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Sintese do sesquinitreto de uranio e seu uso como catalisador da reacao de termodecomposicao da amoniaROCHA, SORAYA M.R. da 09 October 2014 (has links)
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02950.pdf: 4952382 bytes, checksum: 1dddfe6ca71077632e2bdf2d56006ba7 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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The effects of changing enrichment supply conditions on world nuclear fuel trade patternsHammond, Gerald Ellsworth. January 1980 (has links)
Thesis (B.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1980. / Bibliography: leaf 49. / by Gerald Ellsworth Hammond Jr. / Thesis (B.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1980.
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The Future of Nuclear Energy in FloridaEdwards, James Wayne 01 October 1974 (has links) (PDF)
No description available.
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Novel uses of magnetic separation in the nuclear industryCoe, Benjamin Trevor January 1999 (has links)
No description available.
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Essays on uranium enrichment.Charpie, Richard Alan January 1979 (has links)
Thesis. 1979. Ph.D.--Massachusetts Institute of Technology. Alfred P. Sloan School of Management. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND DEWEY. / Includes bibliographies. / Ph.D.
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Investigation of reliability growth in the nuclear industry for probabilistic risk assessmentAhn, Hyunsuk 18 December 1992 (has links)
The current method of determining component failure rates
for probabilistic risk assessment (PRA) in the nuclear
industry is to take the total number of failures divided by
the time over which the failures occurred. The method
proposed in this study is the reliability growth method and
involves taking into account the fact that the amount of
failures per additional year of operation generally decreases
yearly because the operational staff becomes familiar with the
equipment. The reliability growth method will result in lower
component failure rates which when used in PRA studies could
result in a lower core melt frequency value. The component
failure rate would be expected to be higher in the early
stages and should gradually decrease as time goes on. This
study will compare the final core melt frequency of the Trojan
Nuclear Power Plant using both methods. The Nuclear Power
Reactor Data System (NPRDS) data base from the Institute of
Nuclear Power Operations (INPO) was used in this study. The
components which were examined for the reliability growth
method are motor operated valves, service water pump/motors
and emergency diesel generator air chargers. These data were
screened to ensure that only true failures were reported.
A comparison was made of the overall core melt frequency
between the conventional failure rate method and reliability
growth method for the motor operated valves. The overall core
melt frequency was decreased by 1.8 % when using the
reliability growth method compared to the conventional method. / Graduation date: 1993
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The nuclear industry : exploring crisis communications and media relations through in-depth interviews and content analysisWalcott, Nicole C. 09 July 2011 (has links)
This study presents an overview of crisis communications and media relations in
the U.S. nuclear industry. Literature suggests that there is a need for evaluating the
current practice of crisis communications and media relations for the industry through
research. Understanding if practitioners are equipped for effective crisis communications
and media relations in the event of a crisis, provides useful benchmarks for future
evaluation, as the way in which organizations communicate to stakeholder publics and
the media will change given the recent complexities and innovations within technology.
