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Sample records for plants technical progress

  1. [Carbon isotope fractionation in plants]: Annual technical progress report

    International Nuclear Information System (INIS)

    O'Leary, M.H.

    1988-01-01

    Plants fractionate carbon isotopes during photosynthesis in ways which reflect photosynthetic pathway and environment. The fractionation is product of contributions from diffusion, carboxylation and other factors which can be understood using models which have been developed in our work. The object of our work is to use this fractionation to learn about the factors which control the efficiency of photosynthesis. Unlike previous studies, we do not rely principally on combustion methods, but instead develop more specific methods with substantially higher resolving power. We have recently developed a new short-term method for studying carbon isotope fractionation which promises to provide a level of detail about temperature, species, and light intensity effects on photosynthesis which has not been available until now. We are studying the isotopic compositions of metabolites (particularly aspartic acid) in C 3 plants in order to determine the role of phosphoenolpyruvate carboxylase in C 3 photosynthesis. We are studying the relative roles of diffusion and carboxylation in nocturnal CO 2 fixation in CAM plants. We are studying the use of isotopic content as an index of water-use efficiency in C 3 plants. We are developing new methods for studying carbon metabolism in plants. 3 refs

  2. Savannah River Plant Works Technical Department monthly progress report for May 1958: Deleted Version

    Energy Technology Data Exchange (ETDEWEB)

    1958-06-17

    This progress report by the Atomic Energy Division of the Savannah River Plant covers: Reactor Technology; Separation Technology; Engineering Assistance; Health Physics; and General Laboratory Work. (JT)

  3. 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

  4. Instrumentation and process control for fossil demonstration plants. Quarterly technical progress report, April--June 1977

    Energy Technology Data Exchange (ETDEWEB)

    LeSage, L.G.

    1977-07-01

    Work has been performed on updating the study of the state-of-the-art of instrumentation for Fossil Demonstration Plants (FDP), development of mass-flow and other on-line instruments for FDP, process control analysis for FDP, and organization of a symposium on instrumentation and control for FDP. A Solids/Gas Flow Test Facility (S/GFTF) under construction for instrument development, testing, evaluation, and calibration is described. The development work for several mass-flow and other on-line instruments is described: acoustic flowmeter, capacitive density flowmeter, neutron activation flowmeter and composition analysis system, gamma ray correlation flowmeter, optical flowmeter, and capacitive liquid interface level meter.

  5. 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

  6. 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.

  7. Interdisciplinary Research and Training Program in the Plant Sciences. Technical progress report, February 1, 1991--November 30, 1992

    Energy Technology Data Exchange (ETDEWEB)

    Wolk, C.P.

    1992-07-01

    Research on plants continued. Topics include: Molecular basis of symbiotic plant-microbe interations; enzymatic mechanisms and regulation of plant cell wall biosynthesis; molecular mechanisms that regulate the expression of genes in plants; resistance of plants to environmental stress; studies on hormone biosynthesis and action; plant cell wall proteins; interaction of nuclear and organelle genomes; sensor transduction in plants; molecular mechanisms of trafficking in the plant cell; regulation of lipid metabolism; molecular bases of plant disease resistance mechanisms; biochemical and molecular aspects of plant pathogenesis; developmental biology of nitrogen-fixing cyanobacteria; environmental control of plant development and its relation to plant hormones.

  8. 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)

  9. 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.)

  10. 48 CFR 2052.211-71 - Technical progress report.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Technical progress report... Technical progress report. As prescribed at 2011.104-70(b), the contracting officer shall insert the... solicitation. Technical Progress Report (JAN 1993) The contractor shall provide a monthly Technical Progress...

  11. Standard Technical Specifications, Westinghouse plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document, Volume 3, contains the Bases for Sections 3.4--3.9 of the improved STS

  12. Standard Technical Specifications, Westinghouse Plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the unproved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS which contain information on safety limits, reactivity control systems, power distribution limits, and instrumentation

  13. Standard Technical Specifications, Westinghouse plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  14. Technical progress and its strategic consequences

    International Nuclear Information System (INIS)

    Bouchard, G.

    1999-01-01

    The history of energy during recent decades has shown that technical progress can have consequences for the organisation of markets, company strategies and the economy in general, confounding all forecasts and going beyond simple technical change. As a consequence for example, improvements in the techniques concerning the exploration and production of hydrocarbons have led to the petrol 'counter-crisis', the reduction in the power of OPEC and undreamed of gains in wealth for certain countries. The progress in gas turbines has led to the reversal of the age-old tendency towards increases in the size of electricity production units and encouraged the liberation of this sector. When looking at the future it is therefore judicious to try and understand the forces at work, and the major trends which result. This is the aim of the articles in this edition of the Revue de l'Energie, published on the occasion of the European colloquium on 'Technical progress faced with the challenges of the energy sector in the future' organised by the Association of Energy Economists. (authors)

  15. Hanford Waste Vitrification Plant technology progress

    International Nuclear Information System (INIS)

    Wolfe, B.A.; Scott, J.L.; Allen, C.R.

    1989-10-01

    The Hanford Waste Vitrification Plant (HWVP) is currently being designed to safely process and temporarily store immobilized defense liquid high-level wastes from the Hanford Site. These wastes will be immobilized in a borosilicate glass waste form in the HWVP and stored onsite until a qualified geologic waste repository is ready for permanent disposal. Because of the diversity of wastes to be disposed of, specific technical issues are being addressed so that the plant can be designed and operated to produce a waste form that meets the requirements for permanent disposal in a geologic repository. This paper reports the progress to date in addressing these issues. 2 figs., 3 tabs

  16. 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.

  17. Identification and validation of heavy metal and radionuclide hyperaccumulating terrestrial plant species, Quarterly technical progress report, December 20, 1995--March 20, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Kochian, L.; Brady, D.; Last, M.; Ebbs, S.

    1995-12-01

    Although the period covered by this progress report began on December 20, 1994, which was the date that DOE approved the Interagency Agreement, the agreement was not approved by USDA until January 9, 1995 and the first scientists working on the project were not hired until February 1, 1995. The first goal of the research supported by the Interagency Agreement is to use hydroponic techniques to identify plant species and genotypes with potential for heavy metal hyperaccumulation for planting on a test site at Silverbow Creek and for radionuclide ({sup 90}Sr and {sup 137}Cs) accumulation on a test site at INEL, Idaho, later this year. The second goal of this research is to identify soil amendment procedures that will enhance the bioavailability of heavy metals and radionuclides in the soil without increasing the movement of the contaminants of concern (COC`s) into the groundwater. Our initial research covered in this report focuses on the first goal.

  18. Development of innovative techniques and principles that may be used as models to improve plant performance. Technical progress report, February 1, 1990--January 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Hanna, W.W.; Burton, G.W.

    1992-06-01

    Methods and techniques for transferring germplasm from wild to cultivated species are being developed. The transferred germplasm is being shown to be valuable in plant breeding and in cultivar development. In the primary gene pool of the grassy Pennisetum glaucum subspecies monodii germplasm, some cytoplasms are being identified that appear to have significant effects on forage yields and morphological characteristics. One cytoplasm, A{sub 4}, is very stable for male sterility and fertility is not easily restored by other lines. It should be a valuable cytoplasm for producing commercial forage hybrids. Disease resistance and yield genes transferred from monodii to cultivated pearl millet lines are having a major impact on increasing production of animals grazing disease resistant Tifleaf 2 pearl millet. Genes controlling resistance to many of the world-wide diseases on pearl millet are being identified in the monodii germplasm. Valuable germplasm has been transferred from the secondary gene pool P. purpuroum) which is used as the pollinator of the first pearl millet grain hybrid in the US Production of 7-chromosome gametes in 42-chromosome interspecific hybrids appears to be genotype specific and makes possible transfer of germplasm from the secondary gene pool to cultivated diploid pearl millet. Significant progress has been made in transferring genes controlling apomixis from P. squamulatum (tertiary gene pool) to cultivated pearl millet. Highly apomictic BC{sub 4} plants have been recovered, one of which sets five times as much seed as the best BC{sub 3} plant.

  19. 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

  20. 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.

  1. 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.

  2. 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.)

  3. Standard technical specifications combustion engineering plants

    International Nuclear Information System (INIS)

    1992-09-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS) for Combustion Engineering Plants. The improved STS wee developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Sections 3.4--3.9 of the improved STS

  4. 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.

  5. 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

  6. Standard Technical Specifications, Babcock and Wilcox Plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) plants and documents the positions of the Nuclear Regulatory Commission (NRC) based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council. The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for developing improved plant-specific technical specifications by individual nuclear power plant licensees. This volume contains sections 3.4--3.9 which cover: Reactor coolant systems, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations

  7. Nuclear Power Plant Temelin Technical Support Centre

    International Nuclear Information System (INIS)

    Krizek, K.

    2000-01-01

    The erection of the Technical Support Centre for the Nuclear Power Plant Temelin has been a relatively sophisticated and costly issue. It was by proper use of the existing systems, as e.g. I and C, ISE and other systems, that a robust system has been created that is able to meet any requirements laid on the performance of the Technical Support Centre. The decision of the utility CEZ, a.s. that made it possible to establish the Technical Support Centre at the Nuclear Power Plant Temelin has been a right step which shows the level of safety culture within the utility. (author)

  8. Standard Technical Specifications, Babcock and Wilcox plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The unproved STS were developed based on the, criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop proved plant-specific technical specifications. This report contains three volumes. This document, Volume 1 contains the Specifications for all chapters and sections of the improved STS

  9. Fusion power plant simulations: a progress report

    International Nuclear Information System (INIS)

    Cook, J.M.; Pattern, J.S.; Amend, W.E.

    1976-01-01

    The objective of the fusion systems analysis at ANL is to develop simulations to compare alternative conceptual designs of magnetically confined fusion power plants. The power plant computer simulation progress is described. Some system studies are also discussed

  10. 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.

  11. Regional cooperation to stimulate technical progress

    International Nuclear Information System (INIS)

    Ridvan, M.; Ehjrej, P.L.

    1987-01-01

    The main principles of the IAEA regional agreement on co-operation in the field of researches, elaboration and training of specialists in nuclear science and engineering for the states of Asia and Pacific Ocean region (RAC) and of the ARCAL program in Latin America are considered. The RAC projects envisage co-operation in the field of medicine (radiotherapy and nuclear methods, sterilization, etc.), agriculture (nuclear methods, raising of plants, using radiation mutations, food irradiation, etc.), industry (application of isotopes and radiation technology) and others. The ARCAL projects comprise radiation protection, nuclear control instruments, nuclear analytic methods, radioimmune analysis in stock-breeding, product irradiation, nuclear information, etc

  12. 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

  13. Standard Technical Specifications, Babcock and Wilcox plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  14. Standard Technical Specifications, Combustion Engineering plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (M) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  15. Standard Technical Specifications, Combustion Engineering plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved SM. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3 contains the Bases for Sections 3.4--3.9 of the improved M

  16. Hanford Waste Vitrification Plant technical manual

    Energy Technology Data Exchange (ETDEWEB)

    Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

    1996-03-01

    A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

  17. Hanford Waste Vitrification Plant technical manual

    International Nuclear Information System (INIS)

    Larson, D.E.; Watrous, R.A.; Kruger, O.L.

    1996-03-01

    A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version

  18. VGB-requirements regarding technical data for power plants

    International Nuclear Information System (INIS)

    Richnow, Joerg

    2009-01-01

    Much of the technical plant data resulting from the planning, construction and start-up of power plants is needed for subsequent management and maintenance. Because of this, VGB has taken the initiative and has defined standard minimum requirements from power plant operators for technical plant data. They relate to the details and structure of this data, the definition of material classes and characteristics for the main power plant components and IT implementation for delivery of the technical plant data. (orig.)

  19. Independent technical review of the Pinellas Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This report documents an Independent Technical Review (ITR) of facilities, organizations, plans, activities and various other elements required to successfully transition the Pinellas Plant from Defense Program (DP) funded operation to either community developed reuse or safe deactivation leading to decontamination and decommissioning (D&D). The review was conducted at the request of the Department of Energy (DOE) Deputy Assistant Secretary for Facility Transition and Management (EM-60) and is a consensus of the nine member ITR Team.

  20. Technical diagnosis of industrial plants with radioisotopes

    International Nuclear Information System (INIS)

    Hartmann, G.

    1984-01-01

    A survey is given of the application of radioisotopes in technical diagnosis of industrial plants. Proceeding from the economic importance and the state of the art of radioisotope applications, the principles of tracer techniques are outlined including topical examples of application such as passage of coal through a steam generator, wear in impact crashing of coal, wear and corrosion in pipelines, testing the effective cross section of pipes, and investigations of microstructures. Limits and restrictions of applications are briefly discussed

  1. Plant materials program. Progress report, June 1980-May 1981

    International Nuclear Information System (INIS)

    Childs, W.; Cubicciotti, D.; Fox, M.; Giannuzzi, A.; Gilman, J.; Jones, R.; McIlree, A.

    1981-11-01

    This is the first annual progress report of the Plant Materials Subprogram, which was organized in May 1980 to address corrosion-related materials problems in light water reactors. The first section of the report provides an overview of plant materials problems which have a high impact on plant availability. These include pipe and pressure vessel cracking, condenser leakage, turbine disc cracking, and steam generator tube denting and cracking. The status and goals of research and development work related to each of these problems are reviewed briefly. Subsequent report sections provide more detailed reviews of significant progress in the relevant technical topic areas: intergranular stress corrosion cracking of austenitic stainless steels; environmentally-assisted cracking of carbon and low alloy steels; intergranular stress corrosion cracking of nickel-base alloys; and improved fabrication technology

  2. Plant Materials Program: progress June 1981 to May 1982

    International Nuclear Information System (INIS)

    Childs, W.; Cubicciotti, D.; Fox, M.; Giannuzzi, A.; Gilman, J.; Jones, R.

    1983-02-01

    This is the second annual progress report of the Plant Materials Subprogram, which was organized in May 1980 to address corrosion-related materials problems in light water reactors. The first section of the report provides an overview of plant materials problems which have a high impact on plant availability. These include pipe and pressure vessel cracking, condenser leakage, turbine disc cracking, steam geerator tube attack and cracking, and cracking of nickel alloy springs, beams and pins. The status and goals of research and development work related to each of these problems are reviewed briefly. Subsequent report sections provide more detailed reviews of significant progress in the relevant technical topic areas: intergranular stress corrosion cracking of austenitic stainless steels; environmentally-assisted cracking of carbon and low alloy steels; intergranular stress corrosion cracking of nickel-base alloys; and improved fabrication technology

  3. Plant Materials Program: progress June 1981-May 1982

    International Nuclear Information System (INIS)

    Childs, W.; Cubicciotti, D.; Fox, M.; Giannuzzi, A.; Gilman, J.; Jones, R.

    1983-02-01

    This is the second annual progress report of the Plant Materials Subprogram, which was organized in May 1980 to address corrosion-related materials problems in light water reactors. The first section of the report provides an overview of plant materials problems which have impact on plant availability. These include pipe and pressure vessel cracking, condenser leakage, turbine disc cracking, steam generator tube attack and cracking, and cracking of nickel alloy springs, beams and pins. The status and goals of research and development work related to each of these problems are reviewed briefly. Subsequent report sections provide more detailed reviews of significant progress in the relevant technical topic area: integranular stress corrosion cracking of austenitic stainless steels; environmentally-assisted cracking of carbon and low alloy steels; intergranular stress corrosion cracking of nickel-base alloys; and improved fabrication technology

  4. 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

  5. Better Plants Progress Update Fall 2013

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2013-09-23

    This Progress Update summarizes the significant energy saving achievements and cumulative cost savings made by these industry leaders from 2010-2012. The update also shares the plans and priorities over the next year for the Better Plants Program to continue to advance energy efficiency in the industrial sector.

  6. 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.

  7. 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

  8. Technical Safety Appraisal of the Pinellas Plant

    International Nuclear Information System (INIS)

    1991-01-01

    This report presents the Technical Safety Appraisal (TSA) of the Pinellas Plant in Pinellas County, Florida. The plant is owned and controlled by the US Department of Energy and operated by General Electric Neutron Devices (GEND). The TSA was performed during the period January 15--31, 1989, in support of a Tiger Team Assessment which occurred during the period January 15 to February 2, 1989. The TSA provided the Safety and Health Subteam input to the Tiger Team Assessment. The completion of the assessment process includes: (1) submission of the Team's preliminary findings and concerns, in a Draft Report, to the Manager, Albuquerque Operations Office and to the site contractors at the conclusion of the onsite assessment; (2) review of the Draft Report for technical and factual accuracy; incorporation of the appropriate review comments, suggested changes, and modifications, as well as input from all interested Program Secretarial Offices; preparation of a draft Action Plan by the Albuquerque Operations Office to address the Concerns, and submittal of that Action Plan through the Program Office to ES ampersand H for their review and comment. The Secretary approved the final Action Plan on December 16, 1990, and directed its implementation. The comments and suggestions of the Program Secretarial Offices, the Operations Office, and the site contractor have been incorporated, as appropriate, in this report prior to its publication

  9. 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.

  10. Independent technical review of the Mound Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This report documents an Independent Technical Review (ITR) of the facilities, organizations, plans, and activities required to transition particular elements of the Mound Plant from Defense Program (DP) funded operation as appropriate either to community developed reuse or safe deactivation leading to decontamination and decommissioning (D&D). The review was conducted at the request of the Dr. Willis Bixby, Deputy Assistant Secretary, U.S. Department of Energy EM-60, Office of Facility Transition and Management and is a consensus of the nine member ITR Team. Information for the review was drawn from documents provided to the ITR Team by the Miamisburg Area Office (MB) of the DOE, EG&G, the City of Miamisburg, and others; and from presentations, discussions, interviews, and facility inspections at the Mound Plant during the weeks of March 14 and March 28, 1994. During the week of April 25, 1994, the ITR Team met at Los Alamos, New Mexico to develop consensus recommendations. A presentation of the core recommendations was made at the Mound Plant on May 5, 1994. This is an independent assessment of information available to, and used by, the Mound Plant personnel. Repetition of the information is not meant to imply discovery by the ITR Team. Team members, however, acting as independent reviewers, frequently assess the information from a perspective that differs significantly from that of the Mound Plant personnel. The report is based on information obtained and conditions observed during the March 1994 review interval. The ITR process and normal site work often initiate rapid, beneficial changes in understanding and organization immediately following the review. These changes frequently alter conditions observed during the review, but the report does not address changes subsequent to the review interval.

  11. Technical Safety Appraisal of the Rocky Flats Plant

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Blake P.

    1989-01-01

    This report provides the results of a Technical Safety Appraisal (TSA) of the Rocky Flats Plant (RFP) conducted November 14 to 18 and November 28 to December 9, 1988. This appraisal covered the effectiveness and improvements in the RFP safety program across the site, evaluating progress to date against standards of accepted practice. The appraisal included coverage of the timeliness and effectiveness of actions taken in response to the recommendations/concerns in three previous Technical Safety Appraisals (TSAs) of RFP Bldg. 707 conducted in July 1986, Bldgs. 771/774 conducted in October/November 1986, and Bldgs. 776/777 conducted in January/February 1988. Results of this appraisal are given in Section IV for each of 14 technical safety areas at RFP. These results include a discussion, conclusions and any new safety concerns for each technical safety area. Appendix A contains a description of the system for categorizing concerns, and the concerns are tabulated in Appendix B. Appendix C reports on the evaluation of the contractor's actions and the current status of each of the 230 recommendations and concerns contained in the three previous TSA reports.

  12. Technical progress safeguards future. Technischer Fortschritt sichert die Zukunft

    Energy Technology Data Exchange (ETDEWEB)

    1985-01-01

    'Technical progress safeguards future', the guiding theme of the 1985 conference of German engineers, calls for discussion. In five lectures representatives of the subdivisions of 'VDI' issued their statements from the viewpoints of their special fields. These lectures were completed by reports on the part of the remaining VDI subdivisions, which are published together with the lectures in this volume. The complex guiding theme is meant to stimulate discussion, which should be conducted also with representatives of other sciences and the public. The volume contains a.o. contributions regarding future prospects, given certain modifications in construction engineering and user behaviour in the sector heating and air-conditioning, regarding the development of new construction techniques to protect the environment, and regarding clean air as an international concern of engineers. For these three contributions separate entries were made. Other presentations relate to: automobile production technology; energy supply as an engineering task; information, invention, innovation as stages of technical progress; progress in materials technology; noise of motor vehicles - current state and future prospects. (orig./HSCH).

  13. 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.

  14. 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

  15. 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.

  16. 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

  17. 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)

  18. 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.

  19. Technical strategy map to employing nuclear power plant aging management

    International Nuclear Information System (INIS)

    Sekimura, Naoto; Kanno, Masanori

    2008-01-01

    Stated in this report are back ground of technical strategy map for nuclear power plant aging management, result of the first road map, significance of technical strategy map, introduction scenario, technology map, road map, upgrade in every year, three groups of academia, industry and government, plan of technical strategy map, upgrade system, comprehensive introduction scenario, measures of nuclear power plant aging management in Japan and the world, new inspection system, outline of 'technical strategy map 2008', preparation of technical information bases in industry, academia and government, collaboration of them, safety researches of neutron radiation damage, stress corrosion crack, fatigue, piping thinning, insulation degradation, concrete degradation, thermal aging, evaluation technologies of earthquake resistance, preparation of rules and standards, ideal maintenance, and training talent. (S.Y.)

  20. Tele-maintenance 'intelligent' system for technical plants result management

    International Nuclear Information System (INIS)

    Concetti, Massimo; Cuccioletta, Roberto; Fedele, Lorenzo; Mercuri, Giampiero

    2009-01-01

    The management of technical plant for productivity and safety is generally a complex activity, particularly when many plants distributed in the territory are considered (i.e. the more and more frequent case of outsourced plants maintenance by specialized companies), granted quality and cost results are required (i.e. the case of some rather innovative contract solutions) and the technology involved is heterogeneous and innovative (i.e. electro-mechanical plants). In order to efficiently achieve the above aims an 'intelligent' maintenance-management system for the distant monitoring and controlling by a remote control center has been developed. The so-called GrAMS (granted availability management system) system is conceived to give to organizations involved in technical-industrial plants management the possibility to tend to a 'well-known availability' and 'zero-failures' management. In particular, this study deals with the diagnostic aspects and safety level of technical plants (such as elevators, thermo-technical plants, etc.), and with the involvement of ad hoc designed software analysis tools based on neural networks and reliability indicators. Part of the research dealing with the tele-maintenance intelligent system has been financed by the Italian High Institute for Safety (ISPESL) and led to the development of a pre-industrial prototype whose realization and testing is here described

  1. Technical Report Cellulosic Based Black Liquor Gasification and Fuels Plant Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Fornetti, Micheal [Escanaba Paper Company, MI (United States); Freeman, Douglas [Escanaba Paper Company, MI (United States)

    2012-10-31

    produce transportation fuels and produce pulp at the same time. This has the added advantage of reducing or eliminating the need for a recovery boiler. The recovery boiler is an extremely expensive unit operation in the Kraft process and is key to the chemical recovery system that makes the Kraft process successful. Going to a gasification process with potentially higher energy efficiency, improve the pulping process and be more efficient with the use of wood. At the same time a renewable fuel product can be made. Cellulosic Based Black Liquor Gasification and Fuels Plant progressed with the design of the mill as Chemrec continued to work on their pilot plant data gathering. The design information helped to guide the pilot plant and vice versa. In the end, the design details showed that the process was technically feasible. However, at the relatively small size of this plant the specific capital cost was very high and could only be considered if the pulp operation needed to replace the recovery boiler. Some of the reasons for the costs being high are attributed to the many constraints that needed to be addressed in the pulping process. Additionally, the Methanol product did not have a vehicle fuel supply chain to enter into. A different product selection could have eliminated this issue. However, with the selected design, the installation at Escanaba Paper Mill was not economically feasible and the project was not pursued further.

  2. Radiological Effluent Technical Specifications (RETS) implementation, Kewaunee Nuclear Power Plant

    International Nuclear Information System (INIS)

    Serrano, W.; Akers, D.W.

    1985-06-01

    A review of the Radiological Effluent Technical Specifications (RETS) for the Kewaunee Nuclear Power Plant was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7'' of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual and the Radiological Environmental Monitoring Manual were reviewed and generally found to be in compliance with the NRC review guidelines

  3. Standard technical specifications: Babcock and Wilcox Plants. Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Babcock ampersand Wilcox Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  4. 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.

  5. Canadian CANDU plant data systems for technical surveillance and analysis

    International Nuclear Information System (INIS)

    Deverno, M.; Pothier, H.; Xian, C.; Grosbois, J. De; Bosnich, M.

    1996-01-01

    Plant data systems are emerging as a critical plant support system technology. In particular, plant-wide Historical Data Systems (HDS) are pivotal to the successful implementation of technical surveillance and analysis programs supporting plant operations, maintenance, safety, and licensing activities. In partnership with Canadian CANDU utility and design organizations, AECL has conducted a review of current Canadian CANDU HDS approaches with emphasis on understanding the existing functionality and uses of plant historical data systems, their future needs and benefits. The results is a vision of a plant-wide HDS providing seamless access to both near real-time and historical data, user tool-kits for data visualization and analysis, and data management of the large volume of data acquired during the life of a plant. The successful implementation of the HDS vision will lead to higher capability and capacity factors while minimizing Operations, Maintenance, and Administration (OM and A) costs. (author). 5 refs, 3 figs

  6. Canadian CANDU plant data systems for technical surveillance and analysis

    Energy Technology Data Exchange (ETDEWEB)

    Deverno, M; Pothier, H; Xian, C [Atomic Energy of Canada Ltd., Control Centre Technology Branch, Fredericton, NB (Canada); Grosbois, J De; Bosnich, M [Atomic Energy of Canada Ltd., Control Centre Technology Branch, Chalk River, ON (Canada). Chalk River Labs.

    1997-12-31

    Plant data systems are emerging as a critical plant support system technology. In particular, plant-wide Historical Data Systems (HDS) are pivotal to the successful implementation of technical surveillance and analysis programs supporting plant operations, maintenance, safety, and licensing activities. In partnership with Canadian CANDU utility and design organizations, AECL has conducted a review of current Canadian CANDU HDS approaches with emphasis on understanding the existing functionality and uses of plant historical data systems, their future needs and benefits. The results is a vision of a plant-wide HDS providing seamless access to both near real-time and historical data, user tool-kits for data visualization and analysis, and data management of the large volume of data acquired during the life of a plant. The successful implementation of the HDS vision will lead to higher capability and capacity factors while minimizing Operations, Maintenance, and Administration (OM and A) costs. (author). 5 refs, 3 figs.

  7. Application of data-processing to the technical and economical management of the plants of Simo

    International Nuclear Information System (INIS)

    Chastagner, F.

    1988-01-01

    The firm Simo is entrusted with the processing of the uranium ores extracted from the mines of Cogema in France, in its three plants. The paper describes the conception and the functioning of the information system. Among the advantages contributed by the system, the coherence between the technical follow-up and the economical follow-up constitutes one of the principal progressive features [fr

  8. Technical Integration of SMART Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. H.; Park, P. H.; Noh, P. C. (and others)

    2006-12-15

    Preliminary experimental tests were carried out using the thermal-hydraulic integral test facility, VISTA (Experimental Verification by Integral Simulation of Transients and Accidents), which has been constructed to simulate the SMART-P. The VISTA facility is an integral test facility including the primary and secondary systems as well as safety-related Passive Residual heat removal (PRHR) systems. The integrated SMART desalination plant consists of Multi Effect Distillation Process combined with Thermal-Vapor Compressor(MED-TVC) and coupled with the extracted steam from turbine through the steam transformer. Steam transformer produces the main pressure steam and supplies to the MED-TVC unit. MED-TVC was selected as a desalination process coupled with SMART, since the thermal vapor compression is very effective where the steam is available at high temperature and pressure conditions than required in the evaporator. The standard design of the SMART desalination plant is under development as a part of the SMART project. This report describes design concept of these systems and their requirements.

  9. 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

  10. Plant conservation progress in the United States

    Science.gov (United States)

    Kayri Havens; Andrea Kramer; Ed. Guerrant

    2017-01-01

    Effective national plant conservation has several basic needs, including: 1) accessible, up-to-date information on species distribution and rarity; 2) research and management capacity to mitigate the impact of threats that make plants rare; 3) effective networks for conserving species in situ and ex situ; 4) education and training to make sure the right people are...

  11. Waste Isolation Pilot Plant Technical Assessment Team Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2015-03-17

    This report provides the results of the Waste Isolation Pilot Plant (WIPP) technical assessment led by the Savannah River National Laboratory and conducted by a team of experts in pertinent disciplines from SRNL and Lawrence Livermore National Laboratory (LLNL), Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and Sandia National Laboratories (SNL).

  12. Remediation Using Plants and Plant Enzymes: A Progress Report

    National Research Council Canada - National Science Library

    1995-01-01

    .... In every case, the sources are plants growing near the sediment. The use of plants for remediation of hazardous materials such as TNT or other munitions like RDX and HMX has led to a new approach to remediation-- phytoremediation...

  13. 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)

  14. 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

  15. State of work on Main Task 3.1.3 of Complex Programme of Scientific and Technical Progress and precondition for ensuring Czechoslovak automatic control system instrumentation and electrical parts for new-generation power plant project

    International Nuclear Information System (INIS)

    Hrebik, V.

    1990-01-01

    A brief account is given of the state of negotiations with the Soviet partner concerning the preparation, creation and implementation of prospective automated technological equipment control systems at WWER type nuclear power plants. The organization is very clumsy in some fields and their conceptions are not clear. (Z.S.)

  16. Quantifying progress toward a conservation assessment for all plants.

    Science.gov (United States)

    Bachman, Steven P; Nic Lughadha, Eimear M; Rivers, Malin C

    2018-06-01

    The Global Strategy for Plant Conservation (GSPC) set an ambitious target to achieve a conservation assessment for all known plant species by 2020. We consolidated digitally available plant conservation assessments and reconciled their scientific names and assessment status to predefined standards to provide a quantitative measure of progress toward this target. The 241,919 plant conservation assessments generated represent 111,824 accepted land plant species (vascular plants and bryophytes, not algae). At least 73,081 and up to 90,321 species have been assessed at the global scale, representing 21-26% of known plant species. Of these plant species, at least 27,148 and up to 32,542 are threatened. Eighty plant families, including some of the largest, such as Asteraceae, Orchidaceae, and Rubiaceae, are underassessed and should be the focus of assessment effort if the GSPC target is to be met by 2020. Our data set is accessible online (ThreatSearch) and is a baseline that can be used to directly support other GSPC targets and plant conservation action. Although around one-quarter of a million plant assessments have been compiled, the majority of plants are still unassessed. The challenge now is to build on this progress and redouble efforts to document conservation status of unassessed plants to better inform conservation decisions and conserve the most threatened species. © 2017 The Authors. Conservation Biology published by Wiley Periodicals, Inc. on behalf of Society for Conservation Biology.

  17. Technical evaluation of bids for nuclear power plants

    International Nuclear Information System (INIS)

    1981-01-01

    In continuation of its efforts to provide comprehensive and impartial guidance to Member States facing the need to introduce nuclear power, the International Atomic Energy Agency is issuing this guidebook as part of a series of guidebooks and codes of practice and, in particular, as a necessary supplement to 'Economic Evaluation of Bids for Nuclear Power Plants: A Guidebook', published by the IAEA in 1976 as Technical Reports Series No.175. The present publication is intended for project managers and senior engineers of electric utilities who are concerned with the evaluation of bids for a nuclear power project. It assumes that the reader has a good knowledge of the technical characteristics of nuclear power plants and of nuclear power project implementation. Its purpose is to provide the information necessary to organize, guide and supervise the technical evaluation of bids for a nuclear power project. It goes without saying that the technical staff carrying out the evaluation must have prior technical experience which cannot be provided by a guidebook

  18. Standard Technical Specifications, General Electric plants, BWR/4

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

  19. Standard Technical Specifications, General Electric Plants, BWR/6

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  20. Standard Technical Specifications, General Electric plants, BWR/4

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  1. Standard Technical Specifications, General Electric Plants, BWR/6

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

  2. Standard Technical Specifications, General Electric plants, BWR/6

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  3. 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.

  4. Standard Technical Specifications, General Electric plants, BWR/4

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power specifications. This report contains three volumes. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS

  5. Environmental Research Division technical progress report: January 1986--October 1987

    International Nuclear Information System (INIS)

    1988-07-01

    Technical process in the various research activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1986-1987. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Fundamental Molecular Physics and Chemistry, and Organic Geochemistry and Environmental Instrumentation 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. Individual projects under each division are processed separately for the data bases

  6. Environmental Research Division technical progress report: January 1986--October 1987

    Energy Technology Data Exchange (ETDEWEB)

    1988-07-01

    Technical process in the various research activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1986-1987. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Fundamental Molecular Physics and Chemistry, and Organic Geochemistry and Environmental Instrumentation 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. Individual projects under each division are processed separately for the data bases.

  7. 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)

  8. Technical Progress and Development Directions of Oceanic Spatial Information Datum

    Directory of Open Access Journals (Sweden)

    BAO Jingyang

    2017-10-01

    Full Text Available This paper briefly analyzes the basic development and technical situation of oceanic spatial information datum, reviews the main processes of oceanic vertical datum and correlative oceanic tidal study, such as improvement and perfect methods of determining tidal station vertical datum, realizing form of vertical datum controlled by tidal station, effect on maintaining vertical datum by long-term tidal station, oceanic tidal model establishing, and also construction and transformation of tidal datum, and then forecasts the key development directions of oceanic spatial information datum on high-accuracy marine position service, vertical datum and the transferring model refinement and spatial datum application.

  9. 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.

  10. A technical learning on the Pressurized Water Nuclear Power Plants using animation

    International Nuclear Information System (INIS)

    Ito, Hajime; Tomohara, Yasutaka; Kubo, Setsuo; Ninomiya, Toshiaki

    2002-01-01

    The pressurized water nuclear power generation plants tends to reduce construction of its new plant from viewpoints of recent stabilization in power demand/supply balance, development of new siting points, and so on. And, together with reducing any opportunity to experience at site, generation alternation to younger engineers without such experiences is progressing. In order to carry out technical tradition with high quality , as it is important to understand experiences of troubles and so on as valuable inheritance to apply them to actual use, it can be thought, in doubt, to be one of solving measures to prepare some learning tools applying the newest technology. The Kansai Electric Co., Ltd. Developed a CAD software using animation and 3D pictures using a personal computer which is edited some processes of technical transition on nuclear energy as a reference on a shape of CD ROM as an object from initial period of nuclear power station to present APWR. (G.K.)

  11. Crystalline Repository Project. Technical progress report, October 1982-March 1983

    International Nuclear Information System (INIS)

    1985-01-01

    This document reports the progress being made periodically on the development of a geologic repository in crystalline rock for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Crystalline Respository Development (OCRD), a prime contractor of the US Department of Energy Repository Project Office. The studies include work by other prime contractors and by subcontractors to OCRD

  12. 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

  13. Floating natural gas processing plants. Technical ideal or feasible technology

    Energy Technology Data Exchange (ETDEWEB)

    Backhaus, H

    1977-04-01

    Realizability of floating natural gas processing plants is decisively influenced by the economy of the system. Illustrated by the example of the natural gas product LPG (liquefied petroleum gas), a model cost calculation is carried out. It is demonstrated that the increase in the price level during the 1973/1974 energy crisis is an important factor for the realiability in terms of economy of such complicated technical systems. Another aspect which the model calculation revealed is that the economy of floating natural gas processing plants and storage systems can only be estimated in connection with other system components.

  14. Waste Management Program: Technical progress report, July-December 1985

    International Nuclear Information System (INIS)

    1987-12-01

    This report provides information on operations and development programs relating to the management of radioactive wastes at the Savannah River Plant. Information on environmental and safety assessments, waste form development, and process and equipment development are reported for long-term waste management. 13 refs., 20 figs., 16 tabs

  15. Waste Management Program: Technical progress report, January-June 1985

    International Nuclear Information System (INIS)

    1987-12-01

    This report provides information on operations and development programs relating to the management of radioactive wastes at the Savannah River Plant. Information on environmental and safety assessments, waste form development, and process and equipment development are reported for long-term waste management. 35 refs., 12 figs., 8 tabs

  16. U Plant Aggregate Area Management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    This document was prepared in support of an Aggregate Area Management Study of U Plant. It provides a technical baseline of the aggregate area and results from an environmental investigation that was undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC), which is currently the Waste Site and Facility Research Office, Natural Resources, Bechtel Hanford, Inc. (BHI). It is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. U Plant refers to the 221-U Process Canyon Building, a chemical separation facility constructed during World War II. It also includes the Uranium Oxide (UO 3 ) Plant constructed at the same time as 221-U as an adjunct to the original plutonium separation process but which, like 221-U, was converted for other missions. Waste sites are associated primarily with U Plant's 1952 through 1958 Uranium Metal Recovery Program mission and the U0 3 Plant's ongoing U0 3 mission. Waste sites include cribs, reverse wells, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, a waste vault, and the lines and encasements that connect them. It also includes the U Pond and its feed ditches and an underground tank farm designed for high-level liquid wastes

  17. Technical concepts of further improvement of nuclear power plant safety

    International Nuclear Information System (INIS)

    Sochor, R.

    1983-01-01

    The following technical concepts are described which secure the integrity of the containment in case of an accident whose scale exceeds the so-called design basis accident: siting nuclear power plants underground which raises construction costs by 20 - 25%; completing the containment with equipment preventing the outflow of molten corium; completing the containment with emergency pressure space for discharging overpressure - this emergency space is filled with gravel which will trap approximately 50% of fission waste. (Ha)

  18. Progress report of Technical Physics Division: April 1980 - March 1982

    International Nuclear Information System (INIS)

    Chaudhry, Ramesh; Vijendran, P.

    1983-01-01

    Activities, with an individual summary of each, of the Technical Physics Division (TPD) of the Bhabha Atomic Research Centre (BARC), Bombay are reported for the period April 1980 - March 1982. The major thrust of the TPD's work has been in: (i) design and fabrication of instruments, devices and equipment and (ii) development of techniques in the frontline research and technology areas like vacuum science, surface analysis, cryogenics and crystal growing. The Division also provided custombuilt electronics equipment, vacuum systems and glass components and devices to the various Divisions of BARC and other units of the DAE. Training and manpower development activities and technology transfer activities are also reported. Lists of seminars, colloquia, publications during the period of the report are given. (M.G.B.)

  19. 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.)

  20. Electronic refrigerant leak detector. Quarterly technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    Talamas, E. Jr.

    1998-10-15

    The project comprises three main tasks. They are (1) Develop, design, and fabricate sensors, (2) Develop, design, and fabricate test instruments, (3) Testing and data analysis. The milestone includes 17 sub-tasks for the 52-weeks project period, starting on May 1, 1998 and ending on April 30, 1999. As stated in the Application for Federal Assistance, Micronic intended to relocate to a new office by June of 1998. This decision was delayed, since the first partial payment was transferred on August 12, 1998. Micronic plans to relocate this November. A second Provisional Application for a US patent has been filed. Progress made during this period is reported.

  1. Fundamental studies of separation processes. Technical progress report

    International Nuclear Information System (INIS)

    Rogers, L.B.

    1975-06-01

    Studies using high-precision gas chromatography and supercritical fluid chromatography have produced new types of information on liquid crystals and on behavior of substances in the region of the critical temperature, respectively. In addition, the first successful studies of the effects of pressure on cation exchange have been made using aqueous solutions of alkali metal nitrates. In contrast, progress on separations of isotopic species using gas chromatography has been disappointing. In that area, the chief accomplishment has been a determination of the levels of accuracy and precision with which isotopic abundances can be measured using our quadrupole mass spectrometer. (U.S.)

  2. 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)

  3. Waste Management Program. Technical progress report, July-December, 1984

    International Nuclear Information System (INIS)

    1986-10-01

    This report provides information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant and offplant participants. The studies on environmental and safety assessments, other support, in situ storage or disposal, waste form development and characterization, process and equipment development, and the Defense Waste Processing Facility are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations: tank farm operation, inspection program, burial ground operations, and waste transfer/tank replacement

  4. Waste Management Program. Technical progress report, Aporil-June 1983

    Energy Technology Data Exchange (ETDEWEB)

    None

    1984-02-01

    This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant. The studies on environmental and safety assessments, process and equipment development, TRU waste, and low-level waste are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities.

  5. Waste Management Program. Technical progress report, October-December 1982

    International Nuclear Information System (INIS)

    1983-07-01

    This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant and offplant participants. The studies on environmental and safety assessments, in situ storage or disposal, waste from development and characterization, process and equipment development, and low-level waste management are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities

  6. Technical progress report, October 1, 1980-September 30, 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Progress during the 12-month period, October 1, 1980 to September 30, 1981 on the University of Wisconsin Plasma Physics contract is described. Most of the work centers around two major experimental devices, the Levitated Octupole and Tokapole II. A major upgrade of the Octupole is underway to include 2 MW of ICRH and 1.8 MW of neutral beam heating. Meanwhile, gun optimization and low field operation has resulted in the attainment of 35% beta, a factor of 9 above the single fluid ballooning limit. The ICRH experiment is well underway, and the first neutral beam source has been installed. The Tokapole is operating reliably at the full design field of 10 kG with 12 msec discharges. Low q (approx. 0.4) discharges with flat current profiles are obtained at reduced (approx. 3kG) toroidal field. The device is presently being used to study shear Alfven wave heating, ECRH startup, poloidal ohmic heating, and plasma transport

  7. 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...

  8. Automation of technical specification monitoring for nuclear power plants

    International Nuclear Information System (INIS)

    Lin, J.C.; Abbott, E.C.; Hubbard, F.R.

