Fusion materials semiannual progress report for the period ending June 30, 1998

Energy Technology Data Exchange (ETDEWEB)

Burn, G. [ed.] [comp.

1998-09-01

This is the twenty-fourth in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

Fusion materials semiannual progress report for the period ending June 30, 1998

International Nuclear Information System (INIS)

Burn, G.

1998-09-01

This is the twenty-fourth in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

The role of technical progress in the process of recalculating oil reserves

International Nuclear Information System (INIS)

Boulard, J.N.

1999-01-01

Contrary to the concept of resources (which is essentially a geological one), the notion of reserves designates the quantities that are technically and economically recoverable. Beyond the production-related effect, the reserves therefore evolve over time in accordance with numerous technical and economic parameters. Among these parameters, it can be seen that technical progress plays a considerable role throughout the process of converting resources into reserves, including progress in the identification, accessibility and processing of the resources, and improvements in economic viability. After having tackled the problem of measuring the 'technical progress effects' and citing examples, we demonstrate that the evolution in oil reserves is subject to three types of impact. These are a quantitative impact by significantly improving the recovery rates or making it possible to identify hitherto undetectable oil fields, a qualitative impact by widening the resource base thanks to the adoption of new categories of oil (in particular the so-called 'unconventional' oils) and by carrying out the gradual substitution between these resources of differing qualities. There is also a dynamic impact, through the acceleration of resource availability. Through these three approaches, technical progress makes makes it possible to ensure continuity in oil supply and contributes significantly to the recalculation of reserves. It therefore acts as a compensating factor, counterbalancing the progressive depletion of resources. (author)

Fusion reactor materials semiannual progress report for the period ending March 31, 1993

International Nuclear Information System (INIS)

1993-07-01

This is the fourteenth in a series of semiannual technical progress reports on fusion reactor materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Depart of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. Separate abstracts were prepared for each individual section

Fusion reactor materials semiannual progress report for the period ending March 31, 1993

Energy Technology Data Exchange (ETDEWEB)

1993-07-01

This is the fourteenth in a series of semiannual technical progress reports on fusion reactor materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Depart of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. Separate abstracts were prepared for each individual section.

Fusion Materials Semiannual Progress Report for the Period Ending June 30, 1999

Energy Technology Data Exchange (ETDEWEB)

Rowcliffe, A.F.

1999-09-01

This is the twenty-sixth in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and its reported separately.

Technical progress by major task. Semiannual technical progress report, September 29, 1997 - March 29, 1998

International Nuclear Information System (INIS)

1998-01-01

The technical progress achieved during the period 29 September 1997 through 29 March 1998 on Contract DE-AC03-91SF18852 Radioisotope Thermoelectric Generators and Ancillary Activities is described in this report. The report is organized by program task structure: spacecraft integration and liaison; engineering support; safety; qualified unicouple production; RTG fabrication, assembly, and test; ground support equipment; RTG shipping and launch support; designs, reviews, and mission applications; project management, quality assurance, reliability, contract changes, CAGO acquisition (operating funds), and CAGO maintenance and repair

Fusion materials semiannual progress report for the period ending December 31, 1997

International Nuclear Information System (INIS)

Burn, G.

1998-03-01

This is the twenty-third in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Materials Program is a national effort involving several national laboratories, universities, and industries. A large fraction of this work, particularly in relation to fission reactor experiments, is carried out collaboratively with their partners in Japan, Russia, and the European Union. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide

Conjoint utility analysis of technical maturity and project progress of construction project

Directory of Open Access Journals (Sweden)

Ma Wei

2016-01-01

Full Text Available In this paper, taking construction project as the research object, the relationship between the project maturity index calculated by the construction project technical risks with different fine degree and the project progress index is studied, and the equilibrium relationship between the Party A’s utility curve and the Party B’s cost curve of using project maturity index and project progress index as the research variables is analyzed. The results show that, when the construction project technical risk division is more precise, the conjoint utility of the project's technical maturity index and the project progress is higher, and the project’s Party A and Party B two sides are closer to the optimal equilibrium. This shows that the construction project technical risk must be finely divided, and managed and controlled respectively, which will help to improve the conjoint utility of the project Party A and Party B two sides.

Nuclear measurements and reference materials annual progress report, january - december 1988

International Nuclear Information System (INIS)

1989-01-01

The 1988 progress report of the Central Bureau for Nuclear Measurements (CBNM) is presented. The major changes in the role and orientation of the Joint Research Center, of which CBNM is an institute, are included. The main tasks of CBNM, which involve the program on Nuclear Measurements and Reference Materials, are given. Technical activities concerning the GELINA electron beam and Van de Graaff accelerators are reported. The study of transition radiation at linear electron accelerators, and the development of isotope dilution mass spectrometry, for trace analysis and isotope abundance measurements in iron and gallium, are summarized. The scientific and technical support to the commission, work for third parties, and contribution to conferences are presented

Fusion materials semiannual progress report for period ending June 30, 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-08-01

This is the twenty-second in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. Topics covered here are: vanadium alloys; silicon carbide composites; ferritic/martensitic steels; austenitic stainless steels; insulating ceramics and optical materials; solid breeding materials; radiation effects mechanistic studies and experimental methods; dosimetry damage parameters; activation calculations; materials engineering and design requirements; irradiation facilities; test matrices; and experimental methods.

Fusion materials semiannual progress report for period ending June 30, 1997

International Nuclear Information System (INIS)

1997-08-01

This is the twenty-second in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. Topics covered here are: vanadium alloys; silicon carbide composites; ferritic/martensitic steels; austenitic stainless steels; insulating ceramics and optical materials; solid breeding materials; radiation effects mechanistic studies and experimental methods; dosimetry damage parameters; activation calculations; materials engineering and design requirements; irradiation facilities; test matrices; and experimental methods

International linear collider. A technical progress report

Energy Technology Data Exchange (ETDEWEB)

Arnold, Ned [Argonne National Laboratory, IL (United States); Aderhold, Sebastian [DESY, Hamburg (Germany); Adolphsen, Chris [Stanford Linear Accelerator Center, Menlo Park, CA (United States); and others

2012-07-01

The International Linear Collider: A Technical Progress Report marks the halfway point towards the Global Design Effort fulfilling its mandate to follow up the ILC Reference Design Report with a more optimised Technical Design Report (TDR) by the end of 2012. The TDR will be based on much of the work reported here and will contain all the elements needed to propose the ILC to collaborating governments, including a technical design and implementation plan that are realistic and have been better optimised for performance, cost and risk. We are on track to develop detailed plans for the ILC, such that once results from the Large Hadron Collider (LHC) at CERN establish the main science goals and parameters of the next machine, we will be in good position to make a strong proposal for this new major global project in particle physics. The two overriding issues for the ILC R and D programme are to demonstrate that the technical requirements for the accelerator are achievable with practical technologies, and that the ambitious physics goals can be addressed by realistic ILC detectors. This GDE interim report documents the impressive progress on the accelerator technologies that can make the ILC a reality. It highlights results of the technological demonstrations that are giving the community increased confidence that we will be ready to proceed with an ILC project following the TDR. The companion detector and physics report document likewise demonstrates how detector designs can meet the ambitious and detailed physics goals set out by the ILC Steering Committee. LHC results will likely affect the requirements for the machine design and the detectors, and we are monitoring that very closely, intending to adapt our design as those results become available.

International Linear Collider-A Technical Progress Report

Energy Technology Data Exchange (ETDEWEB)

Elsen, Eckhard; /DESY; Harrison, Mike; /Brookhaven; Hesla, Leah; /Fermilab; Ross, Marc; /Fermilab; Royole-Degieux, Perrine; /Paris, IN2P3; Takahashi, Rika; /KEK, Tsukuba; Walker, Nicholas; /DESY; Warmbein, Barbara; /DESY; Yamamoto, Akira; /KEK, Tsukuba; Yokoya, Kaoru; /KEK, Tsukuba; Zhang, Min; /Beijing, Inst. High Energy Phys.

2011-11-04

The International Linear Collider: A Technical Progress Report marks the halfway point towards the Global Design Effort fulfilling its mandate to follow up the ILC Reference Design Report with a more optimised Technical Design Report (TDR) by the end of 2012. The TDR will be based on much of the work reported here and will contain all the elements needed to propose the ILC to collaborating governments, including a technical design and implementation plan that are realistic and have been better optimised for performance, cost and risk. We are on track to develop detailed plans for the ILC, such that once results from the Large Hadron Collider (LHC) at CERN establish the main science goals and parameters of the next machine, we will be in good position to make a strong proposal for this new major global project in particle physics. The two overriding issues for the ILC R&D programme are to demonstrate that the technical requirements for the accelerator are achievable with practical technologies, and that the ambitious physics goals can be addressed by realistic ILC detectors. This GDE interim report documents the impressive progress on the accelerator technologies that can make the ILC a reality. It highlights results of the technological demonstrations that are giving the community increased confidence that we will be ready to proceed with an ILC project following the TDR. The companion detector and physics report document likewise demonstrates how detector designs can meet the ambitious and detailed physics goals set out by the ILC Steering Committee. LHC results will likely affect the requirements for the machine design and the detectors, and we are monitoring that very closely, intending to adapt our design as those results become available.

Technical progress in planning organization of the Ostravo-Karwina coal basin, ''Mining Projects of Ostravo''

Energy Technology Data Exchange (ETDEWEB)

Karpeta, B; Kolar, J

1979-01-01

Based on the main task of further improvement in labor productivity and improvement in the quality of products, the leading planning organization of the Ostravo-Karwina basin is planning and realizing progressive technological plans based on new equipment. Long-term plans for basin development up to 1990 stipulate a rise in capital investments by 180%, increase in the volume of productivity by 164% with a rise in the number of workers by 142%. Corresponding technical progress in planning is based on an improvement in the system of scientific-technical information, automation and technical equipping of the planning process, improvements in the forms and organizational structure. Organization of specialized research-planning groups to substantiate and to technically-economically evaluate technical progress, and also to develop comprehensive technical assignments is stipulated.

Swallowable Wireless Capsule Endoscopy: Progress and Technical Challenges

Directory of Open Access Journals (Sweden)

Guobing Pan

2012-01-01

Full Text Available Wireless capsule endoscopy (WCE offers a feasible noninvasive way to detect the whole gastrointestinal (GI tract and revolutionizes the diagnosis technology. However, compared with wired endoscopies, the limited working time, the low frame rate, and the low image resolution limit the wider application. The progress of this new technology is reviewed in this paper, and the evolution tendencies are analyzed to be high image resolution, high frame rate, and long working time. Unfortunately, the power supply of capsule endoscope (CE is the bottleneck. Wireless power transmission (WPT is the promising solution to this problem, but is also the technical challenge. Active CE is another tendency and will be the next geneion of the WCE. Nevertheless, it will not come true shortly, unless the practical locomotion mechanism of the active CE in GI tract is achieved. The locomotion mechanism is the other technical challenge, besides the challenge of WPT. The progress about the WPT and the active capsule technology is reviewed.

Stockholm international conference 2003 on geological repositories: Political and technical progress

International Nuclear Information System (INIS)

2004-01-01

The conference reviewed global progress made as well as current perspectives on the activities to develop geologic repositories. The objectives were to review the progress in policy making as well as technical issues and to strengthen international co-operation on waste management and disposal issues. The first day of the conference addressed the policy aspects of geological repositories and the second day featured the more technical issues. Session 1: International progress in performing long-term safety studies and security of geological disposal were discussed and reviewed with examples from OECD/NEA, Belgium, Sweden, USA, Switzerland and Russia. Session 2: Views on stakeholder involvement and decision making process were presented by international organisations and national implementers from Japan, United Kingdom, Belgium and OECD/NEA. Session 3: Views on stakeholder involvement and decision making process were presented by regional and local stakeholders from France, Finland, Korea and Sweden. Session 4: International instruments assisting in the implementation of geological repositories were discussed, for example ICRP and IAEA/NEA safety documents, Joint Convention, Safeguard agreements, Nuclear Liability Conventions, etc. Session 5: The contribution of Research, Development and Demonstration was discussed with overviews of the progress achieved on scientific and technical issues over the past four years. Progress and key issues were presented from Switzerland, USA, Finland, Japan, Sweden and IAEA. Each of the papers and poster presentations have been analysed and indexed separately

Logistic management materials-technical support railway enterprises

OpenAIRE

Dykan, V.; Borozenetc, T.

2014-01-01

The essence of logistics management. Determine the feasibility of applying the principles of logistics management in organizing the logistics of railway transport. Discussed measures to develop suppliers in the implementation of logistics management logistics. Identified the need to develop and implement regulatory and methodical system to improve materials-technical support through the introduction of modern logistics principles. Applied systemic campaign to organize the materials-technical ...

Fusion materials semiannual progress report for the period ending December 31, 1996

International Nuclear Information System (INIS)

1997-04-01

This is the twenty-first in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The report covers the following topics: vanadium alloys; silicon carbide composite materials; ferritic/martensitic steels; copper alloys and high heat flux materials; austenitic stainless steels; insulating ceramics and optical materials; solid breeding materials; radiation effects, mechanistic studies and experimental methods; dosimetry, damage parameters, and activation calculations; materials engineering and design requirements; and irradiation facilities, test matrices, and experimental methods

Fusion materials semiannual progress report for the period ending December 31, 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-04-01

This is the twenty-first in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The report covers the following topics: vanadium alloys; silicon carbide composite materials; ferritic/martensitic steels; copper alloys and high heat flux materials; austenitic stainless steels; insulating ceramics and optical materials; solid breeding materials; radiation effects, mechanistic studies and experimental methods; dosimetry, damage parameters, and activation calculations; materials engineering and design requirements; and irradiation facilities, test matrices, and experimental methods.

Assessment of material and technical resources of crop production technologies

Directory of Open Access Journals (Sweden)

V. M. Beylis

2017-01-01

Full Text Available The author explains the general principles of influence of the material and technical resources (MTR on performance and efficiency of the main technological operations in crop production. Various technologies from the point of view of MTR expenses were estimated. The general tendencies in development of crop production technologies were revealed. The distribution of costs of materials and equipment to perform a variety of agricultural activities was determined. Cost indicators should be a guide in the search of innovative technological processes and working elements of agricultural machins. The greatest values of expenses of work, fuel, metal, and also, money where found. The concepts allowing to provide costs production reduction were formulated. To achieve the maximum productivity with the minimum expenses, the perspective calculations shoul be based on «progressive» agrotechnologies. When determining progressive agrotechnology it is necessary on reasonable grounds to approach indicators of crop productivity in various agrozones and regions of the country. For an assessment of efficiency of MTR by crop production and ensuring decrease in resource intensity of agricultural products by search and use of essentially new technologies for energy saving when performing agricultural operations, an integrated percentage indicator of comparison of progressive technologies with the applied ones was developed. MTR at application of new progressive crop production technologies by integrated percentage index were estimated. This indicator can be used for definition of efficiency of MTR. Application of the offered technique will promote an effective assessment of MTR, decrease in resource intensity by search and developments of essentially new technologies of performance of operations in crop production.

Materials Technical Team Roadmap

Energy Technology Data Exchange (ETDEWEB)

none,

2013-08-01

Roadmap identifying the efforts of the Materials Technical Team (MTT) to focus primarily on reducing the mass of structural systems such as the body and chassis in light-duty vehicles (including passenger cars and light trucks) which enables improved vehicle efficiency regardless of the vehicle size or propulsion system employed.

Technical Education Outreach in Materials Science and Technology Based on NASA's Materials Research

Science.gov (United States)

Jacobs, James A.

2003-01-01

The grant NAG-1 -2125, Technical Education Outreach in Materials Science and Technology, based on NASA s Materials Research, involves collaborative effort among the National Aeronautics and Space Administration s Langley Research Center (NASA-LaRC), Norfolk State University (NSU), national research centers, private industry, technical societies, colleges and universities. The collaboration aims to strengthen math, science and technology education by providing outreach related to materials science and technology (MST). The goal of the project is to transfer new developments from LaRC s Center for Excellence for Structures and Materials and other NASA materials research into technical education across the nation to provide educational outreach and strengthen technical education. To achieve this goal we are employing two main strategies: 1) development of the gateway website and 2) using the National Educators Workshop: Update in Engineering Materials, Science and Technology (NEW:Updates). We have also participated in a number of national projects, presented talks at technical meetings and published articles aimed at improving k-12 technical education. Through the three years of this project the NSU team developed the successful MST-Online site and continued to upgrade and update it as our limited resources permitted. Three annual NEW:Updates conducted from 2000 though 2002 overcame the challenges presented first by the September 11,2001 terrorist attacks and the slow U.S. economy and still managed to conduct very effective workshops and expand our outreach efforts. Plans began on NEW:Update 2003 to be hosted by NASA Langley as a part of the celebration of the Centennial of Controlled Flight.

Heavy Vehicle Propulsion Materials Program: Progress and Highlights

International Nuclear Information System (INIS)

D. Ray Johnson; Sidney Diamond

2000-01-01

The Heavy Vehicle Propulsion Materials Program was begun in 1997 to support the enabling materials needs of the DOE Office of Heavy Vehicle Technologies (OHVT). The technical agenda for the program grew out of the technology roadmap for the OHVT and includes efforts in materials for: fuel systems, exhaust aftertreatment, valve train, air handling, structural components, electrochemical propulsion, natural gas storage, and thermal management. A five-year program plan was written in early 2000, following a stakeholders workshop. The technical issues and planned and ongoing projects are discussed. Brief summaries of several technical highlights are given

Recent Progress in First-Principles Methods for Computing the Electronic Structure of Correlated Materials

Directory of Open Access Journals (Sweden)

Fredrik Nilsson

2018-03-01

Full Text Available Substantial progress has been achieved in the last couple of decades in computing the electronic structure of correlated materials from first principles. This progress has been driven by parallel development in theory and numerical algorithms. Theoretical development in combining ab initio approaches and many-body methods is particularly promising. A crucial role is also played by a systematic method for deriving a low-energy model, which bridges the gap between real and model systems. In this article, an overview is given tracing the development from the LDA+U to the latest progress in combining the G W method and (extended dynamical mean-field theory ( G W +EDMFT. The emphasis is on conceptual and theoretical aspects rather than technical ones.

Materials testing and requirements for the ERDA nuclear-powered artificial heart. Technical progress report, July 15, 1974--May 1, 1975

International Nuclear Information System (INIS)

Andrade, J.D.; Coleman, D.L.; Leigh, A.; Hufferd, W.L.

1975-01-01

Progress on the materials research and development effort for the ERDA-sponsored nuclear-powered artificial heart program is presented. Progress made during the first three years on hydrogel grafting and biological studies is summarized. Progress during the fourth year on studies of implanted artificial hearts, development of albumin surfaces, and in vitro mechanical studies is presented. (U.S.)

Heavy Vehicle Propulsion Materials: Recent Progress and Future Plans

International Nuclear Information System (INIS)

D. Ray Johnson; Sidney Diamond

2001-01-01

The Heavy Vehicle Propulsion Materials Program provides enabling materials technology for the U.S. DOE Office of Heavy Vehicle Technologies (OHVT). The technical agenda for the program is based on an industry assessment and the technology roadmap for the OHVT. A five-year program plan was published in 2000. Major efforts in the program are materials for diesel engine fuel systems, exhaust aftertreatment, and air handling. Additional efforts include diesel engine valve-train materials, structural components, and thermal management. Advanced materials, including high-temperature metal alloys, intermetallics, cermets, ceramics, amorphous materials, metal- and ceramic-matrix composites, and coatings, are investigated for critical engine applications. Selected technical issues and planned and ongoing projects as well as brief summaries of several technical highlights are given

Technical Progress of the New Worlds Observer Mission

Science.gov (United States)

Lo, Amy; Noecker, C.; Cash, W.; NWO Study Team

2009-01-01

We report on the technical progress of the New Worlds Observer (NWO) mission concept. NWO is a two spacecraft mission that is capable of detecting and characterizing extra-solar, terrestrial planets and planetary systems. NWO consists of an external starshade and an UV-optical space telescope, flying in tandem. The starshade is a petal-shaped, opaque screen that creates an extremely dark shadow large enough to shade the telescope aperture from the target star. The NWO team has been addressing the top technology challenges of the concept, and report here our progress. We will present the current mission configuration best suited to address Terrestrial Planet Finding requirements, and highlight the technological breakthroughs that we have achieved this year. In particular, we will report on progress made in precision deployables for the large starshade, and the trajectory & alignment control system for NWO. We will also briefly highlight advances in understanding the starshade optical performance.

Technical progress faced with the challenges of the energy sector in the future

International Nuclear Information System (INIS)

Maillard, D.

1999-01-01

The colloquium organised by the Association of Energy Economists dealing with the theme 'Technical progress faced with the challenges of the energy sector in the future' takes place against a backdrop of ever-increasing initiatives in this field, for example at the World Energy Council or the International Energy Agency Faith in technical progress is widespread but should be supported by studies without any preconceived ideas. Research and development efforts must be fully supported, and in a climate of opening markets and liberalization the public authorities have a major role to pay. Historically, the markets have always been able to meet new needs thanks to technology, but the ambitious targets that the international community has set itself regarding the emission of greenhouse gases imply technical improvements and major investments. (authors)

Material and energy balances of technical means in horticulture and farming - from production to disposal

International Nuclear Information System (INIS)

1993-01-01

The twenty papers of this progress report, which are not individually recorded, belong to either one of the subject areas ''material and energy balances of technical means in horticulture and forming from production to disposal'' and ''plastics in construction and technical systems''. The first-mentioned subject area deals with balances for technical means at horticultural enterprises, greenhouse constructions, and styrofoam in farm buildings, and comprises short papers on sewage treatment plants in the form of beds of plants and ecological aspects of horticultural activities in open spaces. The second subject area mainly concerns recycling and multiple uses of plastics (silage and protective foils) as well as air-flow thermal collector systems. Advances in the construction and use of foil-covered greenhouses and experience with protective nets for plant cultures, energy shields, and shading are reported. (UWA) [de

Fusion materials semiannual progress report for the period ending March 31, 1994

International Nuclear Information System (INIS)

1994-09-01

This is the sixteenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. This report is divided into the following areas: (1) irradiation facilities, test matrices, and experimental methods; (2) dosimetry, damage parameters, transmutation, and activation calculations; (3) materials engineering and design requirements; (4) fundamental mechanical behavior; (5) radiation effects, mechanistic studies, theory and modelings; (6) development of structural alloys; (7) solid breeding materials and beryllium; and (8) ceramics. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database

FY2016 Propulsion Materials Annual Progress Report

Energy Technology Data Exchange (ETDEWEB)

None, None

2017-05-01

The Propulsion Materials Program actively supports the energy security and reduction of greenhouse emissions goals of VTO by investigating and identifying the materials properties that are most essential for continued development of cost-effective, highly efficient, and environmentally friendly next-generation heavy and light-duty powertrains. The technical approaches available to enhance propulsion systems focus on improvements in both vehicle efficiency and fuel substitution, both of which must overcome the performance limitations of the materials currently in use. Propulsion Materials Program activities work with national laboratories, industry experts, and VTO powertrain systems (e.g., Advanced Combustion Engines and Fuels) teams to develop strategies that overcome materials limitations in future powertrain performance. The technical maturity of the portfolio of funded projects ranges from basic science to subsystem prototype validation. Projects within a Propulsion Materials Program activity address materials concerns that directly impact critical technology barriers within each of the above programs, including barriers that impact fuel efficiency, thermal management, emissions reduction, improved reliability, and reduced manufacturing costs. The program engages only the barriers that result from material property limitations and represent fundamental, high-risk materials issues.

Evaporation by mechanical vapor recompression. Technical progress report, September 1-December 31, 1979

Energy Technology Data Exchange (ETDEWEB)

Iverson, C.H.; Coury, G.E.

1979-01-01

Progress to date in the development of a study of the application of the technologies of mechanical vapor recompression and falling film evaporators as applied to the beet sugar industry is reported. Progress is reported in the following areas: technical literature search and plant visitations of existing applications of VR/FFE.

FY13 Annual Progress Report for SECA Core Technology Program

Energy Technology Data Exchange (ETDEWEB)

Stevenson, Jeffry W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Koeppel, Brian J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-01-31

This progress report covers technical work performed during fiscal year 2013 at PNNL under Field Work Proposal (FWP) 40552. The report highlights and documents technical progress in tasks related to advanced cell and stack component materials development and computational design and simulation.

US/Japan collaborative program on fusion reactor materials: Summary of the tenth DOE/JAERI Annex I technical progress meeting on neutron irradiation effects in first wall and blanket structural materials

International Nuclear Information System (INIS)

Rowcliffe, A.F.

1989-01-01

This meeting was held at Oak Ridge National Laboratory on March 17, 1989, to review the technical progress on the collaborative DOE/JAERI program on fusion reactor materials. The purpose of the program is to determine the effects of neutron irradiation on the mechanical behavior and dimensional stability of US and Japanese austenitic stainless steels. Phase I of the program focused on the effects of high concentrations of helium on the tensile, fatigue, and swelling properties of both US and Japanese alloys. In Phase II of the program, spectral and isotropic tailoring techniques are fully utilized to reproduce the helium:dpa ratio typical of the fusion environment. The Phase II program hinges on a restart of the High Flux Isotope Reactor by mid-1989. Eight target position capsules and two RB* position capsules have been assembled. The target capsule experiments will address issues relating to the performance of austenitic steels at high damage levels including an assessment of the performance of a variety of weld materials. The RB* capsules will provide a unique and important set of data on the behavior of austenitic steels irradiated under conditions which reproduce the damage rate, dose, temperature, and helium generation rate expected in the first wall and blanket structure of the International Thermonuclear Experimental Reactor

Experimental Facilities Division/User Program Division technical progress report 1999-2000

International Nuclear Information System (INIS)

2001-01-01

In October 1999, the two divisions of the Advanced Photon Source (APS), the Accelerator Systems Division (ASD) and the Experimental Facilities Division (XFD), were reorganized into four divisions (see high-level APS organizational chart, Fig. 1.1). In addition to ASD and XFD, two new divisions were created, the APS Operations Division (AOD), to oversee APS operations, and the User Program Division (UPD), to serve the APS user community by developing and maintaining the highest quality user technical and administration support. Previous XFD Progress Reports (ANL/APS/TB-30 and ANL/APS/TB-34) covered a much broader base, including APS user administrative support and what was previously XFD operations (front ends, interlocks, etc.) This Progress Report summarizes the main scientific and technical activities of XFD, and the technical support, research and development (R and D) activities of UPD from October 1998 through November 2000. The report is divided into four major sections, (1) Introduction, (2) SRI-CAT Beamlines, Technical Developments, and Scientific Applications, (3) User Technical Support, and (4) Major Plans for the Future. Sections 2 and 3 describe the technical activities and research accomplishments of the XFD and UPD personnel in supporting the synchrotron radiation instrumentation (SRI) collaborative access team (CAT) and the general APS user community. Also included in this report is a comprehensive list of publications (Appendix 1) and presentations (Appendix 2) by XFD and UPD staff during the time period covered by this report. The organization of section 2, SRI CAT Beamlines, Technical Developments, and Scientific Applications has been made along scientific techniques/disciplines and not ''geographical'' boundaries of the sectors in which the work was performed. Therefore items under the subsection X-ray Imaging and Microfocusing could have been (and were) performed on several different beamlines by staff in different divisions. The management of

FY2009 Annual Progress Report for Propulsion Materials

Energy Technology Data Exchange (ETDEWEB)

none,

2010-01-16

The Propulsion Materials program focuses on enabling and innovative materials technologies that are critical in improving the efficiency of advanced engines. Projects within the Propulsion Materials Program address materials concerns that directly impact the critical technical barriers in each of these programs—barriers such as fuel efficiency, thermal management, emissions reduction, and reduced manufacturing costs.

Progress in molecular precursors for electronic materials

Energy Technology Data Exchange (ETDEWEB)

Buhro, W.E. [Washington Univ., St. Louis, MO (United States)

1996-09-01

Molecular-precursor chemistry provides an essential underpinning to all electronic-materials technologies, including photovoltaics and related areas of direct interest to the DOE. Materials synthesis and processing is a rapidly developing field in which advances in molecular precursors are playing a major role. This article surveys selected recent research examples that define the exciting current directions in molecular-precursor science. These directions include growth of increasingly complex structures and stoichiometries, surface-selective growth, kinetic growth of metastable materials, growth of size-controlled quantum dots and quantum-dot arrays, and growth at progressively lower temperatures. Continued progress in molecular-precursor chemistry will afford precise control over the crystal structures, nanostructures, and microstructures of electronic materials.

Material and component progress within ARCHER for advanced high temperature reactor

International Nuclear Information System (INIS)

Buckthorpe, D.E.; Davies, M.; Pra, F.; Bonnamy, P.; Fokkens, J.; Heijna, M.; Bout, N. de; Vreeling, A.; Bourlier, F.; Lhachemi, D.; Woayehune, A.; Dubiez-le-Goff, S.; Hahner, P.; Futterer, M.; Berka, J.; Kalivodora, J.; Pouchon, M.A.; Schmitt, R.; Homerin, P.; Marsden, B.; Mummery, P.; Mutch, G.; Ponca, D.; Buhl, P.; Hoffmann, M.; Rondet, F.; Pecherty, A.; Baurand, F.; Alenda, F.; Esch, M.; Kohlz, N.; Reed, J.; Fachinger, J.; Klower, Dr.

2014-01-01

The ARCHER (Advanced High-Temperature Reactors for Cogeneration of Heat and Electricity R and D) integrated project started in 2011 as part of the European Commission 7. Framework Programme (FP7) for a period of four years to perform High Temperature Reactor technology R and D in support of reactor demonstration. The project consortium encompasses conventional and Nuclear Industry, Utilities, Technical Support Organizations, Research and 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 materials and component technologies within ARCHER over the first two years of the project. (authors)

Development of small-bore, high-current-density railgun as testbed for study of plasma-materials interaction. Progress report for October 16, 2000 - May 13, 2003

International Nuclear Information System (INIS)

Kyekyoon, Kim-Kevin

2003-01-01

The present document is a final technical report summarizing the progress made during 10/16/2000 - 05/13/2003 toward the development of a small-bore railgun with transaugmentation as a testbed for investigating plasma-materials interaction

The effects of environmental regulation and technical progress on CO2 Kuznets curve: An evidence from China

International Nuclear Information System (INIS)

Yin, Jianhua; Zheng, Mingzheng; Chen, Jian

2015-01-01

Based on environmental Kuznets curve theory, a panel data model which takes environmental regulation and technical progress as its moderating factors was developed to analyse the institutional and technical factors that affect the path of low-carbon economic development. The results indicated that there was a CO 2 emission Kuznets curve seen in China. Environmental regulation had a significant moderating effect on the curve, and the inflection of CO 2 emissions could come substantially earlier under stricter environmental regulation. Meanwhile, the impact of technical progress on the low-carbon economic development path had a longer hysteresis effect but restrained CO 2 emission during its increasing stage and accelerated its downward trend during the decreasing stage which was conducive to emission reduction. Strict environmental regulation could force the high-carbon emitting industries to transfer from the eastern regions to the central or the western regions of China, which would make the CO 2 Kuznets curve higher in its increasing stage and lower in its decreasing stage than that under looser regulation. Furthermore, energy efficiency, energy structure, and industrial structure exerted a significant direct impact on CO 2 emissions; we should consider the above factors as essential in the quest for low-carbon economic development. - Highlights: • Estimate moderating effect of environmental regulation and technical progress on EKC. • There was a CO 2 emission Kuznets curve in effect in China. • Environmental regulation presents significant moderating effect on EKC. • Technical progress moderates the relationship between income and CO 2 emissions

Materials of 3. scientific-technical seminar: Materials Investigation for Power Industry

International Nuclear Information System (INIS)

1996-01-01

The report is an assembly of the papers concerning material problems during the exploitation of power stations as well as during construction and exploitation of gas pipelines. The accreditation problems according to the European Standards and Office of Technical Inspection prescription are also discussed

FY2011 Annual Progress Report for Propulsion Materials

Energy Technology Data Exchange (ETDEWEB)

Davis, Patrick B. [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States); Schutte, Carol L. [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States); Gibbs, Jerry L. [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States)

2011-12-01

Annual Progress Report for Propulsion Materials focusing on enabling and innovative materials technologies that are critical in improving the efficiency of advanced engines by providing enabling materials support for combustion, hybrid, and power electronics development.

ERIP invention 637. Technical progress report 2nd quarter, April 1997--June 1997

Energy Technology Data Exchange (ETDEWEB)

Thacker, G.W.

1997-07-22

This technical report describes progress in the development of the Pegasus plow, a stalk and root embedding apparatus. Prototype testing is reported, and includes the addition of precision tillage. Disease data, organic matter, and nitrogen levels results are very briefly described. Progress in marketing is also reported. Current marketing issues include test use by cotton and wheat growers, establishment of dealer relationships, incorporation of design modifications, expansion of marketing activities, and expansion of loan and lease program.

Energy materials coordinating committee (EMACC) Fiscal Year 1982. Annual technical report

Energy Technology Data Exchange (ETDEWEB)

None, None

1983-03-01

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/ workshops on selected topics involving both DOE and major contractors. In addition, the EMaCC aids in obtaining materials - related inputs for both intra- and interagency compilations. Membership in the EMaCC is open to any Department organizational unit; participants are appointed by Division or Office Directors. The current membership is listed in Table 1. The EMACC reports to the Director of the Office of Energy Research in his capacity as overseer of the technical programs of the Department. This annual technical report is mandated by the EMACC terms of reference. In this report are described 1) EMACC activities for FY 1982; 2) a summary of materials funding in the Department from FY 1978 to the present; and 3) on-going materials programs in the Department.

Materials testing and requirement for the ERDA nuclear-powered artificial heart. Technical progress report, July 15, 1975--May 30, 1976

International Nuclear Information System (INIS)

Andrade, J.D.; Hufferd, W.L.; Lyman, D.J.

1976-01-01

The two materials currently being used for the artificial heart fabrication are BIOMER and AVCOTHANE. BIOMER is a polyether urethane polymer. AVCOTHANE is a proprietary polyurethane/polydimethylsiloxane polymer blend. Research progress on the chemical degradation, mechanical strength, and blood compatibility is reported

Progress report 1979

International Nuclear Information System (INIS)

1980-12-01

This progress report deals with technical and research work done at the AAEC Research Establishment in the twelve month period ending September 30, 1979. Work done in the following research divisions is reported: Applied Maths and Computing, Chemical Technology, Engineering Research, Environmental Science, Instrumentation and Control, Isotope, Materials and Physics

Materials And Processes Technical Information System (MAPTIS) LDEF materials data base

Science.gov (United States)

Funk, Joan G.; Strickland, John W.; Davis, John M.

1993-01-01

A preliminary Long Duration Exposure Facility (LDEF) Materials Data Base was developed by the LDEF Materials Special Investigation Group (MSIG). The LDEF Materials Data Base is envisioned to eventually contain the wide variety and vast quantity of materials data generated from LDEF. The data is searchable by optical, thermal, and mechanical properties, exposure parameters (such as atomic oxygen flux) and author(s) or principal investigator(s). Tne LDEF Materials Data Base was incorporated into the Materials and Processes Technical Information System (MAPTIS). MAPTIS is a collection of materials data which has been computerized and is available to engineers, designers, and researchers in the aerospace community involved in the design and development of spacecraft and related hardware. The LDEF Materials Data Base is described and step-by-step example searches using the data base are included. Information on how to become an authorized user of the system is included.

Technical considerations in materials management policy development

International Nuclear Information System (INIS)

Avci, H.; Goldberg, M.

1996-01-01

Under the Materials-in-Inventory (MIN) initiative, US DOE intends to develop policies to ensure that materials are managed and use efficiently, cost-effectively, and safely throughout DOE. The MIN initiative covers depleted uranium, scrap metals, chemicals, explosives, spent nuclear fuel, lead, alkali metals, etc.; by far the largest component is depleted uranium hexafluoride (DUF6). A technically defensible approach has been developed and is being used to select a long-term management strategy for DOE's DUF6 inventory. The same approach can be adapted to management of other materials in inventory that have the potential to be reutilized

Fusion reactor materials

International Nuclear Information System (INIS)

Rowcliffe, A.F.; Burn, G.L.; Knee', S.S.; Dowker, C.L.

1994-02-01

This is the fifteenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; Special purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the U.S. Department of Energy. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide

FY2016 Lightweight Materials Annual Progress Report

Energy Technology Data Exchange (ETDEWEB)

None, None

2017-10-31

The Lightweight Materials research and development (R&D) area within the DOE Vehicle Technologies Office (VTO) provides support and guidance for many cutting-edge automotive technologies under development. Research focuses on addressing critical barriers to commercializing lightweight materials for passenger and commercial vehicles. This report describes the progress made on the research and development projects funded by the Lightweight Materials area.

FY2014 Propulsion Materials R&D Annual Progress Report

Energy Technology Data Exchange (ETDEWEB)

None

2015-05-01

The Propulsion Materials Program actively supports the energy security and reduction of greenhouse emissions goals of VTO by investigating and identifying the materials properties that are most essential for continued development of cost-effective, highly efficient, and environmentally friendly next-generation heavy and light-duty powertrains. The technical approaches available to enhance propulsion systems focus on improvements in both vehicle efficiency and fuel substitution, both of which must overcome the performance limitations of the materials currently in use. Propulsion Materials Program activities work with national laboratories, industry experts, and VTO powertrain systems (e.g., Advanced Combustion Engines [ACE], Advanced Power Electronics and Electrical Machines [APEEM], and fuels) teams to develop strategies that overcome materials limitations in future powertrain performance. The technical maturity of the portfolio of funded projects ranges from basic science to subsystem prototype validation. Projects within a Propulsion Materials Program activity address materials concerns that directly impact critical technology barriers within each of the above programs, including barriers that impact fuel efficiency, thermal management, emissions reduction, improved reliability, and reduced manufacturing costs. The program engages only the barriers that result from material property limitations and represent fundamental, high-risk materials issues.

Energy Materials Coordinating Committee (EMaCC): Fiscal year 1996. Annual technical report

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-08-01

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. The EMaCC reports to the Director of the Office of Energy Research in his or her capacity as overseer of the technical programs of the Department. This annual technical report is mandated by the EMaCC terms of reference. This report summarizes EMaCC activities for FY 1996 and describes the materials research programs of various offices and divisions within the Department.

Energy Materials Coordinating Committee (EMaCC): Fiscal year 1996. Annual technical report

International Nuclear Information System (INIS)

1997-08-01

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. The EMaCC reports to the Director of the Office of Energy Research in his or her capacity as overseer of the technical programs of the Department. This annual technical report is mandated by the EMaCC terms of reference. This report summarizes EMaCC activities for FY 1996 and describes the materials research programs of various offices and divisions within the Department

Cassini RTG Program. Monthly technical progress report, 27 November--31 December 1995

International Nuclear Information System (INIS)

1996-01-01

This monthly technical progress report provided information on the following tasks: spacecraft integration and liaison; engineering support; safety analysis; qualified unicouple fabrication; ETG fabrication, assembly, and test; ground support equipment (GSE); RTG shipping and launch support; designs, reviews, and mission applications; project management, quality assurance, and reliability, and contractor acquired government owned (CAGO) property acquisition

Impact of Environmental Regulation and Technical Progress on Industrial Carbon Productivity: An Approach Based on Proxy Measure

Directory of Open Access Journals (Sweden)

Huan Zhang

2016-08-01

Full Text Available This research aims to study the main influencing factors of China’s industrial carbon productivity by incorporating environmental regulation and technical progress into an econometric model. The paper focuses on data from 35 of China’s industrial sectors and covers the period from 2006 to 2014, in order to examine the impact of environmental regulation and technical progress on carbon productivity. Methods applied include panel fixed effect model, panel random effect model and two stage least squares with instrumental variables (IV-2SLS. The effect of environmental regulation and technical progress has industrial heterogeneity. The paper subdivides industrial sectors into capital and technology intensive, resource intensive and labor intensive sectors according to factor intensiveness. The estimation results of the subgroups have uncovered that for capital and technology intensive and resource intensive sectors, environmental regulation has a more significant impact than technical progress; while for labor intensive sectors, innovation more significantly influences carbon productivity. In addition, foreign direct investment (FDI and industrialization level facilitate improving carbon productivity for the full sample. By contrast, industrial structure inhibits the overall industrial carbon productivity. The industry-specific results indicate that for capital and technology intensive sectors, optimizing of the industrial structure can improve carbon productivity; for resource intensive sectors, FDI and energy consumption structure should be emphasized more; for labor intensive sectors, industrialization levels help enhance carbon productivity. Finally the industrial sector-specific policy suggestions are proposed.

Technical regulations for road transport of radioactive materials

International Nuclear Information System (INIS)

Juul-Jensen, P.; Ulbak, K.

