more specifically HREs, major progress is seen in electrophoretic deposition as a method for accurately positioning the HRE on the surface prior to its diffusion into the microstructure. This locally increases the coercivity of the rather small Nd-Fe-B-type magnet, thereby substantially reducing the dependence on the HREs Dy and

  12. (Project 13-5292) Correlating thermal and mechanical coupling based multiphysics behavior of nuclear materials through in-situ measurements

    Energy Technology Data Exchange (ETDEWEB)

    Tomar, Vikas [Purdue Univ., West Lafayette, IN (United States)

    2016-03-15

    Irradiations and post characterization experiments were performed first on Zr samples. This step will help understand the effect of the 2.5% alloying elements on the behavior of Zircaloy-4 (PWR cladding material) when compared to pure Zr. Irradiation flux measurements and sample temperature calibrations were performed at different energies prior to the irradiation experiments. Irradiations were performed with two different energy regimes1: non-displacment energies and displacement energies. Time was also dedicated to optimize transmission electron microscopy (TEM) sample preparation conditions via electropolishing technique. This step is crucial to prepare TEM samples for the in-situ TEM/irradiation experiments (Year 2). In addition, Zircaloy-4 samples are being prepared for irradiation, and a setup is built by one of our collaborators (Dr. Mert Efe) to prepare ultrafine (UF) and nanocrystalline (NC) Zircaloy-4 samples for comparison with the commercial Zircaloy-4 samples.

  13. Direct calibration of GC/MS systems using SRM (Standard Reference Material) gas cylinders. Project report, January 1984-August 1985

    International Nuclear Information System (INIS)

    Byrd, G.D.; Richie, K.L.; Sniegoski, L.T.; White, E.

    1985-10-01

    A cryogenic trapping system has been developed for use in calibrating GC/MS systems for the analysis of volatile organic compounds. This system provides for direct Standard Reference Material (SRM) traceability on data generated on gaseous samples. The cryogenic trap is a coil of stainless steel tubing immersed in a cryogen to trap and preconcentrate organic species present in a gaseous sample. The trap also contains a heated injection port for the addition of isotopically labeled compounds for use in isotope dilution measurements. The first part of this research is concerned with the development of IDMS as an independent method for the quantification of analytes in gaseous samples to be used as standards. Results are presented for the determination of bromobenzene in nitrogen at nominal concentrations of 1 and 25 ppb. In the second part of the research, a calibration curve method was developed for using these standards in auditing the performance of GC/MS systems

  14. Low cost solar array project cell and module formation research area: Process research of non-CZ silicon material

    Science.gov (United States)

    1981-01-01

    Liquid diffusion masks and liquid applied dopants to replace the CVD Silox masking and gaseous diffusion operations specified for forming junctions in the Westinghouse baseline process sequence for producing solar cells from dendritic web silicon were investigated. The baseline diffusion masking and drive processes were compared with those involving direct liquid applications to the dendritic web silicon strips. Attempts were made to control the number of variables by subjecting dendritic web strips cut from a single web crystal to both types of operations. Data generated reinforced earlier conclusions that efficiency levels at least as high as those achieved with the baseline back junction formation process can be achieved using liquid diffusion masks and liquid dopants. The deliveries of dendritic web sheet material and solar cells specified by the current contract were made as scheduled.

  15. Performance Evaluation and Field Application of Porous Vegetation Concrete Made with By-Product Materials for Ecological Restoration Projects

    Directory of Open Access Journals (Sweden)

    Hwang-Hee Kim

    2016-03-01

    Full Text Available The purpose of this study was to evaluate the performance of porous vegetation concrete block made from blast furnace slag cement containing industrial by-products such as blast furnace slag aggregate and powder. The blocks were tested for void ratio, compressive strength and freeze-thaw resistance to determine the optimal mixing ratio for the porous vegetation block. An economic analysis of the mixing ratio showed that the economic efficiency increased when blast furnace slag aggregate and cement were used. Porous vegetation concrete blocks for river applications were designed and produced. Hydraulic safety, heavy metal elution and vegetation tests were completed after the blocks were applied in the field. The measured tractive force ranged between 7.0 kg/m2 for fascine revetment (vegetation revetment and 16.0 kg/m2 for stone pitching (hard revetment, which ensured sufficient hydraulic stability in the field. Plant growth was measured after the porous vegetation concrete block was placed in the field. Seeds began to sprout one week after seeding; after six weeks, the plant length exceeded 300 mm. The average coverage ratio reached as high as 90% after six weeks of vegetation. These results clearly indicated that the porous vegetation concrete block was suitable for environmental restoration projects.

  16. Thermophysical properties database of materials for light water reactors and heavy water reactors. Final report of a coordinated research project 1999-2005

    International Nuclear Information System (INIS)

    2006-06-01

    The IAEA Coordinated Research Project (CRP) on the Establishment of a Thermo-physical Properties Database for Light Water Reactors (LWRs) and Heavy Water Reactors (HWRs) started in 1999. It was included in the IAEA's Nuclear Power Programme following endorsement in 1997 by the IAEA's Technical Working Groups on Advanced Technologies for LWRs and HWRs (the TWG-LWR and the TWG-HWR). Furthermore, the TWG on Fuel Performance and Technology (TWG-FPT) also expressed its support. This CRP was conducted as a joint task within the IAEA's project on technology development for LWRs and HWRs in its nuclear power programme. Improving the technology for nuclear reactors through better computer codes and more accurate materials property data can contribute to improved economics of future plants by helping to remove the need for large design margins, which are currently used to account for limitations of data and methods. Accurate representations of thermo-physical properties under relevant temperature and neutron fluence conditions are necessary for evaluating reactor performance under normal operation and accident conditions. The objective of this CRP was to collect and systematize a thermo-physical properties database for light and heavy water reactor materials under normal operating, transient and accident conditions and to foster the exchange of non-proprietary information on thermo-physical properties of LWR and HWR materials. An internationally available, peer reviewed database of properties at normal and severe accident conditions has been established on the Internet. This report is intended to serve as a useful source of information on thermo-physical properties data for water cooled reactor analyses. The properties data have been initially stored in the THERSYST data system at the University of Stuttgart, Germany, which was subsequently developed into an internationally available Internet database named THERPRO at Hanyang University, Republic of Korea

  17. Research coordination meeting of the coordinated research project on analytical and experimental benchmark analyses of accelerator driven systems. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The Technical Meeting hosted at the Belarus National Academy of Sciences in Minsk by the Joint Institute of Power Engineering and Nuclear Research 'SOSNY' from 5-9 December 2005 was the kick-off Research Coordination Meeting (RCM) of the IAEA Coordinated Research Project (CRP) on 'Analytical and Experimental Benchmark Analyses of Accelerator Driven Systems (ADS)'. The CRP had received proposals for research agreements and contracts from scientists representing the following 25 institutions: Centro Atomico Bariloche, SCK CEN Mol, Instituto de Pesquisas Energeticas e Nucleares Sao Paulo, Joint Institute of Power Engineering and Nuclear Research SOSNY Minsk, China Institute of Atomic Energy, CEA Cadarache, CNRS Paris, FZ Rossendorf, FZ Karlsruhe, Budapest University of Technology and Economics, Politecnico di Torino, Japan Atomic Energy Agency, Nuclear Research and Consultancy Group (NRG) Petten, Pakistan Institute of Nuclear Science and Technology, AGH-University of Science and Technology Krakow, Institute of Atomic Energy Otwock/Swierk, ITEP Moscow, MEPHI Moscow, Kurchatov Institute, JINR Dubna, Universidad Politecnica de Madrid, CIEMAT Madrid, Royal Institute of Technology Stockholm, National Science Center 'Kharkov Institute and Technology', and Argonne National Laboratory). These institutions represent 18 IAEA Member States (i.e., Argentina, Belarus, Belgium, Brazil, China, France, Germany, Hungary, Italy, Japan, Netherlands, Pakistan, Poland, Russia, Spain, Sweden, Ukraine, USA), and one International Organization (JINR Dubna). The overall objective of the CRP is contributing to the generic R and D efforts in various fields common to innovative fast neutron system development, i.e., heavy liquid metal thermal hydraulics, dedicated transmutation fuels and associated core designs, theoretical nuclear reaction models, measurement and evaluation of nuclear data for transmutation, and development and validation of calculational methods and codes. Ultimately, the CRP

  18. Concept and Idea-Project for Yugoslav Low and Intermediate level Radioactive Waste Materials Final Disposal Facility

    International Nuclear Information System (INIS)

    Peric, A.

    1997-01-01

    Encapsulation of rad waste in a mortar matrix and displacement of such solidified waste forms into the shallow land burial system, engineered trench system type is suggested concept for the final disposal of low and intermediate level rad waste. The mortar-rad waste mixtures are cured in containers of either concrete or metal for an appropriate period of time, after which solidified rad waste-mortar monoliths are then placed in the engineered trench system, parallelepiped honeycomb structure. Trench consists of vertical barrier-walls, bottom barrier-floors, surface barrier-caps and permeable-reactive walls. Surroundings of the trench consists of buffer barrier materials, mainly clay. Each segment of the trench is equipped with the independent drainage system, as a part of the main drainage. Encapsulation of each filled trench honeycomb segment is performed with concrete cap. Completed trench is covered with impermeable plastic foil and soil leaner, preferably clay. Paper presents an overview of the final disposal facility engineered trench system type. Advantages in comparison with other types of final disposal system are given. (author)

  19. Pore Space investigation in natural and artificial materials: POSINAM (FP7-MC-IAPP) project (15.10.2009-14.10.2013)

    International Nuclear Information System (INIS)

    Parneix, J.C.; Bouchet, A.; Mazurier, A.; Ramirez, S.; Rassineux, F.; Siitari-Kauppi, M.; Ikonen, J.; Sammaljaervi, J.; Helariutta, K.; Sardini, P.; Bonifait, T.; Hellmuth, K.H.; Pret, D.; Gallier, J.; Shroff Rama, M.

    2012-01-01

    Document available in extended abstract form only. Waste storage requires the analysis of various types of materials in order to measure spatial relationship and connectivity of their pores as well as quantity, shape, and size. It is necessary to describe pore space, to model fluid transport and to identify the material composition in order to understand the 3D organisation of the solids and the pores, and to stabilise the structure of this material for its observation. To characterise heterogeneous spatial porosities of these materials a saturation technique with a 14 C- or 3 H PMMA resin was developed at HYRL. The method includes saturation of matrices with radiolabelled un-viscous methylmethacrylate MMA, irradiation polymerisation and auto-radiographic detection of the sawn surfaces. POSINAM project has been proposed by the SME called ERM due to the increasing need of porosity characterisation of geo-materials by large industrial companies. These demands consist of research applications that will be based on the enhancement of the knowledge on altered natural rocks or materials as well as, saturation and imaging techniques for characterising the porosity of these materials. Thus, there is an essential need for a transfer of technology and knowledge between HYDRASA/HYRL labs and ERM. The combination of developed skills by private and academic partner labs along with ERM represents an innovative means to solve industrial issues on quantification of porosity in materials. The objective of the research program is to produce realistic 3D models of natural and artificial materials including porosity distribution. To achieve this goal it is necessary: To improve knowledge of petrography on rocks, cements and soils, etc. related to porosity organization (HYDRASA). To characterize heterogeneous spatial porosities of these materials using a saturation technique with 14 C- or 3 H doped PMMA resin. To provide service for industries which need 3D models of their materials

  20. Neutron imaging: A non-destructive tool for materials testing. Report of a coordinated research project 2003-2006

    International Nuclear Information System (INIS)

    2008-09-01

    The enhancement of utilization of research reactors is one of the major objectives of the IAEA's project on Effective Utilization of Research Reactors. In particular, the improvement of existing installations for neutron imaging and the effective utilization of such facilities are intended. From the experience of Type A facilities, it is obvious that some investment is required to come from simple neutron imaging methods (film, track-etch foils) to the more enhanced ones. Related to the installation and operation of the whole reactor system, the volume of the investment for an imaging device is minor. Also compared to the installations for neutron scattering research, neutron imaging systems are relatively cheap, but very efficient in the use of the neutrons. Therefore, one of the aims of the CRP was to look for adapted solutions for the individual reactor installation and beam line. Specific Research Objectives: To optimize the neutron beams for imaging purpose using modern simulation techniques; To enhance the beam intensity using modern layout principles, neutron optics, like focusing and beam guides and filters; To develop a standardized, low cost, neutron image grabber and analyzer for efficient data collection that can be used with low intensity sources; To improve signal processing techniques used in neutron imaging applications. Expected Research Outputs: Neutron radiography is used at research reactor centres in many Member States, but the facilities are not optimized for attractive potential applications. This fact has been brought out at various discussion meetings. The CRP is aimed at improving the design of beam lines in terms of neutron collimation and intensity; Improvements in resolution are normally achieved at a cost in intensity. For an instrument exhibiting good resolution, one needs to employ a fast counting system. It is proposed to work along these lines to develop an optimised detection system. Many facilities, at present, have small CCD

  1. Materials identification and surveillance project item evaluation: Items, impure plutonium oxide (ATL27960) and pure plutonium oxide (PEOR3258)

    International Nuclear Information System (INIS)

    Allen, T.; Appert, Q.; Davis, C.

    1997-03-01

    In this report, Los Alamos scientists characterize properties relevant to storage of an impure plutonium oxide (74 mass % plutonium) in accordance with the Department of Energy (DOE) standard DOE-STD-3013-96. This oxide is of interest because it is the first impure plutonium oxide sample to be evaluated and it is similar to other materials that must be stored. Methods used to characterize the oxide at certain points during calcination include surface-area analyses, mass loss-on-ignition (LOI) measurements, elemental analysis, moisture-adsorption measurements, and quantitative supercritical-CO 2 extraction of adsorbed water. Significant decreases in the LOI and surface area occurred as the oxide was calcined at progressively increasing temperatures. Studies indicate that supercritical-CO 2 extraction is an effective method for removing adsorbed water from oxides. We extracted the water from powdered oxides (high-purity ZrO 2 , pure PuO 2 , and impure plutonium oxide) using CO 2 at 3000 psi pressure and 75 degrees C, and we quantitatively determined it by using gravimetric and dew-point procedures. The effectiveness of the extraction method is demonstrated by good agreement between the amounts of water extracted from pure zirconium and plutonium dioxides and the mass changes obtained from LOI analyses. However, the amount of moisture (0.025 mass %) extracted from the impure plutonium oxide after it had been calcined at 950 degrees C and stored for a period of months is much less than the LOI value (0.97 mass %). These results imply that the impure plutonium oxide is free of adsorbed water after calcination at 950 degrees C, even though the sample does not satisfy the LOI requirement of <0.50 mass % for storage

  2. Meeting of Energy Needs During the Period of Raw Materials Insufficiency in the 21st Century (Bulgaria, Czech Republic, Poland, Russia and Slovakia cooperation - draft of project

    International Nuclear Information System (INIS)

    Lelek, V.; Apostolov, T.; Petrov, B.; Chwaszcewski, S.; Andrzejewski, K.; Subbotin, S.; Tsibulskij, V.; Darilek, P.; Zajac, R.; Breza, J.

    2006-01-01

    The main aim of the work is to give into the mutual harmony long term planning of nuclear energy (contemporary power station has supposed lifetime 70 years and will need at least ten years from the decision to full realization) with the possibility of raw materials supply during the whole lifetime. But situation is not so uniquely directed only to nuclear energy - classical sources (coal, gas and oil) are supposed to be exhausted surely in this century (coal could be regionally dependent) and specially Europe will be practically net consumer of energy raw materials. Ways to stabilize market could be production of hydrogen and use of U238 and Th232 in the new reactors. But developments needed to influence practical industrial demand is about 30 years to be able to start to build up industrial new type nuclear power-stations and money of the order of several billion dollars. At the same time political unification has consequence on local raw material resources, which could hardly be interpreted only as the local or national ownership. Their price could sharply rise and there will be pressure to use it not only for energy production, but also as the chemical raw material. Moreover it is expected that in the half of this century the price of natural uranium will be limiting factor for the contemporary PWR reactors use and that there will be necessary to start fast breeders or use thorium fuel to cover demands. Last estimations about the oil peaking and its consequences are included. Armenia, Lithuania and Ukraine representatives expressed will to join the project. Common will is expressed in the presentation to try to understand commonly the future development and to find common solution to the future challenges (Authors)

  3. Law project on the radioactive materials and wastes management 2006 recommendations presented by Anne Duthilleul; Projet de loi sur la gestion des matieres et des dechets radioactifs 2006 avis presente par Mme Anne Duthilleul

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This document provides recommendations on the law project concerning the radioactive material and wastes management. It precises the law objectives, the french particularities concerning the radioactive wastes and materials management, the public debate in France, the evaluation of the researches, the recommendations of the economic and social council. (A.L.B.)