Without academic literature in this area, it allows for the continued practice of ineffective
strategies regarding crisis communications and media relations within the highly
technical nuclear industry. With the use of in-depth interviews of nuclear communication
professionals and a content analysis of media coverage and online newsrooms, this study
will seek to provide research findings for best practices in media relations during a crisis
event and reveal some of the current communication strategies that are used by the
nuclear industry communication practitioners. / Department of Journalism
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An Experimental Investigation of Ignition Propensity of Hot Work Processes in the Nuclear IndustryMikkelsen, Kai January 2014 (has links)
The National Fire Code of Canada (NFCC) is one model code which regulates hot work in Canada. The code specifies that hot work processes need only create heat to be considered hot work processes, and requires that precautions taken adhere to those in Canadian Standards Association (CSA) W117.2, which is intended for welding, cutting and allied processes. CSA W117.2 requires a 15 m spherical radius of separation in which combustibles are ideally relocated or, at minimum, be protected with fire blankets. Openings, cracks and other locations in which sparks or hot particles must also be protected within this distance. Additionally CSA W117.2 requires a fire watch during, and one hour following the completion of the work. The NFCC stipulates more stringent requirements on the fire watch than CSA W117.2, requiring a check back 4 hours after the work. The code in its current form requires the same precautions be taken when using a soldering iron or epoxy resin as when using an oxyacetylene torch to flame cut steel. The lack of hazard characterization of hot work processes, and the umbrella prescription of required fire safety precautions can result in insufficient measures to prevent fires in some scenarios, and inordinate precautionary measures in others. While not applicable law in all jurisdictions, the NFCC is relied on in various Canadian industries for regulative purposes. Nuclear power generation in Canada is one such industry facing onerous fire protection costs resulting from following these precautions for the smallest of jobs requiring heat producing tools. The literature review highlights the dearth of scientific knowledge regarding the propensity of hot work as an ignition source and how this shortcoming manifests itself in issues across the various standards governing hot work practices.
The objective of this research is to assess fire hazards resulting from various processes considered hot work under the National Fire Code of Canada (NFCC). Due to the breadth of processes covered by the NFCC, a spectrum of hot work activities was investigated from processes as innocuous as the application of heated adhesive, to well known sources of ignition such as a variety of welding processes, oxyacetylene cutting and plasma cutting. To streamline the hazard assessment, processes were categorised into three groups based upon expected hazards such that testing could focus on the most prominent ignition danger presented by each. The groups were those processes exhibiting hot surface ignition hazards, processes with hot surface ignition hazards in addition to limited potential to generate hot particles, and those processes in which the generation of significant quantities of spark and hot particles is guaranteed.
For the first two process categories, experimentation focused on determining a critical process temperature with which to rank processes and also compare with ignition temperatures of combustibles commonly involved in hot work fires. The critical process temperature was determined as the highest measured temperature of the workpiece or tool during the chosen process and was typically measured with the use of thermocouples and infrared thermography. Characterization of any hot particles in the second category was performed using infrared thermography, and in some cases, thermal paper.
Literature sources indicated that sparks and hot particles are the largest factor in hot work fires, so specialised methodology was developed for the third category of processes to characterise the distribution of many thousands of hot work particles generated during welding, thermal cutting and other hot particle producing work. The distributions collected were used to determine the area enveloped by the ignition hazard of hot particles as well as areas encompassing the highest threat to combustibles in relative terms.
Several of the processes as studied were found not to exhibit any measurable form of ignition hazard, including forms of manual sanding and filing and rotary filing of steel. Heated adhesive, cutting steel with a reciprocating saw and drilling of steel were shown to exhibit moderate degrees of hazard with temperature rise of 195\degree C or less, suggesting potential hazard to a limited group of combustibles. Welding and cutting processes were shown to have a relative ignition potential across a wide area. Typical welding procedures produced hot particles which travelled a maximum of approximately 3 - 4 m while thermal cutting processes ejected sparks, slag and hot particles up to 9.8 m from the work.
Incorporated properly into updated standards and codes, the results and findings of this research could drastically improve the Canadian model codes regarding the regulation of hot work by decreasing cost and difficulty for Canadian Industry without increasing the risk of loss.
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Design and development of train-the-trainer instruction for subject matter experts using intranet-based interactive multimediaWinn, Gloria Nave. Rhodes, Dent. January 2006 (has links)
Thesis (Ed. D.)--Illinois State University, 2006. / Title from title page screen, viewed on February 4, 2008. Dissertation Committee: Dent M. Rhodes (chair), Ellen A. Spycher, Chandra Sommers, Kenneth F. Jerich. Includes bibliographical references (leaves 109-117) and abstract. Also available in print.
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Contribuicao ao estudo da fusao a arco sob atmosfera de gas inerte da esponja de zirconioJULIO JUNIOR, OSWALDO 09 October 2014 (has links)
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