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  • About
  • The Global ETD Search service is a free service for researchers to find electronic theses and dissertations. This service is provided by the Networked Digital Library of Theses and Dissertations.
    Our metadata is collected from universities around the world. If you manage a university/consortium/country archive and want to be added, details can be found on the NDLTD website.
61

Seismic performance risk analysis for nuclear power plants as input to design decisions

Al-Geroushi, Rajab A. January 1982 (has links)
No description available.
62

An exploratory analysis of quality management audit findings at a nuclear power station

Simons, Rowena Chrystal January 2016 (has links)
Thesis (MTech (Quality))--Cape Peninsula University of Technology, 2016. / The quality assurance role is an essential function in high risk industries such as the nuclear power industry where process failures can potentially have catastrophic results. As part of mitigating the risk inherent in such industries, the need for reliable quality assurance cannot be over-emphasised. Underpinning a reliable quality assurance function, lies the need for effective identification of risk; as well as effective decision making processes by competent auditors. A nuclear quality assurance (QA) department has noted an increase in the variability of its audit outcomes, which has resulted in the value of the audit process being questioned by various stakeholders. The research endeavoured to: explore and describe the practice amongst auditors when rating audit findings; potentially identify reasons for inconsistencies amongst auditors when rating findings; and provide recommendations to improve both the consistency amongst auditors when rating audit finding and the overall performance of the audit process. An exploratory study using the Delphi technique was adopted to enable multiple iterations of qualitative and quantitative data collection and analysis, mimicking elements of a sequential exploratory strategy.
63

Seismic performance risk analysis for nuclear power plants as input to design decisions

Al-Geroushi, Rajab A. January 1982 (has links)
No description available.
64

Digital Computer Analysis of the Kinetic Response of a Thermal Pressurized Water Reactor Power Plant

Alburger, John F. 01 January 1978 (has links) (PDF)
A digital computer model has been developed to simulate the kinetic response of a thermal pressurized water reactor power plant. The program is capable of predicting core power and plant temperature variations which result from disturbances due to routine demand changes, control rod movement, and fission product poison transients as well as from transients during plausible accident situations. The development of the differential equations describing the influence of various primary plant components on the dynamics of the reactor have been heretofore documented in the literature. Finite difference equations facilitating the employment of a digital computer solution are fully derived. Confidence in program validity is supported by the simulation of previously studied accidents and comparison with the safety analyses of a licensed nuclear power generating plant. A source listing of the computer program is provided in the Appendix.
65

SPECIFICATION ERRORS IN ESTIMATING COST FUNCTIONS: THE CASE OF THE NUCLEAR ELECTRIC GENERATING INDUSTRY.

JORGENSEN, EDWARD JOHN. January 1987 (has links)
This study is an application of production-cost duality theory. Duality theory is reviewed for the competitive and rate-of-return regulated firm. The cost function is developed for the nuclear electric power generating industry of the United States using capital, fuel and labor factor inputs. A comparison is made between the Generalized Box-Cox (GBC) and Fourier Flexible (FF) functional forms. The GBC functional form nests the Generalized Leontief, Generalized Square Root Quadratic and Translog functional forms, and is based upon a second-order Taylor-series expansion. The FF form follows from a Fourier-series expansion in sine and cosine terms using the Sobolev norm as the goodness of fit measure. The Sobolev norm takes into account first and second derivatives. The cost function and two factor shares are estimated as a system of equations using maximum likehood techniques, with Additive Standard Normal and Logistic Normal error distributions. In summary, none of the special cases of the GBC function form are accepted. Homotheticity of the underlying production technology can be rejected for both the GBC and FF forms, leaving only the unrestricted versions supported by the data. Residual analysis indicates a slight improvement in skewness and kurtosis for univariate and multivariate cases when the Logistic Normal distribution is used.
66