  4. Background Material

    DEFF Research Database (Denmark)

    Zandersen, Marianne; Hyytiäinen, Kari; Saraiva, Sofia

    This document serves as a background material to the BONUS Pilot Scenario Workshop, which aims to develop harmonised regional storylines of socio-ecological futures in the Baltic Sea region in a collaborative effort together with other BONUS projects and stakeholders.......This document serves as a background material to the BONUS Pilot Scenario Workshop, which aims to develop harmonised regional storylines of socio-ecological futures in the Baltic Sea region in a collaborative effort together with other BONUS projects and stakeholders....

  5. Particles, processes and materials for modern energy needs: Development of a DOE-EPSCoR project in Puerto Rico. Final report for September 30, 1997 - August 31, 2000

    Energy Technology Data Exchange (ETDEWEB)

    Weiner, Brad R.

    2000-09-29

    Twenty-eight (28) faculty researchers focused on High Energy Particle Physics, Novel Thin Film Materials for Optoelectronic Applications, and Catalytic Processes for Energy Sources and Environmental Detoxification to address problems cited as priorities by the DOE and local agencies. The High Energy Particle Physics cluster has DOE-competitive funding, and the number of cluster investigators who have competitive mainstream funding has increased from 2 to 13 since the inception of the program. In this reporting period, 8 postdoctorals, 38 graduate studnets, and 23 undergraduates were involved in DOE projects, and 191 publications and 238 presentations were generated. The UPR-Arecibo Integrated Science Multi-Use Laboratory provided workshops and other activities that directly impacted 360 teachers and 600 students and indirectly impacted over 25,000 through the enhancement of teachers' skills and knowledge.

  6. The direct-Mat Project: Dismantling and Recycling Techniques for road Materials. Sharing Knowledge and Practices; El proyecto DIRECT-MAT: Tecnicas de demolicion y reciclado de materiales para la carretera-Compartiendo conocimientos y practicas

    Energy Technology Data Exchange (ETDEWEB)

    Sinis Fernandez, F.; Rubio guzman, B.; Gonzalez Abadias, A. I.

    2011-07-01

    This article describes the content of the DIRECT-MAT (Dismantling and Recycling for road Materials) project. the DIRECT MAT project objectives consist of sharing and disseminating, at the European scale, national knowledge and field practices regarding the dismantling and recycling of road and road related materials, for the benefit of all European countries. Road material recycling processes have previously been studied in national research projects in the last years; unfortunately, the results of those projects almost never benefit other European countries. This is especially true for the newer Member States. The DIRECT-MAT project, within 7{sup t}h Framework Programme, is a three year project starting in 2009, and is comparised of 20 partners from 15 participating countries. to reach the aims of the project, a WEB database will be created to compile and display the extensive and already validated research and job site data and a set of Best Practices Guides on dismantling and recycling of different types of materials will be issued. Finally, guidelines will be proposed to ensure database updating, including the results of future researches. (Author) 6 refs.

  7. Information on Coordinated Research Project: Behaviours of Cementitious Materials in Multipurpose Packaging for Transportation, Long Term Storage and Disposal

    International Nuclear Information System (INIS)

    Meyer, W.

    2013-01-01

    The durability of concrete is an important issue and the imaging thereof plays a major part in the understanding of the characteristics of concrete. The ability of concrete to withstand the penetration of liquid and oxygen contribute to the durability of concrete. The durability of concrete, can in turn, be quantified by certain characteristics such as the porosity, sorptivity and permeability. For non-destructive analytical quantification of these parameters, neutron radiography was developed and validated against conventional measurements. Results indicated that because the neutron attenuation of the concrete and water differs to a significant degree, the movement of water in concrete (sorptivity) could be visualized. The neutron radiography results were validated against conventional measurements and excellent correlation was found. To improve the characteristics of current grout/cement matrixes used for the encapsulation of radioactive waste, different cement mixtures Cem 1 (96% OPC) and Cem 5 (mixture of 20% fly ash, 20% blast furnace slag and 60% cement powder) with the addition of different admixtures, inert fibre material and plasticizers were investigated. With no formal guidance from the WAC of the disposal site, it was decided that the following matrix requirements have to be met in order to qualify a possible matrix for radioactive waste immobilisation research: -Total porosity less than 10% (Implies a compression strength higher than 50 MPa) and -Sorptivity rate lower than 2.5 g/h (Implies pore structure not interlinked). Results with radioactive waste (excluding organic waste) indicated an admixture of bitumen or asphalt in CEM 1 (96% OPC cement) has the best characteristics and comply with the specified requirement. Treatment of contaminated organic waste which is a non standard waste stream proved to be difficult and direct disposal is also not an option because many organic liquids are immiscible. Cementation is generally not an option as the

  8. High-etch-rate bottom-antireflective coating and gap-fill materials using dextrin derivatives in via first dual-Damascene lithography process

    Science.gov (United States)

    Takei, Satoshi; Sakaida, Yasushi; Shinjo, Tetsuya; Hashimoto, Keisuke; Nakajima, Yasuyuki

    2008-03-01

    The present paper describes a novel class of bottom antireflective coating (BARC) and gap fill materials using dextrin derivatives. The general trend of interconnect fabrication for such a high performance LSI is to apply cupper (Cu)/ low-dielectric-constant (low-k) interconnect to reduce RC delay. A via-first dual damascene process is one of the most promising processes to fabricate Cu/ low-k interconnect due to its wide miss-alignment margin. The sacrificial materials containing dextrin derivatives under resist for lithography were developed in via-first dual damascene process. The dextrin derivatives in this study was obtained by the esterification of the hydroxyl groups of dextrin resulting in improved solubility in the resist solvents such as propylene glycol monomethylether, propylene glycol monomethylether acetate, and ethyl lactate due to avoid the issue of defects that were caused by incompatability. The etch rate of our developed BARC and gap fill materials using dextrin derivatives was more than two times faster than one of the ArF resists evaluated in a CF4 gas condition using reactive ion etching. The improved etch performance was also verified by comparison with poly(hydroxystyrene), acrylate-type materials and latest low-k materials as a reference. In addition to superior etch performance, these materials showed good resist profiles and via filling performance without voids in via holes.

  9. Evaluation of Dredged Material Proposed for Ocean Disposal from Federal Projects in New York and New Jersey and the Military Ocean Terminal (MOTBY)

    Energy Technology Data Exchange (ETDEWEB)

    Barrows, E.S.; Antrim, L.D.; Pinza, M.R.; Gardiner, W.W.; Kohn, N.P.; Gruendell, B.D.; Mayhew, H.L.; Word, J.Q.; Rosman, L.B. [Battelle Marine Sciences Laboratory, Sequim, Washington (United States)

    1996-08-01

    The U.S. Army Corps of Engineers (USACE) is authorized by Section 103 of the Marine Protection, Research, and Sanctuaries Act of 1972 (MPRSA), Public Law 92-532, and by the Clean Water Act of 1972 (CWA) and Amendments of 1977 to permit, evaluate, and regulate the disposal of dredged material in ocean waters to minimize adverse environmental effects. Compliance with the regulations of the MPRSA calls for physical and biological testing of sediment proposed for dredging prior to its disposal in ocean waters. The testing required by the MPRSA criteria is conducted under a testing manual developed by the USACE and the U.S. Environmental Protection Agency (EPA), Evaluation of Dredged Material Proposed for Ocean Disposal (Testing Manual), commonly referred to as the `Green Book.` Testing protocols in the Green Book include bulk sediment analysis, grain size analysis, elutriate testing, and biological testing. The biological testing includes bioassays for acute toxicity as well as analysis to determine bioaccumulation of certain contaminants by marine organisms. The objective of the USACE-NYD Federal Projects Program was to evaluate sediment proposed for dredging and unconfined ocean disposal at the Mud Dump Site. The results of analytical measurements and bioassays performed on the test sediments were compared with analyses of sediment from the Mud Dump Reference Site to determine whether the test sediments were acutely toxic to marine organisms or resulted in statistically significantly greater bioaccumulation of contaminants in marine organisms, relative to the reference sediment. Testing for the federal project areas was performed according to the requirements.

  10. The use of Web-based GIS data technologies in the construction of geoscience instructional materials: examples from the MARGINS Data in the Classroom project

    Science.gov (United States)

    Ryan, J. G.; McIlrath, J. A.

    2008-12-01

    Web-accessible geospatial information system (GIS) technologies have advanced in concert with an expansion of data resources that can be accessed and used by researchers, educators and students. These resources facilitate the development of data-rich instructional resources and activities that can be used to transition seamlessly into undergraduate research projects. MARGINS Data in the Classroom (http://serc.carleton.edu/ margins/index.html) seeks to engage MARGINS researchers and educators in using the images, datasets, and visualizations produced by NSF-MARGINS Program-funded research and related efforts to create Web-deliverable instructional materials for use in undergraduate-level geoscience courses (MARGINS Mini-Lessons). MARGINS science data is managed by the Marine Geosciences Data System (MGDS), and these and all other MGDS-hosted data can be accessed, manipulated and visualized using GeoMapApp (www.geomapapp.org; Carbotte et al, 2004), a freely available geographic information system focused on the marine environment. Both "packaged" MGDS datasets (i.e., global earthquake foci, volcanoes, bathymetry) and "raw" data (seismic surveys, magnetics, gravity) are accessible via GeoMapApp, with WFS linkages to other resources (geodesy from UNAVCO; seismic profiles from IRIS; geochemical and drillsite data from EarthChem, IODP, and others), permitting the comprehensive characterization of many regions of the ocean basins. Geospatially controlled datasets can be imported into GeoMapApp visualizations, and these visualizations can be exported into Google Earth as .kmz image files. Many of the MARGINS Mini-Lessons thus far produced use (or have studentss use the varied capabilities of GeoMapApp (i.e., constructing topographic profiles, overlaying varied geophysical and bathymetric datasets, characterizing geochemical data). These materials are available for use and testing from the project webpage (http://serc.carleton.edu/margins/). Classroom testing and assessment

  11. FY 1990 Report on the results of the research and development project for the industrial base technologies of the next generation. Research and development of nonlinear optoelectronic materials; 1990 nendo hisenkei hikari denshi zairyo no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-03-01

    Described herein are the FY 1990 results of the research and development project for the optoelectronic materials, implemented to cope with the highly information-oriented societies. The FY 1990 is the second year for the phase-I project of the basic plan, and the R and D efforts are directed to elucidation of the mechanisms involved in the nonlinear phenomena, exploration and designs of various materials, and investigations of the technologies for, e.g., the material synthesis and evaluation. The themes to be investigated by the long-term project include exploration and preparation of the superfine particles and base materials for the organic materials; and crystal growth, dispersion of the fine particles and development of the superlattices for development of the materials. The comprehensive investigation and research program investigates the trends of the related technologies, both domestic and foreign. A total of 9 research themes are recommissioned to 9 enterprises. They include organic, low-molecular-weight materials, growth of orientation-controlled crystals, films of high-molecular-weight organic conjugated compounds, glass-dispersed materials (prepared by the vapor-phase, impregnation of porous glass, sol-gel, superlow-melting glass and super-cooling methods), organic dispersed materials, development of the organic superlattices, and development of the three-dimensional superstructures. (NEDO)

  12. IAEA Coordinated Research Project on the Establishment of a Material Properties Database for Irradiated Core Structural Components for Continued Safe Operation and Lifetime Extension of Ageing Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Borio Di Tigliole, A.; Schaaf, Van Der; Barnea, Y.; Bradley, E.; Morris, C.; Rao, D. V. H. [Research Reactor Section, Vianna (Australia); Shokr, A. [Research Reactor Safety Section, Vienna (Australia); Zeman, A. [International Atomic Energy Agency, Vienna (Australia)

    2013-07-01

    Today more than 50% of operating Research Reactors (RRs) are over 45 years old. Thus, ageing management is one of the most important issues to face in order to ensure availability (including life extension), reliability and safe operation of these facilities for the future. Management of the ageing process requires, amongst others, the predictions for the behavior of structural materials of primary components subjected to irradiation such as reactor vessel and core support structures, many of which are extremely difficult or impossible to replace. In fact, age-related material degradation mechanisms resulted in high profile, unplanned and lengthy shutdowns and unique regulatory processes of relicensing the facilities in recent years. These could likely have been prevented by utilizing available data for the implementation of appropriate maintenance and surveillance programmes. This IAEA Coordinated Research Project (CRP) will provide an international forum to establish a material properties Database for irradiated core structural materials and components. It is expected that this Database will be used by research reactor operators and regulators to help predict ageing related degradation. This would be useful to minimize unpredicted outages due to ageing processes of primary components and to mitigate lengthy and costly shutdowns. The Database will be a compilation of data from RRs operators' inputs, comprehensive literature reviews and experimental data from RRs. Moreover, the CRP will specify further activities needed to be addressed in order to bridge the gaps in the new created Database, for potential follow-on activities. As per today, 13 Member States (MS) confirmed their agreement to contribute to the development of the Database, covering a wide number of materials and properties. The present publication incorporates two parts: the first part includes details on the pre-CRP Questionnaire, including the conclusions drawn from the answers received from

  13. IAEA Coordinated Research Project on the Establishment of a Material Properties Database for Irradiated Core Structural Components for Continued Safe Operation and Lifetime Extension of Ageing Research Reactors

    International Nuclear Information System (INIS)

    Borio Di Tigliole, A.; Schaaf, Van Der; Barnea, Y.; Bradley, E.; Morris, C.; Rao, D. V. H.; Shokr, A.; Zeman, A.

    2013-01-01

    Today more than 50% of operating Research Reactors (RRs) are over 45 years old. Thus, ageing management is one of the most important issues to face in order to ensure availability (including life extension), reliability and safe operation of these facilities for the future. Management of the ageing process requires, amongst others, the predictions for the behavior of structural materials of primary components subjected to irradiation such as reactor vessel and core support structures, many of which are extremely difficult or impossible to replace. In fact, age-related material degradation mechanisms resulted in high profile, unplanned and lengthy shutdowns and unique regulatory processes of relicensing the facilities in recent years. These could likely have been prevented by utilizing available data for the implementation of appropriate maintenance and surveillance programmes. This IAEA Coordinated Research Project (CRP) will provide an international forum to establish a material properties Database for irradiated core structural materials and components. It is expected that this Database will be used by research reactor operators and regulators to help predict ageing related degradation. This would be useful to minimize unpredicted outages due to ageing processes of primary components and to mitigate lengthy and costly shutdowns. The Database will be a compilation of data from RRs operators' inputs, comprehensive literature reviews and experimental data from RRs. Moreover, the CRP will specify further activities needed to be addressed in order to bridge the gaps in the new created Database, for potential follow-on activities. As per today, 13 Member States (MS) confirmed their agreement to contribute to the development of the Database, covering a wide number of materials and properties. The present publication incorporates two parts: the first part includes details on the pre-CRP Questionnaire, including the conclusions drawn from the answers received from the MS

  14. Development, Implementation, and Assessment of Climate Curricular Materials for Introductory Undergraduates: Lessons Learned from the InTeGrate Project's Climate of Change Module

    Science.gov (United States)

    Walker, B.; Fadem, C. M.; Shellito, L. J.

