Thesis (M. Phil.)--University of Hong Kong, 1996. / Includes bibliographical references (leaf 164-168).

This dissertation explores the extent to which organizational and institutional factors continue to influence the economic and safety performance of nuclear power plants. Although the importance of non-technological factors during the developmental period of nuclear power has been recognized after the fact, most contemporary research fails to recognize the continued importance of organizational and institutional factors for ongoing nuclear power plant operations. Moreover, a second generation of advanced nuclear reactors is now imminent but technological advances will not suffice to prevent many of the mistakes of this first era of nuclear power. The lessons learned from our experience with the current generation of nuclear power plants must include more than technological improvements. As yet a systematic investigation of the impact of organizational and institutional factors on nuclear power plant performance has not been conducted. This dissertation progresses us much further toward accomplishing this task, although much additional research is still needed.

A suboptimal controller has been developed for a Boiling Water Reactor Nuclear Power Plant, using the DARE P Continuous Simulation Language, which was developed in the Electrical Engineering Department at the University of Arizona. A set of 48 nonlinear first-order differential equations and a large number of algebraic equations has been linearized about the equilibrium state. Using partitioning, the linearized equations were transformed into a block triangular form. The concept of optimal control and a square performance index reflecting the desired plant behavior have been applied on the slow subsystem to develop a suboptimal controller. The obtained feedback law is shown by simulation to be able to compensate for a variety of plant disturbances. A large variety of responses can be obtained by changing the weighting matrices. The control is basically a regulator approach to speed up response during load demand changes. Several simulations are included to demonstrate the control performance. The variables to be controlled have mainly been the average neutron density and the average coolant temperature. Simplifications have been suggested, thus obtaining considerable savings in the computations and ease in design.

No description available.

In this work, description and explanation for the conditions of emergency preparedness is given. The aim was to establish the technical basis for emergency response plans in the event of a nuclear incident that might occur at the PBMR nuclear power station. The Koeberg Nuclear Power Station Technical Basis for Emergency Planning was basically used as a guideline and PC COSYMA, a programme that runs on PC, was used to help ,model the release as described or specified by the regulations set in [5] for South Africa. PC COSYMA runs were done to calculate doses to specific organs and to the whole body. These runs were done considering two weather categories (Pasquill stability category D and F) for neutral and moderately stable weather conditions. Wind speed of 2m/s was used for exposure dose integration periods 1, 10, 30 and 70 days. All dose results (organ and effective) were given by pathways: groundshine, cloudshine and inhalation, except thyroid doses whereby it was assumed that all doses are essentially committed through inhalation. A run for Thyroid including inhalation only as a pathway was also done and a run for iodine prophylaxis as protective action to see the effectiveness of the countermeasures. All the calculated doses were lower than the individual radiation dose limit (50mSv) set by the regulator (NNR) for PBMR [20]. The implementation of countermeasures prevented a further dose accrual. Therefore, there is no need for implementation of countermeasures at PBMR, since they are well below the set criterions. But it will be a good safety culture and Defense in Depth to make an allowance for an emergency plan. Since Defense in Depth is a principle that requires that there should be multiple layers of overlapping safety provision and good safety culture looks at the behaviour on doing things, / MSc. (ARTST) North-West University, Mafikeng Campus, 2003

Project report (M.S.)--Virginia Polytechnic Institute and State University, 1990. / Vita. Abstract. Includes bibliographical references (leaves 123-124). Also available via the Internet.

Thesis (M.S.)--Virginia Polytechnic Institute and State University, 1990. / Vita. Abstract. Includes bibliographical references (leaves 136-137). Also available via the Internet.

Thesis (M.S.)--Virginia Polytechnic Institute and State University, 1993. / Vita. Abstract. Includes bibliographical references (leaves 76-79). Also available via the Internet.

Thesis (doctoral)--Lappeenranta University of Technology, 2009. / Includes bibliographical references. Also available on the World Wide Web.

Thesis (M.S.)--University of Michigan, 1982.