1990-01-01

The technical regulations for the transport of radioactive materials in Denmark are set down by the (Danish) National Board of Health in collaboration with the (Danish) National Institute for Radiation Hygiene in accordance with paragraph 3 of the Danish Ministry of Justice's Executive Order no. 2 of 2, January 1985 on the national road transport of dangerous goods by road, as amended by exutive order no. 251 of April 29th 1987 and no. 704 of November 1989. These regulations are presented here. They are almost identical, with only very few exceptions indicated in the publication, with the rules for Class 7 of the European convention on international transport of dangerous goods by road (ADR). In addition to the aforementioned regulations for national road transport of radioactive materials the general rules for the transport of radioactive materials found in the National Board of Health's executive order no. 721 of November 27th 1989 on the transport of radioactive materials are valid. The abovementioned executive orders, with the exception of certain supplements which are not part of the technical regulations, are also contained in this publication. (AB)

ESTIMATION OF THE MODERN STATE OF PROVISION OF AGRICULTURAL ENTERPRISES IN MYKOLAIV REGION BY MATERIAL AND TECHNICAL RESOURCES

Directory of Open Access Journals (Sweden)

Natalya Potryvaieva

2017-09-01

, the search for prospective ways of its renewal is urgent. In particular, the authors proposed to intensify the formation of the secondary market of restored agricultural machinery based on the experience of foreign countries. Progressive improvement of material and technical resources is seen in the development of a network of local leasing funds and funds of preferential lending to agricultural commodity producers; expansion of cooperative forms of acquisition and exploitation of high-tech; the growth of dealer centres that provide rural commodity producers with equipment on leasing terms. In the conclusions, it is proved that the reduction of the number of the main types of equipment at agricultural enterprises in Mykolaiv region led to the fact that most of the technics are used longer the normative lifetime, on-load for each type of equipment is constantly increasing due to its scarcity. Improvement of the efficiency and growth of agricultural production and the level of its intensification needs updating of the material and technical base of agricultural enterprises, which requires significant investments. Taking into account the implementation of the region targeted programs, the role of public authorities is to develop measures aimed at a comprehensive solution to problems related not only to the implementation of technical, investment, and innovation policies but also to the coordinated co-operation between the industrial, commercial, and financial strategy.

Technical committee meeting on material-coolant interactions and material movement and relocation in liquid metal fast reactors

International Nuclear Information System (INIS)

1994-01-01

The Technical Committee Meeting on Material-Coolant Interactions and Material Movement and Relocation in Liquid Metal Fast Reactors was sponsored by the International Working Group on Fast Reactors (IWGFR), International Atomic Energy Agency (IAEA) and hosted by PNC, on behalf of the Japanese government. A broad range of technical subjects was discussed in the TCM, covering entire aspects of material motion and interactions relevant to the safety of LMFRs. Recent achievement and current status in research and development in this area were presented including European out-of-pile test of molten material movement and relocation; molten material-sodium interaction; molten fuel-coolant interaction; core disruptive accidents; sodium boiling; post accident material relocation, heat removal and relevant experiments already performed or planned

Technical committee meeting on material-coolant interactions and material movement and relocation in liquid metal fast reactors

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-07-01

The Technical Committee Meeting on Material-Coolant Interactions and Material Movement and Relocation in Liquid Metal Fast Reactors was sponsored by the International Working Group on Fast Reactors (IWGFR), International Atomic Energy Agency (IAEA) and hosted by PNC, on behalf of the Japanese government. A broad range of technical subjects was discussed in the TCM, covering entire aspects of material motion and interactions relevant to the safety of LMFRs. Recent achievement and current status in research and development in this area were presented including European out-of-pile test of molten material movement and relocation; molten material-sodium interaction; molten fuel-coolant interaction; core disruptive accidents; sodium boiling; post accident material relocation, heat removal and relevant experiments already performed or planned.

Sandia Laboratories technical capabilities: materials and processes

International Nuclear Information System (INIS)

Lundergan, C.D.; Mead, P.L.

1977-08-01

Materials and process activities have emphasized the balance between research and development necessary to provide materials compatible with the extreme environments and performance requirements associated with nuclear ordnance. Specific technical areas which have continuing emphasis include metallurgy, composites, surface characterization and thin films, polymers, ceramics, and high-temperature characterization. Complete processing and fabrication facilities assure the capability for early evaluation and use of tailored materials. Efforts are focused on material applications involving structural and electronic materials, thermal and electrical insulation, radiation shields, and shock mitigation. Key elements in these efforts are functionability, reliability, and longevity. This interdisciplinary approach to scientific materials engineering results from the recognition that many disciplines are required to understand, characterize, and apply materials, and from the fact that material design is an essential element in meeting the objectives of quality, functionality, and life. In effect, the responsibility of a materials group extends beyond the development of a material into the understanding and description of its behavior in the extreme environments to which it will be subjected

Energy Materials Coordinating Committee (EMaCC): Annual technical report, Fiscal year 1987

International Nuclear Information System (INIS)

1988-09-01

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. This annual technical report is mandated by the EMaCC terms of reference. This report summarizes EMaCC activities for FY 1987 and describes the materials research programs of various offices and divisions within the Department

Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 3

International Nuclear Information System (INIS)

Ulm, Franz-Josef

2000-01-01

OAK-B135 Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 3(NOTE: Part II A item 1 indicates ''PAPER'', but a report is attached electronically)

Computerized access to materials data. A progress report

International Nuclear Information System (INIS)

Rumble, J. Jr.

1985-01-01

As the effort to build a comprehensive computerized materials data system grows, it becomes more obvious that the benefits will be far-reaching. During this workshop, the enthusiasm of the participants grew steadily until the questions became not''What,'' but ''When?''. The engineering community within the United States has banded together many times to advance progress in engineering capability. The computerized materials data system requires such an effort, and the rewards will be substantial. Chapter 3 identifies changes in the use of materials data in the Nuclear Power Industry. Chapter 4 describes the EPRI experience in building computerized materials databases. In Chapter 5, the National Materials Property Data Network is discussed. The next four chapters present summaries of the workshop discussions and its conclusions. Chapter 6 discusses the content of the proposed system, Chapter 7 its size and the data sources, and Chapter 8 the user interfaces and system capabilities. In Chapter 9, ways of making further progress are outlined

Total Factor Productivity Growth, Technical Progress & Efficiency Change in Vietnam Coal Industry - Nonparametric Approach

Science.gov (United States)

Phuong, Vu Hung

2018-03-01

This research applies Data Envelopment Analysis (DEA) approach to analyze Total Factor Productivity (TFP) and efficiency changes in Vietnam coal mining industry from 2007 to 2013. The TFP of Vietnam coal mining companies decreased due to slow technological progress and unimproved efficiency. The decadence of technical efficiency in many enterprises proved that the coal mining industry has a large potential to increase productivity through technical efficiency improvement. Enhancing human resource training, technology and research & development investment could help the industry to improve efficiency and productivity in Vietnam coal mining industry.

Sludge Treatment Evaluation: 1992 Technical progress

International Nuclear Information System (INIS)

Silva, L.J.; Felmy, A.R.; Ding, E.R.

1993-01-01

This report documents Fiscal Year 1992 technical progress on the Sludge Treatment Evaluation Task, which is being conducted by Pacific Northwest Laboratory. The objective of this task is to develop a capability to predict the performance of pretreatment processes for mixed radioactive and hazardous waste stored at Hanford and other US Department of Energy (DOE) sites. Significant cost savings can be achieved if radionuclides and other undesirable constituents can be effectively separated from the bulk waste prior to final treatment and disposal. This work is initially focused on chemical equilibrium prediction of water washing and acid or base dissolution of Hanford single-shell tank (SST) sludges, but may also be applied to other steps in pretreatment processes or to other wastes. Although SST wastes contain many chemical species, there are relatively few constituents -- Na, Al, NO 3 , NO 2 , PO 4 , SO 4 , and F -- contained in the majority of the waste. These constituents comprise 86% and 74% of samples from B-110 and U-110 SSTS, respectively. The major radionuclides of interest (Cs, Sr, Tc, U) are present in the sludge in small molal quantities. For these constituents, and other important components that are present in small molal quantities, the specific ion-interaction terms used in the Pitzer or NRTL equations may be assumed to be zero for a first approximation. Model development can also be accelerated by considering only the acid or base conditions that apply for the key pretreatment steps. This significantly reduces the number of chemical species and chemical reactions that need to be considered. Therefore, significant progress can be made by developing all the specific ion interactions for a base model and an acid dissolution model

Sludge Treatment Evaluation: 1992 Technical progress

Energy Technology Data Exchange (ETDEWEB)

Silva, L J; Felmy, A R; Ding, E R

1993-01-01

This report documents Fiscal Year 1992 technical progress on the Sludge Treatment Evaluation Task, which is being conducted by Pacific Northwest Laboratory. The objective of this task is to develop a capability to predict the performance of pretreatment processes for mixed radioactive and hazardous waste stored at Hanford and other US Department of Energy (DOE) sites. Significant cost savings can be achieved if radionuclides and other undesirable constituents can be effectively separated from the bulk waste prior to final treatment and disposal. This work is initially focused on chemical equilibrium prediction of water washing and acid or base dissolution of Hanford single-shell tank (SST) sludges, but may also be applied to other steps in pretreatment processes or to other wastes. Although SST wastes contain many chemical species, there are relatively few constituents -- Na, Al, NO[sub 3], NO[sub 2], PO[sub 4], SO[sub 4], and F -- contained in the majority of the waste. These constituents comprise 86% and 74% of samples from B-110 and U-110 SSTS, respectively. The major radionuclides of interest (Cs, Sr, Tc, U) are present in the sludge in small molal quantities. For these constituents, and other important components that are present in small molal quantities, the specific ion-interaction terms used in the Pitzer or NRTL equations may be assumed to be zero for a first approximation. Model development can also be accelerated by considering only the acid or base conditions that apply for the key pretreatment steps. This significantly reduces the number of chemical species and chemical reactions that need to be considered. Therefore, significant progress can be made by developing all the specific ion interactions for a base model and an acid dissolution model.

Decontamination Systems Information and Research Program. Quarterly technical progress report, January 1--March 31, 1994

Energy Technology Data Exchange (ETDEWEB)

1994-05-01

West Virginia University (WVU) and the US DOE Morgantown Energy Technology Center (METC) entered into a Cooperative Agreement on August 29, 1992 entitled ``Decontamination Systems Information and Research Programs.`` Stipulated within the Agreement is the requirement that WVU submit to METC a series of Technical Progress Reports on a quarterly basis. This report comprises the first Quarterly Technical Progress Report for Year 2 of the Agreement. This report reflects the progress and/or efforts performed on the sixteen (16) technical projects encompassed by the Year 2 Agreement for the period of January 1 through March 31, 1994. In situ bioremediation of chlorinated organic solvents; Microbial enrichment for enhancing in-situ biodegradation of hazardous organic wastes; Treatment of volatile organic compounds (VOCs) using biofilters; Drain-enhanced soil flushing (DESF) for organic contaminants removal; Chemical destruction of chlorinated organic compounds; Remediation of hazardous sites with steam reforming; Soil decontamination with a packed flotation column; Use of granular activated carbon columns for the simultaneous removal of organics, heavy metals, and radionuclides; Monolayer and multilayer self-assembled polyion films for gas-phase chemical sensors; Compact mercuric iodide detector technology development; Evaluation of IR and mass spectrometric techniques for on-site monitoring of volatile organic compounds; A systematic database of the state of hazardous waste clean-up technologies; Dust control methods for insitu nuclear and hazardous waste handling; Winfield Lock and Dam remediation; and Socio-economic assessment of alternative environmental restoration technologies.

Environmental Research Division technical progress report, January 1984-December 1985

International Nuclear Information System (INIS)

1986-05-01

Technical progress in the various research and assessment activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1984 to 1985. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Environmental Impacts, Fundamental Molecular Physics and Chemistry, and Waste Management Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter

Environmental Research Division technical progress report, January 1984-December 1985

Energy Technology Data Exchange (ETDEWEB)

1986-05-01

Technical progress in the various research and assessment activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1984 to 1985. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Environmental Impacts, Fundamental Molecular Physics and Chemistry, and Waste Management Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter.

Institutional effectiveness of REDD+ MRV: Countries progress in implementing technical guidelines and good governance requirements

NARCIS (Netherlands)

Ochieng, R.M.; Visseren-Hamakers, Ingrid; Arts, B.; Brockhaus, M.; Herold, M.

2016-01-01

The UNFCCC requires REDD+ countries wishing to receive results-based payments to measure, report and verify (MRV) REDD+ impacts; and outlines technical guidelines and good governance requirements for MRV. This article examines institutional effectiveness of REDD+ MRV by assessing countries’ progress

Index to Nuclear Safety: a technical progress review by chrology, permuted title, and author, Volume 11(1) through Volume 20(6)

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W B; Passiakos, M

1980-06-01

This index to Nuclear Safety, a bimonthly technical progress review, covers articles published in Nuclear Safety, Volume II, No. 1 (January-February 1970), through Volume 20, No. 6 (November-December 1979). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 600 technical articles published in Nuclear Safety in the last ten years are listed in this index.

Nonequilibrium photochemical reactions induced by lasers. Technical progress report

International Nuclear Information System (INIS)

Steinfeld, J.I.

1978-04-01

Research has progressed in six principal subject areas of interest to DOE advanced (laser) isotope separation efforts. These are (1) Infrared double resonance spectroscopy of molecules excited by multiple infrared photon absorption, particularly SF 6 and vinyl chloride. (2) Infrared multiphoton excitation of metastable triplet-state molecules, e.g., biacetyl. (3) An Information Theory analysis of multiphoton excitation and collisional deactivation has been carried out. (4) The mechanism of infrared energy deposition and multiphoton-induced reactions in chlorinated ethylene derivatives; and RRKM (statistical) model accounts for all observed behavior of the system, and a deuterium-specific reaction pathway has been identified. (5) Diffusion-enhanced laser isotope separation in N 16 O/N 18 O. (6) A technical evaluation of laser-induced chemistry and isotope separation

Projects at the component development and integration facility. Quarterly technical progress report, April 1, 1994--June 30, 1994

International Nuclear Information System (INIS)

1994-01-01

This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the third quarter of FY94. The CDIF is a major Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: Biomass Remediation Project; Heavy Metal-Contaminated Soil Project; MHD Shutdown; Mine Waste Technology Pilot Program; Plasma Projects; Resource Recovery Project; and Spray Casting Project

Recent progress in sodium technology

Energy Technology Data Exchange (ETDEWEB)

Hallett, W. J.

1963-10-15

Progress over the past year in U. S. laboratories studying some of the materials and engineering problems that must be resolved in bringing the technology of sodium to an economically and technically attractive point is reviewed. The status of sodium cooled power reactors in the U. S. is described. (P.C.H.)

Reducing nuclear danger through intergovernmental technical exchanges on nuclear materials safety management

International Nuclear Information System (INIS)

Jardine, L.J.; Peddicord, K.L.; Witmer, F.E.; Krumpe, P.F.; Lazarev, L.; Moshkov, M.

1997-01-01

The United States and Russia are dismantling nuclear weapons and generating hundreds of tons of excess plutonium and high enriched uranium fissile nuclear materials that require disposition. The U.S. Department of Energy and Russian Minatom organizations.are planning and implementing safe, secure storage and disposition operations for these materials in numerous facilities. This provides a new opportunity for technical exchanges between Russian and Western scientists that can establish an improved and sustained common safety culture for handling these materials. An initiative that develops and uses personal relationships and joint projects among Russian and Western participants involved in fissile nuclear materials safety management contributes to improving nuclear materials nonproliferation and to making a safer world. Technical exchanges and workshops are being used to systematically identify opportunities in the nuclear fissile materials facilities to improve and ensure the safety of workers, the public, and the environment

The Natural Hospital Environment: a Socio-Technical-Material perspective.

Science.gov (United States)

Fernando, Juanita; Dawson, Linda

2014-02-01

This paper introduces two concepts into analyses of information security and hospital-based information systems-- a Socio-Technical-Material theoretical framework and the Natural Hospital Environment. The research is grounded in a review of pertinent literature with previously published Australian (Victoria) case study data to analyse the way clinicians work with privacy and security in their work. The analysis was sorted into thematic categories, providing the basis for the Natural Hospital Environment and Socio-Technical-Material framework theories discussed here. Natural Hospital Environments feature inadequate yet pervasive computer use, aural privacy shortcomings, shared workspace, meagre budgets, complex regulation that hinders training outcomes and out-dated infrastructure and are highly interruptive. Working collaboratively in many cases, participants found ways to avoid or misuse security tools, such as passwords or screensavers for patient care. Workgroup infrastructure was old, architecturally limited, haphazard in some instances, and was less useful than paper handover sheets to ensure the quality of patient care outcomes. Despite valiant efforts by some participants, they were unable to control factors influencing the privacy of patient health information in public hospital settings. Future improvements to hospital-based organisational frameworks for e-health can only be made when there is an improved understanding of the Socio-Technical-Material theoretical framework and Natural Hospital Environment contexts. Aspects within control of clinicians and administrators can be addressed directly although some others are beyond their control. An understanding and acknowledgement of these issues will benefit the management and planning of improved and secure hospital settings. Copyright © 2013 Elsevier Ireland Ltd. All rights reserved.

Energy Materials Coordinating Committee, fiscal year 1997. Annual technical report

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-31

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. This report summarizes EMaCC activities for FY 1997 and describes the materials research programs of various offices and divisions within the Department.

Technical meeting on materials for in-vessel components of ITER

International Nuclear Information System (INIS)

Kalinin, G.; Barabash, V.

2000-01-01

The Technical meeting on materials for in-vessel components of ITER was held at the ITER Joint Work Site in Garching from 31 January to 4 February. The main objectives of the meetings were: 1. to summarize the requirements, 2. to review new data, 3. to discuss in detail the R and D program and to discuss the material assessment report

Modeling the impacts of climate change and technical progress on the wheat yield in inland China: An autoregressive distributed lag approach.

Science.gov (United States)

Zhai, Shiyan; Song, Genxin; Qin, Yaochen; Ye, Xinyue; Lee, Jay

2017-01-01

This study aims to evaluate the impacts of climate change and technical progress on the wheat yield per unit area from 1970 to 2014 in Henan, the largest agricultural province in China, using an autoregressive distributed lag approach. The bounded F-test for cointegration among the model variables yielded evidence of a long-run relationship among climate change, technical progress, and the wheat yield per unit area. In the long run, agricultural machinery and fertilizer use both had significantly positive impacts on the per unit area wheat yield. A 1% increase in the aggregate quantity of fertilizer use increased the wheat yield by 0.19%. Additionally, a 1% increase in machine use increased the wheat yield by 0.21%. In contrast, precipitation during the wheat growth period (from emergence to maturity, consisting of the period from last October to June) led to a decrease in the wheat yield per unit area. In the short run, the coefficient of the aggregate quantity of fertilizer used was negative. Land size had a significantly positive impact on the per unit area wheat yield in the short run. There was no significant short-run or long-run impact of temperature on the wheat yield per unit area in Henan Province. The results of our analysis suggest that climate change had a weak impact on the wheat yield, while technical progress played an important role in increasing the wheat yield per unit area. The results of this study have implications for national and local agriculture policies under climate change. To design well-targeted agriculture adaptation policies for the future and to reduce the adverse effects of climate change on the wheat yield, climate change and technical progress factors should be considered simultaneously. In addition, adaptive measures associated with technical progress should be given more attention.

Modeling the impacts of climate change and technical progress on the wheat yield in inland China: An autoregressive distributed lag approach.

Directory of Open Access Journals (Sweden)

Shiyan Zhai

Full Text Available This study aims to evaluate the impacts of climate change and technical progress on the wheat yield per unit area from 1970 to 2014 in Henan, the largest agricultural province in China, using an autoregressive distributed lag approach. The bounded F-test for cointegration among the model variables yielded evidence of a long-run relationship among climate change, technical progress, and the wheat yield per unit area. In the long run, agricultural machinery and fertilizer use both had significantly positive impacts on the per unit area wheat yield. A 1% increase in the aggregate quantity of fertilizer use increased the wheat yield by 0.19%. Additionally, a 1% increase in machine use increased the wheat yield by 0.21%. In contrast, precipitation during the wheat growth period (from emergence to maturity, consisting of the period from last October to June led to a decrease in the wheat yield per unit area. In the short run, the coefficient of the aggregate quantity of fertilizer used was negative. Land size had a significantly positive impact on the per unit area wheat yield in the short run. There was no significant short-run or long-run impact of temperature on the wheat yield per unit area in Henan Province. The results of our analysis suggest that climate change had a weak impact on the wheat yield, while technical progress played an important role in increasing the wheat yield per unit area. The results of this study have implications for national and local agriculture policies under climate change. To design well-targeted agriculture adaptation policies for the future and to reduce the adverse effects of climate change on the wheat yield, climate change and technical progress factors should be considered simultaneously. In addition, adaptive measures associated with technical progress should be given more attention.

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)

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 2. Engineering technology for geological disposal

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the deep geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, part 2 of the progress report, concerns engineering aspect with reference to Japanese geological disposal plan, according to which the vitrified HLW will be disposed of into a deep, stable rock mass with thick containers and surrounding buffer materials at the depth of several hundred meters. It discusses on multi-barrier systems consisting of a series of engineered and natural barriers that will isolate radioactive nuclides effectively and retard their migrations to the biosphere environment. Performance of repository components, including specifications of containers for vitrified HLW and their overpacks under design as well as buffer material such as Japanese bentonite to be placed in between are described referring also to such possible problems as corrosion arising from the supposed system. It also presents plans and designs for underground disposal facilities, and the presumed management of the underground facilities. (Ohno, S.)

The Impacts of Technical Progress on Sulfur Dioxide Kuznets Curve in China: A Spatial Panel Data Approach

Directory of Open Access Journals (Sweden)

Zhimin Zhou

2017-04-01

Full Text Available This paper aims to reveal the nexus for sulfur dioxide (SO2 emission and income, as well as the effects of technical progress on SO2 emission in China based on environment Kuznets curve (EKC hypothesis. The spatial panel technique is used in case the coefficient estimates are biased due to the negligence of spatial dependence. With the provincial panel data of China from 2004 to 2014, this is the first research that finds an inverse N-trajectory of the relationship between SO2 emission and economic growth and confirms the beneficial impacts of technical advancement on SO2 emission abatement. The empirical results also suggest that the industrial structure change is an important driving force of the SO2 EKC. In addition, the direct and spillover effects of determinants on sulfur emission are clarified and estimated by a correct approach. Finally, we check the stability of our conclusions on the EKC shape for SO2 and technical progress effects when controlling for different variables and specifications, through which we find the turning points are sensitive to variables selections.

Technical progress and climatic change

International Nuclear Information System (INIS)

Ausubel, J.H.

1995-01-01

The global warming debate has neglected and thus underestimated the importance of technical change in considering reduction in greenhouse gases and adaptation to climate change. Relevant quantitative cases of long-run technical change during the past 100 years are presented in computing, communications, transport, energy, and agriculture. A noteworthy technological trajectory is that of decarbonization, or decreasing carbon intensity of primary energy. If human societies have not yet reached the end of the history of technology, the cost structure for mitigation and adaptation changes could be cheap. (Author)

78 FR 65265 - Materials Technical Advisory Committee; Notice of Open Meeting

Science.gov (United States)

2013-10-31

.... Report on regime-based activities. 7. SHUTDOWN Feedback. 8. Public Comments and New Business. The open...; Notice of Open Meeting The Materials Technical Advisory Committee will meet on November 14, 2013, 10:00 a... materials and related technology. Agenda Open Session 1. Opening Remarks and Introductions. 2. Remarks from...

Materials testing and requirement for the ERDA nuclear-powered artificial heart. Technical progress report, July 15, 1975--May 30, 1976. [BIOMER and AVCOTHANE

Energy Technology Data Exchange (ETDEWEB)

Andrade, J. D.; Hufferd, W. L.; Lyman, D. J.

1976-01-01

The two materials currently being used for the artificial heart fabrication are BIOMER and AVCOTHANE. BIOMER is a polyether urethane polymer. AVCOTHANE is a proprietary polyurethane/polydimethylsiloxane polymer blend. Research progress on the chemical degradation, mechanical strength, and blood compatibility is reported. (TFD)

FY2015 Lightweight Materials R&D Annual Progress Report

Energy Technology Data Exchange (ETDEWEB)

None, None

2016-09-30

The Lightweight Materials research and development (R&D) area within the DOE Vehicle Technologies Office (VTO) provides support and guidance for many cutting-edge automotive technologies under development. Research focuses on addressing critical barriers to commercializing lightweight materials for passenger and commercial vehicles. This report describes the progress made on the research and development projects funded by the Lightweight Materials area.

Western Research Institute: Annual technical progress report, October 1987--September 1988

Energy Technology Data Exchange (ETDEWEB)

1988-12-01

This report describes the technical progress made by the Western Research Institute of the University of Wyoming Research Institute of the University of Wyoming Research Corporation on work performed for the period October 1, 1987 through September 30, 1988. This research involves five resource areas: oil shale, tar sand, underground coal gasification, advanced process technology, and advanced fuels research. Under the terms of the cooperative agreement, an annual project plan has been approved by DOE. The work reported herein reflects the implementation of the research in the plan and follows the structure used therein. 49 refs., 32 figs., 87 tabs.

Technical meeting on progress in managing, and limiting the consequences of events exceeding the design basis

International Nuclear Information System (INIS)

Fabian, H.

2004-01-01

The Technical Groups on 'Reactor Safety' and 'Thermodynamics and Fluid Dynamics' of the Kerntechnische Gesellschaft e.V. organized a joint technical meeting on 'Progress in Managing, and Limiting the Consequences of, Events Exceeding the Design Basis' at the FTU Training Center of the Karlsruhe Research Center. The topic chosen, the papers presented, the presenters, and the non-technical part of the program met with lively interest on the part of institutions in the nuclear field. These were the objectives of the technical meeting: - Establishing a forum for communicating relevant topics. - In-depth discussion of the main topic, i.e. the advanced development of reactor safety, research in the field, and its application, in twenty selected papers presented by speakers from different institutions. - Presentation of topical work in a nuclear technology institution, the Karlsruhe Research Center. (orig.) [de

Studies in theoretical high energy particle physics: Technical progress report [February 1987-February 1988

International Nuclear Information System (INIS)

Sukhatme, U.P.; Keung, Wai-Yee; Kovacs, E.

1988-02-01

This is a technical progress report for grant No. FG02-84ER40173 for the period February 1987 to February 1988. Our research on supersymmetric quantum mechanics has yielded many interesting results. In particular, a systematic approach to the tunneling problem in double well potentials has been developed. Higgs boson related physics at the high energy hadron colliders has been extensively studied

Near-real-time material accountancy - A technical status report

International Nuclear Information System (INIS)

Lovett, J.; Ikawa, K.; Sellinschegg, D.; Shipley, J.

1983-01-01

Near-Real-time materials accountancy as applied to reprocessing plants involves two major elements, measurement of the in-process physical inventory at frequent intervals, and statistical evaluation of the resulting sequential material balance data. For most reprocessing plants the bulk of the in-process inventory is in measurable intermediate ''buffer'' tanks. The plutonium inventory in the solvent extraction system, which does not appear to be directly measureable, could cause a reduction in sensitivity of the sequential data analysis. Studies are in progress, and it is hoped that an acceptable means for accounting for these variations can be found. Consultants at a meeting in January 1982 agreed that statistical tests for evaluating sequential material balance data will increase both detection timeliness and detection sensitivity. IAEA verification of operator-generated measurement data is an area requiring significantly increased effort, but here too studies are in progress which should help to reduce inspection effort in increased effectiveness

The role of technical progress in the process of recalculating oil reserves; Le role du progres technique dans le processus de renouvellement des reserves petrolieres

Energy Technology Data Exchange (ETDEWEB)

Boulard, J.N. [Total/Fina/Institut Francais du Petrole (IFP), 92 - Rueil-Malmaison (France)

1999-08-01

Contrary to the concept of resources (which is essentially a geological one), the notion of reserves designates the quantities that are technically and economically recoverable. Beyond the production-related effect, the reserves therefore evolve over time in accordance with numerous technical and economic parameters. Among these parameters, it can be seen that technical progress plays a considerable role throughout the process of converting resources into reserves, including progress in the identification, accessibility and processing of the resources, and improvements in economic viability. After having tackled the problem of measuring the 'technical progress effects' and citing examples, we demonstrate that the evolution in oil reserves is subject to three types of impact. These are a quantitative impact by significantly improving the recovery rates or making it possible to identify hitherto undetectable oil fields, a qualitative impact by widening the resource base thanks to the adoption of new categories of oil (in particular the so-called 'unconventional' oils) and by carrying out the gradual substitution between these resources of differing qualities. There is also a dynamic impact, through the acceleration of resource availability. Through these three approaches, technical progress makes makes it possible to ensure continuity in oil supply and contributes significantly to the recalculation of reserves. It therefore acts as a compensating factor, counterbalancing the progressive depletion of resources. (author)

Advancing materials research

International Nuclear Information System (INIS)

Langford, H.D.; Psaras, P.A.

1987-01-01

The topics discussed in this volume include historical perspectives in the fields of materials research and development, the status of selected scientific and technical areas, and current topics in materials research. Papers are presentd on progress and prospects in metallurgical research, microstructure and mechanical properties of metals, condensed-matter physics and materials research, quasi-periodic crystals, and new and artifically structured electronic and magnetic materials. Consideration is also given to materials research in catalysis, advanced ceramics, organic polymers, new ways of looking at surfaces, and materials synthesis and processing

A Simple extension of Dematerialization Theory: Incorporation of Technical Progress and the Rebound Effect

OpenAIRE

Magee, Christopher L.; Devezas, Tessaleno C.

2016-01-01

Dematerialization is the reduction in the quantity of materials needed to produce something useful over time. Dematerialization fundamentally derives from ongoing increases in technical performance but it can be counteracted by demand rebound - increases in usage because of increased value (or decreased cost) that also results from increasing technical performance. A major question then is to what extent technological performance improvement can offset and is offsetting continuously increasin...

Recent Progress in Advanced Materials for Lithium Ion Batteries

Directory of Open Access Journals (Sweden)

Jiajun Chen

2013-01-01

Full Text Available The development and commercialization of lithium ion batteries is rooted in material discovery. Promising new materials with high energy density are required for achieving the goal toward alternative forms of transportation. Over the past decade, significant progress and effort has been made in developing the new generation of Li-ion battery materials. In the review, I will focus on the recent advance of tin- and silicon-based anode materials. Additionally, new polyoxyanion cathodes, such as phosphates and silicates as cathode materials, will also be discussed.

Surgical resident technical skill self-evaluation: increased precision with training progression.

Science.gov (United States)

Quick, Jacob A; Kudav, Vishal; Doty, Jennifer; Crane, Megan; Bukoski, Alex D; Bennett, Bethany J; Barnes, Stephen L

2017-10-01

Surgical resident ability to accurately evaluate one's own skill level is an important part of educational growth. We aimed to determine if differences exist between self and observer technical skill evaluation of surgical residents performing a single procedure. We prospectively enrolled 14 categorical general surgery residents (six post-graduate year [PGY] 1-2, three PGY 3, and five PGY 4-5). Over a 6-month period, following each laparoscopic cholecystectomy, residents and seven faculty each completed the Objective Structured Assessment of Technical Skills (OSATS). Spearman's coefficient was calculated for three groups: senior (PGY 4-5), PGY3, and junior (PGY 1-2). Rho (ρ) values greater than 0.8 were considered well correlated. Of the 125 paired assessments (resident-faculty each evaluating the same case), 58 were completed for senior residents, 54 for PGY3 residents, and 13 for junior residents. Using the mean from all OSATS categories, trainee self-evaluations correlated well to faculty (senior ρ 0.97, PGY3 ρ 0.9, junior ρ 0.9). When specific OSATS categories were analyzed, junior residents exhibited poor correlation in categories of respect for tissue (ρ -0.5), instrument handling (ρ 0.71), operative flow (ρ 0.41), use of assistants (ρ 0.05), procedural knowledge (ρ 0.32), and overall comfort with the procedure (ρ 0.73). PGY3 residents lacked correlation in two OSATS categories, operative flow (ρ 0.7) and procedural knowledge (ρ 0.2). Senior resident self-evaluations exhibited strong correlations to observers in all areas. Surgical residents improve technical skill self-awareness with progressive training. Less-experienced trainees have a tendency to over-or-underestimate technical skill. Copyright © 2017 Elsevier Inc. All rights reserved.

Productivity Change, Technical Progress, and Relative Efficiency Change in the Public Accounting Industry

OpenAIRE

Rajiv D. Banker; Hsihui Chang; Ram Natarajan

2005-01-01

We present evidence on components of productivity change in the public accounting industry toward the end of the 20th century. Using revenue and human resource data from 64 of the 100 largest public accounting firms in the United States for the 1995--1999 period, we analyze productivity change, technical progress, and relative efficiency change over time. The average public accounting firm experienced a productivity growth of 9.5% between 1995 and 1999. We find support for the hypothesis that...

GPHS-RTGs in support of the Cassini RTG Program. Semi annual technical progress report, September 26, 1994--April 2, 1995

International Nuclear Information System (INIS)

1995-01-01

The technical progress achieved during the period 26 September 1994 through 2 April 1995 on Contract DE-AC03-91SF18852 Radioisotope Thermoelectric Generators and Ancillary Activities is described herein. Monthly technical activity for the period 27 February 1995 through 2 April 1995 is included in this progress report. The report addresses tasks, including: spacecraft integration and liaison; engineering support; safety; qualified unicouple production; ETG Fabrication, assembly, and test; ground support equipment; RTG shipping and launch support; designs, reviews, and mission applications; project management, quality assurance, reliability, contract changes, CAGO acquisition (operating funds), and CAGO maintenance and repair; and CAGO acquisition (capital funds)

Development of TRITN : In-house technical information network of Technical Research Institute in The Chugoku Electric Power Co., Inc.

Science.gov (United States)

Ebara, Hisao

With the increase in information amount, progress in information network, diversified technology and change in in-house organization the Technical Research Institute has necessitated to shift the conventional technical database processing by use of personal computers into new system promised for future use. It enables to; provide classification system which meets the needs of the institute; execute distributed processing using workstations; make the low cost processing using commercial softwares; make networks using LAN, WAN personal computer communication, and provide primary materials (text data) on facsimiles using optical disks. Such features are those of technical information database system "TRITN" which is available to any persons and at any time. This paper describes how TRITN was developed and the system outline.

Works Technical Department progress report, March 1961

Energy Technology Data Exchange (ETDEWEB)

None

1961-04-19

This document details the activities of the Savannah River Works Technical Department during the month of March 1961. Topics discussed are: Reactor Technology, Separations Technology, Engineering Assistance, Health Physics, Laboratories Overview, and Technical Papers Issued.

Energy Materials Coordinating Committee (EMaCC). Annual technical report, Fiscal Year 2001

Energy Technology Data Exchange (ETDEWEB)

None, None

2002-08-01

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations.

Supplemental Journal Article Materials: A progress report on an information industry initiative

Science.gov (United States)

Schwarzman, A. B.

2011-12-01

also intend to address roles and responsibilities of authors, editors, peer reviewers, publishers, libraries, abstracting and indexing services, and official data centers and institutional repositories. Finally, the document is going to contain broad principles and detailed technical implementation related to metadata, linking, packaging, and accessibility of supplemental materials. In this presentation, a co-chair of the NISO/NFAIS Working Group will report on the Group's latest progress in developing the Recommended Practices for Supplemental Journal Article Materials.

FY 2012 Lightweight Materials Annual Report

Energy Technology Data Exchange (ETDEWEB)

None

2013-04-15

The FY 2012 Annual Progress Report for Lightweight Materials provides a detailed description of the activities and technical accomplishments which focuses on the development and validation of advanced materials and manufacturing technologies to significantly reduce light and heavy duty vehicle weight without compromising other attributes such as safety, performance, recyclability, and cost.

The 1988 progress report of the Nuclear Safety and Protection Institut

International Nuclear Information System (INIS)

Anon.

1988-01-01

The 1988 progress report of the Nuclear Safety and Protection Institut (CEA, France). The Institute's fields of action involve: The activities and technical safety of the nuclear power plants, the environmental and human radiation protection which includes technical, health and medical aspects, the nuclear materials compatibility and control and the accident intervention actions. The 1988 Institute activities are characterized by the continuity of the previous technical safety directives, by the improvement of the nuclear risk communication and of the international cooperation [fr

Inertial fusion research: Annual technical report, 1985

International Nuclear Information System (INIS)

Larsen, J.T.; Terry, N.C.

1986-03-01

This report describes the inertial confinement fusion (ICF) research activities undertaken at KMS Fusion (KMSF) during 1985. It is organized into three main technical sections; the first covers fusion experiments and theoretical physics, the second is devoted to progress in materials development and target fabrication, and the third describes laser technology research. These three individual sections have been cataloged separately

Quarterly technical progress report, February 1, 1996--April 30, 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-05-28

This report from the Amarillo National REsource Center for PLutonium provides research highlights and provides information regarding the public dissemination of information. The center is a a scientific resource for information regarding the issues of the storage, disposition, potential utilization and transport of plutonium, high explosives, and other hazardous materials generated from nuclear weapons dismantlement. The center responds to informational needs and interpretation of technical and scientific data raised by interested parties and advisory groups. Also, research efforts are carried out on remedial action programs and biological/agricultural studies.

Helium generation in fusion reactor materials. Technical progress report, April--September 1977

International Nuclear Information System (INIS)

1978-01-01

The near-term objectives of this program are to measure the spectrum-integrated helium generation rates and cross sections of a number of pure elements and alloys in several high-intensity neutron sources, and to develop and demonstrate neutron dosimetry procedures using some of these materials. To this end, four neutron irradiation experiments have now been run: one using accelerator-produced d-Be neutrons, two using the accelerator-produced d-T reaction, and one in the neutron field of a mixed-spectrum fission reactor. All of these irradiations have incorporated a large number of helium-generation materials

Technical limitations of nuclear fuel materials and structures

International Nuclear Information System (INIS)

Hansson, L.; Planman, T.; Vitikainen, E.

1993-05-01

This report gives a summary of the tasks carried out within the project 'Technical limitations of nuclear fuel materials and structures' which belongs to the Finnish national research programme called 'Systems behaviour and operational aspects of safety'. The duration of the project was three years from 1990 to 1992. Most western LWR utilities, including the two Finnish ones have an incentive to implement extended burnup fuel cycles in their nuclear power plants. The aim of this project has been authorities to support them in the assessment and licensing of new fuel designs and materials. The research work of the project was focused on collecting and qualifying fuel performance data and on performing laboratory tests on fresh and irradiated cladding and structural materials. Moreover, knowledge of the high burnup phenomena was obtained through participation in international research projects such as OECD Halden Project and several Studsvik projects. Experimental work within the framework of the VVER fuel cooperative effort was also continued. (orig.)

Nuclear structure theory. Annual technical progress report, October 1, 1976--September 30, 1977

International Nuclear Information System (INIS)

French, J.B.; Koltun, D.S.

1977-01-01

This report summarizes progress during the past year in the following areas of nuclear structure and reaction theory: (1) statistical spectroscopy, including giant resonances for beta and electromagnetic excitation and sum rules (including inverse-energy-weighted sum rules), statistical methods of truncating shell model spaces and renormalization of operators, study of state labelling and ''chains'' of groups, evaluation of fluctuation measures, technical aspects of operator averaging; (2) meson interactions with nuclei, including scattering and absorption of mesons by nuclei (general methods), models for absorption, single- and double-charge exchange of pions, role of rho mesons

FY 1992 work plan and technical progress reports

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-11-01

The Desert Research Institute (DRI) is a division of the University of Nevada System devoted to multidisciplinary scientific research. For more than 25 years, DRI has conducted research for the US Department of Energy`s Nevada Field Office (DOE/NV) in support of operations at the Nevada Test Site (NTS). During that time, the research program has grown from an early focus on hydrologic studies to include the areas of geology, archaeology, environmental compliance and monitoring, statistics, database management, public education, and community relations. The range of DRI`s activities has also expanded to include a considerable amount of management and administrative support in addition to scientific investigations. DRI`s work plan for FY 1992 reflects a changing emphasis in DOE/NV activities from nuclear weapons testing to environmental restoration and monitoring. Most of the environmental projects from FY 1991 are continuing, and several new projects have been added to the Environmental Compliance Program. The Office of Technology Development Program, created during FY 1991, also includes a number of environmental projects. This document contains the FY 1992 work plan and quarterly technical progress reports for each DRI project.

Waste management issues and their potential impact on technical specifications of CANDU fuel materials

International Nuclear Information System (INIS)

Tait, J.C.; Johnson, L.H.

1997-01-01

The technical specifications for the composition of nuclear fuels and materials used in Canada's CANDU reactors have been developed by AECL and materials manufacturers, taking into account considerations specific to their manufacture and the effect of minor impurities on fuel behaviour in reactor. Nitrogen and chlorine are examples of UO 2 impurities, however, where there is no technical specification limit. These impurities are present in the source materials or introduced in the fabrication process and are neutron activated to 14 C and 36 C1, which after 129 I , are the two most significant contributors to dose in safety assessments for the disposal of used fuel. For certain impurities, environmental factors, particularly the safety of the disposal of used fuels, should be taken into consideration when deriving 'allowable' impurity limits for nuclear fuel materials. (author)

Thermoelectric materials evaluation program. Quarterly technical task report No. 46

International Nuclear Information System (INIS)

Hampl, E.F. Jr.

1976-02-01

This forty-sixth Technical Task Report prepared under contract E(11-1)-2331 with the U.S. AEC and U.S. ERDA covers the performance period from October 1, 1975, to December 31, 1975. Highlights include the following tasks: N-type material development (material synthesis--gadolinium selenide compositions; material analyses; material processing; element contacting; ingradient compatibility and life testing; mechanical property characterization), TPM-217 P-type characterization (material preparation and analyses; element contacting; thermodynamic stability; isothermal chemical compatibility; ingradient compatibility and ingradient life testing; performance mapping of contacted and noncontacted elements; high-temperature partitioned P-legs), couple development (design and development of TPM-217/gadolinium selenide rare earth chalcogenide couple; design and development of TPM-217/3N-PbTe couples; advanced generator concepts), module development, liaison with Jet Propulsion Laboratory and material supply, liaison with GGA, and program management. 24 figures, 27 tables

Mixing of incompatible materials in waste tanks technical basis document

International Nuclear Information System (INIS)

SANDGREN, K.R.