    2014-12-01

    Designing climate change curricular materials suitable for wide adoption across institutions and academic disciplines (including those outside of the geosciences) requires collaboration among faculty at different types of institutions and consideration of a variety of student populations, learning styles, and course formats. The Interdisciplinary Teaching of Geoscience for a Sustainable Future (InTeGrate) project, an NSF STEP Center program, provides opportunities for faculty to develop 2-3 week teaching modules to engage students in understanding the intersections between geoscience topics and societal issues. From 2012-2014, a team of 3 faculty from a liberal arts college, comprehensive university, and community college developed, implemented, assessed, and revised a 2-3 week module for introductory undergraduates entitled "Climate of change: interactions and feedbacks between water, air, and ice". The module uses authentic atmosphere, ocean, and cryosphere data from several regions to illustrate how climate impacts human societies and that the climate system has interacting components complicated by feedbacks, uncertainties, and human behavioral decisions. Students also consider past and present human adaptations to climate fluctuations. The module was piloted in introductory geology, meteorology, and oceanography courses during the 2012-2013 academic year, during which time formative and summative assessments were administered and used to modify the curricular materials. We will provide an overview of the module's content, instructional strategies involved in implementing the module, and methods of formative and summative assessment. We will also report on lessons learned during the development, piloting, revision, and publishing process, the importance of fostering partnerships between faculty from different institution types, and design approaches that promote widespread adoption of climate curricular materials.

  15. Nuclear Desalination Demonstration Project (NDDP) in India

    International Nuclear Information System (INIS)

    Tewari, P.K.; Misra, B.M.

    2001-01-01

    In order to gainfully employ the years of experience and expertise in various aspects of desalination activity, BARC (India) has undertaken installation of a hybrid nuclear desalination plant coupled to 170 MW(e) PHWR station at Kalpakkam, Chennai in the Southeast coast of India. The integrated system, called the Nuclear Desalination Demonstration Project (NDDP), will thus meet the dual needs of process water for nuclear power plant and drinking water for the neighbouring people. NDDP aims for demonstrating the safe and economic production of good quality water by nuclear desalination of seawater. It comprises a 4500 m 3 /d Multistage Flash (MSF) and a 1800 m 3 /d Reverse Osmosis (RO) plant. MSF section uses low pressure steam from Madras Atomic Power Station (MAPS), Kalpakkam. The objectives of the NDDP (Kalpakkam) are as follows: to establish the indigenous capability for the design, manufacture, installation and operation of nuclear desalination plants; to generate necessary design inputs and optimum process parameters for large scale nuclear desalination plant; to serve as a demonstration project to IAEA welcoming participation from interested member states. The hybrid plant is envisaged to have a number of advantages: a part of high purity desalted water produced from MSF plant will be used for the makeup demineralised water requirement (after necessary polishing) for the power station; blending of the product water from RO and MSF plants would provide requisite quality drinking water; the RO plant will continue to be operated to provide the water for drinking purposes during the shutdown of the power station

  16. Blades and disks in gas turbines. Material and component behaviour. Project department D. Final report; Schaufeln und Scheiben in Gasturbinen. Werkstoff- und Bauteilverhalten. Projektbereich D. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    The Special Research Department No. 339, ``Disks and Blades in Gas Turbines - Material and Component Characteristics`` received financial support from 1988 through 1996. This final report discusses activities of the years 1994, 1995, and 1996. Project group D, ``Production and Quality Assurance``, investigated rotors and blades. Grinding techniques were developed and optimized for nickel base materials, and the effects of grinding on the marginal zones was investigated, including an analysis of intrinsic stresses induced by machining. In the field of ceramics, separation and production of reinforced ceramics was investigated, and techniques for vacuum soldering of ceramic/ceramic and ceramic/metal compounds for high-temperature applications were developed. In the framework of a part-project carried out at HMI, neutron diffraction was used for nondestructive analysis of volume intrinsic stresses near the joint both on model geometries and on the joint between metal shaft and ceramic rotor. The development and application of computerized tomography for testing of ceramic rotors and joints was an important contribution to quality assurance. (orig./MM) [Deutsch] Der Sonderforschungsbereich 339 `Schaufeln und Scheiben in Gasturbinen - Werkstoff- und Bauteilverhalten` wurde von 1988 bis Ende 1996 gefoerdert. Der vorliegende Abschlussbericht behandelt vor allem die Arbeiten der Jahre 1994, 1995 und 1996. Am Bauteil Rotor und Schaufel orientierten sich die Arbeiten des Projektbereichs D `Fertigung und Qualitaetssicherung`. Zum einen wurden hier Schleifverfahren fuer Nickelbasis-Werkstoffe entwickelt und optimiert und der Einfluss der Schleifbearbeitung auf die Randzoneneigenschaften studiert. Zur Randzonencharakterisierung gehoerte insbesondere auch die Analyse bearbeitungsinduzierter Eigenspannungen. Auf der Seite der Keramiken wurde zum einen die trennende Fertigung verstaerkter Keramiken untersucht. Zum anderen wurden Techniken fuer das Hochvakuumloeten von Keramik

  17. Integration of nuclear spectrometry methods as a new approach to material research. Final report of a coordinated research project 2006-2009

    International Nuclear Information System (INIS)

    2011-10-01

    In 2006, the IAEA initiated a coordinated research project (CRP) on 'Unification of Nuclear Spectrometries: Integrated Techniques as a New Tool for Material Research' as one of the elements of a project on 'Improvements in Nuclear Spectrometry Applications'. The major objective was to assist laboratories in Member States in enhancing proper utilization of nuclear analytical methods and to help them develop nuclear instruments for special applications. An overall objective of the CRP was to help Member States to improve characterization of materials by the effective utilization of nuclear spectrometry instruments and techniques as well as by developing integrated/unified instruments and analytical methodologies in support of environmental pollution monitoring, industry, study of cultural heritage, human health, agriculture, etc. These techniques can be used in small laboratories as well as in state of the art synchrotron sources. The specific research objectives of the CRP included development (or upgrading) of integrated multifunctional instruments based on nuclear spectrometries and related techniques as well as development of software for the handling and operation of integrated multifunctional instruments, including data acquisition. The CRP also covered: development (or upgrading) of integrated analytical approaches/methodologies and software for processing and presentation of data collected by multifunctional instruments; extension of the applications of integrated/unified instruments; and synergistic and complementary use of nuclear spectrometries, with the aim of assisting end users of nuclear spectrometries in various fields. The CRP covered a period of four years (2006-2009). Twelve laboratories from both developed and developing Member States and the IAEA's Laboratories participated. The first research coordination meeting (RCM) was held in Vienna, from 16 to 20 April 2007. The participants presented progress reports, reviewed the status of the

  18. 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)

  19. FY 1992 Report on the results of the research and development project for the industrial base technologies of the next generation. Research and development of nonlinear optoelectronic materials; 1992 nendo hisenkei hikari denshi zairyo no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-03-01

    Described herein are the FY 1992 results of the research and development project for the optoelectronic materials. The FY 1992 is the last year for the phase-I project of the basic plan, and the results are evaluated mainly viewed from extent of attainment of the interim targets. For the organic materials, the highly unique chiral nonlinear compounds are further developed, and direction for the investigations of the conjugated low-molecular-weight compounds is established. The excellent high-molecular-weight films are developed. For the dispersed materials, those developed include CuCl-dispersed glass, CdTe laminated glass developed by the laser evaporation method, glass dispersed with semiconductors at high concentrations, and dispersed materials with high-molecular-weight materials as the matrices. For the material development, those technologies investigated are orientation controlling of the crystals for thin organic films, and development of superlattices. A total of 9 research themes are recommissioned to 9 enterprises. They include organic, low-molecular-weight materials, growth of orientation-controlled crystals, films of high-molecular-weight organic conjugated compounds, glass-dispersed materials (prepared by the vapor-phase, impregnation of porous glass, sol-gel, superlow-melting glass and super-cooling methods), organic dispersed materials, development of the organic superlattices, and development of the three-dimensional superstructures. (NEDO)

  20. Conclusions of the DIRECT-MAT project: Dismantling and recycling techniques for road materials; Conclusiones del proyecto DIRECT-MAT: Tecnicas de demolicion y reciclado de materiales para la carretera

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Abadias, A. I.; Ruiz-Aucar Berlinches, E.; Sinis Fernandez, F.

    2012-07-01

    DIRECT-MAT (Dismantling and Recycling Techniques for road Materials) is a research project included in the 7{sup t}h Framework Programme of the EU, which counted with the participation of 20 partners from 15 different European countries. The Transport Research Centre of CEDEX (Spain) has been part of this project that began in January 2009. The aim of the DIRECT-MAT project has been to enable that national experience in the field of demolition and recycling of materials related to roads can be shared and disseminated among European countries for the benefit of all of them. In 2011 the paper the Direct-Mat Project: Dismantling and recycling techniques for road materials. Sharing knowledge and practices was published in the number 161 of Ingenieria Civil magazine. That paper consisted of an extensive description of the project, explaining in detail its structure, the status of the work in early 2011 and the conclusions drawn from the milestones (review of existing national documents). This paper is a continuation of the one previously published. This this article describes the work carried out since then and the collisions of the project. During this time, the main activities have been the compilation of several case studies and the developing of best practice guides. Regarding the results of the project, it is important to mention the database in which all the information gathered during the project is being uploads. Soon, it will have free online access. This database in perhaps the most remarkable results of the project, as it represents an invaluable reference tool for all the stake holders interested in the wide variety of recycling techniques that are being carried out today in Europe. (Author) 8 refs.

  1. Tulane/Xavier Center for Bioenvironmental Research; project: hazardous materials in aquatic environments; subproject: biomarkers and risk assessment in Bayou Trepagnier, LA

    International Nuclear Information System (INIS)

    Ide, C.

    1996-01-01

    Tulane and Xavier Universities have singled out the environment as a major strategic focus for research and training for now and beyond the year 2000. the Tulane/Xavier Center for Bioenvironmental Research (CBR) was established in 1989 as the umbrella organization to coordinate environmental research at both universities. CBR projects funded by the DOE under the Hazardous Materials in Aquatic Environments grant are defining the following: (1) the complex interactions that occur during the transport of contaminants through wetlands environments, (2) the actual and potential impact of contaminants on ecological systems and health, (3) the mechanisms and new technologies through which these impacts might be remediated, and (4) new programs aimed at educating and training environmental workers of the future. The subproject described in this report, 'Biomarkers and Risk Assessment in Bayou Trepagnier, LN', is particularly relevant to the US Department of Energy's Environmental Restoration and Waste Management program aimed at solving problems related to hazard monitoring and clean-up prioritization at sites with aquatic pollution problems in the DOE complex

  2. 24 CFR 245.416 - Initial submission of materials to HUD: Conversion from project-paid utilities to tenant-paid...

    Science.gov (United States)

    2010-04-01

    ... projects, and utility rate information, as obtained from the utility supplier; (iv) The estimated monthly... HUD: Conversion from project-paid utilities to tenant-paid utilities or a reduction in tenant utility... AUTHORITIES TENANT PARTICIPATION IN MULTIFAMILY HOUSING PROJECTS Procedures for Requesting Approval of a...

  3. The New York State Program for the Conservation and Preservation of Library Research Materials. Selected Press Clippings about Projects Funded by the Discretionary Grant Program, 1988/89 and 1989/90.

    Science.gov (United States)

    New York State Library, Albany. Div. of Library Development.

    This document is composed of clippings from news publications and press releases about projects funded by the New York State Discretionary Grant Program for Conservation and Preservation of Library Research Materials, which annually awards $500,000 to libraries, archives, historical societies, and similar agencies in New York State through…

  4. A lifetime extension project for the PHENIX reactor: additional knowledge regarding the in-service behaviour of its materials and structures

    International Nuclear Information System (INIS)

    Martin, P.; Jerrige, L.; Forgeron, T.; Devos, J.

    2000-01-01

    The PHENIX Life Extension Project groups together all the actions required to pursue operation of the reactor, particularly with a view to performing irradiation experiments in the framework of the back-end of the fuel cycle programs. As such, it comprises a series of investigations whose objective is to assess the state of the reactor after about one hundred thousand hours of operation. The following points have been particularly investigated: the materials behavior (austenitic, austeno-ferritic, and ferritic steels base metal, welds, heat affected zones) in terms of thermal aging and its effect on mechanical properties, embrittlement, sensitiveness to corrosion (in normal and incidental environment), and radiation effect on the potentially exposed structures. Furthermore, specific programs have been devoted to the assessment of thermo-mechanical response of some particular components. This concerns some types of welds with regard to fatigue or creep fatigue, some parts of large shells with regard to ratchetting and buckling, and main secondary piping. An extensive program was dedicated to the recovery of the thermo-mechanical damage undergone by the structures and its extrapolation to the future. This has led to consider in details thermo-hydraulic effects such as fluctuations in streams and bedding zones. Some intergranular cracking of welded joints had to be closely examined; this was achieved by a research work that has produced important advancements in that field. With the aim of evaluating potential defects, real progresses have been made in the knowledge of large defect's behavior in thin shells. The feedback of the examination and studies was also derived in terms of relevance of manufacturing, exploitation and monitoring conditions. It is believed that this experience will be useful for future design rules. (author)

  5. Commissioning of calorimeter in radiochemical laboratory for non-destructive assay of special nuclear materials

    International Nuclear Information System (INIS)

    Patra, S.; Mhatre, A.M.; Agarwal, C.; Chaudhury, S.; Pujari, P.K.

    2017-01-01

    Accounting of special nuclear materials (SNM) in every stages of nuclear fuel cycle is a necessity where one needs the quantitative estimation of SNM in variety of samples like sealed containers or finished products without altering its physical and chemical form. Non-destructive assay (NDA) techniques are capable of assaying such samples by the way of measuring passive/active neutrons/gamma rays or by the measurement of decay heat. Radiochemistry Division has been actively involved in the development and deployment of various NDA methodologies for meeting the demand of nuclear material accounting as and when required. Recently a radiometric calorimeter, developed by Reactor Control Division, E and I Group, BARC, has been installed in Lab C-33, Radiochemistry Division

  6. Law project of program relative to the management of radioactive materials and wastes; Projet de Loi, de programme relatif a la gestion des matieres et des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Villepin, D. de; Breton, T

    2006-03-15

    The law of the 30 December 1991 defined three axis of researches and fixed a the legal aspects of the researches programs management. Based on these researches results a law project has been defined. The first part of the document presents the objectives of the law project and discusses the different articles. The second part is devoted to the text of the law project. (A.L.B.)

  7. Regional Applied Research Effort Project (RARE) with Region 8 - Beneficial Use of Red and Brown Mud and Phosphogypsum as Alternative Construction Materials

    Science.gov (United States)

    Red and brown muds are the secondary materials generated from the extraction of alumina from bauxite, an aluminum-containing sedimentary rock (Ref. 2). Phosphogypsum is the secondary material generated by the phosphorous fertilizer industry from phosphate-containing sedimentary ...

  8. SMART GROUND Project: SMART data collection and inteGRation platform to enhance availability and accessibility of data and infOrmation in the EU territory on SecoNDary Raw Materials

    Science.gov (United States)

    Rossetti, Piergiorgio; Antonella Dino, Giovanna; de la Feld, Marco; Pizza, Antonietta; Coulon, Frederic; Wagland, Stuart; Gomes, Diogo

    2016-04-01

    The issue of resource security has come to the forefront of the debate over recent years, partly due to considerable concern over the security of supply of the so called 'critical' materials, with rare earths attracting the greatest attention in the press. Their supply is fundamental to maintain and develop EU economy and its industries relied on a steady supply of Raw Materials. Thus considering the increasing scarcity and raising prices of both, energy raw materials and other raw materials, such as metals and minerals, the recycling and recovery of these materials from anthropogenic deposits such as landfills is of increasing relevance. Europe has somewhere between 150,000 and 500,000 landfill sites, with an estimated 90% of them being "non-sanitary" pre-dating the EU Landfill Directive of 1999. Thus historical background makes the numerous old waste dumps as possible sources of critical and secondary raw materials (SRM and CRM). However, to date there is no inventory available of SRM and CRM present in EU landfills, and best management practices to recover SRM from landfill activities are inefficient. In this context, the EU SMART GROUND (SG) project (Grant Agreement No 641988) intends to foster resource recovery in landfills by improving both the availability and the accessibility of data and information on SRM in the EU and creating synergies among the different stakeholders involved in the SRM value chain. To do so, the project aims to collect and integrate in a single EU databank (SMART GROUND Data Bank) all the data from existing databases and new information retrieved during project activities. Such data will be collected from the different waste streams including municipal, industrial and mining wastes across EU landfills. It will improve data gathering on SRM from different types of waste, by defining new and integrated data acquisition methods and standards. At last, but not least, the project will also improve the SRM economic and employment potential

  9. Swedish projects

    International Nuclear Information System (INIS)

    Thunell, J.