    1986-01-01

    The complexity of today's nuclear power plants combined with an equally detailed regulatory process makes it necessary for the plant staff to have access to an automated system capable of monitoring the status of limiting conditions for operation (LCO). Pickard, Lowe and Garrick, Inc. (PLG), has developed the first of such a system, called Limiting Conditions for Operation Monitor (LIMCOM). LIMCOM provides members of the operating staff with an up-to-date comparison of currently operable equipment and plant operating conditions with what is required in the technical specifications. LIMCOM also provides an effective method of screening tagout requests by evaluating their impact on the LCOs. Finally, LIMCOM provides an accurate method of tracking and scheduling routine surveillance. (author)

  9. Evaluation of Perry Nuclear Power Plant Unit 1 technical specifications

    International Nuclear Information System (INIS)

    Baxter, D.E.; Bruske, S.J.

    1985-11-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Perry Nuclear Power Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the requirements of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Perry T/S. Several discrepancies were identified and subsequently resolved through telephone conversations with the staff reviewer and the utility representative. Pending completion of the resolutions noted in Parts 3 and 4 of this report, the Perry Nuclear Power Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  10. Evaluation of Watts Bar Nuclear Plant Unit 1 Technical Specifications

    International Nuclear Information System (INIS)

    Baxter, D.E.; Bruske, S.J.

    1985-08-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Watts Bar Nuclear Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumption of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Watts Bar T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Watts Bar Nuclear Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  11. Signal validation in nuclear power plants: Progress report No. 3

    International Nuclear Information System (INIS)

    Kerlin, T.W.; Upadhyaya, B.R.

    1987-01-01

    This report summarizes the progress in the Signal Validation Project. Specifically, the advances made in several of the modules have been described. Some of these modules are now ready for preliminary implementation using plant operational data. Arrangements with Northeast Utilities Service Company (NUSCO) for transferring several sets of plant operational data from Millstone-3 PWR have been made in preparation for this phase of the project

  12. Current progress and technical challenges of flexible liquid crystal displays

    Science.gov (United States)

    Fujikake, Hideo; Sato, Hiroto

    2009-02-01

    We focused on several technical approaches to flexible liquid crystal (LC) display in this report. We have been developing flexible displays using plastic film substrates based on polymer-dispersed LC technology with molecular alignment control. In our representative devices, molecular-aligned polymer walls keep plastic-substrate gap constant without LC alignment disorder, and aligned polymer networks create monostable switching of fast-response ferroelectric LC (FLC) for grayscale capability. In the fabrication process, a high-viscosity FLC/monomer solution was printed, sandwiched and pressed between plastic substrates. Then the polymer walls and networks were sequentially formed based on photo-polymerization-induced phase separation in the nematic phase by two exposure processes of patterned and uniform ultraviolet light. The two flexible backlight films of direct illumination and light-guide methods using small three-primary-color light-emitting diodes were fabricated to obtain high-visibility display images. The fabricated flexible FLC panels were driven by external transistor arrays, internal organic thin film transistor (TFT) arrays, and poly-Si TFT arrays. We achieved full-color moving-image displays using the flexible FLC panel and the flexible backlight film based on field-sequential-color driving technique. Otherwise, for backlight-free flexible LC displays, flexible reflective devices of twisted guest-host nematic LC and cholesteric LC were discussed with molecular-aligned polymer walls. Singlesubstrate device structure and fabrication method using self-standing polymer-stabilized nematic LC film and polymer ceiling layer were also proposed for obtaining LC devices with excellent flexibility.

  13. Texas Experimental Tokamak, a plasma research facility: Technical progress report

    International Nuclear Information System (INIS)

    Wootton, A.J.

    1995-08-01

    In the year just past, the authors made major progress in understanding turbulence and transport in both core and edge. Development of the capability for turbulence measurements throughout the poloidal cross section and intelligent consideration of the observed asymmetries, played a critical role in this work. In their confinement studies, a limited plasma with strong, H-mode-like characteristics serendipitously appeared and received extensive study though a diverted H-mode remains elusive. In the plasma edge, they appear to be close to isolating a turbulence drive mechanism. These are major advances of benefit to the community at large, and they followed from incremental improvements in diagnostics, in the interpretation of the diagnostics, and in TEXT itself. Their general philosophy is that the understanding of plasma physics must be part of any intelligent fusion program, and that basic experimental research is the most important part of any such program. The work here demonstrates a continuing dedication to the problems of plasma transport which continue to plague the community and are an impediment to the design of future devices. They expect to show here that they approach this problem consistently, systematically, and effectively

  14. S Plant Aggregate Area Management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    This document is prepared in support of an Aggregate Area Management Study of S Plant, 200 West Area, at the US Department of Energy's (DOE) Hanford Site near Richland, Washington. It provides a technical baseline of the aggregate area and the results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC). This document is based on review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. This report describes the REDOX facility and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, underground tank farms designed for high-level liquid wastes, and the lines and encasements that connect them

  15. Z plant aggregate area management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    This document was prepared in support of the development of a Aggregate Area Management Study of Z Plant, 200 West Area, at the US Department of Energy (DOE) Hanford Site near Richland, Washington. It provides a technical description and operational history of the aggregate area and results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC) which is currently the Waste Site and Facility Research Office, Natural Resources, Bechtel Hanford, Inc. (BHI). It is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted in support of this report

  16. The research progress on plant mutant germplasm resources in China

    International Nuclear Information System (INIS)

    He Cexi; Ji Linzhen; Zhao Shirong

    1991-07-01

    Mutants induced by nuclear radiation or other mutagens are new artificial germplasm resources. Some mutants have been applied in plant breeding and great achievements have been reached. The status and progress on the collection, identification and utilization of mutants in China are introduced. A proposal for developing mutant germplasm resources with good agronomic characters is suggested

  17. Technical Division quarterly progress report, April 1--June 30, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Slansky, C.M.; Dickey, B.R.; Musgrave, B.C.; Rohde, K.L.

    1977-07-01

    Fuel Cycle Research and Development: Results are presented on the fluidized-bed calcination of high-level radioactive waste from reprocessing on the post treatment of the calcine, and on the removal of actinide elements from the waste prior to calcination. Other projects include the development of storage technology for /sup 85/Kr waste; a study of the hydrogen mordenite catalyzed reaction between NO/sub x/ and NH/sub 3/; the adsorption and storage of /sup 129/I on silver exchanged mordenite; physical properties, materials of construction, and unit operations studies on the evaporation of high-level waste; the behavior of volatile radionuclides during the combustion of HTGR graphite-based fuel; and the use of the uranium-ruthenium system in age-dating uranium ore bodies. Special Materials Production: The long-term management of defense waste from the ICPP covers postcalcination treatment of ICPP calcined waste; the removal of actinide elements from first-cycle raffinate; the retrieval and handling of calcined waste from ICPP storage vaults; and the preparation of the ''Defense Waste Document''. Process improvements are reported on the Fluorinel headend process for Zircaloy-clad fuels and on uranium accountability measurements. Other development results cover the process for recovering spent Rover fuel, buried pipeline transfer systems, support to the Waste Management Program, and effluent monitoring methods evaluation and development. Other Projects Supporting Energy Development: In this category are studies on nuclear materials security; application of a liquid-solid fluidized-bed heat exchanger to the recovery of geothermal heat; in-plant reactor source term measurements; burnup methods for fast breeder reactor fuels; absolute thermal fission yield measurements; analytical support to light water breeder reactor development; research on analytical methods; and the behavior of environmental species of iodine.

  18. 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.

  19. Technical knowledge/skill transfer in nuclear power plant manufacturer

    International Nuclear Information System (INIS)

    Arima, Hiroshi; Sagawa, Wataru; Ogawa, Yukio

    2009-01-01

    Due to environmental concerns such as global warming, needs for nuclear power is increasing. However, many expert engineers and technicians are now entering a period of retirement. And due to weak demands of new plant construction for long years, opportunity for technology learning/experience had been lost. Therefore, to secure human resource and to develop their ability are urgent issues for nuclear industries. Hitachi nuclear division continues efforts for technology transfer and human resource training. This paper describes the following two activities. (1) Improvement of common technical basis, and implementation of PDCA cycle, (2) Development of supporting tools to accelerate technology transfer through OJT (On the Job Training). (author)

  20. Technical progress in INPRO activities on modelling and innovation

    International Nuclear Information System (INIS)

    Villalibre, P.; Haas, E.; Khartabil, H.; Kim, S.; Korinny, A.; Usanov, V. and others

    2010-01-01

    Among the 31 Members of the 'International Project on Innovative Nuclear Reactors and Fuel Cycles' (INPRO) in April 2010, more than 20 are cooperating in the implementation of Collaborative Projects (CPs) related to the four substantive Programme Areas of the INPRO Action Plan. The purpose of the CPs is to contribute to the achievement of goals established in the programmatic areas. This paper presents progress status of several CPs dealing with Modelling and Innovation: - CP on Environmental Impact Benchmarking applicable to Nuclear Energy Systems under Normal Operation (ENV): A benchmark of codes and methods for determining radiation released during normal operation of nuclear facilities is performed by using established source term, release scenario, and target group (humans). - CP on Proliferation Resistance: Acquisition/Diversion Pathway Analysis (PRADA): 'PRADA' addresses the identification and analyses of high level pathways for the acquisition of weapons usable material, and makes recommendations for evaluating the multiplicity and robustness of barriers against proliferation. PRADA develops a case study based on DUPIC fuel cycle. The outcome from the project will support the assessment methodologies developed at GIF and INPRO. - CP on Global Architecture of Nuclear Energy Systems based on Thermal and Fast Reactors including Closed Fuel Cycle (GAINS): GAINS objective is to develop a methodological platform for assessing future nuclear energy systems taking into account the sustainable development, and to validate the results through sample analyses. High and moderate scenarios of nuclear energy demand and supply during the Century (5000 and 2500 GWe respectively in the year 2100) are being analysed using homogeneous and heterogeneous considerations. A non-geographic approach grouping the countries according to their planned use of nuclear energy has being established. - CP on Investigations of the 233 U/Th Fuel Cycle (ThFC): ThFC objective is to explore FC

  1. Technical guidelines for aseismic design of nuclear power plants

    International Nuclear Information System (INIS)

    Park, Y.J.; Hofmayer, C.H.

    1994-06-01

    This document is a translation, in its entirety, of the Japan Electric Association (JEA) publication entitled open-quotes Technical Guidelines for Aseismic Design of Nuclear Power Plants - JEAG 4601-1987.close quotes This guideline describes in detail the aseismic design techniques used in Japan for nuclear power plants. It contains chapters dealing with: (a)the selection of earthquake ground motions for a site, (b) the investigation of foundation and bedrock conditions, (c) the evaluation of ground stability and the effects of ground movement on buried piping and structures, (d) the analysis and design of structures, and (e) the analysis and design of equipment and distribution systems (piping, electrical raceways, instrumentation, tubing and HVAC duct). The guideline also includes appendices which summarize data, information and references related to aseismic design technology

  2. Technical and economic feasibility of membrane technology. Fourth technical progress report, June 17-September 16, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Sandre, A.

    1980-10-01

    Progress is reported on the investigation of the potential application of reverse osmosis, ultrafiltration and electrodialysis to the system of solids concentration in beet sugar process streams. During this period, emphasis was put on running reverse osmosis tests with a new prototype machine to select the most suitable membranes for the concentrating of sugar solutions. An economic analysis of using reverse osmosis in a factory producing 10/sup 6/ gal/day of thin juice is discussed. (DMC)

  3. 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

  4. 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

  5. Amarillo National Resource Center for Plutonium. Quarterly technical progress report, May 1--July 31, 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    Progress is reported on research projects related to the following: Electronic resource library; Environment, safety, and health; Communication, education, training, and community involvement; Nuclear and other materials; and Reporting, evaluation, monitoring, and administration. Technical studies investigate remedial action of high explosives-contaminated lands, radioactive waste management, nondestructive assay methods, and plutonium processing, handling, and storage.

  6. 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

  7. 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)

  8. 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

  9. 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

  10. Restructuring of technical standards for regulation of nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Takehiko Nakamura; Masahiro Aoki; Kiyoshi Takasaka; Yukio Hirano; Eiji Hiraoka; Mikio Kurihara; Junichi Morita; Zenichi Ogiso; Yoshihiko Nishiwaki

    2005-01-01

    Regulatory requirements for nuclear power plants (NPPs) have been reviewed and restructured in Japan, in order to accommodate recent technical progress in a timely manner. In this new regulatory process, the governmental technical requirements are modified to performance specifications and the consensus codes and standards established by academic and public societies are being used as prescriptive specifications to realize the performance. As a first step, a fitness-rule to evaluate structural integrity of the components having cracks was introduced into the Japanese regulatory rules in Oct. 2003. 'Rules on Fitness-for-Service for Nuclear Power Plants' by the Japan Society of Mechanical Engineers (JSME) was utilized as a prescriptive specification for in-service-inspections and for the integrity evaluation of the components with stress corrosion cracks and fatigue cracks. The process is being extended to other requirements for structural design and construction of mechanical components and concrete containments, as well as requirements for welding. Prescriptive specifications for the requirements by the JSME and other consensus codes have been technically reviewed by a regulatory body, the Nuclear and Industrial Safety Agency, and specified as regulatory standards for the licensing procedure. In the course of the review, consistency and coverage of the requirements were examined against the Safety Design Guidelines by the Nuclear Safety Commission and the safety requirements for design of nuclear power plant by the International Atomic Energy Agency, NS-R-1. Additional requirements against the stress corrosion cracking, hydrogen accumulation, high-cycle thermal fatigue, etc. are being specified in the requirements to prevent troubles experienced in NPPs in Japan and overseas. This paper describes outlines of the on-going activities restructuring the technical standards for regulation of NPPs in Japan. (authors)

  11. Technical diagnostics - equipment monitoring for increasing safety and availability of nuclear power plants

    International Nuclear Information System (INIS)

    Sturm, A.; Foerster, R.

    1977-01-01

    Utilization of technical diagnostics in equipment monitoring of nuclear power plants for ensuring nuclear safety, economic availability, and for decision making on necessary maintenance is reviewed. Technical diagnostics is subdivided into inspection and early detection of malfunctions. Moreover, combination of technical diagnostics and equipment monitoring, integration of technical diagnostics into maintenance strategy, and problems of introducing early detection of malfunctions into maintenance management of nuclear power plants are also discussed. In addition, a compilation of measuring techniques used in technical diagnostics has been made. The international state of the art of equipment monitoring in PWR nuclear power plants is illustrated by description of the sound and vibration measuring techniques. (author)

  12. PUREX Plant aggregate area management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    The PUREX aggregate area is made up of six operable units; 200-PO-1 through 200-PO-6 and consists of liquid and solid waste disposal sites in the vicinity of, and related to, PUREX Plant operations. This report describes PUREX and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches and ditches, ponds, catch tanks, settling tanks, diversion boxes, underground tank farms, and the lines and encasements that connect them. Each waste site in the aggregate area is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. This document provides a technical baseline of the aggregate area and results from an environmental investigation. This document is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted

  13. 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.

  14. Cycling of conventional power plants: Technical limits and actual costs

    International Nuclear Information System (INIS)

    Van den Bergh, Kenneth; Delarue, Erik

    2015-01-01

    Highlights: • Literature reports a wide range of cycling parameters (technical and cost-related). • The impact of different cycling parameters is assessed. • The German 2013 system is studied as a case study. • Even for stringent parameters, the dynamic limit of the portfolio is not reached. • Cycling costs can be reduced with 40% when taken into account in the scheduling. - Abstract: Cycling of conventional generation units is an important source of operational flexibility in the electricity generation system. Cycling is changing the power output of conventional units by means of ramping and switching (starting up and shutting down). In the literature, a wide range of technical and cost-related cycling parameters can be found. Different studies allocate different cycling parameters to similar generation units. This paper assesses the impact of different cycling parameters allocated to a conventional generation portfolio. Both the technical limitations of power plants and all costs related to cycling are considered. The results presented in this paper follow from a unit commitment model, used for a case study based on the German 2013 system. The conventional generation portfolio has to deliver different residual load time series, corresponding to different levels of renewables penetration. The study shows, under the assumptions made, that although the dynamic limits of some units are reached, the limits of the conventional generation portfolio as a whole are not reached, even if stringent dynamic parameters are assigned to the generation portfolio and a highly variable residual load is imposed to the system. The study shows also the importance of including full cycling costs in the unit commitment scheduling. The cycling cost can be reduced by up to 40% when fully taken into account

  15. B Plant aggregate area management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    The B aggregate area is made up of 13 operable units; 200-BP 1 through 200-BP 1 1, 200-IU-6, and 200-SS-1 that consist of liquid and solid waste disposal sites in the vicinity of, and related to, B Plant operations. This report describes B Plant and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches and ditches, ponds, catch tanks, settling tanks, diversion boxes, underground tank farms designed for high-level liquid wastes, and the lines and encasements that connect them. Each waste site in the aggregate area is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. This document provides a technical baseline of the aggregate area and results from an environmental investigation. This document is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted

  16. Technical Proposal Salton Sea Geothermal Power Pilot Plant Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1975-03-28

    The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical and technical point-of-view; preliminary design of mineral recovery and brine clean-up facilities of sufficient size to match the planned pilot power plant. The Reservoir Production Subprogram will include monitoring the operation and maintenance of brine production, handling and injection systems which were built with private funding in phase 0, and monitoring of the brine characteristics and potential subsidence effects during well production and injection. Based on the above, recommendations and specifications will be prepared for production and

  17. 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...

  18. Coal to SNG: Technical progress, modeling and system optimization through exergy analysis

    International Nuclear Information System (INIS)

    Li, Sheng; Ji, Xiaozhou; Zhang, Xiaosong; Gao, Lin; Jin, Hongguang

    2014-01-01

    Highlights: • Technical progresses of coal to SNG technologies are reported. • The entire coal to SNG system is modeled. • Coupling between SNG production and power generation is investigated. • Breakthrough points for further energy saving are determined. • System performance is optimized based on the first and second laws of thermodynamics. - Abstract: For both energy security and CO 2 emission reduction, synthetic natural gas (SNG) production from coal is an important path to implement clean coal technologies in China. In this paper, an overview of the progress of coal to SNG technologies, including the development of catalysts, reactor designs, synthesis processes, and systems integration, is provided. The coal to SNG system is modeled, the coupling between SNG production and power generation is investigated, the breakthrough points for further energy savings are determined, and the system performance is optimized based on the first and the second laws of thermodynamics. From the viewpoint of the first law of thermodynamics, the energy conversion efficiency of coal to SNG system can reach 59.8%. To reduce the plant auxiliary power, the breakthrough points are the development of low-energy-consumption oxygen production technology and gas purification technology or seeking new oxidants for coal gasification instead of oxygen. From the viewpoint of the second law of thermodynamics, the major exergy destruction in a coal to SNG system occurs in the coal gasification unit, SNG synthesis unit and the raw syngas cooling process. How to reduce the exergy destruction in these units is the key to energy savings and system performance enhancement. The conversion ratio of the first SNG synthesis reactor and the split ratio of the recycle gas are key factors that determine the performance of both the SNG synthesis process and the whole plant. A “turning point” phenomenon is observed: when the split ratio is higher than 0.90, the exergy destruction of the SNG

  19. Evaluation of the feasibility, economic impact, and effectiveness of underground nuclear power plants. Final technical report

    International Nuclear Information System (INIS)

    1978-05-01

    Information on underground nuclear power plants is presented concerning underground nuclear power plant concepts; public health impacts; technical feasibility of underground concepts; economic impacts of underground construction; and evaluation of related issues

  20. The progress of mutation breeding for ornamental plants in China

    International Nuclear Information System (INIS)

    Jin Shouming

    1994-02-01

    In China, research on mutation breeding of ornamental plants was begun in the late 70's. In the past decade, about 40 plant species were tested, and hundreds of useful mutants were obtained. At least 63 mutant varieties have been produced, approved and released for cultivation in rose, chrysanthemum, canna, dahlia, bougainvillea and lotus. A rapid progress in methodology and technology of induced mutation breeding has been achieved, particularly in the selection of starting material, determination of suitable exposure and irradiation dose, expression and isolation of somatic mutation etc. In the future it is necessary to develop more plant species and mutation varieties to improve the mutation breeding method and to raise the economic benefit. Along with the development of China's economy and improvement of people's living standard more and more new varieties of ornamental plants will be required. In view of the good beginning, rich germplasm resource and favorable conditions, the prospect of mutation breeding for ornamental plants in China is very encouraging

  1. 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.

  2. The Waste Treatment Plant, a Work in Progress

    International Nuclear Information System (INIS)

    Hamel, W. F. Jr.; Duncan, G. M.

    2006-01-01

    There are many challenges in the design and construction of Department of Energy's (DOE) Waste Treatment and Immobilization Plant (WTP) at the Hanford site. The plant is being built to process some 55 million gallons of radioactive waste from 177 underground tanks. Engineering and construction are progressing on this largest project in the DOE complex. This paper describes some of WTP's principal recent challenges and opportunities and how they are being addressed to minimize impact on the project, enhance the capabilities of the facilities, and reduce risk. A significant new development in 2005 was the need to account for higher seismic accelerations than originally specified for the facility structures and equipment. Efforts have centered on continuing design and construction with minimal risk, while the final seismic design spectra was developed. Other challenges include development of an alternative cesium ion exchange resin to minimize the risk from reliance on a single product, implementing advanced analytical techniques to improve laboratory performance, adopting a thinner walled high level waste (HLW) canister to reduce waste volume and mission duration, and commissioning a comprehensive external flowsheet review of the design, along with its underpinning technologies, and projected plant operability. These challenges make it clear that WTP is a work in progress, but the challenges are being successfully resolved as the design and construction move on to completion. (authors)

  3. An analysis of factors that influence the technical efficiency of Malaysian thermal power plants

    International Nuclear Information System (INIS)

    See, Kok Fong; Coelli, Tim

    2012-01-01

    The main objectives of this paper are to measure the technical efficiency levels of Malaysian thermal power plants and to investigate the degree to which various factors influence efficiency levels in these plants. Stochastic frontier analysis (SFA) methods are applied to plant-level data over an eight year period from 1998 to 2005. This is the first comprehensive analysis (to our knowledge) of technical efficiency in the Malaysian electricity generation industry using parametric method. Our empirical results indicate that ownership, plant size and fuel type have a significant influence on technical efficiency levels. We find that publicly-owned power plants obtain average technical efficiencies of 0.68, which is lower than privately-owned power plants, which achieve average technical efficiencies of 0.88. We also observe that larger power plants with more capacity and gas-fired power plants tend to be more technically efficient than other power plants. Finally, we find that plant age and peaking plant type have no statistically significant influence on the technical efficiencies of Malaysian thermal power plants. - Highlights: ► We examine the technical efficiency (TE) levels of Malaysian thermal power plants. ► We also investigate the degree to which various factors influence efficiency levels in these plants. ► Stochastic frontier analysis methods are used. ► Average plant would have to increase their TE level by 21% to reach the efficient frontier. ► Ownership, plant size and fuel type have a significant influence on the TE levels.

  4. Technical safety appraisal of the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    1992-05-01

    On June 27, 1989, Secretary of Energy, Admiral James D. Watkins, US Navy (Retired), announced a 10-point initiative to strengthen environment, safety, and health (ES ampersand H) programs and waste management operations in the Department of Energy (DOE). One of the initiatives involved conducting independent Tiger Team Assessments (TTA) at DOE operating facilities. A TTA of the Idaho National Engineering Laboratory (INEL) was performed during June and July 1991. Technical Safety Appraisals (TSA) were conducted in conjunction with the TTA as its Safety and Health portion. However, because of operational constraints the the Idaho Chemical Processing Plant (ICPP), operated for the DOE by Westinghouse Idaho Nuclear Company, Inc. (WINCO), was not included in the Safety and Health Subteam assessment at that time. This TSA, conducted April 12 - May 8, 1992, was performed by the DOE Office of Performance Assessment to complete the normal scope of the Safety and Health portion of the Tiger Team Assessment of the Idaho National Engineering Laboratory. The purpose of TSAs is to evaluate and strengthen DOE operations by verifying contractor compliance with DOE Orders, to assure that lessons learned from commercial operations are incorporated into facility operations, and to stimulate and encourage pursuit of excellence; thus, the appraisal addresses more issues than would be addressed in a strictly compliance-oriented appraisal. A total of 139 Performance Objectives have been addressed by this appraisal in 19 subject areas. These 19 areas are: organization and administration, quality verification, operations, maintenance, training and certification, auxiliary systems, emergency preparedness, technical support, packaging and transportation, nuclear criticality safety, safety/security interface, experimental activities, site/facility safety review, radiological protection, worker safety and health compliance, personnel protection, fire protection, medical services and natural

  5. Qualification and actuation of the independent technical supervision organisms in nuclear power plants and others facilities

    International Nuclear Information System (INIS)

    1999-09-01

    This norm presents the following objectives: establishment of the Brazilian National Nuclear Energy Commission requirements for qualifying an institution as independent technical supervision organization, in a specific area of activity related to nuclear power plants and others nuclear or radioactive facilities as appropriated; regulation of the independent technical supervision and others complementary activities to be executed by an independent technical supervision organism

  6. Progress report on the investigation of nuclear plant costs

    International Nuclear Information System (INIS)

    Kent, G.F.

    1987-01-01

    Over the past few years, many studies have been performed in an effort to understand, evaluate, and explain the reasons for the substantial increases in nuclear plant costs, as well as for the divergence between predicted and actual costs. Concerns regarding these cost increases is shared by utility owners, engineer/constructors, and public utility commissions. The future use of nuclear power depends on the ability of the industry to control these costs while maintaining safety. Stone and Webster Engineering Corporation (SWEC) has responded to this concern by initiating an internal study to evaluate, quantify, and explain the factors influencing this cost growth. Previously, a conceptual approach was presented in which three explanatory variables or factors were used as surrogates for the many variables that affected plant cost. This paper presents a progress report of that continuing study

  7. Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

    International Nuclear Information System (INIS)

    Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L.

    1978-10-01

    The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems

  8. Folates in plants: research advances and progress in crop biofortification

    Science.gov (United States)

    Gorelova, Vera; Ambach, Lars; Rébeillé, Fabrice; Stove, Christophe; Van Der Straeten, Dominique

    2017-03-01

    Folates, also known as B9 vitamins, serve as donors and acceptors in one-carbon (C1) transfer reactions. The latter are involved in synthesis of many important biomolecules, such as amino acids, nucleic acids and vitamin B5. Folates also play a central role in the methyl cycle that provides one-carbon groups for methylation reactions. The important functions fulfilled by folates make them essential in all living organisms. Plants, being able to synthesize folates de novo, serve as an excellent dietary source of folates for animals that lack the respective biosynthetic pathway. Unfortunately, the most important staple crops such as rice, potato and maize are rather poor sources of folates. Insufficient folate consumption is known to cause severe developmental disorders in humans. Two approaches are employed to fight folate deficiency: pharmacological supplementation in the form of folate pills and biofortification of staple crops. As the former approach is considered rather costly for the major part of the world population, biofortification of staple crops is viewed as a decent alternative in the struggle against folate deficiency. Therefore strategies, challenges and recent progress of folate enhancement in plants will be addressed in this review. Apart from the ever-growing need for the enhancement of nutritional quality of crops, the world population faces climate change catastrophes or environmental stresses, such as elevated temperatures, drought, salinity that severely affect growth and productivity of crops. Due to immense diversity of their biochemical functions, folates take part in virtually every aspect of plant physiology. Any disturbance to the plant folate metabolism leads to severe growth inhibition and, as a consequence, to a lower productivity. Whereas today’s knowledge of folate biochemistry can be considered very profound, evidence on the physiological roles of folates in plants only starts to emerge. In the current review we will discuss the

  9. 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

  10. Technical basis for staffing levels at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Shurberg, D.A.; Haber, S.B. [Brookhaven National Lab., Upton, NY (United States); Morisseau, D. [Nuclear Regulatory Commission, Washington, DC (United States)] [and others

    1995-04-01

    The objective of this project is to provide a technical basis for the establishment of criteria for minimum staffing levels of licensed and non-licensed NPP shift personnel. Minimum staffing levels for the purpose of this study, are defined as those necessary for successful accomplishment of all safety and additional functions that must be performed in order for the licensee to meet applicable regulatory requirements. This project involves a multi-faceted approach to the investigation of the issue. Relevant NRC documentation was identified and reviewed. Using the information obtained from this documentation review, a test plan was developed to aid in the collection of further information regarding the adequacy of current shift staffing levels. The test plan addresses three different activities to be conducted to provide information to the NRC for use in the assessment of current minimum staffing levels. The first activity is collection of data related to industry shift staffing practices through site visits to seven nuclear power plants. The second activity is a simulator study, which will use licensed operator crews responding to a simulated event, under two different staffing levels. Finally, workload models will be constructed for both licensed and non-licensed personnel, using a priori knowledge of the simulator scenarios with data resulting from one of the staffing levels studied in the simulator, and the data collected from the site visits. The model will then be validated against the data obtained from the second staffing level studied in the simulator. The validated model can then be used to study the impact of changing staffing-related variables on the plant shift crew`s ability to effectively mitigate an event.

  11. Have U.S. power plants become less technically efficient? The impact of carbon emission regulation

    International Nuclear Information System (INIS)

    Zhou, Yishu; Huang, Ling

    2016-01-01

    We estimate directional distance functions to measure the impact of carbon emission regulation, the Regional Greenhouse Gas Initiative (RGGI) in particular, on U.S. power plants' technical efficiency. The model shows that the average technical efficiency scores for coal and natural gas plants are 88.70% and 83.14% respectively, indicating a very technically efficient industry. We find no evidence of technical efficiency changes due to the RGGI regime in the RGGI area. In the same area, relatively less efficient coal plants exited the market and slightly more efficient natural gas plants entered, compared to the incumbent plants. In addition, some evidence of a spillover effect is found. Using a counterfactual analysis, the RGGI regulation leads to a 1.48% decline in the average technical efficiency for coal plants within neighboring states of RGGI during 2009–2013. - Highlights: • RGGI does not lead to a change in the technical efficiency of RGGI power plants. • Less efficient coal plants exit. • Entering natural gas plants are more efficient. • RGGI has a spillover effect on neighboring coal plants.

  12. Hydrogen production by supercritical water gasification of biomass. Phase 1 -- Technical and business feasibility study, technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    The nine-month Phase 1 feasibility study was directed toward the application of supercritical water gasification (SCWG) for the economical production and end use of hydrogen from renewable energy sources such as sewage sludge, pulp waste, agricultural wastes, and ultimately the combustible portion of municipal solid waste. Unique in comparison to other gasifier systems, the properties of supercritical water (SCW) are ideal for processing biowastes with high moisture content or contain toxic or hazardous contaminants. During Phase I, an end-to-end SCWG system was evaluated. A range of process options was initially considered for each of the key subsystems. This was followed by tests of sewage sludge feed preparation, pumping and gasification in the SCW pilot plant facility. Based on the initial process review and successful pilot-scale testing, engineering evaluations were performed that defined a baseline system for the production, storage and end use of hydrogen. The results compare favorably with alternative biomass gasifiers currently being developed. The results were then discussed with regional wastewater treatment facility operators to gain their perspective on the proposed commercial SCWG systems and to help define the potential market. Finally, the technical and business plans were developed based on perceived market needs and the projected capital and operating costs of SCWG units. The result is a three-year plan for further development, culminating in a follow-on demonstration test of a 5 MT/day system at a local wastewater treatment plant.

  13. The impact of technical specification surveillance requirements and allowable outage times on plant availability

    International Nuclear Information System (INIS)

    Webster, S.A.; Finnicum, D.J.

    1985-01-01

    Surveillances required to be conducted by a plant's Technical Specifications have resulted in plant shutdowns and lost availability. This paper looks at shutdowns which have occurred due to required surveillance testing and insufficient repair time allowed by Technical Specifications. A loss of plant availability of almost 3% per plant year was found for U.S. pressurized water reactors during the five year period, 1979 to 1984. This figure excludes major problems which required plant shutdown whether or not mandated by the Technical Specifications. In addition to their affect on availability, such shutdowns can add to the challenges to plant safety systems and can affect plant aging by increasing the thermal cycles on plant components

  14. Nuclear challenges and progress in designing stellarator fusion power plants

    International Nuclear Information System (INIS)

    El-Guebaly, L.A.; Wilson, P.; Henderson, D.; Sawan, M.; Sviatoslavsky, G.; Tautges, T.; Slaybaugh, R.; Kiedrowski, B.; Ibrahim, A.

    2008-01-01

    Over the past 5-6 decades, stellarator power plants have been studied in the US, Europe, and Japan as an alternate to the mainline magnetic fusion tokamaks, offering steady-state operation and eliminating the risk of plasma disruptions. The earlier 1980s studies suggested large-scale stellarator power plants with an average major radius exceeding 20 m. The most recent development of the compact stellarator concept delivered ARIES-CS - a compact stellarator with 7.75 m average major radius, approaching that of tokamaks. For stellarators, the most important engineering parameter that determines the machine size and cost is the minimum distance between the plasma boundary and mid-coil. Accommodating the breeding blanket and necessary shield within this distance to protect the ARIES-CS superconducting magnet represents a challenging task. Selecting the ARIES-CS nuclear and engineering parameters to produce an economic optimum, modeling the complex geometry for 3D nuclear analysis to confirm the key parameters, and minimizing the radwaste stream received considerable attention during the design process. These engineering design elements combined with advanced physics helped enable the compact stellarator to be a viable concept. This paper provides a brief historical overview of the progress in designing stellarator power plants and a perspective on the successful integration of the nuclear activity into the final ARIES-CS configuration

  15. Future Scenarios for Plant Virus Pathogens as Climate Change Progresses.

    Science.gov (United States)

    Jones, R A C

    2016-01-01

    Knowledge of how climate change is likely to influence future virus disease epidemics in cultivated plants and natural vegetation is of great importance to both global food security and natural ecosystems. However, obtaining such knowledge is hampered by the complex effects of climate alterations on the behavior of diverse types of vectors and the ease by which previously unknown viruses can emerge. A review written in 2011 provided a comprehensive analysis of available data on the effects of climate change on virus disease epidemics worldwide. This review summarizes its findings and those of two earlier climate change reviews and focuses on describing research published on the subject since 2011. It describes the likely effects of the full range of direct and indirect climate change parameters on hosts, viruses and vectors, virus control prospects, and the many information gaps and deficiencies. Recently, there has been encouraging progress in understanding the likely effects of some climate change parameters, especially over the effects of elevated CO2, temperature, and rainfall-related parameters, upon a small number of important plant viruses and several key insect vectors, especially aphids. However, much more research needs to be done to prepare for an era of (i) increasingly severe virus epidemics and (ii) increasing difficulties in controlling them, so as to mitigate their detrimental effects on future global food security and plant biodiversity. © 2016 Elsevier Inc. All rights reserved.

  16. 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.

  17. 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)

  18. 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.

  19. 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.

  20. 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.

  1. 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

  2. Gas-Cooled Thermal Reactor Program. Semiannual technical progress report, October 1, 1982-March 3, 1983

    International Nuclear Information System (INIS)

    1983-06-01

    This report provides descriptions and results of the technical effort during the first half of FY 83 on the Gas-Cooled Thermal Reactor Program. The work on Integration and Management (WBS 01) includes the preparation of the Advanced Systems Concept Evaluation Plan and the Advanced Systems Technology Development Plan in addition to the program management activities. The Market Definition (WBS 03) efforts considered the application of the Modular Reactor System with reforming (MRS-R) to the production of methanol and ammonia and the refining of petroleum. Within the Plant Technology (WBS 13) task there were activities to develop anlytical methods for investigation of Coolant Transport Behavior and to define methods and criteria for High Temperature Structural Engineering design. In addition to the work on the advanced HTGR for process heat users, new activities were initiated in support of the HTGR-SC/C Lead plant Protect (WBS 30 and 31). The Plant Simulation task (WBS 31) was initiated to develop a computer code for simulation of plant operation and for plant transient systems analysis. The efforts on the advanced HTGR systems was performed under the Modular Systems task (WBS 41) to study the potential for multiple small reactors to provide lower costs, improved safety, and higher availability than the large monolithic core reactors

  3. Using plant status data for off-site emergency management: Technical and political aspects

    International Nuclear Information System (INIS)

    Govaerts, P.

    2004-01-01

    Subsequent to the TMI and Chernobyl accidents, emergency management is investigating the possibility of taking balanced decisions on interventions as early as possible. This process relies more and more on in-plant data to assess the term of releases. The paper discusses the regulatory aspects of the communication related to the source term between the utility and the national authorities, and the authorities of a host country and neighbouring countries that may be affected. The technical aspects of the assessment process are summarised, with the emphasis on the handling of uncertainties. Notwithstanding the technical progress, the main dilemma for the decision makers remains the same. Risk management and prevention measures become more familiar to authorities. Utilities and national authorities have to get rid of complexes with respect to accidents covered by the accepted residual risk. International emergency management has to look for an organisation type ensuring the continuity of countermeasures independent of the presence of administrative borders, and with respect to national autonomies. (authors)

  4. One System Integrated Project Team Progress in Coordinating Hanford Tank Farms and the Waste Treatment Plant

    International Nuclear Information System (INIS)

    Skwarek, Raymond J.; Harp, Ben J.; Duncan, Garth M.

    2013-01-01

    The One System Integrated Project Team (IPT) was formed at the Hanford Site in late 2011 as a way to improve coordination and itegration between the Hanford Tank Waste Treatment and Immobilization Plant (WTP) and the Tank Operations Contractor (TOC) on interfaces between the two projects, and to eliminate duplication and exploit opportunities for synergy. The IPT is composed of jointly staffed groups that work on technical issues of mutal interest, front-end design and project definition, nuclear safety, plant engineering system integration, commissioning, planning and scheduling, and environmental, safety, health and quality (ESH&Q) areas. In the past year important progress has been made in a number of areas as the organization has matured and additional opportunities have been identified. Areas covered in this paper include: Support for development of the Office of Envirnmental Management (EM) framework document to progress the Office of River Protection's (ORP) River Protection Project (RPP) mission; Stewardship of the RPP flowsheet; Collaboration with Savannah River Site (SRS), Savannah River National Laboratory (SRNL), and Pacific Northwest National Laboratory (PNNL); Operations programs integration; and, Further development of the waste acceptance criteria

  5. Guidelines for the technical evaluation of replacement items in nuclear power plants (NCIG-11)

    International Nuclear Information System (INIS)

    Craig, W.E.; Fakhar, A.A.; Shulman, M.N.

    1989-12-01

    This document presents guidelines and supporting information for the technical evaluation of replacement items in nuclear power plants. These guidelines contain six major sections which provide the practical knowledge and a programmatic approach to determine the technical and quality requirements necessary to generate purchase documents to procure the proper replacement items. The technical evaluation methodology includes the following steps. (1) Identification of the need for a technical evaluation. (2) Component/part functional classification procedures. (3) Performance of a Failure Modes and Effects Analysis. (4) Selection of Critical Characteristics for Design Determination. (5) Performance of a ''Like-For-Like'' or ''Alternate'' item Evaluation. (6) Preparation of the Technical and Quality Requirements Specification. Work on this document was initiated in response to the increased emphasis by the utilities owning nuclear power plants and nuclear industry on procurement of replacement items for use in safety related applications at nuclear power plants. 20 refs., 9 figs., 14 tabs

  6. 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

  7. 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.

  8. Catalogue and classification of technical safety rules for light-water reactors and reprocessing plants

    International Nuclear Information System (INIS)

    Bloser, M.; Fichtner, N.; Neider, R.

    1975-08-01

    This report on the cataloguing and classification of technical rules for land-based light-water reactors and reprocessing plants contains a list of classified rules. The reasons for the classification system used are given and discussed

  9. Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward

    Energy Technology Data Exchange (ETDEWEB)

    John Collins

    2009-01-01

    This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

  10. Technical evaluation of RETS-required reports for Kewaunee Nuclear Power Plant for 1983

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review of the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at the Kewaunee Nuclear Power Plant during 1983 was performed. The periodic reports reviewed were the two Semiannual Effluent Release Reports for 1983 and the annual Kewaunee Environmental Radioactivity Survey. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  11. Comparison of methods applicable to evaluation of nuclear power plant technical specifications

    International Nuclear Information System (INIS)

    Cho, N.Z.; Bozoki, G.E.; Youngblood, R.W.

    1986-01-01

    This study compares three probabilistic methods based on the static fault tree analysis, time-dependent unavailability analysis, and Markov analysis, which can be used to evaluate technical specifications in nuclear power plants. They are tested on a sample problem which was devised to closely represent the important and essential characteristics that should be addressed in determination and evaluation of the technical specifications

  12. XML: Solution for the integration of nuclear power plant data and technical documents

    International Nuclear Information System (INIS)

    Gordillo, F.

    2000-01-01

    Assuring proper operation of the systems that make up a nuclear power plant requires handling a massive amount of technical documents. This technical documentation, consisting mainly of system descriptions, operating and maintenance procedures, safety procedures, etc, presents particular characteristics, mainly: Great volume of information. High contents in figures and graphics. High reliability required. Multiple cross-references among documents. (Author)

  13. KWL Lingen nuclear plant. Technical annual report 2016; KWL Kernkraftwerk Lingen. Technischer Jahresbericht 2016

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-07-01

    The technical annual report 2016 for KWL (Lingen nuclear plant) covers the following sections: dismantling project management and operation, monitoring and clearance; waste management, technical qualification, security and safety, central tasks; licensing and supervision procedures, operational data, radiation monitoring, radioactive materials, in-service inspections.