Public opinion and nuclear power : a West Cumbrian case study

Wainwright, Paul Francis January 1995 (has links)
This work investigates the factors which might influence public opinion regarding the nuclear power industry, and the accuracy of existing theories about that opinion. West Cumbrian opinion is of particular interest, because the area has the highest concentration of the nuclear power industry in the UK, and might thereby represent a potentially 'nuclear-friendly' area which would contrast with the increasing scepticism reported in the rest of the country, and indeed across much of the industrialised world. The factors which may influence public opinion are analyzed in three ways. Firstly, historical factors are presented in an account of the development of the nuclear power industry. Next, the socio-economic situation and traditions of West Cumbria are examined, in order to assess particular local influences on public opinion. Thirdly, the public relations methods of important local and national groups are examined in the light of public relations theories, in order to assess the ability of such groups to influence public opinion (a new avenue of research related to nuclear power). In order to discover the state of West Cumbrian opinion in 1994, and to assess the impact of the above factors upon that opinion, a survey was conducted using a representative sample of the population of Cockermouth, chosen as a typical Cumbrian town. The scope of questions employed in previous studies was broadened to analyze attitudes towards antinuclear groups as well as towards the industry. Great attention was paid to the methodology of the new survey, the findings of which were analyzed in the light of a comparative analysis of existing research and theories related to West Cumbrian opinion. Local opinion was contrasted with that of a national 'public' consisting of political, environmental and energy orientated organizations. This study confirmed some previously held ideas about public opinion, but also found several differences which suggest flaws in the methodology of previous research. One very important finding was that it is important not to overstate the existence of controversy surrounding the nuclear industry in West Cumbria. Overall, the West Cumbrian population appeared to be relatively nuclear friendly, but not as strongly pro-nuclear as might have been thought. A surprisingly large number of people displayed a lack of knowledge about the subject, and many showed feelings of apathy and alienation. Nuclear power and coal were found to be controversial choices of fuel supply. Wind power received more support and less opposition. Environmental groups were seen to perform a watchdog role, for which they were welcomed in West Cumbria by more people than supported the presence of either BNFL or NIREX. Levels of pOlitical activity amongst local people were low. The particular socio-economic situation in West Cumbria appeared to have had an impact upon local opinion. Support extended to the local industry, and to BNFL in particular, far more than it did to the nuclear industry in general. The insular aspect of West Cumbrian culture has affected attitudes towards those groups perceived as 'outsiders', including the national media and environmental groups. It has also affected attitudes to the industry where public relations campaigns have been targeted at a national rather than a specifically West Cumbrian audience.
67

A market shock : the effect of the nuclear accident at Three Mile Island upon the prices of electric utility securities

Laslavic, Thomas J January 1981 (has links)
Thesis (M.S.)--Massachusetts Institute of Technology, Alfred P. Sloan School of Management, 1981. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND DEWEY. / Bibliography: leaves 58-59. / by Thomas J. Laslavic. / M.S.
68

Detection of outliers in failure data

Gallup, Donald Robert January 2011 (has links)
Typescript (photocopy). / Digitized by Kansas Correctional Industries
69

Investigation of the IRWST flow patterns during a simulated station blackout experiment on the OSU APEX facility

Strohecker, Mark F. 21 April 1998 (has links)
The OSU/APEX thermal hydraulic test facility models the passive safety systems of the Westinghouse AP600 advanced light water reactor design. Numerous experiments have been performed to test these systems, the one of focus here is the station blackout scenario. This experiment simulated the complete loss of AC power to all plant systems. One of the objectives of this experiment was to determine the effectiveness of the Passive Residual Heat Removal (PRHR) system. The PRHR system removes heat by rejecting it into the In-containment Refueling Water Storage Tank (IRWST). The IRWST houses the PRHR and is used as a heat sink for the decay heat. The PRHR is a C-type tube heat exchanger. Heat is removed through two mechanisms: natural convection and nucleate boiling from the surface of the PRHR. As the experiment progressed, a large degree of thermal stratification was observed in the IRWST with no significant thermal mixing. A thermal layer developed in the top of the tank and as the thermal layer approached saturation the rate of heat removal from the sections of the PRHR engulfed by this layer decreased. The effectiveness of these sections of the PRHR continued to decrease until unexpected flow patterns developed at the same time that the thermal layer reached saturation. The IRWST fluid exhibited a bulk azimuthal flow pattern that increased the effectiveness of the PRHR. This increase allowed for more heat to be injected into the IRWST. However, the bulk fluid motion still did not mix the thermal layers. A three-dimensional computational fluid dynamic model using the CFX-4.2 software was developed to study the PRHR/IRWST system. The model uses the RPI method to account for the sub-cooled boiling that is present on the PRHR surface. The model successfully predicted the thermal stratification in the IRWST to within 4 K of experimental data. A counter-current flow was shown to occur along the interface of the thermal layers. This caused an enhancement of the heat transfer and turbulent mixing occurring across the interface of the thermal layers. / Graduation date: 1998
70

An assessment of citizen action committees as a risk communication strategy in the decommissioning of Connecticut Yankee nuclear power plant /

Pillittere, Joseph T., January 2002 (has links)
Thesis (M.S.)--Central Connecticut State University, 2002. / Thesis advisor: Robert Fischbach. " ... in partial fulfillment of the requirements for the degree of Master of Science in Organizational Communications." Includes bibliographical references (leaves 86-90). Also available via the World Wide Web.

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