    1992-01-01

    A description is given of research activities, concerning heating systems, which were carried out in Sweden during 1991. The main subject areas dealt with under the gas technology group within the area of heating systems were catalytic combustion, polyethylene materials, and gas applications within the paper and pulp industries. A list is given of the titles of project reports published during 1991 and of those begun during that year. Under the Swedish Centre for Gas Technology (SGC), the main areas of research regarding gas applications were polyethylene materials, industrial applications and the reduction of pollutant emissions. A detailed list is given of research projects which were in progress or proposed by March 1992 under the heating system gas technology research group in Sweden. This list also presents the aims and descriptions of the methods, etc. (AB)

  10. New Materials Design

    National Research Council Canada - National Science Library

    Voth, Gregory

    1999-01-01

    Progress has been made on several projects under the Challenge Project award. In the area of high energy density materials, calculations are under way on Al atoms embedded in clusters of H2 molecule...

  11. Long term test of buffer material at the Aespoe Hard Rock Laboratory, LOT project. Final report on the A2 test parcel

    Energy Technology Data Exchange (ETDEWEB)

    Karnland, Ola; Olsson, Siv; Dueck, Ann; Birgersson, Martin; Nilsson, Ulf; Hernan-Haakansson, Tania (Clay Technology AB, Lund (Sweden)); Pedersen, Karsten (Microbial Analytics Sweden AB (Sweden); Goeteborg Univ., Dept. of Cell and Molecular Biology, Goeteborg (Sweden)); Nilsson, Sara; Eriksen, Trygve E. (School of Chemical Science and Engineering, Nuclear chemistry, Royal Inst. of Tech., Stockholm (Sweden)); Rosborg, Bo (Rosborg Consulting, Nykoeping (Sweden))

    2009-11-15

    In the Swedish repository concept for nuclear waste (KBS-3 concept), the spent nuclear fuel will be stored in copper canisters surrounded by compacted bentonite. The decaying power of the fuel will increase the temperature in the repository which, in combination with the uptake of ground-water, are expected to result in minor mineralogical changes in the bentonite. The ongoing LOT test series at the Aespoe Hard Rock Laboratory (HRL) are focused on identifying and quantifying such mineralogical alterations in the bentonite exposed to typical repository-like conditions. Further, buffer-related processes concerning copper corrosion, cation transport, and bacterial survival/activity are studied. In total, the LOT project includes seven test parcels, which contain a central Cu-tube surrounded by cylindrical bentonite blocks with a diameter of 30 cm, and gauges for temperature, total pressure, water pressure and humidity. Electrical heaters placed inside the copper tube are used to simulate the power from the decaying spent fuel. Three parcels are exposed to standard KBS-3 conditions (maximum temperature below 100 deg C) and four parcels to adverse conditions (maximum temperature below approx140 deg C). Both the standard and the adverse test series include short term tests (1 to 2 years), medium term tests (>5 years) and long term tests (>10 years). The present report concerns the A2 test parcel, which was a medium term test exposed to adverse conditions. Cu-coupons, 60Co tracers, bacteria and specific chemical substances were placed in the bentonite at defined positions. After field exposure, the entire test parcel was released from the rock by overlapping percussion drilling and wire sawing. The parcel was lifted and divided at test site and the bentonite material was sampled for specified analyses performed by nine different laboratories in five countries. The main aspects of the various tests and analyses may be summarized in the following items: - physical

  12. Report realized on behalf of the economic affairs, the environment and the territory commission on the law project, after urgency declaration, of the program relative to the sustainable management of materials and radioactive wastes

    International Nuclear Information System (INIS)

    Birraux, C.

    2006-03-01

    In 1991 the France decided to intensify its researches in the high activity radioactive wastes management domain. The law of the 30 December 1991 relative to the radioactive wastes management, decided that a period of 15 years would be devoted to the research of very long dated solutions. Taking into account these researches, a law project has been composed. After a recall of the today situation of radioactive materials and wastes in France and the knowledge since 1991, this document presents the law project. (A.L.B.)

  13. Report realized by the commission of the economical Affairs on the law project, adopted by the National Assembly after urgency declaration, of the program relative to the sustainable management of the radioactive materials and wastes

    International Nuclear Information System (INIS)

    Revol, H.

    2006-01-01

    In the framework of a sustainable development and of the nuclear energy development, the France decided by the law of the 30 December 1991, to study three axis or researches: the radioactive wastes transmutation, their deep underground disposal and their storage during ten years. Today, after evaluation of the researches results a law project on the sustainable management of the radioactive materials and wastes, has been prepared. This document is the approval of the law project and presents some amendments. (A.L.B.)

  14. Fiscal 1991 research report. Research trend survey for next-generation industrial structure technology research and development project - Research and development of advanced materials for extreme environments; 1991 nendo jisedai sangyo kiban gijutsu kenkyu kaihatsu project ni kakawaru kenkyu doko chosa hokokusho. Chotaikankyosei senshin zairyo no kenkyu kaihatsu (sekitoku daiene)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-03-01

    Efforts were exerted to develop intermetallic compounds and C/C (carbon/carbon) composites to serve as advanced materials for extreme environments. In relation with advanced materials, especially with intermetallic compounds and fiber reinforced intermetallic compound composite materials, a technical research survey was conducted covering the three fields of (1) summarization of activities conducted up to fiscal 1991, (2) contents of associated aerospace projects, and (3) aeroengine components. In Field (1), the ground on which the project was created and the project's basic plans, goals, and systems, and its ripple effects are discussed, and the fruits produced so far are summarized. In Field (2), aeroengine component related projects of America, Britain, France, Germany, and Japan are investigated. In Field (3), aluminum alloys, titanium alloys, alloy steel, superalloys, intermetallic compounds, and intermetallic compound composite materials are discussed with attention paid to their current status and future trend, characteristics they are supposed to finally assume, and technical tasks to discharge for the development of technologies concerned. (NEDO)

  15. BARC's efforts towards maintenance of water quality

    International Nuclear Information System (INIS)

    Kamath, P.R.

    1978-01-01

    Some of the studies pursued at the Environmental Survey Laboratories (ESLs) established at the site of nuclear installations in India are discussed. Each site has its special features and these ESLs monitor radioactive pollution in the environment including Man. The major objective of the surveillance programme at nuclear sites is the maintenance of water quality. Environmental investigations carried out to collect data on individual organisms, recipient water characteristics, thermal pollution and its effect on fish are described. (K.M.)

  16. Generation of aerosols: BARC nebulizer and others

    International Nuclear Information System (INIS)

    Soni, P.S.; Raghunath, B.

    1994-01-01

    The concern with atmospheric pollution in recent times has focused attention on aerosols, their distribution pattern after inhalation and the kinetics of their deposition and exclusion from bronchial passages. The technique of radioaerosols for lung imaging is of recent origin. The procedure was proposed as a means of estimating regional ventilation and localizing areas of airway narrowing. The technique is an alternative in the face of non-availability of radioactive gases, especially in developing countries where the cost is the major factor due to economic reasons. Now, it is beyond doubt that radioaerosol lung studies are a potentially valuable tool in the evaluation of respiratory function in health and disease, especially to detect chronic obstructive pulmonary diseases. Also, the administration of a drug by aerosol inhalation provides a convenient method for the treatment of conditions affecting the respiratory system. This write-up will brief us about radioaerosol, its generation and characterisation

  17. Generation of aerosols: BARC nebulizer and others

    Energy Technology Data Exchange (ETDEWEB)

    Soni, P S; Raghunath, B

    1994-07-01

    The concern with atmospheric pollution in recent times has focused attention on aerosols, their distribution pattern after inhalation and the kinetics of their deposition and exclusion from bronchial passages. The technique of radioaerosols for lung imaging is of recent origin. The procedure was proposed as a means of estimating regional ventilation and localizing areas of airway narrowing. The technique is an alternative in the face of non-availability of radioactive gases, especially in developing countries where the cost is the major factor due to economic reasons. Now, it is beyond doubt that radioaerosol lung studies are a potentially valuable tool in the evaluation of respiratory function in health and disease, especially to detect chronic obstructive pulmonary diseases. Also, the administration of a drug by aerosol inhalation provides a convenient method for the treatment of conditions affecting the respiratory system. This write-up will brief us about radioaerosol, its generation and characterisation.

  18. Food preservation technologies developed at BARC

    International Nuclear Information System (INIS)

    Jain, M.P.

    2013-01-01

    Food irradiation is important as it is being used to disinfest food grains, pulses, wheat flour, rice, semolina, raisins etc; quarantining and shelf life increasing of fruits like mangoes; microbial decontamination of spices; sprout inhibition of tubers and bulbs; shelf life increasing and pathogen control of meat and fish. Category-IV type irradiators based on gamma rays exposure of food are currently being employed for this purpose. Cobalt-60 isotope is produced in the nuclear reactors. Isotope gives gamma rays as its nucleus is unstable. The gamma rays pass through the food items and inhibit sprouting of tubers and bulbs, kill bacteria, virus and the larvae of insects

  19. Law project adopted by the National Assembly, after urgency declaration, of the program relative to the sustainable management of radioactive materials and wastes

    International Nuclear Information System (INIS)

    2006-01-01

    The document presents the different articles of the law project dealing with the terminology, the radioactive wastes storage and disposal, the safety and the transport, the financing, the liabilities, the control and the sanctions. (A.L.B.)

  20. Materials risk analysis.

    Science.gov (United States)

    2010-02-01

    State highway authorities routinely examine the quality of the materials used to build highway construction projects. Some : materials are tested, some are accepted through a manufacturers certification of quality or compliance, some are physicall...

  1. Blades and discs in gas turbines. Behaviour of material and components. Project department A-C. Final report; Schaufeln und Scheiben in Gasturbinen. Werkstoff- und Bauteilverhalten. Projektbereiche A bis C. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    The special research area 339 `Blades and discs in gas turbines, behaviour of material and components` was carried on from 1988 to the end of 1196. This final report deals with the work in the years 1994, 1995 and 1996. In the project area A `Development of material` manufacturing processes both for metallic and ceramic high temperature materials were developed, tested and optimised. In the area of optimising casting structure, it was shown that the making grains finer up to the medium temperature range can be a suitable means for significantly raising the resistance to LCF loading with nearly unchanged heat and creep strength properties. Another main point was the characterisation and optimisation of sprayed ceramic layers on metallic substrates (heat insulating layers) and compound ceramic materials. In project area B `Material behaviour` the mechanisms were studied, which, particularly in metallic high temperature materials such as nickel-based superalloys, lead to failure of the material under thermo-mechanical stresses. In project area C `Component design`, on the one hand models for estimating service life for metallic high temperature materials under different thermo-mechanical stresses were developed. [Deutsch] Der Sonderforschungsbereich 339, `Schaufeln und Scheiben in Gasturbinen - Werkstoff- und Bauteilverhalten` wurde von 1988 bis Ende 1996 gefoerdert. Dieser Abschlussbericht behandelt die Arbeiten der Jahre 1994, 1995 und 1996. Im Projektbereich A `Werkstoffentwicklung` wurden Herstellungsverfahren sowohl fuer metallische als auch fuer keramische Hochtemperaturwerkstoffe entwickelt, erprobt und optimiert. Auf dem Gebiet der Gussgefuegeoptimierung konnte gezeigt werden, dass die Kornfeinung bis in den mittleren Temperaturbereich ein geeignetes Mittel sein kann, um den Widerstand gegen LCF-Belastung bei annaehernd unveraenderten Warm- und Kriechfestigkeitseigenschaften signifikant zu erhoehen. Einen weiteren Schwerpunkt bildete die Charakterisierung und

  2. Numatron project

    Energy Technology Data Exchange (ETDEWEB)

    Sugimoto, K [Osaka Univ., Toyonaka (Japan). Dept. of Physics; Hirao, Yasuo

    1977-04-01

    A project of high energy heavy ion acceleration is under consideration. The high energy heavy ions can produce highly condensed states of nuclei. A new phase of nucleus would be seen at the incident energy higher than 140 MeV/nucleon. High energy heavy ions causing high density states and meson emission will produce various new nuclides. Process of formation of atomic elements will be studied. Various fields of science can be also investigated by the high energy heavy ions. Spectroscopic study of multi-valent ions will be made high energy uranium. Study of materials for the fusion reactor is important. Impurity heavy ion from the wall of the fusion reactor may lose the energy of the reactor, and the characteristic features of heavy ions should be investigated. The highly ionized states of atoms are also produced by heavy ion injection into material. Several projects of heavy ion acceleration are in progress in the world. The Numatron project in Japan is to construct a combination machine of a Cockcroft type machine, three linear accelerator and a synchrotron. The planned energy of the machine is 670 MeV/nucleon. Technical problems are under investigation.

  3. INTERWELD - European project to determine irradiation induced material changes in the heat affected zones of austenitic stainless steel welds that influence the stress corrosion behaviour in high-temperature water

    International Nuclear Information System (INIS)

    Roth, A.; Schaaf, Bob van der; Castano, M.L.; Ohms, C.; Gavillet, D.; Dyck, S. van

    2003-01-01

    PWR and BWR RPV internals have experienced stress corrosion cracking in service. The objective of the INTERWELD project is to determine the radiation induced material changes that promote stress corrosion cracking in the heat affected zone of austenitic stainless steel welds. To achieve this goal, welds in austenitic stainless steel types AISI 304/347 have been fabricated, respectively. Stress-relief annealing was applied optionally. The pre-characterisation of both the as-welded and stress relieved material conditions comprises the examination of the weld residual stresses by the ring-core-technique and neutron diffraction, the degree of sensitisation by EPR, and the stress corrosion behaviour by SSRT testing in high-temperature water. The weldments will be irratiated to 2 neutron fluence levels and a postirradiation examination will determine micromechanical, microchemical and microstructural changes in the materials. In detail, the evolution of the residual stress levels and the stress corrosion behaviour after irradiation will be determined. Neutron diffraction will be utilized for the first time with respect to neutron irradiated material. In this paper, the current state of the project will be described and discussed. (orig.)

  4. Mechanisms of Plastic and Fracture Instabilities for Alloy Development of Fusion Materials. Final Project Report for period July 15, 1998 - July 14, 2003

    Energy Technology Data Exchange (ETDEWEB)

    Ghoniem, N. M.

    2003-07-14

    The main objective of this research was to develop new computational tools for the simulation and analysis of plasticity and fracture mechanisms of fusion materials, and to assist in planning and assessment of corresponding radiation experiments.

  5. Mechanisms of Plastic and Fracture Instabilities for Alloy Development of Fusion Materials. Final Project Report for period July 15, 1998 - July 14, 2003

    International Nuclear Information System (INIS)

    Ghoniem, N.M.

    2003-01-01

    The main objective of this research was to develop new computational tools for the simulation and analysis of plasticity and fracture mechanisms of fusion materials, and to assist in planning and assessment of corresponding radiation experiments

  6. National uranium project - an initiative to generate national database on uranium in drinking water of the country

    International Nuclear Information System (INIS)

    Sahoo, S.K.; Tripathi, R.M.; Jha, V.N.; Kumar, Ajay; Patra, A.C.; Vinod Kumar, A.

    2018-01-01

    Uranium is a naturally occurring lithophilic heavy element found in earth crust since inception of the earth. It is present naturally in all rock and soil and the concentration depends on geological formation and local geology. Groundwater interact with the host rocks and the wet weathering process facilitate the solubility of uranium in groundwater. The concentration of uranium in groundwater is influenced by geo-chemical parameters such as host rock characteristics and pH, Eh, ORP, ligands, etc. of the interacting water medium. Uranium is a radioactive element of low specific activity (25 Bq/mg) having both chemical and radiological toxicity but its chemical toxicity supersede the radio-toxicity. After a reporting of high uranium content in drinking water of Punjab, BARC has taken a pro-active initiative to generate a national database on uranium in drinking water in all the districts of India under National Uranium Project (NUP)

  7. Dissemination material template, Deliverable 2.2 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

    NARCIS (Netherlands)

    Tros, M. & Houtenbos, M.