  14. Technical safety appraisal of buildings 9206 and 9212, Oak Ridge Y-12 plant

    International Nuclear Information System (INIS)

    1989-03-01

    This report covers the results of a Safety Performance Review of the Y-12 Plant conducted during the period July 25 through August 3, 1988. A Safety Performance Review is a followup to assess changes in performance since the 1986 Technical Safety Appraisal (TSA). This review is patterned after a TSA and covered the overall safety performance at Y-12, evaluating progress to date against standards of accepted practice. The review included coverage of actions taken in response to recommendations in the TSA conducted in July--August 1986. Remaining issues were identified through an assessment of safety program deficiencies and their root causes. For each of the 14 safety-related functional areas at the Y-12 Plant, results of this review are listed in Section V. These results include a discussion, conclusions, and any new safety concerns for each program. Appendix A contains a description of the system for categorizing concerns, and the concerns are summarily tabulated in Appendix B for all programs. Appendix C describes the contractor's response and current status of each of the 59 recommendations contained in the 1986 TSA

  15. IAEA Team Reviews Safety Progress at French Nuclear Power Plant 19-23 May 2014

    International Nuclear Information System (INIS)

    2014-01-01

    An international team of nuclear installation safety experts led by the International Atomic Energy Agency (IAEA) has evaluated the Gravelines Nuclear Power Plant (NPP) in France to assess how the station has followed up on an Operational Safety Review Team (OSART) mission undertaken in 2012. The IAEA assembled a team of experts at the request of the Government of France to conduct the follow-up OSART mission at Gravelines NPP from 19 to 23 May 2014. Follow-up missions are standard components of the OSART programme; they are typically conducted 15-24 months after the initial OSART mission. The IAEA mission in 2012 made a number of recommendations and suggestions for consideration by the Gravelines NPP operators. The station thoroughly analyzed the OSART recommendations and suggestions and developed corrective action plans. In 18 months, the Gravelines plant has achieved the level ''resolved;; or ''satisfactory progress'' in almost all of the recommendations and suggestions made by the OSART in November 2012. During the follow-up mission, the team assessed that the operators have resolved the issues in several areas, including: Undertaking initiatives to improve fire prevention; Reinforcing contamination control practices; and Enhancing capabilities to protect emergency workers in the event of a release of radioactivity. The team identified some issues which have achieved satisfactory progress toward resolution, but need further work, including: Further improvement of measures to preventing the ingress of items or chemicals into circuits and equipment; Comprehensive application of the corrective actions programme; and Reinforcement of the containment protection system in the event of an extremely adverse situation. The team identified the following issue as one which has made insufficient progress toward resolution and needs further work: Emergency response arrangements do not follow current IAEA safety standards recommending that the plant should have a person on

  16. IAEA Operational Safety Team (OSART) Reviews Progress at Fessenheim Nuclear Power Plant, France

    International Nuclear Information System (INIS)

    2011-01-01

    Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has evaluated the French Nuclear Power Plant (NPP) at Fessenheim to assess how the facility has followed up on an Operational Safety Review Team (OSART) mission undertaken in 2009. The IAEA assembled a team of experts at the request of the Government of France to conduct the mission. Follow-up missions are standard components of the OSART programme and are conducted 18-24 months after the initial OSART mission. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the team performed its review from 7 to 11 February 2011. The team assessed how the Fessenheim NPP has addressed the recommendations and suggestions made during the 2009 OSART mission. The team was made up of experts from Slovakia, Switzerland and the IAEA. The review covered the areas of Management, Organization and Administration; Training and Qualifications; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry and Emergency Planning and Preparedness. The conclusions of the follow-up review are based on the IAEA's Safety Standards and proven good international practices. There were 21 issues raised by the 2009 mission. During the follow-up mission, the team assessed that six issues had been resolved, thirteen had made satisfactory progress to date and two had made insufficient progress to date. 'Resolved' describes action plans for improvement that have been fully implemented; 'satisfactory progress to date' describes action plans that have been developed but are not yet fully implemented; and 'insufficient progress to date' describes situations where additional consideration or strengthening of improvement plans is necessary. Examples of issues falling into different resolution categories include: The plant has resolved the suggestion to establish a process to review initial training materials on a regular basis

  17. 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

  18. 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.

  19. 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)

  20. Nuclear challenges and progress in designing stellarator power plants

    International Nuclear Information System (INIS)

    El-Guebaly, L.

    2007-01-01

    , such as recycling (within the nuclear industry) and clearance (or unconditional release to the commercial market). The ARIES-CS bioshield, cryostat, and individual magnet constituents qualify for clearance, representing ∼80% of the total waste volume. We developed a recycling approach for the non-clearable, in-vessel components using a combination of conventional and advanced remote handling equipment that can handle high doses of 3000 Sv/h or more. Several additional nuclear-related tasks received considerable attention during the ARIES-CS design process. These include the radial build definition, the well-optimized in-vessel components that satisfy the top-level requirements, the carefully selected nuclear and engineering parameters to produce an economic optimum, and the overarching safety constraints to deliver a safe and reliable power plant. This paper provides a brief historical overview of the progress in designing stellarator power plants and a perspective to the successful integration of the nuclear activity into the final ARIES-CS design

  1. Central Heating Plant Coal Use Handbook. Volume 1: Technical Reference.

    Science.gov (United States)

    1996-11-01

    CHUTES LIFT TRUCKS MONORAILS , TRAMWAYS J p WEIGHING, 0 MEASURING SCALES COAL METERS HOPPERS SAMPLERS 9 FIRING EQUIPMENT (Source: Power, February...Defense (DOD) installations employ coal- fired central energy plants, the U.S. Army Construction Engineering Research Laboratories (USACERL) was... fired central heat plant operations cost by improving coal quality specifications. The Handbook is tailored for military installation industrial

  2. 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

  3. [Research progress of genetic engineering on medicinal plants].

    Science.gov (United States)

    Teng, Zhong-qiu; Shen, Ye

    2015-02-01

    The application of genetic engineering technology in modern agriculture shows its outstanding role in dealing with food shortage. Traditional medicinal plant cultivation and collection have also faced with challenges, such as lack of resources, deterioration of environment, germplasm of recession and a series of problems. Genetic engineering can be used to improve the disease resistance, insect resistance, herbicides resistant ability of medicinal plant, also can improve the medicinal plant yield and increase the content of active substances in medicinal plants. Thus, the potent biotechnology can play an important role in protection and large area planting of medicinal plants. In the development of medicinal plant genetic engineering, the safety of transgenic medicinal plants should also be paid attention to. A set of scientific safety evaluation and judgment standard which is suitable for transgenic medicinal plants should be established based on the recognition of the particularity of medicinal plants.

  4. Technical Note: Methionine, a precursor of methane in living plants

    Science.gov (United States)

    Lenhart, K.; Althoff, F.; Greule, M.; Keppler, F.

    2015-03-01

    When terrestrial plants were identified as producers of the greenhouse gas methane, much discussion and debate ensued not only about their contribution to the global methane budget but also with regard to the validity of the observation itself. Although the phenomenon has now become more accepted for both living and dead plants, the mechanism of methane formation in living plants remains to be elucidated and its precursor compounds to be identified. We made use of stable isotope techniques to verify the in vivo formation of methane, and, in order to identify the carbon precursor, 13C positionally labeled organic compounds were employed. Here we show that the amino acid L-methionine acts as a methane precursor in living plants. Employing 13C-labeled methionine clearly identified the sulfur-bound methyl group of methionine as a carbon precursor of methane released from lavender (Lavandula angustifolia). Furthermore, when lavender plants were stressed physically, methane release rates and the stable carbon isotope values of the emitted methane greatly increased. Our results provide additional support that plants possess a mechanism for methane production and suggest that methionine might play an important role in the formation of methane in living plants, particularly under stress conditions.

  5. 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

  6. Technical data for concentrated solar power plants in operation, under construction and in project

    Directory of Open Access Journals (Sweden)

    Ugo Pelay

    2017-08-01

    Full Text Available This article presents technical data for concentrated solar power (CSP plants in operation, under construction and in project all over the world in the form of tables. These tables provide information about plants (e.g., name of the CSP plant, country of construction, owner of the plant, aim of the plant and their technical characteristics (e.g., CSP technology, solar power, area of the plant, presence and type of hybridization system, electricity cost, presence and type of TES, power cycle fluid, heat transfer fluid, operating temperature, operating pressure, type of turbine, type and duration of storage, etc.. Further interpretation of the data and discussions on the current state-of-the-art and future trends of CSP can be found in the associated research article (Pelay et al., 2017 [1].

  7. Recent progress in the feasibility study for the first nuclear power plant in Indonesia

    International Nuclear Information System (INIS)

    Subki, I.R.; Iskandar, A.; Supadi, S.

    1994-01-01

    In September 1989 the Indonesian Government decided to perform a Nuclear Power Plant feasibility study, including a comprehensive investigation of Muris site. This presentation reports on the progress to date in the two main components of this study: (a) the non-site studies, covering energy economics, financing, technical and safety aspects, the fuel cycle and waste management as well as general management aspects, and (b) site and environmental studies, covering field investigations, assessment of site selection, site qualification/evaluation, environmental, socio-economic and cultural impacts. The study is carried out under a comprehensive quality assurance programme developed by a consultancy company - NEWJEC Inc., which compiles with IAEA recommendations and was approved by BATAN. A summary of the main results, recommendations and general conclusions is presented. It is estimated that the total investment for the construction of 2 x 900 MWe or 3 x 600 MWe class Nuclear Power Plant units would be around US$7 to US$9 billion. 8 tabs

  8. Technical report on dc power supplies in nuclear power plants

    International Nuclear Information System (INIS)

    1977-06-01

    Emergency electrical power supplies, both a.c. and d.c. for nuclear power plants are important to safety. For this reason, the electric power systems for operating nuclear plants and those plants under licensing review have been required to provide a high degree of reliability. It is this high reliability that provides confidence that sufficient safety margin exists against loss of all d.c. power for extended periods of time to allow an orderly examination of safety issues, such as this. However, because of the importance of the a.c. and d.c. power systems, the staff has been expending effort to review the reliability of these systems and shall continue to do so in the future

  9. Solar Total Energy System, Large Scale Experiment, Shenandoah, Georgia. Final technical progress report. Volume II, Section 3. Facility concept design. [1. 72 MW thermal and 383. 6 kW electric power for 42,000 ft/sup 2/ knitwear plant

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1977-10-17

    The Stearns-Roger Engineering Company conceptual design of ERDA's Large Scale Experiment No. 2 (LSE No. 2) is presented. The various LSEs are part of ERDA's Solar Total Energy Program (STES) and a separate activity of the National Solar Thermal Power Systems Program. The object of this LSE is to design, construct, test, evaluate and operate a STES for the purpose of obtaining experience with large scale hardware systems and to establish engineering capability for subsequent demonstration projects. This particular LSE is to be located at Shenandoah, Georgia, and will provide power to the Bleyle knitwear factory. The Solar Total Energy system is sized to supply 1.720 MW thermal power and 383.6 KW electrical power. The STES is sized for the extended knitwear plant of 3902 M/sup 2/ (42,000 sq-ft) which will eventually employ 300 people. The details of studies conducted for Phase II of the Solar Total Energy System (STES) for the conceptual design requirements of the facility are presented. Included in this section are the detailed descriptions and analyses of the following subtasks: facility concept design, system concept design, performance analysis, operation plan, component and subsystem development, procurement plan, cost estimating and scheduling, and technical and management plans. (WHK)

  10. Progress and prospects for phosphoric acid fuel cell power plants

    Energy Technology Data Exchange (ETDEWEB)

    Bonville, L.J.; Scheffler, G.W.; Smith, M.J. [International Fuel Cells Corp., South Windsor, CT (United States)

    1996-12-31

    International Fuel Cells (IFC) has developed the fuel cell power plant as a new, on-site power generation source. IFC`s commercial fuel cell product is the 200-kW PC25{trademark} power plant. To date over 100 PC25 units have been manufactured. Fleet operating time is in excess of one million hours. Individual units of the initial power plant model, the PC25 A, have operated for more than 30,000 hours. The first model {open_quotes}C{close_quotes} power plant has over 10,000 hours of operation. The manufacturing, application and operation of this power plant fleet has established a firm base for design and technology development in terms of a clear understanding of the requirements for power plant reliability and durability. This fleet provides the benchmark against which power plant improvements must be measured.

  11. Technical specifications on the welding in fuel reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

    Karino, Motonobu; Uryu, Mitsuru; Matsui, N.; Nakazawa, Fumio; Imanishi, Makoto; Koizumi; Kazuhiko; Sugawara, Junichi; Tanaka, Hideo

    1999-04-01

    The past specifications SGN of the welding in JNC was reexamined for the reprocessing plants in order to further promote the quality control. The specification first concerns the quality of raw materials, items of the quality tests, material management, and qualification standards of the welders. It extends over details of the welding techniques, welding design, welding testings, inspection and the judgment standards. (H. Baba)

  12. Nuclear design and technical development required for ISER plant

    International Nuclear Information System (INIS)

    Yokoyama, Takashi; Yamano, Naoki.

    1987-01-01

    The report outlines some results of a study carried out by the ISER (intrinsically safe and economical reactor) Investigation Group. In particular, nuclear design concepts are examined in relation to the fuel cycle. Discussion is also made on technical development efforts to be made for realizing an ISER. Calculation of some basic nuclear design parameters is performed and results are used to examine the reactor core and fuel for ISER. As a result, it is indicated that a high-burnup type reactor core should be used on a 4.5-batch replacement, 15 EFPM (effective full power month) scheme to optimize an ISER. For technical development, consideration is made on various tests to be performed with an experimental reactor, called ISER-E, as well as other tests to provide basic data required for demonstrating the inherent safety of ISER. The study also deals with the possibility of the application of currently available light water reactor techniques to experiments with a critical assembly, non-nuclear test loop, and the experimental reactor ISER-E. It is revealed that many of the required experiments can be carried out by using test facilities and light water reactor techniques which are currently, or will be readily, available. It is stressed that international cooperation is necessary to accomplish these tests. (Nogami, K.)

  13. A Study on Establishment of Nuclear Power Plant Technical Support System and Activation Plan

    International Nuclear Information System (INIS)

    Wi, M. H.; Park, W. S.; Lee, H. S.; Kim, J. H.; Won, B. C.; Kim, Y. H.; Goo, D. S.; Choi, H. B.

    2009-11-01

    This report includes activities related to establishment of 'BaroBaro nuclear plant technical support center', 'selection of nuclear plant applicable technology', and 'various information interchange between KAERI and nuclear power plant'. 'BaraBaro center was newly organized to support on resolving the technical difficulties in operation of nuclear power plant'. The center consists of 10 technical parts and a leading expert is assigned to each part to support more efficiently. This center is always served for 24 hour. The plant operators can register their problem to the center by a call, e-mail, or internet and they can receive the answer about what they issued from KAERI experts. To make a brochure, we selected 32 technologies which are applicable in nuclear plant without additional R and D activity. The brochure was distributed to the officer in charge of nuclear plant operations. Various meetings were held to increase interchange of experience and technology between KAERI and nuclear power plant and we discussed many different issues at that meeting

  14. 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.)

  15. 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.

  16. 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

  17. 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.

  18. [Health & safety in a steel plant: technical and managerial action].

    Science.gov (United States)

    Fusato, M

    2012-01-01

    The report presents the experience in a steel company to improve the management of issues relating to health and safety of workers. The first part of the work focuses on the description of the interventions made by the company in recent years, which can be divided into technical interventions on production facilities, training and information, organizational activities and specific projects in collaboration with the health service. The second part presents the certification project according to OHSAS 18001, with particular focus on the efforts for a lean management of the documentation required by the management systems and for the automation of internal processes. The last part finally describes in detail the manner in which it was decided to address some issues that significantly affect the factory doctor: the recording and analysis of accidents and medications, management of hazardous substances and personal protective equipment.

  19. Technical considerations for flexible piping design in nuclear power plants

    International Nuclear Information System (INIS)

    Lu, S.C.; Chou, C.K.

    1985-01-01

    The overall objective of this research project is to develop a technical basis for flexible piping designs which will improve piping reliability and minimize the use of pipe supports, snubbers, and pipe whip restraints. The current study was conducted to establish the necessary groundwork based on the piping reliability analysis. A confirmatory piping reliability assessment indicated that removing rigid supports and snubbers tends to either improve or affect very little the piping reliability. A couple of changes to be implemented in Regulatory Guide (RG) 1.61 and RG 1.122 aimed at more flexible piping design were investigated. It was concluded that these changes substantially reduce calculated piping responses and allows piping redesigns with significant reduction in number of supports and snubbers without violating ASME code requirements

  20. Standard technical specifications General Electric plants, BWR/6. Volume 1, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/6 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  1. Standard technical specifications: General Electric plants, BWR/4. Volume 1, Revision 1: Specifications

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  2. Standard technical specifications: Combustion engineering plants. Volume 1, Revision 1: Specifications

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Combustion Engineering Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  3. One fungus, one name promotes progressive plant pathology.

    Science.gov (United States)

    Wingfield, Michael J; De Beer, Z Wilhelm; Slippers, Bernard; Wingfield, Brenda D; Groenewald, Johannes Z; Lombard, Lorenzo; Crous, Pedro W

    2012-08-01

    The robust and reliable identification of fungi underpins virtually every element of plant pathology, from disease diagnosis to studies of biology, management/control, quarantine and, even more recently, comparative genomics. Most plant diseases are caused by fungi, typically pleomorphic organisms, for which the taxonomy and, in particular, a dual nomenclature system have frustrated and confused practitioners of plant pathology. The emergence of DNA sequencing has revealed cryptic taxa and revolutionized our understanding of relationships in the fungi. The impacts on plant pathology at every level are already immense and will continue to grow rapidly as new DNA sequencing technologies continue to emerge. DNA sequence comparisons, used to resolve a dual nomenclature problem for the first time only 19 years ago, have made it possible to approach a natural classification for the fungi and to abandon the confusing dual nomenclature system. The journey to a one fungus, one name taxonomic reality has been long and arduous, but its time has come. This will inevitably have a positive impact on plant pathology, plant pathologists and future students of this hugely important discipline on which the world depends for food security and plant health in general. This contemporary review highlights the problems of a dual nomenclature, especially its impact on plant pathogenic fungi, and charts the road to a one fungus, one name system that is rapidly drawing near. © 2011 The Authors. Molecular Plant Pathology © 2011 BSPP and Blackwell Publishing Ltd.

  4. Recent progress in SG level control in French PWR plants

    International Nuclear Information System (INIS)

    Parry, A.; Petetrot, J.F.; Vivier, M.J.

    1985-10-01

    Controlling the steam generator (SG) level is of major importance in a large PWR plant. This has led to extensive work on SG computer models. This paper presents results of the comparison between calculations and tests on the first four-loop plant in France. Four-loop plants started up after 1985 will be equipped with digital instead of analog controllers. A new SG level control has been designed and then optimised using the validated SG model. A prototype of this new system has been successfully tested on a three-loop plant. 4 refs

  5. 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.

  6. Solvent refined coal (SRC) process. Quarterly technical progress report, January 1980-March 1980. [In process streams

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    This report summarizes the progress of the Solvent Refined Coal (SRC) project at the SRC Pilot Plant in Fort Lewis, Wahsington, and the Process Development Unit (P-99) in Harmarville, Pennsylvania. After the remaining runs of the slurry preheater survey test program were completed January 14, the Fort Lewis Pilot Plant was shut down to inspect Slurry Preheater B and to insulate the coil for future testing at higher rates of heat flux. Radiographic inspection of the coil showed that the welds at the pressure taps and the immersion thermowells did not meet design specifications. Slurry Preheater A was used during the first 12 days of February while weld repairs and modifications to Slurry Preheater B were completed. Two attempts to complete a material balance run on Powhatan No. 6 Mine coal were attempted but neither was successful. Slurry Preheater B was in service the remainder of the quarter. The start of a series of runs at higher heat flux was delayed because of plugging in both the slurry and the hydrogen flow metering systems. Three baseline runs and three slurry runs of the high heat flux program were completed before the plant was shut down March 12 for repair of the Inert Gas Unit. Attempts to complete a fourth slurry run at high heat flux were unsuccessful because of problems with the coal feed handling and the vortex mix systems. Process Development Unit (P-99) completed three of the four runs designed to study the effect of dissolver L/D ratio. The fourth was under way at the end of the period. SRC yield correlations have been developed that include coal properties as independent variables. A preliminary ranking of coals according to their reactivity in PDU P-99 has been made. Techniques for studying coking phenomenona are now in place.

  7. A technical system to improve the operational monitoring of the Zaporozh'ye nuclear power plant

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Schumann, P.; Seidel, A.; Weiss, F.-P.; Zschau, J.; Nowak, K.

    1997-01-01

    As part of a programme of cooperation with Central and Eastern European states, a technical system has been established for the Zaporozhe nuclear power plant, which complements existing operational checking and monitoring facilities with modern means of information technology. It makes it possible to continuously monitor the state of the units in normal operation and in cases of anomalies or incidents. The parameters selected for monitoring are listed, and the system of automatic evaluation at the power plant site is described in detail. Test operation of the technical system started in late 1995 and the industrial testing phase in mid-1996. (A.K.)

  8. Development of standard technical report on using and selecting wireless device in nuclear power plants

    International Nuclear Information System (INIS)

    Koo, I. S.; Hong, S. B.; Cho, J. W.

    2011-11-01

    1. Purpose · Development of IEC technical report on wireless device using in nuclear power plants 2. Contents · IEC technical reports of draft for circulation and final draft for next planary meeting · Case study on experiment of wireless devices 3. Implementation methods · Preparation of first draft with experts group, its circulation, discussions on the results of the circulation · Organizing three teams such as preparation, reviews and experiment 4. Results · Maintenance cost will be reduced with application of the wireless technologies in nuclear power plants · Commercial wireless devices will be developed before standard is issued

  9. Improved technical specifications and related improvements to safety in commercial Nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C. [EXCEL Services Corporation, 11921 Rockville Pike, Suite 100, Rockville, MD 20852 (United States)]. e-mail: donaldh@excelservices.com

    2004-07-01

    Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

  10. Improved technical specifications and related improvements to safety in commercial Nuclear power plants

    International Nuclear Information System (INIS)

    Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C.

    2004-01-01

    Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

  11. One fungus, one name promotes progressive plant pathology

    NARCIS (Netherlands)

    Wingfield, M.J.; De Beer, Z.W.; Slippers, B.; Wingfield, B.D.; Groenewald, J.Z.; Lombard, L.; Crous, P.W.

    2011-01-01

    The robust and reliable identification of fungi underpins virtually every element of plant pathology, from disease diagnosis to studies of biology, management/control, quarantine and, even more recently, comparative genomics. Most plant diseases are caused by fungi, typically pleomorphic organisms,

  12. One fungus, one name promotes progressive plant pathology

    NARCIS (Netherlands)

    Wingfield, M.J.; Beer, de Z.W.; Slippers, B.; Wingfield, B.D.; Groenewald, J.Z.; Lombard, L.; Crous, P.W.

    2012-01-01

    The robust and reliable identification of fungi underpins virtually every element of plant pathology, from disease diagnosis to studies of biology, management/control, quarantine and, even more recently, comparative genomics. Most plant diseases are caused by fungi, typically pleomorphic organisms,

  13. Remote repair and inspection technics in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Koyama, Kenji; Ishibashi, Yuzo; Otani, Yosikuni

    1986-01-01

    Tokai reprocessing plant of Power Reactor and Nuclear Fuel Development Corp. is the only factory in Japan which treats 0.7 t/day of the spent fuel from LWR power stations and recovers remaining uranium and newly produced plutonium. Since the reprocessing plant started the hot test in September, 1977, about eight years have elapsed, and 233 t of spent fuel was treated as of August, 1985. During this period, the development of various remote working techniques have been carried out to cope with the failure of equipment and to strengthen the preventive maintenance of equipment. In this report, the development of the techniques for the remote repair of leaking dissolving tanks and the development of the remote inspection system for confirming the soundness of equipment in cells are described. In nuclear facilities, from the viewpoint of the reduction of radiation exposure accompanying the works under high radiation, labor saving, the increase of capacity factor by shortening the period of repair works, the improvement of safety and reliability of the facilities by perfecting checkup and inspection and so on, it is strongly desired to put robots in practical use for maintenance and inspection. (Kako, I.)

  14. Pulverized coal firing of aluminum melting furnaces. First annual technical progress report, May 1978-June 1979

    Energy Technology Data Exchange (ETDEWEB)

    West, C.E.; Hines, J.E.; Stewart, D.L. Jr.; Yu, H.

    1979-10-01

    The ultimate objective of this program is the commercial demonstration of an efficient, environmentally acceptable coal firing process suitable for implementation on melting furnaces throughout the aluminum industry. To achieve this goal, the program has been divided into two phases. Phase I has begun with the design and construction of a 350 lb/h (coal) staged slagging cyclone combustor (SSCC) attached to a 7-ft dia aluminum melting ladle furnace. Process development will culminate with a 1000 pph prototype SSCC firing a 40,000 lb capacity open hearth melting furnace at the Alcoa Laboratories. Phase II implementation is currently planned for Alcoa's Lafayette, IN, Works, where two of the ingot plant's five open hearth melting furnaces will be converted to utilize coal. In addition to confirmation of data gathered in Phase I, the effect of extended production schedule operation on equipment and efficiencies will be determined. This work would begin in 1982 pursuant to technical and economic evaluation of the process development at that time. A major design subcontract for assistance in the design of the SSCC is 80% completed.

  15. On the technical superiority of domestic power plant equipment and its development

    International Nuclear Information System (INIS)

    Zhao Zhiyi

    1993-01-01

    Under the Presumption of affirmed superiority of domestic power plant equipment, some existing deficiencies are pointed out. The scientific and technical development of domestic power equipment can be impelled through catching up with advanced technologies. The necessity of optimal matching of plant equipment from the engineering point of view is emphasized by the authors in association with a prospective outlook of key power equipment and development suggestions

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

    International Nuclear Information System (INIS)

    2000-01-01

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

  17. Technical aspects of coupling a 6300 m3/day MSF-RO desalination plant to a PHWR nuclear power plant

    International Nuclear Information System (INIS)

    Verma, R.K.

    1998-01-01

    Presently, eight pressurised Heavy Water Reactors (PHWRs) each of 235 MWe capacity are operational in India. Four more units of similar capacity are expected to be commissioned soon. Work on two units each of 500 MWe capacity is also initiated. Extensive engineering development work has also been carried out in India, both on the MSF process and the membrane process. Based on the experience obtained from the presently operating 425 m 3 /d MSF plant and from the R and D work on the RO process, a 6300 m 3 /d MSF-RO plant (4500 m 3 /d MSF and 1800 m 3 /d RO) has been designed and the work for setting up this plant is undertaken. The steam for the heating duty in the brine heater as well as the steam for the evacuation purpose for the MSF plant is proposed to be obtained from the nuclear plant steam cycle. Sea water feed for the MSF plant as well as for the RO plant will be derived from the sea water discharge system of the nuclear power plant. Provision is made for supply of electrical power also from the power plant. The details of the heating steam supply circuit starting from the steam tapping point on the nuclear plant side to the MSF plant brine heater inlet and the arrangement for the return of condensate to the nuclear plant has been described with component requirement and various technical considerations. All the liquid streams and the steam supplied from the nuclear plant to the desalination plant as well as the product water will be monitored to ensure that there is no radioactive contamination. (author)

  18. Technical safety appraisal: Buildings 776/777 Rocky Flats Plant

    Energy Technology Data Exchange (ETDEWEB)

    Field, H C

    1988-03-01

    Buildings 776/777 at the Rocky Flats Plant are major components of the production complex at the plant site. They have been in operation since 1957. The operations taking place in the buildings are nuclear weapons production support, processing of weapons assemblies returned from Pantex, waste processing, research and development in support of production, special projects, and those generated by support groups, such as maintenance. The appraisal team identified nine deficiencies that it believed required prompt attention. DOE management for EH, the program office (Defense Programs), and the field office analyzed the information provided by the appraisal team and instituted compensatory measures for closer monitoring of contractor activities by knowledgeable DOE staff and staff from other sites. Concurrently, the contractor was requested to address both short-term and long-term remedial measures to correct the identified issues as well as the underlying problems. The contractor has provided his action plan, which is included. This plan was under evaluation by EH and the DOE program office at the time this report was prepared. In addressing the major areas of concern identified above, a well as the specific deficiencies identified by the appraisal team, the contractor and the field office are cautioned to search for the root causes for the problems and to direct corrective actions to those root causes rather than solely to the symptoms to assure the sustainability of the improvements being made. The results of prior TSAs led DOE to conclude that previous corrective actions were not sufficient in that a large number of the individual findings are recurrent. Pending completion of remedial actions over the next few months, enhanced DOE oversight of the contractor is warranted.

  19. Next Generation Nuclear Plant Methods Technical Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-12-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  20. Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498

    Energy Technology Data Exchange (ETDEWEB)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-09-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  1. Technical safety appraisal: Buildings 776/777 Rocky Flats Plant

    International Nuclear Information System (INIS)

    Field, H.C.

    1988-03-01

    Buildings 776/777 at the Rocky Flats Plant are major components of the production complex at the plant site. They have been in operation since 1957. The operations taking place in the buildings are nuclear weapons production support, processing of weapons assemblies returned from Pantex, waste processing, research and development in support of production, special projects, and those generated by support groups, such as maintenance. The appraisal team identified nine deficiencies that it believed required prompt attention. DOE management for EH, the program office (Defense Programs), and the field office analyzed the information provided by the appraisal team and instituted compensatory measures for closer monitoring of contractor activities by knowledgeable DOE staff and staff from other sites. Concurrently, the contractor was requested to address both short-term and long-term remedial measures to correct the identified issues as well as the underlying problems. The contractor has provided his action plan, which is included. This plan was under evaluation by EH and the DOE program office at the time this report was prepared. In addressing the major areas of concern identified above, a well as the specific deficiencies identified by the appraisal team, the contractor and the field office are cautioned to search for the root causes for the problems and to direct corrective actions to those root causes rather than solely to the symptoms to assure the sustainability of the improvements being made. The results of prior TSAs led DOE to conclude that previous corrective actions were not sufficient in that a large number of the individual findings are recurrent. Pending completion of remedial actions over the next few months, enhanced DOE oversight of the contractor is warranted

  2. ``Recycling'' Nuclear Power Plant Waste: Technical Difficulties and Proliferation Concerns

    Science.gov (United States)

    Lyman, Edwin

    2007-04-01

    One of the most vexing problems associated with nuclear energy is the inability to find a technically and politically viable solution for the disposal of long-lived radioactive waste. The U.S. plan to develop a geologic repository for spent nuclear fuel at Yucca Mountain in Nevada is in jeopardy, as a result of managerial incompetence, political opposition and regulatory standards that may be impossible to meet. As a result, there is growing interest in technologies that are claimed to have the potential to drastically reduce the amount of waste that would require geologic burial and the length of time that the waste would require containment. A scenario for such a vision was presented in the December 2005 Scientific American. While details differ, these technologies share a common approach: they require chemical processing of spent fuel to extract plutonium and other long-lived actinide elements, which would then be ``recycled'' into fresh fuel for advanced reactors and ``transmuted'' into shorter-lived fission products. Such a scheme is the basis for the ``Global Nuclear Energy Partnership,'' a major program unveiled by the Department of Energy (DOE) in early 2006. This concept is not new, but has been studied for decades. Major obstacles include fundamental safety issues, engineering feasibility and cost. Perhaps the most important consideration in the post-9/11 era is that these technologies involve the separation of plutonium and other nuclear weapon-usable materials from highly radioactive fission products, providing opportunities for terrorists seeking to obtain nuclear weapons. While DOE claims that it will only utilize processes that do not produce ``separated plutonium,'' it has offered no evidence that such technologies would effectively deter theft. It is doubtful that DOE's scheme can be implemented without an unacceptable increase in the risk of nuclear terrorism.

  3. Standard technical specifications, Westinghouse Plants: Bases (Sections 3.4--3.9). Volume 3, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

  4. Standard technical specifications, Westinghouse Plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

  5. Risk-based analysis methods applied to nuclear power plant technical specifications

    International Nuclear Information System (INIS)

    Wagner, D.P.; Minton, L.A.; Gaertner, J.P.

    1989-01-01

    A computer-aided methodology and practical applications of risk-based evaluation of technical specifications are described. The methodology, developed for use by the utility industry, is a part of the overall process of improving nuclear power plant technical specifications. The SOCRATES computer program uses the results of a probabilistic risk assessment or a system-level risk analysis to calculate changes in risk due to changes in the surveillance test interval and/or the allowed outage time stated in the technical specification. The computer program can accommodate various testing strategies (such as staggered or simultaneous testing) to allow modeling of component testing as it is carried out at the plant. The methods and computer program are an integral part of a larger decision process aimed at determining benefits from technical specification changes. These benefits can include cost savings to the utilities by reducing forced shutdowns and decreasing labor requirements for test and maintenance activities, with no adverse impacts on risk. The methodology and the SOCRATES computer program have been used extensively toe valuate several actual technical specifications in case studies demonstrating the methods. Summaries of these applications demonstrate the types of results achieved and the usefulness of the risk-based evaluation in improving the technical specifications

  6. Technical Description Lillgrund Wind Power Plant. Lillgrund Pilot Project

    Energy Technology Data Exchange (ETDEWEB)

    Jeppsson, Joakim; Larsen, Poul Erik; Larsson, Aake [Vattenfall Vindkraft AB, Stockholm (Sweden)

    2008-09-15

    Lillgrund offshore wind power plant comprises 48 wind turbines, each rated at 2.3 MW, bringing the total wind farm capacity to 110 MW. The Lillgrund offshore wind power plant is located in a shallow area of Oeresund, 7 km off the coast of Sweden and 7 km south from the Oeresund Bridge connecting Sweden and Denmark. An average wind speed of around 8,5 m/s at hub height, combined with a relatively low water depth of 4 to 8 meters makes it economically feasible to build here. Vattenfall Vindkraft AB is the owner and operator of Lillgrund offshore wind power plant. Lillgrund is a Swedish pilot project supported by the Swedish Energy Agency. The bidding process was completed during 2005 and the offshore power plant was constructed in the period 2006 to 2007. The wind farm was constructed on time and has now been successfully operational since December 2007. There is, however, always potential for improvement and the aim of this report has been to determine and highlight these areas. It is worth noting out that only the electrical system and the foundations are tailor made at offshore wind power plants. The wind turbines are more or less standard products with none or very limited possibilities for project specific design changes. Geotechnical investigations are expensive and it can be difficult to balance the risks as well as the benefits of this expense in the early phases of a large infrastructure project. As a whole, the geotechnical surveys at Lillgrund proved to be useful. They identified potential issues, such as the fact that extra excavation was required for two of the foundations. It also revealed the location of a small number of boulders that would have to be removed. Vattenfall requested a complete study of the electrical system for Lillgrund to be delivered with the bids. That request was not met. Instead Siemens Wind Power began a complete electrical system study after being awarded the Contract. The electrical system study was completed during the

  7. Implications of power uprates on safety margins of nuclear power plants. Report of a technical meeting

    International Nuclear Information System (INIS)

    2004-09-01

    The safety of nuclear power plants (NPPs) is based on the defence in depth concept, which relies on successive physical barriers (fuel matrix, cladding, primary system pressure boundary and containment) and other provisions to control radioactive materials and on multiple levels of protection against damage to these barriers. Deterministic safety analysis is an important tool for conforming the adequacy and efficiency of provisions within the defence in depth concept and is used to predict the response of an NPP in predetermined operational states. This type of safety analysis applies a specific set of rules and specific acceptance criteria. Deterministic analysis is typically focused on neutronic, thermohydraulic, radiological and structural aspects, which are often analysed with different computational tools. The advanced computational tools developed for deterministic safety analysis are used for better establishment and utilization of licensing margins or safety margins in consideration of analysis results. At the same time, the existence of such margins ensures that NPPs operate safely in all modes of operation and at all times. To properly assess and address the existing margins and to be able to take advantage of unnecessary conservatisms, state of the art analytical tools intended for safety assessment have been developed. Progress made in the development and application of modern codes for safety analysis and better understanding of phenomena involved in plant design and operation enable the analysts to determine safety margins in consideration of analysis results (licensing margins) with higher precision. There is a general tendency for utilities to take advantage of unnecessarily large conservatisms in safety analyses and to utilize them for reactor power uprates, better utilization of nuclear fuel, higher operational flexibility and for justification of lifetime extension. The present publication sets forth the results of a Technical Meeting on the

  8. Technical evaluation of the proposed changes in the technical specifications for emergency power sources for the Big Rock Point nuclear power plant

    International Nuclear Information System (INIS)

    Latorre, V.R.

    1979-12-01

    The technical evaluation is presented for the proposed changes to the Technical Specifications for emergency power sources for the Big Rock Point nuclear power plant. The criteria used to evaluate the acceptability of the changes include those delineated in IEEE Std-308-1974, and IEEE Std-450-1975 as endorsed by US NRC Regulatory Guide 1.129

  9. Power systems development facility. Quarterly technical progress report, July 1--September 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    This quarterly technical progress report summarizes work completed during the Second Quarter of the Second Budget Period, July 1 through September 30, 1993, under the Department of Energy (DOE) Cooperative Agreement No. DE-FC21-90MC25140 entitled ``Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion.`` The objective of this project is to evaluate hot gas particle 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 scaleup of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the existing Transport Reactor gas source and Hot Gas Cleanup Units: Carbonizer/Pressurized Circulating Fluidized Bed Gas Source. Hot Gas Cleanup Units to mate to all gas streams; Combustion Gas Turbine; and Fuel Cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF). The major emphasis during this reporting period was continuing the detailed design of the facility.

  10. 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.

  11. Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

    Science.gov (United States)

    Selwitz, Jason Lawrence

    2017-01-01

    Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum…

  12. Technical and institutional safety features of nuclear power plants in Brazil

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1986-01-01

    This work reports technical, political and institutional safety features of nuclear power plants in Brazil. It is mainly concerned with reactor accidents and personnel safety. The three mile Island and Chernobyl accidents are also discussed and taken as examples. (A.C.A.S.)

  13. Technical and regulatory challenges for digital instrumentation and control and control room systems in nuclear plants

    International Nuclear Information System (INIS)

    Torok, R.; Naser, J.; Harris, T.; Keithline, K.

    2006-01-01

    There are several unsettled technical and licensing issues in the areas of instrumentation and control (I and C), human factors, and updated control room designs that need coordinated, proactive industry attention. Some of these issues are already causing protracted regulatory reviews for existing plants, and left untreated, may cause substantial delays and increased costs for new plant combined construction and operating license approvals. Both industry and the NRC will have roles in resolving the key issues and addressing them in future design efforts and regulatory reviews. Where action is needed, the industry will want to minimize costs and risks by defining industry consensus solutions with corresponding technical bases. NEI has formed a working group to coordinate industry efforts and communications with NRC staff. The working group will also help determine priorities and coordinate both new and existing plant resources. EPRI will provide technical input and guidance for the working group. In order to be able to conduct reviews in a timely fashion, the NRC will likely need to enhance and expand staff resources as existing plants are upgraded and new plant reviews become more active. The industry initiative began with a workshop sponsored by EPRI and NEI on March 28-29, 2006, which led to the creation of the NEI working group. The working group has now identified and prioritized important generic issues, established resolution paths and schedules, and identified the roles of various stakeholders including utility companies, EPRI, NEI, vendors and the NRC. Through the course of this initiative I and C issues for both existing and new plants are being addressed. This paper describes the key I and C related technical and regulatory issues and their implications for new and operating plants, and provides a status report on the efforts to resolve them. (authors)

  14. Variations of Histone Modification Patterns: Contributions of Inter-plant Variability and Technical Factors

    Directory of Open Access Journals (Sweden)

    Sylva Brabencová

    2017-12-01

    Full Text Available Inter-individual variability of conspecific plants is governed by differences in their genetically determined growth and development traits, environmental conditions, and adaptive responses under epigenetic control involving histone post-translational modifications. The apparent variability in histone modifications among plants might be increased by technical variation introduced in sample processing during epigenetic analyses. Thus, to detect true variations in epigenetic histone patterns associated with given factors, the basal variability among samples that is not associated with them must be estimated. To improve knowledge of relative contribution of biological and technical variation, mass spectrometry was used to examine histone modification patterns (acetylation and methylation among Arabidopsis thaliana plants of ecotypes Columbia 0 (Col-0 and Wassilewskija (Ws homogenized by two techniques (grinding in a cryomill or with a mortar and pestle. We found little difference in histone modification profiles between the ecotypes. However, in comparison of the biological and technical components of variability, we found consistently higher inter-individual variability in histone mark levels among Ws plants than among Col-0 plants (grown from seeds collected either from single plants or sets of plants. Thus, more replicates of Ws would be needed for rigorous analysis of epigenetic marks. Regarding technical variability, the cryomill introduced detectably more heterogeneity in the data than the mortar and pestle treatment, but mass spectrometric analyses had minor apparent effects. Our study shows that it is essential to consider inter-sample variance and estimate suitable numbers of biological replicates for statistical analysis for each studied organism when investigating changes in epigenetic histone profiles.

  15. Variations of Histone Modification Patterns: Contributions of Inter-plant Variability and Technical Factors.

    Science.gov (United States)

    Brabencová, Sylva; Ihnatová, Ivana; Potěšil, David; Fojtová, Miloslava; Fajkus, Jiří; Zdráhal, Zbyněk; Lochmanová, Gabriela

    2017-01-01

    Inter-individual variability of conspecific plants is governed by differences in their genetically determined growth and development traits, environmental conditions, and adaptive responses under epigenetic control involving histone post-translational modifications. The apparent variability in histone modifications among plants might be increased by technical variation introduced in sample processing during epigenetic analyses. Thus, to detect true variations in epigenetic histone patterns associated with given factors, the basal variability among samples that is not associated with them must be estimated. To improve knowledge of relative contribution of biological and technical variation, mass spectrometry was used to examine histone modification patterns (acetylation and methylation) among Arabidopsis thaliana plants of ecotypes Columbia 0 (Col-0) and Wassilewskija (Ws) homogenized by two techniques (grinding in a cryomill or with a mortar and pestle). We found little difference in histone modification profiles between the ecotypes. However, in comparison of the biological and technical components of variability, we found consistently higher inter-individual variability in histone mark levels among Ws plants than among Col-0 plants (grown from seeds collected either from single plants or sets of plants). Thus, more replicates of Ws would be needed for rigorous analysis of epigenetic marks. Regarding technical variability, the cryomill introduced detectably more heterogeneity in the data than the mortar and pestle treatment, but mass spectrometric analyses had minor apparent effects. Our study shows that it is essential to consider inter-sample variance and estimate suitable numbers of biological replicates for statistical analysis for each studied organism when investigating changes in epigenetic histone profiles.