2003-01-01

This technical basis document was developed to support the Tank Farms Documented Safety Analysis (DSA) and describes the risk binning process, the technical basis for assigning risk bins, and the controls selected for the mixing of incompatible materials representative accident and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSCs) and/or technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the FR-equency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR level controls. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', as described in this report

TECHNICAL TRAINING SEMINAR: High Temperature Superconductors: Progress and Issues

CERN Multimedia

Davide Vitè

2002-01-01

Monday 24 June from 14:30 to 15:30 - Training Centre Auditorium - bldg. 593-11 High Temperature Superconductors: Progress and Issues Prof. Jan Evetts / UNIVERSITY OF CAMBRIDGE, Department of Materials Science and Metallurgy, UK Grappling with grain boundaries: Current transport processes in granular High Temperature Superconductors (HTS) The development of High Temperature Superconductors, seen from a materials scientist's point of view, is relevant to the superconductivity community at CERN: their possible high current applications can include high performance magnets for future accelerators. There is an urgent need to develop a quantitative description of HTS conductors in terms of their complex anisotropy, inhomogeneity and dimensionality. This is essential both for the practical specification of a conductor and for charting routes to conductor optimisation. The critical current, the n-value, dissipation and quenching characteristics are amongst most important parameters that make up an engineering specifi...

Final Technical Progress Report: Development of Low-Cost Suspension Heliostat; December 7, 2011 - December 6, 2012

Energy Technology Data Exchange (ETDEWEB)

Bender, W.

2013-01-01

Final technical progress report of SunShot Incubator Solaflect Energy. The project succeeded in demonstrating that the Solaflect Suspension Heliostat design is viable for large-scale CSP installations. Canting accuracy is acceptable and is continually improving as Solaflect improves its understanding of this design. Cost reduction initiatives were successful, and there are still many opportunities for further development and further cost reduction.

Energy Materials Coordinating Committee (EMaCC) Fiscal Year 1999 annual technical report

Energy Technology Data Exchange (ETDEWEB)

None

2000-10-31

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. This report summarizes EMaCC activities for FY 1999 and describes the materials research programs of various offices and divisions within the Department.

Progress Report. Teilinstitut Nukleare Festkoerperphysik

International Nuclear Information System (INIS)

Kaefer, K.

1978-10-01

This Progress Report of the Teilinstitut Nukleare Festkoerperphysik covers the work done at the Institute during the period from June 1, 1977 to May 31, 1978. The main research areas presently under investigation are underlined by the arrangement of the report: structure and dynamics of solids, electronic structure and magnetism of solids, and the development and investigation of novel materials. Some technical developments important in carrying out this research are included as well. (orig.) [de

Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Working Material

International Nuclear Information System (INIS)

2013-01-01

In recent years, engineering oriented work, rather than basic research and development (R&D), has led to significant progress in improving the economics of innovative fast reactors and associated fuel cycle facilities, while maintaining and even enhancing the safety features of these systems. Optimization of plant size and layout, more compact designs, reduction of the amount of plant materials and the building volumes, higher operating temperatures to attain higher generating efficiencies, improvement of load factor, extended core lifetimes, high fuel burnup, etc. are good examples of achievements to date that have improved the economics of fast neutron systems. The IAEA, through its Technical Working Group on Fast Reactors (TWG-FR) and Technical Working Group on Nuclear Fuel Cycle Options and Spent Fuel Management (TWG-NFCO), devotes many of its initiatives to encouraging technical cooperation and promoting common research and technology development projects among Member States with fast reactor and advanced fuel cycle development programmes, with the general aim of catalysing and accelerating technology advances in these fields. In particular the theme of fast reactor deployment, scenarios and economics has been largely debated during the recent IAEA International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, held in Paris in March 2013. Several papers presented at this conference discussed the economics of fast reactors from different national and regional perspectives, including business cases, investment scenarios, funding mechanisms and design options that offer significant capital and energy production cost reductions. This Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics addresses Member States’ expressed need for information exchange in the field, with the aim of identifying the main open issues and launching possible initiatives to help and

Waste management issues and their potential impact on technical specifications of CANDU fuel materials

Energy Technology Data Exchange (ETDEWEB)

Tait, J.C.; Johnson, L.H. [Atomic Energy of Canada Limited, Pinawa, Manitoba (Canada)

1997-07-01

The technical specifications for the composition of nuclear fuels and materials used in Canada's CANDU reactors have been developed by AECL and materials manufacturers, taking into account considerations specific to their manufacture and the effect of minor impurities on fuel behaviour in reactor. Nitrogen and chlorine are examples of UO{sub 2} impurities, however, where there is no technical specification limit. These impurities are present in the source materials or introduced in the fabrication process and are neutron activated to {sup 14}C and {sup 36}C1, which after {sup 129}I , are the two most significant contributors to dose in safety assessments for the disposal of used fuel. For certain impurities, environmental factors, particularly the safety of the disposal of used fuels, should be taken into consideration when deriving 'allowable' impurity limits for nuclear fuel materials. (author)

Construction demolition wastes, Waelz slag and MSWI bottom ash: a comparative technical analysis as material for road construction.

Science.gov (United States)

Vegas, I; Ibañez, J A; San José, J T; Urzelai, A

2008-01-01

The objective of the study is to analyze the technical suitability of using secondary materials from three waste flows (construction and demolition waste (CDW), Waelz slag and municipal solid waste incineration (MSWI) bottom ash), under the regulations and standards governing the use of materials for road construction. A detailed technical characterization of the materials was carried out according to Spanish General Technical Specifications for Road Construction (PG3). The results show that Waelz slag can be adequate for using in granular structural layers, while CDW fits better as granular material in roadbeds. Likewise, fresh MSWI bottom ash can be used as roadbed material as long as it does not contain a high concentration of soluble salts. This paper also discusses the adequacy of using certain traditional test methods for natural soils when characterizing secondary materials for use as aggregates in road construction.

Generation and focusing of pulsed intense ion beams. Technical progress report, 20 August 1981-30 September 1982

International Nuclear Information System (INIS)

Hammer, D.A.; Kusse, B.R.; Sudan, R.N.

1983-07-01

The progress on this contract is described in two parts. The first deals with the technical operation of the LION accelerator which is the exact equivalent to one line of PBFA-I. The second part is concerned with the experimental results on the ion diode mounted at the front end of the LION accelerator

Fusion Reactor Materials

International Nuclear Information System (INIS)

Decreton, M.

2002-01-01

The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed

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

Science.gov (United States)

2012-04-18

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

Nuclear waste management. Semiannual progress report, October 1982-March 1983

International Nuclear Information System (INIS)

Chikalla, T.D.; Powell, J.A.

1983-06-01

This document is one of a series of technical progress reports designed to report radioactive waste management programs at the Pacific Northwest Laboratory. Accomplishments in the following programs are reported: waste stabilization; Materials Characterization Center; waste isolation; low-level waste management; remedial action; and supporting studies

Papers of 10. Scientific Technical Seminar on Materials Investigation for Power Industry

International Nuclear Information System (INIS)

2003-01-01

The Report is an assembly of the papers concerning the material and diagnostic problems occurring in the exploitation of power station as well as gas pipelines and underground gas storage technical condition survey. Education and training in welding and non-destructive testing according european rules are also presented as well as provisions of European standards concerning welding consumables. Technical supervision in the light of Poland accession to the european union and quality management system in face of the new standards requirements is described. (author)

The U.S. nuclear waste management program - technical progress at Yucca Mountain

Energy Technology Data Exchange (ETDEWEB)

Barrett, L.H. [U.S. Department of Energy (United States)

2001-07-01

This paper discusses the current status of a national program being developed by the U.S. Department of Energy for the management of spent nuclear fuel and high-level radioactive waste produced by civilian nuclear power generation and defense-related activities. In 1987 the U.S. Congress directed the Department to characterize the Yucca Mountain site in Nevada and determine its suitability for development of a geologic repository. This paper will focus on the technical progress that has been made after more than 15 years of scientific and engineering investigations at Yucca Mountain, and the remaining work that is being done to support a decision on whether to recommend the site for development of a geologic repository. (author)

Fourth Collaborative Materials Exercise of the Nuclear Forensics International Technical Working Group

International Nuclear Information System (INIS)

Schwantes, J.M.; Reilly, D.; Marsden, O.

2018-01-01

The Nuclear Forensics International Technical Working Group is a community of nuclear forensic practitioners who respond to incidents involving nuclear and other radioactive material out of regulatory control. The Group is dedicated to advancing nuclear forensic science in part through periodic participation in materials exercises. The Group completed its fourth Collaborative Materials Exercise in 2015 in which laboratories from 15 countries and one multinational organization analyzed three samples of special nuclear material in support of a mock nuclear forensic investigation. This special section of the Journal for Radioanalytical and Nuclear Chemistry is devoted to summarizing highlights from this exercise. (author)

Material Not Categorized As Waste (MNCAW) data report. Radioactive Waste Technical Support Program

Energy Technology Data Exchange (ETDEWEB)

Casey, C.; Heath, B.A.

1992-11-01

The Department of Energy (DOE), Headquarters, requested all DOE sites storing valuable materials to complete a questionnaire about each material that, if discarded, could be liable to regulation. The Radioactive Waste Technical Support Program entered completed questionnaires into a database and analyzed them for quantities and type of materials stored. This report discusses the data that TSP gathered. The report also discusses problems revealed by the questionnaires and future uses of the data. Appendices contain selected data about material reported.

Recent Progress on the Key Materials and Components for Proton Exchange Membrane Fuel Cells in Vehicle Applications

Directory of Open Access Journals (Sweden)

Cheng Wang

2016-07-01

Full Text Available Fuel cells are the most clean and efficient power source for vehicles. In particular, proton exchange membrane fuel cells (PEMFCs are the most promising candidate for automobile applications due to their rapid start-up and low-temperature operation. Through extensive global research efforts in the latest decade, the performance of PEMFCs, including energy efficiency, volumetric and mass power density, and low temperature startup ability, have achieved significant breakthroughs. In 2014, fuel cell powered vehicles were introduced into the market by several prominent vehicle companies. However, the low durability and high cost of PEMFC systems are still the main obstacles for large-scale industrialization of this technology. The key materials and components used in PEMFCs greatly affect their durability and cost. In this review, the technical progress of key materials and components for PEMFCs has been summarized and critically discussed, including topics such as the membrane, catalyst layer, gas diffusion layer, and bipolar plate. The development of high-durability processing technologies is also introduced. Finally, this review is concluded with personal perspectives on the future research directions of this area.

Progress on research of materials science and biotechnology by ion beam application

Energy Technology Data Exchange (ETDEWEB)

Ishigaki, Isao [Japan Atomic Energy Research Inst., Takasaki, Gunma (Japan). Takasaki Radiation Chemistry Research Establishment

1997-03-01

Research of materials science and biotechnology by ion beam application in Takasaki Establishment was reviewed. Especially, the recent progresses of research on semiconductors in space, creation of new functional materials and topics in biotechnology were reported. (author)

The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Kindergarten. Technical Report # 0921

Science.gov (United States)

Alonzo, Julie; Tindal, Gerald

2009-01-01

In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in kindergarten. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2008 and administered to approximately 2800 students from…

Characterization and testing of materials for nuclear reactors. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2007-03-01

Nuclear techniques in general and neutrons based methods in particular have played and will continue to play an important role in research in materials science and technology. Today the world is looking at nuclear fission and nuclear fusion as the main sources of energy supply for the future. Research reactors have played a key role in the development of nuclear technology. A materials development programme will thus play a major role in the design and development of new nuclear power plants, for the extension of the life of operating reactors as well as for fusion reactors. Against this background, the IAEA had organized a Technical Meeting on Development, Characterization and Testing of Materials - With Special Reference to the Energy Sector under the activity on specific applications of research reactors. The meeting was held in Vienna, May 29- June 2, 2006. There was also participation by experts in techniques, complementary to neutrons. The participants for the technical meeting were experts in the utilization of nuclear techniques namely the high flux and medium flux research reactors, fusion research and positron annihilation. They presented the design, development and utilization of the facilities at their respective centres for materials characterization with main focus on materials for nuclear energy, both fission and fusion. In core irradiation of materials, development of instrument for residual stress measurement in large and / or irradiated specimen, neutron radiography for inspection of irradiated fuel, work on oxide dispersion strengthened (ODS) steels and SiC composites, relevant to future power systems were cited as application of nuclear techniques in fission reactors. The use of neutron scattering for helium bubbles in steel, application of positron annihilation to study helium bubbles in Cu, Ti-stabilized stainless steel and voidswelling studies etc. show that these techniques have an important role in the development of materials for energy

Decontamination Systems Information and Research Program. Quarterly technical progress report, January 1--March 31, 1993

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

This reports reports the progress/efforts performed on six technical projects: 1. systematic assessment of the state of hazardous waste clean-up technologies; 2. site remediation technologies (SRT):drain- enhanced soil flushing for organic contaminants removal; 3. SRT: in situ bio-remediation of organic contaminants; 4. excavation systems for hazardous waste sites: dust control methods for in-situ nuclear waste handling; 5. chemical destruction of polychlorinated biphenyls; and 6. development of organic sensors: monolayer and multilayer self-assembled films for chemical sensors.

Fusion Reactor Materials

Energy Technology Data Exchange (ETDEWEB)

Decreton, M

2002-04-01

The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed.

Technical Progress Report for "Optical and Electrical Properties of III-Nitrides and Related Materials"

Energy Technology Data Exchange (ETDEWEB)

Jiang, Hongxing

2008-10-31

Investigations have been conducted focused on the fundamental material properties of AIN and high AI-content AIGaN alloys and further developed MOCVD growth technologies for obtaining these materials with improved crystalline quality and conductivities.

Nuclear-waste management semiannual progress report, April 1982-September 1982

International Nuclear Information System (INIS)

Chikalla, T.D.; Powell, J.A.

1982-12-01

This document is one of a series of technical progress reports designed to report on radioactive waste management programs at Pacific Northwest Laboratory. Accomplishments in the following programs are reported: waste treatment; nuclear waste Materials Characterization Center (MCC); airborne waste management; low-level waste management; waste isolation; remedial actions; and supporting studies

Divisional progress reports for period 1 July 1982 to 30 June 1983

International Nuclear Information System (INIS)

1984-09-01

This progress report deals with technical and research work done at the AAEC Research establishment for the period 1 July 1982 to 30 June 1983. Work done in the following divisions is reported: Applied Mathematics and Computing, Applied Physics, Environmental Science, Isotope, Materials, Nuclear Technology

Technical Meeting on Liquid Metal Reactor Concepts: Core Design and Structural Materials. Presentations

International Nuclear Information System (INIS)

2013-01-01

The objective of the Technical Meeting is to present and discuss innovative liquid metal fast reactor (LMFR) core designs with special focus on the choice, development, testing and qualification of advanced reactor core structural materials

Progress report of the Teilinstitut Nukleare Festkoerperphysik

International Nuclear Information System (INIS)

Heger, G.

1976-09-01

This progress report of the Teilinstitut Nukleare Festkoerperphysik covers the period from 1st June 1975 - 31st May 1976. The arrangement has been chosen to emphasis the main areas of research in which the institute is presently involved. These areas are Dynamics of Solids and Liquids, Electronic Structure and Magnetism of Solids and Development of Materials. Some of the technical developments relevant to these topics are also included. (orig.) [de

RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

International Nuclear Information System (INIS)

KOZLOWSKI, S.D.

2007-01-01

This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below

Metals and Ceramics Division progress report for period ending June 30, 1984

Energy Technology Data Exchange (ETDEWEB)

Brogden, I. (ed.)

1984-09-01

This progress report covers the research and development activities of the Metals and Ceramics Division from January 1, 1983, through June 30, 1984. The format of the report follows the organizational structure of the division. Short summaries of technical work in progress in the various experimental groups are presented in six parts. Chapter 1 deals with the research and development activities of the Engineering Materials Section, Chapter 2 with the Processing Science and Technology Section, Chapter 3 with the Materials Science Section, Chapter 4 with Project Activities, Chapter 5 with Specialized Research Facilities and Equipment, and Chapter 6 with Miscellaneous Activities.

Metals and Ceramics Division progress report for period ending June 30, 1984

International Nuclear Information System (INIS)

Brogden, I.

1984-09-01

This progress report covers the research and development activities of the Metals and Ceramics Division from January 1, 1983, through June 30, 1984. The format of the report follows the organizational structure of the division. Short summaries of technical work in progress in the various experimental groups are presented in six parts. Chapter 1 deals with the research and development activities of the Engineering Materials Section, Chapter 2 with the Processing Science and Technology Section, Chapter 3 with the Materials Science Section, Chapter 4 with Project Activities, Chapter 5 with Specialized Research Facilities and Equipment, and Chapter 6 with Miscellaneous Activities

Entomology Specialist 1-1. Military Curriculum Materials for Vocational and Technical Education.

Science.gov (United States)

Jones, Jimmie L.

This individualized, self-paced course for training an entomology specialist was adapted from military curriculum materials for use in vocational and technical education. Completion of the course should provide students with basic information needed to accomplish the following duties of an entomology specialist: perform entomological work, apply…

Forty-Fourth Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

International Nuclear Information System (INIS)

2011-01-01

The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 43rd TWG-FR Annual Meeting, including the status of the actions; - Consider topical technical meeting arrangements for 2012-2013, as well as review FR-related activities included in the IAEA Project&Budget (P&B) biennium 2012-2013; - Review the IAEA’s ongoing information exchange and coordinated research projects in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives (GIF, INPRO, NEA, ESNII, etc.)

Forty-Second Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

International Nuclear Information System (INIS)

2009-01-01

The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 41st TWG-FR Annual Meeting, including the status of the actions; - Consider topical technical meetings meeting arrangements for 2009, 2010, 2011 and beyond; - Review the IAEA’s ongoing information exchange and coordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives; - Discuss future joint activities in view of IAEA’s Programme and Budget Cycles beyond 2010-2011

Materials selection as an interdisciplinary technical activity: basic methodology and case studies

Directory of Open Access Journals (Sweden)

M. Ferrante

2000-04-01

Full Text Available The technical activity known as Materials Selection is reviewed in its concepts and methodologies. Objectives and strategies are briefly presented and two important features are introduced and discussed; (i Merit Indices: a combination of materials properties, which maximises the objectives chosen by the designer and (ii Materials Properties Maps: a bi-dimensional space whose coordinates are pairs of properties in which materials can be plotted and compared directly in terms of their merit indices. A general strategy for the deduction of these indices is explained and a formal methodology to establish a ranking of candidate materials when multiple constraints intervene is presented. Finally, two case studies are discussed in depth, one related to materials substitution in the context of mechanical design and a less conventional case linking material selection to physical comfort in the home furniture industry.

GPHS-RTGs in support of the Cassini Mission. Semi annual technical progress report, 1 April 1996--29 September 1996

International Nuclear Information System (INIS)

1996-01-01

This technical progress report discusses work on the Radioisotope Generators and Ancillary Activities for the Cassini spacecraft. The Cassini spacecraft is expected to launch in October 1997, and will explore Saturn and its moons. This progress report discusses issues in: spacecraft integration and liason, engineering support, safety, qualified unicouple fabrication, ETG fabrication and testing, ground support equipment, RTG shipping and launch support, designs, reviews and mission application. Safety analysis of the RTGs during reentry and launch accidents are covered. This report covers the period of April 1 to September 29, 1996

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 1. Geological environment of Japan

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, the part 1 of the progress report, describes first in detail the role of geological environment in high-level radioactive wastes disposal, the features of Japanese geological environment, and programs to proceed the investigation in geological environment. The following chapter summarizes scientific basis for possible existence of stable geological environment, stable for a long period needed for the HLW disposal in Japan including such natural phenomena as volcano and faults. The results of the investigation of the characteristics of bed-rocks and groundwater are presented. These are important for multiple barrier system construction of deep geological disposal. The report furthermore describes the present status of technical and methodological progress in investigating geological environment and finally on the results of natural analog study in Tono uranium deposits area. (Ohno, S.)

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author. Vol. 11(1)--Vol. 18(6)

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W.B.; Klein, A.

1978-04-11

This index to Nuclear Safety covers articles published in Nuclear Safety, Vol. 11, No. 1 (January-February 1970), through Vol. 18, No. 6 (November-December 1977). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 450 technical articles published in Nuclear Safety in the last eight years are listed in this index.

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author. Vol. 11(1)--Vol. 18(6)

International Nuclear Information System (INIS)

Cottrell, W.B.; Klein, A.

1978-01-01

This index to Nuclear Safety covers articles published in Nuclear Safety, Vol. 11, No. 1 (January-February 1970), through Vol. 18, No. 6 (November-December 1977). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 450 technical articles published in Nuclear Safety in the last eight years are listed in this index

Progress on laboratory studies of the immobilisation of plutonium contaminated materials (pcm)

International Nuclear Information System (INIS)

Awmack, A.F.; Hemingway, K.

1984-09-01

This report describes progress on laboratory scale investigations into immobilisation of Plutonium Contaminated Materials for the year ending August 1984. The work is a continuation of that previously reported though some new work is also included. The samples tested were shredded plastic materials and latex. Three areas of work are covered (1) ISO Leach Tests (2) Radiolysis and degradation of organic materials (3) Equilibrium Leach Tests. (author)

International cooperation in combating illicit trafficking of nuclear materials by technical means

International Nuclear Information System (INIS)

Herbillon, J; Koch, L; Mason, G; Niemeyer, S; Nikiforov, N

1999-01-01

A consensus has been emerging during the past several years that illicit trafficking of nuclear materials is a problem that needs a more focused international response. One possible component of a program to combat illicit trafficking is nuclear forensics whereby intercepted nuclear materials are analyzed to provide clues for answering attribution questions. In this report we focus on international cooperation that is specifically addressing the development of nuclear forensics. First we will describe the role of the Nuclear Smuggling International Technical Working Group (ITWG) in developing nuclear forensics, and then we will present some specific examples of cooperative work by the Institute for Transuranium Elements of the European Commission with various European states. Recognizing the potential importance of a nuclear forensics capability, the P-8 countries in 1995 encouraged technical experts to evaluate the role of nuclear forensics in combating nuclear smuggling and possibly developing mechanisms for international cooperation. As a result, an International Conference on Nuclear Smuggling Forensic Analysis was held in November, 1995, at Lawrence Livermore National Laboratory to investigate technical cooperation on nuclear forensics. The International Conference provided a unique mix of scientists, law enforcement, and intelligence experts from 14 countries and organizations. All participants were invited to make presentations, and the format of the Conference was designed to encourage open discussion and broad participation

Energy Materials Coordinating Committee (EMaCC): Annual technical report, fiscal year 1993

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. This report summarizes EMaCC activities for FY 1993 and describes the materials research programs of various offices and divisions within the Department. The program descriptions consist of a funding summary for each Assistant Secretary office and the Office of Energy Research, and detailed project summaries with project goals and accomplishments. The FY 1993 budget summary table for DOE Materials Activities in each of the programs is presented.

The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 1. Technical Report # 0919

Science.gov (United States)

Alonzo, Julie; Tindal, Gerald

2009-01-01

In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grade 1. These measures, available as part of easyCBM [TM], an online progress monitoring assessment system, were developed in 2008 and administered to approximately 2800 students from schools…

The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 2. Technical Report # 0920

Science.gov (United States)

Alonzo, Julie; Lai, Cheng Fei; Tindal, Gerald

2009-01-01

In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grades kindergarten through eighth grade. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2007 and 2008 and administered to…

The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 7. Technical Report 0908

Science.gov (United States)

Lai, Cheng Fei; Alonzo, Julie; Tindal, Gerald

2009-01-01

In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grades kindergarten through eighth grade. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2007 and 2008 and administered to…

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Introductory part and summaries

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan and comprises seven chapters. Chapter I briefly describes the importance of HLW management in promoting nuclear energy utilization. According to the long-term program, the HLW separated from spent fuels at reprocessing plants is to be vitrified and stored for a period of 30 to 50 years to allow cooling, then be disposed of in a deep geological formation. Chapter II mainly explains the concepts of geological disposal in Japan. Chapters III to V are devoted to discussions on three important technical elements (the geological environment of Japan, engineering technology and safety assessment of the geological disposal system) which are necessary for reliable realization of the geological disposal concept. Chapter VI demonstrates the technical ground for site selection and for setup of safety standards of the disposal. Chapter VII summarizes together with plans for future research and development. (Ohno, S.)

Annual Technical Report, Materials Research Laboratory, 1 July 1982 - 30 June 1983.

Science.gov (United States)

1983-06-30

Technical Report 41 SECTION 6 PROPERTIES OF MATERIALS AT LOW TEMPERATURES Introduction The general motivation for this work is that certain interesting...Professor, Chemis- "Photoelectronic Properties of Cu 3 PS4 and try. Cu 3 PS Se Single Crystals," J. V. Marzik, A. K. Hsieh, K. Dwight and A. Wold. J

Progresso tecnico, forme di mercato e disoccupazione. ( Technical progress, market forms and unemployment

Directory of Open Access Journals (Sweden)

A. ASIMAKOPULOS A.

2013-12-01

Full Text Available Lo scopo del presente lavoro è triplice . Il primo obiettivo è quello di sottolineare l'importanza delle intuizioni da trovare nel lavoro di Sylos Labini . Il secondo scopo è quello di espandere su di essa distinguendo tra i diversi tipi di progresso tecnico . Infine , il terzo obiettivo è quello di commentare il confronto di Labini di Ricardo e Keynes sulla possibilità di disoccupazione tecnologica . Per quanto riguarda la sua descrizione del progresso tecnologico come " risparmio di lavoro " , l'autore mostra che una descrizione più completa sarebbe più utile per i suoi scopiThe purpose of the present paper is threefold. The first purpose is to emphasise the importance of the insights to be found in Sylos Labini’s work. The second purpose is to expand upon it by distinguishing  between the different types of technical progress. Finally, the third purpose is to comment on Labini’s comparison of Ricardo and Keynes on the possibility of technological unemployment. Regarding his description of technological progress as “labour saving”, the author shows that a more comprehensive description would be more useful for his purposes.JEL: E24, J64, O33

Applications of Research Reactors Towards Research on Materials for Nuclear Fusion Technology. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2013-11-01

of materials under development for Generation IV concepts. International collaboration among MTRs and specialized facilities has been identified as integral to progress in fusion development as well as enhancing reactor utilization. This publication specifies which areas of research remain in the qualification of structural materials and components, and has detailed the characteristics of many research reactors and devices that can accomplish an important portion of these necessary studies. This publication is the outcome of two recent IAEA sponsored meetings under its programme to enhance the utilization and collaboration of research reactor and material test facilities: - Consultancy meeting on Role of Research Reactors in Materials Research for Nuclear Fusion Technology, 13-15 December 2010, IAEA, Vienna; - Technical meeting on Materials under High Energy and High Intensity Neutron Fluxes for Nuclear Fusion Technology, 27-29 June 2011, IAEA, Vienna. These meetings brought together representatives from MTRs, spallation neutron sources, multiple beam irradiation facilities, material scientists as well as fusion community representatives to discuss the current state of fusion research and to plot necessary studies and modes of research collaboration

Technical progress and efficiency changes in football teams participating in the UEFA Champions League

Directory of Open Access Journals (Sweden)

Lucía Isabel García Cebrián

2015-09-01

Full Text Available This paper commits to calculate and analyze productivy levels and its components for teams that participated in the UEFA Champions League between 2003 and 2012. It will pursue three objectives: 1 evaluate resources usage, 2 analyze the productivity levels of the football teams and the sports results, and 3 see the influence of participation experience in reference to productivity and sports results. Using Malmquist Productivity Index, the results reflect a lack of consistent progression of efficiency, productivity, and technical change. This competition does not reward the efficient usage of resources and there is not a conclusive relationshop between permanence in the competition and productivity.

Volatiles combustion in fluidized beds. Technical progress report, 4 March 1993--3 June 1993

Energy Technology Data Exchange (ETDEWEB)

Hesketh, R.P.

1993-09-01

The goal of this project is to investigate the conditions in which volatiles will burn within both the dense and freeboard regions of fluidized beds. Experiments using a fluidized bed operated at incipient fluidization will be performed to characterize the effect of particle surface area, initial fuel concentration, and particle type on the inhibition of volatiles within a fluidized bed. The work conducted during the period 4 March, 1993 through 3 June, 1993 is reported in this technical progress report. The work during this time period consists primarily of the startup and trouble shooting of the fluidized bed reactor and gas phase modeling of methane and propane.

Progress Report of the Materials Department. First Quarter 1971. RCN Report

International Nuclear Information System (INIS)

Sens, P.F.

1971-06-01

A description of the progress in the various projects concerning the materials development of water cooled reactors, sodium cooled fast reactors and gas cooled reactors. Similar reports have been issued regularly with an internal distribution only. (author)

Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 2003

Energy Technology Data Exchange (ETDEWEB)

none,

2004-10-18

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. Topical subcommittees of the EMaCC are responsible for conducting seminars and otherwise facilitating information flow between DOE organizational units in materials areas of particular importance to the Department. The EMaCC Terms of Reference were recently modified and developed into a Charter that was approved on June 5, 2003. As a result of this reorganization, the existing subcommittees were disbanded and new subcommittees are being formed.

Silicon ribbon growth by a capillary action shaping technique. Annual report (Quarterly technical progress report No. 9)

Energy Technology Data Exchange (ETDEWEB)

Schwuttke, G.H.; Ciszek, T.F.; Kran, A.

1977-10-01

Progress on the technological and economical assessment of ribbon growth of silicon by a capillary action shaping technique is reported. Progress in scale-up of the process from 50 mm to 100 mm ribbon widths is presented, the use of vitreous carbon as a crucible material is analyzed, and preliminary tests of CVD Si/sub 3/N/sub 4/ as a potential die material are reported. Diffusion length measurements by SEM, equipment and procedure for defect display under MOS structure in silicon ribbon for lifetime interpretation, and an assessment of ribbon technology are discussed. (WHK)

Control assembly materials for water reactors: Experience, performance and perspectives. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-02-01

The safe, reliable and economic operation of water cooled nuclear power reactors depends to a large extent upon the reliable operation of control assemblies for the regulation and shutdown of the reactors. These consist of neutron absorbing materials clad in stainless steel or zirconium based alloys, guide tubes and guide cards, and other structural components. Current designs have worked extremely well in normal conditions, but less than ideal behaviour limits the lifetimes of control materials, imposing an economic penalty which acts as a strong incentive to produce improved materials and designs that are more reliable. Neutron absorbing materials currently in use include the ceramic boron carbide, the high melting point metal hafnium and the low melting point complex alloy Ag-In-Cd. Other promising neutron absorbing materials, such as dysprosium titanate, are being evaluated in the Russian Federation. These control materials exhibit widely differing mechanical, physical and chemical properties, which must be understood in order to be able to predict the behaviour of control rod assemblies. Identification of existing failure mechanisms, end of life criteria and the implications of the gradual introduction of extended burnup, mixed oxide (MOX) fuels and more complex fuel cycles constitutes the first step in a search for improved materials and designs. In the early part of this decade, it was recognized by the International Working Group on Fuel Performance and Technology (IWGFPT) that international conferences, symposia and published reviews on the materials science aspects of control assemblies were few and far between. Consequently, the IWGFPT recommended that the IAEA should rectify this situation with a series of Technical Committee meetings (TCMs) devoted entirely to the materials aspects of reactor control assemblies. The first was held in 1993 and in the intervening five years considerable progress has been made. In bringing together experts in the

Control assembly materials for water reactors: Experience, performance and perspectives. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2000-02-01

The safe, reliable and economic operation of water cooled nuclear power reactors depends to a large extent upon the reliable operation of control assemblies for the regulation and shutdown of the reactors. These consist of neutron absorbing materials clad in stainless steel or zirconium based alloys, guide tubes and guide cards, and other structural components. Current designs have worked extremely well in normal conditions, but less than ideal behaviour limits the lifetimes of control materials, imposing an economic penalty which acts as a strong incentive to produce improved materials and designs that are more reliable. Neutron absorbing materials currently in use include the ceramic boron carbide, the high melting point metal hafnium and the low melting point complex alloy Ag-In-Cd. Other promising neutron absorbing materials, such as dysprosium titanate, are being evaluated in the Russian Federation. These control materials exhibit widely differing mechanical, physical and chemical properties, which must be understood in order to be able to predict the behaviour of control rod assemblies. Identification of existing failure mechanisms, end of life criteria and the implications of the gradual introduction of extended burnup, mixed oxide (MOX) fuels and more complex fuel cycles constitutes the first step in a search for improved materials and designs. In the early part of this decade, it was recognized by the International Working Group on Fuel Performance and Technology (IWGFPT) that international conferences, symposia and published reviews on the materials science aspects of control assemblies were few and far between. Consequently, the IWGFPT recommended that the IAEA should rectify this situation with a series of Technical Committee meetings (TCMs) devoted entirely to the materials aspects of reactor control assemblies. The first was held in 1993 and in the intervening five years considerable progress has been made. In bringing together experts in the

MISSE in the Materials and Processes Technical Information System (MAPTIS )

Science.gov (United States)

Burns, DeWitt; Finckenor, Miria; Henrie, Ben

2013-01-01

Materials International Space Station Experiment (MISSE) data is now being collected and distributed through the Materials and Processes Technical Information System (MAPTIS) at Marshall Space Flight Center in Huntsville, Alabama. MISSE data has been instrumental in many programs and continues to be an important source of data for the space community. To facilitate great access to the MISSE data the International Space Station (ISS) program office and MAPTIS are working to gather this data into a central location. The MISSE database contains information about materials, samples, and flights along with pictures, pdfs, excel files, word documents, and other files types. Major capabilities of the system are: access control, browsing, searching, reports, and record comparison. The search capabilities will search within any searchable files so even if the desired meta-data has not been associated data can still be retrieved. Other functionality will continue to be added to the MISSE database as the Athena Platform is expanded

Defense Virtual Library: Technical Metadata for the Long-Term Management of Digital Materials: Preliminary Guidelines

National Research Council Canada - National Science Library

Flynn, Marcy

2002-01-01

... of the digital materials being preserved. This report, prepared by Silver Image Management (SIM), proposes technical metadata elements appropriate for digital objects in the Defense Virtual Library...

Materials studies for magnetic fusion energy applications at low temperatures. VIII. Technical reports

International Nuclear Information System (INIS)

Reed, R.P.

1985-05-01

This report contains results of a research progam to produce material property data that will facilitte design and development of cryogenic structures for the superconducting magnets of magnetic fusion energy power plants and prototypes. Research results for 1984 are summarized in an initial ''Highlights of Results'' section and reported in detail in the technical papers that form the main body of this report. The technical papers are presented under four headings reflecting the main program areas: Welding, Nonmetallics, Structural Alloys, and Technology Transfer. Objectives, approaches, and achievements are summarized in an introduction to each program area

Progress report of the Teilinstitut Nukleare Festkoerperphysik

International Nuclear Information System (INIS)

Geerk, J.; Linker, G.

1977-10-01

This progress report of the Teilinstitut Nukleare Festkoerperphysik covers the period from June 1sup(st), 1976 - May 31sup(st), 1977. The arrangement has been chosen to emphasize the main research areas the institute is presently involved. These areas are the Dynamics of Solids and Liquids, the Electronic Structure and Magnetism of Solids, and the Development and Investigation of New Materials. Some of the technical developments relevant to these topics are also included. (orig.) [de

Application of Nanostructures in Electrochromic Materials and Devices: Recent Progress

Directory of Open Access Journals (Sweden)

Jin Min Wang

2010-11-01

Full Text Available The recent progress in application of nanostructures in electrochromic materials and devices is reviewed. ZnO nanowire array modified by viologen and WO3, crystalline WO3 nanoparticles and nanorods, mesoporous WO3 and TiO2, poly(3,4-ethylenedioxythiophene nanotubes, Prussian blue nanoinks and nanostructures in switchable mirrors are reviewed. The electrochromic properties were significantly enhanced by applying nanostructures, resulting in faster switching responses, higher stability and higher optical contrast. A perspective on the development trends in electrochromic materials and devices is also proposed.

Materials Investigation for Power Plants Industry. Seminar

International Nuclear Information System (INIS)

Szteke, W.; Wasiak, J.; Bilous, W.; Przyborska, M.; Wagner, T.; Wojciechowska, J.; Zubowski, B.

2006-01-01

The Report is an assembly of the papers concerning perspectives of evolution of power in Poland. The material and diagnostic problems occurring the exploitation of power station as well as gas pipelines are discussed. The progress in the accommodation of the Polish technical prescriptions to the European law is described

Neutron reflectometry: A probe for materials surfaces. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2006-01-01

Research reactors play an important role in delivering the benefits of nuclear science and technology. The IAEA, through its project on the effective utilization of research reactors, has been providing technical support to Member States and promotes activities related to specific applications. Neutron beam research is one of the main components in materials science studies. Neutron reflectometry is extremely useful for characterizing thin films and layered structures, polymers, oxide coatings on metals and biological membranes. The neutron has been a major probe for investigating magnetic materials. Development of magnetic multilayers is important for diverse applications in sensors, memory devices, etc. The special nature of the interaction of the neutron with matter makes it an important tool to locate low z elements in the presence of high z elements, which is useful in biology and polymer science. The role of neutron reflectometry in research and development in materials science and technology was discussed in a consultants meeting held in 2003. Following this, a technical meeting was organized from 16 to 20 August 2004 in Vienna to discuss the current status of neutron reflectometry, including the instrumentation, data acquisition, data analysis and applications. Experts in the field of neutron reflectometry presented their contributions, after which there was a brainstorming session on various aspects of the technique and its applications. This publication is the outcome of deliberations during the meeting and the presentations by the participants. This publication will be of use to scientists planning to develop a neutron reflectometer at research reactors. It will also help disseminate knowledge and information to material scientists, biologists and chemists working towards characterizing and developing new materials

The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 3. Technical Report # 09-02

Science.gov (United States)

Alonzo, Julie; Lai, Cheng Fei; Tindal, Gerald

2009-01-01

In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grades kindergarten through eighth grade. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2007 and 2008 and administered to…

The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 5. Technical Report # 09-01

Science.gov (United States)

Lai, Cheng Fei; Alonzo, Julie; Tindal, Gerald

2009-01-01

In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grades kindergarten through eighth grade. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2007 and 2008 and administered to…

The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 4. Technical Report # 09-03

Science.gov (United States)

Alonzo, Julie; Lai, Cheng Fei; Tindal, Gerald

2009-01-01

In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grades kindergarten through eighth grade. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2007 and 2008 and administered to…

The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 8. Technical Report # 09-04

Science.gov (United States)

Lai, Cheng Fei; Alonzo, Julie; Tindal, Gerald

2009-01-01

In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grades kindergarten through eighth grade. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2007 and 2008 and administered to…

Final Technical Progress Report

Energy Technology Data Exchange (ETDEWEB)

J.Y. Hwang; R.C. Greenlund

2002-12-31

Michigan Technological University has demonstrated major inroads in establishing the viability of utilizing aluminum smelting by-product waste materials in lightweight concrete product applications. The research identified key elements of producing various forms of lightweight concrete products through utilizing various procedures and mixture components with the by-product materials. A process was developed through pilot plant testing that results in additional aluminum recovery at finer sizes, a clean returnable salt product through spray drying technology, and a low-salt-content oxide product with enough aluminum metal content that it can be used to form lightweight cementitious mixtures. Having three distinct products aids in generating favorable process economics. Revenue projections from aluminum recovery and salt recovery are enough to cover processing costs and create a cost-free oxide product to market for lightweight concrete applications. This supply side commercialization strategy offers aluminum by-product recyclers a potentially no cost product, which has been demonstrated through this project to create desirable and marketable lightweight concrete products of various forms. Environmental benefits to the public are tremendous. At best, all dross and salt cake materials have the potential to be completely recycled and utilized. At worst, disposal sites would see a reduced amount of material: a post processed oxide product with little salt and no hydrogen sulfide or ammonia gas generating capability, which, if isolated from high alkali conditions, would pose no reactivity concerns. The US aluminum industry has historically, along with the steel industry, been a leader in recycling metal. The findings from this project, increased metal recovery, improved salt recycling, and demonstrated end uses for oxide residues, will go a long way in helping the aluminum industry obtain 100% material utilization and zero discharge.

METHOD IMPROVEMENT FOR DETERMINING THE TECHNICAL LEVEL OF CIVIL AIRCRAFT

Directory of Open Access Journals (Sweden)

2016-01-01

Full Text Available Aircraft are high-tech engineering products which are characterized by a wide range of properties including the two most important groups that respectively characterize the efficiency and technical level.Improving the aircraft efficiency is an essential factor for air transport development, but the efficiency can not be fully describe the technical system, especially in forecasting and new technology requirements development. Aircraft de- signer must evaluate the prospects of a technical solution, but it’s not always possible to calculate the efficiency accuratelyat the design stage. The operator should be able to choose the most technically-advanced aircraft available in the market inorder not to let it grow obsolete quickly. This determines the need for non-economic evaluation of technical systems that can be done by assessment of their technical level.The technical level is a general index that includes a set of technical perfection indicators. Technical perfection is reflected in terms of material and energy intensity, in terms of ergonomics, safety, etc. and is achieved as a result of origi- nal design solutions, the use of new high-strength low-density materials, the introduction of advanced technological pro-cesses, calculation methods, verification, testing, etc.There is a tight connection between the product properties and its weight, because weight is the material reflection of these properties. Therefore, improvement of the product properties usually leads to an intense increase of its weight. To deal with this phenomenon is only possible with widely using scientific and technical progress results. In accordance with this, the technical perfection can be interpreted as a major component of quality that is created without the weight increase. This approach requires investment in research and testing new technical solutions.The method was developed to determine the technical level of civil long-haul aircraft which has been modified to

National Council on Radiation Protection and Measurements semiannual technical progress report, March 1989--August 1989

International Nuclear Information System (INIS)

Ney, W.R.