    2016-01-01

    Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project with the objective of developing an innovative road safety Decision Support System (DSS) that will enable policy-makers and stakeholders to select and implement the most appropriate

  8. Fiscal 1996 international research cooperation project. Report on the result of the development survey of tribo materials; 1996 nendo kokusai kenkyu kyoryoku jigyo. Tribo material no kaihatsu chosa seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    Basic information was collected and assessed on materials and element technology for tribo materials which are expected to contribute to improvement of energy efficiency of machine/equipment having the sliding part such as automobiles. A survey was conducted of creation of substrate materials, the surface treatment method, and evaluation of coating characteristics. For an analysis of high polymer abrasion powder, the micro ATR method is effective. As an analysis method of abrasion scar, the micro ATR method is effective to specify the peeling part of coating, and the Raman method is effective for an analysis of transfer matters or abrasion powder. As a method to collect various shapes of abrasion powder, processing of material surfaces by polishing method is effective. As a dynamic analysis method, the infrared ray stress image method is effective. As an evaluation method of deficient concentration of coating, the GC-MS method is effective. For the application of high-hardness/low-toughness gas phase coating film to the sliding part, important factors are the substrate hardness, surface roughness, and film adhesiveness from the aspect of materials and the determination of pressure of the sliding face from the aspect of sliding conditions. 12 refs., 38 figs., 20 tabs.

  9. International cooperation project. Evaluation report on development of new oxidation and environment resistant materials for petroleum excavation; Sekiyu kussakuyo taisankasei taikankyosei shinzairyo no kaihatsu hyoka hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    In order to enhance the environment and wear resisting performance of the bearing mechanism for petroleum excavation bits assuming use at a depth of 6,000 m, discussions were given on a cubic boron nitride based ultra-hard thin film and a Ti{sub x}M{sub 1-x}N based hard thin film as the new materials. This paper describes the evaluation report for the year 2000. It was found that the promising material is the Ti{sub x}M{sub 1-x}N. The practical applicability test would require a considerable amount of expense and insurance fee, while putting the material into practical use would take some more time. However, the achievements in developing this new material will allow the material to be applied to cutting tools used under the same onerous condition, and theoretical development would be possible on the consideration of the film properties, whereas further development may be expected in the future. An international joint study has performed evaluations on the environmental resistance and the characteristics of the film at the University of Toronto. These evaluations are effective in enhancing further the properties of the thin film in the future. Achievements have been accumulated steadily from starting the fundamental studies, and high level objectives have been achieved. Accurate identification has been made on the state of developing the parts for petroleum excavation bits, with the objectives set properly. Putting the bits into practical use will still require public assistance. (NEDO)

  10. Managing projects using a project management approach

    Directory of Open Access Journals (Sweden)

    Marko D. Andrejić

    2011-04-01

    Full Text Available Modern management theory treats all complex tasks and duties like projects and make these projects possible to be managed by a particular organizational-management concept in order to achieve a goal effectively. A large number of jobs and tasks performed in the system of defense or for defense purposes have the characteristics of projects. Project management is both a skill and a science of monitoring human, material, financial, energy and other resources to achieve required objectives within the given limits: deadlines, time, budget, possibility of realization and the satisfaction of the interests of all project participants. Project management is a traditional area of applied (or functional management focused on managing complex and uncertain situations with defined goals. Introduction In conditions of rapid change and high uncertainty, only adaptive organizations survive, i. e. those that are able not only to react quickly to changes but also to proactively take advantage of changes. Development of project management The biggest influence on the development of the area had complex jobs within the engineering profession. In parallel with the traditional approach new approaches began to develop, while the traditional one still remained in use. Contrary to the traditional engineering approach, a dynamic model first developed in order to respond to demands for greater control of costs. Project management Project management is a skill and knowledge of human and material resources to achieve set objectives within prescribed limits: deadlines, time, budget, possibility of realization, and the satisfaction of all participants in the project. In order to realize a project effectively, it is necessary to manage it rationally. Planning and project management A project plan is a document that allows all team members insight on where to go, when to start and when to arrive, what is necessary to be done in order to achieve the project objectives and what

  11. Risk Assessment for Current and Projected Uses of Source Material Under a U.S. NRC General License and Exemption Request

    International Nuclear Information System (INIS)

    Smith, Michael A.; Napier, Bruce A.; Strom, Daniel J.; Short, Steven M.; Beatty, Cassandra V.; Stoker, Natasha F.; Newman, Teridee

    2006-01-01

    Source material is used under specific license, general license, and various exemptions from licensing requirements in 10 CFR Part 40. Because the Atomic Energy Act of 1946 focused on source material primarily in terms of its significance to the production of special nuclear material, the initial regulation of source material did not, apparently, give much emphasis to public health and safety. This emphasis on the production of special nuclear material continued in later modifications to the regulations. Because the last major update of these regulations was over 40 years ago (1961), the NRC is concerned that the current regulations for source materials may not be consistent with current health and safety regulations. Current industrial trends indicate a general decline in the use of thorium and uranium. Thorium was traditionally used in ceramics for refractory purposes but now is primarily used in scientific research, in a few electrical applications, as a chemical catalyst, and in optical lenses. Uranium, once popular in pigments and glazes, is now almost entirely limited to military applications that require special licensure and in scientific research. Due to high-disposal costs, increasingly stringent regulations, and public concerns related to the natural radioactivity of source material, industry is rapidly developing substitutes and alternate processes that do not involve the use of uranium and thorium. For these reasons, the downward trend in the use of source material is expected to continue. Researchers at Pacific Northwest National Laboratory (PNNL) identified how source materials meeting the exemption and general license requirements of 10 CFR 40.13(a), 40.13(b), and 40.22 are currently being used in industry and by the public. Based on the results of an extensive literature and internet search, few ?truly? new uses of source material were discovered that were not already considered in or represented by previous NRC analyses. Exceptions were (1) the

  12. Materials Science

    Science.gov (United States)

    2003-01-01

    The Materials Science Program is structured so that NASA s headquarters is responsible for the program content and selection, through the Enterprise Scientist, and MSFC provides for implementation of ground and flight programs with a Discipline Scientist and Discipline Manager. The Discipline Working Group of eminent scientists from outside of NASA acts in an advisory capacity and writes the Discipline Document from which the NRA content is derived. The program is reviewed approximately every three years by groups such as the Committee on Microgravity Research, the National Materials Advisory Board, and the OBPR Maximization and Prioritization (ReMaP) Task Force. The flight program has had as many as twenty-six principal investigators (PIs) in flight or flight definition stage, with the numbers of PIs in the future dependent on the results of the ReMaP Task Force and internal reviews. Each project has a NASA-appointed Project Scientist, considered a half-time job, who assists the PI in understanding and preparing for internal reviews such as the Science Concept Review and Requirements Definition Review. The Project Scientist also insures that the PI gets the maximum science support from MSFC, represents the PI to the MSFC community, and collaborates with the Project Manager to insure the project is well-supported and remains vital. Currently available flight equipment includes the Materials Science Research Rack (MSRR-1) and Microgravity Science Glovebox. Ground based projects fall into one or more of several categories. Intellectual Underpinning of Flight Program projects include theoretical studies backed by modeling and computer simulations; bring to maturity new research, often by young researchers, and may include preliminary short duration low gravity experiments in the KC-135 aircraft or drop tube; enable characterization of data sets from previous flights; and provide thermophysical property determinations to aid PIs. Radiation Shielding and preliminary In

  13. Neutron diffraction studies on ordered and disordered materials

    International Nuclear Information System (INIS)

    Krishna, P.S.R

    2016-01-01

    Knowledge of the symmetry and distribution of atoms in the unit cell and the bonding between atoms is the key point for understanding, designing and manipulating chemical behavior or physical properties of novel materials for technological applications. This could be achieved using diffraction techniques. At the Dhruva national facility, BARC, Mumbai, a Powder diffractometer (PD2) and a High-Q diffractometer (HQD) are in operation for more than 2 decades. PD2 and HQD are equipped with banks of 5 and 10 position sensitive detectors (PSD) respectively, to cover the Q-ranges 9.4 Å -1 and 15 Å -1 respectively. The resolutions (Δd/d) of these instruments are 0.8% (λ = 1.24 Å) and 2.5% (λ = 0.78 Å). We report about the studies of changes in the long range order in crystalline materials as a function of temperature and/or composition as well as short and intermediate range orders studied in amorphous materials on these diffractometers in recent years. PD2 has been extensively used in the structural/phase transition studies of ferroics, multiferroics, nanoferrites along with magnetic structure determinations. On the other hand, HQD has been extensively used to understand the short and intermediate range order in network glasses like chalcogenides, H-bonded alcohols, Telluride glasses etc. We will be discussing the recent structural results obtained on many of these crystalline systems, glasses and molecular fluids on both of these diffractometers. (author)

  14. Project Quality Assurance Plan for research and development services provided by Oak Ridge National Laboratory in support of the Westinghouse Materials Company of Ohio Operable Unit 1 Stabilization Development and Treatability Studies Program

    Energy Technology Data Exchange (ETDEWEB)

    Gilliam, T.M.

    1991-05-01

    This Project Quality Assurance Plan (PQAP) sets forth the quality assurance (QA) requirements that are applied to those elements of the Westinghouse Materials Company of Ohio (WMCO) Operable Unit 1 support at Oak Ridge National Laboratory (ORNL) project that involve research and development (R D) performed at ORNL. This is in compliance with the applicable criteria of 10 CFR Part 50, Appendix B, ANSI/ASME NQA-1, as specified by Department of Energy (DOE) Oak Ridge Operations (ORO) Order 5700.6B. For this application, NQA-1 is the core QA Program requirements document. QA policy, normally found in the requirements document, is contained herein. The requirements of this PQAP apply to project activities that affect the quality and reliability/credibility of research, development, and investigative data and documentation. These activities include the functions of attaining quality objectives and assuring that an appropriate QA program scope is established. The scope of activities affecting quality includes organization; personnel training and qualifications; design control; procurement; material handling and storage; operating procedures; testing, surveillance, and auditing; R D investigative activities and documentation; deficiencies; corrective actions; and QA record keeping. 12 figs.

  15. History and practice of material research on the examples of Material Testing and Materialpruefungsanstalt (MPA) Stuttgart, liquid crystals and screen technology as well as superconductivity. An interdisciplinary teaching project of the University of Stuttgart; Geschichte und Praxis der Materialforschung an den Beispielen Materialpruefung und Materialpruefungsanstalt (MPA) Stuttgart, Fluessigkristalle und Bildschirmtechnik sowie Supraleitung. Ein interdisziplinaeres Lehrprojekt der Universitaet Stuttgart

    Energy Technology Data Exchange (ETDEWEB)

    Hentschel, Klaus; Webel, Josef (eds.)

    2016-07-01

    The knowledge of material research and its history is not very common among scientists and engineers alike. Within the scope of an interdisciplinary teaching project carried out for the first time in the summer semester 2014 and ever since then every summer semester at the University of Stuttgart, an attempt is made to approach material research both from a scientific, technical and historical perspective. The Material Testing and Materials Testing Institute in Stuttgart (MPA), the liquid crystals and the screen technology as well as the superconductivity were selected as topics, which have a long tradition in research and teaching in Stuttgart. In this anthology the materials of the teaching project are summarized. [German] Das Wissen um die Materialforschung und ihre Geschichte ist selbst unter Naturwissenschaftlern und Ingenieuren wenig verbreitet. Im Rahmen eines erstmals im Sommersemester 2014 und seither dann jedes Sommersemester an der Universitaet Stuttgart durchgefuehrten interdisziplinaeren Lehrprojektes wird deshalb der Versuch unternommen, sich der Materialforschung sowohl aus naturwissenschaftlicher und technischer als auch aus historischer Perspektive anzunaehern. Als Themenbereiche wurden dafuer die Materialpruefung und Materialpruefungsanstalt (MPA) Stuttgart, die Fluessigkristalle und die Bildschirmtechnik sowie die Supraleitung ausgewaehlt, die in Stuttgart auf eine lange Tradition in Forschung und Lehre zurueckblicken. Im vorliegenden Sammelband sind die Materialien des Lehrprojektes zusammengefasst.

  16. New Bedford Harbor Superfund Project, Acushnet River Estuary Engineering Feasibility Study of Dredging and Dredged Material Disposal Alternatives. Report 4. Surface Runoff Quality Evaluation for Confined Disposal

    Science.gov (United States)

    1988-01-01

    infiltration studies ( Westerdahl and Skogerboe 1982). Exten- sive field verification studies have been conducted with the WES Rainfall Simulator...Lysimeter System on a wide range of USACE project sites ( Westerdahl and Skogerboe 1982, Lee and Skogerboe 1984, Skogerboe et al. 1987). The WES Rainfall...Criteria for Water 1986,"’ Criteria and Standards Division, Washington, DC. Westerdahl , H. E., and Skogerboe, J. G. 1982. "Realistic Rainfall and Water

  17. Prediction of the Effects of Radiation FOr Reactor pressure vessel and in-core Materials using multi-scale modeling - 60 years foreseen plant lifetime (PERFORM-60 project)

    International Nuclear Information System (INIS)

    Al Mazouzi, A.; Bugat, S.; Leclercq, S.; Massoud, J.-P.; Moinereau, D.; Lidbury, D.; Van Dyck, S.; Marini, B.; Alamo, Ana

    2010-01-01

    The PERFECT project of the EURATOM framework program (FP6) is a first step through the development of a simulation platform that contains several advanced numerical tools aiming at the prediction of irradiation damage in both the reactor pressure vessel (RPV) and its internals using state-of-the-art knowledge. These tools allow simulation of irradiation effects on the microstructure and the constitutive behavior of the RPV low alloy steels, as well as their fracture mechanics properties. For the reactor internals, the first partial models were established, describing radiation damage to the microstructure and providing a first description of the stress corrosion behaviour of austenitic steels in primary environment, without physical linking of the radiation and corrosion effects. Thus, relying on the existing PERFECT Roadmap, the FP7 Collaborative Project PERFORM 60 has mainly for objective to develop similar tools that would allow the simulation of the combined effects of irradiation and corrosion on internals, in addition to a further improvement of the existing ones on RPV made of bainitic steels. From the managerial view point, PERFORM 60 is based on two technical sub-projects, namely (i) RPV and (ii) Internals. In addition, a Users' Group and a training scheme have been adopted in order to allow representatives of constructors, utilities, research organizations... from Europe, USA and Japan to participate actively in the process of appraising the limits and potentialities of the developed tools as well as their validation against qualified experimental data

  18. Achievement report for fiscal 1981 on Sunshine Program-assisted project. Research and development of materials for coal liquefaction plant (Research on materials); 1981 nendo sekitan ekika plant zairyo no kenkyu kaihatsu (zairyo no kenkyu) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-03-01

    Research and development is started of materials for constituting a liquefaction reactor which is the primary apparatus in the coal liquefaction process. Tested in the basic research on the designing of alloys for the reactor are Cr-Mo-V-Ti based alloys prepared by adding V, Ti, and B to Cr-Mo based alloys presently in use as materials for pressure vessels. They are melted and 50kg test ingots of steel are prepared, and an alloy with a constitution of Low Si-3%Cr-1%Mo-0.25%V-0.02%Ti-0.002%B is selected. In the designing of alloys to serve as stainless steel overlay welding materials and in the development of basic welding technologies, studies are conducted in search for materials that exhibit excellent durability under the conditions of liquefaction reaction and for technologies in this connection. These are accomplished using a test device installed this fiscal year, which is capable of reproducing high-temperature high-pressure hydrogen atmosphere. As the result, basic technologies are acquired, which will enable the achievement of the goal. In the study of on-site production technologies using medium-size ingots as the materials, an 85-ton medium size steel ingot of a new chemical constitution of Low Si-3Cr-1Mo-1/4V-Ti-B is melted, and a shell which is 400mm in thickness and 2m in internal diameter is forged, and the shell is subjected to a property and performance qualification test. (NEDO)

  19. Solution of problems with material nonlinearities with a coupled finite element/boundary element scheme using an iterative solver. Yucca Mountain Site Characterization Project

    International Nuclear Information System (INIS)

    Koteras, J.R.