  16. Investigative study on the technical code requirements of natural events hazards for nuclear power plants

    International Nuclear Information System (INIS)

    Ito, Kunio; Aoki, Takayuki

    2012-01-01

    Technical codes and standards on natural phenomena, in particular, earthquake and tsunami for nuclear power plants in the other developed countries including IAEA safety standards were investigated. Then, the results were compared with the corresponding Japanese technical codes and standards. As a results, it was found that: (1) technical codes and standards on natural phenomena, especially those for earthquakes and tsunami/flooding in those foreign countries and their requirements are all included in the Japanese technical codes and standards. (2) Nevertheless, the actual measures against tsunami/flooding in those foreign countries are more advanced than those in Japan which had been taken before Fukushima accident. Therefore, further investigation is needed to clarify the reason why there are such differences by investigating the details of the basic ideas and evaluation methods for the protection of tsunami/flooding. (author)

  17. Review. Elimination of viruses in plants: twenty years of progress

    Directory of Open Access Journals (Sweden)

    A. Panattoni

    2013-02-01

    Full Text Available To shed light on trends about elimination of viruses from plants, a bibliographic research was conducted to identify thermotherapy, chemotherapy and tissue culture trials published from 1991 through 2010. Among woody plants, grapevine, apple and peach are the most frequent targets of sanitation protocols because their health status is strictly regulated. Even if thermotherapy represents the preferred method for the host, grapevine viruses can also be eliminated with chemotherapy and tissue culture; apple viruses respond to chemotherapy as well. Although a similar trend was reported among herbaceous plants, chemotherapy was the most frequently used technique in potato. With regard to virus, thermotherapy was successfully applied against viruses belonging to 13 families and an unassigned genus. Instead, chemotherapy and tissue culture techniques eradicated viruses belonging to fewer families (nine. An interpretation of thermotherapy effects considers the new metabolic “pathways” triggered by the natural antiviral response emitted by the infected plant, with particular reference to virus-induced gene silencing. With regard to chemotherapy, several groups of antiviral drugs belong to inosine monophosphate dehydrogenase inhibitors, S-adenosylhomocysteine hydrolase inhibitors, neuraminidase inhibitors. Tissue culture, usually adopted to regenerate plantlets in biotechnological breeding programs, represents the less used tool for eliminate viruses from plants.

  18. Progress and challenges for abiotic stress proteomics of crop plants.

    Science.gov (United States)

    Barkla, Bronwyn J; Vera-Estrella, Rosario; Pantoja, Omar

    2013-06-01

    Plants are continually challenged to recognize and respond to adverse changes in their environment to avoid detrimental effects on growth and development. Understanding the mechanisms that crop plants employ to resist and tolerate abiotic stress is of considerable interest for designing agriculture breeding strategies to ensure sustainable productivity. The application of proteomics technologies to advance our knowledge in crop plant abiotic stress tolerance has increased dramatically in the past few years as evidenced by the large amount of publications in this area. This is attributed to advances in various technology platforms associated with MS-based techniques as well as the accessibility of proteomics units to a wider plant research community. This review summarizes the work which has been reported for major crop plants and evaluates the findings in context of the approaches that are widely employed with the aim to encourage broadening the strategies used to increase coverage of the proteome. © 2013 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  19. Advanced converter technology. Technical progress report, May 23, 1979-May 22, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Banic, C. V.; Eckhouse, S. A.; Kornbrust, F. J.; Lipman, K.; Peterson, J. L.; Rosati, R. W.

    1980-01-01

    The overall objective of this program is to define an advanced converter system employing 1980's technology in all subsystem and component areas for use in electrochemical energy storage systems. Additional experimental effort will validate elements of the advanced commutation circuitry on a full-scale breadboard basis. Improved models of battery electrical characteristics are beng defined and experimental apparatus is being designed to measure these characteristics and to enable better definition of the battery-power conditioner interface. Improvement of energy-storage system performance through modification of battery converter characteristics will also be investigated. During this first year of the contract, a new more advanced concept for power conditioning based on a concept defined by United Technologies Corporation for fuel cell use was evaluated. This high switching frequency concept has the potential for significantly reducing the size and cost of battery plant power conditioners. As a result, the Department of Energy authorized redirection of the program to first evaluate this new concept and then to reorient the program to adopt this concept as the primary one. Progress is reported. (WHK)

  20. Technical and economic aspects of nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Glauberman, H.; Manion, W.J.

    1977-01-01

    Nuclear power plants may be decommissioned by one of three primary methods - mothballing, entombing, or dismantling, or by using combinations such as mothballing or entombing for a period of time followed by dismantling. Mothballing or entombing both result in an end-product which requires surveillance and maintenance for a significant period to ensure protection of public health and safety. This paper discusses costs for each of the decommissioning methods, including factors that will influence the method selected as well as the total costs. Decommissioning costs have been estimated for an 1100-MW(e) light-water reactor within one year after shutdown following forty years of operation. The basic economic parameters for each decommissioning method were developed using unit cost factors based on known costs of previously decommissioned reactors. Decommissioning cost estimates range from less than four million dollars for mothballing to about forty million dollars for complete dismantling. Estimated cost of entombment is about ten million dollars. Subsequent annual cost of surveillance and maintenance for a reactor facility using the mothballing or entombment method could be as high as US $200,000. Although some tooling development will be needed for removing highly activated reactor vessel segments and internals, technology is currently available and has been demonstrated on prior decommissionings, e.g. the BONUS and HALLUM reactor entombments and the Elk River Reactor complete dismantling. Costs associated with decommissioning are significant; however, allowance for them either as a one-time construction period sinking fund, or annual depreciation type operating allowance, will have little effect on construction or on operating costs. (author)

  1. Technical and economic aspects of nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Glauberman, H.; Manion, W.J.

    1977-01-01

    Nuclear power plants may be decommissioned by one of three primary methods, namely, mothballing, entombing, or dismantling or by using combinations such as mothballing or entombing for a period of time followed by dismantling. Mothballing or entombing both result in an end-product which require surveillance and maintenance for a significant period of time to ensure protection of public health and safety. This paper discusses costs for each of the decommissioning methods, including factors that will influence the method selected as well as the total costs. Decommissioning costs have been estimated for a 1100 MW(e) light water reactor within one year after shutdown following forty years of operation. The basic economic parameters for each decommissioning method were developed using unit cost factors based on known costs of previously decommissioned reactors. Decommissioning cost estimates range from less than four million dollars for mothballing to about forty million dollars for complete dismantling. Estimated cost of entombment is about ten million dollars. Subsequent annual cost of surveillance and maintenance for a reactor facility using the mothballing or entombment method could be as high as $200,000. Although some tooling development will be needed for the removal of the highly activated reactor vessel segments and internals, technology is currently available and has been demonstrated on prior decommissionings, e.g., the BONUS and HALLUM reactor entombments and the Elk River Reactor complete dismantling. Costs associated with decommissioning are significant; however, allowance for them either as a one-time construction period sinking fund or annual depreciation type operating allowance will have little impact on either construction or operating costs

  2. Environmental Impact Report from Santa Rita Hydroelectric Power Plant (Minas Gerais State - Brazil): technical strategic for its elaboration

    International Nuclear Information System (INIS)

    Souza, J.A. de; Marques Neto, F.P.

    1989-01-01

    The steps for developing the technical strategies used on the elaboration of Environmental Impact Report from Santa Rita Hydroelectric Power Plant, Minas Gerais State, are described, including the influence area, technical requirements, impact identification, technical selection of mitigative measures, impact meaning and strategy for evaluating the identified impacts. (C.G.C.)

  3. Contributions of plant breeding in Brazil – progress and perspectives

    Directory of Open Access Journals (Sweden)

    Magno Antonio Patto Ramalho

    2012-12-01

    Full Text Available Agribusiness is fundamental for the Brazilian economy. This has become possible due to the use of science and technology in agriculture in the last 35 years. Among the technologies, the use of improved cultivars stands out. This article presents the situation of the species grown in the country in recent years and the contribution of genetic plant breeding to the performance of these species. Challenges multiplied because of populational growth associated with the ever-growing concern of society with the environment. Breeders of the present and future must base plant selection in the field on new technologies so that it is possible to meet demand.

  4. Approaches to the safety of future nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-09-01

    The Technical Committee Meeting on Approaches to Safety of Future Nuclear Power Plants in Different Countries, held from 29 May to 2 June 1995, contributed to this process. Experts from 14 different countries and two international organizations participated in the meeting, which provided the opportunity to exchange information and to review the answers developed to date to these issues (primarily form the IAEA's technical document ''Development of Safety Principles for the Design of Future Nuclear Power Plants'' IAEA-TECDOC-801) and the report of the International Nuclear Safety Advisory Group ''Basic Safety Principles for Nuclear Power Plants'' (INSAG-3). These references were then used as a starting point for answering the question ''to what degree does general agreement (or harmonization) exist on these desired safety approaches for future reactors, and what opportunities remain for further harmonization? 11 refs, 1 tab

  5. Cycle water chemistry based on film forming amines at power plants: evaluation of technical guidance documents

    Science.gov (United States)

    Dyachenko, F. V.; Petrova, T. I.

    2017-11-01

    Efficiency and reliability of the equipment in fossil power plants as well as in combined cycle power plants depend on the corrosion processes and deposit formation in steam/water circuit. In order to decrease these processes different water chemistries are used. Today the great attention is being attracted to the application of film forming amines and film forming amine products. The International Association for the Properties of Water and Steam (IAPWS) consolidated the information from all over the World, and based on the research studies and operating experience of researchers and engineers from 21 countries, developed and authorized the Technical Guidance Document: “Application of Film Forming Amines in Fossil, Combined Cycle, and Biomass Power Plants” in 2016. This article describe Russian and International technical guidance documents for the cycle water chemistries based on film forming amines at fossil and combined cycle power plants.

  6. 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

  7. Progressive building methods in nuclear power plant construction

    International Nuclear Information System (INIS)

    Sikura, V.

    1980-01-01

    A detailed description is given of the new prospective technologies used in the construction of the Bohunice V-1 nuclear power plant. They include the use of steel and large-area forms, the use of profile sheets as a substitute for forms, assembled raw partitions, wall shells consisting of clamped porous concrete slabs, assembled roof shells, special finish of concrete walls, bearing wall deep foundation, the use of modern building machinery for concreting, reinforcing and welding works. (M.S.)

  8. Contributions of plant breeding in Brazil: progress and perspectives

    OpenAIRE

    Ramalho, Magno Antonio Patto; Dias, Luiz Antônio dos Santos; Carvalho, Bruna Line

    2012-01-01

    Agribusiness is fundamental for the Brazilian economy. This has become possible due to the use of science and technology in agriculture in the last 35 years. Among the technologies, the use of improved cultivars stands out. This article presents the situation of the species grown in the country in recent years and the contribution of genetic plant breeding to the performance of these species. Challenges multiplied because of populational growth associated with the ever-growing concern of soci...

  9. Plant invasion science in protected areas: progress and priorities

    Czech Academy of Sciences Publication Activity Database

    Foxcroft, L. C.; Pyšek, Petr; Richardson, D. M.; Genovesi, P.; MacFadyen, S.

    2017-01-01

    Roč. 19, č. 5 (2017), s. 1353-1378 ISSN 1387-3547 R&D Projects: GA ČR GB14-36079G Grant - others:AV ČR(CZ) AP1002 Program:Akademická prémie - Praemium Academiae Institutional support: RVO:67985939 Keywords : plant invasions * global patterns * protected areas Subject RIV: EH - Ecology, Behaviour OBOR OECD: Biodiversity conservation Impact factor: 2.473, year: 2016

  10. Establishment of the technical basis to apply the viscous damper in nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Nakajima, J.; Suezono, N.; Higuchi, T. [Toshiba Corp., Isogo Nuclear Engineering Center, Isogo-ku, Yokohama (Japan); Katayama, H. [Toshiba Corp., Power and Industrial Systems Research and Development Center, Isogo-ku, Yokohama (Japan)

    2014-07-01

    In recent years, the technical development of the damper using viscous fluid (hereinafter called 'the viscous damper') for the structures, bridges and components in the general industrial field is remarkable, and the experiences of the application to mitigate influence in an earthquake is being gathered now. In this paper, purpose of the whole activity, schedule, the research and test results carried out so far, and future plan to establish the technical basis to apply the viscous damper in nuclear power plant are reported. (author)

  11. Establishment of the technical basis to apply the viscous damper in nuclear power plant

    International Nuclear Information System (INIS)

    Nakajima, J.; Suezono, N.; Higuchi, T.; Katayama, H.

    2014-01-01

    In recent years, the technical development of the damper using viscous fluid (hereinafter called 'the viscous damper') for the structures, bridges and components in the general industrial field is remarkable, and the experiences of the application to mitigate influence in an earthquake is being gathered now. In this paper, purpose of the whole activity, schedule, the research and test results carried out so far, and future plan to establish the technical basis to apply the viscous damper in nuclear power plant are reported. (author)

  12. Risk based optimization of technical specifications for operation of nuclear power plants

    International Nuclear Information System (INIS)

    1993-12-01

    The objective of the report is to present an overview of the risk and reliability based approaches (using a probabilistic safety assessment (PSA)) for improving nuclear power plant technical specifications (TS). In that case, it will provide an information base to the Member States in seeking PSA based applications to enhance the effectiveness of their technical specifications. To achieve this objective, the report discusses the basic objectives and reasons for seeking TS changes, the methods, data requirements and uses of different types of applications, and an overview of different applications that have been completed, including detailed descriptions of selected applications. Refs, figs and tabs

  13. Technical requirements on knowledge base and instrumentation system for decision making in plant operation and maintenance

    International Nuclear Information System (INIS)

    Kitamura, Masaharu; Yoshikawa, Shinji; Hasegawa, Makoto

    1998-03-01

    A series of technical surveys and studies are described in this report to examine and identify technical requirements to be posed on knowledge base and instrumentation system as the fundamental in high reliability computational decision making in operation and maintenance of nuclear power plants. Monitoring and diagnosis are focused as the important tasks among the operation/maintenance-related tasks. A concrete monitoring and diagnosis system configuration has been proposed consisting of distributed symptom database and of on-demand measurement subsystem. An prototype of the proposed system configuration has been successfully verified. (author)

  14. 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

  15. LMFBR flexible pipe joint development program. Annual technical progress report, government fiscal year 1977

    International Nuclear Information System (INIS)

    1978-01-01

    Currently, the ASME Boiler and Pressure Vessel Code does not allow the use of flexible pipe joints (bellows) in Section III, Class 1 reactor primary piping systems. Studies have shown that the primary piping loops of LMFBR's could be simplified by using these joints. This simplification translates directly into shorter primary piping runs and reduced costs for the primary piping system. Further cost savings result through reduced vault sizes and reduced containment building diameter. In addition, the use of flexible joints localizes the motions from thermally-induced piping growth into components which are specifically designed to accommodate this motion. This reduces the stress levels in the piping system and its components. It is thus economically and structurally important that flexible piping joints be available to the LMFBR designer. The overall objective of the Flexible Joint Program is to provide this availability. This will be accomplished through the development of ASME rules which allow the appropriate use of such joints in Section III, Class 1 piping systems and through the development and demonstration of construction methods which satisfy these rules. The rule development includes analytic and testing methodology formulations which will be supported by subscale bellows testing. The construction development and demonstration encompass the design, fabrication, and in-sodium testing of prototypical LMFBR plant-size flexible pipe joints which meet all ASME rule requirements. The satisfactory completion of these developmental goals will result in an approved flexible pipe joint design for the LMFBR. Progress is summarized in the following efforts undertaken during 1977 to accomplish these goals: (1) code case support, (2) engineering and design, (3) material development, (4) testing, and (5) manufacturing development

  16. Improved Management of the Technical Interfaces Between the Hanford Tank Farm Operator and the Hanford Waste Treatment Plant - 13383

    Energy Technology Data Exchange (ETDEWEB)

    Duncan, Garth M. [Bechtel National Inc., 2435 Stevens Center Place, Richland, Washington, 99352 (United States); Saunders, Scott A. [Washington River Protection Solutions, P.O. Box 850, Richland, Washington, 99352 (United States)

    2013-07-01

    The Department of Energy (DOE) is constructing the Waste Treatment and Immobilization Plant (WTP) at the Hanford site in Washington to treat and immobilize approximately 114 million gallons of high level radioactive waste (after all retrievals are accomplished). In order for the WTP to be designed and operated successfully, close coordination between the WTP engineering, procurement, and construction contractor, Bechtel National, Inc. and the tank farms operating contractor (TOC), Washington River Protection Solutions, LLC, is necessary. To develop optimal solutions for DOE and for the treatment of the waste, it is important to deal with the fact that two different prime contractors, with somewhat differing contracts, are tasked with retrieving and delivering the waste and for treating and immobilizing that waste. The WTP and the TOC have over the years cooperated to manage the technical interface. To manage what is becoming a much more complicated interface as the WTP design progresses and new technical issues have been identified, an organizational change was made by WTP and TOC in November of 2011. This organizational change created a co-located integrated project team (IPT) to deal with mutual and interface issues. The Technical Organization within the One System IPT includes employees from both TOC and WTP. This team has worked on a variety of technical issues of mutual interest and concern. Technical issues currently being addressed include: - The waste acceptance criteria; - Waste feed delivery and the associated data quality objectives (DQO); - Evaluation of the effects of performing a riser cut on a single shell tank on WTP operations; - The disposition of secondary waste from both TOC and WTP; - The close coordination of the TOC double shell tank mixing and sampling program and the Large Scale Integrated Test (LSIT) program for pulse jet mixers at WTP along with the associated responses to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation

  17. Improved Management of the Technical Interfaces Between the Hanford Tank Farm Operator and the Hanford Waste Treatment Plant - 13383

    International Nuclear Information System (INIS)

    Duncan, Garth M.; Saunders, Scott A.

    2013-01-01

    The Department of Energy (DOE) is constructing the Waste Treatment and Immobilization Plant (WTP) at the Hanford site in Washington to treat and immobilize approximately 114 million gallons of high level radioactive waste (after all retrievals are accomplished). In order for the WTP to be designed and operated successfully, close coordination between the WTP engineering, procurement, and construction contractor, Bechtel National, Inc. and the tank farms operating contractor (TOC), Washington River Protection Solutions, LLC, is necessary. To develop optimal solutions for DOE and for the treatment of the waste, it is important to deal with the fact that two different prime contractors, with somewhat differing contracts, are tasked with retrieving and delivering the waste and for treating and immobilizing that waste. The WTP and the TOC have over the years cooperated to manage the technical interface. To manage what is becoming a much more complicated interface as the WTP design progresses and new technical issues have been identified, an organizational change was made by WTP and TOC in November of 2011. This organizational change created a co-located integrated project team (IPT) to deal with mutual and interface issues. The Technical Organization within the One System IPT includes employees from both TOC and WTP. This team has worked on a variety of technical issues of mutual interest and concern. Technical issues currently being addressed include: - The waste acceptance criteria; - Waste feed delivery and the associated data quality objectives (DQO); - Evaluation of the effects of performing a riser cut on a single shell tank on WTP operations; - The disposition of secondary waste from both TOC and WTP; - The close coordination of the TOC double shell tank mixing and sampling program and the Large Scale Integrated Test (LSIT) program for pulse jet mixers at WTP along with the associated responses to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation

  18. Technical Feasibility Study of Thermal Energy Storage Integration into the Conventional Power Plant Cycle

    Directory of Open Access Journals (Sweden)

    Jacek D. Wojcik

    2017-02-01

    Full Text Available The current load balance in the grid is managed mainly through peaking fossil-fuelled power plants that respond passively to the load changes. Intermittency, which comes from renewable energy sources, imposes additional requirements for even more flexible and faster responses from conventional power plants. A major challenge is to keep conventional generation running closest to the design condition with higher load factors and to avoid switching off periods if possible. Thermal energy storage (TES integration into the power plant process cycle is considered as a possible solution for this issue. In this article, a technical feasibility study of TES integration into a 375-MW subcritical oil-fired conventional power plant is presented. Retrofitting is considered in order to avoid major changes in the power plant process cycle. The concept is tested based on the complete power plant model implemented in the ProTRAX software environment. Steam and water parameters are assessed for different TES integration scenarios as a function of the plant load level. The best candidate points for heat extraction in the TES charging and discharging processes are evaluated. The results demonstrate that the integration of TES with power plant cycle is feasible and provide a provisional guidance for the design of the TES system that will result in the minimal influence on the power plant cycle.

  19. Progress in Decommissioning the Humboldt Bay Power Plant - 13604

    Energy Technology Data Exchange (ETDEWEB)

    Rod, Kerry [PG and E Utility, Humboldt Bay Power Plant, 1000 King Salmon Ave. Eureka, CA 95503 (United States); Shelanskey, Steven K. [Anata Management Solutions, 5180 South Commerce Dr,, Suite F Murray, UT 84107 (United States); Kristofzski, John [CH2MHILL, 295 Bradley Blvd. Suite 300, Richland WA 99353 (United States)

    2013-07-01

    Decommissioning of the Pacific Gas and Electric (PG and E) Company Humboldt Bay Power Plant (HBPP) Unit 3 nuclear facility has now, after more than three decades of SAFSTOR and initial decommissioning work, transitioned to full-scale decommissioning. Decommissioning activities to date have been well orchestrated and executed in spite of an extremely small work site with space constricted even more by other concurrent on-site major construction projects including the demolition of four fossil units, construction of a new generating station and 60 KV switchyard upgrade. Full-scale decommissioning activities - now transitioning from Plant Systems Removal (PG and E self-perform) to Civil Works Projects (contractor performed) - are proceeding in a safe, timely, and cost effective manner. As a result of the successful decommissioning work to date (approximately fifty percent completed) and the intense planning and preparations for the remaining work, there is a high level of confidence for completion of all HBPP Unit 3 decommissions activities in 2018. Strategic planning and preparations to transition into full-scale decommissioning was carried out in 2008 by a small, highly focused project team. This planning was conducted concurrent with other critical planning requirements such as the loading of spent nuclear fuel into dry storage at the Independent Spent Fuel Storage Installation (ISFSI) finishing December 2008. Over the past four years, 2009 through 2012, the majority of decommissioning work has been installation of site infrastructure and removal of systems and components, known as the Plant System Removal Phase, where work scope was dynamic with significant uncertainty, and it was self-performed by PG and E. As HBPP Decommissioning transitions from the Plant System Removal Phase to the Civil Works Projects Phase, where work scope is well defined, a contracting plan similar to that used for Fossil Decommissioning will be implemented. Award of five major work scopes

  20. Progress in Decommissioning the Humboldt Bay Power Plant - 13604

    International Nuclear Information System (INIS)

    Rod, Kerry; Shelanskey, Steven K.; Kristofzski, John

    2013-01-01

    Decommissioning of the Pacific Gas and Electric (PG and E) Company Humboldt Bay Power Plant (HBPP) Unit 3 nuclear facility has now, after more than three decades of SAFSTOR and initial decommissioning work, transitioned to full-scale decommissioning. Decommissioning activities to date have been well orchestrated and executed in spite of an extremely small work site with space constricted even more by other concurrent on-site major construction projects including the demolition of four fossil units, construction of a new generating station and 60 KV switchyard upgrade. Full-scale decommissioning activities - now transitioning from Plant Systems Removal (PG and E self-perform) to Civil Works Projects (contractor performed) - are proceeding in a safe, timely, and cost effective manner. As a result of the successful decommissioning work to date (approximately fifty percent completed) and the intense planning and preparations for the remaining work, there is a high level of confidence for completion of all HBPP Unit 3 decommissions activities in 2018. Strategic planning and preparations to transition into full-scale decommissioning was carried out in 2008 by a small, highly focused project team. This planning was conducted concurrent with other critical planning requirements such as the loading of spent nuclear fuel into dry storage at the Independent Spent Fuel Storage Installation (ISFSI) finishing December 2008. Over the past four years, 2009 through 2012, the majority of decommissioning work has been installation of site infrastructure and removal of systems and components, known as the Plant System Removal Phase, where work scope was dynamic with significant uncertainty, and it was self-performed by PG and E. As HBPP Decommissioning transitions from the Plant System Removal Phase to the Civil Works Projects Phase, where work scope is well defined, a contracting plan similar to that used for Fossil Decommissioning will be implemented. Award of five major work scopes

  1. 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...

  2. Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Bradley, E.W.; Wu, C.F.; Goff, T.E.

    1993-01-01

    The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report

  3. Standard technical specifications combustion engineering plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/6 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes

  4. Control of heavy loads at nuclear power plants: Resolution of Generic Technical Activity A-36. Technical report

    International Nuclear Information System (INIS)

    George, H.J.

    1980-07-01

    This report summarizes work performed by the NRC staff in the resolution of Generic Technical Activity A-36, Control of Heavy Loads Near Spent Fuel. Generic Technical Activity A-36 is one of the generic technical subjects designated as unresolved safety issues pursuant to Section 210 of the Energy Reorganization Act of 1974. The report describes the technical studies and evaluations performed by the NRC staff, the staff's guidelines based on these studies, and the staff's plans for implementaton of its technical guidelines

  5. Technical dictionary power plant engineering. Vol. 1. 4. rev. and enlarged ed.

    International Nuclear Information System (INIS)

    1987-01-01

    This dictionary is a compilation of German and English technical terms of power plant engineering as far as power plants, turbine-generators and assembly engineering are concerned. It is the result of a joint effort by the Kraftwerk Union AG (KWU) and Utility Power Corp. (UPC). The entire content has been revised and approx. 6000 new terms have been added. The dictionary is meant to form a basis for uniform terminology on technical documents as well as correspondence between KWU, UPC and licensees. This computer aided dictionary is printed in capital/low case letters. Only nouns, terms with an article and proper names are capitalized in German. Some terms are written differently in American and British English and are marked with (US) or (GB). (orig./HP) [de

  6. Recent progress in plant nutrition research: cross-talk between nutrients, plant physiology and soil microorganisms.

    Science.gov (United States)

    Ohkama-Ohtsu, Naoko; Wasaki, Jun

    2010-08-01

    Mineral nutrients taken up from the soil become incorporated into a variety of important compounds with structural and physiological roles in plants. We summarize how plant nutrients are linked to many metabolic pathways, plant hormones and other biological processes. We also focus on nutrient uptake, describing plant-microbe interactions, plant exudates, root architecture, transporters and their applications. Plants need to survive in soils with mineral concentrations that vary widely. Describing the relationships between nutrients and biological processes will enable us to understand the molecular basis for signaling, physiological damage and responses to mineral stresses.

  7. Nuclear power plant shift technical advisor. Recommendations for position description, qualifications, education and training

    International Nuclear Information System (INIS)

    1981-01-01

    The purpose of this document is to describe the position and identify specific areas of formal education, plant-specific training and experience necessary to assure an advanced level of analytical ability on shift. These recommendations will provide a level of technical ability that is essential to improved operational safety and are consistent with regulatory requirements. This position was developed in conjunction with representatives of utilities, equipment vendors and engineering educators, giving consideration to specific contributions the function must make to shift operations

  8. Technical specifications review of nuclear power plants: a risk-informed evaluation

    International Nuclear Information System (INIS)

    Saldanha, Pedro Luiz da Cruz; Sousa, Anna Leticia; Frutuoso e Melo, Paulo Fernando Ferreira; Duarte, Juliana Pacheco

    2012-01-01

    The use of risk information by a regulatory body as part of an integrated decision making process addresses the way in which risk information is being used as part of an integrated process in making decisions about safety issues at nuclear plants – commonly referred to as risk-informed decision making. The risk-informed approach aims to integrate in a systematic manner quantitative and qualitative, deterministic and probabilistic safety considerations to obtain a balanced decision. Probabilistic Safety Assessment (PSA) is a methodology that can be applied to provide a structured analysis process to evaluate the frequency and consequences of accidents scenarios in nuclear power plants. Technical Specifications (TS) are specifications regarding the characteristics of nuclear power plants (variables, systems or components) of overriding importance to nuclear safety and radiation protection, which is an integral part of plant operation authorization. Limiting Conditions of Operation (LCO) are the minimum levels of performance or capacity or operating system components required for the safe operation of nuclear plants, as defined in technical specifications. The Maintenance Rule (MR) is a requirement established by the U. S. Nuclear Regulatory Commission (NRC) to check the effectiveness of maintenance carried out in nuclear plants, and plant configuration control. The control of plant configuration is necessary to verify the impact of the maintenance of a safety device out of service on plant safety. The Electric Power Research Institute (EPRI) has assessed the role of probabilistic safety analysis in the regulation of nuclear power plants with the following objectives: a) to provide utilities with an approach for developing and implementing nuclear power station risk-managed technical specification programs; and b) to complement and supplement existing successful configuration risk management applications such as MR. This paper focuses on the evaluation of EPRI

  9. 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.

  10. Savannah River Ecology Laboratory, Annual Technical Progress Report of Ecological Research, June 30, 2002

    Energy Technology Data Exchange (ETDEWEB)

    Paul M. Bertsch, (Director)

    2002-06-30

    The Savannah River Ecology Laboratory (SREL) is a research unit of The University of Georgia (UGA) and has been conducting ecological research on the Savannah River Site (SRS) near Aiken, South Carolina for 50 years. The overall mission of the Laboratory is to acquire and communicate knowledge of ecological processes and principles. SREL conducts fundamental and applied ecological research, as well as education and outreach programs, under a Cooperative Agreement with the U.S. Department of Energy (DOE). The Laboratory's research mission during the 2002 fiscal year was fulfilled with the publication of 76 journal articles and book chapters by faculty, technical staff, students, and visiting scientists. An additional 50 journal articles have been submitted or are in press. Other noteworthy events took place as faculty members, staff, and graduate students received awards. These are described in the section titled Special Accomplishments of Faculty, Staff, Students, and Administration on page 51. Notable scientific accomplishments include work conducted on contaminant transport, stable isotopes, sandhills ecology, and phytoremediation: (1) A collaborative study between Dr. Tom Hinton at SREL and scientists at SRTC demonstrated the feasibility of using illite clay to sequester 137Cs in sediments along the P and R reactor cooling canal system, where approximately 3,000 acres of land are contaminated. Overall, the study showed significant decreases in cesium concentrations and bioavailability following the addition of illite with no sign of harm to the ecosystem. While the cesium remains sequestered from the biosphere, its radioactivity decays and the process progresses from contaminant immobilization to remediation. (2) SREL's stable isotope laboratory is now fully functional. Stable isotope distributions in nature can provide important insights into many historical and current environmental processes. Dr. Christopher Romanek is leading SREL's research

  11. High-Efficiency Nitride-Based Solid-State Lighting. Final Technical Progress Report

    International Nuclear Information System (INIS)

    Paul T. Fini; Shuji Nakamura

    2005-01-01

    In this final technical progress report we summarize research accomplished during Department of Energy contract DE-FC26-01NT41203, entitled ''High-Efficiency Nitride-Based Solid-State Lighting''. Two teams, from the University of California at Santa Barbara (Principle Investigator: Dr. Shuji Nakamura) and the Lighting Research Center at Rensselaer Polytechnic Institute (led by Dr. N. Narendran), pursued the goals of this contract from thin film growth, characterization, and packaging/luminaire design standpoints. The UCSB team initially pursued the development of blue gallium nitride (GaN)-based vertical-cavity surface-emitting lasers, as well as ultraviolet GaN-based light emitting diodes (LEDs). In Year 2, the emphasis shifted to resonant-cavity light emitting diodes, also known as micro-cavity LEDs when extremely thin device cavities are fabricated. These devices have very directional emission and higher light extraction efficiency than conventional LEDs. Via the optimization of thin-film growth and refinement of device processing, we decreased the total cavity thickness to less than 1 (micro)m, such that micro-cavity effects were clearly observed and a light extraction efficiency of over 10% was reached. We also began the development of photonic crystals for increased light extraction, in particular for so-called ''guided modes'' which would otherwise propagate laterally in the device and be re-absorbed. Finally, we pursued the growth of smooth, high-quality nonpolar a-plane and m-plane GaN films, as well as blue light emitting diodes on these novel films. Initial nonpolar LEDs showed the expected behavior of negligible peak wavelength shift with increasing drive current. M-plane LEDs in particular show promise, as unpackaged devices had unsaturated optical output power of ∼ 3 mW at 200 mA drive current. The LRC's tasks were aimed at developing the subcomponents necessary for packaging UCSB's light emitting diodes, and packaging them to produce a white light

  12. Savannah River Ecology Laboratory, Annual Technical Progress Report of Ecological Research, June 30, 2002

    International Nuclear Information System (INIS)

    Paul M. Bertsch,

    2002-01-01

    The Savannah River Ecology Laboratory (SREL) is a research unit of The University of Georgia (UGA) and has been conducting ecological research on the Savannah River Site (SRS) near Aiken, South Carolina for 50 years. The overall mission of the Laboratory is to acquire and communicate knowledge of ecological processes and principles. SREL conducts fundamental and applied ecological research, as well as education and outreach programs, under a Cooperative Agreement with the U.S. Department of Energy (DOE). The Laboratory's research mission during the 2002 fiscal year was fulfilled with the publication of 76 journal articles and book chapters by faculty, technical staff, students, and visiting scientists. An additional 50 journal articles have been submitted or are in press. Other noteworthy events took place as faculty members, staff, and graduate students received awards. These are described in the section titled Special Accomplishments of Faculty, Staff, Students, and Administration on page 51. Notable scientific accomplishments include work conducted on contaminant transport, stable isotopes, sandhills ecology, and phytoremediation: (1) A collaborative study between Dr. Tom Hinton at SREL and scientists at SRTC demonstrated the feasibility of using illite clay to sequester 137Cs in sediments along the P and R reactor cooling canal system, where approximately 3, 000 acres of land are contaminated. Overall, the study showed significant decreases in cesium concentrations and bioavailability following the addition of illite with no sign of harm to the ecosystem. While the cesium remains sequestered from the biosphere, its radioactivity decays and the process progresses from contaminant immobilization to remediation. (2) SREL's stable isotope laboratory is now fully functional. Stable isotope distributions in nature can provide important insights into many historical and current environmental processes. Dr. Christopher Romanek is leading SREL's research in this area

  13. A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Beyer, M; Carl, H; Nowak, K [Technischer Ueberwachungsverein Rheinland, Koeln (Germany). Inst. for Nuclear Engineering and Radiation Protection; Schumann, P; Seidel, A; Weiss, F P; Zschau, J

    1998-10-01

    As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

  14. A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Nowak, K.; Schumann, P.; Seidel, A.; Weiss, F.P.; Zschau, J.

    1998-01-01

    As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

  15. Recent Progress on Data-Based Optimization for Mineral Processing Plants

    Directory of Open Access Journals (Sweden)

    Jinliang Ding

    2017-04-01

    Full Text Available In the globalized market environment, increasingly significant economic and environmental factors within complex industrial plants impose importance on the optimization of global production indices; such optimization includes improvements in production efficiency, product quality, and yield, along with reductions of energy and resource usage. This paper briefly overviews recent progress in data-driven hybrid intelligence optimization methods and technologies in improving the performance of global production indices in mineral processing. First, we provide the problem description. Next, we summarize recent progress in data-based optimization for mineral processing plants. This optimization consists of four layers: optimization of the target values for monthly global production indices, optimization of the target values for daily global production indices, optimization of the target values for operational indices, and automation systems for unit processes. We briefly overview recent progress in each of the different layers. Finally, we point out opportunities for future works in data-based optimization for mineral processing plants.

  16. Advanced Power Ultra-Uprates of Existing Plants (APPU) Final Scientific/Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Rubiolo, Pablo R. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Conway, Lawarence E. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Oriani, Luca [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Lahoda, Edward J. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; DeSilva, Greg [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Hu, Min H. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Hartz, Josh [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Bachrach, Uriel [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Smith, Larry [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Dudek, Daniel F. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Toman, Gary J. [Electric Power Research Inst. (EPRI), Palo Alto, CA (United States); Feng, Dandong [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Hejzlar, Pavel [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Kazimi, Mujid S. [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

    2006-03-31

    This project assessed the feasibility of a Power Ultra-Uprate on an existing nuclear plant. The study determined the technical and design limitations of the current components, both inside and outside the containment. Based on the identified plant bottlenecks, the design changes for major pieces of equipment required to meet the Power Ultra-Uprate throughput were determined. Costs for modified pieces of equipment and for change-out and disposal of the replaced equipment were evaluated. These costs were then used to develop capital, fuel and operating and maintenance cost estimates for the Power Ultra-Uprate plant. The cost evaluation indicates that the largest cost components are the replacement of power (during the outage required for the uprate) and the new fuel loading. Based on these results, the study concluded that, for a standard 4-loop plant, the proposed Power Ultra-Uprate is technically feasible. However, the power uprate is likely to be more expensive than the cost (per Kw electric installed) of a new plant when large capacity uprates are considered (>25%). Nevertheless, the concept of the Power Ultra-Uprate may be an attractive option for specific nuclear power plants where a large margin exists in the steam and power conversion system or where medium power increases (~600 MWe) are needed. The results of the study suggest that development efforts on fuel technologies for current nuclear power plants should be oriented towards improving the fuel performance (fretting-wear, corrosion, uranium load, manufacturing, safety) required to achieve higher burnup rather focusing on potential increases in the fuel thermal output.

  17. Advanced Power Ultra-Uprates of Existing Plants (APPU) Final Scientific/Technical Report

    International Nuclear Information System (INIS)

    Rubiolo, Pablo R.; Conway, Lawarence E.; Oriani, Luca; Lahoda, Edward J.; DeSilva, Greg; Hu, Min H.; Hartz, Josh; Bachrach, Uriel; Smith, Larry; Dudek, Daniel F.; Toman, Gary J.; Feng, Dandong; Hejzlar, Pavel; Kazimi, Mujid S.

    2006-01-01

    This project assessed the feasibility of a Power Ultra-Uprate on an existing nuclear plant. The study determined the technical and design limitations of the current components, both inside and outside the containment. Based on the identified plant bottlenecks, the design changes for major pieces of equipment required to meet the Power Ultra-Uprate throughput were determined. Costs for modified pieces of equipment and for change-out and disposal of the replaced equipment were evaluated. These costs were then used to develop capital, fuel and operating and maintenance cost estimates for the Power Ultra-Uprate plant. The cost evaluation indicates that the largest cost components are the replacement of power (during the outage required for the uprate) and the new fuel loading. Based on these results, the study concluded that, for a ''standard'' 4-loop plant, the proposed Power Ultra-Uprate is technically feasible. However, the power uprate is likely to be more expensive than the cost (per Kw electric installed) of a new plant when large capacity uprates are considered (>25%). Nevertheless, the concept of the Power Ultra-Uprate may be an attractive option for specific nuclear power plants where a large margin exists in the steam and power conversion system or where medium power increases (∼600 MWe) are needed. The results of the study suggest that development efforts on fuel technologies for current nuclear power plants should be oriented towards improving the fuel performance (fretting-wear, corrosion, uranium load, manufacturing, safety) required to achieve higher burnup rather focusing on potential increases in the fuel thermal output

  18. Conceptual design of small-sized HTGR system (4). Plant design and technical feasibility

    International Nuclear Information System (INIS)

    Ohashi, Hirofumi; Sato, Hiroyuki; Yan, Xing L.; Sumita, Junya; Nomoto, Yasunobu; Tazawa, Yujiro; Noguchi, Hiroki; Imai, Yoshiyuki; Tachibana, Yukio

    2013-09-01

    Japan Atomic Energy Agency (JAEA) has started a conceptual design of a 50MWt small-sized high temperature gas cooled reactor (HTGR) for steam supply and electricity generation (HTR50S), which is a first-of-kind of the commercial plant or a demonstration plant of a small-sized HTGR system for steam supply to the industries and district heating and electricity generation by a steam turbine, to deploy in developing countries in the 2020s. HTR50S was designed for steam supply and electricity generation by the steam turbine with the reactor outlet temperature of 750degC as a reference plant configuration. On the other hand, the intermediate heat exchanger (IHX) will be installed in the primary loop to demonstrate the electricity generation by the helium gas turbine and hydrogen production by thermochemical water splitting by utilizing the secondary helium loop with the reactor outlet temperature of 900degC as a future plant configuration. The plant design of HTR50S for the steam supply and electricity generation was performed based on the plant specification and the requirements for each system taking into account for the increase of the reactor outlet coolant temperature from 750degC to 900degC and the installation of IHX. The technical feasibility of HTR50S was confirmed because the designed systems (i.e., reactor internal components, reactor pressure vessel, vessel cooling system, shutdown cooling system, steam generator (SG), gas circulator, SG isolation and drainage system, reactor containment vessel, steam turbine and heat supply system) satisfies the design requirements. The conceptual plant layout was also determined. This paper provides the summary of the plan design and technical feasibility of HTR50S. (author)

  19. Theoretical particle physics. Technical progress report, May 1, 1985-April 30, 1986

    International Nuclear Information System (INIS)

    Gottlieb, S.A.; Hendry, A.W.; Kostelecky, V.A.; Lichtenberg, D.B.

    1986-05-01

    Research activities during this past year included theoretical work in lattice gauge theory, EMC effect, supersymmetry and supergravity, weak interactions including CP violation, and superstrings. Progress in all these areas is reported

  20. Symbol manipulation by computer applied to plasma physics. Technical progress report 2

    International Nuclear Information System (INIS)

    Rosen, B.