1991-01-01

This semiannual technical progress report is for the period 1 March 1989 through 31 August 1989. This National Council on Radiation Protection and Measurements (NCRP) program is designed to provide recommendations for radiation protection based on scientific principles. During this period several reports were published covering the topics of occupational radiation exposure, medical exposure, radon control, dosimetry, and radiation protection standards. Accomplishments of various committees are also reported; including the committees on dental x-ray protection, radiation safety in uranium mining and milling, ALARA, instrumentation, records maintenance, occupational exposures of medical personnel, emergency planning, and others. (SM)

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

International Nuclear Information System (INIS)

Cottrell, W.B.; Passiakos, M.

1982-06-01

This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W.B.; Passiakos, M.

1982-06-01

This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index.

Progress report 2011-2013 - Brazilian Energy and Nuclear Research Institute - IPEN

International Nuclear Information System (INIS)

2014-01-01

This progress report presents the results of the R&D center of IPEN in accordance with the main programs: Lasers Technology, Applications of Ionizing Radiations, Biotechnology, Renewable Energies, Radiopharmacy, Nuclear Science and Technology, Environmental Science and Technology, Nuclear Reactors and Fuel Cycle, Materials and Nanotechnology, Nuclear Safety, Education, Brazilian Multipurpose Reactor and Scientific and Technical Production

Progress report 2008-2010 - Brazilian Energy and Nuclear Research Institute - IPEN

International Nuclear Information System (INIS)

2011-01-01

This progress report presents the results of the R and D center of IPEN in the areas of: Lasers Technology; Renewable Energies; Nuclear Reactors and Fuel Cycle; Applications of Ionizing Radiations; Nuclear Science and Technology; Materials and Nanotechnology; Environmental Science and Technology; Radiopharmacy; Nuclear Safety; and Education. Also presents the Technical and Scientific Production od the center

Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol. 11, No. 1--Vol. 17, No. 6

International Nuclear Information System (INIS)

Cottrell, W.B.; Klein, A.

1977-01-01

This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970), through Vol. 17, No. 6 (Nov.-Dec. 1976). The index includes a chronological list of articles (including abstract) followed by KWIC and Author Indexes. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 350 technical articles in the last six years of publication

Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol. 11, No. 1--Vol. 17, No. 6

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W.B.; Klein, A.

1977-02-23

This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970), through Vol. 17, No. 6 (Nov.-Dec. 1976). The index includes a chronological list of articles (including abstract) followed by KWIC and Author Indexes. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 350 technical articles in the last six years of publication.

A Duration Prediction Using a Material-Based Progress Management Methodology for Construction Operation Plans

Directory of Open Access Journals (Sweden)

Yongho Ko

2017-04-01

Full Text Available Precise and accurate prediction models for duration and cost enable contractors to improve their decision making for effective resource management in terms of sustainability in construction. Previous studies have been limited to cost-based estimations, but this study focuses on a material-based progress management method. Cost-based estimations typically used in construction, such as the earned value method, rely on comparing the planned budget with the actual cost. However, accurately planning budgets requires analysis of many factors, such as the financial status of the sectors involved. Furthermore, there is a higher possibility of changes in the budget than in the total amount of material used during construction, which is deduced from the quantity take-off from drawings and specifications. Accordingly, this study proposes a material-based progress management methodology, which was developed using different predictive analysis models (regression, neural network, and auto-regressive moving average as well as datasets on material and labor, which can be extracted from daily work reports from contractors. A case study on actual datasets was conducted, and the results show that the proposed methodology can be efficiently used for progress management in construction.

Progress report for 1984/85 from the Plutonium Contaminated Materials Working Party

International Nuclear Information System (INIS)

Higson, S.G.

1985-01-01

The progress report for 1984/5 from the 'Plutonium Contaminated Materials Working Party' is presented. The report is divided into eight main topics, each discussed separately, and include: reduction of arisings, plutonium measurement, sorting and packaging, washing of shredded combustible plutonium contaminated materials (PCM), decommissioning and non-combustible PCM treatment, PCM immobilization, treatment of alpha bearing liquid wastes, and engineering objectives. (U.K.)

Combined macroscopic and microscopic approach to the fracture of metals. Technical progress report

International Nuclear Information System (INIS)

Asaro, R.J.; Gurland, J.; Needleman, A.; Rice, R.J.

1979-06-01

Progress is reported on microscopic fracture mechanisms, including studies of void and crack initiation in steels in the absence and presence of hydrogen, the effects of hydrogen on ductile fracture in medium and high carbon steels; elastic--plastic crack growth including the quasi-stable growth of cracks in ductile solids under increasing load and conditions of instability; and elevated temperature rupture including analysis of the stress field near a crack tip in an elastic-nonlinear viscous material under tensile load as well as the processes of diffusion, and cavitation of grain boundaries in plastically creeping materials

Progress of flame gunning materials; Yosha hoshuzai no shinpo

Energy Technology Data Exchange (ETDEWEB)

Murakami, Kakuichi [Harima Ceramic Corp., Hyogo (Japan)

1999-04-01

This report concerns to progress in the thermal spraying for repairing refractory, to say more precisely the flame-gunning materials. Gunning method using wet-slurry materials, in spite of its simplicity in execution, possesses a shortcoming of forming the porous deposit around spraying spot. Contrarily, the flame-gunning method is becoming popular in Japan because this method provides us with the minutely organized deposit having high tenacity and corrosion-resisting property. Flame is made from propane/oxygen mixture to assure the efficient melting of powdered clay. Magnesia/Dromite/slag system is preferable to converter furnace to produce a deposit layer less than 10% porosity. Materials based on alumina are preferable, although giving a relatively elevated porosity, to vacuum degassing vessel, converter furnace of stainless steel, hot stove for blast furnace, etc. Silca-rich system is characterized by the resistivity to recycled thermal procedure which brings about application to coke furnace. (NEDO)

Realization of radiation-chemical processes in national economy-important stage of scientific and technical progress

International Nuclear Information System (INIS)

Breger, A.Kh.

1975-01-01

Realization of energy resourses of the atomic power engineering will greatly contribute to the scientific and technological progress. The dominat role play the radiochemical methods of properties modification applied for the well-known materials and for the production of materials with modern operating characteristics necessary for their application in different branches of industry and agriculture. Radiation modeling of products from polyolefine, wood-plastic and concrete-polymer materials are considered as well as the processes in ''thin'' units of agitating systems. The future developments and present state of the art of radiation sources are presented

Technical committee on transport package test standards (for radioactive materials transport). Vienna, 6-10 August 1979

International Nuclear Information System (INIS)

White, M.C.

1979-11-01

The report of a meeting of the technical committee on transport package test standards is presented. The committee assigned high priority to work on Low Level Solid material and Low Specific Activity material, on the justification for and requirements of a Crush Test and on leakage from packages

Progress report for 1982/83 from the Plutonium Contaminated Materials Working Party

International Nuclear Information System (INIS)

Higson, S.G.

1983-01-01

The report falls under the headings: introduction (definitions of plutonium contaminated materials (PCM)); organisation and role of the Plutonium Contaminated Materials Working Party; management practices in relation to PCM; 1982/1983 Progress Report (engineering objectives; reduction of PCM arisings; plutonium measurement; development of treatment processes; decommissioning and non-combustible PCM treatment; washing of shredded combustible PCM; PCM immobilisation; liquid effluent treatment; actinide chemistry); programme management. (U.K.)

Energy Materials Coordinating Committee (EMaCC), fiscal year 1985. Annual technical report

International Nuclear Information System (INIS)

1986-05-01

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meeting/workshops on selected topics involving both DOE and major contractors. Four topical subcommittees on Structural Ceramics, Batteries and Fuel Cells, Radioactive Waste Containment, and Steel are established and are continuing their own program. The FY 1985 and FY 1986 meeting program is given. The EMaCC aids in obtaining materials-related inputs for both intra- and inter-agency compilations. Brief summaries of the materials research programs associated with each office and division are presented, including tables listing individual projects and the FY 1985 budgets for each. More details on the individual projects within the divisions and the specific tasks or subcontracts within the various projects are given in the paragraph descriptions

Energy Materials Coordinating Committee (EMaCC), fiscal year 1985. Annual technical report

Energy Technology Data Exchange (ETDEWEB)

None

1986-05-01

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meeting/workshops on selected topics involving both DOE and major contractors. Four topical subcommittees on Structural Ceramics, Batteries and Fuel Cells, Radioactive Waste Containment, and Steel are established and are continuing their own program. The FY 1985 and FY 1986 meeting program is given. The EMaCC aids in obtaining materials-related inputs for both intra- and inter-agency compilations. Brief summaries of the materials research programs associated with each office and division are presented, including tables listing individual projects and the FY 1985 budgets for each. More details on the individual projects within the divisions and the specific tasks or subcontracts within the various projects are given in the paragraph descriptions.

Progress report : Technical Physics Division

International Nuclear Information System (INIS)

Gopalaraman, C.P.; Deshpande, R.Y.

1978-01-01

The research and development work carried out in the Technical Physics Division of the Bhabha Atomic Research Centre, Bombay, is reported. Some of the achievements are: (1) fabrication of mass spectrometers for heavy water analysis and lithium 6/7 isotope ratio measurement, (2) fabrication of electronic components for mass spectrometers, (3) growing of sodium iodide crystals for radiation detectors, (4) development of sandwich detectors comprising of NaI(Tl) and CaI(Na), (5) fabrication of mass spectrometer type leak detectors and (6) fabrication of the high vacuum components of the vacuum system of the variable energy cyclotron based at Calcutta. (M.G.B.)

Heavy-section steel irradiation program. Progress report, October 1994--March 1995

International Nuclear Information System (INIS)

Corwin, W.R.

1995-10-01

This document is the October 1994-March 1995 Progress Report for the Heavy Section Steel Irradiation Program. The report contains a summary of activities in each of the 14 tasks of the HSSI Program, including: (1) Program management, (2) Fracture toughness shifts in high-copper weldments, (3) Fracture toughness shifts in low upper-shelf welds, (4) Irradiation effects in a commercial low upper-shelf weld, (5) Irradiation effects on weld heat-affected zone and plate materials, (6) Annealing effects in low upper-shelf welds, (7) Microstructural analysis of radiation effects, (8) In-service irradiated and aged material evaluations, (9) Japanese power development reactor vessel steel examination, (10) fracture toughness curve shift method, (11) Special technical assistance, (12) Technical assistance for JCCCNRS, (13) Correlation monitor materials, and (14) Test reactor irradiation coordination. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

Progress in the US program to develop low-activation structural materials for fusion

International Nuclear Information System (INIS)

Kurtz, R.J.; Jones, R.H.; Bloom, E.E.; Rowcliffe, A.F.; Smith, D.L.; Odette, G.R.; Wiffen, F.W.

1999-01-01

It has long been recognized that attainment of the safety and environmental potential of fusion energy requires the successful development of low-activation materials for the first wall, blanket and other high heat flux structural components. Only a limited number of materials potentially possess the physical, mechanical and low-activation characteristics required for this application. The current US structural materials research effort is focused on three candidate materials: advanced ferritic steels, vanadium alloys, and silicon carbide composites. Recent progress has been made in understanding the response of these materials to neutron irradiation. (author)

Amarillo National Resource Center for Plutonium. Quarterly technical progress report, May 1, 1997--July 31, 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

Progress summaries are provided from the Amarillo National Center for Plutonium. Programs include the plutonium information resource center, environment, public health, and safety, education and training, nuclear and other material studies.

Materials R&D-student internships

Energy Technology Data Exchange (ETDEWEB)

Thompson, R.B.; Jiles, D.C.; Chumbley, L.S. [Iowa State Univ., Ames, IA (United States)

1995-05-01

This program has as an objective the conduct of programmatic research for the Advanced Industrial Concepts Materials Program while training minority graduate students in the process. Well-known demographics indicate that minorities will constitute an increasing fraction of our future work force. Consequently, efforts have been initiated to increase the fraction of minorities and women who choose technical career paths. Included are a wide ranging set of programs beginning with pre-school education, progressing through efforts to retain students in technical paths in grades K-12 and undergraduate education, and ending with encouraging graduate education. The Materials R & D - Student Internships is a unique approach in the latter category. Here, we have focused on a particular area of applied materials research, the Advanced Industrial Concepts Materials Program. Our goal, then, is to educate minority graduate students in the context of this program. The Ames Laboratory was selected as a site for this pilot project since it is a DOE national laboratory, located on the campus of a major research university, which includes in its research interests programs with a strong technological flavor.

Using constitutive equation gap method for identification of elastic material parameters: Technical insights and illustrations

KAUST Repository

Florentin, Éric

2011-08-09

The constitutive equation gap method (CEGM) is a well-known concept which, until now, has been used mainly for the verification of finite element simulations. Recently, CEGM-based functional has been proposed to identify local elastic parameters based on experimental full-field measurement. From a technical point of view, this approach requires to quickly describe a space of statically admissible stress fields. We present here the technical insights, inspired from previous works in verification, that leads to the construction of such a space. Then, the identification strategy is implemented and the obtained results are compared with the actual material parameters for numerically generated benchmarks. The quality of the identification technique is demonstrated that makes it a valuable tool for interactive design as a way to validate local material properties. © 2011 Springer-Verlag.

Summary Report for the Technical Interchange Meeting on Development of Baseline Material Properties and Design Guidelines for In-Space Manufacturing Activities

Science.gov (United States)

Prater, T. J.; Bean, Q. A.; Werkheiser, N. J.; Johnston, M. M.; Ordonez, E. A.; Ledbetter, F. E.; Risdon, D. L.; Stockman, T. J.; Sandridge, S. K. R.; Nelson, G. M.

2016-01-01

NASA Marshall Space Flight Center (MSFC) and the Agency as a whole are currently engaged in a number of in-space manufacturing (ISM) activities that have the potential to reduce launch costs, enhance crew safety, and provide the capabilities needed to undertake long-duration spaceflight. The recent 3D Printing in Zero-G experiment conducted on board the International Space Station (ISS) demonstrated that parts of acrylonitrile butadiene styrene (ABS) plastic can be manufactured in microgravity using fused deposition modeling (FDM). This project represents the beginning of the development of a capability that is critical to future NASA missions. Current and future ISM activities will require the development of baseline material properties to facilitate design, analysis, and certification of materials manufactured using in-space techniques. The purpose of this technical interchange meeting (TIM) was to bring together MSFC practitioners and experts in materials characterization and development of baseline material properties for emerging technologies to advise the ISM team as we progress toward the development of material design values, standards, and acceptance criteria for materials manufactured in space. The overall objective of the TIM was to leverage MSFC's shared experiences and collective knowledge in advanced manufacturing and materials development to construct a path forward for the establishment of baseline material properties, standards development, and certification activities related to ISM. Participants were asked to help identify research and development activities that will (1) accelerate acceptance and adoption of ISM techniques among the aerospace design community; (2) benefit future NASA programs, commercial technology developments, and national needs; and (3) provide opportunities and avenues for further collaboration.

Solar lease grant program. Technical progress report

Energy Technology Data Exchange (ETDEWEB)

1981-04-01

Progress on a lease program for the installation of a solar water heater with no installation charge is reported. Information on the announcement of the program, the selection of participants, the contractural agreement, progress on installation of equipment, monitoring, and evaluation is summarized. The status of the budget concerned with the program is announced. Forms used for applications for the program and an announcement from Resource Alternatives for Cilco customers are presented.

Technical progress report

International Nuclear Information System (INIS)

1996-01-01

This report summarizes experimental and theoretical work in basic nuclear physics carried out between October 1, 1995, the closing of our last Progress Report, and September 30, 1996 at the Nuclear Physics Laboratory of the University of Colorado, Boulder, under contracts DE-FG03-93ER-40774 and DE-FG03-95ER-40913 with the United States Department of Energy. The experimental contract supports broadly-based experimental research in intermediate energy nuclear physics. This report includes results from studies of Elementary Systems involving the study of the structure of the nucleon via polarized high-energy positron scattering (the HERMES experiment) and lower energy pion scattering from both polarized and unpolarized nucleon targets. Results from pion- and kaon-induced reactions in a variety of nuclear systems are reported under the section heading Meson Reactions; the impact of these and other results on understanding the nucleus is presented in the Nuclear Structure section. In addition, new results from scattering of high-energy electrons (from CEBAF/TJNAF) and pions (from KEK) from a broad range of nuclei are reported in the section on Incoherent Reactions. Finally, the development and performance of detectors produced by the laboratory are described in the section titled Instrumentation

Advanced Industrial Materials (AIM) Program: Annual progress report 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 Annual Report for FY 1995 contains the technical details of some very remarkable work by the best materials scientists and engineers in the world. Areas covered here are: advanced metals and composites; advanced ceramics and composites; polymers and biobased materials; and new materials and processes.

Hydrogen storage - are we making progress?

International Nuclear Information System (INIS)

Blair, L.; Milliken, J.; Satyapal, S.

2004-01-01

'Full text:' The efficient storage of hydrogen in compact, lightweight systems that allow greater than 300-mile range has been identified as one of the major technical challenges facing the practical commercialization of fuel cell power systems for light-duty vehicles. Following the hydrogen vision announced by President Bush in his 2003 State of the Union address, the U.S. Department of Energy issued a Grand Challenge, soliciting ideas from universities, national laboratories, and industry. DOE's National Hydrogen Storage Project, an aggressive and innovative research program focused on materials R and D, will be launched in Fiscal Year 2005. An intensive effort is also underway in the private sector, both in the U.S. and abroad, to meet the challenging on-board hydrogen storage requirements. A historical perspective of hydrogen storage research and development will be provided and the current DOE technical targets for hydrogen storage systems will be discussed. The state-of-the-art in hydrogen storage will be summarized and recent progress assessed. Finally future research directions and areas of technical emphasis will be described. (author)

Advances in materials science, Metals and Ceramics Division. Triannual progress report, October 1979-January 1980

Energy Technology Data Exchange (ETDEWEB)

1980-03-31

Progress is summarized concerning magnetic fusion energy materials, laser fusion energy, aluminium-air battery and vehicle, geothermal research, oil-shale research, nuclear waste management, office of basic energy sciences research, and materials research notes. (FS)

A systematic assessment of the state of hazardous waste clean-up technologies. Quarterly technical progress report, April 1--June 30, 1993

Energy Technology Data Exchange (ETDEWEB)

Berg, M.T.; Reed, B.E.; Gabr, M.

1993-07-01

West Virginia University (WVU) and the US DOE Morgantown Energy Technology Center (METC) entered into a Cooperative Agreement on August 29, 1992 entitled ``Decontamination Systems Information and Research Programs.`` Stipulated within the Agreement is the requirement that WVU submit to METC a series of Technical Progress Report for Year 1 of the Agreement. This report reflects the progress and/or efforts performed on the following nine technical projects encompassed by the Year 1 Agreement for the period of April 1 through June 30, 1993: Systematic assessment of the state of hazardous waste clean-up technologies; site remediation technologies -- drain-enhanced soil flushing (DESF) for organic contaminants removal; site remediation technologies -- in situ bioremediation of organic contaminants; excavation systems for hazardous waste sites; chemical destruction of polychlorinated biphenyls; development of organic sensors -- monolayer and multilayer self-assembled films for chemical sensors; Winfield lock and dam remediation; Assessments of Technologies for hazardous waste site remediation -- non-treatment technologies and pilot scale test facility implementation; and remediation of hazardous sites with stream reforming.

Energy Materials Coordinating Committee (EMaCC) annual technical report, fiscal year 1984 with fiscal year 1985 data

Energy Technology Data Exchange (ETDEWEB)

None

1985-07-01

The Department of Energy funded about 374 million dollars of materials science and technology activities in both fiscal years 1984 and 1985. These funds and the commensurate program management responsibilities resided in 21 DOE program offices, each of which has its own mission and responsibilities. The Energy Materials Coordinating Committee (EMaCC) provides a formal mechanism to insure coordinated planning and maximum programmatic effectiveness for the Department's 374 million dollar per year materials effort. The EMaCC reports to the Director of the Office of Energy Research who in turn has oversight responsibilities for proper coordination of the technical programs of the Department. In carrying out this responsibility, EMaCC hosts meetings, organizes working groups, and publishes an annual technical report. This report is mandated by the EMaCC Terms of Reference. Its purpose is to disseminate information on the DOE materials programs for more effective coordination. It describes the materials research programs of various offices and divisions within the Department for FY 1984, contains funding information for FYs 1984 and 1985, and summarizes EMaCC activities for FY 1985.

Energy Materials Coordinating Committee (EMaCC) annual technical report, fiscal year 1984 with fiscal year 1985 data

International Nuclear Information System (INIS)

1985-07-01

The Department of Energy funded about 374 million dollars of materials science and technology activities in both fiscal years 1984 and 1985. These funds and the commensurate program management responsibilities resided in 21 DOE program offices, each of which has its own mission and responsibilities. The Energy Materials Coordinating Committee (EMaCC) provides a formal mechanism to insure coordinated planning and maximum programmatic effectiveness for the Department's 374 million dollar per year materials effort. The EMaCC reports to the Director of the Office of Energy Research who in turn has oversight responsibilities for proper coordination of the technical programs of the Department. In carrying out this responsibility, EMaCC hosts meetings, organizes working groups, and publishes an annual technical report. This report is mandated by the EMaCC Terms of Reference. Its purpose is to disseminate information on the DOE materials programs for more effective coordination. It describes the materials research programs of various offices and divisions within the Department for FY 1984, contains funding information for FYs 1984 and 1985, and summarizes EMaCC activities for FY 1985

Assessment of international reference materials for isotope-ratio analysis (IUPAC Technical Report)

Science.gov (United States)

Brand, Willi A.; Coplen, Tyler B.; Vogl, Jochen; Rosner, Martin; Prohaska, Thomas

2014-01-01

Since the early 1950s, the number of international measurement standards for anchoring stable isotope delta scales has mushroomed from 3 to more than 30, expanding to more than 25 chemical elements. With the development of new instrumentation, along with new and improved measurement procedures for studying naturally occurring isotopic abundance variations in natural and technical samples, the number of internationally distributed, secondary isotopic reference materials with a specified delta value has blossomed in the last six decades to more than 150 materials. More than half of these isotopic reference materials were produced for isotope-delta measurements of seven elements: H, Li, B, C, N, O, and S. The number of isotopic reference materials for other, heavier elements has grown considerably over the last decade. Nevertheless, even primary international measurement standards for isotope-delta measurements are still needed for some elements, including Mg, Fe, Te, Sb, Mo, and Ge. It is recommended that authors publish the delta values of internationally distributed, secondary isotopic reference materials that were used for anchoring their measurement results to the respective primary stable isotope scale.

Plutonium contaminated materials research programme. Progress Report for 1983/84 from the Plutonium Contaminated Materials Working Party

International Nuclear Information System (INIS)

Higson, S.G.

1984-01-01

Plutonium contaminated material (PCM) is a generic term applied to a wide variety of materials which have become contaminated by plutonium compounds, by virtue of their use inside the primary containment of fuel cycle plants, but which generally have low beta gamma content. The report falls under the headings: introduction; organisation and role of the PCMWP; management practices; 1983/84 progress report (a) reduction of arisings; (b) plutonium measurement; (c) treatment of solid PCM; (d) treatment of alpha bearing liquid wastes; (e) actinide chemistry; (f) engineering objectives. (U.K.)

Possible checking of technical parameters in nondestructive materials and products testing

International Nuclear Information System (INIS)

Kesl, J.

1987-01-01

The requirements are summed up for partial technical parameters of instruments and facilities for nondestructive testing by ultrasound, radiography, by magnetic, capillary and electric induction methods. The requirements and procedures for testing instrument performance are presented for the individual methods as listed in domestic and foreign standards, specifications and promotional literature. The parameters to be tested and the methods of testing, including the testing and calibration instruments are shown in tables. The Czechoslovak standards are listed currently valid for nondestructive materials testing. (M.D.)

INCREASING THE EFFICIENCY OF ENTERPRISES' MATERIAL AND TECHNICAL EQUIPMENT (in Russian

Directory of Open Access Journals (Sweden)

Victor NORDIN

2014-07-01

Full Text Available The article pointed out the desirability of use of the “process approach” to material and technical equipment of enterprise, which will link its processes and develop an effective management system. It is proposed a form of table (matrix to enter data into an electronic database. In addition, it is proposed to create a unified management system and a set of information about procurement activities with the efficiency assessment of the resource purchasing processes and their quality through comprehensive quality indicators.

Conceptual framework and technical basis for clearance of materials with residual radioactivity

International Nuclear Information System (INIS)

Chen, S.Y.

1997-01-01

The primary impediment to the release of materials containing residual radioactivity from a controlled environment is the lack of a suitable framework within which release standards can be developed. Recently, the 'risk-based' approach has been proposed as an appropriate means of setting standards. The term 'clearance' has been introduced by the International Atomic Energy Commission as a regulatory process for releasing radioactive materials posing trivial risks. A 'trivial' risk level has been determined to be on the order of 10[sup -6] to 10[sup -7] annual risk to an exposed individual, and a population risk of no more than 0.1 annually. Under these strict constraints, exposure scenarios may account for processing, disposal, and product end-use of materials. This paper discusses these scenarios and also describes the technical basis for deriving release levels under the suggested risk (or dose) constraints

GT-MHR COMMERCIALZATION STUDY. TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD MAY 1 THROUGH MAY 31, 2003

International Nuclear Information System (INIS)

SHENOY, A.S.

2003-01-01

A271 GT-MHR COMMERCIALZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD MAY 1 THROUGH MAY 31, 2003. Petten advised GA the start of the HFR-EU2 irradiation is being delayed until late July 2004. HFR-EU1 (pebble fuel) is also delayed until February/March 2004. The reason for the delays was implementation of new financial regulations at Petten that delayed the contracts for capsule fabrication. Review of the MHR-2 Fuel Product Specification was completed. Revision of the specification to incorporate the review results is in progress. Detailed test matrices have been drafted for capsule irradiation tests and for post-irradiation heating tests proposed for development and qualification of advanced coated-particle fuels capable of meeting anticipated VHTR fuel performance requirements

Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol 11, No. 1 through Vol. 16, No. 6

International Nuclear Information System (INIS)

Cottrell, W.B.; Klein, A.

1976-04-01

This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970) through Vol. 16, No. 6 (Nov.-Dec. 1975). Included in the index is a chronological list of articles (including abstract) followed by both a KWIC index and an Author Index. Nuclear Safety is a bimonthly technical progress review prepared by the Nuclear Safety Information Center and covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 300 technical articles in the last six years of publication

Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol 11, No. 1 through Vol. 16, No. 6

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W.B.; Klein, A.

1976-04-01

This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970) through Vol. 16, No. 6 (Nov.-Dec. 1975). Included in the index is a chronological list of articles (including abstract) followed by both a KWIC index and an Author Index. Nuclear Safety is a bimonthly technical progress review prepared by the Nuclear Safety Information Center and covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 300 technical articles in the last six years of publication.

Progress in the activities on prevention and combating of illicit trafficking of nuclear material in Lithuania

International Nuclear Information System (INIS)

Kurselis, S.; Stadalnikas, A.

2001-01-01

Full text: The paper gives a general overview of the progress which has been made in the activities on prevention and combating of illicit trafficking of nuclear material in Lithuania. It describes the measures which were taken to strengthen nuclear material accounting and control and physical protection. The current status of the national legislation and the functions of institutions involved in control of nuclear material and combating of illicit trafficking are discussed. Lithuania, similar to many countries, did not avoid a new type of a crime - smuggling of nuclear materials - which was observed in the 1990's. The most serious case in Lithuania happened in 1993 when fresh fuel assembly was stolen from Ignalina NPP. This assembly contains approximately 124 kg of UO 2 (enrichment 2%). 100 kg of the pellets from this assembly was found later in several pieces at different places. This case served as a strong stimulus to strengthen prevention measures of Illicit trafficking. The legal basis was created and governmental institutions were obliged with special duties related with nuclear material. The laws and regulations set the order for the shipment and handling of nuclear material. The penalties for violation of these laws and regulations specified in Penal Code and Administrative Code were made stricter. The State system of accounting for and control of nuclear material (SSAC) is a very important element in prevention of the illicit trafficking. The Regulations of Accounting for and Control of Nuclear Material at Nuclear Facilities and LOFs was issued by the State Nuclear Power Safety Inspectorate (VATESI) on 10 December 1997 following the provisions of the Law on Nuclear Energy. Lithuania extended its international obligations by ratifying the Protocol Additional to the Safeguards Agreement (entered into force on 5 July 2000). The fully computerized nuclear material accountancy system was created at Ignalina NPP. The system gives the possibility to find the

Recent progress in the development of anode materials for solid oxide fuel cells

Energy Technology Data Exchange (ETDEWEB)

Cowin, Peter I.; Petit, Christophe T.G.; Lan, Rong; Tao, Shanwen [Department of Chemical and Process Engineering, University of Strathclyde, Glasgow G1 1XJ (United Kingdom); Irvine, John T.S. [School of Chemistry, University of St Andrews, St Andrews, Fife KY16 9ST (United Kingdom)

2011-05-15

The field of research into solid oxide fuel cell (SOFC) anode materials has been rapidly moving forward. In the four years since the last in-depth review significant advancements have been made in the reduction of the operating temperature and improvement of the performance of SOFCs. This progress report examines the developments in the field and looks to draw conclusions and inspiration from this research. A brief introduction is given to the field, followed by an overview of the principal previous materials. A detailed analysis of the developments of the last 4 years is given using a selection of the available literature, concentrating on metal-fluorite cermets and perovskite-based materials. This is followed by a consideration of alternate fuels for use in SOFCs and their associated problems and a short discussion on the effect of synthesis method on anode performance. The concluding remarks compile the significant developments in the field along with a consideration of the promise of future research. The recent progress in the development of anode materials for SOFCs based on oxygen ion conducting electrolytes is reviewed. (Copyright copyright 2011 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

Transportation of nuclear material in France: regulatory and technical aspects

International Nuclear Information System (INIS)

Flory, D.; Renard, C.

1995-01-01

Legislative and regulatory documentation define responsibilities in the field of security and physical protection for transportation of nuclear material. Any transportation activity has to conform to an advance authorization regime delivered by the Ministry of Industry. Responsibility for physical protection of nuclear material rests with the carrier under control of the public authority. Penalties reinforce this administrative regime. Operational responsibility for management and control of transport operations has been entrusted by the ministry to the operational transport unit (Echelon Operationnel des Transports - EOT) of IPSN (Institute for Nuclear Protection and Safety). To guarantee en efficient protection of transport operations, the various following means are provided for: -specialized transport means; - devices for real time tracking of road vehicles; - administrative authorization and declaration procedures; -intervention capacities in case of sabotage... This set of technical means and administrative measures is completed by the existence of a body of inspectors who may control every step of the operations. (authors). 3 tabs

Intense neutron irradiation facility for fusion reactor materials

Energy Technology Data Exchange (ETDEWEB)

Noda, Kenji; Oyama, Yukio; Kato, Yoshio; Sugimoto, Masayoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1997-03-01

Technical R and D of d-Li stripping type neutron irradiation facilities for development of fusion reactor materials was carried out in Fusion Materials Irradiation Test Facility (FMIT) project and Energy Selective Neutron Irradiation Test Facility (ESNIT) program. Conceptual design activity (CDA) of International Fusion Materials Irradiation Facility (IFMIF), of which concept is an advanced version of FMIT and ESNIT concepts, are being performed. Progress of users` requirements and characteristics of irradiation fields in such neutron irradiation facilities, and outline of baseline conceptual design of IFMIF were described. (author)

Urology technical and non-technical skills development: the emerging role of simulation.

Science.gov (United States)

Rashid, Prem; Gianduzzo, Troy R J

2016-04-01

To review the emerging role of technical and non-technical simulation in urological education and training. A review was conducted to examine the current role of simulation in urology training. A PUBMED search of the terms 'urology training', 'urology simulation' and 'urology education' revealed 11,504 titles. Three hundred and fifty-seven abstracts were identified as English language, peer reviewed papers pertaining to the role of simulation in urology and related topics. Key papers were used to explore themes. Some cross-referenced papers were also included. There is an ongoing need to ensure that training time is efficiently utilised while ensuring that optimal technical and non-technical skills are achieved. Changing working conditions and the need to minimise patient harm by inadvertent errors must be taken into account. Simulation models for specific technical aspects have been the mainstay of graduated step-wise low and high fidelity training. Whole scenario environments as well as non-technical aspects can be slowly incorporated into the curriculum. Doing so should also help define what have been challenging competencies to teach and evaluate. Dedicated time, resources and trainer up-skilling are important. Concurrent studies are needed to help evaluate the effectiveness of introducing step-wise simulation for technical and non-technical competencies. Simulation based learning remains the best avenue of progressing surgical education. Technical and non-technical simulation could be used in the selection process. There are good economic, logistic and safety reasons to pursue the process of ongoing development of simulation co-curricula. While the role of simulation is assured, its progress will depend on a structured program that takes advantage of what can be delivered via this medium. Overall, simulation can be developed further for urological training programs to encompass technical and non-technical skill development at all stages, including

Power systems development facility. Quarterly technical progress report, January 1, 1994--March 31, 1994

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

This quarterly technical progress report summarizes work completed during the last quarter of the Second Budget Period, January 1 through March 31, 1994, entitled {open_quotes}Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion.{close_quotes} The objective of this project is to evaluate hot gas particulate control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size.

Association Euratom - DTU, Technical University of Denmark, Department of Physics - Annual Progress Report 2012

DEFF Research Database (Denmark)

The programme of the Research Unit of the Fusion Association Euratom – DTU, Technical University of Denmark covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium...... and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. Within fusion technology there are activities on fusion materials research (Tungsten and ODSFS). Other activities are system analysis...

Association Euratom - DTU, Technical University of Denmark, Department of Physics - Annual Progress Report 2013

DEFF Research Database (Denmark)

The programme of the Research Unit of the Fusion Association Euratom – DTU, Technical University of Denmark covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium...... and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. Within fusion technology there are activities on fusion materials research (Tungsten and ODSFS). Other activities are system analysis...

Progress in the U.S. program to develop low-activation structural materials for fusion

International Nuclear Information System (INIS)

Kurtz, R.J.; Jones, R.H.; Bloom, E.E.; Rowcliffe, A.F.; Smith, D.L.; Odette, G.R.; Wiffen, F.W.

2001-01-01

It has long been recognized that attainment of the safety and environmental potential of fusion energy requires the successful development of low-activation materials for the first wall, blanket and other high heat flux structural components. Only a limited number of materials potentially possess the physical, mechanical and low-activation characteristics required for this application. The current U.S. structural materials research effort is focused on three candidate materials: advanced ferritic steels, vanadium alloys, and silicon carbide composites. Recent progress has been made in understanding the response of these materials to neutron irradiation. (author)

Medical Laboratory Technician--Microbiology, 10-3. Military Curriculum Materials for Vocational and Technical Education.

Science.gov (United States)

Ohio State Univ., Columbus. National Center for Research in Vocational Education.

This course, the second of three courses in the medical laboratory technician field adapted from military curriculum materials for use in vocational and technical education, was designed as a refresher course for student self-study and evaluation. It is suitable for use by advanced students or beginning students participating in a supervised…

Research status on radiation damage in nuclear materials and recommendations for IAEA activities. Technical report

International Nuclear Information System (INIS)

Caro, Alfredo; Caro, Magdalena

2002-03-01

This report addresses the synergy between the continuous progress of parallel computing and the spectacular advances in the theoretical framework that describes materials. Together, they contributed to significantly advance our comprehension of materials properties like mechanical behavior. It also highlights its impact on nuclear technology, as it provides physical insight into the complex processes responsible for the degradation of structural materials under neutron irradiation

Superconducting fault current limiter. Fifth quarterly technical progress report, August 8, 1978-November 7, 1979

Energy Technology Data Exchange (ETDEWEB)

1979-01-01

Progress in the development of fault current limiters for superconducting power transmission systems is reported. The analysis and design of a magnetically switched resistive device and the experimental program were emphasized and reported. A transient heat transfer model was developed which indicates the parameters which are important in determining the thermal heating and recovery of the superconduting film. Designs for the switching coil and the S/C element were also carried out and are reported. A four-pole magnetic coil is recommended; this generates a magnetic field which is nearly perpendicular to spiral or helical S/C film geometrics. A spirally-designed, 3000 ohm limiter is shown to be able to fit within a .5 to 1m inner radius, .05 to .03 m wide, 1.3 to 3.9 m long annualr region. The experimental program has included work on materials development and on prepartion of the switching and thermal recovery experimental facility. The material development program has uncovered several serious short-comings of NbN as the S/C film material. Macroscopic holes and surface debris, and microscopic imperfections reduce the critical current density below the expected value and, in addition, cause nonuniform switching. Reasons for these effects are postulated, and a continuing, vigorous materials program is suggested in hopes of alleviating these problems. Virtually all of the experimental equipment had been installed, and so the magnetic switching and thermal recovery experiments can begin and progress during the next quarter. (LCL)

48 CFR 742.1170-4 - Progress reporting requirements and contract clause.

Science.gov (United States)

2010-10-01

... progress. (b) Because the cognizant technical officer is the individual most familiar with the contractor's performance, the contractor must submit the progress reports directly to the cognizant technical officer. The cognizant technical officer must review the reports and advise the contracting officer, in writing, of any...

Progress report for 1986 from the Plutonium Contaminated Materials Working Party

International Nuclear Information System (INIS)

Higson, S.G.

1987-11-01

The paper covers progress during 1986 under the joint BNFL/MOD/DoE funded PCM Working Party studying the management, treatment and immobilization of plutonium contaminated materials. Development is reported under each of seven main programme headings including reduction of arisings, Pu measurement, decommissioning and non-combustible PCM treatment, liquid effluent treatment, sorting and packaging, PCM immobilisation and engineering objectives. (author)

Materials Down Select Decisions Made Within the Department of Energy Hydrogen Sorption Center of Excellence

Energy Technology Data Exchange (ETDEWEB)

Simpson, Lin [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2009-11-30

Technical report describing DOE's Hydrogen Sorption Center of Excellence investigation into various adsorbent and chemisorption materials and progress towards meeting DOE's hydrogen storage targets. The report presents a review of the material status as related to DOE hydrogen storage targets and explains the basis for the down select decisions.

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

Science.gov (United States)

Rieth, M.; Dudarev, S. L.; Gonzalez de Vicente, S. M.; Aktaa, J.; Ahlgren, T.; Antusch, S.; Armstrong, D. E. J.; Balden, M.; Baluc, N.; Barthe, M.-F.; Basuki, W. W.; Battabyal, M.; Becquart, C. S.; Blagoeva, D.; Boldyryeva, H.; Brinkmann, J.; Celino, M.; Ciupinski, L.; Correia, J. B.; De Backer, A.; Domain, C.; Gaganidze, E.; García-Rosales, C.; Gibson, J.; Gilbert, M. R.; Giusepponi, S.; Gludovatz, B.; Greuner, H.; Heinola, K.; Höschen, T.; Hoffmann, A.; Holstein, N.; Koch, F.; Krauss, W.; Li, H.; Lindig, S.; Linke, J.; Linsmeier, Ch.; López-Ruiz, P.; Maier, H.; Matejicek, J.; Mishra, T. P.; Muhammed, M.; Muñoz, A.; Muzyk, M.; Nordlund, K.; Nguyen-Manh, D.; Opschoor, J.; Ordás, N.; Palacios, T.; Pintsuk, G.; Pippan, R.; Reiser, J.; Riesch, J.; Roberts, S. G.; Romaner, L.; Rosiński, M.; Sanchez, M.; Schulmeyer, W.; Traxler, H.; Ureña, A.; van der Laan, J. G.; Veleva, L.; Wahlberg, S.; Walter, M.; Weber, T.; Weitkamp, T.; Wurster, S.; Yar, M. A.; You, J. H.; Zivelonghi, A.

2013-01-01

The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based on assumptions about the availability of materials with extreme mechanical, heat, and neutron load capacity. In Europe, the development of such structural and armour materials together with the necessary production, machining, and fabrication technologies is pursued within the EFDA long-term fusion materials programme. This paper reviews the progress of work within the programme in the area of tungsten and tungsten alloys. Results, conclusions, and future projections are summarized for each of the programme's main subtopics, which are: (1) fabrication, (2) structural W materials, (3) W armour materials, and (4) materials science and modelling. It gives a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

International Nuclear Information System (INIS)

Rieth, M.; Dudarev, S.L.; Gonzalez de Vicente, S.M.; Aktaa, J.; Ahlgren, T.; Antusch, S.; Armstrong, D.E.J.; Balden, M.; Baluc, N.; Barthe, M.-F.; Basuki, W.W.; Battabyal, M.; Becquart, C.S.; Blagoeva, D.; Boldyryeva, H.

2013-01-01

The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based on assumptions about the availability of materials with extreme mechanical, heat, and neutron load capacity. In Europe, the development of such structural and armour materials together with the necessary production, machining, and fabrication technologies is pursued within the EFDA long-term fusion materials programme. This paper reviews the progress of work within the programme in the area of tungsten and tungsten alloys. Results, conclusions, and future projections are summarized for each of the programme’s main subtopics, which are: (1) fabrication, (2) structural W materials, (3) W armour materials, and (4) materials science and modelling. It gives a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.

Technical critique on radiation test facilities for the CTR surface and materials program

International Nuclear Information System (INIS)

Persiani, P.J.