    1996-01-01

    The prediction of stresses and displacements around tunnels buried deep within the earth is an important class of geomechanics problems. The material behavior immediately surrounding the tunnel is typically nonlinear. The surrounding mass, even if it is nonlinear, can usually be characterized by a simple linear elastic model. The finite element method is best suited for modeling nonlinear materials of limited volume, while the boundary element method is well suited for modeling large volumes of linear elastic material. A computational scheme that couples the finite element and boundary element methods would seem particularly useful for geomechanics problems. A variety of coupling schemes have been proposed, but they rely on direct solution methods. Direct solution techniques have large storage requirements that become cumbersome for large-scale three-dimensional problems. An alternative to direct solution methods is iterative solution techniques. A scheme has been developed for coupling the finite element and boundary element methods that uses an iterative solution method. This report shows that this coupling scheme is valid for problems where nonlinear material behavior occurs in the finite element region

  20. JHR Project: a future Material Testing Reactor working as an International user Facility: The key-role of instrumentation in support to the development of modern experimental capacity

    Energy Technology Data Exchange (ETDEWEB)

    Bignan, G. [CEA, DEN, DER, JHR user Facility Interface Manager' , Cadarache, F-13108 St-Paul-Lez-Durance (France); Gonnier, C. [CEA, DEN, DER, SRJH Jules Horowitz Reactor Service, Cadarache, F-13108 St-Paul-Lez-Durance (France); Lyoussi, A.; Villard, J.F.; Destouches, C. [CEA, DEN, DER, Instrumentation Sensors and Dosimetry Laboratory, Cadarache, F-13108 St-Paul-Lez-Durance (France); Chauvin, J.P. [CEA,DEN, DER, SPEX, Experimental Physics Service, Cadarache, F-13108 St-Paul-Lez-Durance (France); Maugard, B. [CEA, DEN, DER, Reactor Department Studies, Cadarache, F-13108 St-Paul-Lez-Durance (France)

    2015-07-01

    Research and development on fuel and material behaviour under irradiation is a key issue for sustainable nuclear energy in order to meet specific needs by keeping the best level of safety. These needs mainly deal with a constant improvement of performances and safety in order to optimize the fuel cycle and hence to reach nuclear energy sustainable objectives. A sustainable nuclear energy requires a high level of performances in order to meet specific needs such as: - Pursuing improvement of the performances and safety of present and coming water cooled reactor technologies. This will require a continuous R and D support following a long-term trend driven by the plant life management, safety demonstration, flexibility and economics improvement. Experimental irradiations of structure materials are necessary to anticipate these material behaviours and will contribute to their optimisation. - Upgrading continuously nuclear fuel technology in present and future nuclear power plants to achieve better performances and to optimise the fuel cycle keeping the best level of safety. Fuel evolution for generation II, III and III+ is a key stake requiring developments, qualification tests and safety experiments to ensure the competitiveness and safety: experimental tests exploring the full range of fuel behaviour determine fuel stability limits and safety margins, as a major input for the fuel reliability analysis. To perform such accurate and innovative progress and developments, specific and ad hoc instrumentation, irradiation devices, measurement methods are necessary to be set up inside or beside the material testing reactor (MTR) core. These experiments require beforehand in situ and on line sophisticated measurements to accurately determine different key parameters such as thermal and fast neutron fluxes and nuclear heating in order to precisely monitor and control the conducted assays. The new Material Testing Reactor JHR (Jules Horowitz Reactor) currently under

  1. Development of mechanical-hydraulic models for the prediction of the long-term sealing capacity of concrete based sealing materials in rock salt. Project Titel LASA

    Energy Technology Data Exchange (ETDEWEB)

    Czaikowski, Oliver; Dittrich, Juergen; Hertes, Uwe; Jantschik, Kyra; Wieczorek, Klaus; Zehle, Bernd

    2016-08-15

    The research work leading to these results has received funding from the German Federal Ministry of Economic Affairs and Energy (BMWi) under contract no. 02E11132. This report presents the current state of laboratory investigations and modelling activities related to the LASA project. The work is related to the research and development of plugging and sealing for repositories in salt rock and is of fundamental importance for the salt option which represents one of the three European repository options in addition to the clay rock and the crystalline rock options.

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  3. Severity, probability and risk of accidents during maritime transport of radioactive material. Final report of a co-ordinated research project 1995-1999

    International Nuclear Information System (INIS)

    2001-07-01

    The primary purpose of this CRP was to provide a co-ordinated international effort to assemble and evaluate relevant data using sound technical judgement concerning the effects that fires, explosions or breaches of hulls of ships might have on the integrity of radioactive material packages. The probability and expected consequences of such events could thereby be assessed. If it were shown that the proportion of maritime accidents with severity in excess of the IAEA regulatory requirements was expected to be higher than that for land transport, then pertinent proposals could be submitted to the forthcoming Revision Panels to amend the IAEA Regulations for Safe Transport of Radioactive Material and their supporting documents. Four main areas of research were included in the CRP. These consisted of studying the probability of ship accidents; fire; collision; and radiological consequences

  4. Severity, probability and risk of accidents during maritime transport of radioactive material. Final report of a co-ordinated research project 1995-1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The primary purpose of this CRP was to provide a co-ordinated international effort to assemble and evaluate relevant data using sound technical judgement concerning the effects that fires, explosions or breaches of hulls of ships might have on the integrity of radioactive material packages. The probability and expected consequences of such events could thereby be assessed. If it were shown that the proportion of maritime accidents with severity in excess of the IAEA regulatory requirements was expected to be higher than that for land transport, then pertinent proposals could be submitted to the forthcoming Revision Panels to amend the IAEA Regulations for Safe Transport of Radioactive Material and their supporting documents. Four main areas of research were included in the CRP. These consisted of studying the probability of ship accidents; fire; collision; and radiological consequences.

  5. Development and Evaluation of Die Materials for Use in the Growth of Silicon Ribbons by the Inverted Ribbon Growth Process. Task 2: LSSA Project

    Science.gov (United States)

    Duffy, M. T.; Berkman, S.; Moss, H. I.; Cullen, G. W.

    1978-01-01

    Several ribbon growth experiments were performed from V-shaped dies coated with CVD Si3N4. The most significant result was the ability to perform five consecutive growth runs from the same die without mechanical degradation of the die through temperature cycling. The die was made from vitreous carbon coated with CVD Si3N4. Silicon oxynitride, Si2N2O, was examined with respect to thermal stability in contact with molten silicon. The results of X-ray analysis indicate that this material is converted to both alpha - and beta-Si3N4 in the presence of molten silicon. Experiments on the stability of CVD SiOxNy shoe that this material can be maintained in contact with molten silicon (sessile drop test) for greater than 30 h at 1450 C without total decompositon. These layers are converted mainly to beta-Si3N4.

  6. Articulating Material Criteria

    DEFF Research Database (Denmark)

    Hasling, Karen Marie

    2013-01-01

    , imitate and articulate the students’ inclusion of materials. This paper particularly discusses the experiences made and ideas generated after the execution of a material science course for second year students, with emphasis on the concept of the material selection matrix as an educational tool......This paper discusses the experiences and potentials with materials teaching at the Institute for Product Design at Kolding School of Design, using materials teaching as experiments in my PhD project. The project intents to create a stronger material awareness among product design students...... with emphasis on sustainability. The experiments aim to develop an understanding of, how product design students include materials in their design practice and how tools can be developed that further enhance this. Hence experiments are essential for the progress of the PhD project as they help to observe...

  7. Results and implications of the EU-project CARERS ‘Content materials to raise employability and reinforce skills of carers’

    Science.gov (United States)

    Weber, Germain; Zeilinger, Elisabeth; Oppenauer, Claudia; Brehmer, Barbara

    2009-01-01

    Purpose The population, and needs, of informal carers is changing, reflecting not only the changing demographics across Europe, but also the unequal challenges and opportunities for education and training—and official approval of competences—across Europe for people involved in the care sector, formal as well as informal carers. Theory The objective of this European project (Austria, France, Lithuania Luxembourg, Poland and Spain) was to create, offer and evaluate an education and training programme specifically aimed at informal carers (e.g. family members), providing answers to meet their real needs in their support work as well as for their own emotional well-being. Therefore, project partners produced six innovative, online supported training modules (total 60 hours) for face-to-face delivery. Methods The presentation will highlight the development and the content of one training Module for older people with ‘intellectual disabilities’ more detailed. Results and conclusions All trainings were evaluated by the participants through pre/post questionnaires. The results of the trainings will be presented. Discussion The importance of trainings and support for informal carers will be discussed with special emphasis given on the fact that informal carers represent a most substantial economic resource for every country and its care system.

  8. Project Notes

    Science.gov (United States)

    School Science Review, 1978

    1978-01-01

    Presents sixteen project notes developed by pupils of Chipping Norton School and Bristol Grammar School, in the United Kingdom. These Projects include eight biology A-level projects and eight Chemistry A-level projects. (HM)

  9. Ecological evaluation of proposed discharge of dredged material from Oakland Harbor into ocean waters (Phase 3 B of -42-foot project)

    Energy Technology Data Exchange (ETDEWEB)

    Kohn, N.P.; Ward, J.A.; Mayhew, H.L.; Word, J.Q.; Barrows, E.S.; Goodwin, S.M.; Lefkovitz, L.F. (Battelle/Marine Sciences Lab., Sequim, WA (United States))

    1992-06-01

    The Water Resources Development Act of 1986 (Public Law 99-662) authorized the US Army Corps of Engineers (USACE) San Francisco District, to deepen and widen the navigational channels of the Oakland Inner and Outer Harbors to accommodate deeper-draft vessels. The USACE is considering several disposal options for the dredged material removed during these channel improvements including open-water disposal. Dredged material proposed for open-water disposal must be evaluated to determine the potential impacts of the disposal activity on the water column and disposal site environments. The USACE requested that Battelle/Marine Sciences Laboratory (MSL) conduct studies to evaluate open-water disposal options for Oakland Harbor sediments. This request developed into the Oakland Harbor Phase III Program. This is Volume 2 of a two-volume report that presents information gathered to determine the suitability of ocean disposal of sediments dredged from Oakland Harbor. This volume contains the Appendixes (A through N), which provide details of the data analyses and full presentation of the data and results.

  10. Ecological evaluation of proposed discharge of dredged material from Oakland Harbor into ocean waters (Phase 3 B of -42-foot project). Volume 2, Appendixes

    Energy Technology Data Exchange (ETDEWEB)

    Kohn, N.P.; Ward, J.A.; Mayhew, H.L.; Word, J.Q.; Barrows, E.S.; Goodwin, S.M.; Lefkovitz, L.F. [Battelle/Marine Sciences Lab., Sequim, WA (United States)

    1992-06-01

    The Water Resources Development Act of 1986 (Public Law 99-662) authorized the US Army Corps of Engineers (USACE) San Francisco District, to deepen and widen the navigational channels of the Oakland Inner and Outer Harbors to accommodate deeper-draft vessels. The USACE is considering several disposal options for the dredged material removed during these channel improvements including open-water disposal. Dredged material proposed for open-water disposal must be evaluated to determine the potential impacts of the disposal activity on the water column and disposal site environments. The USACE requested that Battelle/Marine Sciences Laboratory (MSL) conduct studies to evaluate open-water disposal options for Oakland Harbor sediments. This request developed into the Oakland Harbor Phase III Program. This is Volume 2 of a two-volume report that presents information gathered to determine the suitability of ocean disposal of sediments dredged from Oakland Harbor. This volume contains the Appendixes (A through N), which provide details of the data analyses and full presentation of the data and results.

  11. Sulphur extended oil sand mix : paving material for lower transport cost and CO{sub 2} reduction : ASRL Syncrude research project 1995

    Energy Technology Data Exchange (ETDEWEB)

    Aquin d' , G. [Con-Sul Inc., Missoula, MT (United States)

    2010-07-01

    This power point presentation discussed the use of sulphur-enhanced oil sands (SEOS) as a paving mixture. Sulphur has been added to asphaltic bitumen paving processes since the 1850s. Research into sulphur additions has been conducted by various Canadian industry members and institutions. A study in 1995 investigated the use of SEOS as a temporary paving material. The benefits of using SEOS included lower capital costs and lower greenhouse gas (GHG) impacts. Increases in equipment efficiency were also observed. Researchers are now developing mixing protocols and testing various paving materials in relation to temperature regimes and percentages of sulphur. Sand, limestone, coke, and rubber additions are also being evaluated, as well as the behaviour of SEOS in freeze-thaw cycles. To date, the studies have indicated that a 30 percent sulphur, 10 percent sand, and 60 percent oil sand mixture provides optimal compression and behaviour under freeze-thaw conditions. The use of SEOS paving at oil sands mine sites will reduce truck and road maintenance as well as reduce fuel emissions and consumption rates. tabs., figs.

  12. Critical Evaluation of an Intercalibration Project Focused on the Definition of New Multi-Element Soil Reference Materials (AMS-MO1 and AMS-ML1

    Directory of Open Access Journals (Sweden)

    Livia Vittori Antisari

    2014-12-01

    Full Text Available Soils are complex matrices and their geochemical investigation necessarily needs reliable Certified Reference Materials (CRMs, i.e. standards, to support analytical precision and accuracy. In particular, the definition of soil multi-element CRMs is particularly complex and involves an inter-laboratory program that employs numerous analytical techniques. In this study, we present the results of the inter-calibration experiment focused on the certification of two new soil standards named AMS-ML1 and AMS-MO1. The two soils developed on sandstone and serpentinite parent materials, respectively. The experiment involved numerous laboratories and focused on the evaluation of soil physicochemical parameters and geochemical analyses of major and trace elements by X-ray fluorescence (XRF and Inductive Coupled Plasma techniques (ICP-OES and ICP-MS. The data was statistically elaborated. Three levels of repeatability and accuracy in function of the different analytical methods and instrumentation equipment was observed. The statistical evaluation of the results obtained by ICP-OES on Aqua Regia extracts (i.e., Lilliefors test for normally, Grubbs test for outliers, Cochran test for outliers in variances and ANOVA allowed to computed some certified values for the two proposed soil standards. This preliminary study will represent the first step of a more thorough intercalibration ring-test involving a higher number of laboratories, in order to propose the investigated matrices as CRMs.

  13. (Project 14-6770) An Investigation to Establish Multiphysical Property Dataset of Nuclear Materials Based on in-situ Observations and Measurements

    Energy Technology Data Exchange (ETDEWEB)

    Tomar, Vikas [Purdue Univ., West Lafayette, IN (United States); Haque, Aman [Pennsylvania State Univ., University Park, PA (United States). Dept of Physics; Hattar, Khalid [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-11-10

    In-core nuclear materials including fuel pins and cladding materials fail due to issues including corrosion, mechanical wear, and pellet cladding interaction. In most such scenario microstructure dependent and corrosioninduced chemistry dependent property changes significantly affect performance of cladding, pellet, and housing. Emphasis of this work was on replace conventional pellet-cladding material models with a new straingradient viscoplasticity model that is informed by transmission electron microscopy (TEM) based measurements and by nanomechanical Raman spectroscopy (NMRS) based measurements. The TEM measurements are quantitative in nature and therefore reveal stress-strain relations with simultaneous insights into mechanisms of deformation at nanoscale. The NMRS measurements reveal the similar information at mesoscale along with additional information on relating local microstructural stresses with applied stresses. The resulting information is used to fit constants in the strain gradient viscoplasticity model as well as to validate one. During TEM measurements, a micro-electro-mechanical system based setup was developed with mechanical actuation, sensing, heating, and electrical loading. Contrary to post-mortem analysis or qualitative visualization, this setup combines direct visualization of the mechanisms behind deformation with measurement of stress, strain, thermal and electrical properties. The unique research philosophy of visualizing the microstructure at high resolution while measuring the properties led to fundamental understanding in grain size and temperature effects on measured mechanical properties such as fracture toughness. A key contribution is the role of mechanical loading boundary conditions to deconvolute the insitu TEM based nanoscale and NMRS based mesoscale data to bulk behavior. First the literature based pellet cladding mechanical interaction model based on the work of Retel’s and Williamson’s in literature work to predict

  14. Materials Genome Initiative

    Science.gov (United States)

    Vickers, John

    2015-01-01

    The Materials Genome Initiative (MGI) project element is a cross-Center effort that is focused on the integration of computational tools to simulate manufacturing processes and materials behavior. These computational simulations will be utilized to gain understanding of processes and materials behavior to accelerate process development and certification to more efficiently integrate new materials in existing NASA projects and to lead to the design of new materials for improved performance. This NASA effort looks to collaborate with efforts at other government agencies and universities working under the national MGI. MGI plans to develop integrated computational/experimental/ processing methodologies for accelerating discovery and insertion of materials to satisfy NASA's unique mission demands. The challenges include validated design tools that incorporate materials properties, processes, and design requirements; and materials process control to rapidly mature emerging manufacturing methods and develop certified manufacturing processes

  15. Material monitoring

    International Nuclear Information System (INIS)

    Kotter, W.; Zirker, L.; Hancock, J.A.