    1977-09-01

    Progress has been made in automating the calculation of parametric processes analytically by computer. The computations are performed automatically to lowest order quickly and efficiently. Work has started on a method for solving the nonlinear differential equations describing interacting modes

  1. University of Florida, University research program in robotics. Annual technical progress report

    International Nuclear Information System (INIS)

    Crane, C.D. III; Tulenko, J.S.

    1994-05-01

    Progress is reported in the areas of environmental hardening, database, world modeling, vision, man-machine interface, advanced liquid metal reactor inspection robot, and articulated transporter/manipulator system (ATMS) development

  2. 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.

  3. Research in elementary particle physics. Technical progress report, June 1, 1983-May 31, 1984

    International Nuclear Information System (INIS)

    Kirsch, L.E.; Schnitzer, H.J.; Bensinger, J.R.; Abbott, L.F.

    1984-01-01

    Under this contract, research has been performed on both the theoretical and experimental properties of elementary particles. A brief description of the work which is either in progress or has been completed is given. Publications are listed

  4. Research in elementary particle physics: Technical progress report, June 1, 1987-May 31, 1988

    International Nuclear Information System (INIS)

    Kirsch, L.E.; Schnitzer, H.J.; Abbott, L.F.; Bensinger, J.R.; Blocker, C.A.

    1988-01-01

    The main topics discussed in the progress report: electron/photon algorithm groups; W and Z analysis; heavy quark analysis; gas gain monitoring; database upgrade; CDF test beam studies; string theory; cosmology; and neutral networks

  5. University of Florida, University research program in robotics. Annual technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    Crane, C.D. III; Tulenko, J.S.

    1994-05-01

    Progress is reported in the areas of environmental hardening, database, world modeling, vision, man-machine interface, advanced liquid metal reactor inspection robot, and articulated transporter/manipulator system (ATMS) development.

  6. Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

    International Nuclear Information System (INIS)

    Groom, S.H.

    1994-01-01

    The workshop which was intended to present operating experiences from utilities with a wide range of numbers of operating nuclear units. The speaker, S.H. Groom, presented N.B. Power's experience with a single nuclear unit, and intended to: Present the objectives, organization, and scope of work of the central and site Technical Service groups within N.B. Power which support the operation of the Point Lepreau NGS; Define responsibilities of, and interfaces between the on-site and the central technical service staff; Recommend methods for the establishment and maintenance of an efficient technical support group for the operation of any nuclear power plant

  7. Technical analysis of advanced wastewater-treatment systems for coal-gasification plants

    Energy Technology Data Exchange (ETDEWEB)

    1981-03-31

    This analysis of advanced wastewater treatment systems for coal gasification plants highlights the three coal gasification demonstration plants proposed by the US Department of Energy: The Memphis Light, Gas and Water Division Industrial Fuel Gas Demonstration Plant, the Illinois Coal Gasification Group Pipeline Gas Demonstration Plant, and the CONOCO Pipeline Gas Demonstration Plant. Technical risks exist for coal gasification wastewater treatment systems, in general, and for the three DOE demonstration plants (as designed), in particular, because of key data gaps. The quantities and compositions of coal gasification wastewaters are not well known; the treatability of coal gasification wastewaters by various technologies has not been adequately studied; the dynamic interactions of sequential wastewater treatment processes and upstream wastewater sources has not been tested at demonstration scale. This report identifies key data gaps and recommends that demonstration-size and commercial-size plants be used for coal gasification wastewater treatment data base development. While certain advanced treatment technologies can benefit from additional bench-scale studies, bench-scale and pilot plant scale operations are not representative of commercial-size facility operation. It is recommended that coal gasification demonstration plants, and other commercial-size facilities that generate similar wastewaters, be used to test advanced wastewater treatment technologies during operation by using sidestreams or collected wastewater samples in addition to the plant's own primary treatment system. Advanced wastewater treatment processes are needed to degrade refractory organics and to concentrate and remove dissolved solids to allow for wastewater reuse. Further study of reverse osmosis, evaporation, electrodialysis, ozonation, activated carbon, and ultrafiltration should take place at bench-scale.

  8. Technical basis for the internal dosimetry program at the Y-12 Plant

    International Nuclear Information System (INIS)

    Ashley, J.C.; Barber, J.M.; Snapp, L.M.; Turner, J.E.

    1992-01-01

    Since the beginning of plant operations. almost all work with radioactive materials has involved isotopes associated with uranium, enriched or depleted in U 235 . While limited quantities of isotopes of elements other than uranium are present, workplace monitoring and precess knowledge have established that internal exposure from these other isotopes is insignificant in comparison with uranium. While the changing plant mission may necessitate the consideration of internal exposure from other isotopes at some point in time, only enriched and depleted uranium will be considered in this basis document. The portions of the internal dosimetry technical basis which may be unique to the Y-12 Plant is considered in this manual. This manual presents the technical basis of the routine in vivo and in vitro bioassay programs including choice of frequency, participant selection criteria, and action level guidelines. Protocols for special bioassay will be presented in the chapters which described the basis for intake, uptake, and dam assessment. A discussion of the factors which led to the need to develop a special biokinetic model for uranium at the Y-12 Plant, as well as a description of the model's basic parameters, are included in this document

  9. 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

  10. Atmospheric Effects of Nuclear Energy Centers (AENEC) Program. Annual technical progress report, July 1975--September 1976

    International Nuclear Information System (INIS)

    Patrinos, A.A.; Hoffman, H.W.

    1977-04-01

    The Technical Memorandum contains information of a preliminary nature from the six participants of the Program describing their activities and presenting the results obtained during the reporting period. The birth of the Program, its definition and evolution are described, and a complete breakdown of responsibilities and tasks assigned to the six AENEC participants is presented

  11. The Michigan high-level radioactive waste program: Final technical progress report

    International Nuclear Information System (INIS)

    1987-01-01

    This report comprises the state of Michigan's final technical report on the location of a proposed high-level radioactive waste disposal site. Included are a list of Michigan's efforts to review the DOE proposal and a detailed report on the application of geographic information systems analysis techniques to the review process

  12. Developing Technical Writing Skills in the Physical Chemistry Laboratory: A Progressive Approach Employing Peer Review

    Science.gov (United States)

    Gragson, Derek E.; Hagen, John P.

    2010-01-01

    Writing formal "journal-style" lab reports is often one of the requirements chemistry and biochemistry students encounter in the physical chemistry laboratory. Helping students improve their technical writing skills is the primary reason this type of writing is a requirement in the physical chemistry laboratory. Developing these skills is an…

  13. 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)

  14. Nuclear heat generating plants - technical concepts and market potentials. Chapter 11

    International Nuclear Information System (INIS)

    Hasenkopf, O.; Erhard, W.D.; Nonnenmacher, A.; Hanselmann, M.

    1988-01-01

    Within the framework of a case study under the Federal Ministry of Research and Technology project 'Nuclear heat generating plants - technological concepts and market potentials', the possible applications of such plants were studied giving the district heat supply network of the Technische Werke der Stadt Stuttgart AG (Technical Works of the City of Stuttgart, Inc.) as an example. The use of district heating systems concentrated specifically on areas identified for economical supply because of their topographical position, existing heat density, distance from power plants, and a reasonable delimination from the available gas network. Based on the results of optimization calculations made by the Stuttgart Institute for Nuclear Technology and Energy Conversion, the required investment capital can be estimated as a function of the amount of fuel savings under the Stuttgart case study. (orig./UA) [de

  15. 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

  16. Technical progress report of biological research on the Volcanic Island Surtsey and its environs for the period 1965--1978

    Energy Technology Data Exchange (ETDEWEB)

    Fridriksson, S.

    1978-01-01

    Progress is reported on the following research projects: changes in shoreline and surface of the island due to volcanic activity; colonization of microorganisms, algae, lichens, and vascular plants; introduction of insects and other arthropods by wind, water, and man; transport of invertebrates to the island by flotsam of the sea; species and nesting habits of birds on the island; behavior of seals on beaches of the island; and future trends of Surtsey ecosystems. (HLW)

  17. Method for assessment of the technical potential of the plant agricultural waste suitable for energy purposes in Bulgaria

    International Nuclear Information System (INIS)

    Georgiev, V.

    2004-01-01

    A method for assessment of technical potential of quantitatively important plant agriculture waste; straw from wheat and barley; corn stalks; sunflower stalks and heads; tobacco stalks; orchard prunings and vineyard prunings suitable for energy purposes for Bulgarian conditions is developed. Data for assessment of the technical potential for 2002 using this method are presented. A comparison between technical potential of mentioned wastes, final energy consumption in agriculture and all branches of Bulgarian economy for 2002 is made. (author)

  18. Results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal

    International Nuclear Information System (INIS)

    Galkin, A.V.; Baldov, A.N.

    2001-01-01

    In the paper the results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal are presented. Ground for the examination conducting was Health of Nation Programme ratified by the President and a number of Governmental decisions. The special plant is planned in the Mangystau Region. In the framework of feasibility study the data base by the worldwide known technologies was implemented, on reprocessing and experience of radioactive waste disposal. The technical requirements for the special plant construction are determined. The alternative options by structure content and site location of the special plant and radioactive waste disposal are cited

  19. Technical evaluation of RETS-required reports for the Edwin I. Hatch Nuclear Plant, Units 1 and 2

    International Nuclear Information System (INIS)

    Young, T.E.; Magleby, E.H.

    1985-01-01

    A review of the reports required by federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed for the Edwin I. Hatch Nuclear Plant were the Annual Radiological Environmental Operating Report for 1983 and the Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant's specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines. 7 refs

  20. Gas-Cooled Thermal Reactor Program. Semiannual technical progress report, April 1, 1983-September 30, 1983

    International Nuclear Information System (INIS)

    1983-12-01

    An assessment of the HTGR opportunities from the year 2000 through 2045 was the principal activity on the Market Definition Task (WBS 03). Within the Plant Technology (WBS 13) task, there were activities to develop analytical methods for investigation of Coolant Transport Behavior and to define methods and criteria for High Temperature Structural Engineering design. The activities in support of the HTGR-SC/C Lead Plant (WBS 30 and 31) were the participation in the Lead Plant System Engineering (LPSE) effort and the plant simulation task. The efforts on the Advanced HTGR systems was performed under the Modular Reactor Systems (MRS) (WBS 41) to study the potential for multiple small reactors to provide lower costs, improved safety, and higher availability than the large monolithic core reactors

  1. Gas-Cooled Thermal Reactor Program. Semiannual technical progress report, April 1, 1983-September 30, 1983

    Energy Technology Data Exchange (ETDEWEB)

    1983-12-01

    An assessment of the HTGR opportunities from the year 2000 through 2045 was the principal activity on the Market Definition Task (WBS 03). Within the Plant Technology (WBS 13) task, there were activities to develop analytical methods for investigation of Coolant Transport Behavior and to define methods and criteria for High Temperature Structural Engineering design. The activities in support of the HTGR-SC/C Lead Plant (WBS 30 and 31) were the participation in the Lead Plant System Engineering (LPSE) effort and the plant simulation task. The efforts on the Advanced HTGR systems was performed under the Modular Reactor Systems (MRS) (WBS 41) to study the potential for multiple small reactors to provide lower costs, improved safety, and higher availability than the large monolithic core reactors.

  2. Association Euratom - Risø National Laboratory, Technical University of Denmark - Annual Progress Report 2007

    DEFF Research Database (Denmark)

    Michelsen, Poul; Korsholm, Søren Bang; Juul Rasmussen, Jens

    The programme of the Research Unit of the Fusion Association Euratom - Risø 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 pla......The programme of the Research Unit of the Fusion Association Euratom - Risø 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...... 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....

  3. Optically pumped polarized 23Na vapor target for use in polarized ion source. Technical progress report

    International Nuclear Information System (INIS)

    Anderson, L.W.

    1984-01-01

    We are currently measuring relaxation times in an optically pumped 23 Na vapor target. Our research is directed toward improvements in the optically pumped Na vapor targets used for the production of polarized H - ions. In this progress report we review the properties of the optically pumped polarized H - ion source and especially the optically pumped Na vapor target employed in this source as well as discussing the progress of our research on relaxation times in an optically pumped Na vapor target. 30 references, 6 figures, 3 tables

  4. Experimental Program Final Technical Progress Report: 15 February 2007 to 30 September 2012

    Energy Technology Data Exchange (ETDEWEB)

    Kinney, Edward R. [University of Colorado, Boulder, CO

    2014-09-12

    This is the final technical report of the grant DE-FG02-04ER41301 to the University of Colorado at Boulder entitled "Intermediate Energy Nuclear Physics" and describes the results of our funded activities during the period 15 February 2007 to 30 September 2012. These activities were primarily carried out at Fermilab, RHIC, and the German lab DESY. Significant advances in these experiments were carried out by members of the Colorado group and are described in detail.

  5. Association Euratom - DTU, Technical University of Denmark, Department of Physics - Annual Progress Report 2011

    DEFF Research Database (Denmark)

    The programme of the Research Unit of the Fusion Association Euratom – DTU, Technical University of Denmark (until 31-12- 2011: Association Euratom – Risø DTU) covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport...... temperature superconductors. Other 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 2011....

  6. Microwave plasma source for neutral-beam injection systems. Quarterly technical progress report

    International Nuclear Information System (INIS)

    1981-01-01

    The overall program is described and the technical and programmatic reasons for the decision to pursue both the RFI and ECH sources into the current hydrogen test stage is discussed. We consider the general characteristics of plasma sources in the parameter regime of interest for neutral beam applications. The operatonal characteristics, advantages and potential problems of RFI and ECH sources are discussed. In these latter two sections we rely heavily on experience derived from developing RFI and ECH ion engine sources for NASA

  7. Clearing of invasive alien plants in South Africa: a preliminary assessment of costs and progress

    CSIR Research Space (South Africa)

    Marais, R

    2004-01-01

    Full Text Available This paper provides estimates of the costs of clearing important species of invasive alien plants, as well as of progress made with clearing, based on data from a recently developed GIS-based project information system. Before the deployment...

  8. 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.

  9. Accelerator research studies. Technical progress report, July 1, 1985-June 30, 1986

    International Nuclear Information System (INIS)

    1986-01-01

    Progress is reported in these areas: study of instabilities and emittance growth in periodic focusing systems for intense beams; study of collective ion acceleration by intense electron beams and pulse powered plasma focus; and study of microwave sources and parameter scaling for high-frequency linacs

  10. Experimental studies of elementary particle interactions at high energies: Technical progress report

    International Nuclear Information System (INIS)

    1987-01-01

    This paper discusses progress of experiments at CERN and Fermilab. At CERN, data accumulation and analysis is discussed for the UA-6 experiment, which involves proton-antiproton collisions. At Fermilab, the testing of a collider detector for the Tevatron is discussed

  11. Accelerator research studies: Technical progress report, June 1, 1988--May 31, 1989

    International Nuclear Information System (INIS)

    1989-01-01

    This report discusses research progress in the following general topics: Study of transport and longitudinal compression of intense, high-brightness beams; study of collective ion acceleration by intense electron beams and pulse powered plasma focus; and study of microwave sources and parameter scaling for high-frequency electron-positron supercollider linacs

  12. High beta and second stability region transport and stability analysis: Technical progress report

    International Nuclear Information System (INIS)

    Hughes, M.H.; Phillips, M.W.

    1995-03-01

    This report summarizes MHD equilibrium and stability studies carried out at Northrop Grumman's Advanced Technology and Development Center during the 12 month period starting March 1, 1994. Progress is reported in both ideal and resistive MHD modeling of TFTR plasmas. The development of codes to calculate the significant effects of highly anisotropic pressure distributions is discussed along with results from this model

  13. Chemistry of gaseous lower-valent actinide halides. Technical progress report

    International Nuclear Information System (INIS)

    Hildenbrand, D.L.

    1984-01-01

    Objective is to provide thermochemical data for key actinide halide and oxyhalide systems. Progress is reported on bond dissociation energies of gaseous ThCl 4 , ThCl 3 , ThCl 2 , and ThCl; bond dissociation energies of ruthenium fluorides; and mass spectroscopy of UF 6

  14. Savannah River Ecology Laboratory annual technical progress report of ecological research, period ending July 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Vaitkus, M.R.; Wein, G.R. [eds.; Johnson, G.

    1993-11-01

    This progress report gives an overview of research programs at the Savannah River Site. Topics include; environmental operations support, wood stork foraging and breeding, defense waste processing, environmental stresses, alterations in the environment due to pollutants, wetland ecology, biodiversity, pond drawdown studies, and environmental toxicology.

  15. High beta and second stability region transport and stability analysis. Technical progress report

    International Nuclear Information System (INIS)

    Hughes, M.H.; Phillips, M.W.

    1994-09-01

    This report summarizes MHD equilibrium and stability studies carried out at Grumman's Corporate Research Center during the 6 month period starting March 1, 1994. Progress is reported in both ideal and resistive MHD modeling of TFTR plasmas. The development of codes to calculate the significant effects of highly anisotropic pressure distributions is discussed along with initial results from this model

  16. 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…

  17. 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…

  18. 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…

  19. 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…

  20. 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…

  1. 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…

  2. 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…

  3. 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…

  4. New technical knowledge to be implemented to the revision of rules on pipe wall thinning management for PWR plants

    International Nuclear Information System (INIS)

    Hirai, Junya; Nakamura, Takao; Amano, Yoichi

    2013-01-01

    Rules for PWR plant pipe wall thinning management were formulated by the Japan Society of Mechanical Engineers in 2006. Since then thinning management of Japanese PWR plants has been carried out based on this rule. Pipe wall thinning phenomena to be dealt with in this rule have been identified in many piping components of power plants. New technical knowledge has been accumulated since the issuance of 2006 edition. We have formulated these knowledge and information about the thinning phenomena in PWR power plants. Given the history of application of this rule, we have to make our best effort to carry out a study of latest technical knowledge and implement them to the revision of rule and improve pipe wall thinning management. This paper summarizes the new technical knowledge and basis to be implemented to the revision of rules on pipe wall thinning management for PWR plants in Japan. (author)

  5. Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

    International Nuclear Information System (INIS)

    Kofron, K.L.

    1994-01-01

    The seminar was held in Wuhan PRC from 01.10/94 - 01/14/94. It revolved about the role of the Technical Support Groups, both onsite and offsite, of the Nuclear Power Plant. This was to assist the Chinese in deciding their best course of action for the establishment and operation of this group

  6. Technical considerations in repowering a nuclear plant for fossil fueled operation

    International Nuclear Information System (INIS)

    Patti, F.J.

    1996-01-01

    Repowering involves replacement of the reactor by a fossil fuel source of steam. This source can be a conventional fossil fueled boiler or the heat recovery steam generator (HRSG) on a gas turbine exhaust. The existing steam turbine plant is used to the extent possible. Alternative fuels for repowering a nuclear plant are coal, natural gas and oil. In today's world oil is not usually an alternative. Selection of coal or natural gas is largely a matter of availability of the fuel near the location of the plant. Both the fossil boiler and the HRSG produce steam at higher pressures and temperatures than the throttle conditions for a saturated steam nuclear turbine. It is necessary to match the steam conditions from the new source to the existing turbine as closely as possible. Technical approaches to achieve a match range from using a topping turbine at the front end of the cycle to attemperation of the throttle steam with feedwater. The electrical output from the repowered plant is usually greater than that of the original nuclear fueled design. This requires consideration of the ability to use the excess electricity. Interfacing of the new facility with the existing turbine plant requires consideration of facility layout and design. Site factors must also be considered, especially for a coal fired boiler, since rail and coal handling facilities must be added to a site for which these were not considered. Additional site factors that require consideration are ash handling and disposal

  7. Radioecology of Natural Systems Sixteenth Technical Progress Report, Aug 1, 1977 - July 31, 1978

    Energy Technology Data Exchange (ETDEWEB)

    Whicker, F. W. [Colorado State Univ., Fort Collins, CO (United States). Dept. of Radiology and Radiation Biology

    1978-07-31

    Major effort during the contract year was devoted to publication of results, with only limited data collection activities. The studies concerning the behavior of plutonium in the terrestrial environs of the Rocky Flats Plant were largely completed one year ago. During the past year, several papers were prepared for publication and several others were either accepted for publication or appeared in print. Three masters theses were completed. Some new data were collected on the food habits of mule deer at the Rocky Flats Plant and on the geochemistry of stable lead in an alpine lake watershed. Some of these data are summarized herein. Miscellaneous activities related to the funded program are also reported.

  8. Radioecology of natural systems. Sixteenth technical progress report, August 1, 1977--July 31, 1978

    International Nuclear Information System (INIS)

    Whicker, F.W.

    1978-01-01

    Major effort during the contract year was devoted to publication of results, with only limited data collection activities. The studies concerning the behavior of plutonium in the terrestrial environs of the Rocky Flats Plant were largely completed one year ago. During the past year, several papers were prepared for publication and several others were either accepted for publication or appeared in print. Three masters these were completed. Some new data were collected on the food habits of mule deer at the Rocky Flats Plant and on the geochemistry of table lead in an alpine lake watershed. Some of these data are summarized herein. Miscellaneous activities related to the funded program are also reported

  9. Gas-Cooled Thermal Reactor Program. Annual technical progress report for the period ending September 30, 1981

    International Nuclear Information System (INIS)

    1982-03-01

    This report provides descriptions and results of the technical effort during FY81 on the Gas-Cooled Thermal Reactor Program. The FY81 work was organized according to the Work Breakdown Structure (WBS) for the National HTGR Program, and fell within five of the WBS tasks. The work on Market Definition and Development (WBS 03) was associated with estimating product costs for HTGR systems and their alternatives, projecting markets and market penetrations for these systems, and providing costs and market input to application analyses and component design. The Plant Technology (WBS 13) effort was mainly in the development of the systems dynamic computer code, STAR, for the transient analysis of HTGR's in reformer applications. The analysis of pebble bed reactors (PBR) was performed under Technology Transfer (WBS 15). The effort on components and systems within the nuclear heat source for reforming plants was performed under High Temperature Nuclear Heat Source (WBS 42)

  10. 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...

  11. 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...

  12. [Review of draft Crystalline Repository Project reports]: Technical progress report, CY 1985-1986

    International Nuclear Information System (INIS)

    1986-01-01

    During the period (CY 1985-86) of this report, the Wisconsin Radioactive Waste Review Board provided technical services under the contract with DOE. These included Participation in the development of variables and screening techniques that would be used in identifying those rock bodies in the Area Recommendation Report (ARR); reviewing and commenting on the report and developing a procedure in which local residents could have input into the process; sought resumption of negotiations with DOE on a full Consultation and Cooperation (CandC) agreement; and Participating in workshops and provided comments on two major DOE transportation documents, ''Transportation Business Plan: Strategy Options Document,'' and ''Transportation Institutional Plan.''

  13. Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

    Science.gov (United States)

    Selwitz, Jason Lawrence

    Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum and course development and evaluation research. First, the context of, and impetus for, what was formerly called vocational education, now referred to as technical or workforce education, is provided. Second, the research that was undertaken to design and evaluate an associate degree-level STEM workforce education program is described. Third, the adaptation of a student self-assessment of learning gains instrument is reviewed, and an analysis of the resulting data using an adapted logic model is provided, to evaluate the extent to which instructional approaches, in two process control/improvement-focused courses, were effective in meeting course-level intended learning outcomes. Finally, eight integrative multiscale exercises were designed from two example process systems, wastewater treatment and fast pyrolysis. The integrative exercises are intended for use as tools to accelerate the formation of an operator-technician's multiscale vision of systems, unit operations, underlying processes, and fundamental reactions relevant to multiple industries. Community and technical colleges serve a vital function in STEM education by training workers for medium- and high-skilled technical careers and providing employers the labor necessary to operate and maintain thriving business ventures. Through development of the curricular, course, and assessment-related instruments and tools, this research helps ensure associate degree-level technical education programs can engage in a continual process of program evaluation and improvement.

  14. New imaging systems in nuclear medicine. Technical progress report, July 1, 1975--March 15, 1976

    International Nuclear Information System (INIS)

    Brownell, G.L.

    1976-01-01

    This progress report covers four areas: development of positron instrumentation, development of NUMEDICS computer system and software, application of cyclotron-produced isotopes ( 11 C, 68 Ga, 13 N, 15 O, and 82 Rb), and application of the NUMEDICS computer system in nuclear medicine. The development of transverse section positron imaging has had a significant impact and a positron camera was designed specifically for transverse section imaging of heart and lungs. The computer net (NUMEDICS II) is progressing rapidly in design and software development. Clinical studies have demonstrated the feasibility of measuring cerebral blood flow using a variety of positron emitting radiopharmaceuticals and oxygen utilization using 15 O 2 . Rubidium-82 also appears to be a promising agent for measurement of cerebral blood flow

  15. Nuclear structure theory. Technical progress report, September 1, 1982-August 31, 1984

    International Nuclear Information System (INIS)

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

    1984-01-01

    Research progress is reported. Spectral Averaging studies are outlined including the theory of level densities for interacting nucleons, the properties of single-particle nuclear excitations, spectral distributions for fixed symmetries, and applications to the secular behavior of fluctuation measures in complex nuclei. Collective States research is described, in particular the boson-fermion symmetries which are related to the U(5) limit of the interacting boson model. Nuclear Reaction studies are described including the statistical theory of pion absorption, direct reactions at intermediate energies, and the properties of the off-shell πN t-matrix. Progress is reported on the quark theory of nuclear matter and the construction of models for a Fermi fluid which, near the nuclear ground state, is a fluid of nucleons composed of quarks, and, at high densities or temperatures, is a quark fluid. Applications of formal scattering theory to the study of phase-conjugate optics are discussed. Publications are listed

  16. AFR spent fuel storage program. Technical progress report, January 1981-March 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Work on this project is focused on developing design and licensing information for the model facility. Deliverables were submitted to DOE for facility modification, security design, and licensing documentation. Work is essentially complete on the high-density rack design with deliverable planned for April 30, 1981. A continuing program for completion of design and licensing information development was initiated by AGNS in February 1981. Progress to date is satisfactory

  17. U.C. Davis high energy particle physics research: Technical progress report -- 1990

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-12-31

    Summaries of progress made for this period is given for each of the following areas: (1) Task A--Experiment, H1 detector at DESY; (2) Task C--Experiment, AMY detector at KEK; (3) Task D--Experiment, fixed target detectors at Fermilab; (4) Task F--Experiment, PEP detector at SLAC and pixel detector; (5) Task B--Theory, particle physics; and (6) Task E--Theory, particle physics.

  18. Nuclear structure theory. Annual technical progress report, October 1, 1979-August 31, 1980

    International Nuclear Information System (INIS)

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

    1980-01-01

    This report summarizes progress during the past year in the following areas of nuclear structure and reaction theory: statistical spectroscopy (including random matrix methods, with applications to fluctuations in spectra and in strength distributions, and to problems of ergodicity; group symmetries in spectral-distribution theory; electromagnetic and β transitions); meson scattering and absorption by nuclei (including general scattering theory with absorption, multiple scattering theory and its reactive content, statistical theory of absorption); and meson currents in electromagnetic transitions

  19. Nuclear methods in chemical kinetics. Technical progress report, April 1, 1978--March 31, 1979

    International Nuclear Information System (INIS)

    1979-01-01

    Significant progress was achieved in the following products: (1) gas phase thermal F-to-HF reactions; (II) gas phase thermal 18 F olefinic addition reactions; (III) steady state hot atom kinetic theory; (IV) moderator effects on nuclear recoil 18 F substitution reactions; and (V) new experimental methodology. New work has been initiated upon the development of a realisitic potential form of kinetic collision theory

  20. High energy particle physics at Purdue. Annual technical progress report, March 1982-March 1983

    International Nuclear Information System (INIS)

    Gaidos, J.A.; Koltick, D.S.; Loeffler, F.J.

    1983-01-01

    Progress is reported in these areas: a study of electron-positron annihilation using the High Resolution Spectrometer at SLAC; proton decay; extensive muon showers; gamma ray astronomy; the DUMAND project; theoretical work on fundamental problems in electromagnetic, weak, strong, and gravitational interactions; chi production by hadrons; p-nucleus interactions; development of the Collider Detector at Fermilab; and study of the observed hadrons as the relativistic bound states of baryons and antibaryons

  1. Deep vadose zone remediation: technical and policy challenges, opportunities, and progress in achieving cleanup endpoints

    International Nuclear Information System (INIS)

    Wellman, D.M.; Freshley, M.D.; Truex, M.J.; Lee, M.H.

    2013-01-01

    Current requirements for site remediation and closure are standards-based and are often overly conservative, costly, and in some cases, technically impractical. Use of risk-informed alternate endpoints provides a means to achieve remediation goals that are permitted by regulations and are protective of human health and the environment. Alternate endpoints enable the establishment of a path for cleanup that may include intermediate remedial milestones and transition points and/or regulatory alternatives to standards-based remediation. A framework is presented that is centered around developing and refining conceptual models in conjunction with assessing risks and potential endpoints as part of a system-based assessment that integrates site data with scientific understanding of processes that control the distribution and transport of contaminants in the subsurface and pathways to receptors. This system-based assessment and subsequent implementation of the remediation strategy with appropriate monitoring are targeted at providing a holistic approach to addressing risks to human health and the environment. This holistic approach also enables effective predictive analysis of contaminant behavior to provide defensible criteria and data for making long-term decisions. Developing and implementing an alternate endpoint-based approach for remediation and waste site closure presents a number of challenges and opportunities. Categories of these challenges include scientific and technical, regulatory, institutional, and budget and resource allocation issues. Opportunities exist for developing and implementing systems-based approaches with respect to supportive characterization, monitoring, predictive modeling, and remediation approaches. (authors)

  2. Deep vadose zone remediation: technical and policy challenges, opportunities, and progress in achieving cleanup endpoints

    Energy Technology Data Exchange (ETDEWEB)

    Wellman, D.M.; Freshley, M.D.; Truex, M.J.; Lee, M.H. [Pacific Northwest National Laboratory, Richland, Washington (United States)

    2013-07-01

    Current requirements for site remediation and closure are standards-based and are often overly conservative, costly, and in some cases, technically impractical. Use of risk-informed alternate endpoints provides a means to achieve remediation goals that are permitted by regulations and are protective of human health and the environment. Alternate endpoints enable the establishment of a path for cleanup that may include intermediate remedial milestones and transition points and/or regulatory alternatives to standards-based remediation. A framework is presented that is centered around developing and refining conceptual models in conjunction with assessing risks and potential endpoints as part of a system-based assessment that integrates site data with scientific understanding of processes that control the distribution and transport of contaminants in the subsurface and pathways to receptors. This system-based assessment and subsequent implementation of the remediation strategy with appropriate monitoring are targeted at providing a holistic approach to addressing risks to human health and the environment. This holistic approach also enables effective predictive analysis of contaminant behavior to provide defensible criteria and data for making long-term decisions. Developing and implementing an alternate endpoint-based approach for remediation and waste site closure presents a number of challenges and opportunities. Categories of these challenges include scientific and technical, regulatory, institutional, and budget and resource allocation issues. Opportunities exist for developing and implementing systems-based approaches with respect to supportive characterization, monitoring, predictive modeling, and remediation approaches. (authors)

  3. Operation of a semi-technical pilot plant for nuclear aided steam gasification of coal

    International Nuclear Information System (INIS)

    Kirchhoff, R.; Heek, K.H. van; Juentgen, H.; Peters, W.

    1984-01-01

    After intensive investigations on a small scale, the principle of the process has been tested in a semi-technical pilot plant. In its gasifier a fluidized bed of approx. 1 m 2 cross-section and of up to 4 m height is operated at 40 bar. Heat is supplied to the bed from an immersed heat exchanger with helium flowing through it, which is heated electrically. The plant was commissioned in 1976 and has been in hot operation for approx. 23000 h, over 13000 h whereof account for coal gasification. Roughly 1600 t of coal have been put through. During recent years the processing of German caking long-flame gas coal and the marked improvement of the process by the use of catalysts have been demonstrated successfully. (orig.)

  4. Floating nuclear energy plants for seawater desalination. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-05-01

    Floating nuclear desalination facilities are one of the alternatives being considered. They may offer a particularly suitable choice for remote locations and small island or coastal communities where the necessary manpower and infrastructure to support desalination plants are not available. In the interest of focusing specific attention on the technology of floating nuclear desalination, the IAEA sponsored a Technical Committee Meeting on Floating Nuclear Plants for Seawater Desalination from 29 to 31 May 1995 in Obninsk, Russian Federation. This publication documents the papers and presentations given by experts from several countries at that meeting. It is hoped that the information contained in this report will be a valuable resource for those interested in nuclear desalination, and that it will stimulate further interest in the potential for floating nuclear desalination facilities. Refs, figs, tabs

  5. Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Saurwein, John

    2011-07-15

    This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

  6. Guideline for the seismic technical evaluation of replacement items for nuclear power plants

    International Nuclear Information System (INIS)

    Harris, S.P.; Cushing, R.W.; Johnson, H.W.; Abeles, J.M.

    1993-02-01

    Seismic qualification for equipment originally installed in nuclear power plants was typically performed by the original equipment suppliers or manufactures (OES/OEM). Many of the OES/OEM no longer maintain quality assurance programs with adequate controls for supplying nuclear equipment. Utilities themselves must provide reasonable assurance in the continued seismic adequacy of such replacement items. This guideline provides practical, cost-effective techniques which can be used to provide reasonable assurance that replacement items will meet seismic performance requirements necessary to maintain the seismic design basis of commercial nuclear power plants. It also provides a method for determining when a seismic technical evaluation of replacement items (STERI) is required as part of the procurement process for spare and replacement items. Guidance on supplier program requirements necessary to maintain continued seismic adequacy and on documentation of maintaining required seismic adequacy is also included

  7. Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

    International Nuclear Information System (INIS)

    Saurwein, J.

    2011-01-01

    This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

  8. Technical improvement of ATE system of Ling'ao Nuclear Power Plant Phase II

    International Nuclear Information System (INIS)

    Zhu Xingbao; Xiong Jingchuan; Liang Qiaohong

    2009-01-01

    In order to solve the problem that the content of SO 4 2- in Steam Generator significantly increased beyond the criteria after the use of the condensate treatment (ATE) system in Daya Bay Nuclear Power Plant and Ling'ao Nuclear Power Plant Phase I, technical improvement have been conducted on the sizes of the fore cation bed and the mixed bed, water distributing devices, ion exchange resins and separation facility. The effectiveness for the ion exchange of the mixed bed is improved, the resolved substance of cation resin is decreased; it is more impossible for fragments and powder which would lead high SO 4 2- content in Steam Generator. Finally, the quality of the steam-water could be improved and ensured. (authors)

  9. Diagnostic systems in nuclear power plants. Proceedings of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Nuclear power industry has a quite long tradition in on-line diagnostic of mechanical components and a considerable effort was put in developing diagnostic systems which are able to detect arising mechanical problems at an early stage. Computers are increasingly exploited to provide higher level information on process behaviour such as: early indication of the process deviation from normal conditions; rapid identification of the cause of any disturbance; prediction of the evolution of a disturbance; operator aid through computerized help. Following the recommendation of Several Member States to strengthen the activity in this field two divisions of IAEA established in 1995 the International Task Force on Nuclear Power Plant Diagnostics. The scope of the task force cover both technological developments and safety/licensing aspects of diagnostics. This report contains papers presented at the last in the series of Technical Committee Meetings on the Diagnostic Systems in Nuclear Power Plants organized in the framework of International Task Force

  10. Diagnostic systems in nuclear power plants. Proceedings of a technical committee meeting. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-31

    Nuclear power industry has a quite long tradition in on-line diagnostic of mechanical components and a considerable effort was put in developing diagnostic systems which are able to detect arising mechanical problems at an early stage. Computers are increasingly exploited to provide higher level information on process behaviour such as: early indication of the process deviation from normal conditions; rapid identification of the cause of any disturbance; prediction of the evolution of a disturbance; operator aid through computerized help. Following the recommendation of Several Member States to strengthen the activity in this field two divisions of IAEA established in 1995 the International Task Force on Nuclear Power Plant Diagnostics. The scope of the task force cover both technological developments and safety/licensing aspects of diagnostics. This report contains papers presented at the last in the series of Technical Committee Meetings on the Diagnostic Systems in Nuclear Power Plants organized in the framework of International Task Force Refs, figs, tabs

  11. CO2 capture from power plants: Part I. A parametric study of the technical performance based on monoethanolamine

    NARCIS (Netherlands)

    Abu-Zahra, Mohammad R.M.; Schneiders, Léon H.J.; Niederer, John; Feron, Paul H.M.; Versteeg, Geert

    2007-01-01

    Capture and storage of CO2 from fossil fuel fired power plants is drawing increasing interest as a potential method for the control of greenhouse gas emissions. An optimization and technical parameter study for a CO2 capture process from flue gas of a 600 MWe bituminous coal fired power plant, based

  12. CO2 capture from power plants. Part I : A parametric study of the technical performance based on monoethanolamine

    NARCIS (Netherlands)

    Abu-Zahra, M. R. M.; Schneiders, L. H. J.; Niederer, J. P. M.; Feron, P. H. M.; Versteeg, G. F.

    Capture and storage of CO2 from fossil fuel fired power plants is drawing increasing interest as a potential method for the control of greenhouse gas emissions. An optimization and technical parameter study for a CO2 capture process from flue gas of a 600 MWe bituminous coal fired power plant, based

  13. Technical specifications, Callaway Plant, Unit No. 1. Appendix A to license No. NPF-25 (Docket No. STN 50-483)

    International Nuclear Information System (INIS)

    Anderson, F.D.

    1984-06-01

    Technical specifications are presented for the limiting conditions for operation and surveillance requirements for the reactor core, reactivity control systems, power distribution limits, instrumentation, reactor coolant system, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations, special test exceptions, radioactive effluents, radiological environmental monitoring; design features of the site, containment, core, coolant system, and fuel storage; and plant staff organization

  14. Y-12 Development Organization technical progress report: Part 3 -- Metal processing, period ending March 1, 1994

    International Nuclear Information System (INIS)

    Northcutt, W.G. Jr.

    1994-01-01

    As part of the effort to downsize its uranium processing facilities, the Y-12 Plant has supported an investigation to identify extraction solvents that would both work efficiently in centrifugal contactors and be disposed of easily. Various organic ethers, hydroxy ethers, ether ketones, acids, amides, and diketones were studied for their ability to extract uranyl nitrate from aqueous solutions. Although many of these solvents were obtained commercially, others had to be synthesized in-house. The authors found a large range of extraction coefficients for these solvents. Because of steric hindrance or some other factor, certain ethers performed poorly. On the other hand, various mono- and diethers of tetrahydrofurfuryl alcohol exhibited excellent extraction and stripping coefficients for uranyl nitrate, justifying purchase of a pilot plant batch of one of this family of solvents. Likewise, the authors determined the extraction coefficient for one of the two amides synthesized in-house to be quite high

  15. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2010

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-04-15

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, 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 related to development of high temperature superconductors. Other 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 2010. (Author)

  16. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2009

    International Nuclear Information System (INIS)

    Korsholm, S.B.; Michelsen, P.K.; Rasmussen, J.J.; Westergaard, C.M.

    2010-04-01

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, 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 related to development of high temperature superconductors. 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 2009. (Author)

  17. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2009

    Energy Technology Data Exchange (ETDEWEB)

    Korsholm, S B; Michelsen, P K; Rasmussen, J J; Westergaard, C M [eds.

    2010-04-15

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, 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 related to development of high temperature superconductors. 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 2009. (Author)

  18. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2008

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-04-15

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, 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. New activities in technology related to development of high temperature superconductors have been initiated in 2008. 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 2008. (Author)

  19. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2008

    International Nuclear Information System (INIS)

    Korsholm, S.B.; Michelsen, P.K.; Rasmussen, J.J.; Westergaard, C.M.

    2009-04-01

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, 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. New activities in technology related to development of high temperature superconductors have been initiated in 2008. 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 2008. (Author)

  20. Progress report [of] Technical Physics and Prototype Engineering Division, April 1982 - March 1984

    International Nuclear Information System (INIS)

    Ramamurthi, S.S.; Chaudhry, Ramesh

    1985-01-01

    The work done by the Technical Physics and Prototype Engineering Division of the Bhabha Atomic Research Centre (BARC) at Bombay during the period from April 1982 to March 1984 is described in the form of summaries. The main thrust of the work of the Division is towards designing, developing, fabricating and if needed, producing on a large scale various instruments, equipment and components required for the programmes of the BARC and the Department of Atomic Energy. The summaries describing the work are grouped under the headings:(1) vacuum, (2) surface analysis, (3) mass spectrometry, (4) electronics, (5) cryogenics, (6) crystals and detectors, (7) glass technology and devices, and (8) optoelectronics. A list of publications of the staff-members of the Division during the report period is given. (M.G.B.)

  1. 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)

  2. 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)

  3. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2010

    International Nuclear Information System (INIS)

    Korsholm, S.B.; Michelsen, P.K.; Rasmussen, J.J.; Westergaard, C.M.

    2011-04-01

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, 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 related to development of high temperature superconductors. Other 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 2010. (Author)

  4. Fusion programs in applied plasma physics. Technical progress report, July 11, 1992--May 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    This report summarizes the progress made in theoretical and experimental research funded by US Department of Energy Grant No. DE-FG03-92ER54150, during the period July 11, 1992 through May 31, 1993. Four main tasks are reported: applied plasma physics theory, alpha particle diagnostic, edge and current density diagnostic, and plasma rotation drive. The report also discusses the research plans for the theory and experimental programs for the next grant year. Reports and publications supported by the grant during this period are listed in the final section.