1975-02-01

Major radiation test facilities will be necessary in the near-term (5 years) and long-term (greater than 10 years) future for the timely development and understanding of fusion confinement systems and of prototype fusion power reactors. The study includes the technical justifications and requirements for CTR Neutron and Plasma Radiation Test Facilities. The initial technical critique covers the feasibility and design problems: in upgrading the performance of the accelerator-rotating (solid TiT) target systems, and in transforming the accelerator-supersonic jet target concept into a radiation testing facility. A scoping assessment on the potential of a pulsed high-beta plasma device (dense plasma focus) is introduced to explore plasma concepts as near-term neutron and plasma radiation sources for the CTR Surface and Materials Program. (U.S.)

Nuclear structure theory. Annual technical progress report, July 1, 1975--September 30, 1976

International Nuclear Information System (INIS)

French, J.B.; Koltun, D.S.

1976-01-01

This report summarizes progress during the past year in the following areas of nuclear structure and reaction theory: Meson interactions with nucleons and nuclei, including elastic and inelastic scattering of pions, three-body theories of scattering and absorption of pions by deuterons, π-p bremsstrahlung, and multiple-excitation models for meson absorption by heavier nuclei. Studies of the inverse scattering problem including 1 S 0 nucleon-nucleon scattering; the relativistic two-body problem, particularly for relativistic effects at low energies: the unitary-pole expansion in nucleon-nucleon scattering with hard-core interactions. Statistical spectroscopy including: strength distributions and sum rules(both energy weighted and inverse energy weighted) for nuclear excitations; fluctuations and correlations in spectra, strengths and expectation values; studies of Garvey-Kelson and similar mass relationships; spectroscopy in huge spaces including spectral methods for renormalization of the interaction and for using (two + three)-body Skyrme interactions; technical aspects of operator averaging

Improvement of technical purpose materials performance characteristics with the radio frequency low pressure plasma

Science.gov (United States)

Makhotkina, L. Yu; Khristoliubova, V. I.

2017-11-01

The main aim of the work is to solve the actual problem of increasing the competitiveness of tanning products by reducing the prime cost and improving the quality of finished products due to the increased durability of the working elements of tanneries. The impact of the low pressure radio frequency (RF) plasma in the processes of treating for modification of the materials for special purposes is considered in the article. The results of working elements of tanneries and the materials for special purposes sample processing by a RF low pressure plasma are described. As a result of leather materials nano structuring and nano modifying physical, mechanical and hygienic characteristics were increased. Processing of the technical purpose materials allows to increase operational performance of products and extend their lifespan.

The progress of the electrode materials development for lithium ion battery

International Nuclear Information System (INIS)

Kang Kai; Dai Shouhui; Wan Yuhua

2001-01-01

The structure and the charge-discharge principle of Li-ion battery are briefly discussed; the progress of electrode materials for Li-ion battery is reviewed in detail. Graphite has found wide applications in commercial Li-ion batteries, however, the hard carbon, especially the carbon with hydrogen is the most promising anode material for Li-ion battery owing to its high capacity, which has now become hot spot of investigation. Following the LiCoO 2 , LiMn 2 O 4 spinel compound becomes the most powerful contestant. On the basis of the authors' results, the synthesis methods of LiMn 2 O 4 and its characterizations are compared. Moreover, the structural properties of intercalation electrode materials that are related to the rechargeable capacity and stability during cycling of lithium ions are also discussed

Technical progress review of extraction of uranium from fly ash

International Nuclear Information System (INIS)

Gao Renxi; Gao Junning; Wu Qingming; Chen Gang; Wan Hongjin; Zhang Ziyue

2014-01-01

The increasing of fly ash in coal-fired power plants at home and abroad year by year and the potential impacts to the environment attracted media attention. Although the extraction of uranium from the fly ash in coal-fired power plants had optional process from technique aspect and sufficient preliminary researches, but considering the low grade of the uranium in fly ash and particularity of the mineral composition, it is easy to have a high cost of extraction. As a consequence, it is not included in the development plan of uranium mining and metallurgy. The present applications of fly ash are only building materials, building roads and pit valley backfill, the resource utilization rate was low and was still in its early stages of development and application. In view of this, the research advances and the latest development trends of extraction of uranium from fly ash at home and abroad were introduced from the technical aspect, and the beneficial analyzes of the prospect and advices to this industry were given. (authors)

IAEA technical meeting on fissile material strategies for sustainable nuclear energy

International Nuclear Information System (INIS)

Ganguly, Chaitanyamoy; Koyama, Kazutoshi

2005-01-01

A Technical Meeting (TM) on 'Fissile Material Management Strategies for Sustainable Nuclear Energy' was organized by the International Atomic Energy Agency (IAEA) in Vienna from 12 to 15 September 2005. Prior to the TM, three Working Groups (WG) composed of experts from 10 countries prepared Key Issues papers on: 1) Uranium Demand and Supply through 2050; 2) Back-end Fuel Cycle Options; and 3) Sustainable Nuclear Energy beyond 2050: Cross-cutting Issues. Some 36 papers, including 3 key issue papers, were presented during the TM in 3 different sessions. The present paper summarizes the deliberations of the TM. (author)

Cladding and structural materials. Semi-annual progress report, July 1975--January 1976

International Nuclear Information System (INIS)

Claudson, T.T.

1976-04-01

Progress on experimental programs and evaluation of results is given for radiation damage studies to LMFBR cladding and structural materials. The primary material being studied is 316 SS in various conditions of cold work and in the welded condition. Tensile, creep, and swelling property data on unirradiated and irradiated 316 SS cladding and duct specimens at various test conditions are provided. The importance of stress on the properties of 316 SS is highlighted. Results on core dosimetry and damage analysis indicate the increasing value of detailed core characterization. 105 figures, 21 tables

Conceptualising Digital Materiality and its Socio-Technical Implications through the Phenomenon of Crowdsourcing

Directory of Open Access Journals (Sweden)

Patricia Morizio

2014-10-01

Full Text Available Digital materiality is a relatively new concept in the information systems literature that attempts to give “substance” to, or explain the material properties of, digital artefacts. These artefacts, such as software programs, are challenging our traditional assumptions of what is “materiality”. Crowdsourcing or the aggregation of publicly-reported data for a variety of purposes – from tracking instances of violence within a geographic area, to coordinating information for aid agencies working in humanitarian emergency situations – is an example technology that transcends the line of a purely physical or digital object. This paper will briefly touch on the definition of digital materiality within IS thought, followed by a discussion of how crowdsourcing fits into its conceptualisation, namely in terms of its characteristics and organisational consequences. The purpose is to instantiate the more theoretical notion of digital materiality through a tangible technology with far-reaching socio-technical implications.

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

Energy Technology Data Exchange (ETDEWEB)

Rieth, M., E-mail: Michael.rieth@kit.edu [Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe (Germany); Dudarev, S.L. [EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Gonzalez de Vicente, S.M. [EFDA-Close Support Unit, Garching (Germany); Aktaa, J. [Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe (Germany); Ahlgren, T. [University of Helsinki, Department of Physics, Helsinki (Finland); Antusch, S. [Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe (Germany); Armstrong, D.E.J. [Department of Materials, University of Oxford (United Kingdom); Balden, M. [Max-Planck-Institut fuer Plasmaphysik, EURATOM Association, Garching (Germany); Baluc, N. [Centre de Recherches en Physique des Plasmas, CRPP EPFL - Materials, 5232 Villigen/PSI (Switzerland); Barthe, M.-F. [CNRS, UPR3079 CEMHTI, 1D Avenue, de la Recherche Scientifique, 45071 Orleans cedex 2 (France); Universite d' Orleans, Polytech ou Faculte des Sciences, Avenue du Parc Floral, BP 6749, 45067 Orleans cedex 2 (France); Basuki, W.W. [Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe (Germany); Battabyal, M. [Centre de Recherches en Physique des Plasmas, CRPP EPFL - Materials, 5232 Villigen/PSI (Switzerland); Becquart, C.S. [Unite Materiaux et Transformations, UMR 8207, 59655 Villeneuve d' Ascq (France); Blagoeva, D. [NRG, Nuclear Research and consultancy Group, Petten (Netherlands); Boldyryeva, H. [Institute of Plasma Physics, Za Slovankou 3, 18200 Praha (Czech Republic); and others

2013-01-15

The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based on assumptions about the availability of materials with extreme mechanical, heat, and neutron load capacity. In Europe, the development of such structural and armour materials together with the necessary production, machining, and fabrication technologies is pursued within the EFDA long-term fusion materials programme. This paper reviews the progress of work within the programme in the area of tungsten and tungsten alloys. Results, conclusions, and future projections are summarized for each of the programme's main subtopics, which are: (1) fabrication, (2) structural W materials, (3) W armour materials, and (4) materials science and modelling. It gives a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.

Core Capabilities and Technical Enhancement -- FY-98 Annual Report

Energy Technology Data Exchange (ETDEWEB)

Miller, David Lynn

1999-04-01

The Core Capability and Technical Enhancement (CC&TE) Program, a part of the Verification, Validation, and Engineering Assessment Program, was implemented to enhance and augment the technical capabilities of the Idaho National Engineering and Environmental Laboratory (INEEL). The purpose for strengthening the technical capabilities of the INEEL is to provide the technical base to serve effectively as the Environmental Management Laboratory for the Office of Environmental Management (EM). An analysis of EM's science and technology needs as well as the technology investments currently being made by EM across the complex was used to formulate a portfolio of research activities designed to address EM's needs without overlapping work being done elsewhere. An additional purpose is to enhance and maintain the technical capabilities and research infrastructure at the INEEL. This is a progress report for fiscal year 1998 for the five CC&TE research investment areas: (a) transport aspects of selective mass transport agents, (b) chemistry of environmental surfaces, (c) materials dynamics, (d) characterization science, and (e) computational simulation of mechanical and chemical systems. In addition to the five purely technical research areas, this report deals with the science and technology foundations element of the CC&TE from the standpoint of program management and complex-wide issues. This report also provides details of ongoing and future work in all six areas.

Core capabilities and technical enhancement, FY-98 annual report

Energy Technology Data Exchange (ETDEWEB)

Miller, D.L.

1999-04-01

The Core Capability and Technical Enhancement (CCTE) Program, a part of the Verification, Validation, and Engineering Assessment Program, was implemented to enhance and augment the technical capabilities of the Idaho National Engineering and Environmental Laboratory (INEEL). The purpose for strengthening the technical capabilities of the INEEL is to provide the technical base to serve effectively as the Environmental Management Laboratory for the Department of Energy's Office of Environmental Management (EM). An analysis of EM's science and technology needs as well as the technology investments currently being made by EM across the complex was used to formulate a portfolio of research activities designed to address EM's needs without overlapping work being done elsewhere. An additional purpose is to enhance and maintain the technical capabilities and research infrastructure at the INEEL. This is a progress report for fiscal year 1998 for the five CCTE research investment areas: (a) transport aspects of selective mass transport agents, (b) chemistry of environmental surfaces, (c) materials dynamics, (d) characterization science, and (e) computational simulation of mechanical and chemical systems. In addition to the five purely technical research areas, this report deals with the science and technology foundations element of the CCTE from the standpoint of program management and complex-wide issues. This report also provides details of ongoing and future work in all six areas.

Nuclear waste glass melter: an update of technical progress

International Nuclear Information System (INIS)

Brouns, R.A.; Hanson, M.S.

1984-08-01

The direct slurry-fed ceramic-lined melter is currently the reference US process for treating defense and civilian high-level liquid waste. Extensive nonradioactive pilot-scale testing at Pacific Northwest Laboratory (PNL) and Savannah River Laboratory has proven the process, defined operating parameters, and identified successful equipment design concepts. Programs at PNL continue to support several of the planned US vitrification plants through preparation of equipment designs and flowsheet testing. Current emphasis is on remotization of equipment, radioactive verification testing, and resolution of remaining technical issues. Development of this technology, technical status, and planned development activities are discussed. 9 references, 4 figures

Measurement of residual stress in materials using neutrons. Proceedings of a technical meeting

International Nuclear Information System (INIS)

2005-06-01

One of the objectives of the IAEA's project on effective utilization of research reactors is to promote the use of the existing research reactors based on their capabilities and is implemented through workshops and technical meetings. Measurement of residual stress is one of the techniques that find wide applications in materials development and testing. The Technical Meeting on Measurement of Residual Stress Using Neutrons was organized to meet this objective. This publication is the outcome of the deliberations during the meeting and the presentations by the participants and is addressed to the research reactor managers, users and designers of facilities for reactor utilization. It will especially benefit those seeking to develop new facilities or upgrade the existing ones to enhance the utilization of their research reactors. Experts with a long experience in developing and using neutron beam instruments in high flux and medium flux research reactors participated in this technical meeting. They presented the design, development and utilization of the facilities at their respective centres and reviewed the current status of the residual stress measurements using neutron beams from research reactors. The sessions included brainstorming on the methodology and data analysis, characterization and standardization of the equipment and identifying the scope for further development. This publication refers to the determination of residual and/or applied stresses in polycrystalline materials using neutron diffraction technique. Stress is developed during the synthesis and use of materials such as alloys and compounds. Measurement of residual stress is essential to improve the quality of synthesized materials and diagnosis of failure and/or reliability of fabricated components. Neutron scattering has played an important role in studying structure and dynamics of condensed matter. Neutron scattering is a non-destructive technique and is useful for testing large samples. The

Progress in materials research and applications of high-Tc Superconductors

International Nuclear Information System (INIS)

Tanaka, S.

1991-01-01

Research on high-T c superconductivity covers most of the fields of materials science, and therefore, interdisciplinary investigations are necessary by scientists with diverse backgrounds in physics, chemistry, ceramics, metallurgy and so on. At present, after much research on the physical properties of materials, the creation of a theory of high-T c superconductivity is extremely urgent. If a theory can be successfully established, its effects must be very wide and deep. solid state physics may be transformed, and the search for new superconducting materials will be accelerated. Furthermore, many applications will be greatly advanced by understanding the phenomena of high-T c materials, and especially concepts for new electronic devices may be forthcoming. In the past, interactions between science and technology have been very clear. They sometimes resonate with each other and exhibit rapid progress in a very short period and give a big impact on society. The research and developments of high-T c superconductivity will hopefully retrace the brilliant history of the great success of the science and technology of semiconductors in the near future. The author is very optimistic about this

Science of materials. Progress report, July 1, 1977--June 30, 1978

Energy Technology Data Exchange (ETDEWEB)

1978-04-01

Progress is reported in research which includes studies of the deformation, stress corrosion and fracture of alloys and geologic materials with emphasis on hydrogen embrittlement of metals; the mechanism of heat transfer across interfaces; catalytic properties of surfaces; and erosion of surfaces by fluid suspended particles. The structure of liquids, polymers and disordered solids is under investigation with emphasis on ionic conduction, phase transitions and radiation damage. Ferro- and pyroelectric materials with potential for solar energy applications are under development. The study of optical properties includes the mechanism of luminescence and new semiconductor materials for photovoltaic devices. The electronic properties of crystals are the subject of a continued effort to resolve current problems of magnetic behavior and photon-solid interactions. Specific quantum properties of matter are explored with emphasis on superconductivity, diffusion of hydrogen in metals and the properties of solid helium.

48 CFR 2052.211-70 - Preparation of technical reports.

Science.gov (United States)

2010-10-01

....211-70 Preparation of technical reports. As prescribed at 2011.104-70(a), the contracting officer... Reports (JAN 1993) All technical reports required by Section C and all Technical Progress Reports required... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Preparation of technical...

The challenge of the future. Technical progress and ecological perspectives

International Nuclear Information System (INIS)

Jischa, M.F.

1993-01-01

The book introduces readers into the interrelated global problems population dynamics, energy supply, imminent climate catastrophe, environmetal pollution, finite resources and the conflict between the North and South. It encourages probing more deeply into the technical challenges of the future. The author demonstrates why economic and technical issues will soon be outstripped by questions of the environmental, human and social compatibility of new technologies. (orig./UA) [de

Technical criteria for terminating or reducing domestic safeguards on low-grade special nuclear material

International Nuclear Information System (INIS)

Crawford, D.W.

1996-01-01

A graded table for terminating or reducing domestic safeguards has been developed for use by programs and facilities within the Department of Energy in decisions regarding the need for or levels of protection of low-grade nuclear materials. Contained in this table are technical criteria which can allow for complete removal of safeguards over many special nuclear material forms and concentrations of typical low-grade materials either currently located at generating or processing sites and materials which may arise from processing operations related to stabilization and disposition activities. In addition, these criteria include higher concentration levels which may warrant maintaining some level of (albeit reduced) security on low-grade materials while allowing reductions in materials control and accountability requirements. These reductions can range from complete removal of these materials from materials control and accountability requirements such as measurements, physical inventories and recordkeeping, to deferring these measurements and physical inventories until a time that either the material is removed from the site or resubmitted for processing. It is important to note that other conditions contained in current Departmental safeguards and security policy be met prior to safeguards termination or reduction

Association Euratom - Risoe National Laboratory, Technical Univ. of Denmark. Annual progress report 2007

Energy Technology Data Exchange (ETDEWEB)

Michelsen, P.K.; Korsholm, S.B.; Rasmussen, J.J. (eds.)

2008-04-15

The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. The activities in technology on investigations of radiation damage of fusion reactor materials have been phased out during 2007. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2007. (Author)

Association Euratom - Risoe National Laboratory, Technical Univ. of Denmark. Annual progress report 2007

International Nuclear Information System (INIS)

Michelsen, P.K.; Korsholm, S.B.; Rasmussen, J.J.

2008-04-01

The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. The activities in technology on investigations of radiation damage of fusion reactor materials have been phased out during 2007. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2007. (Author)

Feasibility study of electric motors constructed with high temperature superconducting materials

International Nuclear Information System (INIS)

Jordan, H.E.

1989-01-01

The potential application of high temperature superconducting (HTSC) materials to electric motors is discussed. The specific application area of motors in electric power generating stations has been selected and a feasible study has been initiated on the use of HTSC materials in the design of motors for this application. A progress report on this feasibility study is presented. Technical challenges in both the development of HTSC wire and the design of a motor to utilize this wire are discussed. Finally, the results of design calculations comparing a superconducting motor with one of conventional design are presented assuming that success can be achieved in overcoming the technical problems which must be resolved to produce a high performance HTSC wire

Synthesis and Characterization of High Aluminum Zeolite X from Technical Grade Materials

Directory of Open Access Journals (Sweden)

Seyed Kamal Masoudian

2013-06-01

Full Text Available Zeolites are widely used as ion exchangers, adsorbents, separation materials and catalyst due to their well-tailored and highly-reproducible structures; therefore, the synthesis of zeolite from low grade resources can be interested. In the present work, high aluminum zeolite X was prepared from mixing technical grade sodium aluminate and sodium silicate solutions at temperatures between 70°C and 100°C. The synthesized zeolite X was characterized by SEM and X-ray methods according to ASTM standard procedures. The results showed that aging of the synthesis medium at the room temperature considerably increased the selectivity of zeolite X formation. On the other hand, high temperature of reaction mixture during crystallization formed zeolite A in the product; therefore, it decreased the purity of zeolite X. In addition, it was found that increasing H2O/Na2O and decreasing Na2O/SiO2 molar ratios in the reaction mixture resulted product with higher purity. © 2013 BCREC UNDIP. All rights reservedReceived: 7th January 2013; Revised: 7th April 2013; Accepted: 19th April 2013[How to Cite: Masoudian, S. K., Sadighi, S., Abbasi, A. (2013. Synthesis and Characterization of High Alu-minum Zeolite X from Technical Grade Materials. Bulletin of Chemical Reaction Engineering & Catalysis, 8 (1: 54-60. (doi:10.9767/bcrec.8.1.4321.54-60][Permalink/DOI: http://dx.doi.org/10.9767/bcrec.8.1.4321.54-60] | View in  |

Energy Frontier Research Center, Center for Materials Science of Nuclear Fuels

Energy Technology Data Exchange (ETDEWEB)

Todd R. Allen

2011-12-01

This is a document required by Basic Energy Sciences as part of a mid-term review, in the third year of the five-year award period and is intended to provide a critical assessment of the Center for Materials Science of Nuclear Fuels (strategic vision, scientific plans and progress, and technical accomplishments).

Radiation effects on structural materials. Technical progress report, January 1, 1984-June 30, 1984

International Nuclear Information System (INIS)

Ghoneim, N.M.

1984-01-01

By a generalization of an analysis due to Frank of the growing precipitate, we derive an analytic sink strength for the growing void that takes account of the void surface motion in a self-consistent fashion. The lower mobility of the vacancies compared to the interstitials ensures that a growing void captures more vacancies than the usual quasi-static void. The various consequences of this void bias for vacancies are discussed in relation to the swelling of reactor materials

Progress on first-principles-based materials design for hydrogen storage.

Science.gov (United States)

Park, Noejung; Choi, Keunsu; Hwang, Jeongwoon; Kim, Dong Wook; Kim, Dong Ok; Ihm, Jisoon

2012-12-04

This article briefly summarizes the research activities in the field of hydrogen storage in sorbent materials and reports our recent works and future directions for the design of such materials. Distinct features of sorption-based hydrogen storage methods are described compared with metal hydrides and complex chemical hydrides. We classify the studies of hydrogen sorbent materials in terms of two key technical issues: (i) constructing stable framework structures with high porosity, and (ii) increasing the binding affinity of hydrogen molecules to surfaces beyond the usual van der Waals interaction. The recent development of reticular chemistry is summarized as a means for addressing the first issue. Theoretical studies focus mainly on the second issue and can be grouped into three classes according to the underlying interaction mechanism: electrostatic interactions based on alkaline cations, Kubas interactions with open transition metals, and orbital interactions involving Ca and other nontransitional metals. Hierarchical computational methods to enable the theoretical predictions are explained, from ab initio studies to molecular dynamics simulations using force field parameters. We also discuss the actual delivery amount of stored hydrogen, which depends on the charging and discharging conditions. The usefulness and practical significance of the hydrogen spillover mechanism in increasing the storage capacity are presented as well.

Federal assistance program. Quarterly project progress report, January 1998--March 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-04-01

This report summarizes geothermal technical assistance, R&D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the second quarter of FY-98-98 (January-March, 1998). It describes 268 contacts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with include requests for general information including maps and material for high school debates, and material on geothermal heat pumps, resource and well data, spacing heating and cooling, greenhouses, aquaculture, equipment, district heating, resorts and spas, industrial applications, electric power and snow melting. Research activities include work on model construction specifications for line shaft submersible pumps and plate heat exchangers and a comprehensive aquaculture developer package. The revised Geothermal Direct Use Engineering and Design Guidebooks was completed, published and is available for distribution. Outreach activities include the publication of the Quarterly Bulletin (Vol. 19, No. 1) which was devoted entirely to geothermal equipment, dissemination of information mainly through mailings of publications, tours of local geothermal uses, geothermal library acquisitions and use, participation in workshops, short courses and technical meetings by the staff, and progress monitor reports on geothermal activities.

Periodic progress report, 6 months

DEFF Research Database (Denmark)

Juhl, Thomas Winther; Nielsen, Jakob Skov

This is the first progress report of the BriteEuram project named "High Power Laser Cutting for Heavy Industry" ("Powercut"). The report contains a summary of the objectives of the first period, an overview of the technical progress, a comparison between the planed and the accomplished work...

Decomposing productivity growth allowing efficiency gains and price-induced technical progress

NARCIS (Netherlands)

Oude Lansink, A.G.J.M.; Silva, E.; Stefanou, S.

2000-01-01

Time- and firm-specific output technical efficiency measures are generated within a price-induced technological change framework. The firm-specific production frontier incorporates past prices as an argument encouraging innovation and a time trend to account for exogenous technical change. The

Materials of 3. scientific-technical seminar: Materials Investigation for Power Industry; Materialy 3. seminarium naukowo-technicznego: Badania Materialowe na Potrzeby Elektrowni i Przemyslu Energetycznego

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

The report is an assembly of the papers concerning material problems during the exploitation of power stations as well as during construction and exploitation of gas pipelines. The accreditation problems according to the European Standards and Office of Technical Inspection prescription are also discussed.

[Fortieth Annual] Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

International Nuclear Information System (INIS)

2008-01-01

The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 39th TWG-FR Annual Meeting, including the status of the actions; - Consider meeting arrangements for 2007, 2008 and 2009; - Review the Agency’s ongoing information exchange and co-ordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations; - Discuss future joint activities in view of the Agency’s Programme and Budget Cycle 2008–2009 (and beyond)

Exploiting Novel Radiation-Induced Electromagnetic Material Changes for Remote Detection and Monitoring: Final Progress Report

Science.gov (United States)

2016-04-01

Exploiting Novel Radiation -Induced Electromagnetic Material Changes for Remote Detection and Monitoring: Final Progress Report Distribution...assess the effects of ionizing radiation on at least three classes of electromagnetic materials. The proposed approach for radiation detection was...that was desired to be monitored remotely. Microwave or low millimeter wave electromagnetic radiation would be used to interrogate the device

Materials research at CMAM

International Nuclear Information System (INIS)

Zucchiatti, Alessandro

2013-01-01

The Centro de Micro Analisis de Materiales (CMAM) is a research centre of the Universidad Autónoma de Madrid dedicated to the modification and analysis of materials using ion beam techniques. The infrastructure, based on a HVEE 5MV tandem accelerator, provided with a coaxial Cockcroft Walton charging system, is fully open to research groups of the UAM, to other public research institutions and to private enterprises. The CMAM research covers a few important lines such as advanced materials, surface science, biomedical materials, cultural heritage, materials for energy production. The Centre gives as well support to university teaching and technical training. A detail description of the research infrastructures and their use statistics will be given. Some of the main research results will be presented to show the progress of research in the Centre in the past few years and to motivate the strategic plans for the forthcoming

Materials research at CMAM

Science.gov (United States)

Zucchiatti, Alessandro

2013-07-01

The Centro de Micro Analisis de Materiales (CMAM) is a research centre of the Universidad Autónoma de Madrid dedicated to the modification and analysis of materials using ion beam techniques. The infrastructure, based on a HVEE 5MV tandem accelerator, provided with a coaxial Cockcroft Walton charging system, is fully open to research groups of the UAM, to other public research institutions and to private enterprises. The CMAM research covers a few important lines such as advanced materials, surface science, biomedical materials, cultural heritage, materials for energy production. The Centre gives as well support to university teaching and technical training. A detail description of the research infrastructures and their use statistics will be given. Some of the main research results will be presented to show the progress of research in the Centre in the past few years and to motivate the strategic plans for the forthcoming.

Forty-Sixth Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

International Nuclear Information System (INIS)

2013-01-01

The objectives of the meeting were to: • Review the current status and the progress since the 45th TWG-FR meeting of FR and ADS technology development activities in IAEA Member States; • Review the activities (past, present and planned) of the IAEA’s project 1.1.5.3, “Support for fast reactor research, technology development and deployment” to ensure that they remain relevant to the needs of Member States; • Provide the experts group with updates to advise the IAEA on FR and ADS activities, including on proposals for relevant studies and reviews; • Serve as a means for exchanging information on national and international FR and ADS programmes; • Review the main achievements and outcomes of the “International Conference on Fast Reactors and Related Fuel Cycle: Safe Technologies and Sustainable Scenarios – FR13”, held on 4 – 7 March 2013 in Paris, France; • Promote the exchange of technical information by proposing topics for, and assisting in the organization of, IAEA Workshops and Technical Meetings for 2014-2015 and further, and • Review the IAEA’s concluded, on-going and planned coordinated research projects (CRPs) in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives (GIF, INPRO, NEA, Euratom, etc.)

Glass melter materials technical options for the French vitrification process and operations experience authors

International Nuclear Information System (INIS)

Bonniaud, R.; Roznad, L.; Demay, R.

1986-09-01

The French vitrification process for solidifying high-level radioactive waste which has been under industrial application since 1978, is mentioned briefly. This technique involves glass melting at 1,150 deg.C, using an induction heated metallic vessel. The molten glass pouring is controlled by a thermal gate, which is also heated by induction. Two types of vessel are in use. Both are remotely removable and disposable to permit replacement at regular intervals. The technical criteria (the materials used have to meet) are described. The behaviour of the materials has been investigated using the industrial experience gained in the AVM facility during 8 years of operation, as well as with operation of a prototype for the new vitrification facilities under construction at La Hague. A short description of the use of these materials is also presented

Introduction to the special issue on the technical status of materials for a fusion reactor

Science.gov (United States)

Stork, D.; Zinkle, S. J.

2017-09-01

Materials determine in a fundamental way the performance and environmental attractiveness of a fusion reactor: through the size (power fluxes to the divertor, neutron fluxes to the first wall); economics (replacement lifetime of critical in-vessel components, thermodynamic efficiency through operating temperature etc); plasma performance (erosion by plasma fluxes to the divertor surfaces); robustness against off-normal accidents (safety); and the effects of post-operation radioactivity on waste disposal and maintenance. The major philosophies and methodologies used to formulate programmes for the development of fusion materials are outlined, as the basis for other articles in this special issue, which deal with the fundamental understanding of the issues regarding these materials and their technical status and prospects for development.

PFBC HGCU Test Facility. Technical progress report No. 24, Third quarter, CY 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

This is the twenty-fourth and final Technical Progress Report submitted to the Department of Energy (DOE) in connection with the cooperative agreement between the DOE and Ohio Power Company for the Tidd PFBC Hot Gas Clean Up Test Facility. This report covers the work completed during the Third Quarter of CY 1995. All activity this quarter was directed toward the completion of the program final report. A draft copy of the final report was forwarded to DOE during this quarter, and DOE submitted their comments on the report to AEPSC. DOE requested that Westinghouse write an appendix to the report covering the performance of the fail-safe regenerator devices during Tad operation, and Westinghouse subsequently prepared the appendix. Additional DOE comments were incorporated into the report, and it will be issued in camera-ready form by the end of October, 1995, which is the program end date. Appendix 1 presents the results of filter candle posttest examination by Westinghouse performed on selected filter candles following final shutdown of the system.

Technical and management challenges associated with structural materials degradation in nuclear reactors in the future

International Nuclear Information System (INIS)

Ford, F.P.

2007-01-01

There are active plans worldwide to increase nuclear power production by significant amounts. In the near term (i.e. by 2020) this will be accomplished by, (a) increasing the power output of the existing reactors and extending their life, and by, (b) constructing new reactors that are very similar to the current water-cooled designs. Beyond 2025-2030, it is possible that new reactors (i.e. the 'GEN IV' designs) will be very different from those currently in service. A full discussion of the technical and management concerns associated with materials degradation that might arise over the next 40 years would need to address a wide range of topics. Quite apart from discussing the structural integrity issues for the materials of construction and the fuel cladding, the debate would also need to cover, for example, fuel resources and the associated issues of fuel cycle management and waste disposal, manufacturing capacity, inspection capabilities, human reliability, etc., since these all impact to one degree or another on the choice of material and the reactor operating conditions. For brevity, the scope of this article is confined to the integrity of the materials of construction for passive components in the current water-cooled reactors and the evolutionary designs (which will dominate the near term new constructions), and the very different GEN IV reactor designs. In all cases the operating environments will be more aggressive than currently encountered. For instance, the concerns for flow accelerated corrosion and flow-induced vibration will be increased under extended power uprate conditions for the current water-cooled reactors. Of greater concern, the design life will be at least 60 years for all of the new reactors and for those current reactors operating with extended licenses. This automatically presents challenges with regard to managing both irradiation damage in metallic and non-metallic materials of construction, and environmentally assisted cracking. This

Progress and Strategies for Testing of Materials for Solar Panels

Energy Technology Data Exchange (ETDEWEB)

Kurtz, Sarah

2017-04-25

Accelerated testing is key to confident launch of a new product. However, for new products like solar panels, the best approach is not always clear. The challenge for materials manufacturers is that test times can be long. Also, small-coupon testing may not predict the behavior in the full-size module, but testing of the full-size module is too expensive. As a result, solar panel test standards like IEC 61215 are useful, but are not sufficient. Material manufacturers have needed to define their own test protocols. This presentation will review some historical data (e.g., data show that manufacturers are making great progress toward reducing encapsulant discoloration) and describe advances in material testing (for example, new techniques are being demonstrated on how to more quantitatively assess adhesion, detect tendency for delamination, and understand how encapsulant properties affect other properties like cracking of cells). The International PV Quality Assurance Task Force has been researching climate-specific weathering tests toward the goal of defining international standards that would simplify qualification and quality assurance testing for materials. The status of these tests and the strategies for how to organize these standards to best meet the needs of the industry will be discussed.

In-Pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials. Proceedings of a Technical Meeting

International Nuclear Information System (INIS)

2013-12-01

For many years, the increase in efficiency in the production of nuclear electricity has been an economic challenge in many countries which have developed this kind of energy. The increase in fuel burnup and fuel residence time leads to a reduction in the volume of fresh fuel loaded and spent fuel discharged, respectively. More demanding nuclear fuel cycle parameters are combined with a need to operate nuclear power plants with maximal availability and load factors, in load-follow mode and with longer fuel cycles. In meeting these requirements, fuel has to operate in a demanding environment of high radiation fields, high temperatures, high mechanical stresses and high coolant flow. Requirements of increased fuel reliability and minimal fuel failures also remain in force. Under such circumstances, continuous development of more radiation resistant fuel materials, especially advanced cladding, careful and incremental examinations, and improved understanding and modelling of high burnup fuel behaviour are required. Following a recommendation of the IAEA Technical Working Group on Fuel Performance and Technology, the Technical Meeting on In-pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials was held in Halden, Norway, on 21-24 August 2012. The purpose of the meeting was to review the current status and the progress in methods and technologies used for the in-pile testing of nuclear fuel achieved since the previous IAEA meeting on In-core Instrumentation and Reactor Core Assessment, also held in Halden in 2007. Emphasis was placed on advanced techniques applied for the understanding of high burnup fuel behaviour of water cooled power reactors that represent the vast majority of the current nuclear reactor fleet. However, the meeting also included papers and discussion on testing techniques applied or developed specifically for new fuel and structural materials considered for Generation-IV systems. The meeting was attended by 43

Modeling Non-Linear Material Properties in Composite Materials

Science.gov (United States)

2016-06-28

Technical Report ARWSB-TR-16013 MODELING NON-LINEAR MATERIAL PROPERTIES IN COMPOSITE MATERIALS Michael F. Macri Andrew G...REPORT TYPE Technical 3. DATES COVERED (From - To) 4. TITLE AND SUBTITLE MODELING NON-LINEAR MATERIAL PROPERTIES IN COMPOSITE MATERIALS ...systems are increasingly incorporating composite materials into their design. Many of these systems subject the composites to environmental conditions

Technical records as material evidence in criminal proceedings

Directory of Open Access Journals (Sweden)

Fitim Shishani

2017-03-01

Full Text Available Nowadays, with the aid of technical records - recordings (audio, visual or combined audiovisual events and occurrences can be registered in the outside world in detail. The recording enables the creator or anyone who has it in disposal that at any moment of its reproduction, it can be found in detail how the recorded event has happened or how an occurrence seemed at the time of the recording. Among the current formats of technical records are included: photography, filming, magnetic, magnetoscope, and videophone recording etc. (Sahiti & Murati 2016, 295. The possibility provided by the rapid technical development is also of interest to criminal procedure because technical records containing any fact that may be proved in criminal proceedings may serve as a source of knowledge about facts. In other words, they may serve as evidence to establish facts in criminal proceedings. Given the extensive options that technical fact recordings provide, entities that use the aid of various devices from this fi eld, as well as the different purposes of the author of the recording which have led to the case of making the recording, there is a reasonable question of the permission on their use as evidence in criminal proceedings. In Kosovo, the situation is clear in terms of recordings made in the criminal procedure, as Kosovo CCP 1 provides the possibility of photographing, filming, sketching, etc., of the crime scene, audio visual recording etc. examination of persons (defendant, witness, expert or recordings of any action on judicial review.

Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 2005

Energy Technology Data Exchange (ETDEWEB)

None, None

2006-09-29

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. Topical subcommittees of the EMaCC are responsible for conducting seminars and otherwise facilitating information flow between DOE organizational units in materials areas of particular importance to the Department. The EMaCC Terms of Reference were recently modified and developed into a Charter that was approved on June 5, 2003. As a result of this reorganization, the existing subcommittees were disbanded and new subcommittees are being formed. The FY 2004 budget summary for DOE Materials Activities is presented on page 8. The distribution of these funds between DOE laboratories, private industry, academia and other organizations is presented in tabular form on page 10. Following the budget summary is a set of detailed program descriptions for the FY 2004 DOE Materials activities. These descriptions are presented according to the organizational structure of the Department. A mission statement, a budget summary listing the project titles and FY 2004 funding, and detailed project summaries are presented for each Assistant Secretary office, the Office of Science, and the National Nuclear Security Administration. The project summaries also provide DOE, laboratory, academic and industrial contacts for each project, as appropriate.

Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 2004

Energy Technology Data Exchange (ETDEWEB)

none,

2005-08-31

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. Topical subcommittees of the EMaCC are responsible for conducting seminars and otherwise facilitating information flow between DOE organizational units in materials areas of particular importance to the Department. The EMaCC Terms of Reference were recently modified and developed into a Charter that was approved on June 5, 2003. As a result of this reorganization, the existing subcommittees were disbanded and new subcommittees are being formed. The FY 2004 budget summary for DOE Materials Activities is presented on page 8. The distribution of these funds between DOE laboratories, private industry, academia and other organizations is presented in tabular form on page 10. Following the budget summary is a set of detailed program descriptions for the FY 2004 DOE Materials activities. These descriptions are presented according to the organizational structure of the Department. A mission statement, a budget summary listing the project titles and FY 2004 funding, and detailed project summaries are presented for each Assistant Secretary office, the Office of Science, and the National Nuclear Security Administration. The project summaries also provide DOE, laboratory, academic and industrial contacts for each project, as appropriate.

Materials Investigation for Power Plants and Power Industry. Seminar

International Nuclear Information System (INIS)

Szteke, W.; Wasiak, J.; Bilous, W.; Przyborska, M.; Wagner, T.; Wojciechowska, J.; Zubowski, B.

2005-01-01

The Report is an assembly of the papers concerning the present state and perspectives of evolution of power industry in Poland, in this the development of atomic energy. The material and diagnostic problems occurring the exploitation of power station as well as gas pipelines are also discussed. The progress in the accommodation of the Polish technical prescriptions to the European law is also described. (authors)

Nuclear power plant diagnostics - Safety aspects and licensing. Report of a technical committee meeting. Working material

International Nuclear Information System (INIS)

1997-01-01

The aim of the Technical Committee Meeting (TCM) was to review developed systems and methods in diagnostics in the scope of their impacts and importance to the safety of Nuclear Power Plants. Papers presented on TCM came from different sources, from developers, from manufacturers, from licensing authorities and from NPP personal. They reflect up to date status in the given subject. Participants of TCM formulated three working groups to elaborate different questions which were raised during the discussions. Their results are reflected in the three chapter titles of the given material. Annex 1 to this document contains presentations made at the Technical Committee Meeting. Refs, figs, tabs

Geothermal direct-heat utilization assistance. Quarterly project progress report, October--December 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-01-01

This report summarizes geothermal technical assistance, R and D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the first quarter of FY-98 (October--December 1997). It describes 216 contacts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with include requests for general information including maps and material for high school debates, and material on geothermal heat pumps, resource and well data, space heating and cooling, greenhouses, aquaculture, equipment, district heating, resorts and spas, industrial applications, electric power and snow melting. Research activities include work on model construction specifications of lineshaft submersible pumps and plate heat exchangers, a comprehensive aquaculture developer package and revisions to the Geothermal Direct Use Engineering and Design Guidebook. Outreach activities include the publication of the Quarterly Bulletin (Vol. 18, No. 4) which was devoted entirely to geothermal activities in South Dakota, dissemination of information mainly through mailings of publications, tours of local geothermal uses, geothermal library acquisition and use, participation in workshops, short courses and technical meetings by the staff, and progress monitor reports on geothermal activities.

Progress in understanding the mechanical behavior of pressure-vessel materials at elevated temperatures

International Nuclear Information System (INIS)

Swindeman, R.W.; Brinkman, C.R.

1981-01-01

Progress during the 1970's on the production of high-temperature mechanical properties data for pressure vessel materials was reviewed. The direction of the research was toward satisfying new data requirements to implement advances in high-temperature inelastic design methods. To meet these needs, servo-controlled testing machines and high-resolution extensometry were developed to gain more information on the essential behavioral features of high-temperature alloys. The similarities and differences in the mechanical response of various pressure vessel materials were identified. High-temperature pressure vessel materials that have received the most attention included Type 304 stainless steel, Type 316 stainless steel, 2 1/4 Cr-1 Mo steel, alloy 800H, and Hastelloy X

Cladding and structural materials semi-annual progress report, January 1975--July 1975

International Nuclear Information System (INIS)

Claudson, T.T.