    1995-01-01

    Waste Reduction Operations Complex (WROC) facilities are located at the Idaho National Engineering Laboratory (INEL). The overall goal for the Pollution Prevention/Waste Minimization Unit is to identify and establish the correct amount of waste generated so that it can be reduced. Quarterly, the INEL Pollution Prevention (P2) Unit compares the projected amount of waste generated per process with the actual amount generated. Examples of waste streams that would be addresses for our facility would include be are not limited to: Maintenance, Upgrades, Office and Scrap Metal. There are three potential sources of this variance: inaccurate identification of those who generate the waste; inaccurate identification of the process that generates the waste; and inaccurate measurement of the actual amount generated. The Materials Monitoring Program was proposed to identify the sources of variance and reduce the variance to an acceptable level. Prior to the implementation of the Material Monitoring Program, all information that was gathered and recorded was done so through an informal estimation of waste generated by various personnel concerned with each processes. Due to the inaccuracy of the prior information gathering system, the Material Monitoring Program was established. The heart of this program consists of two main parts. In the first part potential waste generators provide information on projected waste generation process. In the second part, Maintenance, Office, Scrap Metal and Facility Upgrade wastes from given processes is disposed within the appropriate bin dedicated to that process. The Material Monitoring Program allows for the more accurate gathering of information on the various waste types that are being generated quarterly

  16. One project's waste is another project's resource

    International Nuclear Information System (INIS)

    Short, J.

    1997-01-01

    The author describes the efforts being made toward pollution prevention within the DOE complex, as a way to reduce overall project costs, in addition to decreasing the amount of waste to be handled. Pollution prevention is a concept which is trying to be ingrained into project planning. Part of the program involves the concept that ultimately the responsibility for waste comes back to the generator. Parts of the program involve efforts to reuse materials and equipment on new projects, to recycle wastes to generate offsetting revenue, and to increase awareness, accountability and incentives so as to stimulate action on this plan. Summaries of examples are presented in tables

  17. Project for a beam line consecrated to soft condensed matter, common heterogeneous materials and non-crystalline materials on soleil; Proposition pour une ligne dediee a la matiere molle, aux materiaux de grande diffusion et aux materiaux non-cristallises sur soleil

    Energy Technology Data Exchange (ETDEWEB)

    Ne, F.; Zemb, T. [CEA Saclay, 91 - Gif-sur-Yvette (France). Dept. de Recherche sur l`Etat Condense, les Atomes et les Molecules; Diat, O. [ESRF, 38 - Grenoble (France)

    1998-12-31

    This project is a part of the `SOLEIL` synchrotron project. The camera proposed is optimized for small angle x-ray scattering in the domain of soft condensed matter, common heterogeneous materials such as wood, cements, glass, and more generally non-crystalline materials. The beam line is designed to allow a quick succession of different users without time consuming adjustments. Therefore, optical settings are minimized, taking into account the pluri-disciplinary nature of the analysis possibilities. To this end, the technical requirements are as follows. First and essentially, the wave-length has to be fixed and set around 12 keV. Focusing mirrors, optics to sample and sample to detector distances, and the size of the detector allow for a wide range of wave vector to be used. Rejection rate will be lower, and angular dynamical range will be larger than any of the current synchrotron lines. We want this line to be, and to stay, complementary to more specific systems, such as reflectivity experiments or grazing angle scattering experiments. However, we are thinking of an adaptation to ultra small angle scattering mode, based on the Bonse and Hart camera. Such equipment, actually a kind of `Instamatic` of the reciprocal space, will fulfill to the need of chemical engineers, biophysicists or material scientists interested in hard as well as soft condensed matter. It will allow a large amount of experiments per time unit. (author)

  18. Beginning analog electronics through projects

    CERN Document Server

    Singmin, Andrew

    2001-01-01

    Analog electronics is the simplest way to start a fun, informative, learning program. Beginning Analog Electronics Through Projects, Second Edition was written with the needs of beginning hobbyists and students in mind. This revision of Andrew Singmin's popular Beginning Electronics Through Projects provides practical exercises, building techniques, and ideas for useful electronics projects. Additionally, it features new material on analog and digital electronics, and new projects for troubleshooting test equipment.Published in the tradition of Beginning Electronics Through Projects an

  19. 3. Research Coordination Meeting (RCM) of the Coordinated Research Project (CRP) on 'Studies of advanced reactor technology options for effective incineration of radioactive waste'. Working material

    International Nuclear Information System (INIS)

    2007-01-01

    To meet expressed Member States' needs, the IAEA has initiated a Coordinated Research Project (CRP) on 'Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste'. The final goal of the CRP is to deepen the understanding of the dynamics of transmutation systems, e.g. the accelerator driven system, especially systems with deteriorated safety parameters, qualify the available methods, specify the range of validity of methods, and formulate requirements for future theoretical developments. Should transient experiments be available, the CRP will pursue experimental benchmarking work. In any case, based on the results, the CRP will conclude on the potential need of transient experiments and make appropriate proposals for experimental programs. The Technical Meeting in Chennai was the 3rd Research Coordination Meeting (RCM) of the CRP The man objectives of the RCM were to: - Discuss and perform inter-comparisons of the various benchmark results; - Prepare the first draft of the final CRP Report Status of the analyses and inter-comparisons of the results. The main objective of the CRP was to study innovative technology options for incinerating/utilizing radioactive wastes. The CRP's benchmarking exercises focused on eight innovative transmutation 'Domains', which correspond to different critical and sub-critical concepts or groups of concepts: I. Critical fast reactor, solid fuel, with fertile; II. Critical fast reactor, solid fuel, fertile-free; III. ADS, solid fuel, with fertile; IV. ADS, solid fuel, fertile-free; V. Critical reactor and ADS, molten salt fuel, with fertile; VI. Critical reactor and ADS, molten salt fuel, fertile-free; VII. Critical fast reactor and ADS, gas cooled; VIII. Fusion/fission hybrid system. For each of these Domains, the discussions and inter-comparisons considered the following issues: - Reactor-models; - Scenarios/phenomena; - Static analyses; - Dynamic analyses; - Methods; - Codes; - Neutronic data base

  20. FY 1993 Report on the industrial science and technology research and development project results. Research and development of non-linear photoelectronic materials; 1993 nendo hisenkei hikari denshi zairyo no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-11-01

    Described herein are the results of the industrial science and technology research and development project for nonlinear optoelectronic materials. The more functional chiral and pi-conjugated compounds are investigated as the organic, low-molecular-weight materials. The technologies for the orientation-controlled crystal growth are continuously investigated. Polyacetylene is investigated as the conjugated pi-electron system. The glass-dispersed systems, prepared by the sol-gel, superlow-melting glass and super-cooling methods, are investigated. In order to elucidate the relationship between the organic superlattice and properties (e.g., photoelectronic properties), the intramolecular interactions under the superlattice conditions are estimated by the theoretical chemical calculations, and the optimum structures deduced from the measured properties are proposed. The thin, composite films of fine metallic particles and glass are prepared by the multi-dimensional sputtering, to explore the constituent materials suitable for the three-dimensional superstructures, and their properties are analyzed. The thin semiconductor films of superlattices are prepared by the molecular beam epitaxy method, to investigate the optimization of the structures and compositions. The basic aspects of the three-dimensional superstructures, prepared by the superfine machining, are investigated. The results of the comprehensive investigations and researches are also described. (NEDO)

  1. Development and evaluation of die materials for use in the growth of silicon ribbons by the inverted ribbon growth process, task 2. LSSA project

    Science.gov (United States)

    Duffy, M. T.; Berkman, S.; Moss, H. S.; Cullen, G. W.

    1978-01-01

    The results of emission spectroscopic analysis indicate that molten silicon can remain in contact with hot-pressed Si3N4 (99.2 percent theoretical density) for prolonged periods without attaining the impurity content level of the nitride. Although MgO was used as binder, Mg was not found present in the silicon sessile drop in quantities much above the level initially present in the silicon source material. Preliminary experiments with EFG-type dies coated with CVD Si3N4 or CVD SiOxNy indicate that capillary rise does not occur readily in these dies. The same was found to be true of hot-pressed and reaction-sintered Si3N4 obtained commercially. However, when dies were formed by depositing CVD layers on shaped silicon slabs, a column of molten silicon was maintained in each CVD die while being heated in contact with a crucible of molten silicon. Preliminary wetting of dies appears necessary for EFG growth. Several ribbon growth experiments were performed from V-shaped dies.

  2. Monitoring of colonies and provisioning of rooks with nest material as a potential tool for stabilizing colonies and increasing nesting opportunities in the countryside. Project report

    Directory of Open Access Journals (Sweden)

    Slobodník Roman

    2017-12-01

    Full Text Available The rook is a species inhabiting open agricultural landscape whose non-active nests are also used by other bird species for nesting. It is the decline in rook colonies that has been posited as one of the reasons for decrease in the red-footed falcon (Falco vespertinus population in Slovakia since the 1970s. During the period from 2012 till 2016, four monitorings of rook colonies were carried out in south-western Slovakia (Diakovce, Nitrianska Osada, Sokolce and Tvrdošovce. In the colony at Tvrdošovce, supporting activity involving provisioning of rooks with nest material was under way from 2014 until 2016. While the colonies at Diakovce and Nitrianska Osada have been showing a slight decrease in the number of nesting rooks, despite larger interannual differences the colony at Sokolce has been showing an upward trend. The size of the colony at Tvrdošovce has been stable since the beginning of the supporting activity. This activity had a statistically significant positive effect on the width of rook nests. In 74 cases in the studied rook colonies we have recorded nesting by three other bird species – Eurasian kestrel (Falco tinnunculus 43.8%, western jackdaw (Corvus monedula 39.7% and long-eared owl (Asio otus 16.4%. In 2015 two female redfooted falcons were observed in the colony at Tvrdošovce.

  3. Gorky’s Editorial Project The History of the Civil War: On the Materials of the A.M. Gorky (IWL RAS and RGASPI Archives

    Directory of Open Access Journals (Sweden)

    Olga V. Bystrova

    2017-12-01

    Full Text Available The article focuses on the history of Maksim Gorky’s design — the publication of the History of the Civil War volumes. The analysis of Gorky’s correspondence (1929–1930 from the A.M. Gorky archives (IWL RAS reveals that the idea of the collection emerged at the beginning of 1928. In the course of the preparatory work, the Central Committee of the CPSU(b obliged Communist party officials, Soviet and military functionaries in all Soviet republics and regions to collect documents and memories of the Civil War, to write and review materials for the collection. Gorky conceived the volumes of The History of the Civil War to be popular and accessible to the average reader. For this purpose, he considered inviting talented Soviet authors who took part in the Civil War. Gorky’s recommendations were taken into account while forming the Editorial Board. The CC of the CPSU(b on July 31, 1931 established the Editorial Board (comprised of Chief, Historical and Artistic Boards that Gorky also joined. Under his guidance, the Secretariat of the Chief Editorial Board issued instructions that were intended to direct a wide range of research subjects and provide researchers with methodology. Gorky’s letters from the RGASPI collection give us idea of the huge amount of work done by the writer in the process of preparing the first volume for publication. If the first, 1935 volume reflects Gorky’s vision and concept of the collection, the subsequent 4 volumes published after his death departed from the original design. Despite this and the fact that only 5 volumes out of 15 were issued, we can state that Gorky’s design was realized and that the History of the Civil War still remains an authoritative book in the field.

  4. Designing Material Materialising Design

    DEFF Research Database (Denmark)

    Nicholas, Paul

    2013-01-01

    Designing Material Materialising Design documents five projects developed at the Centre for Information Technology and Architecture (CITA) at the Royal Danish Academy of Fine Arts, School of Architecture. These projects explore the idea that new designed materials might require new design methods....... Focusing on fibre reinforced composites, this book sustains an exploration into the design and making of elastically tailored architectural structures that rely on the use of computational design to predict sensitive interdependencies between geometry and behaviour. Developing novel concepts...

  5. Developing Marine Science Instructional Materials Using Integrated Scientist-Educator Collaborative Design Teams: A Discussion of Challenges and Success Developing Real Time Data Projects for the COOL Classroom

    Science.gov (United States)

    McDonnell, J.; Duncan, R. G.; Glenn, S.

    2007-12-01

    Current reforms in science education place increasing demands on teachers and students to engage not only with scientific content but also to develop an understanding of the nature of scientific inquiry (AAAS, 1993; NRC, 1996). Teachers are expected to engage students with authentic scientific practices including posing questions, conducting observations, analyzing data, developing explanations and arguing about them using evidence. This charge is challenging for many reasons most notably the difficulty in obtaining meaningful data about complex scientific phenomena that can be used to address relevant scientific questions that are interesting and understandable to K-12 students. We believe that ocean sciences provide an excellent context for fostering scientific inquiry in the classroom. Of particular interest are the technological and scientific advances of Ocean Observing Systems, which allow scientists to continuously interact with instruments, facilities, and other scientists to explore the earth-ocean- atmosphere system remotely. Oceanographers are making long-term measurements that can also resolve episodic oceanic processes on a wide range of spatial and temporal scales crucial to resolving scientific questions related to Earth's climate, geodynamics, and marine ecosystems. The availability of a diverse array of large data sets that are easily accessible provides a unique opportunity to develop inquiry-based learning environments in which students can explore many important questions that reflect current research trends in ocean sciences. In addition, due to the interdisciplinary nature of the ocean sciences these data sets can be used to examine ocean phenomena from a chemical, physical, or biological perspective; making them particularly useful for science teaching across the disciplines. In this session we will describe some of the efforts of the Centers for Ocean Sciences Education Excellence- Mid Atlantic (COSEE MA) to develop instructional materials

  6. The stakeholder-consultation process in developing training and awareness-raising material within the framework of the EU Directive on Sustainable Use of Pesticides: The case of the EU-project BROWSE

    Energy Technology Data Exchange (ETDEWEB)

    Sacchettini, Gabriele, E-mail: gabriele.sacchettini@unicatt.it; Calliera, Maura; Marchis, Alexandru; Lamastra, Lucrezia; Capri, Ettore

    2012-11-01

    In September 2009, the Council of the European Union adopted the Directive on Sustainable Use of Pesticides (SUD). The core idea is that in order to achieve sustainable use of pesticides, it is necessary that everyone is conscious about the risks to both human health and the environment associated with the use of plant protection products. Therefore, in the SUD, training and raising awareness play key roles in order to achieve the objectives of the directive. In this sense, the European-founded project BROWSE (Bystanders, Residents, Operators and WorkerS Exposure models for plant protection products) has, as one of its main objectives, to contribute to the implementation of the SUD through the development and dissemination of communication materials for training and raising awareness. For this reason, a consultation process was implemented involving all relevant stakeholders in order to identify their opinions regarding the subjects to be prioritised, the factors influencing pesticide exposure to be focused on and the most suitable formats to develop training and awareness-raising material as well as identification of target groups. To collect the required information, participants were asked to answer an electronic questionnaire (giving the possibility through several debates for additional comments). The collected findings and the ensuing debates are described in this article and are going to be taken into account in the development of the BROWSE training and communication material for the raising of awareness. -- Highlights: Black-Right-Pointing-Pointer Training and raising awareness play key roles in achieving the sustainable use of pesticides. Black-Right-Pointing-Pointer A stakeholder-consultation was made to find priorities for new training and communication material. Black-Right-Pointing-Pointer The priorities will be to explain risk-identifying mitigation measures to reduce exposure. Black-Right-Pointing-Pointer The focus will be to train operators and