  5. Decontamination Systems Information and Research Program. Quarterly technical progress report, July 1--September 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    Progress reports are presented for the following projects: systematic assessment of the state of hazardous waste clean-up technologies; site remediation technologies--drain-enhanced soil flushing (DESF) for organic contaminants removal; 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; Winfield cleanup survey; assessment of technologies for hazardous waste site remediation--non-treatment technologies and pilot scale test facility implementation; assessment of environmental remediation storage technology; assessment of environmental remediation excavation technology; assessment of environmental remediation monitoring technology; and remediation of hazardous sites with steam reforming.

  6. Salt repository project: Technical progress report for the quarter 1 April--30 June 1987

    International Nuclear Information System (INIS)

    1987-01-01

    This document reports the progress being made each quarter on the development of a geologic repository in salt for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Nuclear Waste Isolation, a prime contractor of the US Department of Energy (DOE) Salt Repository Project Office. The studies include work by other DOE prime contractors and by contractors to the Office of Nuclear Waste Isolation

  7. Nuclear structure theory. Annual technical progress report, October 1, 1978-September 30, 1979

    International Nuclear Information System (INIS)

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

    1979-01-01

    This report summarizes progress during the past year in the following areas of nuclear structure and reaction theory: Statistical spectroscopy, including: Random matrix methods, with applications to fluctuations in spectra and in strength distributions, and to problems of ergodicity; Group symmetries in spectral-distribution theory; Electromagnetic and β transitions. Meson scattering and absorption by nuclei, including: general scattering theory with absorption, multiple scattering theory and its reactive content, statistical theory of absorption, theory of the absorption operator (πNN vertex), theory of πN scattering. A list of publications is included

  8. 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

  9. Theoretical nuclear physics. Task B. Technical progress report, August 1, 1982-September 30, 1983

    International Nuclear Information System (INIS)

    1983-01-01

    Progress is reported on the following studies: (a) double delta interactions in pion double charge exchange; (b) isovector correlations in pion-nucleus scattering; (c) nuclear structure effects in pion single charge exchange; (d) a perspective on sequential transfer reactions; (e) inelastic and charge exchange scattering theory; (f) magnitude of the first order DWBA description of the two nuclear transfer reactions; (g) nonlocality effects on deuteron transfer reactions; (h) evaluation of external radial integrals in inelastic electron scattering; (i) experimental observables as a function of Dirac invariant amplitudes; (j) Dirac shell-model wavefunctions in inelastic electron scattering; and (k) impulse approximation Dirac theory of inelastic proton nucleus collective excitations. Publications are listed

  10. High energy particle physics at Purdue. Annual technical progress report, March 1983-March 1984

    International Nuclear Information System (INIS)

    Gaidos, J.A.; Koltick, D.S.; Loeffler, F.J.

    1984-01-01

    Progress is reported in these areas: a study of electron-positron annihilation using the High Resolution Spectrometer; experimental study of proton decay; gamma ray astrophysics; the DUMAND project; fundamental problems in the theory of gravitational, electromagnetic, weak, and strong interactions; chi production by hadrons; study of collective phenomena; search for the onset of collective phenonmena; work on the Collider Detector at Fermilab; search for a deconfined quark-gluon phase of strongly interacting matter at the FNAL proton-antiproton collider; and development of an electrodeless drift chamber

  11. Physics of correlated systems. Technical progress report, December 1996 - June 1999

    International Nuclear Information System (INIS)

    Greene, C.H.

    1999-01-01

    During the current funding period, which covers a period of approximately 2.5 years, the authors have tackled a number of challenging problems that involve nonperturbative particle-particle interactions in two qualitatively different areas: electron-electron interactions in photoionization and photodetachment, and atom-atom interactions in Bose-Einstein condensates. The following discusses the progress achieved in these different areas. The emphasis in this summary will concentrate on approximately the last year of research accomplishments, although the bibliography below includes all research publications that were supported during the time period of this grant

  12. Decontamination Systems Information and Research Program. Quarterly technical progress report, July 1--September 30, 1993

    International Nuclear Information System (INIS)

    1993-10-01

    Progress reports are presented for the following projects: systematic assessment of the state of hazardous waste clean-up technologies; site remediation technologies--drain-enhanced soil flushing (DESF) for organic contaminants removal; 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; Winfield cleanup survey; assessment of technologies for hazardous waste site remediation--non-treatment technologies and pilot scale test facility implementation; assessment of environmental remediation storage technology; assessment of environmental remediation excavation technology; assessment of environmental remediation monitoring technology; and remediation of hazardous sites with steam reforming

  13. Plasma physics research (Tokapole II). Technical progress report, October 1, 1981-December 31, 1983

    International Nuclear Information System (INIS)

    1983-01-01

    Progress during the 27-month period, October 1, 1981 to December 31, 1983 on Tokapole II research is described. Tokapole II is a 4-node poloidal divertor tokamak that can also be run as an octupole. Research during this period has concentrated on studies of discharges with safety factor q less than one and on the identification of the shear Alfven wave resonance. Other topics include measurements of the loop voltage reduction through ECRH startup, plasma gun refueling, fluctuations and transport, pumped limiter studies, plasma-wall interactions, diagnostic development, polarization of electron cyclotron emission, and poloidal ohmic heating

  14. Nuclear structure theory. Annual technical progress report, October 1, 1977--September 30, 1978

    International Nuclear Information System (INIS)

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

    1978-01-01

    Progress during the past year in the following areas of nuclear structure and reaction theory is summarized: statistical spectroscopy, including random matrix methods, with applications to fluctuations in spectra and in strength distributions, and to problems of erogodicity; group symmetries in spectral distribution theory; effective interactions; statistical reaction theory, applied to ''deep inelastic'' collisions of heavy ions, and to pion absorption by nuclei; meson scattering and absorption by nuclei, including general scattering theory with absorption, multiple scattering theory and its reactive content, models for absorption, theory of the absorption operator (πNN vertex), theory of πN scattering. A list of publications is included

  15. Salt Repository Project technical progress report for the quarter 1 January--31 March 1987

    International Nuclear Information System (INIS)

    1988-03-01

    This document reports the progress being made each quarter on the development of a geologic repository in salt for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Nuclear Waste Isolation, a prime contractor of the US Department of energy (DOE) Salt Repository Project Office. The studies include work by other DOE prime contractors and by contractors to the Office of Nuclear Waste Isolation. 23 refs., 1 fig

  16. Nuclear structure theory. Annual technical progress report, September 1, 1980-August 31, 1981

    International Nuclear Information System (INIS)

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

    1981-01-01

    This report summarizes progress during the past year in the following areas of nuclear structure and reaction theory: (1) statistical spectroscopy, including: random matrix methods, with applications to fluctuations in spectra and in strength distributions; group symmetries in spectral-distribution theory; electromagnetic and β transitions, limits to time-reversal symmetry breaking in the nucleon-nucleon interaction; (2) meson scattering and absorption by nuclei, including: general scattering theory with absorption, multiple scattering theory and its reactive content, statistical theory of absorption; and (3) meson currents in electromagnetic transitions

  17. Thermionic cogeneration burner assessment study. Third quarterly technical progress report, April-June, 1983

    Energy Technology Data Exchange (ETDEWEB)

    1983-01-01

    The specific tasks of this study are to mathematically model the thermionic cogeneration burner, experimentally confirm the projected energy flows in a thermal mock-up, make a cost estimate of the burner, including manufacturing, installation and maintenance, review industries in general and determine what groups of industries would be able to use the electrical power generated in the process, select one or more industries out of those for an in-depth study, including determination of the performance required for a thermionic cogeneration system to be competitive in that industry. Progress is reported. (WHK)

  18. Engaging Local Stakeholders on Technical Issues: Test Case at the La Hague Reprocessing Plant - 59211

    International Nuclear Information System (INIS)

    Gilli, Ludivine

    2012-01-01

    In 2009 and 2010, the Institute for Nuclear Safety and Radiation Protection (IRSN) lead a pilot action dealing with the decommissioning of a workshop located on the site of Areva's La Hague fuel-reprocessing plant site in Northwestern France. The purpose of the pilot program was to test ways for IRSN and a few local stakeholders (Non-Governmental Organizations (NGOs) members, local elected officials, etc.) to engage in technical discussions. The discussions were intended to enable the local stakeholders to review the operator's decommissioning application and provide input. The pilot program confirmed there is a definite challenge in successfully opening a meaningful dialogue to discuss technical issues. Three factors influence the extent of the challenge: the knowledge gap between experts and local stakeholders, the conflict between transparency and confidentiality which is inherent with technical topics, and the difficulty for an official expertise institute to hold a dialogue with 'outsiders' during an ongoing reviewing process in which it is participating. The pilot program, given its mixed results, also provided valuable lessons for further improvement of stakeholders' involvement. (authors)

  19. Technical and economical prerequisites of special district-heating nuclear power plant development

    International Nuclear Information System (INIS)

    Baturov, B.B.; Boldyrev, V.M.; Losev, V.L.; Sigal, M.V.

    1983-01-01

    Results are presented of technical and economical analysis of advisability of constructing combined Nuclear Power and Heating Plants (NPHP) assuring the possibility of their location near the areas of heat power consumption in case of observing a given degree of radiation safety for population and personnel. Specific features determining the choice of turbine-driven units for such plants are analyzed. Conditions of competiveness of a specialized NPHP with alternative power units, NPHP based on the WWER-1000 reactor and district heating plants (NDHP), are determined. Analysis of design specifications of NPHP with two VK-500 reactor units and structures of capital investments in such a plant reveal that an increase in the total capital investments in the NPHP would not exceed 2% with account of the difference in costs for grid heaters and a corresponding change in dimensions of operation rooms as well as changes in costs of heat removal system (within one site) at the TK turbine replacement by the T turbine

  20. Technical and economic assessment of the integrated solar combined cycle power plants in Iran

    International Nuclear Information System (INIS)

    Soltani Hosseini, M.; Hosseini, R.; Valizadeh, G.H.

    2002-01-01

    Thermal efficiency, capacity factor, environmental considerations, investment cost, fuel and O and M costs are the main parameters for technical and economic assessment of solar power plants. This analysis has shown that the Integrated Solar Combined Cycle System with 67 MW e solar field(ISCCS-67) is the most suitable plan for the first solar power plant in Iran. The Levelized Energy Costs of combined cycle and ISCCS-67 power plants would be equal if 49 million dollars of ISCCS-67 capital cost supplied by the international environmental organizations such as Global Environmental Facilities and World Bank. This study shows that an ISCCS-67 saves 59 million dollars in fuel consumption and reduces about 2.4 million ton in CO 2 emission during 30 years operating period. Increasing of steam turbine capacity by 50%, and 4% improvement in overall efficiency are other advantages of iSCCS-67 power plant. The LEC of ISCCS-67 is 10% and so 33% lower than the combined cycle and gas turbine, respectively, at the same capacity factor with consideration of environmental costs

  1. Organizational factors influencing human performance in nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-05-01

    In 1991 a Safety Series report on Safety Culture of the International Nuclear Safety Advisory Group (INSAG) was published as 75-INSAG-4 by the IAEA. This report deals with the concept of Safety Culture as it relates to organizations and individuals involved in the operations of nuclear power plants (NPPs). Generally, the role of management and organization in assuring the safe operation of NPPs has been widely recognized and its importance accepted. However, the understanding of what constitutes effective management and organization the area of safety is less developed than the understanding of most of the technical issues which plant operators and regulatory bodies are confronted with. The Technical Committee meeting provided a forum for a broad exchange of information on practices and experiences in the area of organization and management to accomplish operational safety in NPPs and thus enhance Safety Culture. This report and the papers presented at the meeting discuss those factors which influence and improve human performance covering both aspects, i.e. the basic requirements imposed on the operator and the ways of managerial support which enhance the reliable and safety oriented performance of operators. Refs, figs, tabs

  2. 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)

  3. An accelerator neutron source for BNCT. Technical progress report, 1 June 1993--31 May 1994

    International Nuclear Information System (INIS)

    Blue, T.E.; Vafai, K.

    1994-02-01

    This is the progress report for the project entitled, ''An Accelerator Neutron Source for BNCT.'' The progress report is for the period from July 1, 1993 to date. The overall objective of our research project is to develop an Accelerator Epithermal Neutron Irradiation Facility (AENIF) for Boron Neutron Capture Therapy (BNCT). The AENIF consists of a 2.5 MeV high current proton accelerator, a lithium target to produce source neutrons, and a moderator/reflector assembly to obtain from the energetic source neutrons an epithermal neutron field suitable for BNCT treatments. Our project goals are to develop the non-accelerator components of the AENIF, and to specifically include in our development: (1) design, numerical simulation, and experimental verification of a target assembly which is capable of removing 75 kW of beam power; (2) re-optimization of the moderator assembly design based on in-phantom dose assessments using neutron spectra calculated in phantom and an energy-dependent neutron Relative Biological Effectiveness (RBE); (3) construction of a prototype moderator assembly and confirmation of its design by measurements; (4) design of the shielding of the accelerator and treatment rooms for an AENIF; and (5) design of a high energy beam transport system which is compatible with the shielding design and the thermal-hydraulic design

  4. Technical progress report, Contracts DE-AC02-81ER40014, 40015 and 40016

    International Nuclear Information System (INIS)

    1981-01-01

    This Progress Report summarizes work carried out at the Nuclear Physics Laboratory of the University of Colorado from November 1, 1980 through July 31, 1981, under contracts between the University of Colorado and the United States Department of Energy. The shorter report period of nine months is due to a change to an earlier submission date this year for our proposal for support to begin February 1, 1982. Cyclotron operation, research, and development have been supported under contract DE-AC02-81ER40014. The AVF cyclotron has continued to provide reliable and versatile beams of protons, deuterons, 3 He and 4 He. A wide variety of research results in direct reactions, nuclear structure, and compound reaction mechanisms can be noted in this Progress Report, correlated in many cases to current problems in intermediate energy physics. Theoretical work on nuclear reactions, carried out under contract DE-AC02-81ER40015, has been well matched to our experimental programs in low and intermediate energy physics. One important result has been the recasting of the DWBA in an eikonal expansion suited to high energy reactions. Our efforts in intermediate energy physics, under contract DE-AC02-81ER40016, have emphasized pion scattering studies at LAMPF and TRIUMF and proton induced charge exchange reactions at IUCF. Data for an important test of hadronic charge symmetry have been completed at two energies, using elastic pion-deuteron scattering

  5. Technical and economic analysis of integrating low-medium temperature solar energy into power plant

    International Nuclear Information System (INIS)

    Wang, Fu; Li, Hailong; Zhao, Jun; Deng, Shuai; Yan, Jinyue

    2016-01-01

    Highlights: • Seven configurations were studied regarding the integration of solar thermal energy. • Economic analysis was conducted on new built plants and retrofitted power plants. • Using solar thermal energy to preheat high pressure feedwater shows the best performance. - Abstract: In order to mitigate CO_2 emission and improve the efficiency of the utilization of solar thermal energy (STE), solar thermal energy is proposed to be integrated into a power plant. In this paper, seven configurations were studied regarding the integration of STE. A 300 MWe subcritical coal-fired plant was selected as the reference, chemical absorption using monoethanolamine solvent was employed for CO_2 ​capture, and parabolic trough collectors and evacuated tube collectors were used for STE collection. Both technical analysis and economic evaluation were conducted. Results show that integrating solar energy with post-combustion CO_2​ capture can effectively increase power generation and reduce the electrical efficiency penalty caused by CO_2 capture. Among the different configurations, Config-2 and Config-6, which use medium temperature STE to replace high pressure feedwater without and with CO_2 capture, show the highest net incremental solar efficiency. When building new plants, integrating solar energy can effectively reduce the levelized cost of electricity (LCOE). The lowest LCOE, 99.28 USD/MWh, results from Config-6, with a parabolic trough collector price of 185 USD/m"2. When retrofitting existing power plants, Config-6 also shows the highest net present value (NPV), while Config-2 has the shortest payback time at a carbon tax of 50 USD/ton CO_2. In addition, both LCOE and NPV/payback time are clearly affected by the relative solar load fraction, the price of solar thermal collectors and the carbon tax. Comparatively, the carbon tax can affect the configurations with CO_2 capture more clearly than those without CO_2 capture.

  6. The Chernobyl accident and the Spanish nuclear power plants. Technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-15

    On the morning of April 26, 1986, Unit 4 of the Chernobyl Nuclear Power Plant (Ukraine, USSR) suffered an accident of the greatest magnitude among those which have taken place in nuclear energy installations employed for peaceful uses. The accident reached a degree of severity unknown up to now in nuclear energy generating plants, both with respect to the loss of human lives and the effects caused to the neighboring population (as well as to other nations within a wide radius of radioactivity dispersal), and also with respect to the damage caused in the nuclear plant itself. In the light of the anxiety created internationally, the USSR State Committee for the Utilization of Atomic Energy prepared a report (1), based on the conclusions of the Governmental Commission entrusted to study the causes of the accident, which was presented at the international meeting of experts held at the International Atomic Energy Agency (IAEA) headquarters in Vienna from August 25 to 29, 1986. The present technical report has been prepared by the Spanish nuclear power plants within the framework of UNIDAD ELECTRICA, S.A. (UNESA) - the Association of Spanish electric utilities - in collaboration with EMPRESARIOS AGRUPADOS, S.A. The report reflects the utilities' analyses of the causes and consequences of the accident and, based on similarities and differences with Spanish plants under construction and in operation, intends to: a. Evaluate the possibility of an accident with similar consequences occurring in a Spanish plant b. Identify possible design and operation modifications indicated by the lessons learned from this accident.

  7. The Chernobyl accident and the Spanish nuclear power plants. Technical report

    International Nuclear Information System (INIS)

    1986-11-01

    On the morning of April 26, 1986, Unit 4 of the Chernobyl Nuclear Power Plant (Ukraine, USSR) suffered an accident of the greatest magnitude among those which have taken place in nuclear energy installations employed for peaceful uses. The accident reached a degree of severity unknown up to now in nuclear energy generating plants, both with respect to the loss of human lives and the effects caused to the neighboring population (as well as to other nations within a wide radius of radioactivity dispersal), and also with respect to the damage caused in the nuclear plant itself. In the light of the anxiety created internationally, the USSR State Committee for the Utilization of Atomic Energy prepared a report (1), based on the conclusions of the Governmental Commission entrusted to study the causes of the accident, which was presented at the international meeting of experts held at the International Atomic Energy Agency (IAEA) headquarters in Vienna from August 25 to 29, 1986. The present technical report has been prepared by the Spanish nuclear power plants within the framework of UNIDAD ELECTRICA, S.A. (UNESA) - the Association of Spanish electric utilities - in collaboration with EMPRESARIOS AGRUPADOS, S.A. The report reflects the utilities' analyses of the causes and consequences of the accident and, based on similarities and differences with Spanish plants under construction and in operation, intends to: a. Evaluate the possibility of an accident with similar consequences occurring in a Spanish plant b. Identify possible design and operation modifications indicated by the lessons learned from this accident

  8. Technical feasibility and carbon footprint of biochar co-production with tomato plant residue.

    Science.gov (United States)

    Llorach-Massana, Pere; Lopez-Capel, Elisa; Peña, Javier; Rieradevall, Joan; Montero, Juan Ignacio; Puy, Neus

    2017-09-01

    World tomato production is in the increase, generating large amounts of organic agricultural waste, which are currently incinerated or composted, releasing CO 2 into the atmosphere. Organic waste is not only produced from conventional but also urban agricultural practices due recently gained popularity. An alternative to current waste management practices and carbon sequestration opportunity is the production of biochar (thermally converted biomass) from tomato plant residues and use as a soil amendment. To address the real contribution of biochar for greenhouse gas mitigation, it is necessary to assess the whole life cycle from the production of the tomato biomass feedstock to the actual distribution and utilisation of the biochar produced in a regional context. This study is the first step to determine the technical and environmental potential of producing biochar from tomato plant (Solanum lycopersicum arawak variety) waste biomass and utilisation as a soil amendment. The study includes the characterisation of tomato plant residue as biochar feedstock (cellulose, hemicellulose, lignin and metal content); feedstock thermal stability; and the carbon footprint of biochar production under urban agriculture at pilot and small-scale plant, and conventional agriculture at large-scale plant. Tomato plant residue is a potentially suitable biochar feedstock under current European Certification based on its lignin content (19.7%) and low metal concentration. Biomass conversion yields of over 40%, 50% carbon stabilization and low pyrolysis temperature conditions (350-400°C) would be required for biochar production to sequester carbon under urban pilot scale conditions; while large-scale biochar production from conventional agricultural practices have not the potential to sequestrate carbon because its logistics, which could be improved. Therefore, the diversion of tomato biomass waste residue from incineration or composting to biochar production for use as a soil amendment

  9. 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)

  10. Internal Technical Report, Safety Analysis Report 5 MW(e) Raft River Research and Development Plant

    Energy Technology Data Exchange (ETDEWEB)

    Brown, E.S.; Homer, G.B.; Shaber, C.R.; Thurow, T.L.

    1981-11-17

    The Raft River Geothermal Site is located in Southern Idaho's Raft River Valley, southwest of Malta, Idaho, in Cassia County. EG and G idaho, Inc., is the DOE's prime contractor for development of the Raft River geothermal field. Contract work has been progressing for several years towards creating a fully integrated utilization of geothermal water. Developmental progress has resulted in the drilling of seven major DOE wells. Four are producing geothermal water from reservoir temperatures measured to approximately 149 C (approximately 300 F). Closed-in well head pressures range from 69 to 102 kPa (100 to 175 psi). Two wells are scheduled for geothermal cold 60 C (140 F) water reinjection. The prime development effort is for a power plant designed to generate electricity using the heat from the geothermal hot water. The plant is designated as the ''5 MW(e) Raft River Research and Development Plant'' project. General site management assigned to EG and G has resulted in planning and development of many parts of the 5 MW program. Support and development activities have included: (1) engineering design, procurement, and construction support; (2) fluid supply and injection facilities, their study, and control; (3) development and installation of transfer piping systems for geothermal water collection and disposal by injection; and (4) heat exchanger fouling tests.

  11. Internal Technical Report, Safety Analysis Report 5 MW(e) Raft River Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Brown, E.S.; Homer, G.B.; Spencer, S.G.; Shaber, C.R.

    1980-05-30

    The Raft River Geothermal Site is located in Southern Idaho's Raft River Valley, southwest of Malta, Idaho, in Cassia County. EG and G idaho, Inc., is the DOE's prime contractor for development of the Raft River geothermal field. Contract work has been progressing for several years towards creating a fully integrated utilization of geothermal water. Developmental progress has resulted in the drilling of seven major DOE wells. Four are producing geothermal water from reservoir temperatures measured to approximately 149 C (approximately 300 F). Closed-in well head pressures range from 69 to 102 kPa (100 to 175 psi). Two wells are scheduled for geothermal cold 60 C (140 F) water reinjection. The prime development effort is for a power plant designed to generate electricity using the heat from the geothermal hot water. The plant is designated as the ''5 MW(e) Raft River Research and Development Plant'' project. General site management assigned to EG and G has resulted in planning and development of many parts of the 5 MW program. Support and development activities have included: (1) engineering design, procurement, and construction support; (2) fluid supply and injection facilities, their study, and control; (3) development and installation of transfer piping systems for geothermal water collection and disposal by injection; and (4) heat exchanger fouling tests.

  12. Progress report on installing DYMCAS in the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    Mee, W.T.

    1979-01-01

    A material control and accountability system to assist in detecting diversion of special nuclear materials (SNM) was being considered by the management of the Oak Ridge Y-12 Plant in early 1975. The Dynamic Special Nuclear Materials Control and Accountability System (DYMCAS) is the product of these considerations. The evolution of computerized accountability systems for near real-time accounting of SNM will revolutionize the activities for operations and accountability departments in Y-12. The advancement of nondestructive analysis equipment with a capability for real-time input of accounting data is becoming a reality. The progress of installing the DYMCAS in a large plant processing unirradiated enriched uranium is described

  13. 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

  14. GT-MHR COMMERCIALIZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD AUGUST 1 THROUGH AUGUST 31, 2003

    International Nuclear Information System (INIS)

    Shenoy, A.S.

    2003-01-01

    OAK A271 GT-MHR COMERCIALiZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD AUGUST 1 THROUGH AUGUST 31, 2003. In the process of fabricating the MHR-1 irradiation test capsule, Petten has advised that three thermocouples (out of 24) and the Self Powered Neutron detector were damaged during high temperature brazing with the upper capsule lid. Procurement of new TCs and SPN is in process but there will be a delay in the irradiation test of about nine weeks. Startup of the irradiation is now projected to be July or August 2004. In preparation for performing the nuclear design analysis activities required by the advanced fuel studies task, a complete 3-D nuclear design analysis is first being performed of the GT-MHR reference design. This will serve as the baseline for studies of the advanced fuel nuclear design performance

  15. Current status and technical description of Chinese 2 x 250 MWth HTR-PM demonstration plant

    International Nuclear Information System (INIS)

    Zhang Zuoyi; Wu Zongxin; Wang Dazhong; Xu Yuanhui; Sun Yuliang; Li Fu; Dong Yujie

    2009-01-01

    After the nuclear accidents of Three Mile Island and Chernobyl the world nuclear community made great efforts to increase research on nuclear reactors and to develop advanced nuclear power plants with much improved safety features. Following the successful construction and a most gratifying operation of the 10 MW th high-temperature gas-cooled test reactor (HTR-10), the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University has developed and designed an HTR demonstration plant, called the HTR-PM (high-temperature-reactor pebble-bed module). The design, having jointly been carried out with industry partners from China and in collaboration of experts worldwide, closely follows the design principles of the HTR-10. Due to intensive engineering and R and D efforts since 2001, the basic design of the HTR-PM has been finished while all main technical features have been fixed. A Preliminary Safety Analysis Report (PSAR) has been compiled. The HTR-PM plant will consist of two nuclear steam supply system (NSSS), so called modules, each one comprising of a single zone 250 MW th pebble-bed modular reactor and a steam generator. The two NSSS modules feed one steam turbine and generate an electric power of 210 MW. A pilot fuel production line will be built to fabricate 300,000 pebble fuel elements per year. This line is closely based on the technology of the HTR-10 fuel production line. The main goals of the project are two-fold. Firstly, the economic competitiveness of commercial HTR-PM plants shall be demonstrated. Secondly, it shall be shown that HTR-PM plants do not need accident management procedures and will not require any need for offsite emergency measures. According to the current schedule of the project the completion date of the demonstration plant will be around 2013. The reactor site has been evaluated and approved; the procurement of long-lead components has already been started. After the successful operation of the demonstration plant

  16. Waste Isolation Safety Assessment Program. Technical progress report for FY-1978

    International Nuclear Information System (INIS)

    Brandstetter, A.; Harwell, M.A.; Howes, B.W.; Benson, G.L.; Bradley, D.J.; Raymond, J.R.; Serne, R.J.; Schilling, A.H.

    1979-07-01

    Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE) is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Program (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of making those analyses. Progress on the following tasks is reported: release scenario analysis, waste form release rate analysis, release consequence analysis, sorption-desorption analysis, and societal acceptance analysis

  17. Repository Technology Program: Technical progress report for the period May 29, 1986--June 30, 1987

    International Nuclear Information System (INIS)

    1988-10-01

    This document reports the progress made in the 13-month period from May 29, 1986--June 30, 1987, on the development of a second geologic repository in rocks other than those being considered for a first repository. Subsequent periods will be covered in reports to be issued on a semiannual basis. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Waste Technology Development (OWTD), a prime contractor of the US. Department of Energy (DOE) Repository Technology Program (RTP) Office in the Repository Technology and Transportation Division (RTTD) of the Office of Geologic Repositories (OGR). The studies include work by other DOE prime contractors and by contractors to the OWTD. 50 refs

  18. Waste Isolation Safety Assessment Program. Technical progress report for FY-1978

    Energy Technology Data Exchange (ETDEWEB)

    Brandstetter, A.; Harwell, M.A.; Howes, B.W.; Benson, G.L.; Bradley, D.J.; Raymond, J.R.; Serne, R.J.; Schilling, A.H.

    1979-07-01

    Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE) is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Program (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of making those analyses. Progress on the following tasks is reported: release scenario analysis, waste form release rate analysis, release consequence analysis, sorption-desorption analysis, and societal acceptance analysis. (DC)

  19. Texas Experimental Tokamak: A plasma research facility. Technical progress report, November 1, 1993--October 31, 1994

    Energy Technology Data Exchange (ETDEWEB)

    Wootton, A.J.

    1994-07-01

    The purpose is to operate and maintain TEXT Upgrade as a complete facility for applied tokamak physics in order to elucidate the mechanisms of working gas, impurity, and thermal transport in tokamaks and in particular to understand the role of turbulence. So that they can continue to study the physics that is most relevant to the fusion program, TEXT completed a significant device upgrade this year. The new capabilities of the device and new and innovative diagnostics were exploited in all main program areas including: (1) configuration studies; (2) electron cyclotron heating physics; (3) improved confinement modes; (4) edge physics/impurity studies; (5) central turbulence and transport; and (6) transient transport. Details of the progress in each of the research areas are described.

  20. Texas Experimental Tokamak: A plasma research facility. Technical progress report, November 1, 1993--October 31, 1994

    International Nuclear Information System (INIS)

    Wootton, A.J.

    1994-07-01

    The purpose is to operate and maintain TEXT Upgrade as a complete facility for applied tokamak physics in order to elucidate the mechanisms of working gas, impurity, and thermal transport in tokamaks and in particular to understand the role of turbulence. So that they can continue to study the physics that is most relevant to the fusion program, TEXT completed a significant device upgrade this year. The new capabilities of the device and new and innovative diagnostics were exploited in all main program areas including: (1) configuration studies; (2) electron cyclotron heating physics; (3) improved confinement modes; (4) edge physics/impurity studies; (5) central turbulence and transport; and (6) transient transport. Details of the progress in each of the research areas are described

  1. New imaging systems in nuclear medicine. Technical progress report, October 1, 1976--May 31, 1977

    International Nuclear Information System (INIS)

    Brownell, G.L.

    1977-01-01

    Work carried out on the development of instrumentation and techniques for positron scintigraphy is discussed. Progress in positron imaging instrumentation and applications is detailed. The assembly and initial evaluation of the new multicrystal positron camera, PC-II, has been completed. Images have been obtained in both two and three-dimensions which demonstrate the basic physical properties of the instrument. Successful measurements using transverse section imaging have been carried out on animals and human volunteers. Physiological investigation using PC-II is proceeding. A flexible and accurate computer program has been developed for transverse section reconstruction of data acquired by PC-II. This program makes it possible to reconstruct both the activity distribution and the distribution of absorption. The program has been developed in such a way that it can handle variations in the data collection procedure. Clinical studies using PC-I and PC-II are being carried on in areas of heart, lung and brain

  2. [Geothermal system temperature-depth database and model for data analysis]. 5. quarterly technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    Blackwell, D.D.

    1998-04-25

    During this first quarter of the second year of the contract activity has involved several different tasks. The author has continued to work on three tasks most intensively during this quarter: the task of implementing the data base for geothermal system temperature-depth, the maintenance of the WWW site with the heat flow and gradient data base, and finally the development of a modeling capability for analysis of the geothermal system exploration data. The author has completed the task of developing a data base template for geothermal system temperature-depth data that can be used in conjunction with the regional data base that he had already developed and is now implementing it. Progress is described.

  3. Radioecology of natural systems in Colorado. Thirteenth technical progress report, May 1, 1974--April 30, 1975

    International Nuclear Information System (INIS)

    Whicker, F.W.

    1975-01-01

    Progress is reported on studies on the behavior of fallout radionuclides ( 137 Cs and 90 Sr) in selected organisms and natural ecosystems in Colorado. Components of alpine tundra, montane forests, shortgrass plains, and freshwater lakes and streams are currently under investigation. A study on the effect of gut passage on the mean diameter of monodisperse PuO 2 microspheres was initiated. Studies on plutonium in the terrestrial environs of Rocky Flats were initiated in the summer of 1972. Soil movement measurements were conducted to bear on the question of plutonium stability in contaminated areas. The relative importance of root uptake versus aerial deposition was evaluated in the field utilizing a sod block transplant procedure. The study on radiation effects on shortgrass plains vegetation was continued with emphasis on long-term changes in community structure under chronic irradiation stress and recovery patterns. (U.S.)

  4. Research in elementary particle physics. Technical progress report, June 1, 1985-May 31, 1986

    International Nuclear Information System (INIS)

    Kirsch, L.E.; Schnitzer, H.J.; Bensinger, J.R.; Abbott, L.F.; Blocker, C.A.

    1986-01-01

    Progress is reported in both experimental and theoretical elementary particle research. Experimental activities include: construction of the Forward Electromagnetic Shower Counters for the Collider Detector at Fermilab (CDF); a test run in the CDF, involving observation of a small number of proton-antiproton collisions; design of a self-contained single wire proportional chamber with pressure and temperature sensing for monitoring the gain of gases used by various components of the CDF; data acquisition, and calibration. Also included are a search for a dibaryon of strangeness=-1; hyperon weak radiative decay. Theoretical research is reported in the areas of quantum field theory, string theory, elementary particle phenomenology, cosmology, field theory in curved spacetimes, and cosmology. 34 refs

  5. Nuclear structure theory. Annual technical progress report, 1 July 1974--30 June 1975

    International Nuclear Information System (INIS)

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

    1975-01-01

    Progress during the past year is summarized for the following areas of nuclear structure and reaction theory: Meson interactions with nucleons and nuclei, including inelastic scattering of pions, three-body theories of scattering and absorption of pions by deuterons, and π-p bremsstrahlung. Theory of the effective interaction, including behavior of the expansion in orders of the reaction matrix. Statistical spectroscopy including fluctuations in energy levels and excitation strengths, and sum rules and strength distributions for various excitation processes, including single-nucleon transfer, β decay and multipole giant resonances. Studies of the inverse scattering problem. Studies of nuclear symmetries, of nuclear clustering, and of general nuclear structure by α-transfer reactions, and of nuclear shapes by (d, 3 He) reactions. (U.S.)

  6. Scientific and technical progress in high-energy astrophysics at INPE

    International Nuclear Information System (INIS)

    Bui-Van, N.A.; Jayanthi, U.B.; Jardim, J.O.D.; Braga, J.; Santo, C.M.E.

    1984-01-01

    The recent advances in high-energy Astrophysics pertains to the study of compact objects in galactic nuclei, binary systems and pulsars. These aspects are best understood by the study of the emissions in X- and gamma rays of these objects through the temporal variation in flux and spectrum. The Southern Hemisphere offers some of the unique objects for investigations such as galactic center, the Vela pulsar etc. For high temporal and spectra resolution studies two telescopes 'GeLi' and 'Pulsar' were designed and constructed. To support these scientific activities, a program in balloon launching and data acquisition facilities has been developed since 1971. The 'Balloon Launching Center' of INPE has capacity to launch balloons of -850,000 m 3 with payloads weighting about 1,000 Kg. Taking advantage of these facilities, project 'Bantar', with the goal to measure the atmospheric gamma-ray radiation in the Antartic Region, is under progress. (Author) [pt

  7. Crystalline Repository Project: Technical progress report for the period October 1, 1982--May 28, 1986

    International Nuclear Information System (INIS)

    1988-11-01

    This document reports the progress made on the development of a second geologic repository in crystalline rocks during the duration of the Crystalline Repository Project from its inception in October 1982 to its termination in May 1986. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Waste Technology Development (OWTD), successor to the Office of Crystalline Repository Development. OWTD is a prime contractor of the US Department of Energy (DOE) Repository Technology Program Office, itself the successor to the Crystalline Repository Project Office. The studies include work by other DOE prime contractors and by contractors to the Office of Crystalline Repository Development. 151 refs

  8. Savannah River Ecology Laboratory. Annual technical progress report of ecological research

    International Nuclear Information System (INIS)

    Smith, M.H.

    1996-01-01

    The Savannah River Ecology Laboratory (SREL) is a research unit of the University of Georgia (UGA). The overall mission of the Laboratory is to acquire and communicate knowledge of ecological processes and principles. SREL conducts basic and applied ecological research, as well as education and outreach programs, under a contract with the U.S. Department of Energy (DOE) at the Savannah River Site (SRS) near Aiken, South Carolina. Significant accomplishments were made during the past year in the areas of research, education and service. The Laboratory's research mission was fulfilled with the publication of two books and 143 journal articles and book chapters by faculty, technical and students, and visiting scientists. An additional three books and about 80 journal articles currently are in press. Faculty, technician and students presented 193 lectures, scientific presentations, and posters to colleges and universities, including minority institutions. Dr. J Vaun McArthur organized and conducted the Third Annual SREL Symposium on the Environment: New Concepts in Strewn Ecology: An Integrative Approach. Dr. Michael Newman conducted a 5-day course titled Quantitative Methods in Ecotoxicology, and Dr. Brian Teppen of The Advanced Analytical Center for Environmental Sciences (AACES) taught a 3-day short course titled Introduction to Molecular Modeling of Environmental Systems. Dr. I. Lehr Brisbin co-hosted a meeting of the Crocodile Special Interest Group. Dr. Rebecca Sharitz attended four symposia in Japan during May and June 1996 and conducted meetings of the Executive Committee and Board of the International Association for Ecology (ENTECOL)

  9. Savannah River Ecology Laboratory. Annual technical progress report of ecological research

    Energy Technology Data Exchange (ETDEWEB)

    Smith, M.H.

    1996-07-31

    The Savannah River Ecology Laboratory (SREL) is a research unit of the University of Georgia (UGA). The overall mission of the Laboratory is to acquire and communicate knowledge of ecological processes and principles. SREL conducts basic and applied ecological research, as well as education and outreach programs, under a contract with the U.S. Department of Energy (DOE) at the Savannah River Site (SRS) near Aiken, South Carolina. Significant accomplishments were made during the past year in the areas of research, education and service. The Laboratory`s research mission was fulfilled with the publication of two books and 143 journal articles and book chapters by faculty, technical and students, and visiting scientists. An additional three books and about 80 journal articles currently are in press. Faculty, technician and students presented 193 lectures, scientific presentations, and posters to colleges and universities, including minority institutions. Dr. J Vaun McArthur organized and conducted the Third Annual SREL Symposium on the Environment: New Concepts in Strewn Ecology: An Integrative Approach. Dr. Michael Newman conducted a 5-day course titled Quantitative Methods in Ecotoxicology, and Dr. Brian Teppen of The Advanced Analytical Center for Environmental Sciences (AACES) taught a 3-day short course titled Introduction to Molecular Modeling of Environmental Systems. Dr. I. Lehr Brisbin co-hosted a meeting of the Crocodile Special Interest Group. Dr. Rebecca Sharitz attended four symposia in Japan during May and June 1996 and conducted meetings of the Executive Committee and Board of the International Association for Ecology (ENTECOL).

  10. Dual curvature acoustically damped concentrating collector. Semiannual technical progress report, June 1-December 1, 1978

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-12-01

    The project's first objective is to establish, analytically, the cost and performance of design choices within the boundaries of the basic proposed concept. With these cost and performance measures as a guide, the second project objective is to design a cost-effective Dual Curvature collector module and collector field array. The third objective is to establish technical and economic concept feasibility through prototype fabrication and test. The final objective is to define the Dual Curvature collector commercialization requirements. The Dual Curvature collector uses a unique reflector module consisting of a reflective film that is tensioned on a reflector support frame. The tensioned membrane (film) surface approximates a hyperbolic paraboloid that is capable of linear focusing when the surface tracks the sun's apparent motion in one axis. The reflective film can be backed by polystyrene foam with an air space between the film and the foam surfaces. This provides damping of the reflector surface to minimize the effect of wind gusts and physical impacts. The baseline collector is intended to operate at a concentration of ten (10) or greater with a nominal absorber temperature of 150/sup 0/C (300/sup 0/F). The Component Research and Analysis tasks which lead to the selection of a baseline collector configuration are discussed. Also, some preliminary results of the Collector Module Design task are presented.

  11. Signal validation for nuclear power plants: Progress report No. 8, January--March 1989

    International Nuclear Information System (INIS)

    Upadhyaya, B.R.; Kerlin, T.W.

    1989-01-01

    This report is a summary of the progress in the US Department of Energy sponsored project on Signal Validation for Nuclear Power Plants, for the period January--March, 1989. This is the last phase of the project with September 29, 1989 as the official ending date. A preliminary draft of a two-volume final report is scheduled for release in mid-September

  12. 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.

  13. Application of Microprocessor-Based Equipment in Nuclear Power Plants - Technical Basis for a Qualification Methodology

    International Nuclear Information System (INIS)

    Korsah, K.

    2001-01-01

    This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instrumentation and Control (I and C) Systems'' program initiated by the Nuclear Regulatory Commission (NRC); (2) documents a comparative analysis of U.S. and European qualification standards; and (3) provides recommendations for enhancing regulatory guidance for environmental qualification of microprocessor-based safety-related systems. Safety-related I and C system upgrades of present-day nuclear power plants, as well as I and C systems of Advanced Light-Water Reactors (ALWRs), are expected to make increasing use of microprocessor-based technology. The Nuclear Regulatory Commission (NRC) recognized that the use of such technology may pose environmental qualification challenges different from current, analog-based I and C systems. Hence, it initiated the ''Qualification of Advanced Instrumentation and Control Systems'' program. The objectives of this confirmatory research project are to (1) identify any unique environmental-stress-related failure modes posed by digital technologies and their potential impact on the safety systems and (2) develop the technical basis for regulatory guidance using these findings. Previous findings from this study have been documented in several technical reports. This final report in the series documents a comparative analysis of two environmental qualification standards--Institute of Electrical and Electronics Engineers (IEEE) Std 323-1983 and International Electrotechnical Commission (IEC) 60780 (1998)--and provides recommendations for environmental qualification of microprocessor-based systems based on this analysis as well as on the findings documented in the previous reports. The two standards were chosen for this analysis because IEEE 323 is the standard used in the U.S. for the qualification of safety-related equipment in nuclear power plants, and IEC 60780 is its European counterpart. In addition, the IEC document was published in

  14. Solvent refined coal (SRC) process. Annual technical progress report, January 1979-December 1979

    Energy Technology Data Exchange (ETDEWEB)

    1980-11-01

    This report discusses the effects on SRC yields of seven process variables (reactor temperature, SRT, hydrogen partial pressure, recycle ash and coal concentrations, gas velocity and coal type) predicted by second-order regression models developed from a data base containing pilot plant data with both Kentucky and Powhatan coals. The only effect of coal type in the model is a shift in each yield by a constant factor. Although some differences were found between the models developed from the Kentucky data base (1) (which we call Kentucky models) and the pooled coal models, the general conclusions of the previous report are confirmed by the new models and the assumption of similar behavior of the two coals appears to be justified. In some respects the dependence of the yields (MAF coal basis) on variables such as pressure and temperature are clearer than in the previous models. The principal trends which emerge are discussed.