1975-10-01

Theoretical and experimental programs are in progress to determine the effects of fast neutron radiation on the mechanical properties and swelling of 3C4 and 316SS cladding and duct materials. Detailed specimen characterization and detailed test conditions are required in order to provide the 2 to 5 percent accuracy of results at 1γ. Preliminary swelling tests show that swelling in stressed assemblies is much larger than in unstressed structural components. Correlation of swelling data from high exposure cladding (11.4 at. percent burnup) agrees with previous data and with the current design equation for 20 percent CW 316 stainless steel. Improved techniques for TEM specimen preparation are described along with recent results on crack propagation. Initial results are given for the effects of aging on Inconel 718 base and weld materials. Compilations of these design values of materials properties have been issued in the form of the Nuclear Systems Materials Handbook

Combating illicit trafficking in nuclear and other radioactive material. Technical guidance. Reference manual. (Chinese Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is intended for individuals and organizations that may be called upon to deal with the detection of and response to criminal or unauthorized acts involving nuclear or other radioactive material. It will also be useful for legislators, law enforcement agencies, government officials, technical experts, lawyers, diplomats and users of nuclear technology. This manual emphasizes the international initiatives for improving the security of nuclear and other radioactive material. However, it is recognized that effective measures for controlling the transfer of equipment, non-nuclear material, technology or information that may assist in the development of nuclear explosive devices, improvised nuclear devices (INDs) or other radiological dispersal devices (RDDs) are important elements of an effective nuclear security system. In addition, issues of personal integrity, inspection and investigative procedures are not discussed in this manual, all of which are essential elements for an effective overall security system. The manual considers a variety of elements that are recognized as being essential for dealing with incidents of criminal or unauthorized acts involving nuclear and other radioactive material. Depending on conditions in a specific State, including its legal and governmental infrastructure, some of the measures discussed will need to be adapted to suit that State's circumstances. However, much of the material can be applied directly in the context of other national programmes. This manual is divided into four main parts. Section 2 discusses the threat posed by criminal or unauthorized acts involving nuclear and other radioactive material, as well as the policy and legal bases underlying the international effort to restrain such activities. Sections 3 and 4 summarize the major international undertakings in the field. Sections 5-8 provide some basic technical information on radiation, radioactive material, the health consequences of radiation

Appropriability, Technological Opportunity, Market Demand, and Technical Change - Empirical Evidence from Switzerland

OpenAIRE

Harabi, Najib

1992-01-01

The purpose of this paper is to analyze both theoretically and empirically those factors which underlay the - empirically observable - inter-industry differences in technical progress. At the theoretical level economists agree more and more that technical progress can be explained at the industry level by the following three factors: (1) the technological opportunities, (2) the appropriability conditions, meaning the ability to capture and protect the results of technical innovations and (3) ...

Transport safety research abstracts. No. 2. Information on research recently concluded and in progress

International Nuclear Information System (INIS)

1994-09-01

Transport Safety Research Abstracts (TSRA) was first published by the IAEA in 1991 as a means of disseminating information on research in radioactive material transport. This second edition utilizes International Nuclear Information System (INIS) protocol for data processing and report preparation for a research-in-progress database established by the IAEA's Division of Scientific and Technical Information. INIS subject categories and descriptors are included in the information about each project

Transport safety research abstracts. No. 2. Information on research recently concluded and in progress

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-09-01

Transport Safety Research Abstracts (TSRA) was first published by the IAEA in 1991 as a means of disseminating information on research in radioactive material transport. This second edition utilizes International Nuclear Information System (INIS) protocol for data processing and report preparation for a research-in-progress database established by the IAEA`s Division of Scientific and Technical Information. INIS subject categories and descriptors are included in the information about each project.

DOE-DARPA High-Performance Corrosion-Resistant Materials (HPCRM), Annual HPCRM Team Meeting & Technical Review

Energy Technology Data Exchange (ETDEWEB)

Farmer, J; Brown, B; Bayles, B; Lemieux, T; Choi, J; Ajdelsztajn, L; Dannenberg, J; Lavernia, E; Schoenung, J; Branagan, D; Blue, C; Peter, B; Beardsley, B; Graeve, O; Aprigliano, L; Yang, N; Perepezko, J; Hildal, K; Kaufman, L; Lewandowski, J; Perepezko, J; Hildal, K; Kaufman, L; Lewandowski, J; Boudreau, J

2007-09-21

The overall goal is to develop high-performance corrosion-resistant iron-based amorphous-metal coatings for prolonged trouble-free use in very aggressive environments: seawater & hot geothermal brines. The specific technical objectives are: (1) Synthesize Fe-based amorphous-metal coating with corrosion resistance comparable/superior to Ni-based Alloy C-22; (2) Establish processing parameter windows for applying and controlling coating attributes (porosity, density, bonding); (3) Assess possible cost savings through substitution of Fe-based material for more expensive Ni-based Alloy C-22; (4) Demonstrate practical fabrication processes; (5) Produce quality materials and data with complete traceability for nuclear applications; and (6) Develop, validate and calibrate computational models to enable life prediction and process design.

Behaviour of LWR core materials under accident conditions. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1996-12-01

At the invitation of the Government of the Russian Federation, following a proposal of the International Working Group on Water Reactor Fuel Performance and Technology, the IAEA convened a Technical Committee Meeting on Behaviour of LWR Core Materials Under Accident Conditions from 9 to 13 October 1995 in Dimitrovgrad to analyze and evaluate the behaviour of LWR core materials under accident conditions with special emphasis on severe accidents. In-vessel severe accidents phenomena were considered in detail, but specialized thermal hydraulic aspects as well as ex-vessel phenomena were outside the scope of the meeting. Forty participants representing eight countries attended the meeting. Twenty-three papers were presented and discussed during five sessions. Refs, figs, tabs

High temperature turbine technology program. Phase II. Technology test and support studies. Annual technical progress report, January 1, 1979-December 31, 1979

Energy Technology Data Exchange (ETDEWEB)

1980-01-01

Work performed on the High Temperature Turbine Technology Program, Phase II - Technology Test and Support Studies during the period from January 1, 1979 through December 31, 1979 is summarized. Objectives of the program elements as well as technical progress and problems encountered during this Phase II annual reporting period are presented. Progress on design, fabrication and checkout of test facilities and test rigs is described. LP turbine cascade tests were concluded. 350 hours of testing were conducted on the LP rig engine first with clean distillate fuel and then with fly ash particulates injected into the hot gas stream. Design and fabrication of the turbine spool technology rig components are described. TSTR 60/sup 0/ sector combustor rig fabrication and testing are reviewed. Progress in the design and fabrication of TSTR cascade rig components for operation on both distillate fuel and low Btu gas is described. The new coal-derived gaseous fuel synthesizing facility is reviewed. Results and future plans for the supporting metallurgical programs are discussed.

GPHS-RTGs in support of the Cassini mission. Semi annual technical progress report, 2 October 1995--31 March 1996

International Nuclear Information System (INIS)

1996-01-01

The technical progress achieved during the period 2 October 1995 through 31 March 1996 on Contract No. DE-AC03-91SF18852, Radioisotope Generators and Ancillary Activities is described herein. This report is organized by the program task structure as follows: spacecraft integration and liaison; engineering support; safety; qualified unicouple fabrication; ETG fabrication, assembly, and test; ground support equipment (GSE); RTG shipping and launch support; designs, reviews, and mission applications; project management, quality assurance and reliability, contract changes, non-capital CAGO acquisition, and CAGO maintenance; contract acquired government-owned property (CAGO) acquisition; and program calendars

Scientific and technical report, 2000 of the IPSN

International Nuclear Information System (INIS)

2001-01-01

IPSN (Institut de Protection et de Surete Nucleaire) is responsible for dealing with all aspects in the evaluation of safety of nuclear installations involving the human factors. To achieve its objectives, it conducts its own research and development activities on these themes. This report highlights the most significant scientific and technical achievements of the Institut in 2000. Twenty eight reports are presented, grouped in eight sessions, each ones opened by a review paper: the reactors safety, the installations safety, the radioactive materials and transport safety, the public health, the environment protection, the radioactive wastes safety, the crisis management and the IPSN installations. The international research program Phebus PF is detailed, technical progresses concerning the steam generators nondestructive testing or the impact of automation on operator performance are also presented. One session deals with the criticality studies and risk assessment. The control and surveillance of nuclear materials form the subject of research programs and experiments as well as the transport safety. Concerning the public and environment protection inspections, epidemiological studies, radionuclides transportation and radio-contaminant behavior are reported. In the domain of the radioactive wastes safety, the deep underground storage and the model MELODIE are presented. Examples of accidents or the INEX2 exercise are also discussed. (A.L.B.)

Composite Beam Theory with Material Nonlinearities and Progressive Damage

Science.gov (United States)

Jiang, Fang

Beam has historically found its broad applications. Nowadays, many engineering constructions still rely on this type of structure which could be made of anisotropic and heterogeneous materials. These applications motivate the development of beam theory in which the impact of material nonlinearities and damage on the global constitutive behavior has been a focus in recent years. Reliable predictions of these nonlinear beam responses depend on not only the quality of the material description but also a comprehensively generalized multiscale methodology which fills the theoretical gaps between the scales in an efficient yet high-fidelity manner. The conventional beam modeling methodologies which are built upon ad hoc assumptions are in lack of such reliability in need. Therefore, the focus of this dissertation is to create a reliable yet efficient method and the corresponding tool for composite beam modeling. A nonlinear beam theory is developed based on the Mechanics of Structure Genome (MSG) using the variational asymptotic method (VAM). The three-dimensional (3D) nonlinear continuum problem is rigorously reduced to a one-dimensional (1D) beam model and a two-dimensional (2D) cross-sectional analysis featuring both geometric and material nonlinearities by exploiting the small geometric parameter which is an inherent geometric characteristic of the beam. The 2D nonlinear cross-sectional analysis utilizes the 3D material models to homogenize the beam cross-sectional constitutive responses considering the nonlinear elasticity and progressive damage. The results from such a homogenization are inputs as constitutive laws into the global nonlinear 1D beam analysis. The theoretical foundation is formulated without unnecessary kinematic assumptions. Curvilinear coordinates and vector calculus are utilized to build the 3D deformation gradient tensor, of which the components are formulated in terms of cross-sectional coordinates, generalized beam strains, unknown warping

Technical committee meeting on evaluation of radioactive materials release and sodium fires in fast reactors

International Nuclear Information System (INIS)

1996-01-01

The objectives of the Technical Committee Meeting was to review the activities of research on radioactive materials release and sodium fires in fast reactors in each of the participating countries. It covered: out-of-pile experiments and analysis codes on source term; in-pile experiments on source term; core disruptive accidents; sodium leak experience in liquid metal fast reactors; evaluation of sodium fire; and aerosol behaviour

Technical committee meeting on evaluation of radioactive materials release and sodium fires in fast reactors

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

The objectives of the Technical Committee Meeting was to review the activities of research on radioactive materials release and sodium fires in fast reactors in each of the participating countries. It covered: out-of-pile experiments and analysis codes on source term; in-pile experiments on source term; core disruptive accidents; sodium leak experience in liquid metal fast reactors; evaluation of sodium fire; and aerosol behaviour.

Technical progress report to the Department of Energy on the Solid State Sciences Committee (SSSC)

International Nuclear Information System (INIS)

1995-01-01

The Solid State Sciences Committee (SSSC) of the National Research Council (NRC) is charged with monitoring the health of the field of materials science in the United States. Accordingly, the Committee identifies and examines both broad and specific issues affecting the field. Regular meetings, teleconferences, briefings from agencies and the scientific community, the formation of study panels to prepare reports, and special forums are among the mechanisms used by the SSSC to meet its charge. This progress report presents a review of SSSC activities from May 1, 1992 through April 30, 1993. The details of prior activities are discussed in earlier reports. During the above period, the SSSC has continued to track and participate, when requested, in the development of a Federal initiative on advanced materials and processing. Specifically, the SSSC is presently planning the 1993 SSSC Forum (to be cosponsored with the National Materials Advisory Board (NMAB) and the Washington Materials Forum (WNM)). The thrust will be to highlight the Federal Advanced Materials and Processing Program (AMPP). In keeping with its charge to identify and highlight specific areas for scientific and technological opportunities, the SSSC continued to oversee the conduct of a study on biomolecular materials. Preliminary plans also have been developed for studies on neutron scattering science, on ultrasmall devices, and on molecular routes to materials

Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 2002

Energy Technology Data Exchange (ETDEWEB)

none,

2003-08-08

The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. Topical subcommittees of the EMaCC are responsible for conducting seminars and otherwise facilitating information flow between DOE organizational units in materials areas of particular importance to the Department. The EMaCC Terms of Reference were recently modified and developed into a Charter that was approved on June 5, 2003. As a result of this reorganization, the existing subcommittees were disbanded and new subcommittees are being formed. The EMaCC Charter and the memorandum approving it are presented in the Appendix of this report. The FY 2002 budget summary for DOE Materials Activities is presented on page 8. The distribution of these funds between DOE laboratories, private industry, academia and other organizations is presented in tabular form on page 10. Following the budget summary is a set of detailed program descriptions for the FY 2002 DOE Materials activities. These descriptions are presented according to the organizational structure of the Department. A mission statement, a budget summary listing the project titles and FY 2002 funding, and detailed project summaries are presented for each Assistant Secretary office, the Office of Science, and the National Nuclear Security Administration. The project summaries also provide DOE, laboratory, academic and industrial contacts for each project, as appropriate.

ISABELLE: a progress report

Energy Technology Data Exchange (ETDEWEB)

Hahn, H

1980-01-01

This paper discusses the ISABELLE project, which has the objective of constructing a high-energy proton colliding beam facility at Brookhaven National Laboratory. The major technical features of the intersecting storage accelerators with their projected performance are described. Application of over 1000 superconducting magnets in the two rings represents the salient characteristic of the machine. The status of the entire project, the technical progress made so far, and difficulties encountered are reviewed.

ISABELLE: a progress report

International Nuclear Information System (INIS)

Hahn, H.

1980-01-01

This paper discusses the ISABELLE project, which has the objective of constructing a high-energy proton colliding beam facility at Brookhaven National Laboratory. The major technical features of the intersecting storage accelerators with their projected performance are described. Application of over 1000 superconducting magnets in the two rings represents the salient characteristic of the machine. The status of the entire project, the technical progress made so far, and difficulties encountered are reviewed

The general technical regulation and the standardization

International Nuclear Information System (INIS)

Laverie, Michel; Houze, Christian; Lebouleux, Philippe

1980-01-01

Through a certain number of procedures, the thorough appreciation of the safety of a nuclear installation relies more on a specific appreciation taking into account the references as a whole, than on a technical regulation which claims to cover all the problems. Nevertheless, a French technical regulation structure regarding the safety domain must be built up progressively. The authors consider the principles of such a structure, and together they make the inventory of the works, finished, in progress or contemplated. The description of this specifically French approach emphazises the multiple and complementary forms given to statutory implements [fr

Metals and Ceramics Division materials science annual progress report for period ending June 30, 1977

International Nuclear Information System (INIS)

McHargue, C.J.

1977-09-01

Progress is reported for research programs in the metals and ceramics division of ORNL. In structure of materials, theoretical research, x-ray diffraction studies, studies of erosion of ceramics, preparation and synthesis of high temperature and special service materials, and studies of stabilities of microphases in high-temperature structural materials. Research into deformation and mechanical properties included physical metallurgy, and grain boundary segregation and embrittlement. Physical properties and transport phenomena were studied and included mechanisms of surface and solid state reactions, and properties of superconducting materials. The radiation effects program, directed at understanding the effects of composition and microstructure on the structure and properties of materials irradiated at elevated temperatures, is also described

Magnetic fusion energy materials technology program annual progress report for period ending June 30, 1977

International Nuclear Information System (INIS)

Scott, J.L.

1977-09-01

The objectives of the Magnetic Fusion Energy (MFE) Materials Technology Program, which is described in this report, are to continue to solve the materials problems of the Fusion Energy Division of ORNL and to meet needs of the national MFE program, directed by the ERDA Division of Magnetic Fusion Energy (DMFE). This work is a continuation of the program described in previous annual progress reports. The principal areas of work include radiation effects, compatibility studies, materials studies related to the plasma-materials interaction, materials engineering, radiation behavior of superconducting magnet insulation, and mechanical properties of superconducting composites. The level of effort and schedules are consistent with Logic II of the DMFE Program Plan

Laboratory Directed Research and Development FY 2000 Annual Progress Report

Energy Technology Data Exchange (ETDEWEB)

Los Alamos National Laboratory

2001-05-01

This is the FY00 Annual Progress report for the Laboratory Directed Research and Development (LDRD) Program at Los Alamos National Laboratory. It gives an overview of the LDRD Program, summarizes progress on each project conducted during FY00, characterizes the projects according to their relevance to major funding sources, and provides an index to principal investigators. Project summaries are grouped by LDRD component: Directed Research and Exploratory Research. Within each component, they are further grouped into the ten technical categories: (1) atomic, molecular, optical, and plasma physics, fluids, and beams, (2) bioscience, (3) chemistry, (4) computer science and software engineering, (5) engineering science, (6) geoscience, space science, and astrophysics, (7) instrumentation and diagnostics, (8) materials science, (9) mathematics, simulation, and modeling, and (10) nuclear and particle physics.

TECHNICAL COORDINATION

CERN Multimedia

A. Ball

Overview From a technical perspective, CMS has been in “beam operation” state since 6th November. The detector is fully closed with all components operational and the magnetic field is normally at the nominal 3.8T. The UXC cavern is normally closed with the radiation veto set. Access to UXC is now only possible during downtimes of LHC. Such accesses must be carefully planned, documented and carried out in agreement with CMS Technical Coordination, Experimental Area Management, LHC programme coordination and the CCC. Material flow in and out of UXC is now strictly controlled. Access to USC remains possible at any time, although, for safety reasons, it is necessary to register with the shift crew in the control room before going down.It is obligatory for all material leaving UXC to pass through the underground buffer zone for RP scanning, database entry and appropriate labeling for traceability. Technical coordination (notably Stephane Bally and Christoph Schaefer), the shift crew and run ...

AR and TD Fossil Energy Materials Program. Quarterly progress report for the period ending December 31, 1981

Energy Technology Data Exchange (ETDEWEB)

1982-04-01

The ORNL Fossil Energy Materials Program Office compiles and issues this combined quarterly progress report from camera-ready copies submitted by each of the participating subcontractor organizations. This report of activities on the program is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FY 1982-1986 in which projects are organized according to fossil energy technologies. This report is divided into parts and chapters with each part describing projects related to a particular fossil energy technology. Chapters within a part provide details of the various projects associated with that technology. We hope this series of AR and TD Fossil Energy Materials Program quarterly progress reports will aid in the dissemination of information developed on the program. Plans for the program will be issued annually. A draft of the program plan for FY 1982 to 1986 has been prepared and is in the review process. The implementation of these plans will be reflected by these quarterly progress reports, and this dissemination of information will bw augmented by topical or final reports as appropriate.

Non-technical constraints to eradication: the Italian experience.

Science.gov (United States)

Moda, Giuliana

2006-02-25

Although technical constraints to eradication of bovine tuberculosis are well-recognised, non-technical constraints can also delay progress towards eradication, leading to inefficiency and increased programme costs. This paper seeks to analyse the main non-technical constraints that can interfere with the successful implementation of tuberculosis eradication plans, based on experiences from an area of high tuberculosis prevalence in Regione Piemonte, Italy. The main social and economic constraints faced in the past 20 years are reviewed, including a social reluctance to recognise the importance of seeking eradication as the goal of disease control, effective communication of technical issues, the training and the organization of veterinary services, the relationship between the regional authority and farmers and their representatives, and data management and epidemiological reporting. The paper analyses and discusses the solutions that were applied in Regione Piemonte and the benefits that were obtained. Tuberculosis eradication plans are one of the most difficult tasks of the Veterinary Animal Health Services, and non-technical constraints must be considered when progress towards eradication is less than expected. Organizational and managerial resources can help to overcome social or economic obstacles, provided the veterinary profession is willing to address technical, but also non-technical, constraints to eradication.

49 CFR 552.6 - Technical review.

Science.gov (United States)

2010-10-01

... 49 Transportation 6 2010-10-01 2010-10-01 false Technical review. 552.6 Section 552.6... § 552.6 Technical review. The appropriate Associate Administrator conducts a technical review of the petition. The technical review may consist of an analysis of the material submitted, together with...

TECHNICAL COORDINATION

CERN Multimedia

A. Ball and W. Zeuner

2011-01-01

In this report we will review the main achievements of the Technical Stop and the progress of several centrally-managed projects to support CMS operation and maintenance and prepare the way for upgrades. Overview of the extended Technical Stop  The principal objectives of the extended Technical Stop affecting the detector itself were the installation of the TOTEM T1 telescopes on both ends, the readjustment of the alignment link-disk in YE-2, the replacement of the light-guide sleeves for all PMs of both HFs, and some repairs on TOTEM T2 and CASTOR. The most significant tasks were, however, concentrated on the supporting infrastructure. A detailed line-by-line leak search was performed in the C6F14 cooling system of the Tracker, followed by the installation of variable-frequency drives on the pump motors of the SS1 and SS2 tracker cooling plants to reduce pressure transients during start-up. In the electrical system, larger harmonic filters were installed in ...

Effects of humic substances on the migration of radionuclides: complexation and transport of actinides. First technical progress report (work period 01.97 - 12.97)

International Nuclear Information System (INIS)

Buckau, G.

1998-08-01

The present report describes progress within the first year of the EC-project 'Effects of Humic Substances on the Migration of Radionuclides: Complexation and Transport of Actinides'. The project is conducted within the EC-Cluster 'Radionuclide Transport/Retardation Processes'. Contrary to formal requirements of the Commission, this report with a great deal of detail is established already after one year of project work. It is scheduled to be followed by a second technical progress report covering the second year of the project. In agreement with the contractual obligations a final report of similar technical detail will also be generated. The report contains an executive summary written by the coordinator (FZK/INE) with strong support from the other three task leaders (BGS, CEA-SGC and RMC-E). More detailed results are given by individual contributions of the project partners in 13 annexes. In the executive summary report the origin of results presented is given, also serving as guidance for finding more detailed results in the annexes. Not all results are discussed or referred to in the executive summary report and thus readers with a deeper interest also need to consult the annexes. (orig.)

Review on recent progress of nanostructured anode materials for Li-ion batteries

KAUST Repository

Goriparti, Subrahmanyam

2014-07-01

This review highlights the recent research advances in active nanostructured anode materials for the next generation of Li-ion batteries (LIBs). In fact, in order to address both energy and power demands of secondary LIBs for future energy storage applications, it is required the development of innovative kinds of electrodes. Nanostructured materials based on carbon, metal/semiconductor, metal oxides and metal phosphides/nitrides/sulfides show a variety of admirable properties for LIBs applications such as high surface area, low diffusion distance, high electrical and ionic conductivity. Therefore, nanosized active materials are extremely promising for bridging the gap towards the realization of the next generation of LIBs with high reversible capacities, increased power capability, long cycling stability and free from safety concerns. In this review, anode materials are classified, depending on their electrochemical reaction with lithium, into three groups: intercalation/de-intercalation, alloy/de-alloy and conversion materials. Furthermore, the effect of nanoscale size and morphology on the electrochemical performance is presented. Synthesis of the nanostructures, lithium battery performance and electrode reaction mechanisms are also discussed. To conclude, the main aim of this review is to provide an organic outline of the wide range of recent research progresses and perspectives on nanosized active anode materials for future LIBs.

Review on recent progress of nanostructured anode materials for Li-ion batteries

KAUST Repository

Goriparti, Subrahmanyam; Miele, Ermanno; De Angelis, Francesco; Di Fabrizio, Enzo M.; Proietti Zaccaria, Remo; Capiglia, Claudio

2014-01-01

This review highlights the recent research advances in active nanostructured anode materials for the next generation of Li-ion batteries (LIBs). In fact, in order to address both energy and power demands of secondary LIBs for future energy storage applications, it is required the development of innovative kinds of electrodes. Nanostructured materials based on carbon, metal/semiconductor, metal oxides and metal phosphides/nitrides/sulfides show a variety of admirable properties for LIBs applications such as high surface area, low diffusion distance, high electrical and ionic conductivity. Therefore, nanosized active materials are extremely promising for bridging the gap towards the realization of the next generation of LIBs with high reversible capacities, increased power capability, long cycling stability and free from safety concerns. In this review, anode materials are classified, depending on their electrochemical reaction with lithium, into three groups: intercalation/de-intercalation, alloy/de-alloy and conversion materials. Furthermore, the effect of nanoscale size and morphology on the electrochemical performance is presented. Synthesis of the nanostructures, lithium battery performance and electrode reaction mechanisms are also discussed. To conclude, the main aim of this review is to provide an organic outline of the wide range of recent research progresses and perspectives on nanosized active anode materials for future LIBs.

Technical basis of safeguards

International Nuclear Information System (INIS)

Buechler, C.

1975-01-01

Definition of nuclear materials control. Materials accountancy and physical control as technical possibilities. Legal possibilities and levels of responsibility: material holders, national and international authority. Detection vs. prevention. Physical security and containment surveillance. Accountancy: materials balance concept. Materials measurement: inventory taking, flow determination. IAEA safeguards; verification of operator's statement. (HP) [de

Solid State Sciences Committee (SSSC). Technical progress report, May 1, 1992--April 30, 1993

International Nuclear Information System (INIS)

Taylor, R.

1995-01-01

The Solid State Sciences Committee (SSSC) of the National Research Council (NRC) is charged with monitoring the health of the field of materials science in the United States. Accordingly, the Committee identifies and examines both broad and specific issues affecting the field. Regular meetings, teleconferences, briefings from agencies and the scientific community, the formation of study panels to prepare reports, and special forums are among the mechanisms used by the SSSC to meet its charge. This progress report presents a review of SSSC activities from May 1, 1992 through April 30, 1993. The details of prior activities are discussed in earlier reports. During the above period, the SSSC has continued to track and participate, when requested, in the development of a Federal initiative on advanced materials and processing. Specifically, the SSSC is presently planning the 1993 SSSC Forum (to be cosponsored with the National Materials Advisory Board (NMAB) and the Washington Materials Forum (WMF)). The thrust will be to highlight the Federal Advanced Materials and Processing Program (AMPP). In keeping with its charge to identify and highlight specific areas for scientific and technological opportunities, the SSSC continued to oversee the conduct of a study on biomolecular materials. Preliminary plans also were developed for a study on neutron science, however, further activity is pending. A proposed study on ultrasmall devices has been expanded and absorbed into a broader context; the BPA, with SSSC participation, is preparing to hold a program initiation meeting to evaluate the need for a study on information technology and hardware

Sintering and dielectric properties of a technical porcelain prepared from economical natural raw materials

Directory of Open Access Journals (Sweden)

S. Kasrani

Full Text Available Abstract In this study, the production of a technical porcelain, for the ceramic dielectric applications by using economical natural raw materials, was investigated. The basic porcelain composition was selected consisting of 30 wt% kaolin, 45 wt% potash-feldspar and 25 wt% quartz. The obtained phases in the sintered samples were investigated by X-ray diffraction, Fourier transform infrared spectroscopy analysis, and scanning electron microscopy images. It has been confirmed by these techniques that the main crystalline phases were quartz and mullite. Dielectric measurements of technical porcelains have been carried out at 1 kHz from room temperature to 200 °C. The dielectric constant, loss factor, dielectric loss tangent, and resistivity of the porcelain sample sintered at 1160 °C were 22-25, 0.32-1.80, 0.006-0.07, and 0.2-9 x 1013 Ω.cm, respectively. The value of dielectric constant was significantly high when compared to that of conventional porcelains which did not exceed generally 9.

Sintering and dielectric properties of a technical porcelain prepared from economical natural raw materials

Energy Technology Data Exchange (ETDEWEB)

Kasrani, S.; Harabi, A.; Barama, S.-E.; Foughali, L.; Benhassine, M. T., E-mail: souad478@yahoo.fr, E-mail: harabi52@gmail.com, E-mail: sebarama@usa.com, E-mail: foughali_lazhar@yahoo.fr, E-mail: mtb25dz@gmail.com [Ceramics Lab. Mentouri University of Constantine (Algeria); Aldhayan, D.M., E-mail: aldhayan@ksu.edu.sa [Chemistry Department, Riyadh, King Saud University (Saudi Arabia)

2016-10-15

In this study, the production of a technical porcelain, for the ceramic dielectric applications by using economical natural raw materials, was investigated. The basic porcelain composition was selected consisting of 30 wt% kaolin, 45 wt% potash-feldspar and 25 wt% quartz. The obtained phases in the sintered samples were investigated by X-ray diffraction, Fourier transform infrared spectroscopy analysis, and scanning electron microscopy images. It has been confirmed by these techniques that the main crystalline phases were quartz and mullite. Dielectric measurements of technical porcelains have been carried out at 1 kHz from room temperature to 200 °C. The dielectric constant, loss factor, dielectric loss tangent, and resistivity of the porcelain sample sintered at 1160 °C were 22-25, 0.32-1.80, 0.006-0.07, and 0.2-9 x 10{sup 13} Ω.cm, respectively. The value of dielectric constant was significantly high when compared to that of conventional porcelains which did not exceed generally 9. (author)

Sintering and dielectric properties of a technical porcelain prepared from economical natural raw materials

International Nuclear Information System (INIS)

Kasrani, S.; Harabi, A.; Barama, S.-E.; Foughali, L.; Benhassine, M. T.; Aldhayan, D.M.

2016-01-01

In this study, the production of a technical porcelain, for the ceramic dielectric applications by using economical natural raw materials, was investigated. The basic porcelain composition was selected consisting of 30 wt% kaolin, 45 wt% potash-feldspar and 25 wt% quartz. The obtained phases in the sintered samples were investigated by X-ray diffraction, Fourier transform infrared spectroscopy analysis, and scanning electron microscopy images. It has been confirmed by these techniques that the main crystalline phases were quartz and mullite. Dielectric measurements of technical porcelains have been carried out at 1 kHz from room temperature to 200 °C. The dielectric constant, loss factor, dielectric loss tangent, and resistivity of the porcelain sample sintered at 1160 °C were 22-25, 0.32-1.80, 0.006-0.07, and 0.2-9 x 10 13 Ω.cm, respectively. The value of dielectric constant was significantly high when compared to that of conventional porcelains which did not exceed generally 9. (author)

Controlled thermonuclear materials technology program. Annual progress report for period ending June 30, 1975

International Nuclear Information System (INIS)

Scott, J.L.

1975-10-01

Detailed descriptions are given of research progress in the following areas: (1) microstructure of irradiated 316 stainless steel containing high helium concentrations, (2) temperature and fluence limitations for a type 316 stainless steel CTR first wall, (3) swelling and microstructural changes in irradiated vanadium alloys, (4) mechanical properties of irradiated V-20 wt percent Ti, (5) radiation damage calculations, (6) evaluation of irradiation facilities for CTR materials development, (7) surface studies, compatibility studies, (8) magnet development, (9) EPR design support, and (10) the influence of structural materials on fusion-reactor blanket response. (MOW)

Progress of research on plasma facing materials in University of Science and Technology Beijing

International Nuclear Information System (INIS)

Ge, Chang-Chun; Zhou, Zhang-Jian; Song, Shu-Xiang; Du, Juan; Zhong, Zhi-Hong

2007-01-01

In this paper, we report some new progress on plasma facing materials in University of Science and Technology Beijing (USTB), China. They include fabrication of tungsten coating with ultra-fine grain size by atmosphere plasma spraying; fabrication of tungsten with ultra-fine grain size by a newly developed method named as resistance sintering under ultra-high pressure; using the concept of functionally graded materials to join tungsten to copper based heat sink; joining silicon doped carbon to copper by brazing using a Ti based amorphous filler and direct casting

Geothermal Energy R&D Program Annual Progress Report Fiscal Year 1993

Energy Technology Data Exchange (ETDEWEB)

None

1994-04-01

In this report, the DOE Geothermal Program activities were split between Core Research and Industrial Development. The technical areas covered are: Exploration Technology, Drilling Technology, Reservoir Technology (including Hot Dry Rock Research and The Geyser Cooperation), and Conversion Technology (power plants, materials, and direct use/direct heat). Work to design the Lake County effluent pipeline to help recharge The Geysers shows up here for the first time. This Progress Report is another of the documents that are reasonable starting points in understanding many of the details of the DOE Geothermal Program. (DJE 2005)

Quarterly progress report on the evaluation of critical materials for photovoltaic cells

Energy Technology Data Exchange (ETDEWEB)

Watts, R.L.; Pawlewicz, W.W.; Gurwell, W.E.; Jamieson, W.M.; Long, L.W.; Smith, S.A.; Teeter, R.R.

1979-09-01

The scope of the activities included in this program are as follows: (1) characterize new and improved photovoltaic cell designs and production processes for subsequent analysis; (2) review or screen these designs for potential material shortages or other constraints; (3) carry out investigations of the probable costs of new sources of materials potentially in short supply, concentrating on gallium and indium; and (4) identify options for coping with or mitigating the problems identified. The methodology and data base used in the CMAP (Critical Material Analysis Program) computer program were developed as part of a broad scale DOE program to review the potential material constraints of all solar programs. The photovoltaic report screened 13 cells in 15 systems and assumed 100% material utilization (process efficiency) in producing the photovoltaic cells. This study emphasizes the availability of cell fabrication feedstock materials and the effects of process efficiencies on material availability by adding characterizations of photovoltaic production processes. This quarterly report presents the results of work with emphasis on Task I, the characterization of photovoltaic cells and their production processes. Task IIA, CMAP Modification, Data Base Development and Operation has been initiated. Task IIB, Review, Integration, Interpretation and Analysis of Screening will begin once the baseline screening has been completed in Task IIA. Work on Task IIIA, the Assessment of Future Costs and Supplies of Gallium and Indium and Task IIIB, Economics of Coal Derived PV Materials have been initiated. Progress and initial results are reported. (WHK)

OSH technical reference manual

Energy Technology Data Exchange (ETDEWEB)

1993-11-01

In an evaluation of the Department of Energy (DOE) Occupational Safety and Health programs for government-owned contractor-operated (GOCO) activities, the Department of Labor`s Occupational Safety and Health Administration (OSHA) recommended a technical information exchange program. The intent was to share written safety and health programs, plans, training manuals, and materials within the entire DOE community. The OSH Technical Reference (OTR) helps support the secretary`s response to the OSHA finding by providing a one-stop resource and referral for technical information that relates to safe operations and practice. It also serves as a technical information exchange tool to reference DOE-wide materials pertinent to specific safety topics and, with some modification, as a training aid. The OTR bridges the gap between general safety documents and very specific requirements documents. It is tailored to the DOE community and incorporates DOE field experience.

Technical basis for exemption from alpha surveys for personnel, material, and equipment in the 324 facility

International Nuclear Information System (INIS)

RIDDELLE, J.G.

1998-01-01

The purpose of this document is to establish the technical basis for characterizing grouted B-Cell waste for disposal at the Hanford Burial Grounds using the 3-82B shipping cask. The scope of this document includes establishing the technical basis for loading the shipping package, an HN-200 Grout Container, to ensure that: (1) the amount of material in the grout container does not exceed the 100 nCl alpha/g limit that would cause the waste to be designated as ''greater that Category 3'' (GC3) or transuranic (TRU) waste (2) the amount of heat generated by the waste in the grout container does not exceed the 60 Watt heat generation limit established in the 3-82B shipping cask Safety Analysis Report (SAR); and (3) the dose rate on the surface of the shipping cask after loading does not exceed the 200 mrem/h limit established in the cask SAR. This document establishes the technical basis for performing measurements and analyses that will ensure that none of these three limits are exceeded

Technical Training: Technical Training Seminar

CERN Multimedia

2004-01-01

TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch Monday 9 February 2004 From 10:00 to 12:00 - IT Auditorium - bldg. 31, 3rd floor ANSOFT High-Frequency Seminar David Prestaux, Application Engineer, ANSOFT F-78535 BUC, France This Technical Training seminar will present two Ansoft application products: Ansoft HFSS and Ansoft Designer. Ansoft HFSS makes use of the Finite Element Method (FEM) to calculate field solutions from first principles. It can accurately predict all high-frequency behaviours such as dispersion, mode conversion, and losses due to materials and radiation. Ansoft Designer is a suite of design tools to fully integrate high-frequency, physics-based electromagnetic simulations into a seamless system-level simulation environment. Ansoft Designer uses a simple interface to give complete control over every design task, by a method allowing multiple solvers, Solver on Demand. • Introduction • Overview of the Ansoft Total solution • Ansoft HFSS 9...

Progress Report Oct to Dec 1975(2)

International Nuclear Information System (INIS)

1976-01-01

Progress report NO. 2 of Tehran Nuclear Research Centre outlines a brief description of the progress made in each section of the centre. A complete list of dissertations for Master's degrees studied at the Nuclear Research Centre and a list of new technical employee are given at the beginning of the report. Research activities in the third section include, isotope separation, laser research, radiation chemistry, reactor management, environmental research, neutron physics, reactor engineering, and nuclear medicine. The fourth section deals with education and training; technical support and health physics are discussed in sections five and six respectively

Progress report for '89

International Nuclear Information System (INIS)

Podest, M.

1990-08-01

The 1989 Progress Report presents the most important scientific and technical achievements of the Nuclear Research Institute's research work. Some specialized products prepared at or fabricated by the NRI are mentioned as well. (author). 24 figs., 8 tabs., 101 refs

C-Mod Collaboration Informal Technical Progress Report

International Nuclear Information System (INIS)

Kenneth W. Gentle

2007-01-01

The aims of the collaboration have not changed. A specific list of tasks was agreed upon during the Fall of 2006 in preparation for the 2007 C-Mod campaign by Earl Marmar, Head of the Alcator Project, Kenneth Gentle, Principal Investigator, and William Rowan, Collaboration Coordinator with the facilitation of Adam Rosenberg (DOE grant monitor for the collaboration). The activities follow the list of tasks and are discussed in this progress report

Meeting of the Technical Working Group on Fast Reactors (TWG-FR) (41st Annual Meeting). Working Material

International Nuclear Information System (INIS)

2008-01-01

The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 40th TWG-FR Annual Meeting, including the status of the actions; - Consider meeting arrangements for 2008, 2009, 2010 and beyond; - Review the IAEA’s ongoing information exchange and coordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives; - Discuss future joint activities in view of IAEA’s Programme and Budget Cycles beyond 2008-2009

Analytical methods for fissionable materials in the nuclear fuel cycle. Progress report, July 1, 1975--September 30, 1976

International Nuclear Information System (INIS)

Waterbury, G.R.

1976-12-01

Progress continued on development of dissolution techniques for difficult-to-dissolve nuclear materials, development of methods and automated instruments for determinations of plutonium and uranium, preparation of plutonium-containing materials for the Safeguards Analytical Laboratory Evaluation (SALE) program, analysis of SALE uranium materials, and measurement of plutonium isotope half-lives. Gas-solid reactions at elevated temperatures using reactive gases such as chlorine continue to show promise for separating uranium from refractory materials. An extensive study of nonaqueous solvents for the dissolution of refractory materials is in progress. An extraction-separation procedure, highly specific for microgram amounts of uranium, has been developed, and its adaptation to the Los Alamos Scientific Laboratory (LASL) automated spectrophotometer is being evaluated. Development of an electrometric analysis method for plutonium is nearing completion, and design of an automated instrument using the method has been started. Batches of plutonium oxide and mixed uranium--plutonium, intended for issue as Secondary Reference and Calibration Test Materials, are being recharacterized for assay and isotopic contents. The half-life of 239 Pu has been determined by isotope-dilution mass-spectrometric measurement of 235 U grow-in as a function of time

Analytical methods for fissionable materials in the nuclear fuel cycle. Progress report, July 1, 1975--September 30, 1976

Energy Technology Data Exchange (ETDEWEB)

Waterbury, G.R. (comp.)

1976-12-01

Progress continued on development of dissolution techniques for difficult-to-dissolve nuclear materials, development of methods and automated instruments for determinations of plutonium and uranium, preparation of plutonium-containing materials for the Safeguards Analytical Laboratory Evaluation (SALE) program, analysis of SALE uranium materials, and measurement of plutonium isotope half-lives. Gas-solid reactions at elevated temperatures using reactive gases such as chlorine continue to show promise for separating uranium from refractory materials. An extensive study of nonaqueous solvents for the dissolution of refractory materials is in progress. An extraction-separation procedure, highly specific for microgram amounts of uranium, has been developed, and its adaptation to the Los Alamos Scientific Laboratory (LASL) automated spectrophotometer is being evaluated. Development of an electrometric analysis method for plutonium is nearing completion, and design of an automated instrument using the method has been started. Batches of plutonium oxide and mixed uranium--plutonium, intended for issue as Secondary Reference and Calibration Test Materials, are being recharacterized for assay and isotopic contents. The half-life of /sup 239/Pu has been determined by isotope-dilution mass-spectrometric measurement of /sup 235/U grow-in as a function of time.

Review of Recent Progress of Plasmonic Materials and Nano-Structures for Surface-Enhanced Raman Scattering

Directory of Open Access Journals (Sweden)

Alan X. Wang

2015-05-01

Full Text Available Surface-enhanced Raman scattering (SERS has demonstrated single-molecule sensitivity and is becoming intensively investigated due to its significant potential in chemical and biomedical applications. SERS sensing is highly dependent on the substrate, where excitation of the localized surface plasmons (LSPs enhances the Raman scattering signals of proximate analyte molecules. This paper reviews research progress of SERS substrates based on both plasmonic materials and nano-photonic structures. We first discuss basic plasmonic materials, such as metallic nanoparticles and nano-rods prepared by conventional bottom-up chemical synthesis processes. Then, we review rationally-designed plasmonic nano-structures created by top-down approaches or fine-controlled synthesis with high-density hot-spots to provide large SERS enhancement factors (EFs. Finally, we discuss the research progress of hybrid SERS substrates through the integration of plasmonic nano-structures with other nano-photonic devices, such as photonic crystals, bio-enabled nanomaterials, guided-wave systems, micro-fluidics and graphene.

Annual Technical Progress Report of Radioisotope Power System Materials Production and Technical Program Tasks for October 1, 2005 through September 30, 2006

Energy Technology Data Exchange (ETDEWEB)

None

2007-04-02

The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2006. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new radioisotope power systems.

Progress report [of] Technical Physics Division

International Nuclear Information System (INIS)

Vijendran, P.; Deshpande, R.Y.

