Thesis (M. S.)--Nuclear and Radiological Engineering and Medical Physics, Georgia Institute of Technology, 2010. / Committee Chair: Rahnema, Farzad; Committee Member: Wang, Chris; Committee Member: Zhang, Dingkang. Part of the SMARTech Electronic Thesis and Dissertation Collection.

Thesis (Ph. D.)--University of Missouri-Columbia, 2007. / The entire dissertation/thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file (which also appears in the research.pdf); a non-technical general description, or public abstract, appears in the public.pdf file. Title from title screen of research.pdf file (viewed on September 27, 2007) Vita. Includes bibliographical references.

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Made available in DSpace on 2014-10-09T12:54:44Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:07:59Z (GMT). No. of bitstreams: 0 / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energéticas e Nucleares - IPEN/CNEN-SP

Made available in DSpace on 2014-10-09T12:54:44Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:07:59Z (GMT). No. of bitstreams: 0 / Este trabalho descreve o estudo e testes de um sistema capaz de identificar e classificar os transientes, ou estados transitórios, de sistemas termo-hidráulicos, utilizando a técnica de redes neurais artificiais do tipo mapas de características auto-organizáveis, com o objetivo de sua implantação nas novas gerações de reatores nucleares. A técnica desenvolvida neste trabalho consiste no uso de múltiplas redes para fazer a classificação e identificação dos estados transitórios, sendo cada uma especialista em um respectivo transitório do sistema, que competem entre si por meio do erro de quantização, que é uma medida gerada por estas redes neurais. Esta técnica se mostrou eficiente, apresentando características muito promissoras no que diz respeito ao desenvolvimento de novas funcionalidades em futuros projetos. Uma dessas características consiste no potencial de que a rede, além de responder qual estado transitório está em curso, também pode oferecer informações adicionais sobre esse transitório. / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energéticas e Nucleares - IPEN/CNEN-SP

Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE / Includes bibliographical references. / by Kean Wong. / M.S.

Thesis (Nucl.E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1979. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / by Kord S. Smith. / Nucl.E.

Thesis. 1976. M.S.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / Microfiche copy available in Archives and Science. / Includes bibliographical references. / M.S.

Thesis. 1977. Nucl.E.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / M̲i̲c̲ṟo̲f̲i̲c̲ẖe̲ c̲o̲p̲y̲ a̲v̲a̲i̲ḻa̲ḇḻe̲ i̲ṉ A̲ṟc̲ẖi̲v̲e̲s̲ a̲ṉḠS̲c̲i̲e̲ṉc̲e̲. / Includes bibliographical references. / by Farid Bamdad-Haghighi. / Nucl.E.

A dissertation submitted to the Faculty of Science, University of the Witwatersrand, in fulfilment of the requirements for the degree of Master of Science, Johannesburg 2018 / The calculation of reactor-specific fission Q-values is important for the safety analyses of nuclear reactors. The recoverable energy from the fission Q-value is used to normalise reactor quantities to the total power of the reactor. In this work, a detailed recoverable energy from fission Q-value and spatial heat deposition calculations are presented for the SAFARI-1 nuclear reactor. The fission Q-value is composed of the energy released in a fission event by fission products, neutrons, prompt and delayed gamma rays, beta particles and neutrinos. The energy released by neutrinos is not recoverable; however, part of it is recovered by the gamma and beta radiation from the decay of activated materials. We present two methods to calculate the recoverable energy released per fission. The first one uses the Monte Carlo N-Particle (MCNP5) code. MCNP is a probabilistic transport code that has the capability of calculating most of the heating contributions due to particle interactions with matter. The second method uses the Evaluated Nuclear Data File, ENDF/B-VII and ENDF/B-VII.1 data libraries. The ENDF data libraries contains the information required to calculate all the fission Q-value components, excepttheenergyreleasedfromradiativecapture, sincethisquantity depends on the reactor materials. To calculate this, we use the radiative capture reaction rate in MCNP5 and the binding energy of the product of the activation. We obtained a final Q-value of 200.8±0.6 MeV/fission for SAFARI-1. Using the fission Q-value result, we obtained the spatial heat distribution for SAFARI-1 by ii calculating the heating rates of the Q-value components. It was established that 97% of the heat produced is deposited in the fuel and 3% is deposited in the surrounding region of the reactor. / XL2019