  15. Optimal design and routing of power lines; ecological, technical and economic perspectives (OPTIPOL). Progress report 2009

    Energy Technology Data Exchange (ETDEWEB)

    Bevanger, K.; Bartzke, G.; Broeseth, H.; Gjershaug, J.O.; Hanssen, F.; Jacobsen, K.-O.; Kvaloey, P.; May, R.; Nygaard, T.; Pedersen, H.C.; Reitan, O.; Refsnaes, S.; Stokke, S.; Vang, R.

    2009-12-15

    From 2009 inclusive, NINA has received economic support for research on power lines and wildlife from the Norwegian Research Council (NFR) through the RENERGI Programme. The project is named 'Optimal design and routing of power lines; ecological, technical and economic perspectives' (OPTIPOL). It is scheduled for 5 years (2009-1013) and is part of the activities within CEDREN, i.e. the Centre for environmental design of renewable energy (cf. http://www.cedren.no). With a grid close to 200 000 km overhead power-lines, the associated rights-of-way (ROW) affect huge land areas in Norway. The overall goal is to develop predict-ing tools for optimal routing of power lines from an environmental perspective and assess technical and economic solutions to minimize conflicts with wildlife and habitat conservation. Thus, the OPTIPOL rationale is based on the belief that the negative effects of electricity transmission and distribution can be reduced with respect to birds and mammals. OPTIPOL has several ambitious objectives, and is divided into sub-projects and specific tasks. From the first of November a PhD-student became part of the project, a position that will be held for 4 years. The main objective of the PhD-activities will be to assess how and why different wildlife species use deforested areas below power lines, evaluate possible positive and negative effects of power-line ROWs, and assess the possibilities for quality improvement. Another part of the project is dedicated the effects of linear structures on movement patterns and distribution in the landscape in native deer species. Here we will examine how different spatial scales influence the processes that guide movement patterns, and responses to linear structures. Another focus will be small game species, with mountain hare, capercaillie, black grouse and hazel grouse as model species. The main objective will be to assess the impact of transforming ROW habitats into attractive small-game foraging

  16. 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

  17. Exploratory research on solvent refined coal liquefaction. Annual technical progress report, January 1-December 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-09-01

    This report summarizes the progress of the Exploratory Research on Solvent Refined Coal Liquefaction project by The Pittsburg and Midway Coal Mining Co.'s Merriam Laboratory during 1979. In a series of experiments with varying feed gas composition, low levels (5 to 10 mole %) of carbon monoxide had little effect on the SRC II processing of Pittsburgh Seam coal (Powhatan No. 5 Mine) while higher levels (20 to 40 mole %) resulted in a general degradation of operability and reduced oil yields. Addition of finely divided (approx. 1 ..mu..m) pyrite to the reactive Powhatan coal had little effect on oil yields although the molecular weight of the distillation residue was apparently decreased. When finely divided pyrite and magnetite were added to the less reactive coals from the Loveridge and Blacksville No. 1 Mines (also Pittsburgh Seam), however, substantial increases in oil yields and product quality were obtained. In a comparison of upflow and downflow dissolver configurations with Powhatan coal in the SRC II mode, there was no difference in yields or product quality. A study characterizing specific reactors revealed a significantly higher conversion in the SRC I mode with a reactor approximating plug flow conditions compared to a completely backmixed reactor. In the SRC II mode there was only a slightly higher oil yield with the plug flow reactor.

  18. Supramolecular structures for photochemical energy conversion. Technical progress report, 1993--1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    This research project is concerned with the design, synthesis and study by photochemical and spectroscopic methods of complex molecular devices that mimic some important aspects of photosynthetic electron and energy transfer. Properly engineered molecules of this type can functionally mimic photosynthetic light harvesting (singlet-singlet energy transfer between chromophores), photoprotection from light-initiated singlet oxygen damage (triplet-triplet energy transfer from chlorophylls to carotenoid polyenes), and, most importantly, photoinduced multistep electron transfer to generate charge-separated states that preserve some of the photon energy as chemical potential. During the last three years, progress has been made on several fronts, all of which are related to the overall goal. A biomimetic system based on carotenoid-porphyrin-quinone triads has been constructed that demonstrates photoinduced transmembrane charge separation which in turn drives transmembrane proton transfer. Another investigation has focused on the use of proton transfer reactions to stabilize the initial products of photoinduced electron transfer and thereby increase the yield of long-lived charge separation. A third study has investigated the influence of rigid molecular geometries and short donor-acceptor separations on photoinduced electron transfer reactions. Finally, generation and quenching of singlet molecular oxygen by chlorophyll aggregates has been studied. All four studies are described and results are discussed.

  19. Ion rings for magnetic fusion. Technical progress report, August 1, 1993--June 1, 1994

    International Nuclear Information System (INIS)

    Sudan, R.N.

    1994-01-01

    In Our Proposal ''Ion Rings for Magnetic Fusion'' of January 6, 1993, Stage I of our Proposed Program plan (the 12 months) consisted of the following tasks: Experiments on the existing ion ring experimental system IREX to test a new magnetically-controlled anode plasma source (MAP) for the ion beam diode injector; numerical simulations of ion ring formation to optimize design parameters for the field reversed ion ring experiment (FIREX) to be built and operated in Stage II; and designing the power supply for the FIREX injector and the magnetic field system using results for A and B. During the past 7 1/2 months our work has progressed according to the above plan. In addition to testing the MAP diode on IREX we have tested the EMFAPS (evaporating metal film anode plasma source) anode on the Sandia National Laboratories funded LION pulsed power generator. As a result of these experiments, described this paper, we have arrived at the conclusion that EMFAPS anode for the ion at present because the MAP diode beam diode injector is our preferred choice for is still in an early stage of development

  20. Nuclear structure theory. Technical progress report, September 1, 1984-August 31, 1985

    International Nuclear Information System (INIS)

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

    1985-01-01

    This report summarizes progress in the following areas of research: Spectral Averaging, including the theory of level densities and partition functions for interacting nucleons, spectral distributions for fixed symmetries, general studies of distributions (in particular of strength distributions) considered as multivariate processes, and applications to the secular behavior of fluctuation measures; spectral and strength fluctuations, including study of the transitions between different fluctuation patterns (i.e., between different types of quantum chaos) as a conserved symmetry is gradually broken, application of these results to determining values of, or upper bounds for, the goodness of symmetries in complex nuclei, reduction of values or bounds to statements about the nuclear Hamiltonian, in particular for time-reversal symmetry, and specific studies of quantum chaos; statistical theory of pion absorption, including analysis of the (π,p) inclusive reaction; and quark theory of nuclear matter, involving development of models which show two limiting behaviors - that of a Fermi gas of nucleons (quark clusters) at low density and of a Fermi gas of quarks at high density. Both variational and exact solutions of one model have been found. 9 refs

  1. University of Colorado at Boulder Nuclear Physics Laboratory technical progress report

    International Nuclear Information System (INIS)

    Peterson, R.J.

    1991-01-01

    This report summarizes experimental work carried out between October 1, 1990, the closing of our Progress Report, and August 14, 1991 at the Nuclear Physics Laboratory of the University of Colorado, Boulder, under contract DE-FG02-ER40269 with the United States Department of Energy. This contract supports broadly based experimental work in intermediate energy nuclear physics. The program includes pion-nucleon studies at TRIUMF and LAMPF, inelastic pion scattering and charge exchange reactions at LAMPF, and nucleon charge exchange at LAMPF/NTOF. The first results of spin-transfer observables in the isovector (rvec p,rvec n) reaction are included in this report. Our data confirm the tentative result from (rvec p,rvec p') reactions that the nuclear isovector spin response shows neither longitudinal enhancement nor transverse queching. Our program in quasifree scattering of high energy pions shows solid evidence of isoscalar enhancement of the nuclear nonspin response. We include several comparisons of the quasifree scattering of different probes. Results from our efforts in the design of accelerator RF cavities are also included in this report

  2. Proton resonance spectroscopy. Quarterly technical progress report, December 1992--November 1995

    International Nuclear Information System (INIS)

    Shriner, J.F. Jr.

    1995-11-01

    Work on chaos in the low-lying levels of nuclei has continued on several fronts. The major effort has been study of the 29 Si(p,γ) reaction with the goal of establishing a complete level scheme for 30 P and analyzing the eigenvalue fluctuations for evidence of chaos. These measurements are in progress, and the current status is described. A related topic is the search for different signatures of chaos which do not require the extremely high degree of completeness and purity necessary for eigenvalue analyses; those efforts are discussed in Sections 2 and 3. The possibility of studying both parity violation and time-reversal invariance violation with charged particle resonances has been explored by performing calculations using experimentally measured resonance parameters. Large enhancements are indeed available; the results are discussed in Sections 4 and 5. Preparations for an experimental study of parity violation using these techniques are ongoing. An undergraduate project searching for experimental evidence of a parity dependence of level density is discussed in Section 6. A number of improvements to the operation of the TUNL KN accelerator have been implemented in the past three years. These are described in Section 7

  3. Proton resonance spectroscopy. Quarterly technical progress report, December 1992--November 1995

    Energy Technology Data Exchange (ETDEWEB)

    Shriner, J.F. Jr.

    1995-11-01

    Work on chaos in the low-lying levels of nuclei has continued on several fronts. The major effort has been study of the {sup 29}Si(p,{gamma}) reaction with the goal of establishing a complete level scheme for {sup 30}P and analyzing the eigenvalue fluctuations for evidence of chaos. These measurements are in progress, and the current status is described. A related topic is the search for different signatures of chaos which do not require the extremely high degree of completeness and purity necessary for eigenvalue analyses; those efforts are discussed in Sections 2 and 3. The possibility of studying both parity violation and time-reversal invariance violation with charged particle resonances has been explored by performing calculations using experimentally measured resonance parameters. Large enhancements are indeed available; the results are discussed in Sections 4 and 5. Preparations for an experimental study of parity violation using these techniques are ongoing. An undergraduate project searching for experimental evidence of a parity dependence of level density is discussed in Section 6. A number of improvements to the operation of the TUNL KN accelerator have been implemented in the past three years. These are described in Section 7.

  4. Technical progress report for UTSI/CFFF MHD program completion and related activity

    International Nuclear Information System (INIS)

    Chapman, James N.; Muehlhauser, Joel W.

    1998-01-01

    Routine preventive maintenance of the DOE Coal Fired Flow Facility (CFFF) is being performed. Modernization programs, funded under subcontract from Foster Wheeler Development Corporation by the DOE HIPPS Program, have been completed on the coal processing system, the data acquisition and control system and the control room. Late in the quarter, all work was stopped on maintenance of the CFFF at DOE instruction. Environmental restoration actions continued with monitoring of groundwater wells and holding pond effluent. Progress is reported on the approved groundwater remediation plan. Actions are underway to dispose of spent seed/ash mixtures and excess coal remaining from the MHD POC program. The status of five (5) High Temperature Superconductor (HTS) projects is reported. A summary is included of the results attained with sol-gel experiments with buffer layers and YBCO. The status of the cost/performance study of electron beam and PLD deposition is pre-sented. A summary of work performed in diagnostics for real time control of HTS processes is presented

  5. TECHNICAL PROGRESS REPORT FOR UTSI/CFFF MHD PROGRAM COMPLETION AND RELATED ACTIVITIES

    Energy Technology Data Exchange (ETDEWEB)

    DR. JAMES N. CHAPMAN; DR. JOEL W. MUEHLHAUSER

    1998-10-23

    Routine preventive maintenance of the DOE Coal Fired Flow Facility (CFFF) is being performed. Modernization programs, funded under subcontract from Foster Wheeler Development Corporation by the DOE HIPPS Program, have been completed on the coal processing system, the data acquisition and control system and the control room. Late in the quarter, all work was stopped on maintenance of the CFFF at DOE instruction. Environmental restoration actions continued with monitoring of groundwater wells and holding pond effluent. Progress is reported on the approved groundwater remediation plan. Actions are underway to dispose of spent seed/ash mixtures and excess coal remaining from the MHD POC program. The status of five (5) High Temperature Superconductor (HTS) projects is reported. A summary is included of the results attained with sol-gel experiments with buffer layers and YBCO. The status of the cost/performance study of electron beam and PLD deposition is pre-sented. A summary of work performed in diagnostics for real time control of HTS processes is presented.

  6. Nuclear structure theory: Technical progress report for period September 1, 1986-August 31, 1987

    International Nuclear Information System (INIS)

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

    1987-08-01

    This report summarizes progress in the following areas of research: (1) quark theory of nuclear matter, including further development of models in one-dimension with analytic solutions, numerical studies, bound properties, inclusion of spin and isospin degrees of freedom, excitation properties and response function; electron scattering, including application of sum rules to deeply inelastic scattering, and of quark models of nuclei; charge exchange in pion-nucleus reactions, including models of isotensor optical potential, optical theorem for double charge exchange, and coupled-channel calculations of single charge exchange; a unified theory of reaction dynamics and nuclear structure for intermediate energies, including diagrammatic formulation and development of appropriate computer programs; weak interactions: a study of the neutrino mass-matrix; bounds for time reversal noninvariance in the nucleon-nucleon interaction, obtained from spectral and strength fluctuations in complex nuclei, and separately from detailed balance in compound nuclear reactions. The relative sensitivities of the two methods are discussed; fluctuation measures for the two-dimensional harmonic oscillator; random matrices and symmetry-breaking in atomic spectra data; saturation effects for spectral measures in many-particle systems; and finally fluctuation-free statistical spectroscopy, applied to state densities and partition functions, including accurate absolute calculations of nuclear level spacings

  7. 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

  8. 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.

  9. 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

  10. Technical comparison between Integrated Gasification Combined Cycle (IGCC) and Natural Gas Combined Cycle (NGCC) power plants

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz, Pablo Andres Silva; Venturini, Osvaldo Jose; Lora, Electo Eduardo Silva [Federal University of Itajuba - UNIFEI, MG (Brazil). Excellence Group in Thermal Power and Distributed Generation - NEST], e-mails: osvaldo@unifei.edu.br, electo@unifei.edu.br

    2010-07-01

    Among the emerging clean coal technologies for power generation, Integrated Gasification Combined Cycle (IGCC) and Natural Gas Combined Cycle (NGCC) systems are receiving considerable attention as a potentially attractive option to reduce the emissions of greenhouse gases (GHG). The main reason is because these systems has high efficiency and low emissions in comparison with traditional power generation plants. Currently in IGCC and NGCC systems at demonstration stage is been considered to implement CCS technology. CO{sub 2} emissions can be avoided in a gasification-based power plant because by transferring almost all carbon compounds to CO{sub 2} through the water gas shift (WGS) reaction, then removing the CO{sub 2} before it is diluted in the combustion stage. The aim of this study is to compare the technical performance of an IGCC system that uses Brazilian coal and petroleum coke as fuel with a NGCC system, with the same fixed output power of 450 MW. The first section of this paper presents the plant configurations of IGCC systems. The following section presents an analysis of NGCC technology. (author)

  11. PSA-based optimization of technical specifications for the Borssele nuclear power plant

    International Nuclear Information System (INIS)

    Seebregts, A.J.; Schoonakker, H.A.

    1996-01-01

    The Borssele Nuclear Power Plant (NPP) is a Siemens/KWU 472 MWe Pressurized Water Reactor which has been in operation since 1973. In 1989, a Probabilistic Safety Assessment (PSA) program was initiated to complement deterministic safety studies and operational experience in forming a plant safety concept. In 1993, the PSA-MER model was completed and used to determine the effects a package of proposed modifications would have on plant safety and risks to the environment. This model was used to start retrospective risks profile and allowed outage times (AOTs) analyses, which both concerned the calculation of the change in total core damage frequency (TCDF) given a change in configuration. The main problems identified and reported in this paper are: (i) How to calculate the change in TCDF (ΔTCDF)? (section 3); and (ii) How to set practical decision criteria and how to use the PSA as extension to Technical Specifications (TS) AOTs? (section 4). Finally, a pilot study was conducted in order to optimize surveillance test intervals (STIs) which are also part of the TS (section 5). (orig.)

  12. ENSI's technical view on the periodic safety review 2008 of the nuclear power plant Goesgen

    International Nuclear Information System (INIS)

    2012-08-01

    The owner of a license for a nuclear power plant operation in Switzerland has to undergo every 10 years a comprehensive safety check called 'periodic safety review' (PSR). The regulatory authority, the Swiss Federal Nuclear Safety Inspectorate (ENSI), reviews the documents supplied by the licensee. The Goesgen power plant (KKG) obtained its operation license and started operation in 1978. A first PSR was performed in the years 1996 to 1998 (PSR 1998) and reported. KKG delivered an analysis of the safety status, an evaluation of subsystems as well as test reports. The new PSR covers the period 1998 to 2007. The basis of the evaluation by ENSI is the new nuclear energy law in force since 1 February 2005. In comparison to PSR 1998, new aspects have to be considered like the description of the safety concept, including the technical safety classification of buildings, systems and components, or consideration of the protection objective 'limitation of the radiation exposure'. The PSR 2008 is focussed on the estimate of the nuclear safety of KKG. Basically, for the operation of a nuclear power plant, a sufficient protection has to be guaranteed against the release of radioactive materials to the environment as well as the irradiation of persons, during normal operation as well as in the case of accidents. The licensee of a nuclear power plant in operation must retrofit his plant according to the experience already gained and the state-of-the-art. The purpose of the PSR is to check the quality of the plant in the domain of safety. A probabilistic safety assessment (PSA) study must prove that the probability of damages to the reactor core is smaller than 10 -5 /year. In Switzerland the life time of a nuclear power plant is not limited by a fixed maximum time of operation. On the contrary, the limitation proceeds from safety criteria. Insufficiencies in the plant design are often recognized only through the evolution of the technique or some unexpected events. Ageing

  13. Improving human reliability through better nuclear power plant system design. Progress report

    International Nuclear Information System (INIS)

    Golay, M.W.

    1995-01-01

    The project on open-quotes Development of a Theory of the Dependence of Human Reliability upon System Designs as a Means of Improving Nuclear Power Plant Performanceclose quotes has been undertaken in order to address the important problem of human error in advanced nuclear power plant designs. Most of the creativity in formulating such concepts has focused upon improving the mechanical reliability of safety related plant systems. However, the lack of a mature theory has retarded similar progress in reducing the likely frequencies of human errors. The main design mechanism used to address this class of concerns has been to reduce or eliminate the human role in plant operations and accident response. The plan of work being pursued in this project is to perform a set of experiments involving human subject who are required to operate, diagnose and respond to changes in computer-simulated systems, relevant to those encountered in nuclear power plants. In the tests the systems are made to differ in complexity in a systematic manner. The computer program used to present the problems to be solved also records the response of the operator as it unfolds. Ultimately this computer is also to be used in compiling the results of the project. The work of this project is focused upon nuclear power plant applications. However, the persuasiveness of human errors in using all sorts of electromechanical machines gives it a much greater potential importance. Because of this we are attempting to pursue our work in a fashion permitting broad generalizations

  14. Advanced thermally stable jet fuels: Technical progress report, October 1994--December 1994

    Energy Technology Data Exchange (ETDEWEB)

    Schobert, H.H.; Eser, S.; Song, C.; Hatcher, P.G.; Boehman, A.; Coleman, M.M.

    1995-02-01

    There are five tasks within this project on thermally stable coal-based jet fuels. Progress on each of the tasks is described. Task 1, Investigation of the quantitative degradation chemistry of fuels, has 5 subtasks which are described: Literature review on thermal stability of jet fuels; Pyrolytic and catalytic reactions of potential endothermic fuels: cis- and trans-decalin; Use of site specific {sup 13}C-labeling to examine the thermal stressing of 1-phenylhexane: A case study for the determination of reaction kinetics in complex fuel mixtures versus model compound studies; Estimation of critical temperatures of jet fuels; and Surface effects on deposit formation in a flow reactor system. Under Task 2, Investigation of incipient deposition, the subtask reported is Uncertainty analysis on growth and deposition of particles during heating of coal-derived aviation gas turbine fuels; under Task 3, Characterization of solid gums, sediments, and carbonaceous deposits, is subtask, Studies of surface chemistry of PX-21 activated carbon during thermal degradation of jet A-1 fuel and n-dodecane; under Task 4, Coal-based fuel stabilization studies, is subtask, Exploratory screening and development potential of jet fuel thermal stabilizers over 400 C; and under Task 5, Exploratory studies on the direct conversion of coal to high quality jet fuels, are 4 subtasks: Novel approaches to low-severity coal liquefaction and coal/resid co-processing using water and dispersed catalysts; Shape-selective naphthalene hydrogenation for production of thermally stable jet fuels; Design of a batch mode and a continuous mode three-phase reactor system for the liquefaction of coal and upgrading of coal liquids; and Exploratory studies on coal liquids upgrading using mesopores molecular sieve catalysts. 136 refs., 69 figs., 24 tabs.

  15. Directional backlight liquid crystal autostereoscopic display: technical challenges, research progress, and prospect (Conference Presentation)

    Science.gov (United States)

    Fan, Hang; Li, Kunyang; Zhou, Yangui; Liang, Haowen; Wang, Jiahui; Zhou, Jianying

    2016-09-01

    Recent upsurge on virtual and augmented realities (VR and AR) has re-ignited the interest to the immerse display technology. The VR/AR technology based on stereoscopic display is believed in its early stage as glasses-free, or autostereoscopic display, will be ultimately adopted for the viewing convenience, visual comfort and for the multi-viewer purposes. On the other hand, autostereoscopic display has not yet received positive market response for the past years neither with stereoscopic displays using shutter or polarized glasses. We shall present the analysis on the real-world applications, rigid user demand, the drawbacks to the existing barrier- and lenticular lens-based LCD autostereoscopy. We shall emphasize the emerging autostereoscopic display, and notably on directional backlight LCD technology using a hybrid spatial- and temporal-control scenario. We report the numerical simulation of a display system using Monte-Carlo ray-tracing method with the human retina as the real image receiver. The system performance is optimized using newly developed figure of merit for system design. The reduced crosstalk in an autostereoscopic system, the enhanced display quality, including the high resolution received by the retina, the display homogeneity without Moiré- and defect-pattern, will be highlighted. Recent research progress including a novel scheme for diffraction-free backlight illumination, the expanded viewing zone for autostereoscopic display, and the novel Fresnel lens array to achieve a near perfect display in 2D/3D mode will be introduced. The experimental demonstration will be presented to the autostereoscopic display with the highest resolution, low crosstalk, Moiré- and defect- pattern free.

  16. Theory of high-energy-collision processes. Technical progress report, January 1-December 31, 1981

    International Nuclear Information System (INIS)

    1982-01-01

    Progress is described in the following areas: (1) several years ago, surprisingly simple expressions were obtained for the differential cross sections of e + e - → μ + μ - γ and e + e - → e + e - γ at high energies. Such simple expressions were generalized to twelve other similar radiative processes in QED and QCD. Afterwards, it was found that these results can be derived easily with the help of helicity amplitudes. This method is being investigated for many other radiative processes; (2) in the two-dimensional Ising model, the horizontal and vertical interaction energies are usually taken to be different. When this idea of different interactions in different directions is applied to the Z 2 lattice gauge theory in four dimensions, a limiting case is found which is exactly solvable. Contrary to numerical calculations at the symmetry point, the phase transition is found to be of second order; (3) on the subject of supersymmetry, general helicity and spin sum rules were obtained for massless and massive supermultiplets, and a functional integral approach was found as a natural setting for Witten's criterion for the occurrence of dynamic symmetry breaking of supersymmetry. A systematic and exhaustive analysis of explicit soft breaking of global supersymmetry has also been carried out using the methods of superfields; (4) the renormalization of the massless Thirring model in the neighborhood of g = -π/2 was studied. The results are consistent with those found previously by placing the model on a lattice; and (5) in studying the effect of laboratory temperature on scattering processes, it was found that transport phenomena play an important role. As a preparation for this study, an exactly solvable case of the nonlinear Boltzmann equation has been found and studied

  17. Nuclear Physics Laboratory, University of Colorado technical progress report, 1976 and proposal for continuation of contract

    International Nuclear Information System (INIS)

    1976-01-01

    This report summarizes the work carried out at the Nuclear Physics Laboratory of the University of Colorado during the period November 1, 1975 to November 1, 1976. The low energy nuclear physics section is dominated by light-ion reaction studies which span a wide range. These include both two-neutron and two-proton transfer reactions, charge exchange and inelastic scattering, as well as single nucleon transfer reactions. The nuclei studied vary widely in their mass and characteristics. These reaction studies have been aided by the multi-use scattering chamber which now allows the energy-loss-spectrometer beam preparation system (beam swinger) to shift from charged particle studies to neutron time-of-flight studies with a minimum loss of time. The intermediate energy section reflects the increase in activity accompanying the arrival of LAMPF data and the initiation of (p,d) studies at the Indiana separated-sector cyclotron. The nucleon removal results provided by the π beam at EPICS previous to completion of the spectrometer have shown that nuclear effects dominate this process, so that the widely used free interaction picture is inadequate. The section entitled ''Other Activities'' reveals continuing activities in new applications of nuclear techniques to problems in medicine and biology. Reactions important to astrophysics continue to be investigated and our trace-element program remains at a high level of activity. The theoretical section reports new progress in understanding magnitudes of two-step reactions by inclusion of finite-range effects. A new finite-range program which is fast and economical has been completed. Intermediate energy results include calculations of π-γ angular correlations, low energy π-nucleus interactions, as well as (p,d) and nucleon scattering calculations for intermediate energies

  18. Improved methods for water shutoff. Final technical progress report, October 1, 1997--September 30, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Seright, R.S.; Liang, J.T.; Schrader, R.; Hagstrom, J. II; Liu, J.; Wavrik, K.

    1998-10-01

    In the United States, more than 20 billion barrels of salt water are produced each year during oilfield operations. A tremendous economic incentive exists to reduce water production if that can be accomplished without significantly sacrificing hydrocarbon production. This three-year research project had three objectives. The first objective was to identify chemical blocking agents that will (a) during placement, flow readily through fractures without penetrating significantly into porous rock and with screening out or developing excessive pressure gradients and (b) at a predictable and controllable time, become immobile and resistant breakdown upon exposure to moderate to high pressure gradients. The second objective was to identify schemes that optimize placement of the above blocking agents. The third objective was to explain why gels and other chemical blocking agents reduce permeability to one phase (e.g., water) more than that to another phase (e.g., oil or gas). The authors also wanted to identify conditions that maximize this phenomenon. This project consisted of three tasks, each of which addressed one of the above objectives. This report describes work performed during the third and final period of the project. During this three-year project, they: (1) Developed a procedure and software for sizing gelant treatments in hydraulically fractured production wells; (2) Developed a method (based on interwell tracer results) to determine the potential for applying gel treatments in naturally fractured reservoirs; (3) Characterized gel properties during extrusion through fractures; (4) Developed a method to predict gel placement in naturally fractured reservoirs; (5) Made progress in elucidating the mechanism for why some gels can reduce permeability to water more than that to oil; (6) Demonstrated the limitations of using water/oil ratio diagnostic plots to distinguish between channeling and coning; and (7) Proposed a philosophy for diagnosing and attacking water

  19. 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)

  20. Biomass power for rural development: Phase 2. Technical progress report, April 1--June 30, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Neuhauser, E.

    1998-11-01

    The project undertaken by the Salix Consortium is a multi-phased, multi-partner endeavor. Phase-1 focused on initial development and testing of the technology and agreements necessary to demonstrate commercial willow production in Phase-2. The Phase-1 objectives have been successfully completed: preparing final design plans for two utility pulverized coal boilers, developing fuel supply plans for the project, obtaining power production commitments from the power companies for Phase-2, obtaining construction and environmental permits, and developing an experimental strategy for crop production and power generation improvements needed to assure commercial success. The R and D effort also addresses environmental issues pertaining to introduction of the willow energy system. Beyond those Phase-1 requirements the Consortium has already successfully demonstrated cofiring at Greenidge Station and developed the required nursery capacity for acreage scale-up. This past summer 105 acres were prepared in advance for the spring planting in 1998. Having completed the above tasks, the Consortium is well positioned to begin Phase-2. In phase-2 every aspect of willow production and power generation from willow will be demonstrated. The ultimate objective of Phase-2 is to transition the work performed under the Rural Energy for the Future project into a thriving, self-supported energy crop enterprise.

  1. Nondestructive Examination (NDE) Detection and Characterization of Degradation Precursors, Technical Progress Report for FY 2012

    Energy Technology Data Exchange (ETDEWEB)

    Ramuhalli, P.; Meyer, R.M.; Fricke, J.M.; Prowant, M.S.; Coble, J.B.; Griffin, J.W.; Pitman, S.G.; Dahl, M.E.; Kafentzis, T.A.; Roosendaal, T.J.

    2012-09-01

    The overall objective of this project was to investigate the effectiveness of nondestructive examination (NDE) technology in detecting material degradation precursors by initiating and growing cracks in selected materials and using NDE methods to measure crack precursors prior to the onset of cracking. Nuclear reactor components are subject to stresses over time that are not precisely known and that make the life expectancy of components difficult to determine. To prevent future issues with the operation of these plants because of unforeseen failure of components, NDE technology is needed that can be used to identify and quantify precursors to macroscopic degradation of materials. Some of the NDE methods being researched as possible solutions to the precursor detection problem are magnetic Barkhausen noise, nonlinear ultrasonics, acoustic emission, eddy current measurements, and guided wave technology. In FY12, the objective was to complete preliminary assessment of advanced NDE techniques for sensitivity to degradation precursors, using prototypical degradation mechanisms in laboratory-scale measurements. This present document reports on the deliverable that meets the following milestone: M3LW-12OR0402143 – Report detailing an initial demonstration on samples from the crack-initiation tests will be provided (demonstrating acceleration of the work).

  2. Structural Aging Program technical progress for period, January 1, 1992--December 31, 1992

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.

    1993-07-01

    The Structural Aging (SAG) Program is conducted for the Nuclear Regulatory Commission (NRC) by the Oak Ridge National Laboratory (ORNL). The program has the overall objective of preparing an expandable handbook or report which will provide potential structural safety issues and acceptance criteria for use by the NRC in nuclear power plant evaluations of continued service. Initial focus of the program is on concrete and concrete-related materials which comprise safety-related (Category I) structures in light-water reactor facilities. The SAG Program is organized into four tasks: Task S.1 -- Program Management, Task S.2 -- Materials Property Data Base, Task S.3 -- Structural Component Assessment/Repair Technology, and Task S.4 -- Quantitative Methodology for Continued Service Determinations. In meeting the individual objectives of these tasks resources are drawn from ORNL with subcontract support from universities and other research laboratories. This report provides an overview of principal developments in each of the four program tasks from January 1, 1992 to December 31, 1992. Planned activities under each of these tasks are also presented

  3. MHD Integrated Topping Cycle Project. Thirteenth quarterly technical progress report, August 1, 1990--October 31, 1990

    Energy Technology Data Exchange (ETDEWEB)

    1992-01-01

    The overall objective of the project is to design and construct prototypical hardware for an integrated MHD topping cycle, and conduct long duration proof-of-concept tests of integrated system at the US DOE Component Development and Integration Facility in Butte, Montana. The results of the long duration tests will augment the existing engineering design data base on MHD power train reliability, availability, maintainability, and performance, and will serve as a basis for scaling up the topping cycle design to the next level of development, an early commercial scale power plant retrofit. The components of the MHD power train to be designed, fabricated, and tested include: A slagging coal combustor with a rated capacity of 50 MW thermal input, capable of operation with an Eastern (Illinois {number_sign}6) or Western (Montana Rosebud) coal, a segmented supersonic nozzle, a supersonic MHD channel capable of generating at least 1.5 MW of electrical power, a segmented supersonic diffuser section to interface the channel with existing facility quench and exhaust systems, a complete set of current control circuits for local diagonal current control along the channel, and a set of current consolidation circuits to interface the channel with the existing facility inverter.

  4. Biomass power for rural development. Technical progress report, October 1--December 31, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Neuhauser, E.

    1998-05-01

    The focus of the DOE/USDA sponsored biomass power for rural development project is to develop commercial energy crops for power generation by the year 2000. The New York based Salix Consortium project is a multi-partner endeavor, implemented in three stages. Phase-1, Final Design and Project Development, will conclude with the preparation of construction and/or operating permits, feedstock production plans, and contracts ready for signature. Field trials of willow (Salix) have been initiated at several locations in New York (Tully, Lockport, King Ferry, La Fayette, Massena, and Himrod) and co-firing tests are underway at Greenidge Station (NYSEG) and Dunkirk Station (NMPC). Phase-2 of the project will focus on scale-up of willow crop acreage, construction of co-firing facilities at Dunkirk Station (NMPC), and final modifications for Greenidge Station. Cofiring willow is also under consideration for GPU`s Seward Station where testing is underway. There will be an evaluation of the energy crop as part of the gasification trials occurring at BED`s McNeill Power Station. Phase-3 will represent fullscale commercialization of the energy crop and power generation on a sustainable basis. During the fourth quarter of 1997 the Consortium submitted a Phase-2 proposal. A few of the other more important milestones are outlined below. The first quarter of 1998 will be dominated by pre-planting activity in the spring.

  5. Safe Operation of Nuclear Power Plants. Code of Practice and Technical Appendices

    International Nuclear Information System (INIS)

    1969-01-01

    This book is in two parts. The first is a Code of Practice for the Safe Operation of Nuclear Power Plants and the second part is a compilation of technical appendices. Its object is to give information and illustrative examples that would be helpful in implementing the Code of Practice. This second part, although published under the same cover, is not part of the Code. Safe operation of a nuclear power plant postulates suitable siting and proper design, construction and management of the plant. Under the present Code of Practice for the Safe Operation of Nuclear Power Plants, those intending to operate the plant are recommended to prepare documentation which would deal with its operation and include safety analyses. The documentation in question would be reviewed by a regulatory body independent of the operating organization; operation would be authorized on the understanding that it would comply with limits and conditions designed to ensure safety. The Code may be subject to revision in the light of experience. The Appendices provide additional information together with some examples relating to certain topics dealt with in the Code; it must be emphasized that they are included as examples for information only and are not part of any recommendation. Purpose and scope: The recommendations in the Code are designed to protect the general public and the operating personnel from radiation hazards, and the Code forms part of the Agency's Safety Standards. The Code, which should be used in conjunction with the Agency's other Safety Standards, provides guidance and information to persons and authorities responsible for the operation of stationary nuclear power plants whose main function is the generation of thermal, mechanical or electrical power; it is not intended to apply to reactors used solely for experimental or research purposes. It sets forth minimum requirements which, it is believed, in the light of experience, must be met in order to achieve safe operation of a

  6. Advanced direct liquefaction concepts for PETC generic units. Quarterly technical progress report, April 1992--June 1992

    Energy Technology Data Exchange (ETDEWEB)

    1992-08-01

    CAER/UK: Detail coal and starting solvents from Wilsonville were analyzed to develop the data necessary to conduct process studies in the CO Pretreatment and Catalyst Evaluation segment of this program. A comparison of the solvent separation analysis with the distillation/separation used at Wilsonville showed that the residual solvent components contained a large amount of residual pentane soluble products. The ashy resid contained 3% iron and 400 ppM molybdenum. Although the iron content in the distillate and deashed resid was much less, namely about 200 ppM., the molybdenum concentrations in these fractions were not significantly reduced over the concentration in the ashy resid, i.e., 200 ppM in each. The pretreatment of coal with CO/H{sub 2}O in the presence of NaOH and Na{sub 2}CO{sub 3} has been shown to give a product which is lower in oxygen content and higher in hydrogen content compared to the raw coal. The atomic H/C ratios of the H{sub 2}O-insolubles, THF insolubles and the PA+A fractions of the products-together with the hydrogen consumption data suggested that the raw coal has been substantially depolymerized and hydrogenated via the WGS reaction during the pretreatment process. The extensive amount of molecular reconstruction that has occurred in the solid product was evident from the ease of solubilization of the product into pyridine. The result of the pretreatment process is a product which is highly reactive under hydroliquefaction conditions at 400{degrees}C. Reaction rates seem to be much faster than the raw coal, especially at shorter reaction times, providing the opportunity for major reductions in plant vessel sizes, and preliminary data has led us to believe that better efficiency in hydrogen utilization is achieved.

  7. Quarterly technical progress report for the period ending June 30, 1984

    Energy Technology Data Exchange (ETDEWEB)

    1984-10-01

    The Magnetohydrodynamics Program (Component Development and Integration Facility) in Butte, Montana, continued its site preparation for the TRW first-stage combustor installation. In the area of flue gas cleanup, our in-house research program is continuing its investigation into the causes of sorbent attrition in PETC's fluidized-bed copper oxide process for simultaneous SO/sub 2//NO/sub x/ removal. Interwoven with these tests is a series of spray dryer/electrostatic precipitator tests that are being conducted with the cooperation of Wheelabrator-Frye, Inc. This test series was completed this quarter, and the data show that when using a Kentucky coal, Wheelabrator-Frye's electrostatic precipitator provides excellent particulate control efficiency while using a spray dryer for sulfur dioxide removal. A unique project at Carnegie-Mellon University is looking at the concept of integrated environmental control for coal-fired power plants making use of precombustion, combustion, and postcombustion control, including systems for the simultaneous removal of more than one pollutant. The objective of this research is to develop a computer model and assessment for integrated environmental control systems that utilize conventional or advanced systems. The Liquid Phase Methanol Project Development Unit in LaPorte, Texas, was restarted after a successful shakedown run was completed. PETC has recently begun an in-house research project aimed at exploring the basic chemistry of liquefying coal in the presence of water under supercritical conditions. In the Alternative Fuels Technology Program, the Gulf Research and Development Company has completed the preliminary testing phase of its erosion test loop. Their results indicate that when pumping a coal-water slurry fuel through a flow loop, the erosion rate increases as velocity increases, suggesting a well-defined relationship between these two parameters.

  8. Final Technical Progress Report Long term risk from actinides in the environment: Modes of mobility; FINAL

    International Nuclear Information System (INIS)

    Thomas B. Kirchner

    2002-01-01

    The key source of uncertainty in assessing actinide mobility is the relative importance of transport by: (1) wind erosion, (2) water erosion, and (3) vertical migration. Each of these three processes depends on several environmental factors and they compete with one another. A scientific assessment of the long-term risks associated with actinides in surface soils depends on better quantifying each of these three modes of mobility. The objective from our EMSP study was to quantify the mobility of soil actinides by wind erosion, water erosion, and vertical migration at three semiarid sites where actinide mobility is a key technical, social and legal issue. This EMSP project was the first to evaluate all three factors at a site. The approach has been to investigate both short- and long-term issues based on field and lab studies and model comparisons. Our results demonstrate the importance of incorporating threshold responses into a modeling framework that accounts for environmental factors and natural disturbances that trigger large changes in actinide mobility. The study measured erosional losses of sediment and fallout cesium (an actinide analogue) from field plots located near WIPP in 1998. The results highlight the large effect of burning as a disturbance on contaminant transport and mobility via runoff and erosion. The results show that runoff, erosion, and actinide transport are (1) strongly site specific-differences in radionuclide transport between WIPP and Rocky Flats differed by a factor of twelve because of soil and vegetation differences, and (2) are strongly impacted by disturbances such as fire, which can increase runoff, erosion, and actinide transport by more than an order of magnitude. In addition, a laboratory experiment using soil columns was conducted to investigate the vertical transport of contaminants in sandy soils. Nine columns of soil collected from the vicinity of the WIPP site were prepared. The column consisted of a piece of PVC pipe 20 cm

  9. Final Technical Progress Report Long term risk from actinides in the environment: Modes of mobility

    International Nuclear Information System (INIS)

    Kirchner, Thomas B.