1975-01-01

Activities of the Technical Physics Division of the Bhabha Atomic Research Centre, Bombay, over the last few years are reported. This division is engaged in developing various technologies supporting the development of nuclear technology. The various fields in which development is actively being carried out are : (i) vacuum technology, (ii) mass spectrometry, (iii) crystal technology, (iv) cryogenics, and (v) magnet technology. For surface studies, the field emission microscope and the Auger electron spectrometer and other types of spectrometers have been devised and perfected. Electromagnets of requisite strength to be used in MHD programme and NMR instruments are being fabricated. Various crystals such as NaI(Tl), Ge, Fluorides, etc. required as windows and prisms in X and gamma-ray spectroscopy, have been grown. In the cryogenics field, expansion engines required for air liquefaction plants, vacuum insulated dewars, helium gas thermometers etc. have been constructed. In addition to the above, the Division provides consultancy and training to personnel from various institutions and laboratories. Equipment and systems perfected are transferred to commercial organizations for regular production. (A.K.)

The development of an e-learning software, ''Technical ethics''

International Nuclear Information System (INIS)

Matsue, Kazuki; Madarame, Haruki; Okamoto, Koji

2004-01-01

For the engineers and researchers, it is coming to the time when they are asked not only technical progress but also their ethics view. In this study, I aim to develop of the education software ''Technical Ethics'', which cultivates ethics view of the engineers. (author)

Research progress on organic-inorganic halide perovskite materials and solar cells

Science.gov (United States)

Ono, Luis K.; Qi, Yabing

2018-03-01

Owing to the intensive research efforts across the world since 2009, perovskite solar cell power conversion efficiencies (PCEs) are now comparable or even better than several other photovoltaic (PV) technologies. In this topical review article, we review recent progress in the field of organic-inorganic halide perovskite materials and solar cells. We associate these achievements with the fundamental knowledge gained in the perovskite research. The major recent advances in the fundamental perovskite material and solar cell research are highlighted, including the current efforts in visualizing the dynamical processes (in operando) taking place within a perovskite solar cell under operating conditions. We also discuss the existing technological challenges. Based on a survey of recently published works, we point out that to move the perovskite PV technology forward towards the next step of commercialization, what perovskite PV technology need the most in the coming next few years is not only further PCE enhancements, but also up-scaling, stability, and lead-toxicity.

Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

John Ross

2003-04-30

The Final Technical Report summarizes research accomplishments and Publications in the period of 5/1/99 to 4/30/03 done on the grant. Extensive progress was made in the period covered by this report in the areas of chemical kinetics of non-linear systems; spatial structures, reaction - diffusion systems, and thermodynamic and stochastic theory of electrochemical and general systems.

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. An extra issue: background of the geological disposal

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, an extra issue of the progress report, was prepared for the expected readers of the report to have background information on the geological disposal. Thus it gives information about (1) generation of high-level radioactive wastes, (2) history of plans proposed for HLW disposal in Japan, and (3) procedure until the geological disposal plan is finally adopted and basic future schedules. It further discusses on such problems in HLW treatment and disposal, as for example a problem of reliable safety for a very long period. (Ohno, S.)

GT-MHR COMMERCIALZATION STUDY. TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD JUNE 1 THROUGH JUNE 30, 2003

International Nuclear Information System (INIS)

SHENOY, A.S.

2003-01-01

A271 GT-MHR COMMERCIALZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD JUNE 1 THROUGH JUNE 30, 2003. Petten was provided with irradiation dimensional change data for both fuel compacts and H-451 graphite for design of the graphite sleeves that hold the fuel compacts to be irradiated in HFR-EU2. The Fuel Sample Product Specification for the Fuel Performance Irradiation Test Capsule MHR-2 was completed and approved. A Work Breakdown Structure was prepared for the development and qualification of advanced coated-particle fuels capable of meeting anticipated fuel performance requirements and work was initiated on preparation of schedules and a cost estimates for the test matrices

Electrical and Electronics Technical Team Roadmap

Energy Technology Data Exchange (ETDEWEB)

None

2013-06-01

The Electrical and Electronics Technical Team’s (EETT's) mission is to enable cost-effective, smaller, lighter, and efficient power electronics and electric motors for electric traction drive systems (ETDSs) while maintaining performance of internal combustion engine (ICE)-based vehicles. The EETT also identifies technology gaps, establishes R&D targets, develops a roadmap to achieve technical targets and goals, and evaluates the R&D progress toward meeting the established R&D targets and goals.

Enhanced surveillance program FY97 accomplishments. Progress report

Energy Technology Data Exchange (ETDEWEB)

Mauzy, A. [ed.; Laake, B. [comp.

1997-10-01

This annual report is one volume of the Enhanced Surveillance Program (ESP) FY97 Accomplishments. The complete accomplishments report consists of 11 volumes. Volume 1 includes an ESP overview and a summary of selected unclassified FY97 program highlights. Volume 1 specifically targets a general audience, reflecting about half of the tasks conducted in FY97 and emphasizing key program accomplishments and contributions. The remaining volumes of the accomplishments report are classified, organized by program focus area, and present in technical detail the progress achieved in each of the 104 FY97 program tasks. Focus areas are as follows: pits; high explosives; organics; dynamics; diagnostics; systems; secondaries; nonnuclear materials; nonnuclear components; and Surveillance Test Program upgrades.

Metals and ceramics division materials science program. Aunnual progress report for period ending June 30, 1979

International Nuclear Information System (INIS)

McHargue, C.J.; b.

1979-10-01

Progress is reported concerning theoretical studies of metals and alloys, deformation and mechanical properties, physical properties and transport phenomena, radiation effects, and engineering materials. During this period emphasis was shifted from support of nuclear technologies to support of nonnuclear energy systems

Progress report: Variable Energy Cyclotron Centre, Calcutta

International Nuclear Information System (INIS)

1999-01-01

This volume of the progress report brings out the scientific and technical activities of Variable Energy Cyclotron Centre, Calcutta during the year 1999. This includes brief review of the various R and D activities of the Centre and outside users of the cyclotron from the universities and other research institutes. The operational activities of the cyclotron with ECR ion sources, accelerator oriented research activities, activities on detector, target and electronics are reported. The activities of the Computer and Informatics group are described. The status report of the ongoing projects is also provided. The main activities of the superconducting cyclotron project, radioactive ion beam project, heavy ion experimental facility, advanced computational facility, recovery and analysis of helium from hot springs and material science research are described

ATR Technical Specification Upgrade Program

International Nuclear Information System (INIS)

McCracken, R.T.; Durney, J.L.; Freund, G.A.

1990-01-01

The Advanced Test Reactor (ATR) is a 250 MW, uranium-aluminum fueled test reactor which began full power operation in 1969. The initial operation was controlled by an Operating Limits document based on the original Safety Analysis Report. Additional safety bases were later developed to support Technical Specifications which were approved and implemented in 1977. The Technical Specifications which were initially developed with content and format specified in ANSI/ANS--15.1, ''The Development of Technical Specifications for Research Reactors.'' The safety basis documentation and the Technical Specifications have been updated as required to maintain them current with the ATR facility configuration. All revisions have been made with a content, format and style consistent with the original. A major, two-phase program to upgrade the content, format and style is in progress. This paper describes the first phase of this program

Technical considerations for detection of and response to illicit trafficking in radioactive materials

International Nuclear Information System (INIS)

Duftschmid, K.E.; Arlt, R.; Cunningham, J.; Gayral, J.P.; Kravchenko, N.; Smith, D.; York, R.

2001-01-01

Full text: The need for guidance and recommendations explicitly directed to the problem of illicit trafficking in nuclear materials and other radioactive sources was raised by the IAEA Director General at the IAEA General Conference in December 1994, and measures were agreed by the IAEA Board of Governors in March 1995. Measures that might be taken to prevent, detect, and respond to illicit trafficking will be common for all radioactive materials, including nuclear materials. However, nuclear materials are, or should be, subject also to safeguards for nuclear non-proliferation purposes and to physical protection to prevent diversion. The IAEA has established close co-operation with intergovernmental and non-governmental organizations, in particular the World Customs Organization (WCO) and INTERPOL to conduct joint studies, meetings and training programs to support Member States in their border control activities. Within this programme technical information has been derived on requirements and methods to detect and respond to events involving inadvertent movement of and illicit trafficking in radioactive materials. The paper summarises the most important results and the experience obtained in this field. Concerning 'detection' information on strategy of detection, selection of an investigation level, techniques for radiation monitoring at borders, verification of alarms, search techniques and identification of radionuclides has been developed. This includes recommended minimum requirements for monitoring equipment, derived from the results of an extended international pilot study on border monitoring equipment ITRAP, conducted by IAEA in co-operation with the Austrian government. In order to discover illicit trafficking or inadvertent movement in radioactive materials, the following steps are required: detection of any abnormal radiation level, verification of such detection, localisation of the origin of the radiation, radiation safety measurement, and

Technical progress report, 1 April-30 June 1981

Energy Technology Data Exchange (ETDEWEB)

None

1981-01-01

This report describes the technical accomplishments during the quarter ending June 1981, on the commercial nuclear waste management programs under the direction of the Office of Nuclear Waste Isolation (ONWI). The ONWI program is organized into 8 tasks entitled: systems, waste package, site, repository, regulatory and institutional, test facilities and excavations, land acquisition, and program management. Principal investigators in each of these areas have submitted summaries of quarterly highlights for inclusion in this report. Separate abstracts have been prepared for 5 of these tasks for inclusion in the Energy Data Base. (DMC)

Heavy-Section Steel Irradiation Program. Volume 5, No. 2, Progress report, April 1994--September 1994

International Nuclear Information System (INIS)

Corwin, W.R.

1995-07-01

The Heavy-Section Steel Irradiation (HSSI) Program has been established with its primary goal to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior and the fracture toughness properties of typical pressure-vessel steels as they relate to light-water RPV integrity. Effects of specimen size; material chemistry; product form and microstructure; irradiation fluence, flux, temperature, and spectrum; and postirradiation annealing are being examined on a wide range of fracture properties. The HSSI Program is arranged into 14 tasks: (1) program management, (2) fracture toughness curve shift in high-copper weldments (Series 5 and 6), (3) K lc and K la curve shifts in low upper-shelf (LUS) welds (Series 8), (4) irradiation effects in a commercial LUS weld (Series 10), (5) irradiation effects on weld heat-affected zone and plate materials (Series 11), (6) annealing effects in LUS welds (Series 9), (7) microstructural and microfracture analysis of irradiation effects, (8) in-service irradiated and aged material evaluations, (9) Japan Power Development Reactor (JPDR) steel examination, (10) fracture toughness curve shift method, (11) special technical assistance, (12) technical assistance for Joint Coordinating Committee on Civilian Nuclear Reactor Safety (JCCCNRS) Working Groups 3 and 12, (13) correlation monitor materials, and (14) test reactor coordination. Progress on each task is reported

Technical progress of nuclear energy: economic and environmental prospects

International Nuclear Information System (INIS)

Naudet, G.

1994-01-01

This document deals with three different aspects of the nuclear energy: first the operating and economic performances of nuclear power plants in the world, the French nuclear competitiveness. Then, the technical and economic perspectives about reactors and fuels cycle and the advantages towards atmospheric pollution are discussed to favour a new worldwide nuclear development. (TEC). 8 refs., 4 figs., 6 tabs

Medical Laboratory Technician--Hematology, Serology, Blood Banking & Immunohematology, 10-4. Military Curriculum Materials for Vocational and Technical Education.

Science.gov (United States)

Ohio State Univ., Columbus. National Center for Research in Vocational Education.

This course, the third of three courses in the medical laboratory technician field adapted from military curriculum materials for use in vocational and technical education, was designed as a refresher course for student self-study and evaluation. It is suitable for use by advanced students or beginning students participating in a supervised…

Metals and ceramics division materials science program. Aunnual progress report for period ending June 30, 1979

Energy Technology Data Exchange (ETDEWEB)

McHargue, C.J.

1979-10-01

Progress is reported concerning theoretical studies of metals and alloys, deformation and mechanical properties, physical properties and transport phenomena, radiation effects, and engineering materials. During this period emphasis was shifted from support of nuclear technologies to support of nonnuclear energy systems. (FS)

Self vs expert assessment of technical and non-technical skills in high fidelity simulation.

Science.gov (United States)

Arora, Sonal; Miskovic, Danilo; Hull, Louise; Moorthy, Krishna; Aggarwal, Rajesh; Johannsson, Helgi; Gautama, Sanjay; Kneebone, Roger; Sevdalis, Nick

2011-10-01

Accurate assessment is imperative for learning, feedback and progression. The aim of this study was to examine whether surgeons can accurately self-assess their technical and nontechnical skills compared with expert faculty members' assessments. Twenty-five surgeons performed a laparoscopic cholecystectomy (LC) in a simulated operating room. Technical and nontechnical performance was assessed by participants and faculty members using the validated Objective Structured Assessment of Technical Skills (OSATS) and the Non-Technical Skills for Surgeons scale (NOTSS). Assessment of technical performance correlated between self and faculty members' ratings for experienced (median score, 30.0 vs 31.0; ρ = .831; P = .001) and inexperienced (median score, 22.0 vs 28.0; ρ = .761; P = .003) surgeons. Assessment of nontechnical skills between self and faculty members did not correlate for experienced surgeons (median score, 8.0 vs 10.5; ρ = -.375; P = .229) or their more inexperienced counterparts (median score, 9.0 vs 7.0; ρ = -.018; P = .953). Surgeons can accurately self-assess their technical skills in virtual reality LC. Conversely, formal assessment with faculty members' input is required for nontechnical skills, for which surgeons lack insight into their behaviours. Copyright © 2011 Elsevier Inc. All rights reserved.

Nuclear theory research. Technical progress report

International Nuclear Information System (INIS)

1982-01-01

Progress is briefly described on the following studies: (1) Dirac phenomenology for deuteron elastic scattering, (2) Dirac wave functions in nuclear distorted wave calculations, (3) impulse approximation for p→p → dπ + reaction above the 3-3 resonance, (4) coherent π production, (5) nuclear potentials from Dirac bound state wavefunctions, (6) nonlocality effects in nuclear reactions, (7) unhappiness factors in DWBA description of (t,p) and (p,t) reactions, (8) absolute normalization of three-nucleon transfer reactions, (9) formulation of a finite-range CCBA computer program, (10) crossing symmetric solutions of the low equations, (11) pion scattering from quark bags, (12) study of the p 11 channel in the delta model, (13) isovector corrections in pion-nucleus scattering, (14) pionic excitation of nuclear giant resonances, and (15) isospin dependence of the second-order pion-nucleus optical potential

IAEA technical meeting on atomic and plasma-material interaction data for fusion science technology. Summary report

International Nuclear Information System (INIS)

Clark, R.E.H.

2003-10-01

The proceedings and conclusions of the Technical Meeting on 'Atomic and Plasma- Material Interaction Data for Fusion Science Technology' held in Juelich, Germany on October 28-31 are summarized. During the course of the meetings working groups were formed to review the status of specific areas of atomic, molecular and material physics of relevance to fusion and to make recommendations on data needs in fusion from these areas. The reports of those working groups are summarized and the complete reports included as appendices. This meeting brought together over fifty leading scientists in fusion related data. Results of research in a number of topics were presented and very useful discussions were held. The meeting was extremely successful. (author)

Basalt Waste Isolation Project Technical Program Evaluation Process: a criteria-based method

International Nuclear Information System (INIS)

Babad, H.; Evans, G.C.; Wolfe, B.A.

1982-01-01

The need to objectively evaluate the progress being made by the Basalt Waste Isolation Project (BWIP) toward establishing the feasibility of siting a nuclear waste repository in basalt (NWRB) mandates a process for evaluating the technical work of the project. To assist BWIP management in the evaluation process, the Systems Department staff has developed a BWIP Technical Program Evaluation Process (TPEP). The basic process relates progress on project technical work to the SWIP Functional and System Performance Criteria as defined in National Waste Terminal Storage (MWTS) Criteria Documents. The benefits of the TPEP to BWIP and future plans for TPEP are discussed. During fiscal year (FY) 1982, TPEP wll be further formalized and further applied to the review of BWIP technical activities

Development of incident progress prediction technologies for nuclear emergency preparedness. Current status and future subjects

International Nuclear Information System (INIS)

Yoshida, Yoshitaka; Yamamoto, Yasunori; Kusunoki, Takayoshi; Kawasaki, Ikuo; Yanagi, Chihiro; Kinoshita, Ikuo; Iwasaki, Yoshito

2014-01-01

Nuclear licensees are required to maintain a prediction system during normal condition for using a nuclear emergency by the Basic Plan for Disaster Prevention of government. With prediction of the incident progress, if the present condition of nuclear power plant is understood appropriately and it grows more serious with keeping the present situation, it is in predicting what kind of situation will be occurred in the near future, choosing the effective countermeasures against the coming threat, and understanding the time available of intervention time. Following the accident on September 30 1999 in the nuclear fuel fabrication facility in Tokai Village of Ibaraki Prefecture, the Institute of Nuclear Safety System started development of incident progress prediction technologies for nuclear emergency preparedness. We have performed technical applications and made improvements in nuclear emergency exercises and verified the developed systems using the observed values of the Fukushima Daiichi Nuclear Power Plant accident. As a result, our developed Incident Progress Prediction System was applied to nuclear emergency exercises and we accumulated knowledge and experience by which we improved the system to make predictions more rapidly and more precisely, including for example, the development of a prediction method for leak size of reactor coolant. On the other hand, if a rapidly progressing incident occurs, since end users need simple and quick predictions about the public's protection and evacuation areas, we developed the Radioactive Materials Release, Radiation Dose and Radiological Protection Area Prediction System which changed solving an inverse problem into a forward problem solution. In view of the water-level-decline incident of the spent fuel storage facility at the Fukushima Daiichi Nuclear Power Plant, the spent fuel storage facility water level and the water temperature evaluation tool were improved. Such incident progress prediction technologies were

Technical and Regulatory Considerations in Using Freight Containers as Industrial Packages

Energy Technology Data Exchange (ETDEWEB)

Hawk, Mark B [ORNL; Opperman, Erich [Washington Savannah River Company; Natali, Ronald [R. B. Natali Consulting, Inc.

2008-01-01

The US Department of Energy (DOE), Office of Environmental Management (EM), is actively pursuing activities to reduce the radiological risk and clean up the environmental legacy of the nation's nuclear weapons programmes. The EM has made significant progress in recent years in the clean-up and closure of sites and is also focusing on longer term activities necessary for the completion of the clean-up programme. The packaging and transportation of contaminated demolition debris and low level waste materials in a safe and cost effective manner are essential in completing this mission. Toward this end, the US Department of Transportation's Final Rule on Hazardous Materials Regulation issued on 26 January 2004, included a new provision authorising the use of freight containers (e.g. 20 and 40 ft ISO containers) as industrial packages type 2 or 3. This paper will discuss the technical and regulatory considerations in using these newly authorised and large packages for the packaging and transportation of low level waste materials.

Technical Progress Report on Application and Development of Appropriate Tools and Technologies for Cost-Effective Carbon Sequestration

Energy Technology Data Exchange (ETDEWEB)

Bill Stanley; Patrick Gonzalez; Sandra Brown; Jenny Henman; Ben Poulter; Sarah Woodhouse Murdock; Neil Sampson; Tim Pearson; Sarah Walker; Zoe Kant; Miguel Calmon; Gilberto Tiepolo

2006-06-30

The Nature Conservancy is participating in a Cooperative Agreement with the Department of Energy (DOE) National Energy Technology Laboratory (NETL) to explore the compatibility of carbon sequestration in terrestrial ecosystems and the conservation of biodiversity. The title of the research project is ''Application and Development of Appropriate Tools and Technologies for Cost-Effective Carbon Sequestration''. The objectives of the project are to: (1) improve carbon offset estimates produced in both the planning and implementation phases of projects; (2) build valid and standardized approaches to estimate project carbon benefits at a reasonable cost; and (3) lay the groundwork for implementing cost-effective projects, providing new testing ground for biodiversity protection and restoration projects that store additional atmospheric carbon. This Technical Progress Report discusses preliminary results of the six specific tasks that The Nature Conservancy is undertaking to answer research needs while facilitating the development of real projects with measurable greenhouse gas reductions. The research described in this report occurred between April 1st and July 30th 2006. The specific tasks discussed include: Task 1: carbon inventory advancements; Task 2: emerging technologies for remote sensing of terrestrial carbon; Task 3: baseline method development; Task 4: third-party technical advisory panel meetings; Task 5: new project feasibility studies; and Task 6: development of new project software screening tool. Work is being carried out in Brazil, Belize, Chile, Peru and the USA.

Analysis of Technical Status on the Application of Cementitious Materials for Radwaste Repository

International Nuclear Information System (INIS)

Kim, Jin Seop; Kwon, Sang Ki; Cho, Won Jin

2008-12-01

In this report, technical status on the application of cementitious materials and related research trends in Sweden, Switzerland and Japan etc. is listed based on the example of ONKALO in Finland. SKB and POSIVA have defined a pH limit ≤ 11 for cement grout leachates. To attain this pH, blending agents must comprise at least 50 wt % of dry materials. Because low pH cement has little, or no free portlandite, the cement consists predominantly of calcium silicate hydrate(CSH) gel with a Ca/Si ratio ≤ 0.8(Savage D. 2007). Silica fume as a blending agent is considered to be most promising for repository low-pH grouts. When adding silica fume to enhance cement quality, it demands high water content in cement paste. Then it is necessary to use additives such as superplasticiser to improve the workability of low-pH cement. Posiva, SKB and NUMO co-operated in developing low-pH grouts for deep repositories 2002-2005. Additionally, it is needed to study more about long-term performance characteristics, interaction of bentonite buffer material with high pH plume, influence on the migration/sorption of radionuclides and their performance numerical modeling. In this regards, international co-research projects such as ESDRED and IAEA CRP are being actively performed

Application progress of solid 29Si, 27Al NMR in the research of cement-based materials

International Nuclear Information System (INIS)

Feng Chunhua; Wang Xijian; Li Dongxu

2014-01-01

Background: The solid-state Nuclear Magnetic Resonance (NMR) is an effective method for the research of cement-based materials. Now it focuses on using solid 29 Si and 27 Al NMR to research the hydration structure of the cement-based materials in cement chemistry. Purpose: A theoretical guidance is proposed for solid 29 Si and 27 Al NMR technology used in cement chemistry research. Methods: We reviewed the application of solid 29 Si and 27 Al NMR in the cement-based materials and analyzed the problem among the researches. Results: This paper introduced an fundamental, relevant-conditions and basic parameters of NMR, and studied the technical parameters of solid 29 Si and 27 Ai NMR together with the relationship among the hydration structure of cement based material. Moreover, this paper reviewed the related domestic and overseas achievements in the research of hydration structure of the cement-based materials using solid 29 Si and 27 Al NMR. Conclusion: There were some problems in the research on cement-based materials by technology of solid 29 Si and 27 Al NMR. NMR will promote the Hydration theory of cement-based material greatly. (authors)

Technical Readiness and Gaps Analysis of Commercial Optical Materials and Measurement Systems for Advanced Small Modular Reactors

Energy Technology Data Exchange (ETDEWEB)

Anheier, Norman C.; Suter, Jonathan D.; Qiao, Hong (Amy); Andersen, Eric S.; Berglin, Eric J.; Bliss, Mary; Cannon, Bret D.; Devanathan, Ramaswami; Mendoza, Albert; Sheen, David M.

2013-08-06

This report intends to support Department of Energy’s Office of Nuclear Energy (DOE-NE) Nuclear Energy Research and Development Roadmap and industry stakeholders by evaluating optical-based instrumentation and control (I&C) concepts for advanced small modular reactor (AdvSMR) applications. These advanced designs will require innovative thinking in terms of engineering approaches, materials integration, and I&C concepts to realize their eventual viability and deployability. The primary goals of this report include: 1. Establish preliminary I&C needs, performance requirements, and possible gaps for AdvSMR designs based on best available published design data. 2. Document commercial off-the-shelf (COTS) optical sensors, components, and materials in terms of their technical readiness to support essential AdvSMR in-vessel I&C systems. 3. Identify technology gaps by comparing the in-vessel monitoring requirements and environmental constraints to COTS optical sensor and materials performance specifications. 4. Outline a future research, development, and demonstration (RD&D) program plan that addresses these gaps and develops optical-based I&C systems that enhance the viability of future AdvSMR designs. The development of clean, affordable, safe, and proliferation-resistant nuclear power is a key goal that is documented in the Nuclear Energy Research and Development Roadmap. This roadmap outlines RD&D activities intended to overcome technical, economic, and other barriers, which currently limit advances in nuclear energy. These activities will ensure that nuclear energy remains a viable component to this nation’s energy security.

Strengthening the material-technical base of modern agrarian ...

African Journals Online (AJOL)

At present, in agriculture there is a tendency of equipment obsolescence and break ... by means of acquisition of high-energy, high-performance equipment and the ... and to make recommendations for the development of technical capacity.

Alloy development for irradiation performance. Semiannual progress report for period ending September 30, 1985

International Nuclear Information System (INIS)

1986-02-01

This report is the twenty-second in a series of Technical Progress Reports on ''Alloy Development for Irradiation Performance'' (ADIP), which is one element of the Fusion Reactor Materials Program, conducted in support of the magnetic Fusion Energy Program of the US Department of energy. This report is organized along topical lines with Chapters 3 through 8 devoted to the various alloy classes that are currently under investigation. Thus the work of a given laboratory may appear at several different places in the report. The materials compatibility and environmental effects work on all alloy classes is collected together in Chapter 9. The Table of Contents is annotated for the convenience of the reader

Technical meeting to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)'. Working material

International Nuclear Information System (INIS)

2003-01-01

36th Annual Meeting of the Technical Working Group on Fast Reactors, the IAEA Technical Meeting (TM) on 'Review of National Programmes on Fast Reactors and Accelerator Driven Systems (ADS)', hosted by the Korean Atomic Energy Research Institute (KAERI) was attended by TWG-FR Members and Advisers from the following Member States (MS) and International Organizations: Brazil, France, Germany, India, Japan, the Republic of Kazakhstan, the Republic of Korea, the Russian Federation, the United Kingdom, the United States of America, and the OECD/NEA. The objectives of the meeting were to: 1) exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); 2) review the progress since the 35th TWG-FR Annual Meeting, including the status of the actions; 3) consider meeting arrangements for 2003 and 2004; 4) review the Agency's co-ordinated research activities in the field of FRs and ADS, as well as co-ordination of the TWG-FR's activities with other organizations. The participants made presentations on the status of the respective national programmes on FR and ADS development. A summary of the highlights for the period since the 35th TWG-FR Annual Meeting

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)

Recent progresses and achievements in photovoltaic-phase change material technology: A review with special treatment on photovoltaic thermal-phase change material systems

International Nuclear Information System (INIS)

Islam, M.M.; Pandey, A.K.; Hasanuzzaman, M.; Rahim, N.A.

2016-01-01

Highlights: • Broad summary of phase change materials based cooling for photovoltaic modules. • Compendium on phase change materials that are mostly used in photovoltaic systems. • Extension of heat availability period by 75–100% with phase change material. • Heat storage potential improves by 33–50% more with phase change material. • Future trend and move in photovoltaic thermal research. - Abstract: This communication lays out an appraisal on the recent works of phase change materials based thermal management techniques for photovoltaic systems with special focus on the so called photovoltaic thermal-phase change material system. Attempt has also been made to draw wide-ranging classification of both photovoltaic and photovoltaic thermal systems and their conventional cooling or heat harvesting methods developed so far so that feasible phase change materials application area in these systems can be pointed out. In addition, a brief literature on phase change materials with particular focus on their solar application has also been presented. Overview of the researches and studies establish that using phase change materials for photovoltaic thermal control is technically viable if some issues like thermal conductivity or phase stability are properly addressed. The photovoltaic thermal-phase change material systems are found to offer 33% (maximum 50%) more heat storage potential than the conventional photovoltaic-thermal water system and that with 75–100% extended heat availability period and around 9% escalation in output. Reduction in temperature attained with photovoltaic thermal-phase change material system is better than that with regular photovoltaic-thermal water system, too. Studies also show the potential of another emerging technology of photovoltaic thermal-microencapsulated phase change material system that makes use of microencapsulated phase change materials in thermal regulation. Future focus areas on photovoltaic thermal-phase change

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 3. Safety assessment for geological disposal systems

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, the part 3 of the progress report, concerns safety assessment for geological disposal systems definitely introduced in part 1 and 2 of this series and consists of 9 chapters. Chapter I concerns the methodology for safety assessment while Chapter II deals with diversity and uncertainty about the scenario, the adequate model and the required data of the systems above. Chapter III summarizes the components of the geological disposal system. Chapter IV refers to the relationship between radioactive wastes and human life through groundwater, i.e. nuclide migration. In Chapter V is made a reference case which characterizes the geological environmental data using artificial barrier specifications. (Ohno. S.)

Defining a Progress Metric for CERT RMM Improvement

Science.gov (United States)

2017-09-14

REV-03.18.2016.0 Defining a Progress Metric for CERT-RMM Improvement Gregory Crabb Nader Mehravari David Tobar September 2017 TECHNICAL ...fendable resource allocation decisions. Technical metrics measure aspects of controls implemented through technology (systems, soft- ware, hardware...implementation metric would be the percentage of users who have received anti-phishing training . • Effectiveness/efficiency metrics measure whether

Introducing errors in progress ratios determined from experience curves

NARCIS (Netherlands)

van Sark, W.G.J.H.M.

2008-01-01

Progress ratios (PRs) derived from historical data in experience curves are used for forecasting development of many technologies as a means to model endogenous technical change in for instance climate–economy models. These forecasts are highly sensitive to uncertainties in the progress ratio. As a

The Basalt Waste Isolation Project technical program evaluation process: A criteria-based method

International Nuclear Information System (INIS)

Babad, H.; Evans, C.; Wolfe, B.A.

1982-01-01

The need to objectively evaluate the progress being made by the Basalt Waste Isolation Project (BWIP) toward establishing the feasibility of siting a nuclear waste repository in basalt (NWRB) mandates a process for evaluating the technical work of the project. To assist BWIP management in the evaluation process, the Systems Department staff has developed a BWIP Technical Program Evaluation Process (TPEP). The basic process relates progress on project technical work to the BWIP Functional and System Performance Criteria as defined in National Waste Terminal Storage (NWTS) Criteria Documents. The benefits of the TPEP to BWIP and future plans for TPEP are discussed. During fiscal year (FY) 1982, TPEP will be further formalized and further applied to the review of BWIP technical activities

History of Resistance Welding Oxide Dispersion Strengthened Cladding and other High Temperature Materials at Center for Advanced Energy Studies

International Nuclear Information System (INIS)

Zirker, Larry; Jerred, Nathan; Charit, Indrajit; Cole, James

2012-01-01

Research proposal 08-1079, 'A Comparative Study of Welded ODS Cladding Materials for AFCI/GNEP,' was funded in 2008 under an Advanced Fuel Cycle Initiative (AFCI) Research and Development Funding Opportunity, number DE-PS07-08ID14906. Th proposal sought to conduct research on joining oxide dispersion strengthen (ODS) tubing material to a solid end plug. This document summarizes the scientific and technical progress achieved during the project, which ran from 2008 to 2011.

Recent progress and tests of radiation resistant impregnation materials for Nb3Sn coils

International Nuclear Information System (INIS)

Bossert, R.; Krave, S.; Ambrosio, G.; Andreev, N.; Chlachidze, G.; Nobrega, A.; Novitski, I.; Yu, M.; Zlobin, A. V.

2014-01-01

Fermilab is collaborating with Lawrence Berkeley National Laboratory (LBNL) and Brookhaven National Laboratory (BNL) (US-LARP collaboration) to develop a large-aperture Nb 3 Sn superconducting quadrupole for the Large Hadron Collider (LHC) luminosity upgrade. An important component of this work is the development of materials that are sufficiently radiation resistant for use in critical areas of the upgrade. This paper describes recent progress in characterization of materials, including the baseline CTD101K epoxy, cyanate ester blends, and Matrimid 5292, a bismaleimide-based system. Structural properties of “ten stacks” of cable impregnated with these materials are tested at room and cryogenic temperatures and compared to the baseline CT-101K. Experience with potting 1 and 2 meter long coils with Matrimid 5292 are described. Test results of a single 1-m coil impregnated with Matrimid 5292 are reported and compared to similar coils impregnated with the traditional epoxy

Recent progress and tests of radiation resistant impregnation materials for Nb3Sn coils

Science.gov (United States)

Bossert, R.; Krave, S.; Ambrosio, G.; Andreev, N.; Chlachidze, G.; Nobrega, A.; Novitski, I.; Yu, M.; Zlobin, A. V.

2014-01-01

Fermilab is collaborating with Lawrence Berkeley National Laboratory (LBNL) and Brookhaven National Laboratory (BNL) (US-LARP collaboration) to develop a large-aperture Nb3Sn superconducting quadrupole for the Large Hadron Collider (LHC) luminosity upgrade. An important component of this work is the development of materials that are sufficiently radiation resistant for use in critical areas of the upgrade. This paper describes recent progress in characterization of materials, including the baseline CTD101K epoxy, cyanate ester blends, and Matrimid 5292, a bismaleimide-based system. Structural properties of "ten stacks" of cable impregnated with these materials are tested at room and cryogenic temperatures and compared to the baseline CT-101K. Experience with potting 1 and 2 meter long coils with Matrimid 5292 are described. Test results of a single 1-m coil impregnated with Matrimid 5292 are reported and compared to similar coils impregnated with the traditional epoxy.

Progress in Gamma Ray Measurement Information Barriers for Nuclear Material Transparency Monitoring

International Nuclear Information System (INIS)

Wolford, J.K.; White, G.K.

2000-01-01

Negotiations between technical representatives of the US and the Russian Federation in support of several pending nuclear arms and nuclear material control agreements must take account of the need for assurances against the release of sensitive information. Most of these agreements involve storing nuclear material and in some cases nuclear components from stockpile weapons in specially designed containers. Strategies for monitoring the agreements typically include measuring neutron and gamma radiation from the controlled items to verify declared attributes of plutonium or highly enriched uranium. If accurate enough to be useful, these measurements will contain information about the design of the component being monitored, information considered sensitive by one or both parties to the agreement. Safeguards have evolved to prevent disclosure of this information during inspections. These measures combine hardware, software, and procedural measures to contain the sensitive data, presenting only the results needed for verification. Custom features preserve data security and guard against disclosure in case of failure. This paper summarizes the general problem and discusses currently developing solutions for a high resolution gamma ray detection system. It argues for the simplest possible implementation of several key system components

Feed-in tariffs versus quotas: how to promote renewable s and stimulate technical progress for cost decrease?

International Nuclear Information System (INIS)

Menanteau, Ph.; Finon, D.; Lamy, M.L.

2002-01-01

Incentive schemes for the development of renewable energy sources may focus on quantities (defining national targets and setting up bidding systems, or quota systems providing for green certificate trading), or they may focus on prices (feed-in tariffs). Whatever the system chosen, the role of the public authorities is quite specific: to stimulate technical progress and speed up the technological learning processes so that ultimately renewable energy technologies will be able to compete with conventional technologies, once the environmental costs have been internalized. A comparison of instruments must thus take into account the characteristics of the innovation process and adoption conditions (uncertainties regarding cost curves, learning effects) which means also looking at dynamic efficiency criteria. The paper concludes that a system of feed-in tariffs is more efficient than a bidding system, but highlights the theoretical interest of green certificate trading which must be confirmed through practice, given the influence of market structures and rules on the performance of this type of approach. (author)

High temperature metallic materials for gas-cooled reactors

International Nuclear Information System (INIS)

1989-06-01

The Specialists' Meeting was organized in conjunction with an earlier meeting on this topic held in Vienna, Austria, 1981, which provided for a comprehensive review of the status of materials development and testing at that time and for a description of test facilities. This meeting provided an opportunity (1) to review and discuss the progress made since 1981 in the development, testing and qualification of high temperature metallic materials, (2) to critically assess results achieved, and (3) to give directions for future research and development programmes. In particular, the meeting provided a form for a close interaction between component designers and materials specialists. The meeting was attended by 48 participants from France, People's Republic of China, Federal Republic of Germany, Japan, Poland, Switzerland, United Kingdom, USSR and USA presenting 22 papers. The technical part of the meeting was subdivided into four technical sessions: Components Design and Testing - Implications for Materials (4 papers); Microstructure and Environmental Compatibility (4 papers); Mechanical Properties (9 papers); New Alloys and Developments (6 papers). At the end of the meeting a round table discussion was organized in order to summarize the meeting and to make recommendations for future activities. This volume contains all papers presented at the meeting. A separate abstract was prepared for each of these papers. Refs, figs and tabs

How to be an Effective Technical Writer?

OpenAIRE

M Solaiman Ali; Dheya Al-Othmany

2012-01-01

Abstract--This paper has focused on technical writing as a skill for engineers. It has sought to define technical writing and throw light on the content and technique of writing the various components of successful technical reports (for example, articles, papers, or research reports, such as theses and dissertations). Then, it has highlighted other special features and principles of effective technical writing. The material in this paper is divided into seven major parts. Part 1 (Technical w...

Advanced research and technology development fossil energy materials program. Quarterly progress report for the period ending September 30, 1981

Energy Technology Data Exchange (ETDEWEB)

Bradley, R.A. (comp.)

1981-12-01

This is the fourth combined quarterly progress report for those projects that are part of the Advanced Research and Technology Development Fossil Energy Materials Program. The objective is to conduct a program of research and development on materials for fossil energy applications with a focus on the longer-term and generic needs of the various fossil fuel technologies. The program includes research aimed toward a better understanding of materials behavior in fossil energy environments and the development of new materials capable of substantial enhancement of plant operations and reliability. Work performed on the program generally falls into the Applied Research and Exploratory Development categories as defined in the DOE Technology Base Review, although basic research and engineering development are also conducted. A substantial portion of the work on the AR and TD Fossil Energy Materials Program is performed by participating cntractor organizations. All subcontractor work is monitored by Program staff members at ORNL and Argonne National Laboratory. This report is organized in accordance with a work breakdown structure defined in the AR and TD Fossil Energy Materials Program Plan for FY 1981 in which projects are organized according to fossil energy technologies. We hope this series of AR and TD Fossil Energy Materials Program quarterly progress reports will aid in the dissemination of information developed on the program.

Progress on EPRI electrical equipment qualification research

International Nuclear Information System (INIS)

Sliter, G.E.

1983-01-01

The objective of EPRI's electrical equipment qualification research program is to provide technical assistance to utilities in meeting nuclear plant safety requirements in a manner consistent with the state of the art. This paper reports progress on several research projects including: radiation effects studies, which compile data on degradation of organic materials in electrical equipment exposed to operational and accident radiation doses; the Equipment Qualification Data Bank, which is a remotely accessible computer system for disseminating qualification information on in-plant equipment, seismic data, and materials data; an aging/seismic correlation program, which is providing test data showing that, in many cases, age degradation has a negligibly small effect on the performance of electrical components under seismic excitation; a review of condition monitoring techniques, which has identified surveillance methods for measuring key performance parameters that have the potential for predicting remaining equipment life; and large-scale hydrogen burn equipment response tests, which are providing data to assess the ability of equipment to remain functional during and after hydrogen burning in postulated degraded core accidents

Technical obstacles to nuclear security - Russian perspective

International Nuclear Information System (INIS)

Pshakin, G.

2005-01-01

Full text: Present political, economical and social development the world - wide and in particular countries and regions facilitate number of serious and dangerous challenges for people responsible for security of materials and facilities, which could be used as a threat to the humankind in case of unauthorized approach. A number of factors have impact on the security including political, social, financial and technical nature. The security of nuclear materials and facilities where nuclear materials located and under processing is facing a number of problems such as control of the personnel who is handling the materials, access to the materials and the facilities, accounting and control of the materials storage, transportation, transactions, processing, physical protection of the materials. Each aspect of those problems must be taken into account for establishing most efficient way to keep the nuclear materials out of hands of the terrorists. Technical aspects which require serious and intent relation from political and technical communities in Russia (as example) are the following: legal base for nuclear materials protection, control and accounting and export control; personnel for nuclear materials control and accounting - skill, reliability, responsibility, training and new generation education; personnel for physical protection - skill, reliability, responsibility, training; structure of the system and equipment for materials control, verification, accountability; structure of the system and equipment for physical protection; regulatory supervision of the MPC+A system effectiveness. (author)

Mechanical Engineering Department Technical Review

International Nuclear Information System (INIS)

Carr, R.B.; Denney, R.M.

1981-01-01

The Mechanical Engineering Department Technical Review is published to inform readers of various technical activities within the Department, promote exchange of ideas, and give credit to personnel who are achieving the results. The report is presented in two parts: technical achievements and publication abstracts. The first is divided into seven sections, each of which reports on an engineering division and its specific activities related to nuclear tests, nuclear explosives, weapons, energy systems, engineering sciences, magnetic fusion, and materials fabrication

TECHNICAL CULTURE AND HUMAN AXJOSPHERE

OpenAIRE

­Krystyna Chałas

2014-01-01

Technical culture is the value of each historical period. It is the subject of the ongoing development. While it is a value which is associated with different categories of values, mainly material, cognitive, social. Between culture and these three categories of values ​ there is a cognitive effect. Technical culture determines the quality of human axjosphere. The aim of this study is to show the relationships and dependencies between technical culture and the structures in which a person liv...

Progress report for 1978-79, Technical Physics Division

International Nuclear Information System (INIS)

Gopalaraman, C.P.; Deshpande, R.Y.