  7. The stakeholder-consultation process in developing training and awareness-raising material within the framework of the EU Directive on Sustainable Use of Pesticides: The case of the EU-project BROWSE

    International Nuclear Information System (INIS)

    Sacchettini, Gabriele; Calliera, Maura; Marchis, Alexandru; Lamastra, Lucrezia; Capri, Ettore

    2012-01-01

    In September 2009, the Council of the European Union adopted the Directive on Sustainable Use of Pesticides (SUD). The core idea is that in order to achieve sustainable use of pesticides, it is necessary that everyone is conscious about the risks to both human health and the environment associated with the use of plant protection products. Therefore, in the SUD, training and raising awareness play key roles in order to achieve the objectives of the directive. In this sense, the European-founded project BROWSE (Bystanders, Residents, Operators and WorkerS Exposure models for plant protection products) has, as one of its main objectives, to contribute to the implementation of the SUD through the development and dissemination of communication materials for training and raising awareness. For this reason, a consultation process was implemented involving all relevant stakeholders in order to identify their opinions regarding the subjects to be prioritised, the factors influencing pesticide exposure to be focused on and the most suitable formats to develop training and awareness-raising material as well as identification of target groups. To collect the required information, participants were asked to answer an electronic questionnaire (giving the possibility through several debates for additional comments). The collected findings and the ensuing debates are described in this article and are going to be taken into account in the development of the BROWSE training and communication material for the raising of awareness. -- Highlights: ► Training and raising awareness play key roles in achieving the sustainable use of pesticides. ► A stakeholder-consultation was made to find priorities for new training and communication material. ► The priorities will be to explain risk-identifying mitigation measures to reduce exposure. ► The focus will be to train operators and inform people living in rural areas. ► Videos are considered the most suitable technique to deliver

  8. Heavy water reactors: Status and projected development. Part II. Final draft of a report to be published in the IAEA technical reports series. Working material

    International Nuclear Information System (INIS)

    2001-01-01

    In 1996, the 40th General Conference of the IAEA approved the establishment of a new International Working Group (IWG) on Advanced Technologies for Heavy Water Reactors (HWR). At its first meeting, held in June 1997, the IWG-HWR advised the Agency to prepare a TECDOC to present: a) the status of HWR advanced technology in the areas of economics, safety and fuel cycle flexibility and sustainable development; and b) the advanced technology developments needed in the following two decades to achieve the vision of the advanced HWR. The IAEA convened two consultancies and two Advisory Group Meetings to prepare the TECDOC. One of the consultancies was on 'Fuel Cycle Flexibility and Sustainable Development'; the second was on 'Passive Safety Features of HWRs Status and Projected Advances'. The members of the IWG-HWR collectively agreed on the essential features that the development of HWRs must emphasize. These 'drivers' are: improved economics: the fundamental requirement for all successful high technology developments to advance, is real economic improvements, consistent with improved quality; enhanced safety: to meet increasingly stringent requirements to satisfy the regulatory authorities, the public and the operators, an evolutionary safety path will be followed, incorporating advanced passive safety concepts where it is feasible and sensible to do so; sustainable development: the high neutron economy of HWRs results in a reactor that can burn natural uranium at high utilization, utilize spent fuel from other reactor types, and, through various recycle strategies including use of thorium, extend fissile fuel resources into the indefinite future. The objectives of this document are: to present the status of HWR technology; to document the safety characteristics of current HWR designs and the potential enhancements; to present a 'vision' of the long-term development of the HWR for use into the next century as an electricity source that is sustainable and flexible and

  9. Report of the consultancy meeting for the coordinated research project on comparative analysis of methods and tools for nuclear knowledge preservation. Working material

    International Nuclear Information System (INIS)

    2006-01-01

    In response to long-term energy scenarios, it is necessary to preserve and maintain the accumulated knowledge in nuclear science and the nuclear industry. Within these scenarios is the reality of ageing of the human workforce in the nuclear sector and the sharp decline in the number of entrants to education and training in nuclear science and engineering. The challenge of the IAEA to this reality is to enhance the capacity of Member States to maintain and preserve the information and knowledge resources related to the peaceful use of nuclear energy. This knowledge could be tacit and/or explicit. Appendix A lists examples of tacit and explicit knowledge that need to be preserved. Finally, the need to manage, access and preserve this knowledge across human generations (30 years) and even nuclear facility lifetimes (over 60) years extends the challenges for the CRP. Implementation of the recommendations and conclusions from this CRP may be difficult due to resources, legal factors and legacy systems, but nevertheless the goal of nuclear knowledge preservation should be permanent access and knowledge resource interoperability that will allow knowledge sharing for as long as the knowledge remains useful. This Coordinated Research Project was started in the IAEA Program for the period 2004-2005 and continues for the 2006-2007, Programme C, Capacity Building and Nuclear Knowledge Maintenance for Sustainable Energy Development, Section C.3, Nuclear Knowledge Management and Section C.3.03, Maintenance and preservation of knowledge in specific areas of nuclear science and technology, specifically a 'CRP on knowledge preservation technologies leading to archiving of information'. The objectives of the consultancy were: - to review the CRP's Terms of Reference, research framework and specific research topics, and - to develop the survey form on current status of knowledge preservation to establish a baseline source of information on nuclear knowledge management in IAEA

  10. Heavy water reactors: Status and projected development. Part I. Final draft of a report to be published in the IAEA technical reports series. Working material

    International Nuclear Information System (INIS)

    2001-01-01

    In 1996, the 40th General Conference of the IAEA approved the establishment of a new International Working Group (IWG) on Advanced Technologies for Heavy Water Reactors (HWR). At its first meeting, held in June 1997, the IWG-HWR advised the Agency to prepare a TECDOC to present: a) the status of HWR advanced technology in the areas of economics, safety and fuel cycle flexibility and sustainable development; and b) the advanced technology developments needed in the following two decades to achieve the vision of the advanced HWR. The IAEA convened two consultancies and two Advisory Group Meetings to prepare the TECDOC. One of the consultancies was on 'Fuel Cycle Flexibility and Sustainable Development'; the second was on 'Passive Safety Features of HWRs Status and Projected Advances'. The members of the IWG-HWR collectively agreed on the essential features that the development of HWRs must emphasize. These 'drivers' are: improved economics: the fundamental requirement for all successful high technology developments to advance, is real economic improvements, consistent with improved quality; enhanced safety: to meet increasingly stringent requirements to satisfy the regulatory authorities, the public and the operators, an evolutionary safety path will be followed, incorporating advanced passive safety concepts where it is feasible and sensible to do so; sustainable development: the high neutron economy of HWRs results in a reactor that can burn natural uranium at high utilization, utilize spent fuel from other reactor types, and, through various recycle strategies including use of thorium, extend fissile fuel resources into the indefinite future. The objectives of this document are: to present the status of HWR technology; to document the safety characteristics of current HWR designs and the potential enhancements; to present a 'vision' of the long-term development of the HWR for use into the next century as an electricity source that is sustainable and flexible and

  11. Materials and nanotechnology

    International Nuclear Information System (INIS)

    2014-01-01

    The focus of the Materials and Nanotechnology Program is technology development related to processing, analysis, testing and characterization of materials in general. These are achieved through execution of R&D projects in engineering and materials science, cooperative projects with private and public sector companies, universities and other research institutes. Besides technology development, this Program also fosters training and human resource development in association with the University of São Paulo and many industrial sectors. This Program is divided into sub-programs in broad areas such as ceramic, composite and metallic materials as well as characterization of physical and chemical properties of materials. The sub-programs are further divided into general topics and within each topic, R&D projects. A brief description of progress in each topic during the last three years follows. (author)

  12. Articulating Material Criteria

    DEFF Research Database (Denmark)

    Hasling, Karen Marie

    2013-01-01

    This paper discusses the experiences and potentials with materials teaching at the Institute for Product Design at Kolding School of Design, using materials teaching as experiments in my PhD project. The project intents to create a stronger material awareness among product design students...... with emphasis on sustainability. The experiments aim to develop an understanding of, how product design students include materials in their design practice and how tools can be developed that further enhance this. Hence experiments are essential for the progress of the PhD project as they help to observe....... Furthermore the purpose is to initiate a discussion on, how to create educational tools for material awareness creation in the design education e.g. by applying objective and quantitative methods in an otherwise often subjective design process....

  13. FY 2000 report on the results of the research and development project for new industry creation type industrial science technologies. R and D of the intellectual material and structural systems (R and D of the intellectual material and structural systems); 2000 nendo shinki sangyo soshutsugata sangyo kagaku gijutsu kenkyu kaihatsu seika hokokusho. Chiteki kozo system no kenkyu kaihatsu (chiteki kozo system no kenkyu kaihatsu)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Described herein are the FY 2000 results of the R and D project for development of intellectual materials and structural systems, where the fibrous or leafy sensor material or element (muscle) is integrated with a structure of an advanced material (skeleton) to process and control information (brain). The program for development of the health monitoring technologies successfully improves the fine FRG (Fiber Bragg Grating) as the high-performance sensor, equipped with a connector which allows the sensor to be easily connected to the normal diameter one, and develops various prototype sensors. The program for self-diagnosis of structural soundness and controlling damages verifies detection effectiveness of the embedded fine FRG sensor. The impact-related characteristics and damages of the reinforced flat plate are detected by embedding the optical fiber sensor. The program for developing the actuator materials and elements prepares the 20{mu}m thick piezoelectric sheet of adequate strength and toughness by dispersing the PNN-PZT system with partially stabilized zirconia (PSZ). The program for the function-gradient systems prepares the FGM driven at normal temperature, characterized by its structure of more evenly distributed stress, to evaluate its characteristics. It is proved to have high durability. The results of the comprehensive survey are also described. (NEDO)

  14. Photovoltaic Materials

    Energy Technology Data Exchange (ETDEWEB)

    Duty, C.; Angelini, J.; Armstrong, B.; Bennett, C.; Evans, B.; Jellison, G. E.; Joshi, P.; List, F.; Paranthaman, P.; Parish, C.; Wereszczak, A.

    2012-10-15

    The goal of the current project was to help make the US solar industry a world leader in the manufacture of thin film photovoltaics. The overall approach was to leverage ORNL’s unique characterization and processing technologies to gain a better understanding of the fundamental challenges for solar cell processing and apply that knowledge to targeted projects with industry members. ORNL has the capabilities in place and the expertise required to understand how basic material properties including defects, impurities, and grain boundaries affect the solar cell performance. ORNL also has unique processing capabilities to optimize the manufacturing process for fabrication of high efficiency and low cost solar cells. ORNL recently established the Center for Advanced Thin-film Systems (CATS), which contains a suite of optical and electrical characterization equipment specifically focused on solar cell research. Under this project, ORNL made these facilities available to industrial partners who were interested in pursuing collaborative research toward the improvement of their product or manufacturing process. Four specific projects were pursued with industrial partners: Global Solar Energy is a solar industry leader in full scale production manufacturing highly-efficient Copper Indium Gallium diSelenide (CIGS) thin film solar material, cells and products. ORNL worked with GSE to develop a scalable, non-vacuum, solution technique to deposit amorphous or nanocrystalline conducting barrier layers on untextured stainless steel substrates for fabricating high efficiency flexible CIGS PV. Ferro Corporation’s Electronic, Color and Glass Materials (“ECGM”) business unit is currently the world’s largest supplier of metallic contact materials in the crystalline solar cell marketplace. Ferro’s ECGM business unit has been the world's leading supplier of thick film metal pastes to the crystalline silicon PV industry for more than 30 years, and has had operational

  15. Define Project

    DEFF Research Database (Denmark)

    Munk-Madsen, Andreas

    2005-01-01

    "Project" is a key concept in IS management. The word is frequently used in textbooks and standards. Yet we seldom find a precise definition of the concept. This paper discusses how to define the concept of a project. The proposed definition covers both heavily formalized projects and informally...... organized, agile projects. Based on the proposed definition popular existing definitions are discussed....

  16. Project Management

    DEFF Research Database (Denmark)

    Project Management Theory Meets Practice contains the proceedings from the 1st Danish Project Management Research Conference (DAPMARC 2015), held in Copenhagen, Denmark, on May 21st, 2015.......Project Management Theory Meets Practice contains the proceedings from the 1st Danish Project Management Research Conference (DAPMARC 2015), held in Copenhagen, Denmark, on May 21st, 2015....

  17. Project Management

    DEFF Research Database (Denmark)

    Pilkington, Alan; Chai, Kah-Hin; Le, Yang

    2015-01-01

    This paper identifies the true coverage of PM theory through a bibliometric analysis of the International Journal of Project Management from 1996-2012. We identify six persistent research themes: project time management, project risk management, programme management, large-scale project management......, project success/failure and practitioner development. These differ from those presented in review and editorial articles in the literature. In addition, topics missing from the PM BOK: knowledge management project-based organization and project portfolio management have become more popular topics...

  18. Project financing

    International Nuclear Information System (INIS)

    Cowan, A.

    1998-01-01

    Project financing was defined ('where a lender to a specific project has recourse only to the cash flow and assets of that project for repayment and security respectively') and its attributes were described. Project financing was said to be particularly well suited to power, pipeline, mining, telecommunications, petro-chemicals, road construction, and oil and gas projects, i.e. large infrastructure projects that are difficult to fund on-balance sheet, where the risk profile of a project does not fit the corporation's risk appetite, or where higher leverage is required. Sources of project financing were identified. The need to analyze and mitigate risks, and being aware that lenders always take a conservative view and gravitate towards the lowest common denominator, were considered the key to success in obtaining project financing funds. TransAlta Corporation's project financing experiences were used to illustrate the potential of this source of financing

  19. FOREWORD: Materials metrology Materials metrology

    Science.gov (United States)

    Bennett, Seton; Valdés, Joaquin

    2010-04-01

    It seems that so much of modern life is defined by the materials we use. From aircraft to architecture, from cars to communications, from microelectronics to medicine, the development of new materials and the innovative application of existing ones have underpinned the technological advances that have transformed the way we live, work and play. Recognizing the need for a sound technical basis for drafting codes of practice and specifications for advanced materials, the governments of countries of the Economic Summit (G7) and the European Commission signed a Memorandum of Understanding in 1982 to establish the Versailles Project on Advanced Materials and Standards (VAMAS). This project supports international trade by enabling scientific collaboration as a precursor to the drafting of standards. The VAMAS participants recognized the importance of agreeing a reliable, universally accepted basis for the traceability of the measurements on which standards depend for their preparation and implementation. Seeing the need to involve the wider metrology community, VAMAS approached the Comité International des Poids et Mesures (CIPM). Following discussions with NMI Directors and a workshop at the BIPM in February 2005, the CIPM decided to establish an ad hoc Working Group on the metrology applicable to the measurement of material properties. The Working Group presented its conclusions to the CIPM in October 2007 and published its final report in 2008, leading to the signature of a Memorandum of Understanding between VAMAS and the BIPM. This MoU recognizes the work that is already going on in VAMAS as well as in the Consultative Committees of the CIPM and establishes a framework for an ongoing dialogue on issues of materials metrology. The question of what is meant by traceability in the metrology of the properties of materials is particularly vexed when the measurement results depend on a specified procedure. In these cases, confidence in results requires not only traceable

  20. Project descriptions

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    This part specifies the activities and project tasks of each project broken down according to types of financing, listing the current projects Lw 1 through 3 funded by long-term provisions (budget), the current projects LB 1 and 2, LG 1 through 5, LK1, LM1, and LU 1 through 6 financed from special funds, and the planned projects ZG 1 through 4 and ZU 1, also financed from special funds. (DG) [de