    2002-01-01

    The key source of uncertainty in assessing actinide mobility is the relative importance of transport by: (1) wind erosion, (2) water erosion, and (3) vertical migration. Each of these three processes depends on several environmental factors and they compete with one another. A scientific assessment of the long-term risks associated with actinides in surface soils depends on better quantifying each of these three modes of mobility. The objective from our EMSP study was to quantify the mobility of soil actinides by wind erosion, water erosion, and vertical migration at three semiarid sites where actinide mobility is a key technical, social and legal issue. This EMSP project was the first to evaluate all three factors at a site. The approach has been to investigate both short- and long-term issues based on field and lab studies and model comparisons. Our results demonstrate the importance of incorporating threshold responses into a modeling framework that accounts for environmental factors and natural disturbances that trigger large changes in actinide mobility. The study measured erosional losses of sediment and fallout cesium (an actinide analogue) from field plots located near WIPP in 1998. The results highlight the large effect of burning as a disturbance on contaminant transport and mobility via runoff and erosion. The results show that runoff, erosion, and actinide transport are (1) strongly site specific-differences in radionuclide transport between WIPP and Rocky Flats differed by a factor of twelve because of soil and vegetation differences, and (2) are strongly impacted by disturbances such as fire, which can increase runoff, erosion, and actinide transport by more than an order of magnitude. In addition, a laboratory experiment using soil columns was conducted to investigate the vertical transport of contaminants in sandy soils. Nine columns of soil collected from the vicinity of the WIPP site were prepared. The column consisted of a piece of PVC pipe 20 cm

  10. Savannah River Ecology Laboratory Annual Technical Progress Report of Ecological Research, June 30, 2001

    Energy Technology Data Exchange (ETDEWEB)

    Bertsch, Paul M.; Janecek, Laura; Rosier, Brenda

    2001-06-30

    The Savannah River Ecology Laboratory (SREL) is a research unit of the University of Georgia (UGA) and has been conducting ecological research on the Savannah River Site (SRS) in South Carolina for 50 years. The overall mission of the Laboratory is to acquire and communicate knowledge of ecological processes and principles. SREL conducts fundamental and applied ecological research, as well as education and outreach programs, under a Cooperative Agreement with the U.S. Department of Energy (DOE) SRS near Aiken, South Carolina. The Laboratory's research mission during the 2001 fiscal year was fulfilled with the publication of one book and 83 journal articles and book chapters by faculty, technical staff, students, and visiting scientists. An additional 77 journal articles have been submitted or are in press. Other noteworthy events took place as faculty members and graduate students received awards. These are described in the section Special Accomplishments of Faculty, Staff, Students, and Administration on page 54. Notable scientific accomplishments include work conducted on contaminant transport, global reptile decline, phytoremediation, and radioecology. Dr. Domy Adriano authored the second edition of his book ''Trace Elements in Terrestrial Environments: Biogeochemistry, Bioavailability, and Risks of Metals'', which was recently published by Springer-Verlag. The book provides a comprehensive treatment of many important aspects of trace elements in the environment. The first edition of the book, published in 1986, has become a widely acclaimed and cited reference. International attention was focused on the problem of reptile species decline with the publication of an article on this topic in the journal ''Bioscience'' in August, 2000. The article's authors included Dr. Whit Gibbons and a number of other SREL herpetologists who researched the growing worldwide problem of decline of reptile species. Factors related

  11. Final Technical Progress Report Long term risk from actinides in the environment: Modes of mobility

    Energy Technology Data Exchange (ETDEWEB)

    Thomas B. Kirchner

    2002-03-22

    The key source of uncertainty in assessing actinide mobility is the relative importance of transport by: (1) wind erosion, (2) water erosion, and (3) vertical migration. Each of these three processes depends on several environmental factors and they compete with one another. A scientific assessment of the long-term risks associated with actinides in surface soils depends on better quantifying each of these three modes of mobility. The objective from our EMSP study was to quantify the mobility of soil actinides by wind erosion, water erosion, and vertical migration at three semiarid sites where actinide mobility is a key technical, social and legal issue. This EMSP project was the first to evaluate all three factors at a site. The approach has been to investigate both short- and long-term issues based on field and lab studies and model comparisons. Our results demonstrate the importance of incorporating threshold responses into a modeling framework that accounts for environmental factors and natural disturbances that trigger large changes in actinide mobility. The study measured erosional losses of sediment and fallout cesium (an actinide analogue) from field plots located near WIPP in 1998. The results highlight the large effect of burning as a disturbance on contaminant transport and mobility via runoff and erosion. The results show that runoff, erosion, and actinide transport are (1) strongly site specific-differences in radionuclide transport between WIPP and Rocky Flats differed by a factor of twelve because of soil and vegetation differences, and (2) are strongly impacted by disturbances such as fire, which can increase runoff, erosion, and actinide transport by more than an order of magnitude. In addition, a laboratory experiment using soil columns was conducted to investigate the vertical transport of contaminants in sandy soils. Nine columns of soil collected from the vicinity of the WIPP site were prepared. The column consisted of a piece of PVC pipe 20 cm

  12. A decade of plant proteomics and mass spectrometry: Translation of technical advancements to food security and safety issues

    NARCIS (Netherlands)

    Agrawal, G.; Sarkar, A.; Righetti, P.; Pedreschi Plasencia, R.P.

    2013-01-01

    Tremendous progress in plant proteomics driven by mass spectrometry (MS) techniques has been made since 2000 when few proteomics reports were published and plant proteomics was in its infancy. These achievements include the refinement of existing techniques and the search for new techniques to

  13. Standard Technical Specifications General Electric plants, BWR/4:Bases (Sections 3.4-3.10). Volume 3, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the specifications for all chapters and sections of the improved STS. Volume 2 contains he Bases for Chapters 2.0 and 3.0, and Sections 3.1-3.3 of the improved STS. This document, Volume 3, contains the Bases for Sections 3.4-3.10 of the improved STS

  14. Standard technical specifications: Combustion engineering plants. Volume 3, Revision 1: Bases (Sections 3.4--3.9)

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Combustion Engineering Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  15. Standard technical specifications: Babcock and Wilcox plants. Volume 3, Revision 1: Bases (Sections 3.4--3.9)

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Babcock and Wilcox Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

  16. Standard Technical Specifications General Electric plants, BWR/4: Bases (Sections 2.0-3.3). Volume 2, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This report documents the results of the combined effort of the NRC and the industry produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved ST or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume I contains the Specifications for all chapters and sections of the improved STS. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1-3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4-3.10 of the improved STS

  17. Technical and economical analysis of concepts for using the heat of biogas plants in rural areas

    International Nuclear Information System (INIS)

    Kaths, Friederike Annette

    2012-08-01

    Since the implementation of the EEG in Germany the biogas production becomes an independent branch of industry in the agriculture. At this time more than 90 percent of the biogas plants work with co-generation plant for heat and power with a thermal engine efficiencies of more than 50 percent. Because of the location in the rural area heat costumers with a continuous demand of heat over the whole year are rare. This research had a closer look how to use the heat of biogas production efficiently and also generating profit. The aim of the study was to use heat over the whole year, a profitable heat concept without counting the KWK-bonus and an added value on the farm. During the study the following concepts were analyzed: asparagus production using soil heating, drying equipment for different products, the production of fish in aquaculture, the poultry production and the heated production of tomatoes. The results showed different concepts using heat of biogas plants as efficient for farmers. However with only one concept the aims - to use the heat over the whole year, generating a profitable heat concept without counting the KWK-bonus, add an value on the farm - mostly can not be achieved. The combination of different heat concepts is necessary. In this analysis the poultry production in combination with the dryer can be considered as the most efficient concept. Bearing in mind the benefit which can be generated with a heat concept as well as the higher income and the higher technical efficiency of biogas plants operators should implement an individual concept for their heat.

  18. I-NERI QUARTERLY TECHNICAL PROGRESS REPORT - JANUARY 1 - MARCH 31, 2005

    International Nuclear Information System (INIS)

    Chang Oh

    2005-01-01

    codes. The three categories of experiments were performed in the facility; (1) upper pool cooling trip test, (2) LOFC experiment, (3) emissivity measurement experiment. (C) Prof. NO continued Task 3. (Prof NO) The experimental work of air ingress is going on without any concern: Geometry and size effect test has been completed. The conversion factor for internal surface area was obtained through this experiment. Burn-off test was performed and the uniformity of internal reaction was confirmed. (D) INEEL engineers continued to extend the diffusion model for multiple chemical species and made some calculations. (E) Prof. Lee and Martin at University of Michigan continued to analyze the effect of the stochastic fuel on the neutronic analysis and have initiated fuel depletion calculations for the VHTGR core. Progress during the past quarter includes: Further analysis of stochastic fuel geometry; Preliminary Monte Carlo depletion of full-core VHTGR; and Installation of MCNP5 on Unix cluster

  19. Projects at the Western Environmental Technology Office. Quarterly technical progress report, July 1, 1995--September 30, 1995

    International Nuclear Information System (INIS)

    1996-01-01

    The goal of this project is to demonstrate the technical and economic feasibility of commercializing a biotechnology that uses plants to remediate soils, sediments, surface waters, and groundwaters contaminated by heavy metals and radionuclides. This technology, known as phytoremediation, is particularly suited to remediation of soils or water where low levels of contaminants are widespread. Project objectives are to provide an accurate estimate of the capability and rate of phytoremediation for removal of contaminants of concern from soils and groundwaters at Department of Energy (DOE) sites and to develop data suitable for engineering design and economic feasibility evaluations, including methods for destruction or final disposition of plants containing contaminants of concern. The bioremediation systems being evaluated could be less expensive than soil removal and treatment systems, given the areal extent and topography of sites under consideration and the investment of energy and money in soil-moving and -treating processes. In situ technology may receive regulatory acceptance more easily than ex situ treatments requiring excavation, processing, and replacement of surface soils. In addition, phytoremediation may be viable for cleanup of contaminated waters, either as the primary treatment or the final polishing stage, depending on the contaminant concentrations and process economics considerations

  20. Projects at the Western Environmental Technology Office. Quarterly technical progress report, July 1, 1995--September 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    The goal of this project is to demonstrate the technical and economic feasibility of commercializing a biotechnology that uses plants to remediate soils, sediments, surface waters, and groundwaters contaminated by heavy metals and radionuclides. This technology, known as phytoremediation, is particularly suited to remediation of soils or water where low levels of contaminants are widespread. Project objectives are to provide an accurate estimate of the capability and rate of phytoremediation for removal of contaminants of concern from soils and groundwaters at Department of Energy (DOE) sites and to develop data suitable for engineering design and economic feasibility evaluations, including methods for destruction or final disposition of plants containing contaminants of concern. The bioremediation systems being evaluated could be less expensive than soil removal and treatment systems, given the areal extent and topography of sites under consideration and the investment of energy and money in soil-moving and -treating processes. In situ technology may receive regulatory acceptance more easily than ex situ treatments requiring excavation, processing, and replacement of surface soils. In addition, phytoremediation may be viable for cleanup of contaminated waters, either as the primary treatment or the final polishing stage, depending on the contaminant concentrations and process economics considerations.

  1. Optimal design and routing of power lines; ecological, technical and economic perspectives (OPTIPOL). Progress report 2012

    Energy Technology Data Exchange (ETDEWEB)

    Bevanger, Kjetil; Bartzke, Gundula; Broeseth, Henrik; Dahl, Espen Lie; Gjershaug, Jan Ove; Hanssen, Frank; Jacobsen, Karl-Otto; Kleven, Oddmund; Kvaloey, Paal; May, Roel; Meaas, Roger; Nygaaard, Torgeir; Resnaes, Steinar; Stokke, Sigbjoern; Thomassen, Joern

    2012-07-01

    birds in the database, compared to only 117 a year earlier. WP5 - 'A Least Cost Path (LCP) toolbox for optimal route routing of power lines', has developed an LCP-pilot to demonstrate the LCP method, based on the impact studies were undertaken prior to construction of a 420 kV transmission line in Central Norway 2005. Relevant economic, ecological and technological environment criteria based on suggestions from interested users (NGOs, government, industry, etc.), was used. LCP-pilot and a fuzzy-logic approach of this was demonstrated in the first dialogue-based workshop, 23.-24. april 2012. The seminar, which had an emphasis on criteria definitions were followed up with a working seminar that focused criterion values ??on 20 november 2012. Lecture - 'A Least Cost Path (LCP) Toolbox for Optimal Routing of Power Lines, -was presented and submitted as contributions to the conference report from 'The 10th ROW Conference' in Arizona, 'The 32nd Annual Conference of the International Association for Impact Assessment (IAIA12) ' in Porto, Portugal, and 'The ESRI European User Conference' in Oslo. WP6 - 'Birds and camouflaging of power lines', has almost completed the final report, 'Power line camouflaging. An assessment of the ecological and technical challenges'. 'Because of the budget situation in CEDREN However, completion of the report postponed until the end of April 2013. WP7 - 'Effect of line marking / modifications remedial measures against bird mortality' has almost completed the final report 'Opportunities and limitations in terms of reducing mortality in birds due to collision and electrocution.' Due to overall budget situation in CEDREN the report deferred to the end of april 2013. WP8, 'guidelines for technological solutions that may reduce mortality in birds because of the power line's', has focused topics relating to the labeling, design, insulation, camouflage and wiring. The results, which are presented in the notes and articles, will be implemented in

  2. Bi-gas pilot plant operation. Technical progress report, 1 July 1980-30 September 1980

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-01-01

    The stainless steel process gas line from the gasifier to the gas washer was replaced with chrome molybdenum steel. Test G-13 was the longest to date and was characterized by smooth start-up and operation, long Stage I thermocouple life, and collection of much material balance data. Stress corrosion cracking in several areas of the process gas line delayed start-up of Test G-14 and a large part of the quarter was spent in replacing this piping. The results of test G-13 are described in detail. Conclusions for the test and recommendation are given, especially for burner modifications, prevention of calcium carbonate deposits, etc.

  3. Technical solutions for mitigating adverse impacts on the environment implemented at Deva Thermal Power Plant

    International Nuclear Information System (INIS)

    Vaida, Victor; Egyed, Francisc; Manea, Laurean

    2004-01-01

    Situated at the south-west of Transylvania, 9 km from Deva town on the Mures River bank, Deva Power Plant has an installed capacity of 1260 MW, in six 210 MW generation units. Each unit operates with two steam boilers of 330 t/h, and steam rated parameters are 13.72 MPa and 550 deg C. The generated electricity is delivered in the national grid at voltage levels of 200 and 400 kV; there exists also the possibility of delivering electricity to the neighbouring countries through the power line Sibiu - Arad - Szeged. The Power Plant also produces thermal energy. The total installed thermal capacity is 400 MWt. Deva Power Plant was commissioned in three stages. During the first stage, between 1969 and 1971, Units No. 1, 2, 3 and 4 were commissioned, followed by Unit No. 5 in 1977 and by Unit No. 6 in 1980. All main equipment was manufactured in Russia. The main fuel utilised here is hard coal extracted from Valea Jiului basins, with calorific value between 14600 and 18800 kJ/kg. Natural gas is used as a flame support fuel. Deva Power Plant has actually produced 9% to 12% of the total electricity produced in the country and 18% to 25% of the electricity produced on coal. Continuous efforts have been made for the rehabilitation and modernisation of this power plant aiming to improve operational safety whilst equal interest has been paid to mitigating the environmental damage caused by the great size combustion systems. In this paper we present some of the preoccupations concerning earliest as well as prospective actions to be taken to protect the environment and to comply with the relevant standards and laws in force. The major role played by Deva Power Plant within the National Power Grid secured through reliable and steady operation also means undertaking exceptional environmental protection actions, to comply with current requirements. By its comprehensive modernisation programme already in progress, Deva Power Plant focus on the continuous upgrading of their plant in

  4. Progress in the integration of the ITER plant systems in auxiliary buildings

    International Nuclear Information System (INIS)

    Kotamäki, M.; Cordier, J.-J.; Kuehn, I.; Perrin, J.-L.; Sweeney, S.; Villedary, B.

    2016-01-01

    Highlights: • Usage of 3D CAD model in ITER configuration management presented. • 3D CAD models efficient in configuration and interface management. • Costly and schedule delaying changes avoided with proper interface management. • ITER buildings construction progressing. - Abstract: The ITER Tokamak machine is located in the center of Tokamak complex buildings consisting of Tokamak, Diagnostic, and Tritium buildings. Around the Tokamak complex there are over 30 auxiliary buildings housing various plant systems serving the Tokamak machine either directly or indirectly. The layout and space allocation of each auxiliary building and plant systems housed by the building are represented in the so-called Configuration Management Models (CMM). These are light 3D CAD models that define the required space envelope and the physical interfaces between the systems and the buildings and in-between the systems. The paper describes the CMM and interface management processes of the ITER auxiliary buildings and plant systems, and discusses the preparations for the plant installation phase. In addition, the current baseline configuration of the ITER plant systems in auxiliary buildings is described together with the recent developments in the configuration of different systems, as well as the current status of the construction of the buildings.

  5. Progress in the integration of the ITER plant systems in auxiliary buildings

    Energy Technology Data Exchange (ETDEWEB)

    Kotamäki, M., E-mail: miikka.kotamaki@iter.org; Cordier, J.-J.; Kuehn, I.; Perrin, J.-L.; Sweeney, S.; Villedary, B.

    2016-11-01

    Highlights: • Usage of 3D CAD model in ITER configuration management presented. • 3D CAD models efficient in configuration and interface management. • Costly and schedule delaying changes avoided with proper interface management. • ITER buildings construction progressing. - Abstract: The ITER Tokamak machine is located in the center of Tokamak complex buildings consisting of Tokamak, Diagnostic, and Tritium buildings. Around the Tokamak complex there are over 30 auxiliary buildings housing various plant systems serving the Tokamak machine either directly or indirectly. The layout and space allocation of each auxiliary building and plant systems housed by the building are represented in the so-called Configuration Management Models (CMM). These are light 3D CAD models that define the required space envelope and the physical interfaces between the systems and the buildings and in-between the systems. The paper describes the CMM and interface management processes of the ITER auxiliary buildings and plant systems, and discusses the preparations for the plant installation phase. In addition, the current baseline configuration of the ITER plant systems in auxiliary buildings is described together with the recent developments in the configuration of different systems, as well as the current status of the construction of the buildings.

  6. Technical evaluation of RETS-required reports for Crystal River Nuclear Generating Plant, Unit 3, for 1983

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review was performed on the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at Florida Power Corporation's Crystal River Nuclear Plant, Unit 3, during 1983. The three periodic reports reviewed were (1) the Effluent and Waste Disposal Semiannual Report, January 1-June 30, 1983, (2) the Effluent and Waste Disposal Semiannual Report, July 1-December 31, 1983, and (3) the Annual Environmental Operating Report, Radiological, 1983. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  7. Regulatory surveillance of safety related maintenance at nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-08-01

    The operational safety and reliability of a nuclear power plant as well as its availability for electricity generation depend on, among other things, its maintenance programme. Regulatory bodies therefore have considerable interest in maintenance activities. There are several approaches to maintenance, i.e. reliability centered maintenance or risk focused maintenance, aimed at optimizing maintenance by focusing on important components or systems. These approaches may result in significant changes to maintenance activities and therefore have to be considered for regulatory acceptance. In order to review and discuss the status of maintenance regulation in participating countries, the IAEA convened a Technical Committee Meeting on Regulatory Oversight of Maintenance Activities at Nuclear Power Plants in Vienna from 9 to 13 October 1995. The meeting was attended by 16 experts from 11 countries. In addition to the consideration of papers that were presented and which are reproduced here, extensive group and panel discussions took place during the meeting. These covered three main topics: general features and basic characteristics of maintenance regulation, regulatory acceptance of maintenance optimization and use of PSA for maintenance optimization. The discussion are summarized in Section 2. Section 3 discusses the following three additional topics: regulatory involvement in the maintenance programme, modifications to the maintenance programme and personnel related aspects of maintenance. The conclusions are presented in Section 4. Figs, tabs

  8. Reviewing PSA-based analyses to modify technical specifications at nuclear power plants

    International Nuclear Information System (INIS)

    Samanta, P.K.; Martinez-Guridi, G.; Vesely, W.E.

    1995-12-01

    Changes to Technical Specifications (TSs) at nuclear power plants (NPPs) require review and approval by the United States Nuclear Regulatory Commission (USNRC). Currently, many requests for changes to TSs use analyses that are based on a plant's probabilistic safety assessment (PSA). This report presents an approach to reviewing such PSA-based submittals for changes to TSs. We discuss the basic objectives of reviewing a PSA-based submittal to modify NPP TSs; the methodology of reviewing a TS submittal, and the differing roles of a PSA review, a PSA Computer Code review, and a review of a TS submittal. To illustrate this approach, we discuss our review of changes to allowed outage time (AOT) and surveillance test interval (STI) in the TS for the South Texas Project Nuclear Generating Station. Based on this experience gained, a check-list of items is given for future reviewers; it can be used to verify that the submittal contains sufficient information, and also that the review has addressed the relevant issues. Finally, recommended steps in the review process and the expected findings of each step are discussed

  9. Annual meeting on nuclear technology '85. Technical session on nuclear power plant simulators. Jahrestagung Kerntechnik '85. Fachsitzung Simulatoren bei Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    The ten lectures read at this Technical Session deal with nuclear power plant simulators and their functions for the training of control room personnel, with test facilities for analysis and simulation of incidents and the relevant plant behaviour, and with the computer codes for fast simulation of reactor processes. The papers explain in particular the HAMMLAB project, the COSIMA fast core simulator, and the OPAL simulator for the KWU convoy process information system named PRINS.

  10. Progress in Aluminum Electrolysis Control and Future Direction for Smart Aluminum Electrolysis Plant

    Science.gov (United States)

    Zhang, Hongliang; Li, Tianshuang; Li, Jie; Yang, Shuai; Zou, Zhong

    2017-02-01

    The industrial aluminum reduction cell is an electrochemistry reactor that operates under high temperatures and highly corrosive conditions. However, these conditions have restricted the measurement of key control parameters, making the control of aluminum reduction cells a difficult problem in the industry. Because aluminum electrolysis control systems have a significant economic influence, substantial research has been conducted on control algorithms, control systems and information systems for aluminum reduction cells. This article first summarizes the development of control systems and then focuses on the progress made since 2000, including alumina concentration control, temperature control and electrolyte molecular ratio control, fault diagnosis, cell condition prediction and control system expansion. Based on these studies, the concept of a smart aluminum electrolysis plant is proposed. The frame construction, key problems and current progress are introduced. Finally, several future directions are discussed.

  11. The Pennsylvania State University Light Water Ultra-Safe Plant Concept: 3rd quarter progress report

    International Nuclear Information System (INIS)

    Klevans, E.

    1987-01-01

    Progress in the Ultra Safe study has substantially increased since the last report. The search for pressurizing pump turbine component information is now complete and a final plant layout for detailed evaluation has been chosen. Significant results for the normal operation performance of the Ultra Safe pressurizing technique are included. The plan of attack for the evaluation of the Ultra Safe shutdown scenario and natural circulation capability is discussed. This process is expected to be the next key area for analysis. The reactor design is complete including a change to alleviate the need for a soluble boron system. Material on the reactor building layout is also provided

  12. Standard technical specifications - Babcock and Wilcox Plants: Bases (Sections 2.0-3.3). Volume 2, Revision 1

    International Nuclear Information System (INIS)

    1995-04-01

    This NUREG contains the improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the B ampersand W Owners Group (BWOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

  13. 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)

  14. Evaluation of systems interactions in nuclear power plants: Technical findings related to Unresolved Safety Issue A-17

    International Nuclear Information System (INIS)

    Thatcher, D.

    1989-05-01

    This report presents a summary of the activities related to Unresolved Safety Issue (USI)A-17, ''Systems Interactions in Nuclear Power Plants,'' and also includes the NRC staff's conclusions based on those activities. The staff's technical findings provide the framework for the final resolution of this unresolved safety issue. The final resolution will be published later as NUREG-1229. 52 refs., 4 tabs

  15. 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.

  16. 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.

  17. Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

    International Nuclear Information System (INIS)

    Dey, M.K.

    1998-01-01

    This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include ''engineering tools'' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire PRA analyses are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (author)

  18. Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

    International Nuclear Information System (INIS)

    Dey, M.K.

    2000-01-01

    This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include 'engineering tools' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire probabilistic risk analyses (PRA) are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (orig.) [de

  19. Technical progress report

    International Nuclear Information System (INIS)

    1982-01-01

    This report summarizes the work carried out by personnel at the Nuclear Physics Laboratory of the University of Colorado from about August 1, 1981 to October 1, 1982, under contract with the Department of Energy. The intermediate energy studies summarized in this report were carried out at the meson physics facilities at Los Alamos (LAMPF), the cyclotron at Indiana University (IUCF), and the meson physics facilities at Vancouver (TRIUMF). This year, for the first time, intermediate energy experimental studies are being reported in separate documents from the low energy and theoretical nuclear physics efforts. Experimental studies are reported on pion-nucleus interactions, charge exchange reactions, nucleon transfer reactions, and apparatus development

  20. 1996 technical progress report

    International Nuclear Information System (INIS)

    1997-01-01

    Summaries of the researches are grouped into programs as follows: research and development in food and agriculture; research and development in health, environment and industry which includes all the PNRI research projects in 1996; scientific and technological services; and the nuclear regulations, licensing and safeguards of the institute

  1. 1997 technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    This report presents the on-going research and development projects of the Philippine Nuclear Research Institute (PNRI) in the fields of agriculture, environment and industry, scientific and technological services and nuclear regulations, licensing and safeguards.

  2. Annual technical progress report

    International Nuclear Information System (INIS)

    1980-01-01

    During the present contract period Phaedrus has begun operation as a true tandem mirror. This was accomplished by achieving the rf sustained mode in which the plug densities were built up by a combination of central cell gas puffing and plug ICRH following stream gun turn off. It was demonstrated that the tandem mirror plasma could be sustained by plug ICRH for up to 1 msec following decay of the external plasma. In this mode plasma characteristics were no longer dominated by problems associated with a high conductivity stream gun plasma in the external region (as was the case in many previous experiments in Phaedrus). Among these problems were (1) line tying which significantly reduced instabilities in a way that would not apply to reactors and (2) low electron temperatures which had been held to approx. 20 eV

  3. 1999 technical progress report

    International Nuclear Information System (INIS)

    2000-01-01

    This report presents the on-going research and development projects of the Philippine Nuclear Research Institute (PNRI) in the fields of agriculture, environment and industry, scientific and technological services and nuclear regulations, licensing and safeguards

  4. 1999 technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This report presents the on-going research and development projects of the Philippine Nuclear Research Institute (PNRI) in the fields of agriculture, environment and industry, scientific and technological services and nuclear regulations, licensing and safeguards.

  5. 1996 technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    Summaries of the researches are grouped into programs as follows: research and development in food and agriculture; research and development in health, environment and industry which includes all the PNRI research projects in 1996; scientific and technological services; and the nuclear regulations, licensing and safeguards of the institute.

  6. 1997 technical progress report

    International Nuclear Information System (INIS)

    1998-01-01

    This report presents the on-going research and development projects of the Philippine Nuclear Research Institute (PNRI) in the fields of agriculture, environment and industry, scientific and technological services and nuclear regulations, licensing and safeguards

  7. 1995 technical progress report

    International Nuclear Information System (INIS)

    1997-01-01

    Summaries of the researches are grouped into programs as follows: research and development which covers all the PNRI research projects in 1994; scientific and technological services; and the nuclear regulations, licensing and safeguards of the institute

  8. Technical Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    Paul D. Ronney

    2004-08-26

    An ignition source was constructed that is capable of producing a pulsed corona discharge for the purpose of igniting mixtures in a test chamber. The corona generator can also be used as the ignition source for one cylinder on a test engine. The first tests were performed in a cylindrical shaped chamber to study the characteristics of the corona and analyze various electrode geometries. Next a test chamber was constructed that closely represented the dimensions of the combustion chamber of the test engine at USC. Combustion tests were performed in this chamber and various electrode diameters and geometries were tested. Higher peak pressures and faster pressure rise times were realized consistently in all test chambers versus standard spark plug ignition. A test engine was purchased for the project that has two spark plug ports per cylinder to The data acquisition and control system hardware for the USC engine lab was updated with new equipment. New software was also developed to perform the engine control and data acquisition functions including cylinder pressure monitoring. A ceramic corona electrode has been designed that fits in the new test engine and is capable of withstanding the pressures and temperatures encountered inside the combustion chamber. The corona ignition system was tested on the engine and an increase in both peak pressure and IMEP were seen in the initial test. There are issues that must be addressed before on-engine testing can continue such as EMF interference from the corona generator and electrical insulation on portions of the piston and cylinder head to prevent arcing. The EMF issue can be solved with proper shielding and grounding and various ceramic coatings are being researched for electrical insulation.

  9. Technical Progress Report

    International Nuclear Information System (INIS)

    Engelhardt, G.R.; MacDonald, D.D.

    1999-01-01

    During the past quartile (two month period) most attention has been concentrated on the problem of definition critical temperature at which ''wet'' corrosion first became operable. It has been shown that, in principle, ''wet'' corrosion processes can not be ignored for Yucca Mountain, even for initial times, when the temperature of the surface of containers is well above the boiling temperature of water for the prevailing conditions. This is because the surfaces are covered by highly hydrophilic oxides (e.g. Fe 2 O 3 , NiO, Cr 2 O 3 ) that will hydrate to the form of corresponding hydroxides, which are proton conductors, at least when in the ''wet'' condition. Because proton conduction and the presence of ''bound'' water are all that are required for the external environment to support metallic corrosion in either its general or localized form. Thus, the temperature of dehydration of the hydroxide, e.g. M(OH) 2 → MO + H 2 O(g), is a better criterion for the upper temperature limit for ''wet'' corrosion than is the boiling temperature of ''bulk'' water. During this first task, we have reviewed the existing thermodynamic data base for the dehydration of metal hydroxides and analytical expressions have been developed that allow the upper temperature limit to be estimated

  10. IMPROVEMENT OF SYSTEMS OF TECHNICAL WATER SUPPLY WITH COOLING TOWERS FOR HEAT POWER PLANTS TECHNICAL AND ECONOMIC INDICATORS PERFECTION. Part 2

    Directory of Open Access Journals (Sweden)

    Yu. A. Zenovich-Leshkevich-Olpinskiy

    2016-01-01

    Full Text Available The method of calculation of economic efficiency that can be universal and is suitable for feasibility study of modernization of irrigation and water distribution system of cooling towers has been developed. The method takes into account the effect of lower pressure exhaust steam in the condenser by lowering the temperature of the cooling water outlet of a cooling tower that aims at improvement of technical and economic indicators of heat power plants. The practical results of the modernization of irrigation and water distribution system of a cooling tower are presented. As a result, the application of new irrigation and water distribution systems of cooling towers will make it possible to increase the cooling efficiency by more than 4 оС and, therefore, to obtain the fuel savings by improving the vacuum in the turbine condensers. In addition, the available capacity of CHP in the summer period is increased. The results of the work, the experience of modernization of irrigation and water distribution systems of the Gomel CHP-2 cooling towers system, as well as the and methods of calculating of its efficiency can be disseminated for upgrading similar facilities at the power plants of the Belarusian energy system. Some measures are prosed to improve recycling systems, cooling towers and their structures; such measures might significantly improve the reliability and efficiency of technical water supply systems of heat power plants.

  11. Analysis and evaluation of the ASTEC model basis on plant simulations. 2. Technical report

    International Nuclear Information System (INIS)

    Koppers, Vera; Braehler, Thimo; Koch, Marco K.

    2015-06-01

    The present report is the 2 nd Technical Report of the research project ''Analysis and Evaluation of the ASTEC model basis'' funded by the Federal Ministry for Economic Affairs and Energy (BMWi 1501433) and conducted at the Reactor Simulation and Safety Group, Chair of Energy Systems and Energy Economics (LEE) at Ruhr-Universitaet Bochum. Within this report, the quality of a nuclear power plant simulation with ASTEC is investigated. Different parameters are varied to analyze the simulation stability within the dataset, which describes a generic German Konvoi power plant and is deposit in the program set of ASTEC. Firstly, plant specifications in the data set are checked for plausibility. In addition, the compliance of the data set with the nodalization rules is verified. After that, the stationary phase, in which no accident is calculated, is analyzed and parametric studies are performed in the transient phase, focusing on the primary and secondary circuit as well as on the containment behavior. The performed calculations focusing the primary and secondary circuit indicate a high dependency of the simulation results on the user's input in the data set. There are significant deviations between each simulations results, for example in the different calculated point of time of the reactor pressure vessel failure. Already changes in the stationary phase cause a significantly earlier reactor pressure vessel failure compared to the simulation with the original data. Beyond that, the location of the leakage of the reactor pressure vessel lower head varied and therefore cannot be clearly determined, although there have been no changes by the user on the accident course. A reliable indication of the plant behavior under severe accident conditions is therefore difficult using ASTEC. The results of the parametric studies within the Containment show the same significant influence of certain parameter changes on the simulation results. By using the

  12. Plant hormone cytokinins control cell cycle progression and plastid replication in apicomplexan parasites.

    Science.gov (United States)

    Andrabi, Syed Bilal Ahmad; Tahara, Michiru; Matsubara, Ryuma; Toyama, Tomoko; Aonuma, Hiroka; Sakakibara, Hitoshi; Suematsu, Makoto; Tanabe, Kazuyuki; Nozaki, Tomoyoshi; Nagamune, Kisaburo

    2018-02-01

    Cytokinins are plant hormones that are involved in regulation of cell proliferation, cell cycle progression, and cell and plastid development. Here, we show that the apicomplexan parasites Toxoplasma gondii and Plasmodium berghei, an opportunistic human pathogen and a rodent malaria agent, respectively, produce cytokinins via a biosynthetic pathway similar to that in plants. Cytokinins regulate the growth and cell cycle progression of T. gondii by mediating expression of the cyclin gene TgCYC4. A natural form of cytokinin, trans-zeatin (t-zeatin), upregulated expression of this cyclin, while a synthetic cytokinin, thidiazuron, downregulated its expression. Immunofluorescence microscopy and quantitative PCR analysis showed that t-zeatin increased the genome-copy number of apicoplast, which are non-photosynthetic plastid, in the parasite, while thidiazuron led to their disappearance. Thidiazuron inhibited growth of T. gondii and Plasmodium falciparum, a human malaria parasite, suggesting that thidiazuron has therapeutic potential as an inhibitor of apicomplexan parasites. Copyright © 2017 The Authors. Published by Elsevier B.V. All rights reserved.

  13. Environment, safety and Health Progress Assessment of the Rocky Flats Plant

    International Nuclear Information System (INIS)

    1993-05-01

    This report documents the result of the US Department of Energy's (DOE) Environment, Safety and Health (ES ampersand H) Progress Assessment of the DOE Rocky Flats Plant (RFP) in Golden, Colorado. The assessment, which was conducted during the period of May 17 through May 28, 1993, included a selective review of the ES ampersand H management systems and programs of the responsible DOE Headquarters Program Offices (Defense Programs (DP) and Environmental Restoration and Waste Management (EM)), the DOE Rocky Flats Office (RFO), and the site contractor, EG ampersand G Rocky Flats, Inc. (EG ampersand G). Despite the near constant state of flux under which RFP has been required to operate, the Progress Assessment Team has concluded that significant progress has been made in correcting the deficiencies identified in the 1989 Assessment and in responding responsibly to regulations, and DOE directives and guidance that have been issued since that time. The Team concluded that the improvements have been concentrated in the activities associated with plutonium facilities and in regulatory driven programs. Much remains to be done with respect to implementing on a sitewide basis those management systems that anchor an organization's pursuit of continuous ES ampersand H improvement. Furthermore the Team concluded that the pace of improvement has been constrained by a combination of factors that have limited the site's ability to manage change in the pursuit of sitewide ES ampersand H excellence

  14. Technical and economical feasibility study of a sewage sludge disinfection plants by irradiation process

    International Nuclear Information System (INIS)

    Rojas Bustos, Gustavo

    1999-01-01

    This report presents a technical and economical evaluation for a disinfection plant of sewage sludge based on irradiation. The process starts after sludge stabilization which is achieved by anaerobic digestion. It includes two stages, plus an optional: the first corresponds to dewatering of sewage sludge up to a solids content between 20 and 25 %, the second stage corresponds to disinfection by gamma or electron beam irradiation, and the third, which is optional, corresponds to the drying of sewage sludge up to a water content of 50%, which allows to diminish significantly the volumes of solids to be transported. If this stage is not accomplished the final product corresponds to a sewage sludge with 25 % of dry solids, which can also be disposed in agricultural land. Process was designed to treat 60 tons per day of sewage sludge (dry matter basis). The report presents the design of process equipment, principal and auxiliary, the investment and operational cost estimations as well as the total cost of treatment per ton of sewage sludge. A sensitivity analysis is also included to determine the influence of operational process parameters in operational and investment costs. The results showed that a sewage sludge plant including dewatering and disinfection process through gamma irradiation, achieves a capital investment of about US$ 12.000.000 with a treatment cost per ton of dry sludge of US$140. Including the optional air-drying stage, the total cost of treatment is about US$148 per ton of dry matter. In the case of electron beam irradiation the capital investment achieves a value of US$ 11 millions with a total treatment cost of US$ 136 per ton of dry matter. These values resulted quite similar to the cost of alternative treatment, i.e., disposal in a dedicated landfill. (L.V.)

  15. Technical requirements for the ASME PRA standard for nuclear power plant applications

    International Nuclear Information System (INIS)

    Fleming, Karl N.; Bernsen, Sidney A.; Simard, Ronald L.

    2000-01-01

    In 1998 the American Society of Mechanical Engineers (ASME) formed the Committee on Nuclear Risk Management (CNRM) and a Project Team to develop a standard on PRAs for use in risk informed applications. This ASME standard is being developed to help provide an adequate level of quality in PRAs that are being used to support ASME initiatives to risk informed in-service inspection (ISI) and in-service testing (IST) of nuclear power plant components. A related need supported by the industry and the U.S. Nuclear Regulatory Commission is to reduce the level of effort that is being expended in pilot applications of risk informed initiatives to address questions about the sufficiency of quality in the supporting PRA models. The purpose of this paper is to discuss the authors' views on some of the technical issues that were encountered in the effort to develop the ASME PRA standard. Draft 12 of this standard has been issued for comment, and is currently being finalized with the aim of releasing the standard in early 2001. (author)

  16. Technical basis for environmental qualification of computer-based safety systems in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Tanaka, T.J.; Antonescu, C.E.

    1997-01-01

    This paper summarizes the results of research sponsored by the US Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. This research was conducted by the Oak Ridge National Laboratory (ORNL) and Sandia National Laboratories (SNL). ORNL investigated potential failure modes and vulnerabilities of microprocessor-based technologies to environmental stressors, including electromagnetic/radio-frequency interference, temperature, humidity, and smoke exposure. An experimental digital safety channel (EDSC) was constructed for the tests. SNL performed smoke exposure tests on digital components and circuit boards to determine failure mechanisms and the effect of different packaging techniques on smoke susceptibility. These studies are expected to provide recommendations for environmental qualification of digital safety systems by addressing the following: (1) adequacy of the present preferred test methods for qualification of digital I and C systems; (2) preferred standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging in qualification testing for equipment that is to be located in mild environments; and (5) determination of an appropriate approach to address smoke in a qualification program

  17. Review of the scientific and technical criteria for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1984-01-01

    The panel has evaluated the scientific and technical adequacy of work being done on the Waste Isolation Pilot Plant (WIPP) project to satisfy the charge to the panel set out in Chapter 1. The panel concluded that the scientific work has been carried out with a high degree of professional competence. The panel notes that the geology revealed by shaft sinking and excavation of drifts and the preliminary measurements generally confirm the geologic expectations derived from surface explorations and boreholes. The purity and volume of the salt, the absence of brine pockets at the repository horizon in the areas excavated, the absence of breccia pipes and of toxic gases, and the nearly horizontal bedding of the salt indicate that a repository can be constructed that will meet the geologic criteria for site selection. Thus, the important issues about the geology at the site have been resolved, but there remain some issues about the hydrology and design of the facility that should be resolved before large-scale transuranic (TRU) waste emplacement begins. The panel's conclusions and recommendations regarding the following studies are presented: site selection and characterization; in-situ tests and experiments; waste acceptance criteria; design and construction of underground facilities; and performance assessment. 65 references, 17 figures, 3 tables

  18. Three technical issues in fatigue damage assessment of nuclear power plant components

    International Nuclear Information System (INIS)

    Ware, A.G.; Shah, V.N.

    1991-01-01

    This paper addresses three technical issues that affect the fatigue damage assessment of nuclear power plant components: the effect of the environment on the fatigue life, the importance of the loading sequence in calculating the fatigue crack-initiation damage, and the adequacy of current inservice inspection requirements and methods to characterize fatigue cracks. The environmental parameters that affect the fatigue life of carbon and low alloy steel components are the sulphur content in the steel, the temperature, the amount of dissolved oxygen in the coolant, and the presence of oxidizing agents such as copper oxide. The occurrence of large-amplitude stress cycles early in a component's life followed by low-amplitude stress cycles may cause crack initiation at a cumulative usage factor less than 1.0. The current inservice inspection requirements include volumetric inspections of welds but not of some susceptible sites in the base metal. In addition, the conventional ultrasonic testing techniques need to be improved for reliable detection and accurate sizing of fatigue cracks. 28 refs., 4 figs., 1 tab

  19. Technical Basis for Radiological Emergency Plan Annex for WTD Emergency Response Plan: West Point Treatment Plant

    Energy Technology Data Exchange (ETDEWEB)

    Hickey, Eva E.; Strom, Daniel J.

    2005-08-01

    Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document, Volume 3 of PNNL-15163 is the technical basis for the Annex to the West Point Treatment Plant (WPTP) Emergency Response Plan related to responding to a radiological emergency at the WPTP. The plan primarily considers response to radioactive material that has been introduced in the other combined sanitary and storm sewer system from a radiological dispersion device, but is applicable to any accidental or deliberate introduction of materials into the system.

  20. Interim technical evaluation report of testing procedures for activated carbon adsorbers in ventilation filter assemblies in nuclear power plants

    International Nuclear Information System (INIS)

    Sill, C.W.; Scarpellino, C.D.; Tkachyk, J.W.; Grey, A.E.; Frank, C.W.

    1985-05-01

    Laboratory analysis of activated carbon is required by nuclear power plant technical specifications for use in Engineered Safety Feature (ESF) ventilation systems to determine the capability of those systems to remove radioiodines from air during normal operation and following a design basis accident (DBA). The lask of agreement of laboratory results from a recent round robin raised concerns regarding the adequacy of the analyses, using the ASTM D3803-79 standard, to assure compliance with plant technical specifications. EG and G Idaho was contracted by the NRC to conduct a program to provide the bases for resolving these concerns. This EG and G report serves as an interim Technical Evaluation Report (TER) of the program and presents reviews of the ASTM D3803-79 standard and the commercial testing laboratories. Results of EG and G laboratory studies and the NRC/EG and G Interlaboratory Comparison are presented with conclusions and recommendations concerning changes required to improve the standard and its application. Possible revisions to plant technical specifications required to reflect the true capability of activated carbon to remove radioiodines are also presented