- About
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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.
Search results
Showing 81 to 90 of 174 (0.012 seconds)| 81 |
Nuclear reactor safety P.W.R. refill studiesCampbell, T. January 1978 (has links)
No description available.
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| 82 |
A Study of Fluctuations in a Nuclear Reactor at PowerGreef, C. P. January 1971 (has links)
No description available.
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| 83 |
Advanced analysis of fluid control systems for nuclear reactorsRussell, D. W. January 1970 (has links)
No description available.
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| 84 |
Isotope studies to determine the mechanism of reactions induced by radiation : the carbon monoxide-carbon dioxide exchange reactionWickham, A. J. January 1971 (has links)
No description available.
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| 85 |
Alloy design for a fusion power plantKemp, Richard January 2006 (has links)
Fusion power is generated when hot deuterium and tritium nuclei react, producing alpha particles and 14 MeV neutrons. These neutrons escape the reaction plasma and are absorbed by the surrounding material structure of the plant, transferring the heat of the reaction to an external cooling circuit. In such high-energy neutron irradiation environments, extensive atomic displacement damage and transmutation production of helium affect the mechanical properties of materials. Among these effects are irradiation hardening, embrittlement, and macroscopic swelling due to the formation of voids within the material. To aid understanding of these effects, Bayesian neural networks were used to model irradiation hardening and embrittlement of a set of candidate alloys, reduced-activation ferritic-martensitic steels. The models have been compared to other methods, and it is demonstrated that a neural network approach to modelling the properties of irradiated steels provides a useful tool in the future engineering of fusion materials, and for the first time, predictions are made on irradiated property changes based on the full range of available experimental parameters rather than a simplified model. In addition, the models are used to calculate optimised compositions for potential fusion alloys. Recommendations on the most fruitful ways of designing future experiments have also been made. In addition, a classical nucleation theory approach was taken to modelling the incubation and nucleation of irradiation-induced voids in these steels, with a view to minimising this undesirable phenomenon in candidate materials. Using these models, recommendations are made with regards to the engineering of future reduced-activation steels for fusion applications, and further research opportunities presented by the work are reviewed.
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| 86 |
Aspects of the design and structural analysis of the prestressed cast iron nuclear reactor pressure vesselThomas, R. G. January 1978 (has links)
No description available.
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| 87 |
A study of a mechanism for the contamination of water-cooled nuclear reactor circuits by corrosion productsNasib, Chaudhry Muhammad January 1975 (has links)
No description available.
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| 88 |
Reaction rate measurements in nuclear reactors using solid state track recordersLycos, Theofilos January 1976 (has links)
No description available.
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| 89 |
Radiation streaming in ducts and void spacesMiller, P. C. January 1973 (has links)
No description available.
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| 90 |
Studies of the behaviour of fast reactor fuel elements using a computer modelGrosberg, A. J. January 1979 (has links)
No description available.
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