1980-01-01

The research and development activities of the Technical Physics Division (TPD) of the Bhabha Atomic Research Centre, Bombay, during the calendar years 1978 and 1979 are reported. The TPD's major areas of work are electronics instrumentation, crystal technology, mass spectrometers, cryogenic equipment and vacuum equipment. Some of the major achievements are: (1) fabrication of various electronic instruments and components for the pulsed nuclear magnetic resonance spectrometers, (2) growth of large size NaI(Tl) and Ge crystals, (3) growth of CsI, KDP and arsenic selenide crystals, (4) fabrication of quadrupole mass filters and (5) fabrication of mass spectrometers for gas analysis and D/H analysis in water samples. (M.G.B.)

A Preliminary Rhetoric of Technical Copywriting.

Science.gov (United States)

Henson, Leigh

1994-01-01

Discusses the rhetorical elements of technical copywriting, including its shared communicative aims with technical writing; authorship considerations such as ethics, education, and professionalism; and the concerns of promotional strategy, audience analysis, choice of media and materials, writing strategy, and style. (SR)

Improving the Technology of Obtaining Technical Ethanol from Alternative Raw Materials

Directory of Open Access Journals (Sweden)

Sergіj Petrov

2018-05-01

Full Text Available The purpose of the article is to study the properties of fallen leaves as raw materials for the production of bioethanol; Improvement of the technology of recycling cellulosic raw materials into bioethanol in the most energy-efficient and ecological way. As a result of the study, it has been found out that the production of biofuels from renewable raw materials is characterized by features of innovative technology: the rapid growth of this sector of economy is accompanied by a significant increase in market share. The use of fallen leaves as raw material will eliminate the current conflict of interests associated with the use of food raw materials for the production of bioethanol, will prevent the withdrawal of resources from the sphere of food production. Significant positive factors in the production and use of biofuels are improvement of environmental conditions, reduction of the harmful effects of exhaust gases on the human body, reducing environmental pollution and, consequently, reducing morbidity and associated costs of medical care. The use of bioethanol as an ecobiopilot makes it possible to increase the octane number of fuel, and, accordingly, increase the efficiency of the engine. Thus, the use of bioethanol leads to a qualitative improvement of technical and economic indicators, which is also an indicator of innovation. The threat of reducing (exhausting non-renewable sources of energy is also the factor that necessitates the development and improvement of biofuel production technology. The relatively low profitability of biofuel production is due to the low yield of the target product and the high cost of pre-treatment of cellulose raw materials. The method of obtaining bioethanol from renewable non-demanded raw materials - fallen leaves - was improved. The technique allows to increase the bioethanol yield due to more effective hydrolysis of hard-hydrolysable polysaccharides. Further development of the study of the differences in

Sources of technical assistance

International Nuclear Information System (INIS)

Laue, H.J.

1977-01-01

This paper shows examples of technical assistance programmes within bilateral cooperation agreements between the Federal Republic of Germany and a number of developing countries of very different characteristics and summarizes the possibilities of technical assistance granted by international organizations, such as IAEA, UNDP, etc. A basic requirement for a successful transfer of technology is a high knowledge level of the indigenous scientists and engineers. Therefore, programmes for training and education and for information exchange are presented. Based on these, the means and methods of planning, performance and quality assurance are explained by practical examples and are related to the progress achieved in the use of nuclear energy and in establishing a national industry in the developing countries. (orig.) [de

GPHS-RTGs in support of the Cassini Mission. Semi-annual technical progress report, April 3, 1995--October 1, 1995

International Nuclear Information System (INIS)

1995-01-01

This document is the April-October 1995 Progress Report on the Cassini RTG Program. Nine tasks are summarized; (1) Spacecraft integration and liason, (2) Engineering support, (3) Safety, (4) Unicouple fabrication, (5) ETG fabrication, assembly, and test, (6) Ground support equipment, (7) RTG shipping and launch support, (8) Design, reviews, and mission applications, and (9) Project management, QA, contract changes, and material acquisitions

Geothermal progress monitor. Progress report No. 3, March-April 1980

Energy Technology Data Exchange (ETDEWEB)

1980-01-01

Progress is reviewed in the following areas: electric uses; direct heat uses; drilling activities; exploration; leases; outreach and technical assistance; feasibility studies and application demonstrations; geothermal loan guarantee program; general activities; R and D activities; legal, institutional, and regulatory activities; environmental activities; and state, local, and private sector activities. Also included are a list of reports and publications and a directory of individuals in the geothermal community. (MHR)

DOE progress in assessing the long term performance of waste package materials

International Nuclear Information System (INIS)

Berusch, A.; Gause, E.

1987-01-01

Under the Nuclear Waste Policy Act of 1982 (NWPA)[1], the US Dept. of Energy (DOE) is conducting activities to select and characterize candidate sites suitable for the construction and operation of a geologic repository for the disposal of high-level nuclear wastes. DOE is funding three first repository projects: Basalt Waste Isolation Project, BWIP; Nevada Nuclear Waste Isolation Project, NNWSI; and Salt Repository Project Office, SRPO. It is essential in the licensing process that DOE demonstrate to the NRC that the long-term performance of the materials and design will be in compliance with the requirements of 10 CFR 60.113 on substantially complete containment within the waste packages for 300 to 1000 years and a controlled release rate from the engineered barrier system (EBS) for 10,000 years of 1 part in 10 5 per year for radionuclides present in defined quantities 100 years after permanent closure. Obviously, the time spans involved make it impractical to base the assessment of the long term performance of waste package materials on real time, prototypical testing. The assessment of performance will be implemented by the use of models that are supported by real time field and laboratory tests, monitoring, and natural analog studies. Each of the repository projects is developing a plan for demonstrating long-term waste package material performance depending on the particular materials and the package-perturbed, time-dependent environment under which the materials must function. An overview of progress in each of these activities for each of the projects is provided in the following

Current technical issues in international safeguards

International Nuclear Information System (INIS)

Bennett, C.A.

1977-01-01

Safeguards systems, and the associated need for technical and systems development, reflect changing conditions and concerns associated with the nuclear fuel cycle and the safety and security of nuclear materials and facilities. In particular, the implementation of international safeguards has led to the recognition of certain technical issues, both old and new, which are in need of resolution. These are: 1. The grading of nuclear materials and facilities with respect to their relative safeguards significance. 2. The extension and upgrading of safeguards techniques to maintain adequate protection in view of constantly increasing amounts of material to be safeguarded. 3. The balance between safeguards mechanisms based on physical protection and material accounting, and the role of surveillance and containment in each case. 4. The role of information systems as a basis for both analytical feedback and the determination of the factors affecting system effectiveness and their interrelationship. 5. A determination of the degree to which the overall technical effectiveness of international inspection activities can be quantified. Each of these technical issues must be considered in light of the specific objectives of international safeguards, which differ from domestic safeguards in terms of the level of the threat, the safeguards mechanisms available, and the diversion strategies assumed. Their resolution in this international context is essential if the effectiveness and viability of international safeguards are to be maintained

Inkjet printing metals on flexible materials for plastic and paper electronics

DEFF Research Database (Denmark)

Al-Shamery, K.; Raut, N. C.

2018-01-01

Inorganic printed electronics is now recognized as an area of tremendous commercial, potential and technical progress. Many research groups are actively involved worldwide in developing metal nanoparticle inks and precursors for printing inorganic/organic materials using different printing....... Besides some examples demonstrating aspects on ink formulation via patterning solid surfaces such as glass and silicon oxide, special emphasis will be placed on compatibility for usage in plastic and paper electronics. Printing of nanoparticles of copper, silver, gold etc. will be discussed...... and will be compared to printing of a variety of metal-organic precursor inks. Finally, a brief account on exemplary applications using the printed inorganic nanoparticles/materials is provided....

Progress in MPC and A upgrades at Luch

International Nuclear Information System (INIS)

Mizin, P.; Chukov, V.; Rogatchev, V.; Curtiss, J.; Erkkila, B.; Goodey, K.; Hembree, D. Jr.; Lowe, D.; Turner, C.

1997-01-01

Luch, a MINATOM facility, has been engaged in both scientific research and uranium processing for fifty years. Since the spring of 1996, Luch has participated in a program of US/Russia Cooperation in Nuclear MPC and A Upgrades. The program began with planning for immediate upgrades in MPC and A, with en emphasis on physical protection. In addition, US and Luch experts exchanged technical data during a number of workshops, to establish a common understanding of available MPC and A tools and equipment. Site characterizations and vulnerability assessments were then prepared by Luch, to form the basis for the current program of methodical upgrades in all areas of MPC and A. Access control, alarms and alarm communications are being improved as part of this program. Control of nuclear material is being enhanced through improvements in material monitoring and in transportation security when nuclear material is moved between buildings on the Luch site. A comprehensive, site-wide computer network for Luch was designed during a recent workshop. Acquiring and installing this computer system, complete with COREMAS software, is currently in progress. Nuclear material analysis will be improved through NDA techniques using Canberra InSpector systems. The planned upgrades in nuclear MPC and A will reinforce safeguards over large quantities of HEU at Luch

River Protection Project waste feed delivery program technical performance measurement assessment plan

International Nuclear Information System (INIS)

O'TOOLE, S.M.

1999-01-01

This plan establishes a formal technical performance-monitoring program. Technical performance is assessed by establishing requirements based performance goals at the beginning of a program and routinely evaluating progress in meeting these goals at predetermined milestones throughout the project life cycle

Integral Fast Reactor Program annual progress report, FY 1994

International Nuclear Information System (INIS)

Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, J.J.

1994-12-01

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1994. Technical accomplishments are presented in the following areas of the IFR technology development activities: metal fuel performance; pyroprocess development; safety experiments and analyses; core design development; fuel cycle demonstration; and LMR technology R ampersand D

ATF Neutron Irradiation Program Technical Plan

Energy Technology Data Exchange (ETDEWEB)

Geringer, J. W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division; Katoh, Yutai [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division

2016-03-01

The Japan Atomic Energy Agency (JAEA) under the Civil Nuclear Energy Working Group (CNWG) is engaged in a cooperative research effort with the U.S. Department of Energy (DOE) to explore issues related to nuclear energy, including research on accident-tolerant fuels and materials for use in light water reactors. This work develops a draft technical plan for a neutron irradiation program on the candidate accident-tolerant fuel cladding materials and elements using the High Flux Isotope Reactor (HFIR). The research program requires the design of a detailed experiment, development of test vehicles, irradiation of test specimens, possible post-irradiation examination and characterization of irradiated materials and the shipment of irradiated materials to JAEA in Japan. This report discusses the technical plan of the experimental study.

FY2016 Advanced Batteries R&D Annual Progress Report - Part 4 of 5

Energy Technology Data Exchange (ETDEWEB)

None, None

2017-08-31

The Advanced Batteries research and development (R&D) subprogram within the DOE Vehicle Technologies Office (VTO) provides support and guidance for projects focusing on batteries for plug-in electric vehicles. Program targets focus on overcoming technical barriers to enable market success including: (1) significantly reducing battery cost, (2) increasing battery performance (power, energy, durability), (3) reducing battery weight & volume, and (4) increasing battery tolerance to abusive conditions such as short circuit, overcharge, and crush. This report describes the progress made on the research and development projects funded by the Battery subprogram in 2016. This section covers Advanced Battery Materials Research (BMR) part 1.

Recent progresses in materials for the direct methanol fuel cell

Energy Technology Data Exchange (ETDEWEB)

Lamy, C; Leger, J M [Centre National de la Recherche Scientifique (CNRS), 86 - Poitiers (France)

1998-12-31

Research programs are being conducted worldwide to develop a clean, zero emissions electric vehicle. However, even with the most advanced batteries, such as nickel/metal hydride, or lithium ion batteries, the driving range is limited and the recharging time is long. Only fuel cells which can convert chemical energy directly into electrical energy can compete with internal combustion engines. This paper reviewed the recent progress made in the development of a direct methanol fuel cell using the concept developed for the proton exchange membrane fuel cell (PEMFC). It was noted that the electrode materials, at the methanol anode and oxygen cathode need to be improved by using multifunctional electrocatalysts. The development of new temperature resistant proton exchange membranes with good ionic conductivity and low methanol cross-over, which resulted from the need to increase operating temperatures above 100 degrees C was also reviewed. 35 refs., 1 tab., 2 figs.

History of Resistance Welding Oxide Dispersion Strengthened Cladding and other High Temperature Materials at Center for Advanced Energy Studies

Energy Technology Data Exchange (ETDEWEB)

Larry Zirker; Nathan Jerred; Dr. Indrajit Charit; James Cole

2012-03-01

Research proposal 08-1079, 'A Comparative Study of Welded ODS Cladding Materials for AFCI/GNEP,' was funded in 2008 under an Advanced Fuel Cycle Initiative (AFCI) Research and Development Funding Opportunity, number DE-PS07-08ID14906. Th proposal sought to conduct research on joining oxide dispersion strengthen (ODS) tubing material to a solid end plug. This document summarizes the scientific and technical progress achieved during the project, which ran from 2008 to 2011.

Laboratory Directed Research and Development FY 1998 Progress Report

Energy Technology Data Exchange (ETDEWEB)

John Vigil; Kyle Wheeler

1999-04-01

This is the FY 1998 Progress Report for the Laboratory Directed Research and Development (LDRD) Program at Los Alamos National Laboratory. It gives an overview of the LDRD Program, summarizes work done on individual research projects, relates the projects to major Laboratory program sponsors, and provides an index to the principle investigators. Project summaries are grouped by their LDRD component: Competency Development, Program Development, and Individual Projects. Within each component, they are further grouped into nine technical categories: (1) materials science, (2) chemistry, (3) mathematics and computational science, (4) atomic, molecular, optical, and plasma physics, fluids, and particle beams, (5) engineering science, (6) instrumentation and diagnostics, (7) geoscience, space science, and astrophysics, (8) nuclear and particle physics, and (9) bioscience.

Laboratory directed research and development: FY 1997 progress report

Energy Technology Data Exchange (ETDEWEB)

Vigil, J.; Prono, J. [comps.

1998-05-01

This is the FY 1997 Progress Report for the Laboratory Directed Research and Development (LDRD) program at Los Alamos National Laboratory. It gives an overview of the LDRD program, summarizes work done on individual research projects, relates the projects to major Laboratory program sponsors, and provides an index to the principal investigators. Project summaries are grouped by their LDRD component: Competency Development, Program Development, and Individual Projects. Within each component, they are further grouped into nine technical categories: (1) materials science, (2) chemistry, (3) mathematics and computational science, (4) atomic and molecular physics and plasmas, fluids, and particle beams, (5) engineering science, (6) instrumentation and diagnostics, (7) geoscience, space science, and astrophysics, (8) nuclear and particle physics, and (9) bioscience.

Annual progress report 1981

International Nuclear Information System (INIS)

1982-01-01

This annual progress report of the CEA Protection and Nuclear Safety Institut outlines a brief description of the progress made in each section of the Institut. Research activities of the Protection department include, radiation effects on man, radioecology and environment radioprotection techniques. Research activities of the Nuclear Safety department include, reactor safety analysis, fuel cycle facilities safety analysis, safety research programs. The third section deals with nuclear material security including security of facilities, security of nuclear material transport and monitoring of nuclear material management [fr

Geothermal direct-heat utilization assistance. Quarterly project progress report, April--June 1993

Energy Technology Data Exchange (ETDEWEB)

Lienau, P.

1993-06-01

Technical assistance was provided to 60 requests from 19 states. R&D progress is reported on: evaluation of lineshaft turbine pump problems, geothermal district heating marketing strategy, and greenhouse peaking analysis. Two presentations and one tour were conducted, and three technical papers were prepared. The Geothermal Progress Monitor reported: USGS Forum on Mineral Resources, Renewable Energy Tax Credits Not Working as Congress Intended, Geothermal Industry Tells House Panel, Newberry Pilot Project, and Low-Temperature Geothermal Resources in Nevada.

Technical co-operation report for 2001. Report by the Director General

International Nuclear Information System (INIS)

2001-01-01

Using nuclear technology as an effective tool for development is the challenge faced by the Agency's technical co-operation programme. This was the subject of the 4th IAEA Scientific Forum, entitled 'Nuclear technology for sustainable development: serving human needs,' which was held in conjunction with the 45th General Conference in September 2001. Opening the Forum, Professor Jeffrey Sachs of Harvard University emphasized the importance of developing mechanisms to mobilize science and technology to meet the growing challenge of serving human needs in a sustainable manner and commended the Agency for its achievements in this regard. This report provides information on how the technical co-operation programme has responded to that challenge over the past year. One of the highlights of the technical co-operation programme in 2001 was the launching of the Pan-African Tsetse and Trypanosomosis Eradication Campaign (PATTEC) in Ouagadougou, Burkina Faso, in October. This represented the culmination of years of effort by African Member States, working in partnership with the Agency and the Organization for African Unity (OAU), and was an important milestone in the progress of applying the sterile insect technique (SIT) to the area-wide eradication of the tsetse fly in Africa. It is a good example of how science and technology can contribute to socio-economic development with a direct impact at the community level. The level of Member States' pledges to the Technical Co-operation Fund (TCF) for 2001, more than $59 million, was the second highest ever. This represented a rate of attainment of 80.01% (as of 31 March 2002), thus achieving the target set by the General Conference for that year. The extra budgetary contributions, more than $7 million, were the highest in ten years. These contributions, together with payments of assessed programme costs and other income, meant that total new resources for the year reached $71.1 million. In December 2000, the Board approved an

Technical co-operation report for 2001. Report by the Director General

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

Using nuclear technology as an effective tool for development is the challenge faced by the Agency's technical co-operation programme. This was the subject of the 4th IAEA Scientific Forum, entitled 'Nuclear technology for sustainable development: serving human needs,' which was held in conjunction with the 45th General Conference in September 2001. Opening the Forum, Professor Jeffrey Sachs of Harvard University emphasized the importance of developing mechanisms to mobilize science and technology to meet the growing challenge of serving human needs in a sustainable manner and commended the Agency for its achievements in this regard. This report provides information on how the technical co-operation programme has responded to that challenge over the past year. One of the highlights of the technical co-operation programme in 2001 was the launching of the Pan-African Tsetse and Trypanosomosis Eradication Campaign (PATTEC) in Ouagadougou, Burkina Faso, in October. This represented the culmination of years of effort by African Member States, working in partnership with the Agency and the Organization for African Unity (OAU), and was an important milestone in the progress of applying the sterile insect technique (SIT) to the area-wide eradication of the tsetse fly in Africa. It is a good example of how science and technology can contribute to socio-economic development with a direct impact at the community level. The level of Member States' pledges to the Technical Co-operation Fund (TCF) for 2001, more than $59 million, was the second highest ever. This represented a rate of attainment of 80.01% (as of 31 March 2002), thus achieving the target set by the General Conference for that year. The extra budgetary contributions, more than $7 million, were the highest in ten years. These contributions, together with payments of assessed programme costs and other income, meant that total new resources for the year reached $71.1 million. In December 2000, the Board approved an

1996 Progress report on energies and raw materials; 1996 rapport d`activite energies et matieres premieres

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

The 1996 annual progress report, from the French Department of Energy, reviews the key points of the French policy for energy and raw materials: competitiveness, environmental protection, long term supply safety, and public service. 1996 was marked by positive results for the French energy industry, difficulties for the oil refining industry, and a new impetus for renewable energies. Five surveys are presented: nuclear safety in Eastern Europe, the european directive on electric power domestic market, evolution of the oil market, conditions of refining in France, and restructuring of the Mine bureau (BRGM). 40 prominent facts are briefly reviewed, concerning sustainable energy development, nuclear energy, electric power and gas, coal, oil products, raw materials. Diagrams on energy and raw materials are also included

1996 Progress report on energies and raw materials; 1996 rapport d`activite energies et matieres premieres

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

The 1996 annual progress report, from the French Department of Energy, reviews the key points of the French policy for energy and raw materials: competitiveness, environmental protection, long term supply safety, and public service. 1996 was marked by positive results for the French energy industry, difficulties for the oil refining industry, and a new impetus for renewable energies. Five surveys are presented: nuclear safety in Eastern Europe, the european directive on electric power domestic market, evolution of the oil market, conditions of refining in France, and restructuring of the Mine bureau (BRGM). 40 prominent facts are briefly reviewed, concerning sustainable energy development, nuclear energy, electric power and gas, coal, oil products, raw materials. Diagrams on energy and raw materials are also included

Industrial recovered-materials-utilization targets for the textile-mill-products industry

Energy Technology Data Exchange (ETDEWEB)

None

1979-01-01

The Congress, in the National Energy Conservation and Policy Act of 1978 (NECPA), directed the Department of Energy to establish materials recovery targets for the metals and metal products, paper and allied products, rubber, and textile-mill-products industries. The targets were developed to provide incentives for using energy-saving recorded materials and to provied a yardstick for measuring progress and improvement in this endeavor. The NECPA indicates that the targets should represent the maximum technically and economically feasible increase in the use of energy-saving recovered materials that each industry can achieve progressively by January 1, 1987. Materials affected by recovered-materials targets include and are limited to aluminum, copper, lead, zinc, iron, steel, paper and associated products, textile-mill, products, and rubber. Using information gathered from the textile-mill-products industry and from other textile-relaed sources, DOE has developed recovered materials targets for that industry. This report presents those targets and their basis and justification. Following an overview of the textile industry, the chapters are: Textile-Mill-Products Industry Operations; Economic Analysis of the Textile-Mill-Products Industry; Governmental and Regulatory Influence on the US Textile Industry; Current Mill Use of Recovered Materials in the Textile-Mill-Products Industry; Limitations on the Use of Recovered Materials in the US Textile-Mill-Products Industry; Materials-Recovery Targets; and Government and Industry Actions That Could Increase the Use of Recovered Materials.

Geothermal direct-heat utilization assistance. Quarterly progress report, April--June 1993

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

Progress is reported on the following R&D activities: evaluation of lineshaft turbine pump problems, geothermal district heating marketing strategy, and greenhouse peaking analysis. Other activities are reported on technical assistance, technology transfer, and the geothermal progress monitor.

Integral Fast Reactor Program. Annual progress report, FY 1992

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

1993-06-01

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R&D.

TECHNICAL AND REGULATORY CONSIDERATIONS IN USING FREIGHT CONTAINERS AS INDUSTRIAL PACKAGES

Energy Technology Data Exchange (ETDEWEB)

Opperman, E; Mark Hawk, M; Ron Natali, R

2007-10-16

The United States (US) Department of Energy (DOE), Office of Environmental Management (EM), is actively pursuing activities to reduce the radiological risk and clean up the environmental legacy of the nation's nuclear weapons programs. EM has made significant progress in recent years in the clean-up and closure of sites and is also focusing on longer-term activities necessary for the completion of the clean-up program. The packaging and transportation of contaminated demolition debris and low-level waste (LLW) materials in a safe and cost-effective manner are essential in completing this mission. Toward this end, the US Department of Transportation's (DOT) Final Rule on Hazardous Materials Regulation Final Rule issued January 26, 2004, included a new provision authorizing the use of Freight Containers (e.g., 20 and 40-foot ISO Containers) as Industrial Packages Type 1, 2, or 3 (IP-1, IP-2, and IP-3). This paper will discuss the technical and regulatory considerations in using these newly authorized and large packages for the packaging and transportation of LLW materials.

Development and application of basis database for materials life cycle assessment in china

Science.gov (United States)

Li, Xiaoqing; Gong, Xianzheng; Liu, Yu

2017-03-01

As the data intensive method, high quality environmental burden data is an important premise of carrying out materials life cycle assessment (MLCA), and the reliability of data directly influences the reliability of the assessment results and its application performance. Therefore, building Chinese MLCA database is the basic data needs and technical supports for carrying out and improving LCA practice. Firstly, some new progress on database which related to materials life cycle assessment research and development are introduced. Secondly, according to requirement of ISO 14040 series standards, the database framework and main datasets of the materials life cycle assessment are studied. Thirdly, MLCA data platform based on big data is developed. Finally, the future research works were proposed and discussed.

A study on technical issues of materials and design bases in ASME section III subsection NH code

International Nuclear Information System (INIS)

Lee, Hyeong Yeon; Kim, Jong Bum; Yoo, Bong

2000-12-01

In this study, an analysis of evaluation report by ORNL on the technical issues of elevated temperatures design guide line, ASME Code Section III Subsection NH was conducted and a brief evaluation procedure of the creep-fatigue damage was presented. ORNL published the report in 1993 and reviewed the issue areas where code rules or regulatory guides may be lacking or inadequate to ensure safe operation over the expected life cycles for liquid metal reactor systems. From historical viewpoint of the ASME NH code development, ASME Code Case 47 was changed much in 1989 edition, which includes the stress relaxation behavior in creep damage evaluation. Afterwards the 1992 version of CC N-47 was upgraded to Subsection NH in 1995 edition, which is the same with that of CC N-47 1992 edition except few material data. This report brings up the technical and regulatory issues that can not guarantee the safe and reliable operation of the ALMR which got the conceptual design certification from NRC. Twenty three technical issues were raised and settlement methodology were proposed. Additionally, the status of items approved by ASME code subgroup of elevated temperature design committee for the revision of the most recent 1998 edition of ASME NH was described

Science to support DOE site cleanup: The Pacific Northwest National Laboratory Environmental Management Science Program awards. Fiscal year 1998 mid-year progress report

International Nuclear Information System (INIS)

1998-05-01

Pacific Northwest National Laboratory was awarded ten (10) Environmental Management Science Program (EMSP) research grants in Fiscal Year 1996 and six (6) in Fiscal Year 1997. This section summarizes how each grant addresses significant US Department of Energy (DOE) cleanup issues, including those at the Hanford Site. The technical progress made to date in each of these research projects is addressed in more detail in the individual progress reports contained in this document. This research is focused primarily in four areas: Tank Waste Remediation, Spent Nuclear Fuel and Nuclear Materials, Soil and Groundwater Cleanup, and Health Effects

Science to support DOE site cleanup: The Pacific Northwest National Laboratory Environmental Management Science Program awards. Fiscal year 1998 mid-year progress report

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-05-01

Pacific Northwest National Laboratory was awarded ten (10) Environmental Management Science Program (EMSP) research grants in Fiscal Year 1996 and six (6) in Fiscal Year 1997. This section summarizes how each grant addresses significant US Department of Energy (DOE) cleanup issues, including those at the Hanford Site. The technical progress made to date in each of these research projects is addressed in more detail in the individual progress reports contained in this document. This research is focused primarily in four areas: Tank Waste Remediation, Spent Nuclear Fuel and Nuclear Materials, Soil and Groundwater Cleanup, and Health Effects.

Engineered Materials for Cesium and Strontium Storage Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Sean M. McDeavitt

2010-04-14

Closing the nuclear fuel cycle requires reprocessing spent fuel to recover the long-lived components that still have useful energy content while immobilizing the remnant waste fission products in stable forms. At the genesis of this project, next generation spent fuel reprocessing methods were being developed as part of the U.S. Department of Energy's Advanced Fuel Cycle Initiative. One of these processes was focused on solvent extraction schemes to isolate cesium (Cs) and strontium (Sr) from spent nuclear fuel. Isolating these isotopes for short-term decay storage eases the design requirements for long-term repository disposal; a significant amount of the radiation and decay heat in fission product waste comes from Cs-137 and Sr-90. For the purposes of this project, the Fission Product Extraction (FPEX) process is being considered to be the baseline extraction method. The objective of this project was to evaluate the nature and behavior of candidate materials for cesium and strontium immobilization; this will include assessments with minor additions of yttrium, barium, and rubidium in these materials. More specifically, the proposed research achieved the following objectives (as stated in the original proposal): (1) Synthesize simulated storage ceramics for Cs and Sr using an existing labscale steam reformer at Purdue University. The simulated storage materials will include aluminosilicates, zirconates and other stable ceramics with the potential for high Cs and Sr loading. (2) Characterize the immobilization performance, phase structure, thermal properties and stability of the simulated storage ceramics. The ceramic products will be stable oxide powders and will be characterized to quantify their leach resistance, phase structure, and thermophysical properties. The research progressed in two stages. First, a steam reforming process was used to generate candidate Cs/Sr storage materials for characterization. This portion of the research was carried out at

Engineered Materials for Cesium and Strontium Storage. Final Technical Report

International Nuclear Information System (INIS)

McDeavitt, Sean M.

2010-01-01

Closing the nuclear fuel cycle requires reprocessing spent fuel to recover the long-lived components that still have useful energy content while immobilizing the remnant waste fission products in stable forms. At the genesis of this project, next generation spent fuel reprocessing methods were being developed as part of the U.S. Department of Energy's Advanced Fuel Cycle Initiative. One of these processes was focused on solvent extraction schemes to isolate cesium (Cs) and strontium (Sr) from spent nuclear fuel. Isolating these isotopes for short-term decay storage eases the design requirements for long-term repository disposal; a significant amount of the radiation and decay heat in fission product waste comes from Cs-137 and Sr-90. For the purposes of this project, the Fission Product Extraction (FPEX) process is being considered to be the baseline extraction method. The objective of this project was to evaluate the nature and behavior of candidate materials for cesium and strontium immobilization; this will include assessments with minor additions of yttrium, barium, and rubidium in these materials. More specifically, the proposed research achieved the following objectives (as stated in the original proposal): (1) Synthesize simulated storage ceramics for Cs and Sr using an existing labscale steam reformer at Purdue University. The simulated storage materials will include aluminosilicates, zirconates and other stable ceramics with the potential for high Cs and Sr loading. (2) Characterize the immobilization performance, phase structure, thermal properties and stability of the simulated storage ceramics. The ceramic products will be stable oxide powders and will be characterized to quantify their leach resistance, phase structure, and thermophysical properties. The research progressed in two stages. First, a steam reforming process was used to generate candidate Cs/Sr storage materials for characterization. This portion of the research was carried out at Purdue

Gatlinburg conference: barometer of progress in analytical chemistry

International Nuclear Information System (INIS)

Shults, W.D.

1981-01-01

Much progress has been made in the field of analytical chemistry over the past twenty-five years. The AEC-ERDA-DOE family of laboratories contributed greatly to this progress. It is not surprising then to find a close correlation between program content of past Gatlinburg conferences and developments in analytical methodology. These conferences have proved to be a barometer of technical status

76 FR 29333 - Pipeline Safety: Meetings of the Technical Pipeline Safety Standards Committee and the Technical...

Science.gov (United States)

2011-05-20

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... Technical Hazardous Liquid Pipeline Safety Standards Committee AGENCY: Pipeline and Hazardous Materials... for natural gas pipelines and for hazardous liquid pipelines. Both committees were established under...

1985. Annual progress report

International Nuclear Information System (INIS)

1986-01-01

This annual progress report of the CEA Protection and Nuclear Safety Institut outlines a description of the progress made in each sections of the Institut Research activities of the different departments include: reactor safety analysis, fuel cycle facilities analysis; and associated safety research programs (criticality, sites, transport ...), radioecology and environmental radioprotection techniques; data acquisition on radioactive waste storage sites; radiation effects on man, studies on radioprotection techniques; nuclear material security including security of facilities, security of nuclear material transport, and monitoring of nuclear material management; nuclear facility decommissioning; and finally the public information [fr

Technical memory 2007

International Nuclear Information System (INIS)

2009-01-01

The technical memory 2007 of the Nuclear Regulatory Authority (ARN) of the Argentine Republic, compiles the papers published in the subject on radiation protection and nuclear safety, and presented in journals, technical reports, congress or meetings of these specialities by personnel of the mentioned institution during 2007. In this edition the documents are presented on: environmental protection; transport of radioactive materials; regulations; research reactors and nuclear power plants; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; physical dosimetry; knowledge management; radioactive waste management [es

Technical progress report for the quarter 1 October-31 December 1980

International Nuclear Information System (INIS)

1981-01-01

This report describes the technical accomplishments on the commercial nuclear waste management programs and on the geologic disposal of nuclear wastes. The program is organized into eight tasks: systems, waste package, site, repository, regulatory and institutional, test facilities and excavations, land acquisition, and program management

Magnetic fusion energy plasma interactive and high heat flux components. Volume II. Technical assessment of the critical issues and problem areas in high heat flux materials and component development

International Nuclear Information System (INIS)

Abdou, M.A.; Boyd, R.D.; Easor, J.R.

1984-06-01

A technical assessment of the critical issues and problem areas for high heat flux materials and components (HHFMC) in magnetic fusion devices shows these problems to be of critical importance for the successful operation of near-term fusion experiments and for the feasibility and attractiveness of long-term fusion reactors. A number of subgroups were formed to assess the critical HHFMC issues along the following major lines: (1) source conditions, (2) systems integration, (3) materials and processes, (4) thermal hydraulics, (5) thermomechanical response, (6) electromagnetic response, (7) instrumentation and control, and (8) test facilities. The details of the technical assessment are presented in eight chapters. The primary technical issues and needs for each area are highlighted

Magnetic fusion energy plasma interactive and high heat flux components. Volume II. Technical assessment of the critical issues and problem areas in high heat flux materials and component development

Energy Technology Data Exchange (ETDEWEB)

Abdou, M.A.; Boyd, R.D.; Easor, J.R.; Gauster, W.B.; Gordon, J.D.; Mattas, R.F.; Morgan, G.D.; Ulrickson, M.A,; Watson, R.D.; Wolfer, W.G,

1984-06-01

A technical assessment of the critical issues and problem areas for high heat flux materials and components (HHFMC) in magnetic fusion devices shows these problems to be of critical importance for the successful operation of near-term fusion experiments and for the feasibility and attractiveness of long-term fusion reactors. A number of subgroups were formed to assess the critical HHFMC issues along the following major lines: (1) source conditions, (2) systems integration, (3) materials and processes, (4) thermal hydraulics, (5) thermomechanical response, (6) electromagnetic response, (7) instrumentation and control, and (8) test facilities. The details of the technical assessment are presented in eight chapters. The primary technical issues and needs for each area are highlighted.

Office of Waste Isolation progress report, October 1976

International Nuclear Information System (INIS)

1977-01-01

Progress of the National Waste Terminal Storage program is reported under: technical projects, facility projects, systems projects, and regulatory affairs. Various media (salt, shales, rocks) for geologic storage are covered

Annual technical progress report: reactor safety, Government fiscal year 1978

International Nuclear Information System (INIS)

1978-01-01

Progress in LMFBR safety studies on accident debris behavior is reported under the following subtask titles: high-temperature-concentration aerosols, large-scale molten fuel tests, sodium release tests, and risk analysis

Geothermal direct-heat utilization assistance. Federal Assistance Program quarterly project progress report, April 1--June 30, 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

This report summarizes geothermal technical assistance, R and D and technology transfer activities of the Geo-Heat Center at Oregon Institute of Technology for the third quarter of FY98 (April--June, 1998). It describes 231 contacts with parties during this period related to technical assistance with geothermal direct heat projects. Areas dealt with included requests for general information including material for high school and university students, and material on geothermal heat pumps, resource and well data, spacing heating and cooling, greenhouses, aquaculture, equipment, district heating, resorts and spas, industrial applications, snow melting and electric power. Research activities include work on model construction specifications for line shaft submersible pumps and plate heat exchangers, and a comprehensive aquaculture developers package. A brochure on Geothermal Energy in Klamath County was developed for state and local tourism use. Outreach activities include the publication of the Quarterly Bulletin (Vol. 19, No. 2) with articles on research at the Geo-Heat Center, sustainability of geothermal resources, injection well drilling in Boise, ID and a greenhouse project in the Azores. Other outreach activities include dissemination of information mainly through mailings of publications, tours of local geothermal uses, geothermal library acquisitions and use, participation in workshops, short courses and technical meetings by the staff, and progress monitor reports on geothermal activities.

Bio-aggregates based building materials state-of-the-art report of the RILEM Technical Committee 236-BBM

CERN Document Server

Collet, Florence

2017-01-01

The work of the RILEM Technical Committee (TC -236 BBM) was dedicated to the study of construction materials made from plant particles. It considered the question whether building materials containing as main raw material recyclable and easily available plant particles are renewable. This book includes a state-of-the-art report and an appendix. The state-of-the-art report relates to the description of vegetal aggregates. Then, hygrothermal properties, fire resistance, durability and finally the impact of the variability of the method of production of bio-based concrete are assessed. The appendix is a TC report which presents the experience of a working group. The goal was to define testing methods for the measurement of water absorption, bulk density, particle size distribution, and thermal conductivity of bio aggregates. The work is based on a first round robin test of the TC-BBM where the protocols in use by the different laboratories (labs) are compared. .

1984-85 ISN progress report

International Nuclear Information System (INIS)

1985-01-01

This progress report ISN 1984-1985 deals with the following subjects: nuclear physics theory, peripheral and intermediate energy physics, characteristics of reaction mechanisms in heavy ion collisions, nuclear structure, fundamental interactions, experimental methods and new instrumentation, some interdisciplinary research activities and technical activities, the SARA cyclotron and finally, technology transfer and valorisation [fr

Instrumentation of dynamic gas pulse loading system. Technical progress report, first quarter 1992

Energy Technology Data Exchange (ETDEWEB)

Mohaupt, H.

1992-04-14

The overall goal of this work is to further develop and field test a system of stimulating oil and gas wells, which increases the effective radius of the well bore so that more oil can flow into it, by recording pressure during the gas generation phase in real time so that fractures can be induced more predictably in the producing formation. Task 1: Complete the laboratory studies currently underway with the prototype model of the instrumentation currently being studied. Task 2: Perform field tests of the model in the Taft/Bakersfield area, utilizing operations closest to the engineers working on the project, and optimize the unit for various conditions encountered there. Task 3: Perform field test of the model in DGPL jobs which are scheduled in the mid-continent area, and optimize the unit for downhole conditions encountered there. Task 4: Analyze and summarize the results achieved during the complete test series, documenting the steps for usage of downhole instrumentation in the field, and compile data specifying use of the technology by others. Task 5: Prepare final report for DOE, and include also a report on the field tests completed. Describe and estimate the probability of the technology being commercialized and in what time span. The project has made substantial technical progress, though we are running about a month behind schedule. Expenditures are in line with the schedule. Increased widespread interest in the use of DGPL stimulation has kept us very busy. The computer modeling and test instrumentation developed under this program is already being applied to commercial operations.

The BGO collaboration progress report 1990

International Nuclear Information System (INIS)

Anon.

1990-01-01

A large solid angle BGO calorimeter is under contruction for photo-nuclear experiments at intermediate energy facilities. In this note the status progress of the project, the technical steps undertaken in the construction of the apparatus and the goals of this initiative are reviewed

Savannah River Plant, Works Technical Department monthly progress report for March 1956

International Nuclear Information System (INIS)

1956-01-01

This document details activities of the Works Technical Department during the month of March 1956. It covers reactor technology, separations technology, engineering assistance and heavy water technology

Technical progress report for the quarter 1 October-31 December 1980

Energy Technology Data Exchange (ETDEWEB)

1981-01-01

This report describes the technical accomplishments on the commercial nuclear waste management programs and on the geologic disposal of nuclear wastes. The program is organized into eight tasks: systems, waste package, site, repository, regulatory and institutional, test facilities and excavations, land acquisition, and program management. (DLC)

TECHNICAL COORDINATION

CERN Multimedia

Austin Ball

2013-01-01

  Since the last report, much visible progress has been made, as the LS1 programme approaches the halfway point. From early October, technical and safety shift-crew have been present around the clock, allowing detectors to stay switched on overnight, ensuring that safety systems are operational and instructions for non-expert shift-crew are clear. LS1 progress Throughout the summer, whilst the solenoid vacuum tank and YB0 surfaces were accessible, an extensive installation programme took place to prepare for Tracker colder operation and the PLT installation, in 2014, the Phase 1 Pixel Tracker installation, in 2016–’17, and the HCAL Phase 1 upgrade completion, ending in LS2. This included pipework for N2 or dry air to flush the Tracker bulkhead region, many sensors to monitor temperature and dew point in the Tracker and its service channels, heating wires outside the Tracker cooling bundles, supports for the new vacuum-jacketed, concentric, CO2 Pixel cooling lines, the PLT cool...

Progress and status of the Integral Fast Reactor (IFR) fuel cycle development

International Nuclear Information System (INIS)

Till, C.E.; Chang, Y.I.

1993-01-01

The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions

Progress and status of the Integral Fast Reactor (IFR) fuel cycle development

Energy Technology Data Exchange (ETDEWEB)

Till, C.E.; Chang, Y.I.

1993-03-01

The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions.

Progress and status of the Integral Fast Reactor (IFR) fuel cycle development

Energy Technology Data Exchange (ETDEWEB)

Till, C.E.; Chang, Y.I.

1993-01-01

The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions.

The technical support organization at BNL is twenty years old

International Nuclear Information System (INIS)

Indusi, J.P.

1988-01-01

The Technical Support Organization was established by the Atomic Energy Commission in January 1968 at Brookhaven National Laboratory (BNL). The original idea came from a small group of scientists at BNL. The group included Willy Higinbotham, Herb Kouts, Frank Miles, Richard Dodson, and Gerhardt Friedlander. The AEC endorsed the idea of a technical support group to provide technical assistance to AEC's Office of Safeguards and Materials Management and they sent requests for expressions of interest throughout the complex. For a number of reasons, to be discussed in the paper, the Technical Support Organization was established at BNL. An early project was the Conceptual Design for Safeguarding Nuclear Material which formed the first logical and systematic description of the integration of several elements into a safeguards system for protecting nuclear materials. Many other projects were undertaken over the years. TSO today provides technical assistance to the DOE Office of Safeguards and Secuirty, the Office of Classification and Technology Policy, and the Office of Security Evaluations. Technical support to the IAEA is provided under the Program of Technical Assistance to Agency Safeguards (POTAS). Recently, TSO began a program of technical assistance to the Air Force Weapons Laboratory in the area of nuclear systems security

Integral Fast Reactor Program annual progress report, FY 1991

International Nuclear Information System (INIS)

1992-06-01

This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1991. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R ampersand D