published_or_final_version / Public Administration / Master / Master of Social Sciences

published_or_final_version / Mechanical Engineering / Master / Master of Philosophy

No description available.

Thesis (M.S.)--University of Michigan, 1958.

Thesis (M. Phil.)--University of Hong Kong, 1991.

Thesis (M.Soc.Sc.)--University of Hong Kong, 1988. / Also available in print.

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.

No description available.

No description available.

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.